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{{#Wiki_filter:PAGE 1 OF 16 R39 
{{#Wiki_filter:ES-301                              Administrative Topics Outline                          Form ES-301-1 Facility: __Fort Calhoun______________                            Date of Examination: __3/30/09_____
Examination Level: RO                                              Revision Number: 2 Administrative Topic            Type                    Describe activity to be performed (see Note)                Code*
A-1                                  M, R        Calculate Shutdown Margin with inoperable CEA Conduct of Operations KA 2.1.37 (RO Imp 4.3)
A-2                                  N, R        Determine Pressurizer Level During Cooldown Conduct of Operations KA 2.1.25 (RO Imp 3.9)
A-3                                  N, R        Determine Equipment Lost by Tagout of an MCC Equipment Control KA 2.2.41 (RO Imp 3.5)
A-4                                    D        RCA Entry and Exit with PCM Alarms Radiation Control KA 2.3.13 (RO Imp 3.4)
Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs;  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)


Fort Calhoun Station Unit 1   
ES-301                              Administrative Topics Outline                          Form ES-301-1 Facility: __Fort Calhoun_______________                            Date of Examination:    _3/30/09____
Examination Level: SRO                                              Revision Number: 2 Administrative Topic            Type                    Describe activity to be performed (see Note)                Code*
A-5                                M, R        Review Shutdown Margin Calculation with inoperable CEA Conduct of Operations KA 2.1.37 (SRO Imp 4.6)
A-6                                M, R        Determine Shift Staffing Conduct of Operations KA 2.1.5 (SRO Imp 3.9)
A-7                                D, R        Determine RW System Operability Equipment Control KA 2.2.37 (SRO Imp 4.6)
A-8                                  D, R        Authorize Release of Monitor Tank WD-22B Radiation Control KA 2.3.6 (SRO Imp 3.6)
A-9                                  M, R        Emergency Classification and PARs Emergency Procedures/Plan KA's 2.4.41 (SRO Imp 4.6) and 2.4.44 (SRO Imp 4.4)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:          (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)


TDB-V.9 TECHNICAL DATA BOOK
ES-301                            Control Room/In-Plant Systems Outline                              Form ES-301-2 Facility: __Fort Calhoun_____________________                            Date of Examination: 3/30/09__
Exam Level:        RO                                                  Revision Number.: 2
                              @
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test                        S, N, A                    1 S-2. 004000 A4.08 / Establish Charging Flow via the HPSI Header                    S, N                      2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection                        S,A, M, EN, L              3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump                                  S, A, L,M                4P S-5 061000 A2.04 / Initiate AFW to SGs                                            S, EN, A, N, L            4S S-6 028000 A1.01 / Operate the Containment Hydrogen Analyzer                      S, D                      5 S-7 062000 A4.01 / Transfer 4160 volt busses from 345 KV to 161                    S, D                      6 KV S-8. 012000 A4.02 / RPS Power Adjustment                                          S, N                      7
                      @
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 022000 A2.05 / Provide Raw Water Backup Cooling to                            E,R,M                      5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV                          E, N                      6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire                E,A,D                      8 Pump
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                    Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                              9/8/4 (E)mergency or abnormal in-plant                                                1/1/1 (EN)gineered safety feature                                                        - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                          1/1/1 (N)ew or (M)odified from bank including 1(A)                                    2/2/1 (P)revious 2 exams                                                                3 /  3 /  2 (randomly selected)
(R)CA                                                                            1/1/1 (S)imulator


SHUTDOWN MARGIN WORKSHEET
ES-301                            Control Room/In-Plant Systems Outline                              Form ES-301-2 Facility: __Fort Calhoun_____________________                            Date of Examination: 3/30/09__
Exam Level:        ISRO                                                Revision Number.: 2
                              @
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test                        S, N, A                    1 S-2. 004000 A4.08 / Establish Charging Flow via the HPSI Header                    S, N                      2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection                        S,A, M, EN, L              3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump                                  S, A, L,M                4P S-5 061000 A2.04 / Initiate AFW to SGs                                            S, EN, A, N, L            4S S-7 062000 A4.01 / Transfer 4160 volt busses from 345 KV to 161                    S, D                      6 KV S-8. 012000 A4.02 / RPS Power Adjustment                                          S, N                      7
                      @
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 022000 A2.05 / Provide Raw Water Backup Cooling to                            E,R,M                      5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV                          E, N                      6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire                E,A,D                      8 Pump
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                    Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                              9/8/4 (E)mergency or abnormal in-plant                                                1/1/1 (EN)gineered safety feature                                                        - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                          1/1/1 (N)ew or (M)odified from bank including 1(A)                                    2/2/1 (P)revious 2 exams                                                                3 /  3 /  2 (randomly selected)
(R)CA                                                                            1/1/1 (S)imulator


Change No.
ES-301                            Control Room/In-Plant Systems Outline                              Form ES-301-2 Facility: __Fort Calhoun_____________________                            Date of Examination: 3/30/09__
EC 40685 Reason for Change Added new power defect figure to TDB-II; base percent power on 1500 MWth. Made editorial changes for consistency. Requestor M.
Exam Level:        USRO                                                Revision Number.: 2
Rybenski Preparer D.
                              @
Weis Issue Date 05-18-08   8:30 pm
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                  Type Code*            Safety Function S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection                        S,A, M, EN, L              3 S-5 061000 A2.04 / Initiate AFW to SGs                                            S, EN, A, N, L            4S
                      @
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 022000 A2.05 / Provide Raw Water Backup Cooling to                            E,R,M                     5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV                          E, N                      6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire                E,A,D                      8 Pump
@          All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes                                    Criteria for RO / SRO-I / SRO-U (A)lternate path                                                                4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                              9/8/4 (E)mergency or abnormal in-plant                                                1/1/1 (EN)gineered safety feature                                                        - / - / 1 (control room system)
(L)ow-Power / Shutdown                                                          1/1/1 (N)ew or (M)odified from bank including 1(A)                                    2/2/1 (P)revious 2 exams                                                                3 /  3 /  2 (randomly selected)
(R)CA                                                                            1/1/1 (S)imulator


FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 2 OF 16 R39 SHUTDOWN MARGIN WORKSHEET
Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Fort Calhoun                  Scenario No: 2009-2                  Revision: 3 Examiners:          _________________________                    Operators:  _________________________
_________________________                                _________________________
_________________________                                _________________________
Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.
Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.
Event          Malf      Event                                        Event No.            No.      Type*                                      Description 1                          N-BOPO        Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min)                                  3.
2                          N-ATCO        Rotate Containment Cooling Units In accordance with OI-VA-1.
(10 min) 3                          C-ATCO        Dropped CEA - Tech Spec Entry.
LE CUE                      C-BOPO 4                          R-ATCO        AOP-05 shutdown to 70% Power.
N-BOPO 5                          I-ATCO        Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE                                    High.
6                          C-BOPO        Loss of 161 KV - Tech Spec Entry.
LE CUE 7                          C-ATCO        Another Dropped CEA - Manual Reactor Trip Required.
LE CUE 8                          M-ALL        Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
*        (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)        Actual Attributes
: 1. Total malfunctions (5-8)                                                        5
: 2. Malfunctions after EOP entry (1-2)                                              1
: 3. Abnormal events (2-4)                                                          3
: 4. Major transients (1-2)                                                          1
: 5. EOPs entered/requiring substantive actions (1-2)                                1
: 6. EOP contingencies requiring substantive actions (0-2)                          1
: 7. Critical tasks (2-3)                                                            2


PART I - Instantaneous Shutdown Margin for use prior to a Reactor Trip or immediately following a Reactor trip. No changes are assumed for either boron or xenon, since this worksheet is only applicable for calculation of an instantaneous shutdown
Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Fort Calhoun                  Scenario No: 2009-4                  Revision: 4 Examiners:          _________________________                    Operators:  _________________________
_________________________                                _________________________
_________________________                                _________________________
Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.
Turnover: Maintain 50% operation. Rotate CCW Pumps.
Event          Malf      Event                                        Event No.            No.      Type*                                      Description 1                          N-ATCO        Rotate CCW Pumps.
(2 min) 2                          C-BOPO        Isolated Phase Bus Duct Cooling Fan Motor Trips.
LE CUE 3                          I-ATCO        Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE                      TS-CRS        Entry.
4                          C - ATCO      10-15 gpm leak to containment - Tech Spec Entry.
LE CUE                      TS-CRS 5                          I-BOPO        Steam header pressure transmitter, PT-910 Fails High.
LE CUE 6                          C - ATCO      Feedwater Pump Trips, Reactor Trip.
LE CUE 7                          C-BOPO        Blowdown fails to isolate automatically.
8                          M - ALL      Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE                                    Feedwater.
*        (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)        Actual Attributes
: 1. Total malfunctions (5-8)                                                        7
: 2. Malfunctions after EOP entry (1-2)                                              2
: 3. Abnormal events (2-4)                                                          2
: 4. Major transients (1-2)                                                          1
: 5. EOPs entered/requiring substantive actions (1-2)                                1
: 6. EOP contingencies requiring substantive actions (0-2)                          1
: 7. Critical tasks (2-3)                                                          2 or 3


margin. NOTE: Enter values exactly as determined fr om the figures in the Technical Data Book and carry the algebraic si gns through the calculations.
Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Fort Calhoun                  Scenario No: 2009-1 (SPARE)          Revision: 3 Examiners:          _________________________                    Operators:  _________________________
Condition
_________________________                                _________________________
: 1. Present Date/Time:  
_________________________                                _________________________
Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.
Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.
Event          Malf        Event                                        Event No.            No.        Type*                                      Description 1                          N-ATCO        Transfer Letdown Flow Control Valves.
(2 min) 2                          N-BOPO        Rotate EHC Pumps.
(14 min) 3                          I-ATCO        Power Range NI Channel B fails - Tech Spec Entry.
LE CUE 4                          C-BOPO        Running Bearing Cooling Water Pump, AC-9A, trips.
LE CUE 5                          I-ATCO        Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE                                    Entry 6                          C-All        Loss of Instrument Air.
LE CUE 7                          C-ATCO        Manual Reactor Trip Required.
8                          M-All        Steam Generator Safety Valve Fails Open.
LE CUE
*        (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)        Actual Attributes
: 1. Total malfunctions (5-8)                                                        5
: 2. Malfunctions after EOP entry (1-2)                                              1
: 3. Abnormal events (2-4)                                                          2
: 4. Major transients (1-2)                                                          1
: 5. EOPs entered/requiring substantive actions (1-2)                                1
: 6. EOP contingencies requiring substantive actions (0-2)                          1
: 7. Critical tasks (2-3)                                                            3


/ 2. Reactor Power (before trip): 
ES-301                                        Transient and Event Checklist                                    Form ES-301-5 Facility: Fort Calhoun                      Date of Exam: 3/30/09                            Revision Number.: 3 A          E                                                      Scenarios P          V              1                      2                 3                    4                T      M P          E                                                                                              O        I L          N          CREW                    CREW                CREW        CREW POSITION              T      N I          T        POSITION              POSITION              POSITI                                    A I
%
ON                                              M C                                                                                                          L      U A          T        C      A    B        C        A      B    C A    B        C          A    B            M(*)
: 3. CEA Positions: Group 1 inches Group 2 inches Group 3 inches Group 4 inches
N          Y        R      T    O        R        T      O    R T    O        R          T    O R      I  U T          P        S      C    P        S        C      P    S C    P        S          C    P E              O    O                  O      O        O    O                    O    O RX                            4                                                                  1    1    1  0 NOR                          1,2,4                                                              3    1    1  1 USRO-        I/C                          3,5,6,7                                                      2,5,7 7      4    4  2 1,2 MAJ                          8                                                            8      2    2    2  1 TS                            3,6                                                                2    0    2  2 RX                                      4                                                        1    1    1  0 NOR                                      2                          1                            2    1    2  1 ISRO-1,2 I/C                                          3,5,7                      2,3,4,5,6,7                  9    4    4  2 MAJ                                      8                          8                            2     2    2  1 TS                                                                  3,4                          2    0    2  2 RX                                                                                                      1    1  0 NOR                                              1,4                               1            3    1    1  1 RO-1,2      I/C                                              3,6                              3,4,6        5    4    4  2 MAJ                                              8                                8            2    2    2  1 TS                                                                                                      0    2  2 RX                                                                                                      1    1  0 NOR                                                                                                    1    1  1 I/C                                                                                                    4    4  2 MAJ                                                                                                    2    2  1 TS                                                                                                      0    2  2 Instructions:
: 4. Reactor Coolant System Boron Concentration prior to shutdown:  (Boron concentration analysis must have been performed within the pas t 24 hours or more recently if boration or dilution has occurred.)  
: 1.        Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
: 2.        Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
: 3.      Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.


ppm 4
______________________________________________________________________________
: 5. Burnup (Take the most recent burnup fr om the Control Room Log and add 30 MWD/MTU per EFPD.)
ES-301                                  Competencies Checklist                      Form ES-301-6 Facility: Fort Calhoun          Date of Examination: 3/30/09          Revision No: 3 APPLICANTS USRO-1,2            ISRO-1,2        RO-1,2 Competencies              SCENARIO          SCENARIO        SCENARIO        SCENARIO 1    2    3  4    1    2    3 4   1  2  3  4  1  2  3  4 Position (A-ATCO,                    C        B          A      C      B      A B-BOPO,C-CRS)
Interpret/Diagnose                  3,5,    2,5,      3,5,    2,3,    6,8  3,4 6,7,    6,7,        7      4,5, Events and Conditions                8        8                6,8 Comply With and                      3,4,    2,5,      2,3,    3,4,    3,4  1,3 6,7,    6,7,      4,5,    6,7,    ,6,    ,4, Use Procedures (1)                    8        8          7      8      7    6,8 Operate Control                              2,5,      2,4,            1,3  1,3 6,7,      5,8            ,4,    ,4, Boards (2)                                    8                        6,7  6,8 Communicate                          3,4,    2,5,      3,4,    3,4,    1,3  1,3 6,7,    6,7,      5,7,    5,6,    ,4,    ,4, and Interact                          8        8          8      7,8    6,8  6,8 Demonstrate                          3,4,                        3,4, 6,7,                        5,6, Supervisory Ability (3)              8                          7,8 Comply With and                      3,6                        3,4 Use Tech. Specs. (3)
Notes:
(1)      Includes Technical Specification compliance for an RO.
(2)      Optional for an SRO-U.
(3)      Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.


MWD/MTU  5  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs Approximate Time:    20 minutes          Actual Time: _________________
Reference(s):    K/A 2.1.37 RO Importance 4.3 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" Handout(s)      TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" Time Critical:  NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/23/09 Page 1 of 5


Calculation of Shutdown Margin
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs Operators Name: _____________________ Employee # ______________
: 6. Enter Regulating Group Worth, based on bu rnup (Step 5) and CEA positions (Step 3) using TDB Figure II.B.2.
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            TDB, ruler. calculator Safety Considerations:        None Comments:
Page 2 of 5


  %   TDB Figure used:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs TASK                The candidate has calculated the shutdown margin in STANDARD:            accordance with TDB-V.9 and determined that it is inadequate.
6
INITIAL              The plant is operating at 60% power with group 4 CEAs CONDITIONS:          at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
INITIATING CUE:      You have been requested to perform an instantaneous shutdown margin calculation using TDB-V.9 to determine if technical specification requirement for shutdown margin is being met.
Page 3 of 5


FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 3 OF 16 R39 7. Enter Shutdown Group Worths, based on bu rnup (Step 5) using TDB Figure II.B.1.a.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Obtain a copy of TDB-V.9.             After candidate locates TDB-V.9 in the Technical Data Book, provide a copy of TDB-V.9 Part I.
: a. Shutdown Group B 
[ SAT ]    [ UNSAT ]
%  b. Shutdown Group A 
2              Obtain a copy of TDB section          Obtains copy of TDB-II.
%  c. Total Shutdown Worth
II, Reactivity Curves.
     +   =  %  7.a 7.b 7.c
[ SAT ]    [ UNSAT ]
: 8. Determine Power Defect
3              Determines part I of TDB-V.9.          Performs calculation using part procedure should be used.             1.
[ SAT ]     [ UNSAT ]
4              Performs calculation of the            Difference calculated on line difference between actual and          11 of TDB-V.9, section 1 is required shutdown margin.              +0.7 [between +0.6, +0.8]
[ SAT ]    [ UNSAT ]
5              Determines if SDM is                  Determines Shutdown Margin adequate.                             is inadequate
[ SAT ]    [ UNSAT ]
Termination Criteria:   Shutdown Margin determination has been made and TDB V.9, Part One has been filled out.
Page 4 of 5


Enter Power Defect based on Reactor power level (Step 2) and burnup (Step 5) using TDB Figure II.C.2.a or Figure II.C.2.b.  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 INITIAL            The plant is operating at 60% power with group 4 CEAs CONDITIONS:        at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU INITIATING CUE:    You have been requested to perform an instantaneous shutdown margin calculation using TDB-V.9 to determine if technical specification requirement for shutdown margin is being met.
Operator Name: _________________________________
Shutdown Margin adequate? (circle one)              YES        NO Page 5 of 5


  %  8
PAGE 1 OF 16 Fort Calhoun Station Unit 1 TDB-V.9 TECHNICAL DATA BOOK SHUTDOWN MARGIN WORKSHEET Change No.       EC 40685 Reason for Change Added new power defect figure to TDB-II; base percent power on 1500 MWth. Made editorial changes for consistency.
: 9. Determination of Stuck CEA Allowance (3 cases)
Requestor        M. Rybenski Preparer          D. Weis Issue Date        05-18-08 8:30 pm R39
NOTE:  Consider dropped CEAs which can not be verified to be fully inserted as inoperable.
(Enter N/A if this ca se is not applicable.)
: a. Case I - All CEAs are assumed to be operable. (No known inoperable CEAs)
Assume the highest worth CEAs will stick out of the core upon a Reactor trip. Enter the value of the most reactive CEA, based on burnup (Step 5), from TDB Figure II.B.1.b., lines (1) thru (3) for the pre-trip configur ation. Select the higher value. 
  %  9.a


FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 4 OF 16 R39 NOTE: The worth of one inoperable CEA is dependent on the conf iguration of the withdrawn group(s) and the inoperable CEA.
FORT CALHOUN STATION                                                                     TDB-V.9 TECHNICAL DATA BOOK                                                                 PAGE 2 OF 16 SHUTDOWN MARGIN WORKSHEET PART I -      Instantaneous Shutdown Margin for use prior to a Reactor Trip or immediately following a Reactor trip. No changes are assumed for either boron or xenon, since this worksheet is only applicable for calculation of an instantaneous shutdown margin.
9 b. Case II - One CEA is known to be inoperable (per Technical Specification 2.10.2(4) a.)
NOTE: Enter values exactly as determined from the figures in the Technical Data Book and carry the algebraic signs through the calculations.
(Enter N/A if this ca se is not applicable.)
Condition
Account for this defective CEA (and the hi ghest worth stuck CEA) by entering only the value from lines (4) thru (17) of TDB Figure II.B.1.b. for the inoperable CEA, based on burnup (Step 5). Select the higher value.
: 1. Present Date/Time:                                                                /
    %  9.b NOTE:  The worth of more t han one inoperable CEA is calc ulated by multiplying the most conservative Stuck CEA plus Ejected CEA Worth (TDB Figure II.B.1.b.
: 2. Reactor Power (before trip):                                                            %
lines 4-17 by the number of inoperable CEAs.
: 3. CEA Positions:      Group 1                    inches Group 2                     inches Group 3                    inches Group 4                    inches
: 4. Reactor Coolant System Boron Concentration prior to shutdown: (Boron concentration analysis must have been performed within the past 24 hours or more recently if boration or dilution has occurred.)
ppm 4
: 5. Burnup (Take the most recent burnup from the Control Room Log and add 30 MWD/MTU per EFPD.)
MWD/MTU 5
Calculation of Shutdown Margin
: 6. Enter Regulating Group Worth, based on burnup (Step 5) and CEA positions (Step 3) using TDB Figure II.B.2.
                            %                TDB Figure used:
6 R39


NOTE: The values of lines (4) thru (17) of TDB Figure II.B.1.b. Include the total reactivity associated with the known in operable CEA and the highest worth CEA which is assumed to stick out of the core upon a Reactor trip.
FORT CALHOUN STATION                                                                        TDB-V.9 TECHNICAL DATA BOOK                                                                  PAGE 3 OF 16
: c. Case III - More than one CEA is k nown to be inoperable (per Technical Specification 2.10.2.(4)a.).
: 7. Enter Shutdown Group Worths, based on burnup (Step 5) using TDB Figure II.B.1.a.
(Enter N/A if this ca se is not applicable.)
: a. Shutdown Group B                              %
(1) Enter total number of CEA's which are known to be inoperable per Technical Specificat ion 2.10.2.(4) a.).  
: b. Shutdown Group A                              %
: c. Total Shutdown Worth
                          +                  =                  %
7.a                 7.b                7.c
: 8. Determine Power Defect Enter Power Defect based on Reactor power level (Step 2) and burnup (Step 5) using TDB Figure II.C.2.a or Figure II.C.2.b.
                          %
8
: 9. Determination of Stuck CEA Allowance (3 cases)
NOTE: Consider dropped CEAs which can not be verified to be fully inserted as inoperable.
(Enter N/A if this case is not applicable.)
: a. Case I - All CEAs are assumed to be operable. (No known inoperable CEAs)
Assume the highest worth CEAs will stick out of the core upon a Reactor trip.
Enter the value of the most reactive CEA, based on burnup (Step 5), from TDB Figure II.B.1.b., lines (1) thru (3) for the pre-trip configuration. Select the higher value.
                                  %
9.a R39


#   9.c(1)
FORT CALHOUN STATION                                                                    TDB-V.9 TECHNICAL DATA BOOK                                                              PAGE 4 OF 16 NOTE: The worth of one inoperable CEA is dependent on the configuration of the withdrawn group(s) and the inoperable CEA.
(2) Enter the most conservative defective CEA worth from TDB Figure II.B.1.b. Lines (4) thru (17) depending on defective CEA(s) location, based on  
9
: b. Case II - One CEA is known to be inoperable (per Technical Specification 2.10.2(4) a.)
(Enter N/A if this case is not applicable.)
Account for this defective CEA (and the highest worth stuck CEA) by entering only the value from lines (4) thru (17) of TDB Figure II.B.1.b. for the inoperable CEA, based on burnup (Step 5). Select the higher value.
                                %
9.b NOTE: The worth of more than one inoperable CEA is calculated by multiplying the most conservative Stuck CEA plus Ejected CEA Worth (TDB Figure II.B.1.b.
lines 4-17 by the number of inoperable CEAs.
NOTE: The values of lines (4) thru (17) of TDB Figure II.B.1.b. Include the total reactivity associated with the known inoperable CEA and the highest worth CEA which is assumed to stick out of the core upon a Reactor trip.
: c. Case III - More than one CEA is known to be inoperable (per Technical Specification 2.10.2.(4)a.).
(Enter N/A if this case is not applicable.)
(1)    Enter total number of CEAs which are known to be inoperable per Technical Specification 2.10.2.(4) a.).
                #
9.c(1)
(2)   Enter the most conservative defective CEA worth from TDB Figure II.B.1.b.
Lines (4) thru (17) depending on defective CEA(s) location, based on burnup (Step 5). Select the higher value.
                                        %
9.c(2)
                - (#          )X(              %)  =                  %
9.c(1)          9.c(2)                  9.c R39


burnup (Step 5). Select the higher value.
FORT CALHOUN STATION                                                                     TDB-V.9 TECHNICAL DATA BOOK                                                                 PAGE 5 OF 16 9
 
: d.     Enter total available CEA worth from TDB Figure II.B.1.a. based on burnup (Step 5)
  %  9.c(2)
                                    %
(#  ) X (  %)  =    %  9.c(1) 9.c(2) 9.c FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 5 OF 16 R39 9 d. Enter total available CEA worth from TDB Figure II.B.1.a. based on burnup (Step 5)     %   9.d
9.d
: e. Determine the maximum stuck CEA worth by selecting the minimum of either 9.c or 9.d and record that value.  
: e.     Determine the maximum stuck CEA worth by selecting the minimum of either 9.c or 9.d and record that value.
 
                                    %
  %  9.e
9.e
: f. Enter value from 9.a or 9.b or 9.e as appropriate
: f.     Enter value from 9.a or 9.b or 9.e as appropriate                   %
%  9.f
9.f
: 10. Calculation of the Total In stantaneous Shutdown Margin (SDM I): SDM I = Stuck CEAs + Power Defect - S/D CEAs worth - Regulating CEA worth  
: 10. Calculation of the Total Instantaneous Shutdown Margin (SDMI):
 
SDMI = Stuck CEAs + Power Defect - S/D CEAs worth - Regulating CEA worth SDMI =           %  +           %  -         %  -         % =           %  Total 9.f                 8             7.c             6                 10
SDM I =   %  +   %  -   %  -   %   =   %  Total 9.f 8 7.c 6 10
: 11. Calculate difference from required 3.6% p Shutdown Margin.
: 11. Calculate difference from required 3.6% p Shutdown Margin.
( % ) + 3.6%  =   %   10 11 NOTE: A 3.6%  shutdown margin must be mainta ined in a Hot Shutdown condition, Tc > 210 F (Technical Specification 2.10.2(1) and TDB-VI Item 13.0).
(               % ) + 3.6%  =                     %
10                                   11 NOTE: A 3.6%  shutdown margin must be maintained in a Hot Shutdown condition, Tc > 210 F (Technical Specification 2.10.2(1) and TDB-VI Item 13.0).
: 12. Shutdown Margin check:
: 12. Shutdown Margin check:
: a. If Step 11 is less than or equal to ze ro, the shutdown margin is adequate.
: a.     If Step 11 is less than or equal to zero, the shutdown margin is adequate.
: b. If Step 11 is greater than zero, use OI-ERFCS-1, to determine the number of gallons of acid to add.  
: b.     If Step 11 is greater than zero, use OI-ERFCS-1, to determine the number of gallons of acid to add.
REMARKS Completed by                                                          Date/Time          /
R39


REMARKS      
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown Approximate Time:  10 minutes            Actual Time: _________________
Reference(s):  K/A# 2.1.25     RO Importance 3.9 TDB-III.1.a, "TEMPERATURE CORRECTION FOR PRESSURIZER LEVEL INDICATORS LI-101X/Y".
TDB-III.2, "ACTUAL LEVEL IN PRESSURIZER VS. INDICATED LEVEL IN PRESSURIZER.
Handouts(s):    None Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/24/09 Page 1 of 5


Completed by  Date/Time  /
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            TDB, Ruler, Steam Tables Safety Considerations:
Comments:
Page 2 of 5


ooo
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown TASK                The candidate has determined the actual pressurizer STANDARD            level from LI-101Y using TDB-III.1.a and from LI-106 using TDB-III.2 and has recommended that the pressurizer heaters not be turned off.
INITIAL                    The RCS is being cooled down per OP-3A. RCS CONDITIONS                  pressure is at 250 psia.
A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.
The pressurizer level indications are as follows:
o LI-101X = 48%
o LI-101Y = 50%
o LI-106 = 34%
INITIATING CUE:    The CRS has directed you to determine actual pressurizer level using both LI-101Y and LI-106 and recommend if the pressurizer heaters need to be turned off?
Page 3 of 5


ooo
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Refers to TDB-III.1.a and              Level based on LR-101Y is determines that the actual            approximately 40% (39 - 40%)
pressurizer level based on LR-101Y.                                  [ SAT ]        [ UNSAT ]
2              Refers to TDB-III.2 and                Level based on LI-106 is determines that the actual            approximately 40% (39 - 41%)
pressurizer level based on LI-106.                                  [ SAT ]        [ UNSAT ]
3              Determines if heaters need to          Determines that heaters do not be turned off.                        have to be turned off because actual level is above 32%
[ SAT ]        [ UNSAT ]
Termination Criteria:    Actual level has been determined both channels and a determination has been made on the need to turn off the heaters.
Page 4 of 5


oooooooo
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-2 Rev 3 INITIAL                    The RCS is being cooled down per OP-3A. RCS CONDITIONS                  pressure is at 250 psia.
A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.
The pressurizer level indications are as follows:
o LI-101X = 48%
o LI-101Y = 50%
o LI-106 = 34%
INITIATING CUE:    The CRS has directed you to determine actual pressurizer level using both LI-101Y and LI-106 and recommend if the pressurizer heaters need to be turned off?
NAME: ________________________________________
Actual Level based on LR-101Y: ______________%
Actual Level based on LI-106: _______________%
Do Heaters Need to be turned off:    YES      NO Page 5 of 5


oooooooo
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.
Approximate Time:  20 minutes            Actual Time: _________________
Reference(s):  K/A# 2.2.15 RO Importance 3.9 P&ID Figure 8.1-1 (File 12234)
Handout(s)      None Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/05/09 Page 1 of 8


FORT CALHOUN STATION FC-1188 GENERAL FORM R22  PAGE 1 OF 2 FORT CALHOUN STATION - EMER GENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactor's Call Back #: THE COMMAND AND CONTROL POSITION MUST:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.
Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed. Ensure that all offsite notifications are performed as required. 1. [  ] Initial Declaration
Operators Name: _____________________ Employee # ______________
- for Initial declaration of any emergency classification  [  ] Hourly - When completing Hourly updates, one hour from time of the most recent event notification and  on an hourly basis until event termination. [  ] PAR Change
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
- Any change in Protective Action Recommendations (PARs) and a new classification is not being declared.  [  ] Termination Classification: [  ]  NOUE [  ]  Alert [  ]  Site Area [  ]  General EAL #: Time Event Declared: Time Event Terminated: OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable) 2. Wind From Degrees (10m): Weather  Wind Speed MPH (Use Slowest 10m): Precipitation:  [  ] Yes  [  ] NoTemperature Difference 
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
°C/100m  (use most positive T) Stability Class
Reason, if unsatisfactory:
-[  ] A  -1.9 [  ] B >-1.9 to  -1.7[  ] C >-1.7 to  -1.5[  ] D >-1.5 to  -0.5 [  ] E >-0.5 to  1.5 [  ] F >1.5 to  4.0 [  ] G+ > 4.0 3. There [  ]  is
Tools & Equipment:           P&ID Books Safety Considerations:
[  ]  was
Comments:
[  ]  will be
Page 2 of 8
[  ]  no [  ]  an airborne [  ]  a liquid release of radioactive effluent to the environment that is the result of or associated with this event REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS 4. Protective Action Recommendations (PARs)
None Evacuate Sectors Shelter Sectors 0-2 Miles 2-5 Miles 5-10 Miles
: 5. Prognosis: [  ]  Stable [  ]  Unstable Plant Status: [  ] at Power [  ] Shutdown 6. Remarks Approved: Date:
Time:
FORT CALHOUN STATION FC-1188 GENERAL FORM R22  PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers)  Name of contact (optional)
State of Iowa  State of Nebraska  Harrison County  Pottawattamie County  Washington County  Record any comments, difficulties or observations you had while making this notification


NOTE 1: If on-site meteorological data is not ava ilable, contact the National Weather Service (number in the Emergen cy Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a  T of +2.0 and a stability class F. For all other conditions, use a  T of -1.0 and a stability class D.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.
FORT CALHOUN STATION FC-1188 GENERAL FORM R22  PAGE 1 OF 2 FORT CALHOUN STATION - EMER GENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactor's Call Back #: THE COMMAND AND CONTROL POSITION MUST:
TASK                The candidate has referred to plant electrical drawing STANDARD:          Figure 8.1-1 (File 12234) and has listed the electrical loads powered from MCC-3B2. In addition, the candidate has provided a list of the breakers that would need to be ensured closed to supply power from bus 1B3C to FW-54 Fuel Oil Transfer Pump, FO-37.
Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed. Ensure that all offsite notifications are performed as required. 1. [  ] Initial Declaration
INITIAL                    The plant is operating at full power.
- for Initial declaration of any emergency classification  [  ] Hourly - When completing Hourly updates, one hour from time of the most recent event notification and  on an hourly basis until event termination. [  ] PAR Change
CONDITIONS:
- Any change in Protective Action Recommendations (PARs) and a new classification is not being declared. [  ] Termination Classification: [  ]  NOUE [  ]  Alert [  ]  Site Area [  ]  General EAL #: Time Event Declared: Time Event Terminated: OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable) 2. Wind From Degrees (10m): Weather  Wind Speed MPH (Use Slowest 10m): Precipitation:  [  ] Yes  [  ] NoTemperature Difference 
You are working in the Operations Control Center (OCC).
°C/100m  (use most positive T) Stability Class
Maintenance is requesting that MCC-3B2 be taken out of service for some equipment repairs.
-[  ] A  -1.9 [  ] B >-1.9 to -1.7[  ] C >-1.7 to -1.5[  ] D >-1.5 to -0.5 [  ] E >-0.5 to 1.5 [  ] F >1.5 to 4.0 [  ] G+ > 4.0 3. There [  ]  is
The OCC Supervisor is working on a change to procedure EOP-07, "STATION BLACKOUT" INITIATING CUE:            The OCC Supervisor has directed you to determine what equipment would be affected by tagout of MCC-3B2.
[  ]  was
The OCC Supervisor has directed you to list the breakers that you would need to ensure closed to be able to supply power to FW-54 Fuel Oil Transfer Pump, FO-37, if bus 1B3C were energized from 13.8 KV and FW-54's shaft driven generator, EE-54, failed.
[  ]  will be
Page 3 of 8
[  ]  no [  ]  an airborne [  ]  a liquid release of radioactive effluent to the environment that is the result of or associated with this event REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS 4. Protective Action Recommendations (PARs)
None Evacuate Sectors Shelter Sectors 0-2 Miles 2-5 Miles 5-10 Miles
: 5. Prognosis: [  ]  Stable [  ]  Unstable Plant Status: [  ] at Power [  ] Shutdown 6. Remarks Approved: Date:
Time:
FORT CALHOUN STATION FC-1188 GENERAL FORM R22  PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers)  Name of contact (optional)
State of Iowa  State of Nebraska  Harrison County  Pottawattamie County  Washington County  Record any comments, difficulties or observations you had while making this notification


NOTE 1: If on-site meteorological data is not ava ilable, contact the National Weather Service (number in the Emergen cy Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a  T of +2.0 and a stability class F. For all other conditions, use a  T of -1.0 and a stability class D. 
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.
Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1               Refers to P&ID to determine            Note:
affected equipment.                    If candidate requests copy of the ELDL, "Electrical Load Distribution List",
Inform him that the ELDL is not available.
Uses P&ID Figure 8.1-1 (File 12234) to determine affected equipment.
[ SAT ]        [ UNSAT ]
2              Provides list of affected              List includes:
equipment.                                 VD-7A AC-9A EHC-3A EE2G-1A VD-5A CF-4 CF-5 CF-7A VA-151C VA-158A,C,E,G,H,K,M LO-7 LO-6 LO-2 VA-766
[ SAT ]        [ UNSAT ]
Page 4 of 8


AOP-11 Page 20 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. IF CCW can NOT be restored, THEN align RW to desired components as follows:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.
: a. IF SIAS/CIAS has occurred, THEN ensure ALL of the following switches are in
STEP                    ELEMENT                              STANDARD 3              Refers to P&ID to determine          Uses P&ID Figure 8.1-1 (File breakers that must be ensured        12234) to determine breakers closed to supply power from          that must be ensured closed.
bus 1B3C to FO-37.
[ SAT ]      [ UNSAT ]
4              Provides list of breakers            Breakers include:
BT-1B3C BT-1B4C 1B4C-1 EE-55 Feeder breaker on MCC-4C5 FO-37 Feeder Breaker on MCC-4C6 Note: he may also list Auto Transfer Switch, EE-55, position, but this is not required.
[ SAT ]      [ UNSAT ]
Termination Criteria:   List of affected equipment from MCC-3B2 has been provided and a list of breakers that must be ensured closed to power FO-37 from bus 1B3C has been provided.
Page 5 of 8


"OVRRD":   HC-2809/11/14/15, "SI PUMP AC VALVES SIAS OVERRIDE SWITCH"    HC-2808/10/12/13, "SI PUMP AC VALVES SIAS OVERRIDE SWITCH"  HC-400/403, "CNTMT CLR AC VLVS CIAS OVERRIDE
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 INITIAL                The plant is operating at full power.
CONDITIONS:
You are working in the Operations Control Center (OCC).
Maintenance is requesting that MCC-3B2 be taken out of service for some equipment repairs.
The OCC Supervisor is working on a change to procedure EOP-07, "STATION BLACKOUT" INITIATING CUE:         The OCC Supervisor has directed you to determine what equipment would be affected by tagout of MCC-3B2.
The OCC Supervisor has directed you to list the breakers that you would need to ensure closed to be able to supply power to FW-54 Fuel Oil Transfer Pump, FO-37, if bus 1B3C were energized from 13.8 KV and FW-54's shaft driven generator, EE-54, failed.
Page 6 of 8


SWITCH"      b. Ensure BOTH RW/CCW Backup Header Isolation Valves are open:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 Operator Name:_______________________________________
HCV-2893  HCV-2894
Equipment affected by tagout of MCC-3B2:
Page 7 of 8


(continue)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 Operator Name:_______________________________________
Breakers that must be ensured closed to power FO-37 from bus 1B3C:
Page 8 of 8


AOP-11 Page 21 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Approximate Time:  12 minutes            Actual Time: _________________
NOTE  The RW Interface Valves are locally opened and closed using a local IA Supply Valve.
Reference(s):  K/A# 2.3.7 RO Importance 3.5 GET-Radiation Worker Training.
Positions on the local valve correspond to t he position of the RW Interface Valve.  
Standing Order G-101, "RADIATION WORKER PRACTICES."
****************************************************************************************************
Handouts:      None Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/05/09 Page 1 of 8
CAUTIONS  1. To prevent Raw Water Pump damage, maintain flowrates between 1700 and 8500 gpm per pump.
: 2. Backup cooling should not be used on Containment Cooling Coils with river level less than 983.5 ft or Containment temperatures greater than 150&deg;F. Flashing and potential water hammer in the Containment Coils may be present with Raw Water aligned under low river conditions (<983.5 ft) and at higher


temperatures.
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Operators Name: _____________________ Employee # ______________
: 3. To prevent seal degradation, it is desir able to align RW to operating HPSI, LPSI and CS Pumps. During Shutdown Cooling operations, it should be aligned
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            EAD, TLD, PCM-1, G-M with pancake probe Safety Considerations:
Comments:                    Can be conducted in GET trailer or during actual RCA Entry Page 2 of 8


within one hour. However, after a RAS, a loss of cooling water can be
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms TASK                The candidate has entered and started to exit the STANDARD:          Radiation Control Area (RCA). After receiving an alarm on the first PCM-1 that was used to monitor for contamination, he used a different PCM-1 to monitor again for contamination. After receiving the second alarm, he contacted Radiation Protection and frisked himself using a pancake probe, as directed. After determining that he was not contaminated, he exited the RCA.
INITIAL            The plant is operating at full power. Charging Pump, CONDITIONS:        CH-1A is running but its motor current is higher than expected. The CRS is planning to place CH-1B in service and shutdown CH-1A.
INITIATING CUE:    The CRS has directed you to enter the RCA and place the Packing Cooling Pump for CH-1B in service. After starting the pump, you are to return to the Control Room.
Page 3 of 8


tolerated with no loss of pump performance.  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Review the RWP.                        Reads RWP.
****************************************************************************************************
[ SAT ]      [ UNSAT ]
: c. IF VA-3A, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1A by performing the
2              Determine Radiological                Checks survey maps or Conditions.                            discusses radiological conditions with RP personnel.
[ SAT ]      [ UNSAT ]
3              Obtains Dosimetry.                    Obtain TLD and EAD.
[ SAT ]      [ UNSAT ]
4              Sign on to appropriate RWP.            Insert EAD in reader. Scan PID and RWP number.
[ SAT ]      [ UNSAT ]
5              Enter RCA.                            RCA Entered.
[ SAT ]      [ UNSAT ]
6                                                      CUE: The Packing Cooling Pump for CH-1B has been started , exit the RCA.
NOTE: Do not actually enter room 6 for ALARA reasons.
7              Exits RCA.                            Returns to RCA access point.
[ SAT ]      [ UNSAT ]
Page 4 of 8


following steps:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms STEP                    ELEMENT                              STANDARD 8              Monitor for personnel                  Monitor for contamination contamination prior to exiting        using PCM-1.
: 1) Place "CNTMT CLG COIL VA-1A AC VLVS CONTROL
RCA.
[ SAT ]      [ UNSAT ]
CUE: After examinee has completed counting on a PCM-1, tell him to assume that the PCM-1 alarmed-zone 6.
9              Monitor for contamination a            Monitor for contamination second time.                          again using a different PCM-1.
[ SAT ]      [ UNSAT ]
CUE: After examinee has completed counting on another PCM-1, tell him to assume that this PCM-1 also alarmed- zone 6.
10            Contact RP.                            RP Contacted.
[ SAT ]      [ UNSAT ]
CUE: RP directs you to monitor for contamination using frisker.
11            Uses Frisker to monitor for            Slowly moves pancake probe contamination.                        over hands, shoes and body surface.
CUE: Frisker cpm as read.
[ SAT ]      [ UNSAT ]
Page 5 of 8


SW HCV-400B/D" in
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Termination Criteria:  RCA has been exited.
Page 6 of 8


"CLOSE". (continue)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms NOTE to RP Tech As a part of this candidates NRC license exam, he must enter and exit the RCA.
During RCA exit, he has been given verbal Cues that he has received a zone 6 alarm on two separate PCM-1 monitors.
As a part of this JPM, we would like you to direct him to perform a whole body frisk on himself.
Page 7 of 8


AOP-11 Page 22 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.c. (continued)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 INITIAL          The plant is operating at full power. Charging Pump, CONDITIONS:      CH-1A is running but its motor current is higher than expected. The CRS is planning to place CH-1B in service and shutdown CH-1A.
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
INITIATING CUE:   The CRS has directed you to enter the RCA and place the Packing Cooling Pump for CH-1B in service. After starting the pump, you are to return to the Control Room.
Page 8 of 8


Valves (Room 69):
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 JPM Title: Review Shutdown Margin Calculation with inoperable CEAs Approximate Time:    25 minutes          Actual Time: _________________
HCV-400E, "CNTMT VA-1A COOLING COIL RAW WATER INLET
Reference(s):   K/A 2.1.37 SRO Importance 4.6 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" Handout(s):      Completed TDB-V.9 Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/23/09


VALVE"  HCV-400F, "CNTMT VA-1A COOLING COIL
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            TDB, ruler, calculator Safety Considerations:
Comments:


BACK-UP RAW WATER
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 TASK              The candidate reviewed the Shutdown Margin STANDARD:        calculation that was prepared by the STA and found 2 errors in the calculation, corrected the errors and determined that the Shutdown Margin is inadequate.
INITIAL                The plant is operating at 60% power with group 4 CONDITIONS:              CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
INITIATING CUE:  The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has directed you to review the shutdown margin calculation and, if there are any mistakes, correct them.


OUTLET VALVE"
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 Critical Steps shown in gray STEP                  ELEMENT                              STANDARD Note to Examiner:
: 3) Locally open both VA-1A RW Interface Valves, HCV-400E/F by placing the  
Provide Shutdown Margin Calculation to candidate with initiating cue.
1              Reviews shutdown margin                Determines that there was an calculation.                          error in step 7.a due to reading the value from the wrong row.
5.238 (Shutdown Group A+B worth was entered instead of shutdown group B worth).
[ SAT ]      [ UNSAT ]
2                                                      Determines that in step 8, the 100% power defect was used instead of the 60% power defect.
[ SAT ]      [ UNSAT ]
3              Performs calculation of the            Difference calculated on line difference between actual and          11 of TDB-V.9, section 1 is required shutdown margin                +0.7 [between +0.6, +0.8].
using corrected values.
[ SAT ]      [ UNSAT ]
4              Determines if SDM is                  Determines Shutdown Margin adequate.                              is inadequate.
[ SAT ]      [ UNSAT ]
Termination Criteria:    The SRO has determined that shutdown margin is not adequate and has corrected the SDM calculation.


following valves to "OPEN" (Room 69):
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 INITIAL                  The plant is operating at 60% power with group 4 CONDITIONS:              CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).
IA-HCV-400E-TV, "4-WAY MANUAL CONTROL VALVE"  IA-HCV-400F-TV, "4-WAY MANUAL CONTROL
The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.
INITIATING CUE:   The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has directed you to review the shutdown margin calculation and, if there are any mistakes, correct them.
Operator Name: _________________________________
Shutdown Margin adequate? (circle one)              YES        NO


VALVE"   (continue)  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Approximate Time:  15 minutes            Actual Time: _________________
Reference(s):  K/A# 2.1.5 SRO Importance 3.9 Technical Specifications Table 5.2-1 SO-O-1, "CONDUCT OF OPERATIONS" SO-G-52, "PLANT STAFF WORKING HOURS" SO-G-28, "STATION FIRE PLAN" Handout(s):    None Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/23/09 Page 1 of 6


AOP-11 Page 23 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Operators Name: _____________________ Employee # ______________
: d. IF VA-3B, Containment Vent Fan, is in service, 
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:
Comments:
Page 2 of 6


THEN establish RW Flow to VA-1B by performing the  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing TASK                The candidate has reviewed the staffing suggestions STANDARD:          made by his STA and his AON and has determined that either a qualified STA or a qualified CRS must be called in and be in position within two hours. He has also determined that the AON cannot also serve as Control Room Communicator due to Fire Brigade manning requirements.
INITIAL                    The plant is operating at full power.
CONDITIONS:
You are the Shift Manager. Your crew consists of:
o you o a CRS o a STA (who is also CRS qualified) o two RO's o an EONA, o an EONT, o an AON (who is also Communicator qualified) o a Control Room Communicator.
Half way through your shift, your CRS and your Control Room Communicator became sick and needed to go home.
INITIATING CUE:    Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.
Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.
Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.
Page 3 of 6


following steps:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Determine if the STA may fill          Refers to Technical both the CRS and the STA              Specifications Table 5.2-1 and position for the remainder of          Standing Order SO-O-1.
: 1) Place "CNTMT CLG COIL VA-1B AC VLVS CONTROL
the shift.
Determines that 2 SROs and an STA are required and this suggestion is not acceptable.
[ SAT ]      [ UNSAT ]
2              Determine if the AON may fill          Refers to Technical both the AON and the Control          Specifications Table 5.2-1 and Room Communicator position            Standing Order SO-G-28.
for the remainder of the shift.
Determines that an AON, an EONT and a communicator are required for the Fire Brigade.
[ SAT ]      [ UNSAT ]
3              Determine what actions must            Determines that the CRS must be taken and when these                turnover to the CRS qualified actions must be taken.                STA and that immediate action must be taken to call in another qualified STA or another qualified CRS and another plant Operator or Communicator and the called in Operators must be in position within 2 hours.
[ SAT ]      [ UNSAT ]
Page 4 of 6


SW HCV-401B/D" in
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Termination Criteria:  Candidate has determined shift staffing requirements, actions that must be taken and required time frame for these actions.
Page 5 of 6


"CLOSE".     2) Unlock and release the hand-jacks from BOTH of the following RW Interface
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 INITIAL                    The plant is operating at full power.
CONDITIONS:
You are the Shift Manager. Your crew consists of:
o you o a CRS o a STA (who is also CRS qualified) o two RO's o an EONA, o an EONT, o an AON (who is also Communicator qualified) o a Control Room Communicator.
Half way through your shift, your CRS and your Control Room Communicator became sick and needed to go home.
INITIATING CUE:      Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.
Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.
Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.
NAME:_____________________________________________
Can the STA serve as both CRS and STA?                YES        NO Can the AON serve as both AON and Control Room Communicator          YES    NO What action, if any, must be taken? When must it be taken?
Page 6 of 6


Valves (Room 69):
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability Approximate Time:  12 minutes            Actual Time: _________________
HCV-401E, "CNTMT VA-1B COOLING COIL BACK-UP RAW WATER
Reference(s):   K/A# 2.2.22 SRO Importance 4.7 TDB VIII, "EQUIPMENT OPERABILITY GUIDANCE" Technical Specification 2.4 Technical Specification 2.0.1 Handout(s):    None Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 02/20/09 Page 1 of 5


INLET VALVE" HCV-401F, "CNTMT VA-1B COOLING COIL
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:
Comments:
Page 2 of 5


BACK-UP RAW WATER
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability TASK                The candidate has reviewed TDB-VIII and Technical STANDARD:          Specifications and has determined that the action statement for Technical Specification 2.0.1 applies. The plant must be in hot shutdown within 6 hours.
INITIAL                    The plant is operating at full power.
CONDITIONS:
It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.
INITIATING CUE:    Determine the applicable Technical Specification and required actions, if any, to be taken.
Page 3 of 5


OUTLET VALVE" (continue)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Refers to TDB-VIII.                    Enters TDB-VIII.
[ SAT ]      [ UNSAT ]
2              Refers to Table 2-1 to                Determines that T.S. 2.0.1 determine applicable LCO.              applies with these conditions.
[ SAT ]      [ UNSAT ]
3              Determines Tech Spec. 2.0.1            Plant must be in Hot Shutdown required Action Statement.            within 6 hours.
[ SAT ]      [ UNSAT ]
Termination Criteria:    Technical Specification 2.0.1 has been entered.
Page 4 of 5


AOP-11 Page 24 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.d (continued)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 INITIAL                    The plant is operating at full power.
: 3) Locally open both VA-1B RW Interface Valves, HCV-401E/F by placing the  
CONDITIONS:
It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.
INITIATING CUE:      Determine the applicable Technical Specification and required actions, if any, to be taken.
Name: ________________________________________
Technical Specification Entered, if any:
Required Action, if any:
Page 5 of 5


following valves in "OPEN" (Room 69):
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B Approximate Time:    10 minutes            Actual Time: _________________
IA-HCV-401E-TV, "4-WAY MANUAL CONTROL VALVE"   IA-HCV-401F-TV, "4-WAY MANUAL CONTROL
Reference(s):   K/A# 2.3.6 SRO Importance 3.8 OI-WDL-3, "LIQUID WASTE DISPOSAL RELEASE" FC-211, "WASTE LIQUID TANK RELEASE PERMIT" Handout(s):    Partially filled out OI-WDL-3 Approved FC-211 Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 03/23/09 Page 1 of 5


VALVE"      e. IF VA-7C, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8A by performing the
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            Calculator Safety Considerations:
Comments:
Page 2 of 5


following steps:
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B TASK                The SRO candidate reviewed OI-WDL-3 and the FC-211 STANDARD:            release permit and determined that the EONA used the wrong maximum release rate when filling out OI-WDL-3 and that the chemist specified the wrong flow rate in the release permit, section VII. Special Instructions. The release was not authorized as written.
: 1) Place "CNTMT CLG COIL VA-8A AC VLVS CONTROL
INITIAL                    The plant is operating at full power.
CONDITIONS:               Three Circulating Water Pumps are running.
Two Raw Water Pumps are operating.
All Radiation Monitors are operable.
A release of Monitor Tank, WD-22B is planned.
INITIATING CUE:     You are the Shift Manager. The EONA has given you a copy of OI-WDL-3 and a Release Permit for the release of WD-22B. Review the permit and, if acceptable, authorize the release. If not acceptable, make any required corrections.
Page 3 of 5


SW HCV-402B/D" in  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Reviews partially filled out OI-      Examines procedure and WDL-3 and associated FC-211            Release Permit.
Release Permit.
[ SAT ]      [ UNSAT ]
2              Determines that the maximum            Maximum release rate should release rate and administrative        be 84.6 gpm. Administrative release rate recorded on the          release rate should be 76.1 procedure do not agree with            gpm.
the Release Permit.
[ SAT ]      [ UNSAT ]
3              Determines that the Chemist            Unloader should be set to has used the wrong flow rate          allow a flow rate of 76.1 gpm.
on the FC-211 release rate, section VII. Special Instructions, item B.                  [ SAT ]      [ UNSAT ]
4              Release Authorization.                Does not authorize release as written.
Corrects maximum (84.6 gpm) and administrative (76.1 gpm) release rates.
[ SAT ]      [ UNSAT ]
Termination Criteria:    Candidate has reviewed the procedure and release permit and has refused to authorize the release as written.
Page 4 of 5


"CLOSE".
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 INITIAL                The plant is operating at full power.
CONDITIONS:            Three Circulating Water Pumps are running.
Two Raw Water Pumps are operating.
All Radiation Monitors are operable.
A release of Monitor Tank, WD-22B is planned.
INITIATING CUE:  You are the Shift Manager. The EONA has given you a copy of OI-WDL-3 and a Release Permit for the release of WD-22B. Review the permit and, if acceptable, authorize the release. If not acceptable, make any required corrections.
Page 5 of 5


(continue)  
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs Approximate Time:    20 minutes            Actual Time: _________________
Reference(s):    K/A# 2.4.41 SRO Importance 4.6 K/A# 2.4.44 SRO Importance 4.4 EPIP-OSC-1, "EMERGENCY CLASSIFICATION" EPIP-EOF-7, "PROTECTIVE ACTION GUIDELINES TDB-IV.8, "AREA MONITORING SETPOINTS" EAGLE 6.0.0 Users Manual Handouts(s):    FC-1188 EAGLE OUTPUT Time Critical:  YES  (Cue# 2)
Alternate Path:  NO JPM Prepared by:    Jerry Koske                                  Date: 3/25/09 Page 1 of 7


AOP-11 Page 25 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.e (continued)
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs Operators Name: _____________________ Employee # ______________
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:           None Safety Considerations:        None Comments:                    SRO , Time Critical - 15 minutes after determining EAL Page 2 of 7


Valves (Room 69):
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs TASK              The SRO candidate reviewed the plant conditions, STANDARD:          referred to EPIP-OSC-1 and TDB-IV.8 and classified the event as a SITE AREA EMERGENCY, EAL 7.3.
HCV-402E, "CNTMT VA-8A COOLING COIL BACK-UP RAW WATER
Within 15 minutes of classifying the event, the candidate used the EAL and the data from the EAGLE output to determine there are no Protective Action Recommendations and completed page one of form FC-1188 so that offsite notifications can be made.
INITIAL                  A refueling outage is in progress.
CONDITIONS:              Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack.
High radiation alarms were received on RM-085 and RM-087.
RM-085 is reading 1200 mrem/hr.
RM-087 is reading 1100 mrem/hr.
Radiation levels on RM-052 and RM-062 are also rising.
There is no precipitation.
Your Shift HP is running EAGLE INITIATING CUE:    You are the Shift Manager. Determine the appropriate EAL, if any, in accordance with EPIP-OSC-1.
CUE #2:            ***** TIME CRITICAL*****
Your Shift HP has run EAGLE and has provided you with the output. You are directed to complete page 1 of form FC-1188 so your Communicator can make the required notifications.
Page 3 of 7


INLET VALVE" HCV-402F, "CNTMT VA-8A COOLING COIL
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs Critical Steps shown in gray STEP                  ELEMENT                              STANDARD Examiner Note:
Provide only the initiating cue to the candidate at this time.
1              Refer to Emergency Plan.              Refer to EPIP-OSC-1.
[ SAT ]      [ UNSAT ]
2              Classify the event.                  This Event should be classified as a SITE AREA EMERGENCY, EAL 7.3, "MAJOR IRRADIATED FUEL ACCIDENT" RM-087 is reading more than 1000 times its normal refueling shutdown value per TDB-IV.8
[ SAT ]      [ UNSAT ]
Examiner Note: Provide cue#2, EAGLE output and Blank FC-1188 form to candidate. Note the time Start Time:______________
Page 4 of 7


BACK-UP RAW WATER
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs STEP                    ELEMENT                              STANDARD 3              Determine Protective Action            ***** TIME CRITICAL *****
Recommendations and fill out          Form FC-1188 must be filled form FC-1188 for notifications.        out within 15 minutes and must contain the following information:
Initial Declaration Site Area EAL 7.3 Wind from 122&deg; Wind Speed10 MPH No Precipitation Temperature difference 1&deg;C/100m Stability Class "E" There is an airborne release There are no PARs Plant Status: shutdown Approval Signature, date and time.
End Time:____________
Elapsed Time:__________
[ SAT ]      [ UNSAT ]
Termination Criteria:  PARS have been determined and FC-1188 has been filled out within 15 minutes of classifying the event.
Page 5 of 7


OUTLET VALVE"
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 4 INITIAL                      A refueling outage is in progress.
: 3) Locally open both VA-8A RW Interface Valves, HCV-402E/F by placing the  
CONDITIONS:                 Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack.
High radiation alarms were received on RM-085 and RM-087.
RM-085 is reading 1200 mrem/hr.
RM-087 is reading 1100 mrem/hr.
Radiation levels on RM-052 and RM-062 are also rising.
There is no precipitation.
Your Shift HP is running EAGLE INITIATING CUE:      You are the Shift Manager. Determine the appropriate EAL, if any, in accordance with EPIP-OSC-1.
Name:_________________________________________________
Event Classification (circle one)
NONE Notice of Unusual Event Alert Site Area Emergency General Emergency EAL# ___________________
Page 6 of 7


following valves to "OPEN" (Room 69):
Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 4 CUE #2:          ***** TIME CRITICAL*****
IA-HCV-402E-TV, "4-WAY MANUAL CONTROL VALVE"  IA-HCV-402F-TV, "4-WAY MANUAL CONTROL
Your Shift HP has run EAGLE and has provided you with the output. You are directed to complete page 1 of form FC-1188 so your Communicator can make the required notifications.
Page 7 of 7


VALVE"   (continue)  
FORT CALHOUN STATION                                                                                            FC-1188 GENERAL FORM                                                                                                        R22 PAGE 1 OF 2 FORT CALHOUN STATION - EMERGENCY NOTIFICATION FORM Off-Site Contact Time:                  Person Making Off-Site Report:                      Contactors Call Back #:
THE COMMAND AND CONTROL POSITION MUST:
* Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed.
* Ensure that all offsite notifications are performed as required.
: 1.   [ ]  Initial Declaration - for Initial declaration of any emergency classification
[ ]  Hourly - When completing Hourly updates, one hour from time of the most recent event notification and on an hourly basis until event termination.
[ ]  PAR Change - Any change in Protective Action Recommendations (PARs) and a new classification is not being declared.
[ ]  Termination Classification:    [ ] NOUE        [ ] Alert      [ ] Site Area        [ ] General          EAL #:
Time Event Declared:                                              Time Event Terminated:
OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)
: 2. Wind From                      Weather      Wind Speed MPH (Use                  Precipitation: [ ] Yes [ ] No Degrees (10m):                                Slowest 10m):
Temperature Difference                        &deg;C/100m (use most positive T)
Stability Class      -[ ] A        [ ]B            [ ]C            [ ]D          [ ]E            [ ]F        [ ] G+
                        -1.9  >-1.9 to  -1.7 >-1.7 to  -1.5  >-1.5 to  -0.5 >-0.5 to  1.5  >1.5 to  4.0    > 4.0
: 3. There      [ ] is              [ ] no release of radioactive effluent to the environment
[ ] was            [ ] an airborne that is the result of or associated with this event
[ ] will be        [ ] a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS
: 4. Protective Action Recommendations (PARs)
None              Evacuate Sectors                            Shelter Sectors 0-2 Miles 2-5 Miles 5-10 Miles
: 5. Prognosis:      [ ] Stable          [ ] Unstable          Plant Status:    [ ] at Power        [ ] Shutdown
: 6. Remarks Approved:                                                            Date:                          Time:


AOP-11 Page 26 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
FORT CALHOUN STATION                                                                        FC-1188 GENERAL FORM                                                                                      R22 PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers) 3    Name of contact (optional)
: f. IF VA-7D, Containment VentFan, is in service,   
State of Iowa State of Nebraska Harrison County Pottawattamie County Washington County Record any comments, difficulties or observations you had while making this notification NOTE 1: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a  T of +2.0 and a stability class F. For all other conditions, use a T of -1.0 and a stability class D.


THEN establish RW Flow to VA-8B by performing the  
FORT CALHOUN STATION                                                                                            FC-1188 GENERAL FORM                          KEY                                                                          R22 PAGE 1 OF 2 FORT CALHOUN STATION - EMERGENCY NOTIFICATION FORM Off-Site Contact Time:                  Person Making Off-Site Report:                      Contactors Call Back #:
THE COMMAND AND CONTROL POSITION MUST:
* Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed.
* Ensure that all offsite notifications are performed as required.
: 1.  [ X]  Initial Declaration - for Initial declaration of any emergency classification
[ ]  Hourly - When completing Hourly updates, one hour from time of the most recent event notification and on an hourly basis until event termination.
[ ]  PAR Change - Any change in Protective Action Recommendations (PARs) and a new classification is not being declared.
[ ]  Termination Classification:    [ ] NOUE        [ ] Alert      [X ] Site Area      [ ] General          EAL #:    7.3 Time Event Declared:                                              Time Event Terminated:
OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)
: 2. Wind From                      Weather      Wind Speed MPH (Use                  Precipitation: [ ] Yes [X] No Degrees (10m): 122                            Slowest 10m): 10 Temperature Difference                        &deg;C/100m (use most positive T)
Stability Class        -[ ] A      [ ]B            [ ]C            [ ]D          [X ] E          [ ]F        [ ] G+
                          -1.9  >-1.9 to -1.7 >-1.7 to  -1.5  >-1.5 to  -0.5 >-0.5 to  1.5  >1.5 to  4.0    > 4.0
: 3. There      [X ] is            [ ] no release of radioactive effluent to the environment
[ ] was            [X] an airborne that is the result of or associated with this event
[ ] will be        [ ] a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS
: 4. Protective Action Recommendations (PARs)
None              Evacuate Sectors                            Shelter Sectors 0-2 Miles  X 2-5 Miles  X 5-10 Miles    X
: 5. Prognosis:        [X ] Stable        [ ] Unstable          Plant Status:    [ ] at Power        [X ] Shutdown
: 6. Remarks Approved:                                                            Date:                          Time:


following steps:
FORT CALHOUN STATION                                                                        FC-1188 GENERAL FORM                                                                                      R22 PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers) 3    Name of contact (optional)
: 1) Place "CNTMT CLG COIL VA-8B AC VLVS CONTROL
State of Iowa State of Nebraska Harrison County Pottawattamie County Washington County Record any comments, difficulties or observations you had while making this notification NOTE 1: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a  T of +2.0 and a stability class F. For all other conditions, use a  T of -1.0 and a stability class D.


SW HCV-403B/D" in
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Location:            Auxiliary Building (RCA) and Room 81 Approximate Time:    30 minutes          Actual Time: _________________
Reference(s):  K/A 022000 A2.05 AOP-11, "LOSS OF COMPONENT COOLING WATER" OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" Handout(s):    AOP-11, "LOSS OF COMPONENT COOLING WATER", Step 12.
OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" Time Critical: NO Alternate Path:  NO JPM Prepared by:    Jerry Koske                                  Date: 3/23/09 Page 1 of 8


"CLOSE".     2) Unlock and release the hand-jacks from BOTH of the following RW Interface
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:        This JPM requires entry into the RCA.
Climbing of a ladder may be required.
Comments:
Page 2 of 8


Valves (Room 69):
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers TASK                The Candidate placed Raw Water Backup cooling in STANDARD:            service for Containment Cooling Coil, VA-1A and Shutdown Cooling Heat Exchanger, AC-4B in accordance with AOP-11.
HCV-403E, "RAW WATER RETURN HEADER TO CONT AIR CLNG &  
INITIAL                    A LOCA occurred 8 hours ago.
CONDITIONS:                EOP-AOP Attachment 8, "COOLED SI FLOW WITH RAS" has been implemented.
15 minutes ago, a total loss of CCW occurred.
The CRS is implementing AOP-11.
Containment temperature is 120&deg;F.
The river level is 990 feet.
INITIATING CUE:      The CRS has directed you to establish Raw Water Backup to Containment Cooling Coil, VA-1A, per AOP-11 step 12.c. and OI-AOV-1.
CUE #2:              The CRS has directed you to establish Raw Water Backup to Shutdown Cooling Heat Exchanger, AC-4B, per AOP-11 step 12.h.
Page 3 of 8


FILTERING ISOLATION
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Obtain copies of AOP-11 and            Cue: Provide copies of AOP-OI-AOV-1.                              11, step 12 and OI-AOV-1.
[ SAT ]      [ UNSAT ]
2              Place CNTMT CLG COIL                  CUE: Control Room VA-1A AC VLVS CONTROL                  Operator reports that HCV-SW HCV-400B/D in CLOSE.            400B/D is in CLOSE.
[ SAT ]      [ UNSAT ]
3              Unlock and release the                Room-69 hand-jacks from BOTH of the            Remove the locking following RW Interface                mechanisms and covers from Valves:                                BOTH HCV-400E and HCV-HCV-400E, CNTMT                400F. Use the ratchet to VA-1A COOLING COIL              release the handjacks by RAW WATER INLET                turning the locking nut VALVE.                        CLOCKWISE until it reaches HCV-400F, CNTMT                the bottom.
VA-1A COOLING COIL BACK-UP RAW WATER              [ SAT ]      [ UNSAT ]
OUTLET VALVE.
CUE: Another Operator will make the entry in the Locked Components Log.
4              Locally open both VA-1A RW            Room-69 Interface Valves, HCV-400E/F          IA-HCV-400E-TV 4-way by placing the following valves        manual control valve in OPEN.
to OPEN:
IA-HCV-400E-TV, 4-              IA-HCV-400F-TV 4-way WAY MANUAL                      manual control valve in OPEN.
CONTROL VALVE.
IA-HCV-400F-TV, 4-WAY MANUAL CONTROL VALVE.                [ SAT ]      [ UNSAT ]
Page 4 of 8


VALVE"  HCV-403F, "CNTMT VA-8B COOLING COIL
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers STEP                    ELEMENT                              STANDARD Note to Examiner: Provide Cue #2 to Candidate.
5              Close Both AC-4B CCW                  CUE: The Control Room Isolation Valves:                      Operator reports that HCV-HCV-481                          481 and HCV-485 are closed.
HCV-485 6              Unlock and release the                Corridor 4 hand-jacks from BOTH of the following RW Interface                Unlock and release the hand-Valves (Corridor 4):                  jacks from both:
HCV-483A,                            HCV-483A SHUTDOWN                          HCV-483B COOLING HT EXCH AC-4B BACK-UP RAW WATER INLET VALVE HCV-483B,                        [ SAT ]      [ UNSAT ]
SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER OUTLET VALVE 7              Locally open both AC-4B RW            Corridor 4 Interface Valves,HCV-483A/B, by placing the following valves        IA-HCV-483A-TV 3-way to OPEN:                            manual control valve in OPEN.
IA-HCV-483A-TV, 3-WAY MANUAL                    IA-HCV-483B-TV 3-way CONTROL VALVE                 manual control valve in OPEN.
IA-HCV-483B-TV, 3-WAY MANUAL CONTROL VALVE                [ SAT ]      [ UNSAT ]
Page 5 of 8


BACK-UP RAW WATER
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Termination Criteria:  Raw Water Backup Cooling is being provided to VA-1A and AC-4B.
Page 6 of 8


OUTLET VALVE" (continue)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 INITIAL                  A LOCA occurred 8 hours ago.
CONDITIONS:              EOP-AOP Attachment 8, "COOLED SI FLOW WITH RAS" has been implemented.
15 minutes ago, a total loss of CCW occurred.
The CRS is implementing AOP-11.
Containment temperature is 120&deg;F.
The river level is 990 feet.
INITIATING CUE:    The CRS has directed you to establish Raw Water Backup to Containment Cooling Coil, VA-1A, per AOP-11 step 12.c. and OI-AOV-1.
Page 7 of 8


AOP-11 Page 27 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.f (continued)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 CUE #2:          The CRS has directed you to establish Raw Water Backup to Shutdown Cooling Heat Exchanger, AC-4B, per AOP-11 step 12.h.
: 3) Locally open both VA-8B RW Interface Valves, HCV-403E/F by placing the
Page 8 of 8


following valves to "OPEN" (Room 69):
AOP-11 Page 20 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS
IA-HCV-403E-TV, "4-WAY MANUAL CONTROL VALVE"  IA-HCV-403F-TV, "4-WAY MANUAL CONTROL
: 12. IF CCW can NOT be restored, THEN align RW to desired components as follows:
: a. IF SIAS/CIAS has occurred, THEN ensure ALL of the following switches are in OVRRD:
* HC-2809/11/14/15, SI PUMP AC VALVES SIAS OVERRIDE SWITCH
* HC-2808/10/12/13, SI PUMP AC VALVES SIAS OVERRIDE SWITCH
* HC-400/403, CNTMT CLR AC VLVS CIAS OVERRIDE SWITCH
: b. Ensure BOTH RW/CCW Backup Header Isolation Valves are open:
* HCV-2893
* HCV-2894 (continue)
R14


VALVE"      g. IF AC-4A, SDC HX, is in service, THEN establish RW flow to AC-4A by performing the following steps:
AOP-11 Page 21 of 49 INSTRUCTIONS                                            CONTINGENCY ACTIONS
: 1) Close BOTH AC-4A CCW Isolation Valves:
: 12.    (continued)
HCV-480  HCV-484 (continue)  
NOTE The RW Interface Valves are locally opened and closed using a local IA Supply Valve.
Positions on the local valve correspond to the position of the RW Interface Valve.
  ****************************************************************************************************
CAUTIONS
: 1. To prevent Raw Water Pump damage, maintain flowrates between 1700 and 8500 gpm per pump.
: 2. Backup cooling should not be used on Containment Cooling Coils with river level less than 983.5 ft or Containment temperatures greater than 150&deg;F.
Flashing and potential water hammer in the Containment Coils may be present with Raw Water aligned under low river conditions (<983.5 ft) and at higher temperatures.
: 3. To prevent seal degradation, it is desirable to align RW to operating HPSI, LPSI and CS Pumps. During Shutdown Cooling operations, it should be aligned within one hour. However, after a RAS, a loss of cooling water can be tolerated with no loss of pump performance.
  ****************************************************************************************************
: c. IF VA-3A, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1A by performing the following steps:
: 1)   Place CNTMT CLG COIL VA-1A AC VLVS CONTROL SW HCV-400B/D in CLOSE.
(continue)
R14


AOP-11 Page 28 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12.g (continued)
AOP-11 Page 22 of 49 INSTRUCTIONS                               CONTINGENCY ACTIONS 12.c. (continued)
NOTE  The operator may need assistance during performance of the next step as the handwheel may be difficult to reach. Climbi ng on wall-mounted accumulators to reach the handwheel should be avoided. 2) Unlock and release the hand-jacks from BOTH of the following SDC HX RW  
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
* HCV-400E, CNTMT VA-1A COOLING COIL RAW WATER INLET VALVE
* HCV-400F, CNTMT VA-1A COOLING COIL BACK-UP RAW WATER OUTLET VALVE
: 3) Locally open both VA-1A RW Interface Valves, HCV-400E/F by placing the following valves to OPEN (Room 69):
* IA-HCV-400E-TV, 4-WAY MANUAL CONTROL VALVE
* IA-HCV-400F-TV, 4-WAY MANUAL CONTROL VALVE (continue)
R14


Interface Valves (Corridor 4):
AOP-11 Page 23 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS
HCV-482A, "SHUTDOWN COOLING HT EXCH AC-4A BACK-UP RAW  
: 12. (continued)
: d. IF VA-3B, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1B by performing the following steps:
: 1)  Place CNTMT CLG COIL VA-1B AC VLVS CONTROL SW HCV-401B/D in CLOSE.
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
* HCV-401E, CNTMT VA-1B COOLING COIL BACK-UP RAW WATER INLET VALVE
* HCV-401F, CNTMT VA-1B COOLING COIL BACK-UP RAW WATER OUTLET VALVE (continue)
R14


WATER INLET VALVE" HCV-482B, "SHUTDOWN COOLING HT EXCH
AOP-11 Page 24 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.d (continued)
: 3)  Locally open both VA-1B RW Interface Valves, HCV-401E/F by placing the following valves in OPEN (Room 69):
* IA-HCV-401E-TV, 4-WAY MANUAL CONTROL VALVE
* IA-HCV-401F-TV, 4-WAY MANUAL CONTROL VALVE
: e. IF VA-7C, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8A by performing the following steps:
: 1)  Place CNTMT CLG COIL VA-8A AC VLVS CONTROL SW HCV-402B/D in CLOSE.
(continue)
R14


AC-4A BACK-UP RAW  
AOP-11 Page 25 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.e (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
* HCV-402E, CNTMT VA-8A COOLING COIL BACK-UP RAW WATER INLET VALVE
* HCV-402F, CNTMT VA-8A COOLING COIL BACK-UP RAW WATER OUTLET VALVE
: 3) Locally open both VA-8A RW Interface Valves, HCV-402E/F by placing the following valves to OPEN (Room 69):
* IA-HCV-402E-TV, 4-WAY MANUAL CONTROL VALVE
* IA-HCV-402F-TV, 4-WAY MANUAL CONTROL VALVE (continue)
R14


WATER OUTLET VALVE"
AOP-11 Page 26 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS
: 3) Locally open both AC-4A RW Interface Valves by placing the following valves to
: 12. (continued)
: f. IF VA-7D, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8B by performing the following steps:
: 1)   Place CNTMT CLG COIL VA-8B AC VLVS CONTROL SW HCV-403B/D in CLOSE.
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
* HCV-403E, RAW WATER RETURN HEADER TO CONT AIR CLNG &
FILTERING ISOLATION VALVE
* HCV-403F, CNTMT VA-8B COOLING COIL BACK-UP RAW WATER OUTLET VALVE (continue)
R14


"OPEN" (Corridor 4):
AOP-11 Page 27 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS 12.f (continued)
IA-HCV-482A-TV, "3-WAY MANUAL CONTROL VALVE"  IA-HCV-482B-TV, "3-WAY MANUAL CONTROL  
: 3)  Locally open both VA-8B RW Interface Valves, HCV-403E/F by placing the following valves to OPEN (Room 69):
* IA-HCV-403E-TV, 4-WAY MANUAL CONTROL VALVE
* IA-HCV-403F-TV, 4-WAY MANUAL CONTROL VALVE
: g. IF AC-4A, SDC HX, is in service, THEN establish RW flow to AC-4A by performing the following steps:
: 1)  Close BOTH AC-4A CCW Isolation Valves:
* HCV-480
* HCV-484 (continue)
R14


VALVE" AOP-11 Page 29 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12. (continued)
AOP-11 Page 28 of 49 INSTRUCTIONS                                   CONTINGENCY ACTIONS 12.g  (continued)
: h. IF AC-4B, SDC HX, is in service, THEN establish RW flow to AC-4B by performing the  
NOTE The operator may need assistance during performance of the next step as the handwheel may be difficult to reach. Climbing on wall-mounted accumulators to reach the handwheel should be avoided.
: 2)  Unlock and release the hand-jacks from BOTH of the following SDC HX RW Interface Valves (Corridor 4):
* HCV-482A, SHUTDOWN COOLING HT EXCH AC-4A BACK-UP RAW WATER INLET VALVE
* HCV-482B, SHUTDOWN COOLING HT EXCH AC-4A BACK-UP RAW WATER OUTLET VALVE
: 3)  Locally open both AC-4A RW Interface Valves by placing the following valves to OPEN (Corridor 4):
* IA-HCV-482A-TV, 3-WAY MANUAL CONTROL VALVE
* IA-HCV-482B-TV, 3-WAY MANUAL CONTROL VALVE R14


following steps:
AOP-11 Page 29 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS
: 1) Close BOTH AC-4B CCW Isolation Valves:
: 12. (continued)
HCV-481 HCV-485     2) Unlock and release the hand-jacks from BOTH of the following RW Interface  
: h. IF AC-4B, SDC HX, is in service, THEN establish RW flow to AC-4B by performing the following steps:
: 1)   Close BOTH AC-4B CCW Isolation Valves:
* HCV-481
* HCV-485
: 2)   Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Corridor 4):
* HCV-483A, SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER INLET VALVE
* HCV-483B, SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER OUTLET VALVE (continue)
R14


Valves (Corridor 4):
AOP-11 Page 30 of 49 INSTRUCTIONS                                     CONTINGENCY ACTIONS 12.h (continued)
HCV-483A, "SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW
: 3)   Locally open both AC-4B RW Interface Valves, HCV-483A/B, by placing the following valves to OPEN (Corridor 4):
 
* IA-HCV-483A-TV, 3-WAY MANUAL CONTROL VALVE
WATER INLET VALVE" HCV-483B, "SHUTDOWN COOLING HT EXCH
* IA-HCV-483B-TV, 3-WAY MANUAL CONTROL VALVE
 
: i. IF VA-46A, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46A, by performing the following steps:
AC-4B BACK-UP RAW
NOTE Manual isolation of RW direct cooling is required when LAS-2898 alarms.
 
: 1)   Close HCV-2898A/B, CCW Valves.
WATER OUTLET VALVE" (continue)
(continue)
 
R14
AOP-11 Page 30 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12.h (continued)
: 3) Locally open both AC-4B RW Interface Valves, HCV-483A/B, by placing the  
 
following valves to "OPEN" (Corridor 4):
IA-HCV-483A-TV, "3-WAY MANUAL CONTROL VALVE"  IA-HCV-483B-TV, "3-WAY MANUAL CONTROL  
 
VALVE"      i. IF VA-46A, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46A, by performing the  
 
following steps:
NOTE Manual isolation of RW direct coo ling is required when LAS-2898 alarms. 1) Close HCV-2898A/B, CCW Valves.   (continue)  
 
AOP-11 Page 31 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.i (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 81):
HCV-2898C, "CONTROL ROOM VA UNIT VA-46A RAW WATER INLET
 
VALVE"  HCV-2898D, "CONTROL ROOM VA UNIT VA-46A
 
RAW WATER OUTLET


VALVE"      3) Open BOTH HCV-2898C/D, VA-46A RW Valves by placing the following valves  
AOP-11 Page 31 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.i (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 81):
* HCV-2898C, CONTROL ROOM VA UNIT VA-46A RAW WATER INLET VALVE
* HCV-2898D, CONTROL ROOM VA UNIT VA-46A RAW WATER OUTLET VALVE
: 3) Open BOTH HCV-2898C/D, VA-46A RW Valves by placing the following valves to OPEN (Room 81):
* IA-HCV-2898C-TV, 3-WAY MANUAL CONTROL VALVE
* IA-HCV-2898D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14


to "OPEN" (Room 81):
AOP-11 Page 32 of 49 INSTRUCTIONS                                    CONTINGENCY ACTIONS
IA-HCV-2898C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2898D-TV, "3-WAY MANUAL
: 12.  (continued)
: j. IF VA-46B, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46B by performing the following steps:
NOTE Manual isolation of RW direct cooling is required when LAS-2899 alarms.
: 1)  Close HCV-2899A/B, VA-46B CCW Valves.
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 81):
* HCV-2899C, CONTROL ROOM VA UNIT VA-46B RAW WATER INLET VALVE
* HCV-2899D, CONTROL ROOM VA UNIT VA-46B RAW WATER OUTLET VALVE (continue)
R14


CONTROL VALVE" (continue)
AOP-11 Page 33 of 49 INSTRUCTIONS                                 CONTINGENCY ACTIONS 12.j (continued)
 
: 3) Open BOTH HCV-2899C/D, VA-46B RW Valves by placing the following valves to OPEN (Room 81):
AOP-11 Page 32 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
* IA-HCV-2899C-TV, 3-WAY MANUAL CONTROL VALVE
: j. IF VA-46B, Control Room Ventilation Fan, is in service, 
* IA-HCV-2899D-TV, 3-WAY MANUAL CONTROL VALVE
 
THEN establish RW flow to VA-46B by performing the
 
following steps:
NOTE  Manual isolation of RW direct coo ling is required when LAS-2899 alarms. 1) Close HCV-2899A/B, VA-46B CCW Valves.
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 81):
HCV-2899C, "CONTROL ROOM VA UNIT VA-46B RAW WATER INLET
 
VALVE"  HCV-2899D, "CONTROL ROOM VA UNIT VA-46B
 
RAW WATER OUTLET
 
VALVE" (continue)
 
AOP-11 Page 33 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12.j (continued)
: 3) Open BOTH HCV-2899C/D, VA-46B RW Valves by  
 
placing the following valves  
 
to "OPEN" (Room 81):
IA-HCV-2899C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2899D-TV, "3-WAY MANUAL  
 
CONTROL VALVE"
: k. IF SI-3A, CS Pump, is in service, THEN establish RW flow to SI-3A by performing the following steps:
: k. IF SI-3A, CS Pump, is in service, THEN establish RW flow to SI-3A by performing the following steps:
: 1) Close HCV-2813A/B, Spray Pump SI-3A Bearing Cooler CCW Valves.  
: 1) Close HCV-2813A/B, Spray Pump SI-3A Bearing Cooler CCW Valves.
 
(continue)
(continue)  
R14
 
AOP-11 Page 34 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.k (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 21):
HCV-2813C, "CNTMT SPRAY PUMP SI-3A BRG CLR RAW WATER INLET
 
VALVE"  HCV-2813D, "CNTMT SPRAY PUMP SI-3A BRG
 
CLR RAW WATER
 
OUTLET VALVE"
: 3) Locally open HCV-2813C/D, Spray Pump SI-3A Bearing Cooler RW Valves by placing
 
the following valves to


"OPEN" (Room 21):
AOP-11 Page 34 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.k (continued)
IA-HCV-2813C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2813D-TV, "3-WAY MANUAL  
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
* HCV-2813C, CNTMT SPRAY PUMP SI-3A BRG CLR RAW WATER INLET VALVE
* HCV-2813D, CNTMT SPRAY PUMP SI-3A BRG CLR RAW WATER OUTLET VALVE
: 3) Locally open HCV-2813C/D, Spray Pump SI-3A Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
* IA-HCV-2813C-TV, 3-WAY MANUAL CONTROL VALVE
* IA-HCV-2813D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14


CONTROL VALVE" (continue)  
AOP-11 Page 35 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS
: 12. (continued)
: l. IF SI-1A, LPSI Pump, is in service, THEN establish RW flow to SI-1A by performing the following steps:
: 1)  Close HCV-2808A/B, LPSI Pump SI-1A Bearing Cooler CCW Valves.
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
* HCV-2808C, LPSI PUMP SI-1A BRG CLR RAW WATER INLET VALVE
* HCV-2808D, LPSI PUMP SI-1A BRG CLR RAW WATER OUTLET VALVE (continue)
R14


AOP-11 Page 35 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
AOP-11 Page 36 of 49 INSTRUCTIONS                                 CONTINGENCY ACTIONS 12.l (continued)
: l. IF SI-1A, LPSI Pump, is in service, 
: 3) Open HCV-2808C/D, SI-1A Bearing Cooler CCW Valves by placing the following valves to OPEN (Room 21):
 
* IA-HCV-2808C-TV, 3-WAY MANUAL CONTROL VALVE
THEN establish RW flow to SI-1A by performing the following steps:
* IA-HCV-2808D-TV, 3-WAY MANUAL CONTROL VALVE
: 1) Close HCV-2808A/B, LPSI Pump SI-1A Bearing Cooler
 
CCW Valves.
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 21):
HCV-2808C, "LPSI PUMP SI-1A BRG CLR RAW WATER INLET VALVE" HCV-2808D, "LPSI PUMP SI-1A BRG CLR RAW
 
WATER OUTLET VALVE"
 
(continue)
 
AOP-11 Page 36 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12.l (continued)
: 3) Open HCV-2808C/D, SI-1A Bearing Cooler CCW Valves  
 
by placing the following  
 
valves to "OPEN" (Room 21):
IA-HCV-2808C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2808D-TV, "3-WAY MANUAL  
 
CONTROL VALVE"
: m. IF SI-2A, HPSI Pump, is in service, THEN establish RW flow to SI-2A by performing the following steps:
: m. IF SI-2A, HPSI Pump, is in service, THEN establish RW flow to SI-2A by performing the following steps:
: 1) Close HCV-2810A/B, HPSI Pump SI-2A Bearing Cooler  
: 1) Close HCV-2810A/B, HPSI Pump SI-2A Bearing Cooler CCW Valves.
 
(continue)
CCW Valves.  
R14
 
(continue)  
 
AOP-11 Page 37 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.m (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 21):
HCV-2810C, "HPSI PUMP SI-2A BRG CLR RAW WATER INLET VALVE" HCV-2810D, "HPSI PUMP SI-2A BRG CLR RAW
 
WATER OUTLET VALVE"
: 3) Open HCV-2810C/D, SI-2A Bearing Cooler RW Valves by placing the following
 
valves to "OPEN" (Room 21):
IA-HCV-2810C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2810D-TV, "3-WAY MANUAL
 
CONTROL VALVE" (continue)
 
AOP-11 Page 38 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
: n. IF SI-2C, HPSI Pump, is in service, 
 
THEN establish RW flow to SI-2C by performing the following steps:
: 1) Close HCV-2812A/B, HPSI Pump SI-2C Bearing Cooler


CCW Valves.
AOP-11 Page 37 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.m (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface  
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
* HCV-2810C, HPSI PUMP SI-2A BRG CLR RAW WATER INLET VALVE
* HCV-2810D, HPSI PUMP SI-2A BRG CLR RAW WATER OUTLET VALVE
: 3) Open HCV-2810C/D, SI-2A Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
* IA-HCV-2810C-TV, 3-WAY MANUAL CONTROL VALVE
* IA-HCV-2810D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14


Valves (Room 21):
AOP-11 Page 38 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS
HCV-2812C, "HPSI PUMP SI-2C BRG CLR RAW WATER INLET VALVE" HCV-2812D, "HPSI PUMP SI-2C BRG CLR RAW  
: 12. (continued)
: n. IF SI-2C, HPSI Pump, is in service, THEN establish RW flow to SI-2C by performing the following steps:
: 1)  Close HCV-2812A/B, HPSI Pump SI-2C Bearing Cooler CCW Valves.
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
* HCV-2812C, HPSI PUMP SI-2C BRG CLR RAW WATER INLET VALVE
* HCV-2812D, HPSI PUMP SI-2C BRG CLR RAW WATER OUTLET VALVE (continue)
R14


WATER OUTLET VALVE"
AOP-11 Page 39 of 49 INSTRUCTIONS                                 CONTINGENCY ACTIONS 12.n (continued)
 
: 3) Open HCV-2812C/D, SI-2C Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
(continue)
* IA-HCV-2812C-TV, 3-WAY MANUAL CONTROL VALVE
 
* IA-HCV-2812D-TV, 3-WAY MANUAL CONTROL VALVE
AOP-11 Page 39 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12.n (continued)
: 3) Open HCV-2812C/D, SI-2C Bearing Cooler RW Valves  
 
by placing the following  
 
valves to "OPEN" (Room 21):
IA-HCV-2812C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2812D-TV, "3-WAY MANUAL  
 
CONTROL VALVE"
: o. IF SI-3B, Containment Spray Pump, is in service, THEN establish RW flow to SI-3B by performing the following steps:
: o. IF SI-3B, Containment Spray Pump, is in service, THEN establish RW flow to SI-3B by performing the following steps:
: 1) Close HCV-2814A/B, Spray Pump SI-3B Bearing Cooler  
: 1) Close HCV-2814A/B, Spray Pump SI-3B Bearing Cooler CCW Valves.
 
(continue)
CCW Valves.  
R14
 
(continue)
 
AOP-11 Page 40 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.o (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 22):
HCV-2814C, "CNTMT SPRAY PUMP SI-3B BRG CLR RAW WATER INLET
 
VALVE"  HCV-2814D, "CNTMT SPRAY PUMP SI-3B BRG
 
CLR RAW WATER
 
OUTLET VALVE"
: 3) Open HCV-2814C/D, SI-3B Bearing Cooler RW Valves by placing the following
 
valves to "OPEN" (Room 22):
IA-HCV-2814C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2814D-TV, "3-WAY MANUAL
 
CONTROL VALVE" (continue)  
 
AOP-11 Page 41 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
: p. IF SI-3C, Containment Spray Pump, is in service, 
 
THEN establish RW flow to SI-3C by performing the following steps:
: 1) Close HCV-2815A/B, Spray Pump SI-3C Bearing Cooler
 
CCW Valves.
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 22):
HCV-2815C, "CNTMT SPRAY PUMP SI-3C BRG CLR RAW WATER INLET


VALVE"  HCV-2815D, "CNTMT SPRAY PUMP SI-3C BRG  
AOP-11 Page 40 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.o (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
* HCV-2814C, CNTMT SPRAY PUMP SI-3B BRG CLR RAW WATER INLET VALVE
* HCV-2814D, CNTMT SPRAY PUMP SI-3B BRG CLR RAW WATER OUTLET VALVE
: 3) Open HCV-2814C/D, SI-3B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
* IA-HCV-2814C-TV, 3-WAY MANUAL CONTROL VALVE
* IA-HCV-2814D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
R14


CLR RAW WATER  
AOP-11 Page 41 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS
: 12. (continued)
: p. IF SI-3C, Containment Spray Pump, is in service, THEN establish RW flow to SI-3C by performing the following steps:
: 1)  Close HCV-2815A/B, Spray Pump SI-3C Bearing Cooler CCW Valves.
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
* HCV-2815C, CNTMT SPRAY PUMP SI-3C BRG CLR RAW WATER INLET VALVE
* HCV-2815D, CNTMT SPRAY PUMP SI-3C BRG CLR RAW WATER OUTLET VALVE (continue)
R14


OUTLET VALVE" (continue)
AOP-11 Page 42 of 49 INSTRUCTIONS                                 CONTINGENCY ACTIONS 12.p (continued)
 
: 3) Open HCV-2815C/D, SI-3C Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
AOP-11 Page 42 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS   12.p (continued)
* IA-HCV-2815C-TV, 3-WAY MANUAL CONTROL VALVE
: 3) Open HCV-2815C/D, SI-3C Bearing Cooler RW Valves  
* IA-HCV-2815D-TV, 3-WAY MANUAL CONTROL VALVE
 
by placing the following  
 
valves to "OPEN" (Room 22):
IA-HCV-2815C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2815D-TV, "3-WAY MANUAL  
 
CONTROL VALVE"
: q. IF SI-1B, LPSI Pump, is in service, THEN establish RW flow to SI-1B by performing the following steps:
: q. IF SI-1B, LPSI Pump, is in service, THEN establish RW flow to SI-1B by performing the following steps:
: 1) Close HCV-2809A/B, LPSI Pump SI-1B Bearing Cooler  
: 1) Close HCV-2809A/B, LPSI Pump SI-1B Bearing Cooler CCW Valves.
 
(continue)
CCW Valves.
R14
 
(continue)
 
AOP-11 Page 43 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.q (continued)
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 22):
HCV-2809C, "LPSI PUMP SI-1B BRG CLR RAW WATER INLET VALVE" HCV-2809D, "LPSI PUMP SI-1B BRG CLR RAW
 
WATER OUTLET VALVE"
: 3) Open HCV-2809C/D, SI-1B Bearing Cooler RW Valves by placing the following
 
valves to "OPEN" (Room 22):
IA-HCV-2809C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2809D-TV, "3-WAY MANUAL
 
CONTROL VALVE" (continue)
 
AOP-11 Page 44 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12. (continued)
: r. IF SI-2B, HPSI Pump, is in service, 
 
THEN establish RW flow to SI-2B by performing the following steps:
: 1) Close HCV-2811A/B, HPSI Pump SI-2B Bearing Cooler
 
CCW Valves.
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface
 
Valves (Room 22):
HCV-2811C, "HPSI PUMP SI-2B BRG CLR RAW WATER INLET VALVE" HCV-2811D, "HPSI PUMP SI-2B BRG CLR RAW
 
WATER OUTLET VALVE"
 
(continue)  
 
AOP-11 Page 45 of 49 R14 INSTRUCTIONS CONTINGENCY ACTIONS    12.r (continued)
: 3) Open HCV-2811C/D, SI-2B Bearing Cooler RW Valves
 
by placing the following
 
valves to "OPEN" (Room 22):
IA-HCV-2811C-TV, "3-WAY MANUAL CONTROL VALVE" IA-HCV-2811D-TV, "3-WAY MANUAL
 
CONTROL VALVE"
: s. IF SIAS relays are tripped, THEN override the open signals on RW/CCW Heat Exchanger Isolation Valves by placing BOTH of the following switches in
 
"OVERRIDE":
HC-4350, "AC-1A AND AC-1C RW VALVES SIAS OVERRIDE" HC-4351, "AC-1B AND AC-1D RW VALVES SIAS
 
OVERRIDE"
 
WP12 Fort Calhoun Station Unit No. 1 OI-AOV-1 OPERATING INSTRUCTION Title:AIR OPERATED VALVE MANUAL OPERATION                                                                                                                                                            FC-68 Number:EC 43771Reason for Change:Provided guidance for handjacking HCV-341.
Requestor:K. Kingston Preparer:L. HautzingerISSUED:    07-31-08    3:00 pmR12 FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 1 OF 69 R12 AIR OPERATED VALVE MANUAL OPERATION SAFETY RELATED ATT PURPOSE PAGE1 - Operation of Raw Water Air Operated Valves .....................................3 2 - Operation of Component Coo ling Water Air Operated Valves.........................133 - Operation of Safety Injection Air Operated Valves.................................34 4 - Operation of Chemical Volume Control System Air Operated Valves...................50 5 - Operation of Turbine Plant Cooling Water Air Operated Valves.......................51
 
6 - Operation of Containment Instrument Air Supply Outboard Pressure Control Valve........547 - Operation of Main Steam Air Operated Valves....................................56
 
8 - Operation of Feed Water Heater Level Control Air Operated Valves...................58 9 - Operation of Feed Water Air Operated Valves....................................62 PRECAUTIONS1.This procedure contains attachments to manually operate AOVs (Air Operated Valves) throughout the plant. Consideration should alwa ys be given to current plant conditions prior to operation of any of these valves manually.2.This procedure should only be used with proper planning and pre-operation briefings.
Contact the AOV Engineer with concerns prior to its use.3.This procedure is for guidance only and should not be used to mitigate plant transients unless authorized by the Shift Manger.4.Inoperability of a Raw Water Header, Raw Water Pump(s) and/or a Raw Water Heat Exchanger requires entry into Technical Specif ication LCO(s). The LCO entry is dependent on river temperature.
FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 2 OF 69 R12 REFERENCES/COMMITMENTS1.Technical Specifications:
!  2.3:  Emergency Core Cooling System
!  2.4:  Containment Cooling2.DrawingsFileDescription11405-M-10010454Raw Water System 11405-M-4044354Component Cooling System 11405-M-25910465Potable Water System 3.Others:!EA-FC-95-012, Effect of Post-DBA CCW Temperature Transient on Components
!OPPD Calculation FC07259, Rev.
0; FCS RW/CCW Gothic Model
!OPPD Calculation FC07238, Rev. 0; FCS RW/CCW Gothic Analyses - Additional
 
Configurations APPENDICES None C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 3 OF 69 R12 Attachment 1 - Operation of Raw Water Air Operated Valves PREREQUISITES () INITIALS1Procedure Revision Verification:
Revision No.
Date:             
 
PROCEDURE NOTES1.To minimize RW Pump operation in the run-out condition, the four CCW Heat Exchanger Discharge Isolation Valv es are set in a throttled position via the measured exposed valve stem. This throttling is intended to assist
 
the restricting orifaces in limit ing flow to approximately 3000-3500 gpm flow through one Hx with one pump running. The measured exposed valve stem is recorded in OI-RW-1-CL-A.2.At the Shift Manager's discretion th is throttled position may be adjusted to meet system and/or plant requirements.
If so the new measured exposed valve stem  shall be document ed in the Control Room Log, OI-RW-1-CL-A,  and on a new caution tag hung on the valves(s) adjusted.
If the throttle position is adjusted, the System Engineer should be notified in a timely manner to evaluate system flow conditions (i.e., the need for performance of SE-EQT-RW-0001).
The Caution Tag may be removed after OI-RW-1-CL-A has been updated.3.The four CCW Hx Discharge Isol ation Valves are equipped with a handjack to limit the open position of t he valve disc. These valves are handjacked closed when the HX is removed from service for
 
maintenance/cleaning.
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 4 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
()INITIALS R12 CAUTIONS1.Limit the time one RW Pump operates in the run out condition (Flows greater than 7500 gpm) to reduce the potential of pump degradation.2.Adjustment of the throttle positi on may cause limit switch contact mismatch for remote valve position indication.1.If handjacking HCV-2880B, HCV-2881B, HCV-2882B, OR HCV-2883B Closed, complete the following steps:a.Ensure the Raw Water Discharge Valve is Closed:
!HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve
!HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve
!HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve
!HCV-2883B, Comp CoolingValve b.Loosen the Handjacks stem nut and run it up to contact the bottom face of the handwheel:
!HCV-2880B!HCV-2881B!HCV-2882B!HCV-2883B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 5 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
()INITIALS R12 CAUTION Do not force the handwheel if excessive resistance is met before the Handjacks stem nut contacts the bonnet of the actuator housing. It is
 
possible that the valve disc is being forced into or beyond the valve seat.


This condition can cause the valve to be stuck in the closed position.1c.Turn the handwheel clockwise until t he handjacks stem nut contacts the bonnet of the actuator housing:
AOP-11 Page 43 of 49 INSTRUCTIONS                              CONTINGENCY ACTIONS 12.q (continued)
!HCV-2880B!HCV-2881B!HCV-2882B!HCV-2883B                        d.If excessive resistance is met befor e the stem nut contacts the bonnet ofthe actuator housing, contact the System Engineer.              2.If removing the valve handjacks from a RW Discharge Valve, perform the following:a.Turn handwheel counter-clockwise until the measured valve stem matches the stem position recorded in OI-RW-1-CL-A:
: 2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
!HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve
* HCV-2809C, LPSI PUMP SI-1B BRG CLR RAW WATER INLET VALVE
!HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve
* HCV-2809D, LPSI PUMP SI-1B BRG CLR RAW WATER OUTLET VALVE
!HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve
: 3) Open HCV-2809C/D, SI-1B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
!HCV-2883B, Comp Cooling Ht Exch AC-1D Raw Water Outlet Valve b.Run the Handjacks stem nut down unt il it contacts the bonnet of the actuator housing:
* IA-HCV-2809C-TV, 3-WAY MANUAL CONTROL VALVE
!HCV-2880B!HCV-2881B!HCV-2882B!HCV-2883B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 6 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
* IA-HCV-2809D-TV, 3-WAY MANUAL CONTROL VALVE (continue)
()INITIALS R122c.Verify the exposed threaded s haft measurement and adjust as necessary:
R14
!HCV-2880B!HCV-2881B!HCV-2882B!HCV-2883B                        d.Stroke the valve(s) as necessary to verify proper operation and position indication:
!HCV-2880B!HCV-2881B!HCV-2882B!HCV-2883B NOTES1.The Declutching pin will automatically move out of the outer slot when the hand wheel is pushed in.2.When the worm gear is fully engaging the gear segment, the pin will drop into the inner slot.3.If handjacking HCV-2880A, HCV-2881A, HCV-2882A, or HCV-2883A is desired, complete the following for the applicable valves:a.Engage the handwheel by pushing in and turning clockwise:
!HCV-2880A!HCV-2881A!HCV-2882A!HCV-2883A                        b.Place the valve in the desired position:
!HCV-2880A!HCV-2881A!HCV-2882A!HCV-2883A C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 7 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
()INITIALS R124.If removing the handjack, complete the following for the applicable valve:a.Simultaneously press declutching spring to push the pin out, and turn the hand wheel counterclockwise until the worm gear disengages the gear segment:
!HCV-2880A, Comp Cooling Ht Exch AC-1A Raw Water Inlet Valve
!HCV-2881A, Comp Cooling Ht Exch AC-1B Raw Water Inlet Valve
!HCV-2882A, Comp Cooling Ht Exch AC-1C Raw Water Inlet Valve
!HCV-2883A, Comp Cooling Ht Exch AC-1D Raw Water Inlet Valve NOTE The pin engages the outer slot to keep the handwheel in the engaged


position.b.Allow the spring to move the handwheel all of the way out, and release the pin:!HCV-2880A!HCV-2881A!HCV-2882A!HCV-2883A                        c.Stroke the valve(s) as necessary to verify proper operation and position indication:
AOP-11 Page 44 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS
!HCV-2880A!HCV-2881A!HCV-2882A!HCV-2883A C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 8 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
: 12. (continued)
()INITIALS R125.If hand jacking HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, HCV-2893, OR HCV-2894, perform the following:a.Ensure selected valve is Closed:
: r. IF SI-2B, HPSI Pump, is in service, THEN establish RW flow to SI-2B by performing the following steps:
!HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve 
: 1)  Close HCV-2811A/B, HPSI Pump SI-2B Bearing Cooler CCW Valves.
!HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
: 2)  Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
* HCV-2811C, HPSI PUMP SI-2B BRG CLR RAW WATER INLET VALVE
* HCV-2811D, HPSI PUMP SI-2B BRG CLR RAW WATER OUTLET VALVE (continue)
R14


Isolation Valve 
AOP-11 Page 45 of 49 INSTRUCTIONS                                CONTINGENCY ACTIONS 12.r (continued)
!HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
: 3)  Open HCV-2811C/D, SI-2B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
* IA-HCV-2811C-TV, 3-WAY MANUAL CONTROL VALVE
* IA-HCV-2811D-TV, 3-WAY MANUAL CONTROL VALVE
: s. IF SIAS relays are tripped, THEN override the open signals on RW/CCW Heat Exchanger Isolation Valves by placing BOTH of the following switches in OVERRIDE:
* HC-4350, AC-1A AND AC-1C RW VALVES SIAS OVERRIDE
* HC-4351, AC-1B AND AC-1D RW VALVES SIAS OVERRIDE R14


Isolation Valve 
WP12 Fort Calhoun Station Unit No. 1 OI-AOV-1 OPERATING INSTRUCTION Title:  AIR OPERATED VALVE MANUAL OPERATION FC-68 Number:        EC 43771 Reason for Change:  Provided guidance for handjacking HCV-341.
!HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
Requestor:          K. Kingston Preparer:            L. Hautzinger ISSUED:    07-31-08 3:00 pm                                    R12


Isolation Valve
FORT CALHOUN STATION                                                                                        OI-AOV-1 OPERATING INSTRUCTION                                                                                PAGE 1 OF 69 AIR OPERATED VALVE MANUAL OPERATION SAFETY RELATED ATT PURPOSE                                                                                                      PAGE 1 - Operation of Raw Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2 - Operation of Component Cooling Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . 13 3 - Operation of Safety Injection Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 4 - Operation of Chemical Volume Control System Air Operated Valves . . . . . . . . . . . . . . . . . . . 50 5 - Operation of Turbine Plant Cooling Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . 51 6 - Operation of Containment Instrument Air Supply Outboard Pressure Control Valve . . . . . . . . 54 7 - Operation of Main Steam Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 8 - Operation of Feed Water Heater Level Control Air Operated Valves . . . . . . . . . . . . . . . . . . . 58 9 - Operation of Feed Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 PRECAUTIONS
!HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
: 1. This procedure contains attachments to manually operate AOVs (Air Operated Valves) throughout the plant. Consideration should always be given to current plant conditions prior to operation of any of these valves manually.
: 2. This procedure should only be used with proper planning and pre-operation briefings.
Contact the AOV Engineer with concerns prior to its use.
: 3. This procedure is for guidance only and should not be used to mitigate plant transients unless authorized by the Shift Manger.
: 4. Inoperability of a Raw Water Header, Raw Water Pump(s) and/or a Raw Water Heat Exchanger requires entry into Technical Specification LCO(s). The LCO entry is dependent on river temperature.
R12


Isolation Valve 
FORT CALHOUN STATION                                                            OI-AOV-1 OPERATING INSTRUCTION                                                      PAGE 2 OF 69 REFERENCES/COMMITMENTS
!HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
: 1. Technical Specifications:
    ! 2.3: Emergency Core Cooling System
    ! 2.4: Containment Cooling
: 2. Drawings          File              Description 11405-M-100      10454            Raw Water System 11405-M-40        44354            Component Cooling System 11405-M-259      10465            Potable Water System
: 3. Others:
    !   EA-FC-95-012, Effect of Post-DBA CCW Temperature Transient on Components
    !  OPPD Calculation FC07259, Rev. 0; FCS RW/CCW Gothic Model
    !  OPPD Calculation FC07238, Rev. 0; FCS RW/CCW Gothic Analyses - Additional Configurations APPENDICES None R12


Isolation Valve 
FORT CALHOUN STATION                                                                 OI-AOV-1 OPERATING INSTRUCTION                                                           PAGE 3 OF 69 C
!HCV-2893, Raw Water to CCW Isolation Valve
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PREREQUISITES                                                                    (%) INITIALS 1  Procedure Revision Verification:
!HCV-2894, Raw Water to CCW Isolation Valve b.Loosen the nut on the hand jack stem for selected valves:
Revision No.                 Date:
!HCV-2877A 
PROCEDURE NOTES
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 9 OF 69 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
: 1. To minimize RW Pump operation in the run-out condition, the four CCW Heat Exchanger Discharge Isolation Valves are set in a throttled position via the measured exposed valve stem. This throttling is intended to assist the restricting orifaces in limiting flow to approximately 3000-3500 gpm flow through one Hx with one pump running. The measured exposed valve stem is recorded in OI-RW-1-CL-A.
()INITIALS R125c.Turn the hand wheel CLOCKWISE, counting each turn, until handwheel stop contacts diaphragm for selected valves:
: 2. At the Shift Manager's discretion this throttled position may be adjusted to meet system and/or plant requirements. If so the new measured exposed valve stem shall be documented in the Control Room Log, OI-RW-1-CL-A, and on a new caution tag hung on the valves(s) adjusted.
!HCV-2877A, Turns:___________
If the throttle position is adjusted, the System Engineer should be notified in a timely manner to evaluate system flow conditions (i.e., the need for performance of SE-EQT-RW-0001). The Caution Tag may be removed after OI-RW-1-CL-A has been updated.
!HCV-2877B,Turns:___________
: 3. The four CCW Hx Discharge Isolation Valves are equipped with a handjack to limit the open position of the valve disc. These valves are handjacked closed when the HX is removed from service for maintenance/cleaning.
!HCV-2878A, Turns:___________
R12
!HCV-2878B, Turns:___________
!HCV-2879A, Turns:___________
!HCV-2879B, Turns:___________
!HCV-2893, Turns:___________
!HCV-2894, Turns:___________
d.Tighten the hand jack locking nut against diaphragm housing for selected valves:
!HCV-2877A 
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894                                                e.Record the number of turns on t he danger/caution tag end, and in the tag removal notes of the clearance for selected valves:
!HCV-2877A 
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 10 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
()INITIALS R126.If removing the handjack from HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, perform the following:a.Ensure air drain on filter regulat or for selected valve(s) is closed:
!HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
!HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header


Isolation Valve
FORT CALHOUN STATION                                                                OI-AOV-1 OPERATING INSTRUCTION                                                          PAGE 4 OF 69 C
!HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS CAUTIONS
: 1. Limit the time one RW Pump operates in the run out condition (Flows greater than 7500 gpm) to reduce the potential of pump degradation.
: 2. Adjustment of the throttle position may cause limit switch contact mismatch for remote valve position indication.
: 1. If handjacking HCV-2880B, HCV-2881B, HCV-2882B, OR HCV-2883B Closed, complete the following steps:
: a. Ensure the Raw Water Discharge Valve is Closed:
        !   HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve
        !    HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve
        !    HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve
        !    HCV-2883B, Comp CoolingValve
: b. Loosen the Handjacks stem nut and run it up to contact the bottom face of the handwheel:
        !    HCV-2880B
        !    HCV-2881B
        !    HCV-2882B
        !    HCV-2883B R12


Isolation Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                              PAGE 5 OF 69 C
!HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS CAUTION Do not force the handwheel if excessive resistance is met before the Handjacks stem nut contacts the bonnet of the actuator housing. It is possible that the valve disc is being forced into or beyond the valve seat.
This condition can cause the valve to be stuck in the closed position.
1  c. Turn the handwheel clockwise until the handjacks stem nut contacts the bonnet of the actuator housing:
        !    HCV-2880B
        !    HCV-2881B
        !    HCV-2882B
        !    HCV-2883B
: d. If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer.
: 2. If removing the valve handjacks from a RW Discharge Valve, perform the following:
: a. Turn handwheel counter-clockwise until the measured valve stem matches the stem position recorded in OI-RW-1-CL-A:
        !   HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve
        !    HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve
        !    HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve
        !    HCV-2883B, Comp Cooling Ht Exch AC-1D Raw Water Outlet Valve
: b. Run the Handjacks stem nut down until it contacts the bonnet of the actuator housing:
        !    HCV-2880B
        !    HCV-2881B
        !    HCV-2882B
        !    HCV-2883B R12


Isolation Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 6 OF 69 C
!HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS 2  c. Verify the exposed threaded shaft measurement and adjust as necessary:
        !    HCV-2880B
        !    HCV-2881B
        !    HCV-2882B
        !    HCV-2883B
: d. Stroke the valve(s) as necessary to verify proper operation and position indication:
        !    HCV-2880B
        !   HCV-2881B
        !    HCV-2882B
        !    HCV-2883B NOTES
: 1. The Declutching pin will automatically move out of the outer slot when the hand wheel is pushed in.
: 2. When the worm gear is fully engaging the gear segment, the pin will drop into the inner slot.
: 3. If handjacking HCV-2880A, HCV-2881A, HCV-2882A, or HCV-2883A is desired, complete the following for the applicable valves:
: a. Engage the handwheel by pushing in and turning clockwise:
        !    HCV-2880A
        !    HCV-2881A
        !    HCV-2882A
        !    HCV-2883A
: b. Place the valve in the desired position:
        !    HCV-2880A
        !    HCV-2881A
        !    HCV-2882A
        !    HCV-2883A R12


Isolation Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 7 OF 69 C
!HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS
: 4. If removing the handjack, complete the following for the applicable valve:
: a. Simultaneously press declutching spring to push the pin out, and turn the hand wheel counterclockwise until the worm gear disengages the gear segment:
        !    HCV-2880A, Comp Cooling Ht Exch AC-1A Raw Water Inlet Valve
        !   HCV-2881A, Comp Cooling Ht Exch AC-1B Raw Water Inlet Valve
        !    HCV-2882A, Comp Cooling Ht Exch AC-1C Raw Water Inlet Valve
        !    HCV-2883A, Comp Cooling Ht Exch AC-1D Raw Water Inlet Valve NOTE The pin engages the outer slot to keep the handwheel in the engaged position.
: b. Allow the spring to move the handwheel all of the way out, and release the pin:
        !    HCV-2880A
        !    HCV-2881A
        !    HCV-2882A
        !    HCV-2883A
: c. Stroke the valve(s) as necessary to verify proper operation and position indication:
        !    HCV-2880A
        !    HCV-2881A
        !    HCV-2882A
        !    HCV-2883A R12


Isolation Valve 
FORT CALHOUN STATION                                                           OI-AOV-1 OPERATING INSTRUCTION                                                       PAGE 8 OF 69 C
!HCV-2893, Raw Water to CCW Isolation Valve
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                       (T) INITIALS
!HCV-2894, Raw Water to CCW Isolation Valve b.Ensure Air Supply Isolation Valve(s) for selected Valve is open:
: 5. If hand jacking HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, HCV-2893, OR HCV-2894, perform the following:
!HCV-2877A!HCV-2878B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 11 OF 69 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
: a. Ensure selected valve is Closed:
()INITIALS R12 NOTE On removing power from the valve, the solenoid will fail the valve open.6c.Ensure selected valve has a Closed signal:
        !   HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
!HCV-2877A!HCV-2878B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894                                               d.Loosen the Locking nut on selected valve handwheel stem:
        !   HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
!HCV-2877A
        !   HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894                                                e.Turn handwheel COUNTER-CLOCKWISE the number of turns recorded in step 5.c for selected valves:
        !   HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
!HCV-2877A 
        !   HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 12 OF 69  - Operation of Raw Water Air Operated Valves PROCEDURE (continued)
        !   HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
()INITIALS R126f.Tighten lock nut on valve stem against diaphragm housing for selected valve:!HCV-2877A
        !   HCV-2893, Raw Water to CCW Isolation Valve
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894                                                g.Stroke valve as needed to ensure proper operation and indication for selected valve:
        !   HCV-2894, Raw Water to CCW Isolation Valve
!HCV-2877A 
: b. Loosen the nut on the hand jack stem for selected valves:
!HCV-2877B!HCV-2878A!HCV-2878B!HCV-2879A!HCV-2879B!HCV-2893!HCV-2894 Completed by Date/Time            /
        !   HCV-2877A
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 13 OF 69 R12 Attachment 2 - Operation of Component Cooling Water Air Operated Valves PREREQUISITES
        !   HCV-2877B
()INITIALS1.Procedure Revision Verification Revision No.
        !   HCV-2878A
Date:             
        !   HCV-2878B
        !   HCV-2879A
        !   HCV-2879B
        !   HCV-2893
        !   HCV-2894 R12


PROCEDURE CAUTION Operating a valve hand jack against spring pressure may cause valve damage.1.If hand jacking  HCV-489A, HCV-490A/B , HCV-491B, or HCV-492A/B, Comp Cooling Ht Exchs AC-1A-D CCW Valves, Closed, complete the following:a.Ensure valve to be hand jacked is Closed:
FORT CALHOUN STATION                                                           OI-AOV-1 OPERATING INSTRUCTION                                                       PAGE 9 OF 69 C
!HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                       (T) INITIALS 5  c. Turn the hand wheel CLOCKWISE, counting each turn, until handwheel stop contacts diaphragm for selected valves:
!HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve
      !   HCV-2877A, Turns:___________
!HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve
      !   HCV-2877B, Turns:___________
!HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve
      !   HCV-2878A, Turns:___________
!HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve
      !   HCV-2878B, Turns:___________
!HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve b.Align and insert J-hook into slot on the manual operator side of the valve
      !   HCV-2879A, Turns:___________
!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 14 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
      !   HCV-2879B, Turns:___________
()INITIALS R121c.Loosen hose clamp and remove J-hook from the air operator side of the valve:!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B                                    d.Re-tighten hose clamp around slot to prevent J-hook from entering slot:
      !   HCV-2893, Turns:___________
!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B                                                  2.If removing hand jack from HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exch AC-1A CCW Valves, complete the following:a.Ensure valve has a Closed signal:
      !   HCV-2894, Turns:___________
!HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve
: d. Tighten the hand jack locking nut against diaphragm housing for selected valves:
!HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve
      !   HCV-2877A
!HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve
      !   HCV-2877B
!HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve
      !   HCV-2878A
!HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve
      !   HCV-2878B
!HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve b.Ensure that the valve is manually hand jacked in the Closed position:
      !   HCV-2879A
!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 15 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
      !   HCV-2879B
()INITIALS R122c.Loosen hose clamp and insert J-hook into slot on air operator side of the valve:!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B                                    d.Re-tighten the hose clam p around J-hook and the slot:
      !   HCV-2893
!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B                                    e.Remove J-hook from the slot on t he manual operator side of the valve:
      !   HCV-2894
!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B                                                  f.Stroke valve as necessary to verify proper operation and position indication:
: e. Record the number of turns on the danger/caution tag end, and in the tag removal notes of the clearance for selected valves:
!HCV-489A!HCV-490A!HCV-490B!HCV-491B!HCV-492A!HCV-492B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 16 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
      !   HCV-2877A
()INITIALS R123.If hand jacking HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:a.Ensure valve to be hand jacked is Closed:
      !   HCV-2877B
!HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve
      !   HCV-2878A
!HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve b.Align notch in pointer to hole in gear on manual operator and insert pin.
      !   HCV-2878B
!HCV-489B!HCV-491A            c.Loosen hose clamp and remove J-hook from the air operator side of the valve.!HCV-489B!HCV-491A            d.Re-tighten hose clamp around slot to prevent J-hook from entering slot.
      !   HCV-2879A
!HCV-489B!HCV-491A                          4.If removing hand jack from HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Coo ling Ht Exch AC-1C CCW Inlet Valve, Closed,  complete the following:
      !   HCV-2879B
a.Ensure valve has a Closed signal:
      !   HCV-2893
!HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve
      !   HCV-2894 R12
!HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve b.Ensure that the valve is manually hand jacked in the closed position.
!HCV-489B!HCV-491A C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 17 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
()INITIALS R124c.Loosen hose clamp and insert J-hook into slot on air operator side of the valve.!HCV-489B!HCV-491A            d.Re-tighten the hose clam p around J-hook and the slot.
!HCV-489B!HCV-491A            e.Remove pin from manual operator.
!HCV-489B!HCV-491A            f.Stroke the valve  as necessary to verify proper operation and position indication.
!HCV-489B!HCV-491A                          5.If hand jacking HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:a.Ensure HCV-497 is Open.      b.Loosen stem nut.
c.Turn handwheel clockwise until handwheel stem pusher plate contactsdiaphragm plate.      d.Tighten stem nut.
6.If removing hand jack from HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
a.Ensure HCV-497 has an Open signal.      b.Loosen stem nut.


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 18 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
FORT CALHOUN STATION                                                               OI-AOV-1 OPERATING INSTRUCTION                                                         PAGE 10 OF 69 C
()INITIALS R126c.Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusherplate contacts upper diaphragm casing.      d.Tighten stem nut.
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                           (T) INITIALS
e.Stroke HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve as necessary to verify proper operation and positionindication.
: 6. If removing the handjack from HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, perform the following:
7.If hand jacking HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolati on Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard
: a. Ensure air drain on filter regulator for selected valve(s) is closed:
        !  HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
        !  HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
        !  HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
        !  HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
        !  HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
        !  HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve
        !  HCV-2893, Raw Water to CCW Isolation Valve
        !  HCV-2894, Raw Water to CCW Isolation Valve
: b. Ensure Air Supply Isolation Valve(s) for selected Valve is open:
        !  HCV-2877A
        !  HCV-2878B
        !  HCV-2878A
        !  HCV-2878B
        !  HCV-2879A
        !  HCV-2879B
        !  HCV-2893
        !  HCV-2894 R12


Isolation Valves, Open, complete the following:a.Ensure that the valve to be hand jacked is Open:
FORT CALHOUN STATION                                                                OI-AOV-1 OPERATING INSTRUCTION                                                          PAGE 11 OF 69 C
!HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS NOTE On removing power from the valve, the solenoid will fail the valve open.
!HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet
6  c. Ensure selected valve has a Closed signal:
        !    HCV-2877A
        !    HCV-2878B
        !    HCV-2878A
        !    HCV-2878B
        !    HCV-2879A
        !    HCV-2879B
        !    HCV-2893
        !    HCV-2894
: d. Loosen the Locking nut on selected valve handwheel stem:
        !    HCV-2877A
        !    HCV-2877B
        !    HCV-2878A
        !    HCV-2878B
        !    HCV-2879A
        !    HCV-2879B
        !    HCV-2893
        !    HCV-2894
: e. Turn handwheel COUNTER-CLOCKWISE the number of turns recorded in step 5.c for selected valves:
        !    HCV-2877A
        !    HCV-2877B
        !   HCV-2878A
        !    HCV-2878B
        !    HCV-2879A
        !   HCV-2879B
        !    HCV-2893
        !    HCV-2894 R12


Header Outboard Isolation Valve
FORT CALHOUN STATION                                                                OI-AOV-1 OPERATING INSTRUCTION                                                          PAGE 12 OF 69 C
!HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet
Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS 6  f. Tighten lock nut on valve stem against diaphragm housing for selected valve:
        !   HCV-2877A
        !    HCV-2877B
        !    HCV-2878A
        !    HCV-2878B
        !    HCV-2879A
        !    HCV-2879B
        !    HCV-2893
        !    HCV-2894
: g. Stroke valve as needed to ensure proper operation and indication for selected valve:
        !    HCV-2877A
        !    HCV-2877B
        !    HCV-2878A
        !    HCV-2878B
        !    HCV-2879A
        !    HCV-2879B
        !    HCV-2893
        !    HCV-2894 Completed by                                                        Date/Time      /
R12


Header Outboard Isolation Valve
FORT CALHOUN STATION                                                                      OI-AOV-1 OPERATING INSTRUCTION                                                                PAGE 13 OF 69 C
!HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PREREQUISITES                                                                        (T) INITIALS
: 1. Procedure Revision Verification Revision No.                        Date:
PROCEDURE CAUTION Operating a valve hand jack against spring pressure may cause valve damage.
: 1. If hand jacking HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exchs AC-1A-D CCW Valves, Closed, complete the following:
: a. Ensure valve to be hand jacked is Closed:
          !  HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve
          !   HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve
          !  HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve
          !  HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve
          !  HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve
          !  HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve
: b. Align and insert J-hook into slot on the manual operator side of the valve
          !  HCV-489A
          !  HCV-490A
          !  HCV-490B
          !  HCV-491B
          !  HCV-492A
          !  HCV-492B R12


Outlet Header Outboard Isolation Valve b.Turn handwheel counter-clockwise until handwheel contacts stem nut:
FORT CALHOUN STATION                                                                 OI-AOV-1 OPERATING INSTRUCTION                                                           PAGE 14 OF 69 C
!HCV-425B!HCV-425D!HCV-467B!HCV-467D                                      c.If excessive resistence  is met before handwheel contacts stem nut,contact System Engineer.
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                             (T) INITIALS 1  c. Loosen hose clamp and remove J-hook from the air operator side of the valve:
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 19 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
        !  HCV-489A
()INITIALS R128.If removing hand jack from HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW
        !  HCV-490A
        !  HCV-490B
        !  HCV-491B
        !  HCV-492A
        !  HCV-492B
: d. Re-tighten hose clamp around slot to prevent J-hook from entering slot:
        !  HCV-489A
        !  HCV-490A
        !  HCV-490B
        !  HCV-491B
        !  HCV-492A
        !  HCV-492B
: 2. If removing hand jack from HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exch AC-1A CCW Valves, complete the following:
: a. Ensure valve has a Closed signal:
        !  HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve
        !  HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve
        !  HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve
        !  HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve
        !  HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve
        !  HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve
: b. Ensure that the valve is manually hand jacked in the Closed position:
        !  HCV-489A
        !  HCV-490A
        !  HCV-490B
        !  HCV-491B
        !  HCV-492A
        !  HCV-492B R12


Inlet/Outlet Header Outboard Isolation Valves, complete the following:a.Ensure valve has an Open signal:
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 15 OF 69 C
!HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS 2  c. Loosen hose clamp and insert J-hook into slot on air operator side of the valve:
!HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet
      !    HCV-489A
      !    HCV-490A
      !    HCV-490B
      !    HCV-491B
      !    HCV-492A
      !    HCV-492B
: d. Re-tighten the hose clamp around J-hook and the slot:
      !    HCV-489A
      !    HCV-490A
      !    HCV-490B
      !    HCV-491B
      !    HCV-492A
      !    HCV-492B
: e. Remove J-hook from the slot on the manual operator side of the valve:
      !    HCV-489A
      !    HCV-490A
      !    HCV-490B
      !    HCV-491B
      !    HCV-492A
      !    HCV-492B
: f. Stroke valve as necessary to verify proper operation and position indication:
      !   HCV-489A
      !    HCV-490A
      !    HCV-490B
      !   HCV-491B
      !    HCV-492A
      !    HCV-492B R12


Header Outboard Isolation Valve
FORT CALHOUN STATION                                                                    OI-AOV-1 OPERATING INSTRUCTION                                                              PAGE 16 OF 69 C
!HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS
: 3. If hand jacking HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:
: a. Ensure valve to be hand jacked is Closed:
        !  HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve
        !  HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve
: b. Align notch in pointer to hole in gear on manual operator and insert pin.
        !  HCV-489B
        !  HCV-491A
: c. Loosen hose clamp and remove J-hook from the air operator side of the valve.
        !  HCV-489B
        !  HCV-491A
: d. Re-tighten hose clamp around slot to prevent J-hook from entering slot.
        !  HCV-489B
        !  HCV-491A
: 4. If removing hand jack from HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:
: a. Ensure valve has a Closed signal:
        !  HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve
        !   HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve
: b. Ensure that the valve is manually hand jacked in the closed position.
        !  HCV-489B
        !  HCV-491A R12


Header Outboard Isolation Valve
FORT CALHOUN STATION                                                                    OI-AOV-1 OPERATING INSTRUCTION                                                              PAGE 17 OF 69 C
!HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS 4  c. Loosen hose clamp and insert J-hook into slot on air operator side of the valve.
        !    HCV-489B
        !    HCV-491A
: d. Re-tighten the hose clamp around J-hook and the slot.
        !    HCV-489B
        !    HCV-491A
: e. Remove pin from manual operator.
        !    HCV-489B
        !    HCV-491A
: f. Stroke the valve as necessary to verify proper operation and position indication.
        !    HCV-489B
        !    HCV-491A
: 5. If hand jacking HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
: a. Ensure HCV-497 is Open.
: b. Loosen stem nut.
: c. Turn handwheel clockwise until handwheel stem pusher plate contacts diaphragm plate.
: d. Tighten stem nut.
: 6. If removing hand jack from HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
: a. Ensure HCV-497 has an Open signal.
: b. Loosen stem nut.
R12


Outlet Header Outboard Isolation Valve b.Turn handwheel clockwise until handwheel contacts upper diaphragm casing:!HCV-425B!HCV-425D!HCV-467B!HCV-467D                                      c.Stroke valve as necessary to verify proper operation and position indication:
FORT CALHOUN STATION                                                               OI-AOV-1 OPERATING INSTRUCTION                                                         PAGE 18 OF 69 C
!HCV-425B!HCV-425D!HCV-467B!HCV-467D C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 20 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                         (T) INITIALS 6  c. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing.
()INITIALS R129.If hand jacking HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water S upply/Return Valves, Closed, complete the following:a.Ensure valve that is to be hand jacked is Closed:
: d. Tighten stem nut.
!HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve
: e. Stroke HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve as necessary to verify proper operation and position indication.
!HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet
: 7. If hand jacking HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard Isolation Valves, Open, complete the following:
: a. Ensure that the valve to be hand jacked is Open:
        !   HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve
        !    HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet Header Outboard Isolation Valve
        !    HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet Header Outboard Isolation Valve
        !   HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW Outlet Header Outboard Isolation Valve
: b. Turn handwheel counter-clockwise until handwheel contacts stem nut:
        !    HCV-425B
        !    HCV-425D
        !    HCV-467B
        !    HCV-467D
: c. If excessive resistence is met before handwheel contacts stem nut, contact System Engineer.
R12


Outboard Isolation Valve b.Loosen stem nut:
FORT CALHOUN STATION                                                              OI-AOV-1 OPERATING INSTRUCTION                                                        PAGE 19 OF 69 C
!HCV-438B!HCV-438D            c.Turn handwheel CLOCKWISE until handwheel stem pusher plate contacts diaphragm plate:
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS
!HCV-438B!HCV-438D            d.Tighten stem nut:
: 8. If removing hand jack from HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard Isolation Valves, complete the following:
!HCV-438B!HCV-438D                          10.If removing hand jack from HCV-438B/D , Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, complete the following:a.Ensure valve has a Closed signal:
: a. Ensure valve has an Open signal:
!HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve
        !   HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve
!HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet
        !    HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet Header Outboard Isolation Valve
        !    HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet Header Outboard Isolation Valve
        !   HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW Outlet Header Outboard Isolation Valve
: b. Turn handwheel clockwise until handwheel contacts upper diaphragm casing:
        !    HCV-425B
        !    HCV-425D
        !    HCV-467B
        !    HCV-467D
: c. Stroke valve as necessary to verify proper operation and position indication:
        !    HCV-425B
        !    HCV-425D
        !    HCV-467B
        !    HCV-467D R12


Outboard Isolation Valve
FORT CALHOUN STATION                                                              OI-AOV-1 OPERATING INSTRUCTION                                                      PAGE 20 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                        (T) INITIALS
: 9. If hand jacking HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, Closed, complete the following:
: a. Ensure valve that is to be hand jacked is Closed:
        !  HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve
        !  HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet Outboard Isolation Valve
: b. Loosen stem nut:
        !  HCV-438B
        !  HCV-438D
: c. Turn handwheel CLOCKWISE until handwheel stem pusher plate contacts diaphragm plate:
        !  HCV-438B
        !  HCV-438D
: d. Tighten stem nut:
        !  HCV-438B
        !  HCV-438D
: 10. If removing hand jack from HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, complete the following:
: a. Ensure valve has a Closed signal:
        !  HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve
        !  HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet Outboard Isolation Valve R12


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 21 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
FORT CALHOUN STATION                                                               OI-AOV-1 OPERATING INSTRUCTION                                                       PAGE 21 OF 69 C
()INITIALS R1210b.Loosen stem nut:
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                         (T) INITIALS 10  b. Loosen stem nut:
!HCV-438B!HCV-438D           c.Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing:
        !   HCV-438B
!HCV-438B!HCV-438D           d.Tighten stem nut:
        !   HCV-438D
!HCV-438B!HCV-438D           e.Stroke valve as necessary to verify proper operation and position indication:
: c. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing:
!HCV-438B!HCV-438D                           11.If hand jacking HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
        !   HCV-438B
DW-46B-2 Outlet/Inlet Valves, Open, complete the following:a.Ensure that the valve to be hand jacked is Open:
        !   HCV-438D
!HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
: d. Tighten stem nut:
        !   HCV-438B
        !   HCV-438D
: e. Stroke valve as necessary to verify proper operation and position indication:
        !   HCV-438B
        !   HCV-438D
: 11. If hand jacking HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Outlet/Inlet Valves, Open, complete the following:
: a. Ensure that the valve to be hand jacked is Open:
        !   HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Inlet Valve
DW-46B-2 Inlet Valve
!HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
        !   HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Outlet Valve
: b. Push in handwheel and turn CLOCKWISE until worm-gear fully engages the gear segment:
        !    HCV-2895A
        !    HCV-2895B R12


DW-46B-2 Outlet Valve b.Push in handwheel and turn CLOCKWISE until worm-gear fully engages the gear segment:
FORT CALHOUN STATION                                                                 OI-AOV-1 OPERATING INSTRUCTION                                                           PAGE 22 OF 69 C
!HCV-2895A!HCV-2895B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 22 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                           (T) INITIALS 11  c. Verify declutching pin has dropped into inner slot on handwheel:
()INITIALS R1211c.Verify declutching pin has dropped into inner slot on handwheel:
        !   HCV-2895A
!HCV-2895A!HCV-2895B                           12.IF removing Handjack from HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 & DW-46B-2 Outlet/Inlet Valves:a.Ensure valve has an OPEN signal:
        !   HCV-2895B
!HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
: 12. IF removing Handjack from HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 & DW-46B-2 Outlet/Inlet Valves:
: a. Ensure valve has an OPEN signal:
        !   HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
DW-46B-2 Inlet Valve
DW-46B-2 Inlet Valve
!HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
        !   HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &
 
DW-46B-2 Outlet Valve
DW-46B-2 Outlet Valve b.Press declutching spring to push out declutching pin:
: b. Press declutching spring to push out declutching pin:
!HCV-2895A!HCV-2895B           c.Turn Handwheel COUNTER-CLOCKWISE until worm gear disengages the gear segment:
        !   HCV-2895A
!HCV-2895A!HCV-2895B           d.Allow spring to move handwheel all the way out and release declutching pin into outer slot on handwheel shaft:
        !   HCV-2895B
!HCV-2895A!HCV-2895B                           e.Stroke valve as necessary to verify proper operation and position indication:
: c. Turn Handwheel COUNTER-CLOCKWISE until worm gear disengages the gear segment:
!HCV-2895A!HCV-2895B C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 23 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
        !   HCV-2895A
()INITIALS R1213.If locally Closing of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following on the applicable valves:a.Place the control valve to Close for:
        !   HCV-2895B
!IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve!IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual
: d. Allow spring to move handwheel all the way out and release declutching pin into outer slot on handwheel shaft:
 
        !   HCV-2895A
Control Valve
        !   HCV-2895B
!IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control
: e. Stroke valve as necessary to verify proper operation and position indication:
 
        !   HCV-2895A
Valve!IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual
        !   HCV-2895B R12
 
Control Valve
!IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control
 
Valve!IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual
 
Control Valve
!IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control
 
Valve!IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual
 
Control Valve b.Verify valve strokes fully Closed for:
!HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet
 
Valve!HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet
 
Valve!HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet
 
Valve!HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet
 
Valve!HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet
 
Valve!HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet
 
Valve!HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet
 
Valve !HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet
 
Valve C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 24 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
()INITIALS R1213c.Use rachet to replace Handjack by turning COUNTER-CLOCKWISE until it reaches the top:
!HCV-400E!HCV-400F!HCV-401E!HCV-401F!HCV-402E!HCV-402F!HCV-403E!HCV-403F                                                d.Reinstall cover and locking device:
!HCV-400E!HCV-400F!HCV-401E!HCV-401F!HCV-402E!HCV-402F!HCV-403E!HCV-403F                                                              e.Verify locking device is installed:
!HCV-400E!HCV-400F!HCV-401E!HCV-401F!HCV-402E!HCV-402F!HCV-403E!HCV-403F Ind Verif C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 25 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
()INITIALS R1213f.Remove selected valve from the Locked Component Deviation Log:
!HCV-400E!HCV-400F!HCV-401E!HCV-401F!HCV-402E!HCV-402F!HCV-403E!HCV-403F CAUTION The following steps may drain CCW from this portion of the system.14.If locally Opening of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following for the applicable valves:
a.Ensure CCW isolation valves for selected unit(s) are closed:
!HCV-400B, Cntmt Clg Coil VA-1A AC Inlet Valve Valve
!HCV-400D, Cntmt Clg Coil VA-1A AC Outlet Valve
!HCV-401B, Cntmt Clg Coil VA-1B AC Inlet Valve Valve
!HCV-401D, Cntmt Clg Coil VA-1B AC Outlet Valve
!HCV-402B, Cntmt Clg Coil VA-8A AC Inlet Valve Valve
!HCV-402D, Cntmt Clg Coil VA-8A AC Outlet Valve
!HCV-403B, Cntmt Clg Coil VA-8BAC Inlet Valve Valve
!HCV-403D, Cntmt Clg Coil VA-8B AC Outlet Valve
 
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 26 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
()INITIALS R1214b.Remove the locking mechanism and cover from the valve and place valve information in the Locked Component Deviation Log for the selected valve:
!HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet
 
Valve!HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet
 
Valve!HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet
 
Valve!HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet
 
Valve!HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet
 
Valve!HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet
 
Valve!HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet
 
Valve !HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet
 
Valve                                                c.Use the ratchet to release handjack by turning the locking nut CLOCKWISE until it reaches the bottom:
!HCV-400E!HCV-400F!HCV-401E!HCV-401F!HCV-402E!HCV-402F!HCV-403E!HCV-403F C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 27 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
()INITIALS R1214d.Place the Control Valve to Open:
!IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve!IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual


Control Valve  
FORT CALHOUN STATION                                                              OI-AOV-1 OPERATING INSTRUCTION                                                        PAGE 23 OF 69 C
!IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS
: 13. If locally Closing of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following on the applicable valves:
: a. Place the control valve to Close for:
          !    IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve
          !    IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual Control Valve
          !   IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control Valve
          !    IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual Control Valve
          !    IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control Valve
          !    IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual Control Valve
          !    IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control Valve
          !    IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual Control Valve
: b. Verify valve strokes fully Closed for:
          !    HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet Valve
          !    HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet Valve
          !    HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet Valve
          !    HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet Valve
          !    HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet Valve
          !    HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet Valve
          !    HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet Valve
          !    HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet Valve R12


Valve!IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual
FORT CALHOUN STATION                                                            OI-AOV-1 OPERATING INSTRUCTION                                                    PAGE 24 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                      (T) INITIALS 13  c. Use rachet to replace Handjack by turning COUNTER-CLOCKWISE until it reaches the top:
      !    HCV-400E
      !    HCV-400F
      !    HCV-401E
      !    HCV-401F
      !    HCV-402E
      !    HCV-402F
      !    HCV-403E
      !    HCV-403F
: d. Reinstall cover and locking device:
      !    HCV-400E
      !    HCV-400F
      !   HCV-401E
      !    HCV-401F
      !    HCV-402E
      !    HCV-402F
      !    HCV-403E
      !    HCV-403F
: e. Verify locking device is installed:
      !    HCV-400E
      !    HCV-400F
      !    HCV-401E
      !    HCV-401F
      !    HCV-402E
      !    HCV-402F
      !    HCV-403E
      !    HCV-403F Ind Verif R12


Control Valve
FORT CALHOUN STATION                                                              OI-AOV-1 OPERATING INSTRUCTION                                                        PAGE 25 OF 69 C
!IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS 13  f. Remove selected valve from the Locked Component Deviation Log:
          !    HCV-400E
          !    HCV-400F
          !    HCV-401E
          !    HCV-401F
          !    HCV-402E
          !    HCV-402F
          !    HCV-403E
          !    HCV-403F CAUTION The following steps may drain CCW from this portion of the system.
: 14. If locally Opening of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following for the applicable valves:
: a. Ensure CCW isolation valves for selected unit(s) are closed:
          !    HCV-400B, Cntmt Clg Coil VA-1A AC Inlet Valve Valve
          !    HCV-400D, Cntmt Clg Coil VA-1A AC Outlet Valve
          !    HCV-401B, Cntmt Clg Coil VA-1B AC Inlet Valve Valve
          !    HCV-401D, Cntmt Clg Coil VA-1B AC Outlet Valve
          !   HCV-402B, Cntmt Clg Coil VA-8A AC Inlet Valve Valve
          !    HCV-402D, Cntmt Clg Coil VA-8A AC Outlet Valve
          !    HCV-403B, Cntmt Clg Coil VA-8BAC Inlet Valve Valve
          !    HCV-403D, Cntmt Clg Coil VA-8B AC Outlet Valve R12


Valve!IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual
FORT CALHOUN STATION                                                            OI-AOV-1 OPERATING INSTRUCTION                                                    PAGE 26 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                      (T) INITIALS 14  b. Remove the locking mechanism and cover from the valve and place valve information in the Locked Component Deviation Log for the selected valve:
      !  HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet Valve
      !  HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet Valve
      !  HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet Valve
      !   HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet Valve
      !  HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet Valve
      !  HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet Valve
      !  HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet Valve
      !  HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet Valve
: c. Use the ratchet to release handjack by turning the locking nut CLOCKWISE until it reaches the bottom:
      !  HCV-400E
      !  HCV-400F
      !  HCV-401E
      !  HCV-401F
      !  HCV-402E
      !  HCV-402F
      !  HCV-403E
      !  HCV-403F R12


Control Valve
FORT CALHOUN STATION                                                            OI-AOV-1 OPERATING INSTRUCTION                                                    PAGE 27 OF 69 C
!IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                      (T) INITIALS 14  d. Place the Control Valve to Open:
      !  IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve
      !  IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual Control Valve
      !  IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control Valve
      !  IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual Control Valve
      !  IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control Valve
      !   IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual Control Valve
      !  IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control Valve
      !  IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual Control Valve
: e. Verify the valve strokes Open:
      !  HCV-400E
      !  HCV-400F
      !  HCV-401E
      !  HCV-401F
      !  HCV-402E
      !  HCV-402F
      !  HCV-403E
      !  HCV-403F R12


Valve!IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 28 OF 69 C
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS
: 15. If handjacking HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valves, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, perform the following:
: a. Ensure isolation valves are closed for selected valve by taking the air control valve to Close:
        !    IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
        !    IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve
        !    IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve
        !   IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way Manual Control Valve
: b. Loosen required stem nut on selected valves:
        !    HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve
        !    HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet Valve
        !    HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve
        !    HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet Valve
: c. Unlock and turn hand wheel CLOCKWISE until the handwheel stem pusher plate contacts the diaphragm on selected valves:
        !    HCV-2898C
        !    HCV-2898D
        !    HCV-2899C
        !    HCV-2899D
: d. Tighten stem nut on handjacked valve:
        !    HCV-2898C
        !    HCV-2898D
        !    HCV-2899C
        !    HCV-2899D R12


Control Valve e.Verify the valve strokes Open:
FORT CALHOUN STATION                                                              OI-AOV-1 OPERATING INSTRUCTION                                                        PAGE 29 OF 69 C
!HCV-400E!HCV-400F!HCV-401E!HCV-401F!HCV-402E!HCV-402F!HCV-403E!HCV-403F C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 28 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS 15  e. Place locking Device on hand wheel for selected valve:
()INITIALS R1215.If handjacking HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valves, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, perform the following:a.Ensure isolation valves are closed for selected valve by taking the air control valve to Close:
        !   HCV-2898C
!IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
        !   HCV-2898D
!IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way
        !   HCV-2899C
        !   HCV-2899D
: f. Independently verify valve is Locked Closed:
        !    HCV-2898C
        !   HCV-2898D
        !   HCV-2899C
        !   HCV-2899D Ind Verif
: g. Remove selected valve from the Locked Component Deviation Log:
        !   HCV-2898C
        !    HCV-2898D
        !    HCV-2899C
        !    HCV-2899D
: 16. If handjacking HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:
NOTE HCV-2898A/B and HCV-2899A/B can only be hand jacked in the open position.
: a. Ensure the valve to be handjacked is open:
        !   HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
        !    HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
        !   HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
        !    HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12


Manual Control Valve
FORT CALHOUN STATION                                                              OI-AOV-1 OPERATING INSTRUCTION                                                        PAGE 30 OF 69 C
!IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS 16  b. Loosen stem nut for selected valves:
        !    HCV-2898A
        !    HCV-2898B
        !    HCV-2899A
        !    HCV-2899B
: c. Turn hand wheel COUNTER-CLOCKWISE until the handwheel is fully backseated for selected valves:
        !    HCV-2898A
        !    HCV-2898B
        !    HCV-2899A
        !    HCV-2899B
: d. Tighten stem nut for selected valves:
        !    HCV-2898A
        !    HCV-2898B
        !    HCV-2899A
        !    HCV-2899B
: 17. If removing handjack from HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:
NOTE Can verify the handjack removed for HCV-2898A/B and HCV-2899A/B by verifying the hand wheel in the full CLOCKWISE position.
: a. Ensure the selected valve has an open signal:
        !    HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
        !   HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
        !    HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
        !    HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12


Manual Control Valve
FORT CALHOUN STATION                                                                OI-AOV-1 OPERATING INSTRUCTION                                                        PAGE 31 OF 69 C
!IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS 17  b. Loosen stem nut on selected valves:
          !    HCV-2898A
          !    HCV-2898B
          !    HCV-2899A
          !    HCV-2899B
: c. Turn hand wheel CLOCKWISE until the handwheel contacts the top of the diaphram casing for selected valves:
          !    HCV-2898A
          !    HCV-2898B
          !    HCV-2899A
          !    HCV-2899B
: d. Tighten stem nut on selected valves:
          !    HCV-2898A
          !    HCV-2898B
          !    HCV-2899A
          !   HCV-2899B CAUTION The following steps may drain CCW from this portion of the system.
: 18. If removing Handjack from HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valve, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, complete the following:
: a. Ensure CCW isolation valves for the selected unit are Closed:
          !    HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
          !    HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
          !    HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
          !    HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12


Manual Control Valve b.Loosen required stem nut on selected valves:
FORT CALHOUN STATION                                                            OI-AOV-1 OPERATING INSTRUCTION                                                    PAGE 32 OF 69 C
!HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                      (T) INITIALS 18  b. Ensure the hand jacked valves have a Closed signal:
!HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet
      !  IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
      !  IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve
      !  IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve
      !  IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way Manual Control Valve
: c. Loosen Stem nut on selected Hand jacked valves:
      !   HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve
      !   HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet Valve
      !  HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve
      !  HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet Valve
: d. Unlock handwheel and place valve information in the Locked Component Deviation Log for the selected valve:
      !  HCV-2898C
      !  HCV-2898D
      !  HCV-2899C
      !  HCV-2899D
: e. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts the upper diaphragm casing for selected valves:
      !  HCV-2898C
      !  HCV-2898D
      !  HCV-2899C
      !  HCV-2899D R12


Valve!HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 33 OF 69 C
!HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet
Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS 18  f. Tighten stem nut on selected valves:
        !    HCV-2898C
        !    HCV-2898D
        !    HCV-2899C
        !    HCV-2899D
: g. Open selected valve by turning air valve to the Open position:
        !    IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
        !   IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve
        !    IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve
        !   IA-HCV-2899D-TV, Raw Water Inlet Valve HCV-2899D 3-Way Manual Control Valve Completed by                                                          Date/Time      /
R12


Valve                        c.Unlock and turn hand wheel CLOCKWISE until the handwheel stem pusher plate contacts the diaphragm on selected valves:
FORT CALHOUN STATION                                                                 OI-AOV-1 OPERATING INSTRUCTION                                                           PAGE 34 OF 69 C
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D                        d.Tighten stem nut on handjacked valve:
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PREREQUISITES                                                                    (T) INITIALS
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 29 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
: 1. Procedure Revision Verification Revision No.           Date:
()INITIALS R1215e.Place locking Device on hand wheel for selected valve:
PROCEDURE
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D                        f.Independently verify valve is Locked Closed:
: 1. If Handjacking LCV-383-1, or LCV-383-2, perform the following:
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D Ind Verifg.Remove selected valve from the Locked Component Deviation Log:
: a. Ensure valve to be Handjacked is Closed:
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D                                      16.If handjacking HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:
        !   LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve
NOTE HCV-2898A/B and HCV-2899A/B can only be hand jacked in the open
        !   LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve
: b. Loosen stem nut on valve to be handjacked:
        !   LCV-383-1
        !   LCV-383-2
: c. Turn Handwheel CLOCKWISE, counting the number of turns, until the handwheel stem pusher plate contacts the diaphragm plate on the valve to be Handjacked:
        !   LCV-383-1
        !   LCV-383-2
: d. Record number of turns for Handjacked valve:
        !  LCV-383-1, Turns__________
        !  LCV-383-2, Turns__________
: e. Tighten stem nut on hand jacked valve:
        !  LCV-383-1
        !  LCV-383-2 R12


position.a.Ensure the valve to be handjacked is open:
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 35 OF 69 C
!HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS
!HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
: 2. If removing handjack from LCV-383-1, or LCV-383-2, perform the following:
!HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
: a. Ensure that the Handjacked valve has a Closed signal:
!HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve
        !  LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve
        !  LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve
: b. Loosen stem nut on Handjacked valve:
        !  LCV-383-1
        !  LCV-383-2
: c. Turn Handwheel on Handjacked valve COUNTER-CLOCKWISE the number of turns recorded in step 1.d:
        !  LCV-383-1
        !  LCV-383-2
: d. Tighten the stem nut for handjacked valve:
        !  LCV-383-1
        !  LCV-383-2
: e. Stroke valve as necessary to verify proper operation and position indication.
        !  LCV-383-1
        !  LCV-383-2
: 3. If handjacking HCV-753, HCV-754, HCV-749, or HCV-750, perform the following:
: a. Enure the valve to be handjacked is Closed:
        !   HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve
        !   HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve
        !   HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve
        !   HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve R12


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 30 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
FORT CALHOUN STATION                                                                   OI-AOV-1 OPERATING INSTRUCTION                                                             PAGE 36 OF 69 C
()INITIALS R1216b.Loosen stem nut for selected valves:
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                             (T) INITIALS 3  b. Align the holes on the manual operator end of stem on valve to be handjacked.
!HCV-2898A!HCV-2898B!HCV-2899A!HCV-2899B                        c.Turn hand wheel COUNTER-CLOCKWISE until the handwheel is fully backseated for selected valves:
        !   HCV-753
!HCV-2898A!HCV-2898B!HCV-2899A!HCV-2899B                        d.Tighten stem nut for selected valves:
        !   HCV-754
!HCV-2898A!HCV-2898B!HCV-2899A!HCV-2899B                                      17.If removing handjack from HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:
        !   HCV-749
NOTE Can verify the handjack removed for HCV-2898A/B and HCV-2899A/B
        !   HCV-750
: c. Insert Pin into hole on valve to be handjacked:
        !   HCV-753
        !   HCV-754
        !   HCV-749
        !   HCV-750
: d. Remove Pin from the air actuator assembly end on valve to be handjacked:
        !   HCV-753
        !   HCV-754
        !   HCV-749
        !   HCV-750
: 4. If removing the handjack from HCV-753, HCV-754, HCV-749, HCV-750, perform the following:
: a. Ensure that the Handjacked valve has a Closed signal:
        !  HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve
        !  HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve
        !  HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve
        !  HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve
: b. Insert the Pin on the Air actuator assembly end for handjacked valve
        !  HCV-753
        !  HCV-754
        !  HCV-749
        !  HCV-750 R12


by verifying the hand wheel in the full CLOCKWISE position. a.Ensure the selected valve has an open signal:
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 37 OF 69 C
!HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS 4  c. Remove the Pin from the manual operator end of stem for handjacked valve:
!HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
        !  HCV-753
!HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
        !  HCV-754
!HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve
        !  HCV-749
        !  HCV-750
: d. Stroke valve as necessary to verify proper operation and position indication for handjacked valve
        !  HCV-753
        !  HCV-754
        !  HCV-749
        !  HCV-750
: 5. If handjacking HCV-341, HCV-344 or HCV-345, perform the following:
: a. Ensure that the valve to be handjacked is Closed:
        !   HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve
        !  HCV-344, Containment Spray Header Isolation Valve
        !   HCV-345, Containment Spray Header Isolation Valve
: b. Using handwheel, align hole in manual operator for valve to be handjacked:
        !  HCV-341
        !  HCV-344
        !   HCV-345
: c. Insert pin into hole in manual operator for valve to be handjacked:
        !  HCV-341
        !   HCV-344
        !  HCV-345 R12


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 31 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
FORT CALHOUN STATION                                                                   OI-AOV-1 OPERATING INSTRUCTION                                                             PAGE 38 OF 69 C
()INITIALS R1217b.Loosen stem nut on selected valves:
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                             (T) INITIALS
!HCV-2898A!HCV-2898B!HCV-2899A!HCV-2899B                        c.Turn hand wheel CLOCKWISE until the handwheel contacts the top of the diaphram casing for selected valves:
: 6. If removing handjack from HCV-341, HCV-344, or HCV-345, perform the following:
!HCV-2898A!HCV-2898B!HCV-2899A!HCV-2899B                        d.Tighten stem nut on selected valves:
: a. Ensure valve that is Handjacked has a Closed signal:
!HCV-2898A!HCV-2898B!HCV-2899A!HCV-2899B CAUTION The following steps may drain CCW from this portion of the system.18.If removing Handjack from HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valve, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, complete the following:a.Ensure CCW isolation valves for the selected unit are Closed:
        !   HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve
!HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve
        !   HCV-344, Containment Spray Header Isolation Valve
!HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve
        !   HCV-345, Containment Spray Header Isolation Valve
!HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve
: b. Remove Pin from Manual operator for handjacked valve:
!HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve
        !   HCV-341
        !   HCV-344
        !   HCV-345
: c. Ensure handwheel in its neutral position for valve that was handjacked:
        !   HCV-341
        !  HCV-344
        !  HCV-345
: d. Stroke valve as necessary to verify proper operation and position indication for handjacked valve:
        !   HCV-341
        !   HCV-344
        !   HCV-345 R12


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 32 OF 69 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
FORT CALHOUN STATION                                                                 OI-AOV-1 OPERATING INSTRUCTION                                                           PAGE 39 OF 69 C
()INITIALS R1218b.Ensure the hand jacked valves have a Closed signal:
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                             (T) INITIALS
!IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
: 7. If handjacking HCV-482 A/B, OR HCV-483 A/B Shutdown Cooling Heat Exchanger Back Up Raw Water Valves, perform the following:
!IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way
: a. Enure the valve to be hand jacked is Closed:
        !  HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve
        !  HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Outlet Valve
        !  HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Inlet Valve
        !  HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Outlet Valve
: b. Ensure Instrument Air supply Insolation Valve is Open for selected valve:
        !  IA-HCV-482A-B, HCV-482A Instrument Air Supply Isolation Valve
        !  IA-HCV-482B-B, HCV-482B Instrument Air Supply Isolation Valve
        !  IA-HCV-483A-B, HCV-483A Instrument Air Supply Isolation Valve
        !  IA-HCV-483B-B, HCV-483B Instrument Air Supply Isolation Valve
: c. Place Raw Water Manual control valve in the Closed position for the selected valve:
        !   IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve
        !  IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual Control Valve
        !  IA-HCV-483A-TV, Raw Water Inlet Valve HCV-843A Manual Control Valve
        !   IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual Control Valve R12


Manual Control Valve
FORT CALHOUN STATION                                                                    OI-AOV-1 OPERATING INSTRUCTION                                                              PAGE 40 OF 69 C
!IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS
: 7. d. Loosen the Hand Jack Stem Nut, and back it up to the bottom of the hand wheel for the selected valve:
        !   HCV-482A
        !    HCV-482B
        !    HCV-483A
        !    HCV-483B CAUTION Do Not Force the hand wheel if excessive resistance is met before the handjack stem nut contacts the bonnet of the actuator housing. It is possible that the valve disk is being forced into the valve seat.
: e. Turn the hand wheel CLOCKWISE until the handjack stem nut contacts the bonnet of the actuator housing for the selected valve:
        !    HCV-482A
        !    HCV-482B
        !    HCV-483A
        !    HCV-483B
: f. If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer for the selected valve:
        !    HCV-482A
        !    HCV-482B
        !    HCV-483A
        !    HCV-483B
: g. Lock hand wheel for the selected valve:
        !    HCV-482A
        !    HCV-482B
        !    HCV-483A
        !    HCV-483B Ind Verif R12


Manual Control Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 41 OF 69 C
!IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS
: 7. h. Remove selected valve from the Locked Component Deviation Log:
          !  HCV-482A
          !  HCV-482B
          !  HCV-483A
          !  HCV-483B CAUTION The following steps may drain CCW from this portion of the system.
: 8. If removing the handjack from HCV-482A, HCV-482B, HCV-483A, HCV-483B, perform the following:
: a. Ensure CCW isolation valves for selected heat exchanger(s) are closed:
          !  HCV-480, Shtdn Ht Exch AC-4A AC Inlet Valve
          ! HCV-484, Shtdn Ht Exch AC-4A AC Outlet Valve
          !  HCV-481, Shtdn Ht Exch AC-4B AC Inlet Valve
          !  HCV-485, Shtdn Ht Exch AC-4B AC Outlet Valve
: b. Ensure that the Handjacked valve has a Closed signal:
          !  HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve
          !  HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Outlet Valve
          !  HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Inlet Valve
          !  HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Outlet Valve
: c. Ensure Instrument Air Isolation valve is Open for selected valve:
          !  IA-HCV-482A-B, Instrument Air Supply Isolation Valve
          !  IA-HCV-482B-B, Instrument Air Supply Isolation Valve
          !  IA-HCV-483A-B, Instrument Air Supply Isolation Valve
          !  IA-HCV-483B-B, Instrument Air Supply Isolation Valve R12


Manual Control Valve c.Loosen Stem nut on selected Hand jacked valves:
FORT CALHOUN STATION                                                                OI-AOV-1 OPERATING INSTRUCTION                                                          PAGE 42 OF 69 C
!HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS
!HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet
: 8. d. Unlock and turn Hand wheel COUNTER-CLOCKWISE until valve stem travel stops for selected valve:
      !  HCV-482A
      !  HCV-482B
      !  HCV-483A
      !  HCV-483B
: e. Contact the Control Room and have selected valve entered into the Locked Component Deviation Log:
      !  HCV-482A
      !  HCV-482B
      !  HCV-483A
      !  HCV-483B
: f. Run the hand jack stem nut down until it contacts the Bonnet of the actuator housing for the selected valve:
      !  HCV-482A
      !  HCV-482B
      !  HCV-483A
      !  HCV-483B
: g. Place the raw water manual control valve for the selected valve in the OPEN position for the selected valve:
      !   IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve
      !  IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual Control Valve
      !   IA-HCV-483A-TV, Raw Water Inlet Valve HCV-483A Manual Control Valve
      !  IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual Control Valve R12


Valve!HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 43 OF 69 C
!HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS
: 8. h. Ensure selected valve is in the Open position:
        !  HCV-482A
        !  HCV-482B
        !  HCV-483A
        !  HCV-483B
: 9. If handjacking HCV-2908, HCV-2918, or HCV-2928 HPSI Pump Discharge Valves, perform the following:
: a. Ensure the valve to be Handjacked is Closed:
        !  HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve
        !   HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve
        !   HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve
: b. Remove the Handjack Locking pin from the Valve stem for the selected valve:
        !  HCV-2928
        !  HCV-2908
        !  HCV-2918
: c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
        !  HCV-2928
        !  HCV-2908
        !  HCV-2918
: d. Attach the Hand wheel locking pin to the hand wheel for the selected valve:
        !  HCV-2928
        !  HCV-2908
        !  HCV-2918 R12


Valve                        d.Unlock handwheel and place valve information in the Locked Component Deviation Log for the selected valve:
FORT CALHOUN STATION                                                                    OI-AOV-1 OPERATING INSTRUCTION                                                              PAGE 44 OF 69 C
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D                        e.Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts the upper diaphragm casing for selected valves:
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 33 OF 69  - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued)
: 10. If removing the handjack from HCV-2908, HCV-2918, or HCV-2928, perform the following:
()INITIALS R1218f.Tighten stem nut on selected valves:
: a. Ensure that the Handjacked valve has a Closed signal:
!HCV-2898C!HCV-2898D!HCV-2899C!HCV-2899D                        g.Open selected valve by turning air valve to the Open position:
        !   HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve
!IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve
        !   HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve
!IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way
        !   HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve
: b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
        !   HCV-2928
        !   HCV-2908
        !   HCV-2918
: c. Insert the Handjack locking pin in the valve stem for the selected valve:
        !   HCV-2928
        !   HCV-2908
        !   HCV-2918
: d. Contact the Control Room that the hand jack has been removed for the selected valve:
        !   HCV-2928
        !  HCV-2908
        !   HCV-2918 R12


Manual Control Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 45 OF 69 C
!IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS
: 11. If handjacking HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves:
: a. Ensure valve to be Handjacked is Closed:
        !  HCV-2907, HPSI Pump SI-2B Suction Isolation Valve
        !  HCV-2917, HPSI Pump SI-2C Suction Isolation Valve
        !  HCV-2927, HPSI Pump SI-2A Suction Isolation Valve
        !  HCV-2938, LPSI Pump SI-1B Discharge Valve
        !  HCV-2948, LPSI Pump SI-1A Discharge Valve
        !  HCV-2957, Containment Spray Pump SI-3A Suction Valve
        !  HCV-2958, Containment Spray Pump SI-3A Discharge Valve
        !  HCV-2967, Containment Spray Pump SI-3B Suction Valve
        !   HCV-2968, Containment Spray Pump SI-3B Discharge Valve
        !  HCV-2977, Containment Spray Pump SI-3C Suction Valve
        !  HCV-2978, Containment Spray Pump SI-3C Discharge Valve
: b. Remove the Handjack Locking pin from the Valve stem for the selected valve:
        !  HCV-2907
        !  HCV-2917
        !  HCV-2927
        !  HCV-2938
        !  HCV-2948
        !  HCV-2957
        !  HCV-2958
        !  HCV-2967
        !  HCV-2968
        !  HCV-2977
        !  HCV-2978 R12


Manual Control Valve
FORT CALHOUN STATION                                                                OI-AOV-1 OPERATING INSTRUCTION                                                          PAGE 46 OF 69 C
!IA-HCV-2899D-TV, Raw Water Inlet Valve HCV-2899D 3-Way
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                          (T) INITIALS
: 11. c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
      !  HCV-2907
      !  HCV-2917
      !  HCV-2927
      !  HCV-2938
      !  HCV-2948
      !  HCV-2957
      !  HCV-2958
      !   HCV-2967
      !  HCV-2968
      !  HCV-2977
      !  HCV-2978
: d. Attach the Hand wheel locking pin to the hand wheel for the selected valve:
      !  HCV-2907
      !  HCV-2917
      !  HCV-2927
      !  HCV-2938
      !  HCV-2948
      !  HCV-2957
      !  HCV-2958
      !  HCV-2967
      !  HCV-2968
      !  HCV-2977
      !  HCV-2978 R12


Manual Control Valve
FORT CALHOUN STATION                                                                  OI-AOV-1 OPERATING INSTRUCTION                                                            PAGE 47 OF 69 C
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                            (T) INITIALS
: 12. If Removing the Handjack from HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves.
: a. Ensure the valve to be Handjacked has a Closed signal.
        !  HCV-2907, HPSI Pump SI-2B Suction Isolation Valve
        !  HCV-2917, HPSI Pump SI-2C Suction Isolation Valve
        !  HCV-2927, HPSI Pump SI-2A Suction Isolation Valve
        !  HCV-2938, LPSI Pump SI-1B Discharge Valve
        !  HCV-2948, LPSI Pump SI-1A Discharge Valve
        !  HCV-2957, Containment Spray Pump SI-3A Suction Valve
        !  HCV-2958, Containment Spray Pump SI-3A Discharge Valve
        !  HCV-2967, Containment Spray Pump SI-3B Suction Valve
        !  HCV-2968, Containment Spray Pump SI-3B Discharge Valve
        !  HCV-2977, Containment Spray Pump SI-3C Suction Valve
        !  HCV-2978, Containment Spray Pump SI-3C Discharge Valve
: b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
        !  HCV-2907
        !  HCV-2917
        !  HCV-2927
        !  HCV-2938
        !  HCV-2948
        !  HCV-2957
        !  HCV-2958
        !  HCV-2967
        !  HCV-2968
        !  HCV-2977
        !  HCV-2978 R12


Completed by Date/Time            /
FORT CALHOUN STATION                                                                   OI-AOV-1 OPERATING INSTRUCTION                                                             PAGE 48 OF 69 C
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 34 OF 69 R12 Attachment 3 - Operation of Safe ty Injection Air Operated Valves PREREQUISITES1.Procedure Revision Verification Revision No.
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                              (T) INITIALS
Date:
: 12. c. Insert the Handjack locking pin in the valve stem for the selected valve:
()INITIALS PROCEDURE1.If Handjacking LCV-383-1, or LCV-383-2, perform the following:a.Ensure valve to be Handjacked is Closed:
        !   HCV-2907
!LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve
        !  HCV-2917
!LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve b.Loosen stem nut on valve to be handjacked:
        !   HCV-2927
!LCV-383-1!LCV-383-2            c.Turn Handwheel CLOCKWISE, counti ng the number of turns, until the handwheel stem pusher plate contacts the diaphragm plate on the valve to be Handjacked:
        !   HCV-2938
!LCV-383-1!LCV-383-2            d.Record number of turns for Handjacked valve:
        !   HCV-2948
!LCV-383-1, Turns__________
        !   HCV-2957
!LCV-383-2, Turns__________
        !   HCV-2958
e.Tighten stem nut on hand jacked valve:
        !   HCV-2967
!LCV-383-1!LCV-383-2 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 35 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
        !   HCV-2968
()INITIALS R122.If removing handjack from LCV-383-1, or LCV-383-2, perform the following:a.Ensure that the Handjacked valve has a Closed signal:
        !   HCV-2977
!LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve
        !   HCV-2978
!LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve b.Loosen stem nut on Handjacked valve:
: d. Contact the Control Room that the hand jack has been removed for the selected valve:
!LCV-383-1!LCV-383-2            c.Turn Handwheel on Handjacked valve COUNTER-CLOCKWISE the number of turns recorded in step 1.d:
        !   HCV-2907
!LCV-383-1!LCV-383-2            d.Tighten the stem nut for handjacked valve:
        !  HCV-2917
!LCV-383-1!LCV-383-2            e.Stroke valve as necessary to verify proper operation and position indication.
        !   HCV-2927
!LCV-383-1!LCV-383-2                          3.If handjacking HCV-753, HCV-754, HCV
        !   HCV-2938
-749, or HCV-750, perform the following:a.Enure the valve to be handjacked is Closed:
        !   HCV-2948
!HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve
        !   HCV-2957
!HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve
        !   HCV-2958
!HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve
        !   HCV-2967
!HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve
        !   HCV-2968
        !   HCV-2977
        !   HCV-2978
: 13. If Handjacking HCV-2937, or HCV-2947, complete the following for the selected valve:
: a. Ensure the selected valve is Closed:
        !   HCV-2937, LPSI Pump SI-1B Suction Valve
        !   HCV-2947, LPSI Pump SI-1A Suction Valve R12


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 36 OF 69 - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
FORT CALHOUN STATION                                                                   OI-AOV-1 OPERATING INSTRUCTION                                                             PAGE 49 OF 69 C
()INITIALS R123b.Align the holes on the manual oper ator end of stem on valve to be handjacked.
Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued)                                                               (T) INITIALS
!HCV-753!HCV-754!HCV-749!HCV-750                        c.Insert Pin into hole on valve to be handjacked:
: 13. b. Remove the Handjack Locking pin from the Valve stem for the selected valve:
!HCV-753!HCV-754!HCV-749!HCV-750                        d.Remove Pin from the air actuator assembly end on valve to be handjacked:
        !   HCV-2937
!HCV-753!HCV-754!HCV-749!HCV-750                                      4.If removing the handjack from HCV
        !   HCV-2947
-753, HCV-754, HCV-749, HCV-750, perform the following:a.Ensure that the Handjacked valve has a Closed signal:
: c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
!HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve
        !   HCV-2937
!HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve
        !   HCV-2947
!HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve
: 14. If REMOVING Handjack from HCV-2937, or HCV-2947, perform the following:
!HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve b.Insert the Pin on the Air actuator assembly end for handjacked valve
: a. Ensure the selected valve has a CLOSED signal:
!HCV-753!HCV-754!HCV-749!HCV-750 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 37 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
        !   HCV-2937, LPSI Pump SI-1B Suction Valve
()INITIALS R124c.Remove the Pin from the manual operator end of stem for handjacked valve:!HCV-753!HCV-754!HCV-749!HCV-750                        d.Stroke valve as necessary to verify proper operation and position indication for handjacked valve
        !   HCV-2947, LPSI Pump SI-1A Suction Valve
!HCV-753!HCV-754!HCV-749!HCV-750                                      5.If handjacking HCV-341, HCV-344 or HCV-345, perform the following:a.Ensure that the valve to be handjacked is Closed:
: b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
!HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve
        !   HCV-2937
!HCV-344, Containment Spray Header Isolation Valve
        !   HCV-2947
!HCV-345, Containment Spray Header Isolation Valve b.Using handwheel, align hole in manual operator for valve to be handjacked:
: c. Insert the handjack locking pin in the valve stem for the selected valve:
!HCV-341!HCV-344!HCV-345                  c.Insert pin into hole in manual operator for valve to be handjacked:
        !   HCV-2937
!HCV-341!HCV-344!HCV-345 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 38 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
        !   HCV-2947
()INITIALS R126.If removing handjack from HCV-341, HCV-344, or HCV-345, perform the following:a.Ensure valve that is Handjacked has a Closed signal:
: d. Contact the Control Room that the hand jack has been removed for the selected valve.
!HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve
Completed by                                                            Date/Time      /
!HCV-344, Containment Spray Header Isolation Valve
R12
!HCV-345, Containment Spray Header Isolation Valve b.Remove Pin from Manual operator for handjacked valve:
!HCV-341!HCV-344!HCV-345                  c.Ensure handwheel in its neutral position for valve that was handjacked:
!HCV-341!HCV-344!HCV-345                  d.Stroke valve as necessary to verify proper operation and position indication for handjacked valve:
!HCV-341!HCV-344!HCV-345 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 39 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R127.If handjacking HCV-482 A/B, OR HCV
-483 A/B Shutdown Cooling Heat Exchanger Back Up Raw Water Valves, perform the following:a.Enure the valve to be hand jacked is Closed:
!HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve
!HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water


Outlet Valve
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM Title: Energize 480 volt buses from 13.8 KV Location:            Switchgear Rooms Approximate Time:    20 minutes            Actual Time: _________________
!HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water
Reference(s):    K/A 000055 EA1.07 EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV" Handout(s):      EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV" Time Critical: NO Alternate Path: NO JPM Prepared by:      Jerry Koske                                  Date: 3/25/09


Inlet Valve
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 Operators Name: _____________________ Employee # ______________
!HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:        Be careful not to bump equipment in switchgear rooms Comments:


Outlet Valve b.Ensure Instrument Air supply Insolation Valve is Open for selected valve: !IA-HCV-482A-B, HCV-482A Instrum ent Air Supply Isolation Valve
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 TASK              The candidate energized 480V buses 1B3C and 1B3C-STANDARD:        4C from the 13.8 KV supply in accordance with EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV."
!IA-HCV-482B-B, HCV-482B Instrum ent Air Supply Isolation Valve
INITIAL                A station blackout has occurred.
!IA-HCV-483A-B, HCV-483A Instrum ent Air Supply Isolation Valve
CONDITIONS:            Both 161 KV and 345 KV supplies to the station have been lost.
!IA-HCV-483B-B, HCV-483B Instrum ent Air Supply Isolation Valve c.Place Raw Water Manual control valve in the Closed position for the selected valve:
Both Diesel Generators have failed to start.
!IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control
Energy Marketing reports that 13.8 KV power is available to the plant.
INITIATING CUE:   You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP Attachment
: 5. The Control Room Operators have completed steps 1 and 2.


Valve!IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Trip ALL of the following 480 V      East Switchgear room breakers :                            Trip breakers.
1B3C, "T1B-3C MAIN              Verify breaker position SECONDARY FEED TO              indicators display "OPEN."
480 VAC BUS 1B3C."
1B3C-2, "MCC-3C2 AUX BUILDING (CORR.
26)."
1B3C-7, "TURBINE BUILDING CRANE HE-3."
1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A."
1B3C-3, "OUTDOOR LIGHTING XFMR T1C-3B."
1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)."
1B3C-8, "AIR COMPRESSORCA-1A FEED TO LOCAL CONTACTOR."                    [ SAT ]      [ UNSAT ]
2              Trip ALL of the following 480 V breakers:                            East Switchgear room 1B3C-4C-2, "BREAKER            Trip breakers.
UNIT MCC-3C4C-2                Verify breaker position TURBINE BLDG                    indicators display "OPEN."
(MEZZANINE)."
1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C."              [ SAT ]      [ UNSAT ]
1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C."


Control Valve
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP                    ELEMENT                              STANDARD 3              Trip listed 1B4C 480 V                  West Switchgear room Breakers.
!IA-HCV-483A-TV, Raw Water Inlet Valve HCV-843A Manual Control
CUE: After candidate identifies location of bus 1B4C, "Another Operator will trip the breakers."
[ SAT ]      [ UNSAT ]
4              Place ALL of the following              East Upper Electrical breakers in "OFF"                      Penetration Room MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF                MCC breakers placed in OFF VALVE."                        position.
MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF STRESS TEST DISC SWITCH."
MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER."
MCC-3C1-A3R, HE                        DS/STRESS GALL-DS, ROOM 66 HOIST &
STRESS GALLERY TEST DISC SWITCHES.
MCC-3C1-A4L, "SPARE.
MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER."
MCC-3C1-A05, "TRANSFORMER T1B-               [ SAT ]      [ UNSAT ]
3C COOLING FANS."


Valve!IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP                    ELEMENT                              STANDARD 5              Energize bus 1B3C:                    CUE: After Candidate identifies the correct handle Obtain the circuit breaker            at the AOP-06 cabinet, "You handle from the Shift Manager          have obtained the circuit or the AOP-06 Cabinet.                breaker handle."
[ SAT ]      [ UNSAT ]
6              Close breaker 1B3C-4,                  East Switchgear room "EMERG. FEED TO BUS 1B3C              Close breaker 1B3C-4 and FROM 13.8KV/480V XFMR                  verify breaker position T1B-3C-1."                            indicators display CLOSED.
[ SAT ]      [ UNSAT ]
7              Check that Bus 1B3C is                Checks indication on VG-energized.                            1/1B3C Voltmeters T1B-3C Secondary Phase (1,2,3) (Line to GND) and amber lights for each phase.
CUE: Equal voltage indicated on all three phases and all three amber lights ON with equal intensity.
[ SAT ]      [ UNSAT ]
8              Close BT-1B3C, "BUS TIE                East Switchgear room 1B3C & 1B3C-4C NORMALLY                Close breaker BT-1B3C and CLOSED."                              verify breaker position indicators display CLOSED.
[ SAT ]      [ UNSAT ]


Control Valve
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP                    ELEMENT                              STANDARD 9              Close BT-1B4C, "BUS TIE                CUE: Another Operator will 1B4C & 1B3C-4C NORMALLY                close breaker BT-1B4C, OPEN."                                place Battery Charger #3 in service and transfer DC control power.
Termination Criteria:  480 volt buses 1B3C and 1B3C-4C are energized from 13.8 KV.


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 40 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 INITIAL                A station blackout has occurred.
()INITIALS R127.d.Loosen the Hand Jack Stem Nut, and back it up to the bottom of the hand wheel for the selected valve:
CONDITIONS:            Both 161 KV and 345 KV supplies to the station have been lost.
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                        CAUTION Do Not Force the hand wheel if excessive resistance is met before the handjack stem nut contacts the bonnet of the actuator housing. It is possible that the valve disk is being forced into the valve seat.e.Turn the hand wheel CLOCKWISE unt il the handjack stem nut contacts the bonnet of the actuator hous ing for the selected valve:
Both Diesel Generators have failed to start.
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                        f.If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer for the selected valve:
Energy Marketing reports that 13.8 KV power is available to the plant.
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                        g.Lock hand wheel for the selected valve:
INITIATING CUE:   You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP Attachment
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                                     
: 5. The Control Room Operators have completed steps 1 and 2.


Ind Verif C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 41 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
EOP/AOP ATTACHMENTS Page 17 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                  CONTINGENCY ACTIONS
()INITIALS R127.h.Remove selected valve from the Locked Component Deviation Log:
: 1. Trip BOTH of the following 4160 V breakers:
!HCV-482A!HCV-482B!HCV-483A!HCV-483B CAUTION The following steps may drain CCW from this portion of the system.8.If removing the handjack from HCV-482A, HCV-482B, HCV-483A, HCV-483B, perform the following:
* T1B-3C
a.Ensure CCW isolation valves for selected heat exchanger(s) are closed:
* T1B-4C
!HCV-480, Shtdn Ht Exch AC-4A AC Inlet Valve
: 2. Place the following control switches in PULL-TO-LOCK:
!HCV-484, Shtdn Ht Exch AC-4A AC Outlet Valve
* CA-1A, Air Compressor
!HCV-481, Shtdn Ht Exch AC-4B AC Inlet Valve
* AC-3C, CCW pump
!HCV-485, Shtdn Ht Exch AC-4B AC Outlet Valve b.Ensure that the Handjacked valve has a Closed signal:
* SI-2B, HPSI Pump
!HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve
* VA-3B, Containment Vent Fan
!HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water
* SI-3A, CS Pump
* VA-7C, Containment Vent Fan R26


Outlet Valve
EOP/AOP ATTACHMENTS Page 18 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                  CONTINGENCY ACTIONS
!HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water
: 3. Trip ALL of the following 480 V breakers (East Switchgear Room):
* 1B3C, "T1B-3C MAIN SECONDARY FEED TO 480 VAC BUS 1B3C"
* 1B3C-2, "MCC-3C2 AUX BUILDING (CORR. 26)"
* 1B3C-7, "TURBINE BUILDING CRANE HE-3"
* 1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A"
* 1B3C-3, "OUTDOOR LIGHTING XFMR T1C-3B"
* 1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)"
* 1B3C-8, "AIR COMPRESSOR CA-1A FEED TO LOCAL CONTACTOR" R26


Inlet Valve
EOP/AOP ATTACHMENTS Page 19 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                  CONTINGENCY ACTIONS
!HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water
: 4. Trip ALL of the following 480 V breakers (East Switchgear Room):
* 1B3C-4C-2, "BREAKER UNIT MCC-3C4C-2 TURBINE BLDG (MEZZANINE)"
* 1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C"
* 1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C" R26


Outlet Valve c.Ensure Instrument Air Isolation valve is Open for selected valve:
EOP/AOP ATTACHMENTS Page 20 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                  CONTINGENCY ACTIONS
!IA-HCV-482A-B, Instrument Air Supply Isolation Valve
: 5. Trip ALL of the following 480 V breakers (West Switchgear Room):
!IA-HCV-482B-B, Instrument Air Supply Isolation Valve
* 1B4C, "T1B-4C MAIN SECONDARY FEED TO 480 VAC BUS 1B4C"
!IA-HCV-483A-B, Instrument Air Supply Isolation Valve
* 1B4C-8, "CONTAINMENT COOLING & FILTER FAN VA-3B"
!IA-HCV-483B-B, Instrument Air Supply Isolation Valve
* 1B4C-3, "MCC-4C2 AUX BLDG (CORR 4)"
* 1B4C-4, "MCC-4C3 TURB BLDG (MEZZANINE)"
* 1B4C-7, "MCC-4C4 INTAKE STRUCTURE"
* 1B4C-5, "HI PRESS SAFETY INJ.
PUMP SI-2B"
* 1B4C-2, "MCC-4C1 ELECT PENET.
AREA (RM 57W)"
* 1B4C-1, "MCC-4C5 MOTOR CONTROL CENTER TURBINE BUILDING" R26


C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 42 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
EOP/AOP ATTACHMENTS Page 21 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                  CONTINGENCY ACTIONS
()INITIALS R128.d.Unlock and turn Hand wheel COUNTER-CLOCKWISE until valve stem travel stops for selected valve:
: 6. Place ALL of the following breakers in "OFF" (East Upper Electrical Penetration Room):
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                        e.Contact the Control Room and have selected valve entered into the Locked Component Deviation Log:
* MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF VALVE"
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                                      f.Run the hand jack stem nut down until it contacts the Bonnet of the actuator housing for the selected valve:
* MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF STRESS TEST DISC SWITCH"
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                        g.Place the raw water manual control valve for the selected valve in the OPEN position for the selected valve:
* MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER"
!IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve!IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual
* MCC-3C1-A3R, HE-12-DS/STRESS GALL-DS, ROOM 66 HOIST & STRESS GALLERY TEST DISC SWITCHES
* MCC-3C1-A4L, "SPARE
* MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER"
* MCC-3C1-A05, "TRANSFORMER T1B-3C COOLING FANS" R26


Control Valve
EOP/AOP ATTACHMENTS Page 22 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                   CONTINGENCY ACTIONS
!IA-HCV-483A-TV, Raw Water Inlet Valve HCV-483A Manual Control
: 7. Energize Bus 1B3C by performing the following steps:
 
: a. Obtain the circuit breaker handle from the Shift Manager or the AOP-06 Cabinet.
Valve!IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual
 
Control Valve
 
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 43 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R128.h.Ensure selected valve is in the Open position:
!HCV-482A!HCV-482B!HCV-483A!HCV-483B                                      9.If handjacking HCV-2908, HCV-2918, or HCV-2928 HPSI Pump Discharge Valves, perform the following:a.Ensure the valve to be Handjacked is Closed:
!HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve
!HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve
!HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve b.Remove the Handjack Locking pin from the Valve stem for the selected valve:!HCV-2928!HCV-2908!HCV-2918                  c.Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
!HCV-2928!HCV-2908!HCV-2918                  d.Attach the Hand wheel locking pin to the hand wheel for the selected valve:!HCV-2928!HCV-2908!HCV-2918 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 44 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R1210.If removing the handjack from HCV-2908, HCV-2918, or HCV-2928, perform the following:a.Ensure that the Handjacked valve has a Closed signal:
!HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve
!HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve
!HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve b.Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
!HCV-2928!HCV-2908!HCV-2918                  c.Insert the Handjack locking pin in t he valve stem for the selected valve:
!HCV-2928!HCV-2908!HCV-2918                  d.Contact the Control Room that the hand jack has been removed for the selected valve:
!HCV-2928!HCV-2908!HCV-2918 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 45 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R1211.If handjacking HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves:a.Ensure valve to be Handjacked is Closed:
!HCV-2907, HPSI Pump SI-2B Suction Isolation Valve
!HCV-2917, HPSI Pump SI-2C Suction Isolation Valve
!HCV-2927, HPSI Pump SI-2A Suction Isolation Valve
!HCV-2938, LPSI Pump SI-1B Discharge Valve
!HCV-2948, LPSI Pump SI-1A Discharge Valve
!HCV-2957, Containment Spray Pump SI-3A Suction Valve
!HCV-2958, Containment Spray Pump SI-3A Discharge Valve
!HCV-2967, Containment Spray Pump SI-3B Suction Valve
!HCV-2968, Containment Spray Pump SI-3B Discharge Valve
!HCV-2977, Containment Spray Pump SI-3C Suction Valve
!HCV-2978, Containment Spray Pump SI-3C Discharge Valve b.Remove the Handjack Locking pin from the Valve stem for the selected valve:!HCV-2907!HCV-2917!HCV-2927!HCV-2938!HCV-2948!HCV-2957!HCV-2958!HCV-2967!HCV-2968!HCV-2977!HCV-2978 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 46 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R1211.c.Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
!HCV-2907!HCV-2917!HCV-2927!HCV-2938!HCV-2948!HCV-2957!HCV-2958!HCV-2967!HCV-2968!HCV-2977!HCV-2978                                                                  d.Attach the Hand wheel locking pin to the hand wheel for the selected valve:!HCV-2907!HCV-2917!HCV-2927!HCV-2938!HCV-2948!HCV-2957!HCV-2958!HCV-2967!HCV-2968!HCV-2977!HCV-2978 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 47 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R1212.If Removing the Handjack fr om HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves.a.Ensure the valve to be Handjacked has a Closed signal.
!HCV-2907, HPSI Pump SI-2B Suction Isolation Valve
!HCV-2917, HPSI Pump SI-2C Suction Isolation Valve
!HCV-2927, HPSI Pump SI-2A Suction Isolation Valve
!HCV-2938, LPSI Pump SI-1B Discharge Valve
!HCV-2948, LPSI Pump SI-1A Discharge Valve
!HCV-2957, Containment Spray Pump SI-3A Suction Valve
!HCV-2958, Containment Spray Pump SI-3A Discharge Valve
!HCV-2967, Containment Spray Pump SI-3B Suction Valve
!HCV-2968, Containment Spray Pump SI-3B Discharge Valve
!HCV-2977, Containment Spray Pump SI-3C Suction Valve
!HCV-2978, Containment Spray Pump SI-3C Discharge Valve b.Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
!HCV-2907!HCV-2917!HCV-2927!HCV-2938!HCV-2948!HCV-2957!HCV-2958!HCV-2967!HCV-2968!HCV-2977!HCV-2978 C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 48 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R1212.c.Insert the Handjack locking pin in the valve stem for the selected valve:
!HCV-2907!HCV-2917!HCV-2927!HCV-2938!HCV-2948!HCV-2957!HCV-2958!HCV-2967!HCV-2968!HCV-2977!HCV-2978                                                                  d.Contact the Control Room that the hand jack has been removed for the selected valve:
!HCV-2907!HCV-2917!HCV-2927!HCV-2938!HCV-2948!HCV-2957!HCV-2958!HCV-2967!HCV-2968!HCV-2977!HCV-2978                                                                                13.If Handjacking HCV-2937, or HCV-2947, complete the following for the selected valve:a.Ensure the selected valve is Closed:
!HCV-2937, LPSI Pump SI-1B Suction Valve
!HCV-2947, LPSI Pump SI-1A Suction Valve
 
C Continuous Use FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 49 OF 69  - Operation of Safe ty Injection Air Operated Valves PROCEDURE (continued)
()INITIALS R1213.b.Remove the Handjack Locking pin fr om the Valve stem for the selected valve:!HCV-2937!HCV-2947            c.Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:
!HCV-2937!HCV-2947                          14.If REMOVING Handjack from HCV
-2937, or HCV-2947, perform the following:a.Ensure the selected valve has a CLOSED signal:
!HCV-2937, LPSI Pump SI-1B Suction Valve
!HCV-2947, LPSI Pump SI-1A Suction Valve b.Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:
!HCV-2937!HCV-2947            c.Insert the handjack locking pin in the valve stem for the selected valve:
!HCV-2937!HCV-2947            d.Contact the Control Room that the hand jack has been removed for theselected valve.     
 
Completed by Date/Time            /         
 
EOP/AOP ATTACHMENTS Page 17 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS    1. Trip BOTH of the following 4160 V breakers:
T1B-3C  T1B-4C
: 2. Place the following control switches in "PULL-TO-LOCK":
CA-1A, Air Compressor  AC-3C, CCW pump  SI-2B, HPSI Pump  VA-3B, Containment Vent Fan  SI-3A, CS Pump  VA-7C, Containment Vent Fan
 
EOP/AOP ATTACHMENTS Page 18 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS    3. Trip ALL of the following 480 V breakers (East Switchgear Room):
1B3C, "T1B-3C MAIN SECONDARY FEED TO 480 VAC BUS 1B3C"  1B3C-2, "MCC-3C2 AUX BUILDING (CORR. 26)"  1B3C-7, "TURBINE BUILDING CRANE HE-3"  1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A"  1B3C-3, "OUTDOOR LIGHTING XFMR T1C-3B" 1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)"  1B3C-8, "AIR COMPRESSOR CA-1A FEED TO LOCAL CONTACTOR" EOP/AOP ATTACHMENTS Page 19 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS    4. Trip ALL of the following 480 V breakers (East Switchgear Room):
1B3C-4C-2, "BREAKER UNIT MCC-3C4C-2 TURBINE BLDG (MEZZANINE)"  1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN
 
VA-7C"  1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER
 
PUMP AC-3C" EOP/AOP ATTACHMENTS Page 20 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS   5. Trip ALL of the following 480 V breakers (West Switchgear Room):
1B4C, "T1B-4C MAIN SECONDARY FEED TO 480 VAC BUS 1B4C"  1B4C-8, "CONTAINMENT COOLING & FILTER FAN VA-3B"  1B4C-3, "MCC-4C2 AUX BLDG (CORR 4)"  1B4C-4, "MCC-4C3 TURB BLDG (MEZZANINE)"  1B4C-7, "MCC-4C4 INTAKE STRUCTURE"  1B4C-5, "HI PRESS SAFETY INJ.
PUMP SI-2B"  1B4C-2, "MCC-4C1 ELECT PENET.
AREA (RM 57W)"  1B4C-1, "MCC-4C5 MOTOR CONTROL CENTER TURBINE BUILDING" EOP/AOP ATTACHMENTS Page 21 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS    6. Place ALL of the following breakers in "OFF" (East Upper Electrical
 
Penetration Room):
MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF VALVE"  MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF
 
STRESS TEST DISC SWITCH"  MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL
 
TRANSFORMER"  MCC-3C1-A3R, "HE-12-DS/STRESS GALL-DS, ROOM 66 HOIST & STRESS
 
GALLERY TEST DISC SWITCHES" MCC-3C1-A4L, "SPARE" MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS
 
TRANSFORMER"  MCC-3C1-A05, "TRANSFORMER T1B-3C COOLING FANS" EOP/AOP ATTACHMENTS Page 22 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS    7. Energize Bus 1B3C by performing the following steps:
: a. Obtain the circuit breaker handle from the Shift Manager or the  
 
AOP-06 Cabinet.
: b. Close breaker 1B3C-4, "EMERG.
: b. Close breaker 1B3C-4, "EMERG.
FEED TO BUS 1B3C FROM  
FEED TO BUS 1B3C FROM 13.8KV/480V XFMR T1B-3C-1" (East Switchgear Room).
 
13.8KV/480V XFMR T1B-3C-1" (East Switchgear Room).
: 8. Check that Bus 1B3C is energized.
: 8. Check that Bus 1B3C is energized.
: 9. Close BOTH of the following 480 V breakers:
: 9. Close BOTH of the following 480 V breakers:
BT-1B3C, "BUS TIE 1B3C &
* BT-1B3C, "BUS TIE 1B3C &
1B3C-4C NORMALLY CLOSED" (East Switchgear Room)
1B3C-4C NORMALLY CLOSED" (East Switchgear Room)
BT-1B4C, "BUS TIE 1B4C &
* BT-1B4C, "BUS TIE 1B4C &
1B3C-4C NORMALLY OPEN" (West Switchgear Room)  
1B3C-4C NORMALLY OPEN" (West Switchgear Room)
R26


EOP/AOP ATTACHMENTS Page 23 of 168 R26 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS   10. Place Battery Charger 3 in service by performing the following steps:
EOP/AOP ATTACHMENTS Page 23 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS                                   CONTINGENCY ACTIONS
: a. Ensure breaker 1B3C-1, "MCC-3C1 ELECT PENET.  
: 10. Place Battery Charger 3 in service by performing the following steps:
 
: a. Ensure breaker 1B3C-1, "MCC-3C1 ELECT PENET.
AREA (RM 57E)", is closed (East  
AREA (RM 57E)", is closed (East Switchgear Room).
: b. Open BOTH Battery Charger 3 breakers (West Switchgear Room):
* EE-8E-CB1, BATT CHARGER 3 (EE-8E) AC INPUT BREAKER
* EE-8E-CB2, BATT CHARGER 3 (EE-8E)DC OUTPUT BREAKER
: c. Place the "VOLTAGE SELECTOR" switch in "FLOAT" (EE-8E).
(continue)
R26


Switchgear Room).
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Location:          Intake Structure Approximate Time:  10 minutes            Actual Time: _________________
: b. Open BOTH Battery Charger 3 breakers (West Switchgear
Reference(s):  K/A# 086000 A2.04 OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRAINER OPERATION."
Handout(s):     OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRAINER OPERATION."
Time Critical: NO Alternate Path: YES JPM Prepared by:    Jerry Koske                                  Date: 3/05/09 Page 1 of 7


Room):   EE-8E-CB1, "BATT CHARGER 3 (EE-8E) AC INPUT BREAKER" EE-8E-CB2, "BATT CHARGER 3 (EE-8E)DC OUTPUT BREAKER"
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Operators Name: _____________________ Employee # ______________
: c. Place the "VOLTAGE SELECTOR" switch in "FLOAT" (EE-8E).     (continue)
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:        Potential tripping hazards. Do Not operate any controls.
Comments:                    Alternate Path Page 2 of 7


C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 18 OF 186 R68 Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PREREQUISITES
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump TASK                The Candidate performed a local emergency start of STANDARD:          Diesel Fire Pump, FP-1B. The candidate manually opened the Fuel Oil Solenoid Valve and the Cooling Water Bypass valve and started the pump using a Starter Contactor because Manual Start number 1 and 2 were both unsuccessful.
()INITIALS1.Procedure Revision Verification Revision No.
INITIAL                  The Electric Fire Pump, FP-1A, is out of service.
Date:             
CONDITIONS:              Transformer deluge has activated due to a fire.
The Diesel Fire Pump, FP-1B, did not start automatically.
INITIATING CUE:    You are directed to perform a local emergency manual start of the diesel fire pump in accordance with OI-FP-1, Attachment 3, step 3.
Page 3 of 7


PROCEDURE NOTE Prior to declaring FP-1B inoperable the Fire Protection System Engineer or designee shall analyze Room 19 Fire Protection System per SO-G-58 to  minimize risk to sa fety related cable trays.1.IF removing FP-1B, Diesel Fire Pump, from service, THEN complete the following:a.Notify the Control Room this system is being removed from service.              b.Ensure the requirements of SO-G-103 are met and log into any requiredAction Statements in the Control Room Log.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Critical Steps shown in gray STEP                  ELEMENT                              STANDARD Note to Examiner: Provide candidate with a copy of OI-FP-1, Attachment 3.
Shift Mgrc.A Fire Impairment has been issued for removing FP-1B from service.
1               Ensure the following are on:          AI-183 AI-183-CB1, Fire Pump FP-1B Batt 1 Switch.          Battery 1 is ON.
NOTE The following will alarm when FP-1B is placed in PULL OUT:
AI-183-CB2, Fire Pump FP-1B Batt 2 Switch.           Battery 2 is ON.
!ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10,11/A13, B-3L)d.Place FP-1B control switch in PULL-OUT (CB-10/11).     e.Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, in OFF (AI-183).     f.Close FP-153, Diesel Fire Pump FP-1B Discharge to Main Header.      g.Verify FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed.
[ SAT ]      [ UNSAT ]
C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 19 OF 186  - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
2              Place HC/FP-1B-MS, Diesel             AI-183 Fire Pump FP-1B Local Control Switch, to Manual 1.                 Select Manual #1.
()INITIALS R681.h.Ensure  FP-154, From Screenwash Header Crosstie Valve, is closed.    
[ SAT ]      [ UNSAT ]
3              Press HC/FP-1B-1, "Fire Pump         AI-183 FP-1B Crank 1 Start Button.
Push Crank 1 Start Button.
[ SAT ]      [ UNSAT ]
CUE: Engine did not turn over or start 4              Place HC/FP-1B-MS, Diesel             AI-183 Fire Pump FP-1B Local Control Switch, to Manual 2.                  Select Manual #2.
[ SAT ]      [ UNSAT ]
Page 4 of 7


CAUTION A  leak greater than the makeup of the Jockey Pump will cause an inadvertent start of FP-1 A when draining FP-1B header.i.IF necessary to drain header, THEN open FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve.              2.IF returning Diesel Fire Pump FP-1B to service, THEN complete the following:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump STEP                    ELEMENT                              STANDARD 5              Press HC/FP-1B-1, "Fire Pump          AI-183 FP-1B Crank 2 Start Button.
CAUTION Security must be present at the Screen F enclosure and remain there
Push Crank 2 Start Button.
[ SAT ]      [ UNSAT ]
CUE: Engine did not turn over or start 6              Open FO-169, Fuel Oil                  South side of Engine Solenoid Valve.
Turn Knob clockwise to full-in position.
[ SAT ]      [ UNSAT ]
7              Open FP-161, Pressure control          South side of Engine valve FP-162 bypass valve.
Cooling water bypass valve to OPEN.
[ SAT ]      [ UNSAT ]
8               Read Caution                          Read Caution on page 24
[ SAT ]      [ UNSAT ]
9              Engage the starter using either        North side of Engine of the two starter contactors.
Raise lever knob on either:
YS/FP-1B-1.
YS/FP-1B-1.
CUE: Engine has started and is running.
Release lever.
[ SAT ]      [ UNSAT ]
Page 5 of 7


until Sluice Gate CW-14F is closed or CW-1C is placed back in service.a.Ensure one of the following Suction Well flow paths is aligned as follows
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Termination Criteria:  Diesel Fire Pump has been started Page 6 of 7
!CW-14E, Circ Water Pump CW-1C Screen Sluice Gate, is open
!CW-14F, Circ Water Pump CW-1C Screen Sluice Gate, is open
!CW-16B, Circ Water Pumps interconnection Sluice Gate and


CW-14C, Traveling Screen Sluice Gate, are open
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 INITIAL                The Electric Fire Pump, FP-1A, is out of service.
!CW-16B, Circ Water Pumps interconnection Sluice Gate and
CONDITIONS:            Transformer deluge has activated due to a fire.
The Diesel Fire Pump, FP-1B, did not start automatically.
INITIATING CUE:  You are directed to perform a local emergency manual start of the diesel fire pump in accordance with OI-FP-1, Attachment 3, step 3.
Page 7 of 7


CW-14D, Traveling Screen Sluice Gate, are open
FORT CALHOUN STATION                                                                  OI-FP-1 OPERATING INSTRUCTION                                                          PAGE 18 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PREREQUISITES                                                                    (T) INITIALS
: 1. Procedure Revision Verification Revision No. 68            Date: 3/31/09                                          JEK PROCEDURE NOTE Prior to declaring FP-1B inoperable the Fire Protection System Engineer or designee shall analyze Room 19 Fire Protection System per SO-G-58 to minimize risk to safety related cable trays.
: 1. IF removing FP-1B, Diesel Fire Pump, from service, THEN complete the following:
: a. Notify the Control Room this system is being removed from service.
: b. Ensure the requirements of SO-G-103 are met and log into any required Action Statements in the Control Room Log.
Shift Mgr
: c. A Fire Impairment has been issued for removing FP-1B from service.
NOTE The following will alarm when FP-1B is placed in PULL OUT:
          ! ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10,11/A13, B-3L)
: d. Place FP-1B control switch in PULL-OUT (CB-10/11).
: e. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, in OFF (AI-183).
: f. Close FP-153, Diesel Fire Pump FP-1B Discharge to Main Header.
: g. Verify FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed.
R68


Shift Mgrb.Ensure FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed.
FORT CALHOUN STATION                                                                     OI-FP-1 OPERATING INSTRUCTION                                                             PAGE 19 OF 186 C
C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 20 OF 186 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                               (T) INITIALS
()INITIALS R68 CAUTION If FP-1A control switch is taken to pull-to-lock to prevent inadvertent starting a Dedicated Operator must be stationed at the control switch (Ref. SO-G-103)2.c.If desired by the Shift Mgr/CRS to prevent an inadvertent start of FP-1A:1)Station a Dedicated Operator at the FP-1A control switch with instructions to immediately retu rn the control switch to AFTER STOP should water be needed for the Fire Protection System. This
: 1. h. Ensure FP-154, From Screenwash Header Crosstie Valve, is closed.
CAUTION A leak greater than the makeup of the Jockey Pump will cause an inadvertent start of FP-1A when draining FP-1B header.
: i. IF necessary to drain header, THEN open FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve.
: 2. IF returning Diesel Fire Pump FP-1B to service, THEN complete the following:
CAUTION Security must be present at the Screen F enclosure and remain there until Sluice Gate CW-14F is closed or CW-1C is placed back in service.
: a. Ensure one of the following Suction Well flow paths is aligned as follows
          !    CW-14E, Circ Water Pump CW-1C Screen Sluice Gate, is open
          !    CW-14F, Circ Water Pump CW-1C Screen Sluice Gate, is open
          !    CW-16B, Circ Water Pumps interconnection Sluice Gate and CW-14C, Traveling Screen Sluice Gate, are open
          !    CW-16B, Circ Water Pumps interconnection Sluice Gate and CW-14D, Traveling Screen Sluice Gate, are open Shift Mgr
: b. Ensure FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed.
R68


would be indicated by receipt of a fire suppression system flow
FORT CALHOUN STATION                                                                          OI-FP-1 OPERATING INSTRUCTION                                                                  PAGE 20 OF 186 C
 
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                                    (T) INITIALS CAUTION If FP-1A control switch is taken to pull-to-lock to prevent inadvertent starting a Dedicated Operator must be stationed at the control switch (Ref. SO-G-103)
alarm, initiation of manual fire s uppression activities using fire hose stations or confirmation of a fire in a protected area.
: 2. c. If desired by the Shift Mgr/CRS to prevent an inadvertent start of FP-1A:
: 1) Station a Dedicated Operator at the FP-1A control switch with instructions to immediately return the control switch to AFTER STOP should water be needed for the Fire Protection System. This would be indicated by receipt of a fire suppression system flow alarm, initiation of manual fire suppression activities using fire hose stations or confirmation of a fire in a protected area.
Dedicated Operator NOTE The following will alarm when FP-1A is placed in PULL OUT:
Dedicated Operator NOTE The following will alarm when FP-1A is placed in PULL OUT:
!MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD
                !   MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD TRIP (CB-10,11/A13, B-4U)
 
: 2) Place FP-1A control switch (CB-10/11) in pullout.
TRIP (CB-10,11/A13, B-4U)2)Place FP-1A control switch (CB-10/11) in pullout.    
CAUTION Slowly throttling open FP-502 while maintaining Fire Main pressure greater than 116 psig will prevent inadvertent starting of Electric Fire Pump FP-1A on low pressure.
 
: d. IF maintenance was performed on FP-6B, Diesel Driven Fire Pump FP-1B Strainer, THEN ensure maintenance personnel are available and standing by prior to pressurization.
CAUTION Slowly throttling open FP-502 while maintaining Fire Main pressure
R68
 
greater than 116 psig will prevent inadv ertent starting of Electric Fire
 
Pump FP-1A on low pressure.d.IF maintenance was performed on FP-6B, Diesel Driven Fire Pump FP-1B Strainer, THEN ensure maintenance personnel are available and standing by prior to pressurization.
C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 21 OF 186  - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
()INITIALS R682.e.Slowly throttle open FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, to pressurize line to FP-1B.
f.Verify Fire Main pressure is greater than 116 psig.
g.Open and Lock Open FP-153, Diesel Fire Pump FP-1B Discharge to Main Header.      h.Close FP-502.
i.Return FP-1A to auto if required by:
NOTE The following alarm will reset when FP-1A is placed in AFTER STOP:!MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD
 
TRIP (CB-10,11/A13, B-4U)1)Place FP-1A control switch (CB-10/11) in AFTER STOP.      2)Secure the Dedicated Operator for FP-1A.
j.Place FP-1B control switch in AFTER-STOP (CB-10/11).
 
C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 22 OF 186  - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
()INITIALS R68 NOTE The following alarm will reset when HC/FP-1B-MS is placed in AUTO:
!ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10/11/A13, B-3L)2.k.Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, toAUTO (AI-183).      l.Ensure minimum Level of 75% indicat ed level of diesel fuel in FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank, by completing the
 
following:1)Unlock and open FO-231, Diesel Tank FO-27 Sightglass Root Valve.      2)Allow level in the sightglass to settle at its equilibrium point.
m.Record FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank level:
Level (33" min.)1)Close and Lock FO-231.
n.Independently verify the following valve positions:
[AR 06498]
!FO-231, Diesel Tank FO-27 Sightglass Root Valve, is Locked Closed
!FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed
!FP-153, Diesel Fire Pump FP-1B Discharge to Main Headers, is Locked Open
!FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed
!FP-1B CS, Diesel Fire Pump Control Switch, is in AFTER STOP (CB-10/11)
!HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, is in
 
AUTO (AI-183)
 
Ind Verifo.Notify Control Room Operator t he system has been returned to service.
[AR 06498]


C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 23 OF 186 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
FORT CALHOUN STATION                                                                   OI-FP-1 OPERATING INSTRUCTION                                                         PAGE 21 OF 186 C
()INITIALS R682.p.Exit from any Action Statements entered in the Control Room Log.              q.Clear the Fire Impairment issued for FP-1B.
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                           (T) INITIALS
3.IF Local Emergency Manual Starting of the Diesel Fire Pump (AI-183) is required, THEN complete the following:a.Ensure the following are ON:
: 2. e. Slowly throttle open FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, to pressurize line to FP-1B.
!AI-183-CB1, Fire Pump FP-1B Batt 1 Switch
: f. Verify Fire Main pressure is greater than 116 psig.
!AI-183-CB2, Fire Pump FP-1B Batt 2 Switch b.Place HC/FP-1B-MS,  Diesel Fire Pu mp FP-1B Local Control Switch, toMANUAL 1.      c.Press HC/FP-1B-1, Fire Pump FP-1B Crank 1 Start Button.
: g. Open and Lock Open FP-153, Diesel Fire Pump FP-1B Discharge to Main Header.
d.IF Engine does not start, THEN perform the following:
: h. Close FP-502.
1)Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, toMANUAL 2.     2)Press HC/FP-1B-2, Fire Pump FP-1B Crank 2 Start Button.
: i. Return FP-1A to auto if required by:
e.IF the Engine has not started, THEN perform the following:
NOTE The following alarm will reset when FP-1A is placed in AFTER STOP:
1)Open FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, byturning the knob in (clockwise).     2)Open FP-161, Pressure Control Valve FP-162 Bypass Valve.
                !    MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD TRIP (CB-10,11/A13, B-4U)
: 1) Place FP-1A control switch (CB-10/11) in AFTER STOP.
: 2) Secure the Dedicated Operator for FP-1A.
: j. Place FP-1B control switch in AFTER-STOP (CB-10/11).
R68


C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 24 OF 186 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
FORT CALHOUN STATION                                                                   OI-FP-1 OPERATING INSTRUCTION                                                         PAGE 22 OF 186 C
()INITIALS R68 CAUTION As soon as the engine is running in Step 3), release the lever.3.e3)Engage the starter by raising the le ver knob on either of the two starter contactors:
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                           (T) INITIALS NOTE The following alarm will reset when HC/FP-1B-MS is placed in AUTO:
!  YS/FP-1B-1, Diesel Fire Pump FP-1B #1 Starter Contactor
          ! ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10/11/A13, B-3L)
!  YS/FP-1B-2, Diesel Fire Pump FP-1B #2 Starter Contactor 4.IF securing from Local Emergency Manual Starting of the Diesel Fire Pump (AI-183), THEN complete the following:a.Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, toOFF.      b.Ensure FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, is closed(by turning the knob out counter-clockwise).      c.Ensure FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed.     d.Independently verify the following valve positions:
: 2. k. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to AUTO (AI-183).
: l. Ensure minimum Level of 75% indicated level of diesel fuel in FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank, by completing the following:
: 1) Unlock and open FO-231, Diesel Tank FO-27 Sightglass Root Valve.
: 2) Allow level in the sightglass to settle at its equilibrium point.
: m. Record FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank level:
Level (33" min.)
: 1) Close and Lock FO-231.
: n. Independently verify the following valve positions: [AR 06498]
        !    FO-231, Diesel Tank FO-27 Sightglass Root Valve, is Locked Closed
        !    FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed
        !    FP-153, Diesel Fire Pump FP-1B Discharge to Main Headers, is Locked Open
        !    FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed
        !    FP-1B CS, Diesel Fire Pump Control Switch, is in AFTER STOP (CB-10/11)
        !    HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, is in AUTO (AI-183)
Ind Verif
: o. Notify Control Room Operator the system has been returned to service.
[AR 06498]
[AR 06498]
!FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed
R68
!FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve (by turning the knob out counter-clockwise)
 
Ind Verif C Continuous Use FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 25 OF 186  - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)
()INITIALS R685.IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO or MANUAL, THEN complete one of the following:a.IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO,THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to AUTO.
CAUTION If the Fire Pumps are in AUTO-STANDBY and FP-1B is not operating, placing FP-6B control box toggle switch in MANUAL will depressurize the


Fire Main and start both Fire Pumps.b.IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in MANUAL,THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to MANUAL.
FORT CALHOUN STATION                                                                OI-FP-1 OPERATING INSTRUCTION                                                      PAGE 23 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                          (T) INITIALS
: 2. p. Exit from any Action Statements entered in the Control Room Log.
: q. Clear the Fire Impairment issued for FP-1B.
: 3. IF Local Emergency Manual Starting of the Diesel Fire Pump (AI-183) is required, THEN complete the following:
: a. Ensure the following are ON:
      !  AI-183-CB1, Fire Pump FP-1B Batt 1 Switch
      !  AI-183-CB2, Fire Pump FP-1B Batt 2 Switch
: b. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to MANUAL 1.
: c. Press HC/FP-1B-1, Fire Pump FP-1B Crank 1 Start Button.
: d. IF Engine does not start, THEN perform the following:
: 1) Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to MANUAL 2.
: 2) Press HC/FP-1B-2, Fire Pump FP-1B Crank 2 Start Button.
: e. IF the Engine has not started, THEN perform the following:
: 1) Open FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, by turning the knob in (clockwise).
: 2) Open FP-161, Pressure Control Valve FP-162 Bypass Valve.
R68


Completed by Date/Time             /
FORT CALHOUN STATION                                                                      OI-FP-1 OPERATING INSTRUCTION                                                            PAGE 24 OF 186 C
Reviewed by Shift Manager
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                              (T) INITIALS CAUTION As soon as the engine is running in Step 3), release the lever.
[AR 06498]  
3.e    3) Engage the starter by raising the lever knob on either of the two starter contactors:
            ! YS/FP-1B-1, Diesel Fire Pump FP-1B #1 Starter Contactor
             ! YS/FP-1B-2, Diesel Fire Pump FP-1B #2 Starter Contactor
: 4. IF securing from Local Emergency Manual Starting of the Diesel Fire Pump (AI-183),
THEN complete the following:
: a. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to OFF.
: b. Ensure FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, is closed (by turning the knob out counter-clockwise).
: c. Ensure FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed.
: d. Independently verify the following valve positions: [AR 06498]
      !    FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed
      !    FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve (by turning the knob out counter-clockwise)
Ind Verif R68


PAGE 1 OF 9 R13 
FORT CALHOUN STATION                                                                  OI-FP-1 OPERATING INSTRUCTION                                                        PAGE 25 OF 186 C
Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued)                                                          (T) INITIALS
: 5. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO or MANUAL, THEN complete one of the following:
: a. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO, THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to AUTO.
CAUTION If the Fire Pumps are in AUTO-STANDBY and FP-1B is not operating, placing FP-6B control box toggle switch in MANUAL will depressurize the Fire Main and start both Fire Pumps.
: b. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in MANUAL, THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to MANUAL.
Completed by                                                        Date/Time        /
Reviewed by Shift Manager [AR 06498]
R68


Fort Calhoun Station Unit No. 1  
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test Location:            Simulator Approximate Time:    18 minutes          Actual Time: _________________
Reference(s):  K/A: 001000 A4.03 OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)
PARTIAL MOVEMENT TEST" OI-RR-1, "REACTOR REGULATING SYSTEM NORMAL OPERATION" Handout(s):    OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)
PARTIAL MOVEMENT TEST" Time Critical:  NO Alternate Path:  YES JPM Prepared by:    Jerry Koske                                  Date: 3/3/09 Page 1 of 7


OP-ST-CEA-0003
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:
Comments:                    Alternate Path Page 2 of 7


SURVEILLANCE TEST
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test TASK                The candidate performed the CEA partial movement STANDARD:            check for group 3 CEAs using OP-ST-CEA-003. While inserting one of the CEAs, the CEA continued to insert after releasing the IN-OUT-HOLD switch. The candidate stopped the uncontrolled motion by placing the Mode Selector Switch in OFF.
INITIAL              The plant is operating at full power with all CEAs fully CONDITIONS:          withdrawn.
INITIATING CUE:      You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.
All prerequisites have been met.
Page 3 of 7


CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test Critical Steps shown in gray STEP                  ELEMENT                               STANDARD 1              Record the initial position of        Records position of CEAs each group 3 CEA.                      2,3,4 and 5 as 128 inches on OP-ST-CEA-003, attachment 1.
[ SAT ]      [ UNSAT ]
2              Rotate the Mode selector              CB-4 switch to Manual Individual            Places Mode Selector Switch position.                              (M/M) to the Manual Individual Position (M/I).
[ SAT ]      [ UNSAT ]
3              Rotate the Group Selector              CB-4 Switch (M/G) to the group              Rotate Group Selector Switch containing the CEA to be              (M/G) to the "Group 3" moved.                                position.
[ SAT ]      [ UNSAT ]
4              Verify on the DCS display              CB-4 CEA_ALL that the group button          Ensure CEA-ALL is displayed is DARK GREY.                          and that Group 3 is DARK GREY.
[ SAT ]      [ UNSAT ]
5              Rotate the Rod Selector Switch        CB-4 to the CEA to be moved.                Rotate Rod Selector Switch to CEA position.
[ SAT ]      [ UNSAT ]
Page 4 of 7


Change No. EC 34712 Reason for Change These changes are intended to facilitate use of the GARDEL core monitoring program and to allow operator, STA, and RE to use the
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test STEP                    ELEMENT                              STANDARD 6              Insert CEA a minimum of 6              CB-4 inches then return to normal          Push IN-OUT-HOLD switch in position.                              until CEA position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA is fully withdrawn.
[ SAT ]        [ UNSAT ]
7              Record Information on                  Note to Examiner: This step Attachment 1.                          may be completed after all CEAs have been exercised.
Record inserted to and returned to position for CEA on Attachment 1.
[ SAT ]        [ UNSAT ]
8              Rotate the Rod Selector Switch        CB-4 to the CEA to be moved.                Rotate Rod Selector Switch to next CEA position.
[ SAT ]        [ UNSAT ]
9              Insert CEA a minimum of 6              CB-4 inches then return to normal          Push IN-OUT-HOLD switch in position.                              until CEA position is 122 inches or less.
[ SAT ]        [ UNSAT ]
NOTE: CEA will continue to insert Page 5 of 7


program for the performance of va rious core monitoring and testing
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test STEP                    ELEMENT                              STANDARD 10            Immediately place Mode                CB-4 Selector Switch in OFF.                Immediately return Mode Selector Switch to OFF position before the CEA has been inserted to less than 108 inches. Verify CEA motion has stopped.
[ SAT ]        [ UNSAT ]
11            Notify Shift Manager of failure.      Notified Shift Manager of uncontrolled CEA motion.
[ SAT ]        [ UNSAT ]
12            Verify position of all CEAs.          CB-4 Verifies position off all CEAs using Primary and Secondary CEA Position Indication.
[ SAT ]        [ UNSAT ]
CUE: The Shift Manager has directed that this surveillance test be terminated.
Termination Criteria:  The Mode Selector Switch is in the OFF position and the test has been terminated by the Shift Manager.
Page 6 of 7


functions. Requestor T.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 INITIAL          The plant is operating at full power with all CEAs fully CONDITIONS:      withdrawn.
Heng Preparer T.
INITIATING CUE:  You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.
Heng Issue Date 06-06-08  3:00 pm
All prerequisites have been met.
Page 7 of 7


FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 2 OF 9 R13 CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK SAFETY RELATED
PAGE 1 OF 9 Fort Calhoun Station Unit No. 1 OP-ST-CEA-0003 SURVEILLANCE TEST CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK Change No.       EC 34712 Reason for Change These changes are intended to facilitate use of the GARDEL core monitoring program and to allow operator, STA, and RE to use the program for the performance of various core monitoring and testing functions.
: 1. PURPOSE To satisfy, at least quarterly when the Reacto r is critical, the requi rements of Technical Specification 3.2, T able 3-5, Item 2.
Requestor        T. Heng Preparer          T. Heng Issue Date        06-06-08 3:00 pm R13
: 2. REFERENCES/COMMITMENT DOCUMENTS


2.1 Technical Specifications:
FORT CALHOUN STATION                                                            OP-ST-CEA-0003 SURVEILLANCE TEST                                                                    PAGE 2 OF 9 CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK SAFETY RELATED
3.2, Table 3-5, Minimum Frequencies for Equipment Tests 2.10.2 (4), Full Length CEA Po sition During Power Operation 2.10.2 (6), Shutdown CEA Insert ion Limit During Power Operation 2.10.2 (7), Regulating CEA Insertion Limi ts During Hot Standby and Power Operation 2.15, Table 2-5, Instrum entation Operating R equirements for Other Safety Feature Functions 2.2 USAR, Section 7  
: 1. PURPOSE To satisfy, at least quarterly when the Reactor is critical, the requirements of Technical Specification 3.2, Table 3-5, Item 2.
 
: 2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:
2.3 SO-G-23, Surveillance Test Program  
* 3.2, Table 3-5, Minimum Frequencies for Equipment Tests
 
* 2.10.2 (4), Full Length CEA Position During Power Operation
2.4 Ongoing Commitment Documents  
* 2.10.2 (6), Shutdown CEA Insertion Limit During Power Operation
 
* 2.10.2 (7), Regulating CEA Insertion Limits During Hot Standby and Power Operation
AR 04922, LIC-87-0013 AR 08779, LIC 0765 (LER-88-018) AR 14801, LIC 0294 (LER-93-016)
* 2.15, Table 2-5, Instrumentation Operating Requirements for Other Safety Feature Functions 2.2 USAR, Section 7 2.3 SO-G-23, Surveillance Test Program 2.4 Ongoing Commitment Documents
* AR 04922, LIC-87-0013
* AR 08779, LIC-88-0765 (LER-88-018)
* AR 14801, LIC-93-0294 (LER-93-016)
: 3. DEFINITIONS None
: 3. DEFINITIONS None
: 4. EQUIPMENT LIST None
: 4. EQUIPMENT LIST None
: 5. PRECAUTIONS AND LIMITATIONS
: 5. PRECAUTIONS AND LIMITATIONS 5.1 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted in the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.
 
R13
5.1 All anomalies and deficiencies shall be repor ted immediately to the Shift Manager and noted in the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.  
 
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 3 OF 9 R13 5.2 Manipulation of all contro ls as defined in 10CFR55 shall be done by, or under the direct supervision of, a NRC licensed operator.
5.3 Only one method of positive reactivity addition shall be used at any one time.
 
5.4 During all rod motion, nuclear instrumentation and RCS te mperature shall be observed for response.
 
5.5 Be alert for any abnormal noise or i ndications when CEDMs are in operation.
 
5.6 Power Dependent Insertion Limits shall not be violated by more than one (1) CEA at a time during this test.
 
5.7 Shutdown CEAs shall not be inserted below the exercise limit.
 
5.8 Each CEA shall be returned to its pret est position prior to testing other CEAs.
 
5.9 CEAs within a Group should be kept within two (2) inches of eac h other per OI-RR-1, unless specifically required otherwise by this procedure.
 
5.10 The Reactor shall not be placed in the Automatic mode.
 
5.11 No maintenance shall be conducted within this Surveillance Test other than that specifically directed by this procedure.


FORT CALHOUN STATION                                                            OP-ST-CEA-0003 SURVEILLANCE TEST                                                                  PAGE 3 OF 9 5.2  Manipulation of all controls as defined in 10CFR55 shall be done by, or under the direct supervision of, a NRC licensed operator.
5.3  Only one method of positive reactivity addition shall be used at any one time.
5.4  During all rod motion, nuclear instrumentation and RCS temperature shall be observed for response.
5.5  Be alert for any abnormal noise or indications when CEDMs are in operation.
5.6  Power Dependent Insertion Limits shall not be violated by more than one (1) CEA at a time during this test.
5.7  Shutdown CEAs shall not be inserted below the exercise limit.
5.8  Each CEA shall be returned to its pretest position prior to testing other CEAs.
5.9  CEAs within a Group should be kept within two (2) inches of each other per OI-RR-1, unless specifically required otherwise by this procedure.
5.10 The Reactor shall not be placed in the Automatic mode.
5.11 No maintenance shall be conducted within this Surveillance Test other than that specifically directed by this procedure.
5.12 Any time the Mode Selector Switch is in any position other than OFF, all available rod position indications shall be monitored, Synchros, SCEAPIS, ERF (page 302), and Core Mimic. [AR 14801]
5.12 Any time the Mode Selector Switch is in any position other than OFF, all available rod position indications shall be monitored, Synchros, SCEAPIS, ERF (page 302), and Core Mimic. [AR 14801]
 
5.13 If a CEA position abnormality occurs, verify the position of all CEAs. [AR 14801]
5.13 If a CEA position abnormality occurs, verify the position of all CEAs.
[AR 14801]
 
5.14 The following annunciators may Alarm during the performance of this Surveillance test:
5.14 The following annunciators may Alarm during the performance of this Surveillance test:
REGULATING GROUP WITHDRAWAL PROHIBIT (CB-4, A8, A-1L) PDIL GR 1 COMPUTER (CB-4, A8, A-3U) PPDIL GR 1 COMPUTER (CB-4, A8, A-4U) PDIL GR 2 COMPUTER (CB-4, A8, A-3L) PPDIL GR 2 COMPUTER (CB-4, A8, A-4L) ROD DRIVE POWER INTERRUPT (CB-4, A8, A-5U) ROD POSITION DEVIATION LOW LIMIT (CB-4, A8, B-1U) ROD POSITION DEVIATION LOW-LOW LIMIT (CB-4, A8, B-1L) PDIL GR 3 COMPUTER (CB-4, A8, B-3U) PPDIL GR 3 COMPUTER (CB-4, A8, B-4U) VLPM ALARM OR TROUBLE (CB-1,2,3, A6, D-3)  
* REGULATING GROUP WITHDRAWAL PROHIBIT (CB-4, A8, A-1L)
 
* PDIL GR 1 COMPUTER (CB-4, A8, A-3U)
FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 4 OF 9 R13 5.15 The following DCS alarms may occur during the performance of this Surveillance Test:
* PPDIL GR 1 COMPUTER (CB-4, A8, A-4U)
ROD BLOCK  PPDIL  PDIL  ISH  6. PREREQUISITES
* PDIL GR 2 COMPUTER (CB-4, A8, A-3L)
 
* PPDIL GR 2 COMPUTER (CB-4, A8, A-4L)
6.1 Procedure Revision Verification:
* ROD DRIVE POWER INTERRUPT (CB-4, A8, A-5U)
 
* ROD POSITION DEVIATION LOW LIMIT (CB-4, A8, B-1U)
Revision No.
* ROD POSITION DEVIATION LOW-LOW LIMIT (CB-4, A8, B-1L)
INITIALS/DATE
* PDIL GR 3 COMPUTER (CB-4, A8, B-3U)
 
* PPDIL GR 3 COMPUTER (CB-4, A8, B-4U)
/    6.2 Reactor is critical.  /
* VLPM ALARM OR TROUBLE (CB-1,2,3, A6, D-3)
6.3 No other test is in progress which c ould potentially affect this test, or if this test were performed, coul d have an effect on that test.
R13
  /    6.4 A prejob briefing has been c onducted prior to the start of this test.    /
6.5 Primary Synchro CEA Position Indicating System is operable.
[AR 14801]
    /    6.6 Shift Manager authorizes performance of this test:
 
Shift Manager  Date/Time  /
: 7. PROCEDURE NOTE:  Step 7.1 can be performed at anytime and repeated as necessary.
 
7.1 IF this Surveillance Test is tu rned over, a prejob briefing must be conducted prior to the cont inuation of this test.
 
/    CAUTION [AR 04922]
When the Reactor is critical, this Surv eillance Test must be performed within the specified Technical Specification time interval regardless of rod
 
configuration or use.


7.2 IF not in an All-Rods-Out configuration, THEN contact the Reactor Engineer prior to commencing this test for guidance to ensure the requirements of Technical Specification 3.2, Table 3-5, Item 2 are met.
FORT CALHOUN STATION                                                              OP-ST-CEA-0003 SURVEILLANCE TEST                                                                    PAGE 4 OF 9 5.15 The following DCS alarms may occur during the performance of this Surveillance Test:
[AR 04922]
* ROD BLOCK
* PPDIL
* PDIL
* ISH
: 6. PREREQUISITES                                                                INITIALS/DATE 6.1  Procedure Revision Verification:
Revision No.      13                                                          JEK  / 3/31/09 6.2  Reactor is critical.                                                          JEK  / 3/31/09 6.3  No other test is in progress which could potentially affect this test, or if JEK      3/31/09 this test were performed, could have an effect on that test.                        /
6.4  A prejob briefing has been conducted prior to the start of this test.          JEK  / 3/31/09 6.5  Primary Synchro CEA Position Indicating System is operable.
[AR 14801]                                                                      JEK / 3/31/09 6.6  Shift Manager authorizes performance of this test:
Shift Manager        SHIFT MANAGER                              Date/Time 3/31/09 / 0730
: 7. PROCEDURE NOTE: Step 7.1 can be performed at anytime and repeated as necessary.
7.1  IF this Surveillance Test is turned over, a prejob briefing must be            N/A conducted prior to the continuation of this test.                                    /
CAUTION [AR 04922]
When the Reactor is critical, this Surveillance Test must be performed within the specified Technical Specification time interval regardless of rod configuration or use.
7.2 IF not in an All-Rods-Out configuration, THEN contact the Reactor Engineer prior to commencing this test for guidance to ensure the requirements of Technical Specification 3.2, Table 3-5, Item 2 are met. [AR 04922]
N/A
[AR 08779]
[AR 08779]
R13


FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 5 OF 9 R13 7.3 Record Initial Position of all CEAs on Attachment 1.     7.4 Rotate the Mode Select or Switch (M/M) to the Manual Individual (M/I) position.
FORT CALHOUN STATION                                                             OP-ST-CEA-0003 SURVEILLANCE TEST                                                                   PAGE 5 OF 9 7.3     Record Initial Position of all CEAs on Attachment 1.
7.5 Rotate the Group Selector Switch (M/G) to the Group containing the CEA to be moved.
7.4     Rotate the Mode Selector Switch (M/M) to the Manual Individual (M/I) position.
7.6 If available, verify on SCEAPIS (DCS) display CEA_ALL that the group button is DARK GREY for the group selected.
7.5     Rotate the Group Selector Switch (M/G) to the Group containing the CEA to be moved.
7.7 Rotate the Rod Selector Switch to the CEA to be moved.
7.6     If available, verify on SCEAPIS (DCS) display CEA_ALL that the group button is DARK GREY for the group selected.
NOTE: If Group 4 CEAs are being used for ASI control, movement of 6 inches in a single direction may be credited. The retu rned to position may not necessarily be the initial position. Note the time of Group 4 movement for ASI control on the Comment Sheet if applicable.  
7.7     Rotate the Rod Selector Switch to the CEA to be moved.
NOTE: If Group 4 CEAs are being used for ASI control, movement of 6 inches in a single direction may be credited. The returned to position may not necessarily be the initial position. Note the time of Group 4 movement for ASI control on the Comment Sheet if applicable.
7.8    Insert or withdraw the CEA, as applicable, a minimum of six (6) inches, THEN return the CEA to its Initial Position.
NOTE: Step 7.9 may be completed after all CEAs within a Group have been exercised, after all CEAs have been exercised, OR after exercising each CEA.
7.9    Record Inserted/Withdrawn To AND Return To information on Test Data Sheet, THEN initial Attachment 1.
7.10    Repeat Steps 7.5 through 7.9 for all CEAs listed on Attachment 1.
7.11    Rotate Mode Selector Switch (M/M) to the OFF position.
7.12    Independently verify each CEA returned to its initial position listed on Attachment 1.
Ind Verif Completed By:                                                            Date/Time        /
: 8.      RESTORATION 8.1    Shift Manager notified this test is completed:
Shift Manager                                                    Date/Time        /
: 9.      ACCEPTANCE CRITERIA 9.1    All CEAs have been moved a minimum of six (6) inches.
R13


7.8 Insert or withdraw the CEA, as applicable, a minimum of six (6) inches, THEN return the CEA to its Initial Position.  
FORT CALHOUN STATION                                                      OP-ST-CEA-0003 SURVEILLANCE TEST                                                              PAGE 6 OF 9
: 10. TEST RECORD 10.1 This entire procedure.
: 11. REVIEW NOTE: The Reactor Engineer shall be notified within 24 hours of the completion of this test of any unexpected results.
11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours of completion of this test.
Evaluated by                                                Date/Time          /
STA Reviewed by                                                Date/Time          /
Shift Manager R13


NOTE:  Step 7.9 may be completed afte r all CEAs within a Group have been exercised, after all CEAs have been exercised, OR after exercising each CEA.  
FORT CALHOUN STATION                                                    OP-ST-CEA-0003 SURVEILLANCE TEST                                                          PAGE 7 OF 9 Attachment 1 - CEA Partial Movement Check Test Data Sheet Initial      Inserted/                          Ind Verif CEA                              Returned to Position      Withdrawn                  Initials  Initials      Remarks No.                             (Inches)
(inches)        (inches) 30 31 32 33 34 35 36 37 14 15 16 17 6
8 10 12 22 23 24 25 26 27 28 29 2
R13


7.9 Record Inserted/Withdrawn To AND Return To information on Test Data Sheet, THEN initial Attachment 1.
FORT CALHOUN STATION                                                        OP-ST-CEA-0003 SURVEILLANCE TEST                                                              PAGE 8 OF 9 Attachment 1 - CEA Partial Movement Check Test Data Sheet Initial      Inserted/                         Ind Verif CEA                              Returned to Position    Withdrawn                 Initials  Initials          Remarks No.                              (Inches)
(inches)        (inches) 3 4
5 38 39 40 41 1
Completed By:                                                      Date/Time        /
R13


7.10 Repeat Steps 7.5 through 7.9 for all CEAs listed on Attachment 1.
FORT CALHOUN STATION              OP-ST-CEA-0003 SURVEILLANCE TEST                    PAGE 9 OF 9 Comment Sheet R13
7.11 Rotate Mode Selector Switch (M/M) to the OFF position.
7.12 Independently verify each CEA returned to its initial position listed on  .
Ind Verif  Completed By:  Date/Time  /
: 8. RESTORATION


8.1 Shift Manager notified this test is completed:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header Location:            Simulator Approximate Time:    12 minutes          Actual Time: _________________
Reference(s):  K/A# 004000 A4.08 AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."
Handout(s):    AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."
Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 3/23/09 Page 1 of 7


Shift Manager  Date/Time  /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header Operators Name: _____________________ Employee # ______________
: 9. ACCEPTANCE CRITERIA
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:           None Safety Considerations:
Comments:
Page 2 of 7


9.1 All CEAs have been moved a minimum of six (6) inches.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header TASK                  The candidate established Charging flow to the RCS STANDARD:            using the Loop 2A High Pressure Safety Injection (HPSI) header following the identification of a leak in the charging line.
INITIAL              The plant is operating at full power. AOP-33 has been CONDITIONS:          entered due to a leak in the charging header. Charging and letdown have been isolated and the leak has stopped.
INITIATING CUE:      The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop 2A injection valve, HCV-318, per AOP-33, Attachment B.
Page 3 of 7


FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 6 OF 9 R13 10. TEST RECORD 10.1 This entire procedure.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Close CH-194, "CHARGING                Direct EONA to close CH-194.
: 11. REVIEW NOTE:  The Reactor Engineer shall be notified wit hin 24 hours of the completion of this test of any unexpected results.
PUMPS CH-1A/B/C DISCHARGE HEADER                      [ SAT ]        [ UNSAT ]
CONTAINMENT OUTBOARD ISOLATION VALVE" (Room                CUE: EONA reports that CH-13).                                  194 is closed.
2              Open HCV-308, Charging                CB-1,2,3 Pump HPSI Header Isolation            Hold HCV-308 Control Switch Valve.                                in OPEN until GREEN light goes OFF. Then Release and allow it to return to NORM.
Verify RED light ON and GREEN light OFF.
[ SAT ]        [ UNSAT ]
3              Ensure HCV-2987, HPSI                  AI-30A Header Isolation Valve, is            RED light is ON and GREEN open.                                  light is OFF.
[ SAT ]        [ UNSAT ]
4              Ensure HCV-307, HPSI Header AI-30B Isolation Valve, is open.              RED light ON.
GREEN light OFF.
[ SAT ]        [ UNSAT ]
5              Ensure HCV-305, SI-2A and              AI-30B SI-2C Discharge Cross-                RED light ON.
Connect Valve, is open.                GREEN light OFF.
[ SAT ]        [ UNSAT ]
Page 4 of 7


11.1 Test data shall be evaluated by the ST A and reviewed by the Shift Manager for acceptability within 24 hours of completion of this test.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header STEP                    ELEMENT                              STANDARD 6              Ensure HCV-304, SI-2B and              AI-30A SI-2C Discharge Cross-                RED light ON.
Evaluated by  Date/Time  /
Connect Valve, is open.                GREEN light OFF.
STA  Reviewed by  Date/Time  /
[ SAT ]      [ UNSAT ]
Shift Manager
7              Ensure HCV-306, HPSI Header AI-30A Isolation Valve, is open.             RED light ON.
GREEN light OFF.
[ SAT ]      [ UNSAT ]
8              Close the SI Tank Leakage              AI-30A Cooler Pressure Control Valves        Place Control Switch in on the loop in which the HPSI          MANUAL valve(s) will be opened,              If required, adjust PCV-2949 PCV-2949.                              Controller such that needle indicates 100% (full right).
GREEN light ON.
RED light OFF.
[ SAT ]      [ UNSAT ]
9              Open HCV-318 (Loop 2A).                AI-30B HCV-318 Control Switch to OPEN. RED light ON, GREEN light OFF.
(Note: may also PULLOUT switch, but not required)
[ SAT ]      [ UNSAT ]
Page 5 of 7


FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 7 OF 9 R13 Attachment 1 - CEA Partial Movement Check Test Data Sheet CEA No. Initial Position (inches) Inserted/
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header STEP                    ELEMENT                              STANDARD 10              Ensure a charging pump                CB-1,2,3 suction source is available.          Ensure LCV-218-2 open RED light ON and VCT level indicated on chart or indicator.
Withdrawn (inches) Returned to (Inches) Initials Ind Verif Initials Remarks 30      31      32      33      34      35      36      37      14      15      16      17      6      8      10      12      22      23      24      25      26      27      28      29      2 FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 8 OF 9 R13 Attachment 1 - CEA Partial Movement Check Test Data Sheet CEA No. Initial Position (inches) Inserted/
OR Ensure LCV-218-3 open RED light ON.
Withdrawn (inches) Returned to (Inches) Initials Ind Verif Initials Remarks 3      4      5      38      39      40      41      1       
[ SAT ]        [ UNSAT ]
11              Operate any available                CB-1,2,3 Charging Pumps as necessary          Start at least one charging to maintain PZR level within          pump, CH-1A/B/C by taking 4% of programmed level.              Control switch out of Pull-To-Lock, taking to AFTER-START and verifying RED light ON.
[ SAT ]        [ UNSAT ]
Termination Criteria:    A charging pump is supplying water to the RCS via the HPSI header.
Page 6 of 7


Completed By:  Date/Time  /
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 INITIAL          The plant is operating at full power. AOP-33 has been CONDITIONS:      entered due to a leak in the charging header. Charging and letdown have been isolated and the leak has stopped.
INITIATING CUE:  The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop 2A injection valve, HCV-318, per AOP-33, Attachment B.
Page 7 of 7


FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 9 OF 9 R13 Comment Sheet
AOP-33 Page 21 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS                                    CONTINGENCY ACTIONS NOTE Charging through the HPSI Header will result in the addition of approximately 100 gallons of water at refueling boron concentration into the RCS.
: 1. Close CH-194, "CHARGING PUMPS CH-1A/B/C DISCHARGE HEADER CONTAINMENT OUTBOARD ISOLATION VALVE" (Room 13).
: 2. Open HCV-308, Charging Pump HPSI Header Isolation Valve.
: 3. Ensure ALL of the following valves are open:
* HCV-2987, HPSI Header Isolation Valve
* HCV-307, HPSI Header Isolation Valve
* HCV-305, SI-2A and SI-2C Discharge Cross-Connect Valve
* HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve
* HCV-306, HPSI Header Isolation Valve R7


AOP-33 Page 21 of 52 R7 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS   NOTE  Charging through the HPSI Header will resu lt in the addition of approximately 100 gallons of water at refueling boron concentration into the RCS. 1. Close CH-194, "CHARGING PUMPS CH-1A/B/C DISCHARGE HEADER
AOP-33 Page 22 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS                                     CONTINGENCY ACTIONS
: 4. Close the SI Tank Leakage Cooler Pressure Control Valves on the loop in which the HPSI valve(s) will be opened in Step 5:
Loop 1B
* PCV-2909 Loop 1A
* PCV-2929 Loop 2A
* PCV-2949 Loop 2B
* PCV-2969
: 5. Open at least one of the following HPSI Loop Injection Valves:
* HCV-312 (Loop 1B)
* HCV-315 (Loop 1A)
* HCV-318 (Loop 2A)
* HCV-321 (Loop 2B)
R7


CONTAINMENT OUTBOARD
AOP-33 Page 23 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS                                      CONTINGENCY ACTIONS NOTE Using the SIRWT as a suction source will inject water with refueling boron concentration into the RCS.
: 6. Ensure a charging pump suction source is available.
NOTE Charging flow can be verified on the associated HPSI flow indicator(s) for the HPSI Loop Valve(s) in use, or on ERF (Page 323).
: 7. Operate any available Charging Pumps as necessary to maintain PZR level within 4% of programmed level.
: 8. IF Charging Header repairs are possible      8.1  IF Charging Header repairs are NOT with the Plant in its current operating            possible with the Plant in its current mode,                                              operating mode, THEN direct Maintenance to repair leak.            THEN place the Plant in desired mode PER ONE of the following procedures:
* AOP-05, Emergency Shutdown
* OP-4, Load Change and Normal Power Operations R7


ISOLATION VALVE" (Room 13).
AOP-33 Page 24 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS                                      CONTINGENCY ACTIONS
: 2. Open HCV-308, Charging Pump HPSI Header Isolation Valve.
: 9. WHEN the Charging Header has been repaired, THEN return the CVCS to normal operation PER OI-CH-1, Startup of Charging and Letdown.
: 3. Ensure ALL of the following valves are open:  HCV-2987, HPSI Header Isolation Valve  HCV-307, HPSI Header Isolation Valve  HCV-305, SI-2A and SI-2C Discharge Cross-Connect Valve  HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve  HCV-306, HPSI Header Isolation Valve AOP-33 Page 22 of 52 R7 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS    4. Close the SI Tank Leakage Cooler Pressure Control Valves on the loop in
: 10. WHEN the CVCS has been returned to normal, THEN IMPLEMENT Attachment E, HPSI Piping Flush, to flush all safety injection piping used in this procedure.
: 11. WHEN HPSI piping flush is completed, THEN GO TO Section 5.0, Exit Conditions.
End of Attachment B R7


which the HPSI valve(s) will be opened
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection Location:            Simulator Approximate Time:    15 minutes          Actual Time: _________________
Reference(s):  K/A# 006000 A1.11 EOP/AOP Attachment 9, "SIMULTANEOUS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" Handout(s):    EOP/AOP Attachment 9, "SIMULTANEOUS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" Time Critical: YES - 30 Minutes Alternate Path:  YES JPM Prepared by:    Jerry Koske                                  Date: 3/25/09 Page 1 of 10


in Step 5:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection Operators Name: _____________________ Employee # ______________
Loop 1B  PCV-2909 Loop 1A  PCV-2929 Loop 2A  PCV-2949 Loop 2B  PCV-2969
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
: 5. Open at least one of the following HPSI Loop Injection Valves:
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
HCV-312 (Loop 1B) HCV-315 (Loop 1A) HCV-318 (Loop 2A)  HCV-321 (Loop 2B)  
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:        None Comments:                    Time Critical (30 Minutes), Alternate Path Page 2 of 10


AOP-33 Page 23 of 52 R7 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS    NOTE  Using the SIRWT as a suction source will in ject water with refueling boron concentration into the RCS. 6. Ensure a charging pump suction source is available.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection TASK                The candidate began to initiate Simultaneous Hot and STANDARD:          Cold Leg injection 5.5 hours after a LOCA occurred using EOP/AOP Attachment 9, SIMULTANEOUS HOT AND COLD LEG INJECTION. Upon recognizing that HCV-305 could not be closed, the Candidate transitioned to EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR, and successfully provided sufficient flow to both a RCS hot leg and the cold legs.
NOTE  Charging flow can be verified on the associat ed HPSI flow indicator(s) for the HPSI Loop Valve(s) in use, or on ERF (Page 323).
INITIAL                    A large LOCA occurred 5.5 hours ago.
: 7. Operate any available Charging Pumps as necessary to maintain PZR level
CONDITIONS:                A RAS (Recirculation Actuation Signal) was received 4 hours ago.
HPSI pumps, SI-2A and SI-2B, are operating.
There are no signs of containment sump blockage.
All systems are operating as expected.
INITIATING CUE:    ***** TIME CRITICAL *****
The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection in accordance with EOP/AOP Attachment 9.
Page 3 of 10


within 4% of programmed level.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection Critical Steps shown in gray STEP                  ELEMENT                              STANDARD Note to Examiner:
: 8. IF Charging Header repairs are possible with the Plant in its current operating
Do Not provide Attachment 10 to candidate until he makes the transition in JPM step 9.
: mode, THEN direct Maintenance to repair leak.
1              Read Cautions on page 44 of           Reads both Cautions.
8.1 IF Charging Header repairs are NOT possible with the Plant in its current
EOP/AOP Attachments.
[ SAT ]      [ UNSAT ]
2              Verify conditions in step 1.          Verifies:
A LOCA exists.
RCS Pressure is less than 140 psia 5.5 hours have elapsed.
[ SAT ]      [ UNSAT ]
3              Open at least one of the              CB-1,2,3 Charging Pumps HPSI Header Isolation Valves:                      At least one valves control HCV-308.                        switch to OPEN with RED light HCV-2988.                        ON.
[ SAT ]      [ UNSAT ]
4              Open at least one of the               CB-1,2,3 following PZR Auxiliary Spray Isolation Valves:                      At least one valves control
* HCV-240.                            switch to OPEN with RED light
* HCV-249.                            ON.
[ SAT ]      [ UNSAT ]
Page 4 of 10


operating mode,
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP                      ELEMENT                              STANDARD NOTE: A rapid loss of instrument air pressure occurs due to the rupture of Auxiliary Building air riser "AS."
CUE: If candidate addresses loss of instrument air, inform him that another Operator has responded to the loss of Instrument Air.
5              If only one HPSI Pump is                AI-30A/B available, GO TO Attachment
: 11.                                    Verifies that 2 HPSI Pumps are operating and stays in Attachment 9
[ SAT ]        [ UNSAT ]
6              Read Caution on page 45.                Reads Caution
[ SAT ]        [ UNSAT ]
7              Ensure ALL of the following            CB-1,2,3 Charging Isolation Valves are          For each valve:
closed:                                GREEN light ON.
* HCV-238.                              RED light OFF.
* HCV-239.                              Determines that HCV-247 and
* HCV-247.                              HCV-248 are closed but that
* HCV-248.                              HCV-238 and HCV-239 are open.
Does not go to attachment 11 because HCV-247 and HCV-248 are closed.
[ SAT ]        [ UNSAT ]
Page 5 of 10


THEN place the Plant in desired mode PER ONE of the following procedures:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP                    ELEMENT                              STANDARD 8              IF ANY of the following HPSI          Reads step 6.
AOP-05, Emergency Shutdown OP-4, Load Change and Normal Power Operations
Discharge Cross-Connect Valves can NOT be closed              Note: May determine that because of a loss of Instrument        instrument air is not Air:                                  available and immediately HCV-305                        transition to EOP/AOP HCV-306                        Attachment 10.
THEN Go To Attachment 10 9              IF HPSI Pump, SI-2A, is                AI-30B operating,THEN close HCV-             Key Switch to CLOSE.
305, SI-2A and SI-2C                  GREEN light ON.
Discharge Cross-Connect                RED light OFF.
Valve.
Determines that HCV-305 will not close due to a loss of instrument air.
[ SAT ]      [ UNSAT ]
10              Transitions to EOP/AOP                Transitions to EOP/AOP Attachment 10.                        Attachment 10.
[ SAT ]      [ UNSAT ]
NOTE to Examiner: Provide a copy of EOP/AOP Attachment 10 to Candidate.
11              Reviews Cautions.                      Reads both Cautions.
[ SAT ]      [ UNSAT ]
Page 6 of 10


AOP-33 Page 24 of 52 R7 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS    9. WHEN the Charging Header has been
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP                      ELEMENT                              STANDARD 12              Verify conditions in step 1.            Verifies:
A LOCA exists.
RCS Pressure is less than 140 psia 5.5 hours have elapsed.
[ SAT ]        [ UNSAT ]
13              Verify open at least one of the        CB-1,2,3 Charging Pumps HPSI Header Isolation Valves:                      At least one valves RED light HCV-308.                          ON.
HCV-2988.
[ SAT ]        [ UNSAT ]
14              Verify open at least one of the         CB-1,2,3 following PZR Auxiliary Spray Isolation Valves:                      At least one valves RED light
* HCV-240.                              ON.
* HCV-249.
[ SAT ]        [ UNSAT ]
15              If only one HPSI Pump is                AI-30A/B available, GO TO Attachment
: 11.                                    Verifies that 2 HPSI Pumps are operating and stays in Attachment 10
[ SAT ]        [ UNSAT ]
16              Read Caution on page 49.                Reads Caution
[ SAT ]        [ UNSAT ]
Page 7 of 10


repaired,
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP                    ELEMENT                              STANDARD 17              Ensure ALL of the following            CB-1,2,3 Charging Isolation Valves are          For each valve:
closed:                                GREEN light ON.
* HCV-238.                            RED light OFF.
* HCV-239.                            Determines that HCV-247 and
* HCV-247.                            HCV-248 are closed but that
* HCV-248.                            HCV-238 and HCV-239 are open.
Stays in Attachment 10
[ SAT ]      [ UNSAT ]
18              Close ALL of the following            AI-30A/B HPSI Loop Injection Valves:
* HCV-315.                            Control Switches to CLOSE
* HCV-318.                            (pull out, counter-clockwise)
* HCV-312.                            until GREEN lights ON.
* HCV-321.                            RED light OFF.
[ SAT ]      [ UNSAT ]
19              Close HCV-2987, HPSI Header            AI-30A/B Isolation Valve.
Control Switch to CLOSE.
GREEN light ON.
RED light OFF.
[ SAT ]      [ UNSAT ]
Page 8 of 10


THEN return the CVCS to normal operation PER OI-CH-1, Startup of Charging and Letdown.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP                      ELEMENT                              STANDARD 20              IF evidence of containment              AI-30A/B sump blockage does NOT exist, THEN throttle the HPSI          Throttle one or more of the Loop Injection Valves until ALL        following valves:
: 10. WHEN the CVCS has been returned to
of the following criteria are                HCV-314.
satisfied:                                  HCV-317.
Charging flow is greater              HCV-311.
than180 gpm (FIA-236).              HCV-320.
Total HPSI flow is              Verify greater than 200 gpm greater than 200 gpm.          total flow on FI-313, FI-316, FI-319 and FI-322.
CB-1,2,3 Verify greater than 180 gpm flow on FIA-236.
Note: Plant computer may also be used to verify flows.
[ SAT ]      [ UNSAT ]
Termination Criteria:    Simultaneous Hot and Cold Leg Injection has been established with greater than 180 gpm flow through charging (Hot Leg) and greater than 200 gpm flow through the HPSI Header (Cold Legs).
Page 9 of 10


normal, THEN IMPLEMENT Attachment E, HPSI Piping Flush , to flush all safety injection piping used in this procedure.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 INITIAL                  A large LOCA occurred 5.5 hours ago.
: 11. WHEN HPSI piping flush is completed, 
CONDITIONS:              A RAS (Recirculation Actuation Signal) was received 4 hours ago.
HPSI pumps, SI-2A and SI-2B, are operating.
There are no signs of containment sump blockage.
All systems are operating as expected.
INITIATING CUE:  ***** TIME CRITICAL *****
The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection in accordance with EOP/AOP Attachment 9.
Page 10 of 10


THEN GO TO Section 5.0, Exit Conditions.      End of Attachment B
EOP/AOP ATTACHMENTS Page 44 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS                                           CONTINGENCY ACTIONS
 
  ***************************************************************************************************
EOP/AOP ATTACHMENTS Page 44 of 168 R26 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS   ***************************************************************************************************
CAUTIONS
CAUTIONS 1. Closing HPSI Loop Valves may cause a reduction in RCS pressure and subcooling.
: 1. Closing HPSI Loop Valves may cause a reduction in RCS pressure and subcooling.
: 2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.  
: 2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.
***************************************************************************************************
  ***************************************************************************************************
: 1. Verify that ALL of the following criteria are satisfied:
: 1. Verify that ALL of the following criteria        1.1  IF all of the criteria are NOT satisfied, are satisfied:                                         THEN continue efforts to initiate SDC.
A LOCA exists RCS pressure is less than 140 psia Five and one-half hours may elapse before SDC can be established 1.1 IF all of the criteria are NOT satisfied, THEN continue efforts to initiate SDC.
* A LOCA exists
* RCS pressure is less than 140 psia
* Five and one-half hours may elapse before SDC can be established
: 2. Open at least one of the Charging Pumps HPSI Header Isolation Valves:
: 2. Open at least one of the Charging Pumps HPSI Header Isolation Valves:
HCV-308 HCV-2988  
* HCV-308
* HCV-2988 R26


EOP/AOP ATTACHMENTS Page 45 of 168 R26 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS   3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
EOP/AOP ATTACHMENTS Page 45 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS                                           CONTINGENCY ACTIONS
HCV-240 HCV-249
: 3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
: 4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.     ***************************************************************************************************
* HCV-240
CAUTION Closing HCV-247 isolates a CVCS relief valve.  
* HCV-249
****************************************************************************************************
: 4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.
: 5. Ensure ALL of the following Charging Isolation Valves are closed:
  ***************************************************************************************************
HCV-238 HCV-239  HCV-247  HCV-248 4.1 IF ANY of the following Charging Isolation Valves are open:
CAUTION Closing HCV-247 isolates a CVCS relief valve.
HCV-247 HCV-248 THEN GO TO Attachment 11, Alternate Hot Leg Injection.
  ****************************************************************************************************
EOP/AOP ATTACHMENTS Page 46 of 168 R26 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS    6. IF ANY of the following HPSI Discharge Cross-Connect Valves can
: 5. Ensure ALL of the following Charging              4.1  IF ANY of the following Charging Isolation Valves are closed:                            Isolation Valves are open:
* HCV-238
* HCV-247
* HCV-239
* HCV-248
* HCV-247
* HCV-248                                       THEN GO TO Attachment 11, Alternate Hot Leg Injection.
R26


NOT be closed because of a loss of Instrument Air:
EOP/AOP ATTACHMENTS Page 46 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS                                  CONTINGENCY ACTIONS
HCV-305 HCV-304 THEN GO TO Attachment 10, Simultaneous Hot and Cold Leg Injection without Instrument Air.
: 6. IF ANY of the following HPSI Discharge Cross-Connect Valves can NOT be closed because of a loss of Instrument Air:
: 7. IF HPSI Pump, SI-2A is operating, THEN close HCV-305, SI-2A and SI-2C Discharge Cross-Connect Valve.
* HCV-305
7.1 IF HPSI Pump, SI-2A is NOT operating, 
* HCV-304 THEN GO TO Attachment 10, Simultaneous Hot and Cold Leg Injection without Instrument Air.
 
: 7. IF HPSI Pump, SI-2A is operating,         7.1  IF HPSI Pump, SI-2A is NOT THEN close HCV-305, SI-2A and                   operating, SI-2C Discharge Cross-Connect Valve.             THEN close HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve.
THEN close HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve.
: 8. Close ALL of the following HPSI Loop Injection Valves:
: 8. Close ALL of the following HPSI Loop Injection Valves:
HCV-315 HCV-318 HCV-312 HCV-321
* HCV-315
: 9. Close HCV-2987, HPSI Header Isolation Valve.  
* HCV-318
* HCV-312
* HCV-321
: 9. Close HCV-2987, HPSI Header Isolation Valve.
R26


EOP/AOP ATTACHMENTS Page 47 of 168 R26 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS   10. IF evidence of containment sump blockage does NOT exist, THEN throttle the HPSI Loop Injection Valves until ALL of the following criteria are satisfied:
EOP/AOP ATTACHMENTS Page 47 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS                                   CONTINGENCY ACTIONS
Charging flow is greater than 80 gpm (FIA-236)
: 10. IF evidence of containment sump            10.1 IF evidence of containment sump blockage does NOT exist,                         blockage does NOT exist, THEN throttle the HPSI Loop Injection             AND all of the criteria are NOT Valves until ALL of the following                 satisfied:
Total HPSI flow is greater than 200 gpm 10.1 IF evidence of containment sump blockage does NOT exist, AND all of the criteria are NOT satisfied:
criteria are satisfied:                           THEN GO TO Attachment 11, Alternate Hot leg Injection.
* Charging flow is greater than 80 gpm (FIA-236) 10.2 IF evidence of containment sump
* Total HPSI flow is greater than 200 gpm                                       blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time.
End of Attachment 9 R26


THEN GO TO Attachment 11, Alternate Hot leg Injection. 10.2 IF evidence of containment sump blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time. End of Attachment 9
EOP/AOP ATTACHMENTS Page 48 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS                                            CONTINGENCY ACTIONS
  ***************************************************************************************************
CAUTIONS
: 1. Closing HPSI Loop Valves may cause a reduction in RCS pressure and subcooling.
: 2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.
  ***************************************************************************************************
: 1. Verify that ALL of the following criteria        1.1  IF all of the criteria are NOT satisfied, are satisfied:                                          THEN continue efforts to initiate SDC.
* A LOCA exists
* RCS pressure is less than 140 psia
* Five and one-half hours may elapse before SDC can be established
: 2. Open at least one of the Charging Pump HPSI Header Isolation Valves:
* HCV-308
* HCV-2988 R26


EOP/AOP ATTACHMENTS Page 48 of 168 R26 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS   ***************************************************************************************************
EOP/AOP ATTACHMENTS Page 49 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS                                           CONTINGENCY ACTIONS
CAUTIONS  1. Closing HPSI Loop Valves may cause a reduction in RCS pressure and subcooling.
: 3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
: 2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.  
* HCV-240
***************************************************************************************************
* HCV-249
: 1. Verify that ALL of the following criteria are satisfied:
: 4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.
A LOCA exists RCS pressure is less than 140 psia Five and one-half hours may elapse before SDC can be established 1.1 IF all of the criteria are NOT satisfied, THEN continue efforts to initiate SDC.
  ***************************************************************************************************
: 2. Open at least one of the Charging Pump HPSI Header Isolation Valves:
CAUTION Closing HCV-247 isolates a CVCS relief valve.
HCV-308  HCV-2988
  ****************************************************************************************************
: 5. Ensure ALL of the following Charging              4.1   IF ANY of the following Charging Isolation Valves are closed:                           Isolation Valves are open:
* HCV-238
* HCV-247
* HCV-239
* HCV-248
* HCV-247
* HCV-248                                              THEN GO TO Attachment 11, Alternate Hot Leg Injection.
R26


EOP/AOP ATTACHMENTS Page 49 of 168 R26 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS   3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
EOP/AOP ATTACHMENTS Page 50 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS                                   CONTINGENCY ACTIONS
HCV-240  HCV-249
: 6. Close ALL of the following HPSI Loop Injection Valves:
: 4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.      ***************************************************************************************************
* HCV-315
CAUTION  Closing HCV-247 isolates a CVCS relief valve.
* HCV-318
****************************************************************************************************
* HCV-312
: 5. Ensure ALL of the following Charging Isolation Valves are closed:
* HCV-321
HCV-238  HCV-239  HCV-247  HCV-248  4.1 IF ANY of the following Charging Isolation Valves are open:
HCV-247  HCV-248  THEN GO TO Attachment 11, Alternate Hot Leg Injection.
EOP/AOP ATTACHMENTS Page 50 of 168 R26 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS    6. Close ALL of the following HPSI Loop Injection Valves:
HCV-315 HCV-318 HCV-312 HCV-321
: 7. Close HCV-2987, HPSI Header Isolation Valve.
: 7. Close HCV-2987, HPSI Header Isolation Valve.
: 8. IF evidence of containment sump blockage does NOT exist, THEN throttle the HPSI Loop Injection Valves until ALL of the following criteria are satisfied:
: 8. IF evidence of containment sump           8.1  IF evidence of containment sump blockage does NOT exist,                        blockage does NOT exist, THEN throttle the HPSI Loop Injection           AND all of the criteria are NOT Valves until ALL of the following               satisfied:
Charging flow is greater than 180 gpm (FIA-236)
criteria are satisfied:                         THEN GO TO Attachment 11, Alternate Hot leg Injection.
Total HPSI flow is greater than 200 gpm 8.1 IF evidence of containment sump blockage does NOT exist, AND all of the criteria are NOT satisfied:
* Charging flow is greater than 180 gpm (FIA-236) 8.2  IF evidence of containment sump
THEN GO TO Attachment 11, Alternate Hot leg Injection.
* Total HPSI flow is greater than 200 gpm                                     blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time.
8.2 IF evidence of containment sump blockage exists, 
End of Attachment 10 R26


THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time. End of Attachment 10
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump Location:            Simulator Approximate Time:    7 minutes            Actual Time: _________________
Reference(s):    K/A# 003000 A4.06 OI-RC-9, "REACTOR COOLANT PUMP OPERATION" Handout(s):      OI-RC-9, "REACTOR COOLANT PUMP OPERATION" Time Critical:  NO Alternate Path:  YES JPM Prepared by:    Jerry Koske                                  Date: 3/23/09 Page 1 of 8


C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 6 OF 66 R69 Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump Operators Name: _____________________ Employee # ______________
PREREQUISITES
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
()INITIALS NOTES1.Attachment 7 provides guidance for starting RCPs for sweeping steam generator tubes.2.Attachment 6 provides recovery gui dance from the possibility of a slug of water with reduced boron concentration in an idle RCS loop.1.Procedure Revision Verification Revision No.
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Date:
Reason, if unsatisfactory:
2.The Reactor is Shutdown (Mode 3, Mode 4 or Mode 5).
Tools & Equipment:            None Safety Considerations:        None Comments:                    Alternate Path Page 2 of 8
3.Communications have been established between the Control Room and locally at each Reactor Coolant Pump, as needed, prior to Reactor CoolantPump start.              4.Applicable sections of Checklist OI-RC-9-CL-A have been completed foreach RCP to be run.              5.A minimum Reactor Coolant System pr essure per TDB-III.7.a or TDB-III.7.d, RCS Pressure and Temperature Limits, has been established to ensure


adequate Reactor Coolant Pump Net Positive Suction Head (NPSH).              6.The Component Cooling Water System is in operation to each ReactorCoolant Pump to be run per OI-CC-1.              7.The Red Motor Heater Lights for each non-operating Reactor Coolant Pumpare energized.              8.The ERF Computer is operable per OI-ERFCS-1.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump TASK                The Candidate started Reactor Coolant Pump RC-3A in STANDARD:            accordance with OI-RC-9, "REACTOR COOLANT PUMP OPERATION." The Candidate then tripped the pump when the motor current did not fall below 425 amps within the time specified in the procedure.
9.If the RCP has been idle for a long outage OR for maintenance, a generalvisual inspection of the RCP should be performed prior to starting.              10.The Reactor Coolant Pump Motor upper and lower oil reservoirs are filled tolevels as specified in Tables 1 through 4.               11.Instrumentation and alarms associated with RCPs to be run are operable.
INITIAL                    The plant is in hot shutdown.
C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 7 OF 66  - Starting Reactor Coolant Pumps (Coupled)
CONDITIONS:                Reactor Coolant Pump, RC-3C, is running.
PREREQUISITES (continued)
RC-3A is scheduled to be started.
()INITIALS R6912.4.16 KV Buses for RCPs to be run (1A1, 1A2, 1A3 and 1A4) are energized.              13.RCPs to be operated are coupled per MM-RR-RC-0008.
The motor on RC-3A is cold.
There is no one in containment.
INITIATING CUE:      You are directed to place RC-3A in service in accordance with OI-RC-9, Attachment 1.
All prerequisites are met.
Page 3 of 8


PROCEDURE NOTE Controlled Bleedoff Flow can be establis hed within 24 hrs of starting the first RCP.1.Open all the following valves:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump Critical Steps shown in gray STEP                    ELEMENT                              STANDARD NOTE to Examiner:
!RC-308, RC-3A Reactor Coolant Pump Controlled Bleedoff Isolation Valve!RC-309, RC-3B Reactor Coolant Pump Controlled Bleedoff Isolation
Simulator Operator has inserted the seized rotor malfunction for RC-3A and has also failed the overcurrent relays for the pump's motor.
1               Read the note and cautions            Reads the Note and Cautions on page 8 of OI-RC-9
[ SAT ]      [ UNSAT ]
2                Setup ERF Display for RC-3A.          ERF Type [440] [DSP]
RC-3A Page displays.
[ SAT ]      [ UNSAT ]
3                Station operator to respond to        CUE: Operator is at AI-270.
vibration alarms.
[ SAT ]      [ UNSAT ]
4                Read Note                              Reads first note on page 9.
Determines it is not applicable.
[ SAT ]      [ UNSAT ]
5                Verify controlled Bleed-off flow.      ERF page 342 Verify positive bleed-off flow.
[ SAT ]      [ UNSAT ]
6                Read Note                              Reads second note on page 9.
Determines it is not applicable.
[ SAT ]      [ UNSAT ]
Page 4 of 8


Valve!RC-310, RC-3C Reactor Coolant Pump Controlled Bleedoff Isolation
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump STEP                      ELEMENT                              STANDARD 7                Ensure RCS Pressure and                Verifies RCS Pressure above RCP NPSH.                              225 psia.
Use Figure TDB III.7.a to verify NPSH.
[ SAT ]      [ UNSAT ]
8                OI-RC-9, Attachment 1 steps 6          Records N/A for steps and 7                                  because a RCP is running.
[ SAT ]      [ UNSAT ]
9                Read Note                              Reads note near top of page 10
[ SAT ]      [ UNSAT ]
10              Ensure 86/RC-3A reset.                CB-1/2/3 86/RC-3A AMBER light ON.
[ SAT ]      [ UNSAT ]
11              Verify RCP Reverse rotation is        CB-1/2/3 cleared.                              ANN A-6, A5 is clear.
[ SAT ]      [ UNSAT ]
12              Read Note and Caution.                Reads note and caution near bottom of page 10
[ SAT ]      [ UNSAT ]
13              Start RC-3A oil lift pump.            CB-1/2/3 RC-3A-1 to AFTER START and RED light ON.
[ SAT ]      [ UNSAT ]
Page 5 of 8


Valve!RC-311, RC-3D Reactor Coolant Pump Controlled Bleedoff Isolation
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump STEP                      ELEMENT                              STANDARD 14              Verify ARRD oil flow for RC-3A.        ERF Page 342.
Note: Page 342 does not display ARRD oil flow for RC-3A.
[ SAT ]      [ UNSAT ]
CUE: The oil lift pump has been running for two minutes 15              Start RC-3A.                          CB-1/2/3 RC-3A CS in AFTER START and RED light ON.
[ SAT ]      [ UNSAT ]
16              Monitor Amps.                          CB-1/2/3 Determines that RC-3A's ammeter did not drop below 425 amps within 17 seconds.
[ SAT ]      [ UNSAT ]
17              Trip RC-3A                            CB-1/2/3 RC-3A CS in AFTER STOP and RED light OFF.
[ SAT ]      [ UNSAT ]
18              Monitor RC-3A motor amps.              CB-1/2/3 Verifies zero amps on ammeter.
[ SAT ]      [ UNSAT ]
Page 6 of 8


Valve C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 8 OF 66  - Starting Reactor Coolant Pumps (Coupled)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump STEP                    ELEMENT                              STANDARD 19              Report RC-3A problem to CRS          Reports RC-3A problem and need to manually trip pump to CRS
PROCEDURE (continued)
[ SAT ]      [ UNSAT ]
()INITIALS R69 NOTE High vibration alarms should be anticipated when starting RCPs.
Termination Criteria:   RC-3A has been tripped.
CAUTIONS1.IF the Steam Generator secondary si de temperature is greater than 30&deg;F above the RCS cold leg temperature, the effects of heat input from the secondary side, and the subsequent effects on heatup rate, must be evaluated/considered.2.If no RCP is running, and Tc is less than 350&deg;F, then a Reactor Coolant Pump shall NOT be started unless t he following conditions are satisfied:
Page 7 of 8
!Actual PZR level is less than or equal to 50% per TDB-III.1.a
!RCS pressure must be less than the "Maximum Pressure for First


Start RCP" (TDB-III.7.a curve 3)3.When starting a RCP, ensure RCS Pre ssure is greater than 225 psia to reduce the possibility of seal failure.4.Each RCP shall be monitored continuously on the ERF Computer throughout each starting period.2.Set up one ERF Display Screen to monitor the selected Reactor Coolant Pump and Motor parameters as follows:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 INITIAL                The plant is in hot shutdown.
!RC-3Apage 440
CONDITIONS:            Reactor Coolant Pump, RC-3C, is running.
!RC-3Bpage 441
RC-3A is scheduled to be started.
!RC-3Cpage 442
The motor on RC-3A is cold.
!RC-3Dpage 443 3.Station an operator at AI-270 (Room 57) to respond to vibration alarms. OI-RC-13 provides alarm response guidance.
There is no one in containment.
C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 9 OF 66  - Starting Reactor Coolant Pumps (Coupled)
INITIATING CUE:  You are directed to place RC-3A in service in accordance with OI-RC-9, Attachment 1.
PROCEDURE (continued)
All prerequisites are met.
()INITIALS R69 NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.4.Verify positive Controlled Bleedoff Flow for the selected RCP on ERF (page 342):
Page 8 of 8
!RC-3A!RC-3B!RC-3C!RC-3D NOTE When starting the first Reactor Coolant Pump, use TR-346, Shutdown Cooling Inlet/Outlet Temp, black pen LPSI Suction Temp indication to verify NPSH requirements are met.5.Ensure RCS Pressure is greater than 225 psia for RCP seal protection (ensures RCS Pressure is greater than minimum NPSH Pressure per


TDB-III.7.a and TDB-III.7.d, RCS Pressure and Temperature Limits).              6.Ensure RCS Pressure is less than the Maximum Pressure for First RCP Start curve per TDB-III.7.a, RCS Pressure and Temperature Limits.  (NA if an RCP is running).              7.Ensure actual corrected level per TD B-III.1.a Pressurizer level is less than50%.  (NA if an RCP is running).
FORT CALHOUN STATION                                                                 OI-RC-9 OPERATING INSTRUCTION                                                           PAGE 6 OF 66 C
C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 10 OF 66 - Starting Reactor Coolant Pumps (Coupled)
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued)
PREREQUISITES                                                                  (T) INITIALS NOTES
()INITIALS R69 NOTE IF Lockout Relays are NOT RESET, THEN Electrical Maintenance shall be contacted for an inspection of the affected relay(s).8.Ensure the Lockout Relay Switch for the selected RCP is in RESET and the Amber indicating light is ON:
: 1. Attachment 7 provides guidance for starting RCPs for sweeping steam generator tubes.
!86/RC-3A, Pump RC-3A Motor Current Diff
: 2. Attachment 6 provides recovery guidance from the possibility of a slug of water with reduced boron concentration in an idle RCS loop.
!86/RC-3B, Pump RC-3B Motor Current Diff
: 1. Procedure Revision Verification Revision No. 69          Date: 3/31/09                                          JEK
!86/RC-3C, Pump RC-3C Motor Current Diff
: 2. The Reactor is Shutdown (Mode 3, Mode 4 or Mode 5).                               JEK
!86/RC-3D, Pump RC-3D Motor Current Diff 9.For the selected RCP verify the following Annunciator is clear:
: 3. Communications have been established between the Control Room and locally at each Reactor Coolant Pump, as needed, prior to Reactor Coolant Pump start.                                                                      JEK
!RC-3A REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)
: 4. Applicable sections of Checklist OI-RC-9-CL-A have been completed for each RCP to be run.                                                               JEK
!RC-3B REACTOR COOLANT PUMP RC-3B REVERSE ROTATION (CB-1/2/3, A6, B5)
: 5. A minimum Reactor Coolant System pressure per TDB-III.7.a or TDB-III.7.d, RCS Pressure and Temperature Limits, has been established to ensure JEK adequate Reactor Coolant Pump Net Positive Suction Head (NPSH).
!RC-3C REACTOR COOLANT PUMP RC-3C REVERSE ROTATION (CB-1/2/3, A6, C5)
: 6. The Component Cooling Water System is in operation to each Reactor Coolant Pump to be run per OI-CC-1.                                              JEK
!RC-3D REACTOR COOLANT PUMP RC-3D REVERSE ROTATION (CB-1/2/3, A6, D5)
: 7. The Red Motor Heater Lights for each non-operating Reactor Coolant Pump are energized.                                                                    JEK
: 8. The ERF Computer is operable per OI-ERFCS-1.                                      JEK
: 9. If the RCP has been idle for a long outage OR for maintenance, a general visual inspection of the RCP should be performed prior to starting.                JEK
: 10. The Reactor Coolant Pump Motor upper and lower oil reservoirs are filled to levels as specified in Tables 1 through 4.                                        JEK
: 11. Instrumentation and alarms associated with RCPs to be run are operable.            JEK R69


NOTE The Oil Lift Pump shall not be run fo r longer than 10 minutes before starting the Reactor Coolant Pump.
FORT CALHOUN STATION                                                                  OI-RC-9 OPERATING INSTRUCTION                                                            PAGE 7 OF 66 C
CAUTIONPrior to starting a RCP when personnel are in Containment, the Containment Coordinator shall be notified, OR an announcement made on the Gaitronics.10.Place the Oil Lift Pump for the selected RCP to AFTER START:
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
!RC-3A-1, Oil Lift Pump
PREREQUISITES (continued)                                                        (T) INITIALS
!RC-3B-1, Oil Lift Pump
: 12. 4.16 KV Buses for RCPs to be run (1A1, 1A2, 1A3 and 1A4) are energized.           JEK
!RC-3C-1, Oil Lift Pump
: 13. RCPs to be operated are coupled per MM-RR-RC-0008.                                JEK PROCEDURE NOTE Controlled Bleedoff Flow can be established within 24 hrs of starting the first RCP.
!RC-3D-1, Oil Lift Pump
: 1. Open all the following valves:
    !   RC-308, RC-3A Reactor Coolant Pump Controlled Bleedoff Isolation Valve                                                                  O
    !   RC-309, RC-3B Reactor Coolant Pump Controlled Bleedoff Isolation Valve                                                                  O
    !   RC-310, RC-3C Reactor Coolant Pump Controlled Bleedoff Isolation Valve                                                                  O
    !   RC-311, RC-3D Reactor Coolant Pump Controlled Bleedoff Isolation Valve                                                                    O  JEK R69


C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 11 OF 66 - Starting Reactor Coolant Pumps (Coupled)
FORT CALHOUN STATION                                                               OI-RC-9 OPERATING INSTRUCTION                                                         PAGE 8 OF 66 C
PROCEDURE (continued)
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
()INITIALS R6911.Verify adequate ARRD Lube Oil Flow for the selected RCP. ERF indication shall read NORMAL: (ERF page 342)
PROCEDURE (continued)                                                         (T) INITIALS NOTE High vibration alarms should be anticipated when starting RCPs.
!RC-3AF3181
CAUTIONS
!RC-3BF3184
: 1. IF the Steam Generator secondary side temperature is greater than 30&deg;F above the RCS cold leg temperature, the effects of heat input from the secondary side, and the subsequent effects on heatup rate, must be evaluated/considered.
!RC-3CF3187
: 2. If no RCP is running, and Tc is less than 350&deg;F, then a Reactor Coolant Pump shall NOT be started unless the following conditions are satisfied:
!RC-3DF3190 12.Startup sequence for selected RCP:a.Run the oil lift pump for the selected RCP a minimum of two minutes.
    !   Actual PZR level is less than or equal to 50% per TDB-III.1.a
!RC-3A-1, Oil Lift Pump
    !   RCS pressure must be less than the Maximum Pressure for First Start RCP (TDB-III.7.a curve 3)
!RC-3B-1, Oil Lift Pump
: 3. When starting a RCP, ensure RCS Pressure is greater than 225 psia to reduce the possibility of seal failure.
!RC-3C-1, Oil Lift Pump
: 4. Each RCP shall be monitored continuously on the ERF Computer throughout each starting period.
!RC-3D-1, Oil Lift Pump b.Place the selected RCP control switch in AFTER START:
: 2. Set up one ERF Display Screen to monitor the selected Reactor Coolant Pump and Motor parameters as follows:
!RC-3A, RC Pump
    !   RC-3A     page 440
!RC-3B, RC Pump
    !   RC-3B     page 441
!RC-3C, RC Pump
    !   RC-3C     page 442
!RC-3D, RC Pump c.IF the Reactor Coolant Pump motor amps fail to drop below 425 amps within the time listed below, THEN place the control switch in AFTER STOP:
    !   RC-3D     page 443
!RC-3A - seventeen (17) seconds
: 3. Station an operator at AI-270 (Room 57) to respond to vibration alarms.
!RC-3B - nineteen (19) seconds
OI-RC-13 provides alarm response guidance.                                    JEK R69
!RC-3C - seventeen (17) seconds
!RC-3D - seventeen (17) seconds


C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 12 OF 66 - Starting Reactor Coolant Pumps (Coupled)
FORT CALHOUN STATION                                                                   OI-RC-9 OPERATING INSTRUCTION                                                             PAGE 9 OF 66 C
PROCEDURE (continued)
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
()INITIALS R6913.Verify the following for the selected RCP:a.Oil Lift Pump stops (Green indicating light ON):
PROCEDURE (continued)                                                             (T) INITIALS NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.
!RC-3A-1 !RC-3B-1!RC-3C-1!RC-3D-1                                      b.For the selected RCP verify the following Annunciator is clear:
: 4. Verify positive Controlled Bleedoff Flow for the selected RCP on ERF (page 342):
!RC-3A REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)
      !   RC-3A
!RC-3B REACTOR COOLANT PUMP RC-3B REVERSE
      !   RC-3B
      !   RC-3C
      !   RC-3D NOTE When starting the first Reactor Coolant Pump, use TR-346, Shutdown Cooling Inlet/Outlet Temp, black pen LPSI Suction Temp indication to verify NPSH requirements are met.
: 5. Ensure RCS Pressure is greater than 225 psia for RCP seal protection (ensures RCS Pressure is greater than minimum NPSH Pressure per TDB-III.7.a and TDB-III.7.d, RCS Pressure and Temperature Limits).
: 6. Ensure RCS Pressure is less than the Maximum Pressure for First RCP Start curve per TDB-III.7.a, RCS Pressure and Temperature Limits. (NA if an RCP is running).
: 7. Ensure actual corrected level per TDB-III.1.a Pressurizer level is less than 50%. (NA if an RCP is running).
R69


ROTATION (CB-1/2/3, A6, B5)
FORT CALHOUN STATION                                                                OI-RC-9 OPERATING INSTRUCTION                                                          PAGE 10 OF 66 C
!RC-3C REACTOR COOLANT PUMP RC-3C REVERSE
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued)                                                          (T) INITIALS NOTE IF Lockout Relays are NOT RESET, THEN Electrical Maintenance shall be contacted for an inspection of the affected relay(s).
: 8. Ensure the Lockout Relay Switch for the selected RCP is in RESET and the Amber indicating light is ON:
      !    86/RC-3A, Pump RC-3A Motor Current Diff
      !    86/RC-3B, Pump RC-3B Motor Current Diff
      !    86/RC-3C, Pump RC-3C Motor Current Diff
      !    86/RC-3D, Pump RC-3D Motor Current Diff
: 9. For the selected RCP verify the following Annunciator is clear:
      !    RC-3A    REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)
      !    RC-3B REACTOR COOLANT PUMP RC-3B REVERSE ROTATION (CB-1/2/3, A6, B5)
      !   RC-3C REACTOR COOLANT PUMP RC-3C REVERSE ROTATION (CB-1/2/3, A6, C5)
      !    RC-3D REACTOR COOLANT PUMP RC-3D REVERSE ROTATION (CB-1/2/3, A6, D5)
NOTE The Oil Lift Pump shall not be run for longer than 10 minutes before starting the Reactor Coolant Pump.
CAUTION Prior to starting a RCP when personnel are in Containment, the Containment Coordinator shall be notified, OR an announcement made on the Gaitronics.
: 10. Place the Oil Lift Pump for the selected RCP to AFTER START:
      !    RC-3A-1, Oil Lift Pump
      !    RC-3B-1, Oil Lift Pump
      !    RC-3C-1, Oil Lift Pump
      !    RC-3D-1, Oil Lift Pump R69


ROTATION (CB-1/2/3, A6, C5)
FORT CALHOUN STATION                                                                OI-RC-9 OPERATING INSTRUCTION                                                        PAGE 11 OF 66 C
!RC-3D REACTOR COOLANT PUMP RC-3D REVERSE
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued)                                                          (T) INITIALS
: 11. Verify adequate ARRD Lube Oil Flow for the selected RCP. ERF indication shall read NORMAL: (ERF page 342)
    !    RC-3A    F3181
    !    RC-3B    F3184
    !    RC-3C    F3187
    !    RC-3D    F3190
: 12. Startup sequence for selected RCP:
: a. Run the oil lift pump for the selected RCP a minimum of two minutes.
        !    RC-3A-1, Oil Lift Pump
        !    RC-3B-1, Oil Lift Pump
        !    RC-3C-1, Oil Lift Pump
        !    RC-3D-1, Oil Lift Pump
: b. Place the selected RCP control switch in AFTER START:
        !    RC-3A, RC Pump
        !    RC-3B, RC Pump
        !    RC-3C, RC Pump
        !    RC-3D, RC Pump
: c. IF the Reactor Coolant Pump motor amps fail to drop below 425 amps within the time listed below, THEN place the control switch in AFTER STOP:
        !    RC-3A - seventeen (17) seconds
        !   RC-3B - nineteen (19) seconds
        !    RC-3C - seventeen (17) seconds
        !    RC-3D - seventeen (17) seconds R69


ROTATION (CB-1/2/3, A6, D5)
FORT CALHOUN STATION                                                              OI-RC-9 OPERATING INSTRUCTION                                                        PAGE 12 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued)                                                        (T) INITIALS
: 13. Verify the following for the selected RCP:
: a. Oil Lift Pump stops (Green indicating light ON):
          !    RC-3A-1
          !    RC-3B-1
          !    RC-3C-1
          !    RC-3D-1
: b. For the selected RCP verify the following Annunciator is clear:
          !    RC-3A    REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)
          !    RC-3B    REACTOR COOLANT PUMP RC-3B REVERSE ROTATION (CB-1/2/3, A6, B5)
          !    RC-3C    REACTOR COOLANT PUMP RC-3C REVERSE ROTATION (CB-1/2/3, A6, C5)
          !    RC-3D    REACTOR COOLANT PUMP RC-3D REVERSE ROTATION (CB-1/2/3, A6, D5)
NOTE RCP Vibration Hi annunciator may be erratic until pump speed/flow stabilizes.
: c. For the selected RCP verify the following Annunciator is clear:
          !    RC-3A    REACTOR COOLANT PUMP RC-3A VIBRATION HI (CB-1/2/3, A6, A4)
          !    RC-3B    REACTOR COOLANT PUMP RC-3B VIBRATION HI (CB-1/2/3, A6, B4)
          !    RC-3C    REACTOR COOLANT PUMP RC-3C VIBRATION HI (CB-1/2/3, A6, C4)
          !    RC-3D    REACTOR COOLANT PUMP RC-3D VIBRATION HI (CB-1/2/3, A6, D4)
R69


NOTE RCP Vibration Hi annunciator may be erratic until pump speed/flow
FORT CALHOUN STATION                                                                  OI-RC-9 OPERATING INSTRUCTION                                                            PAGE 13 OF 66 C
Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)
PROCEDURE (continued)                                                            (T) INITIALS NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.
: 14. Verify positive Controlled Bleedoff flow for the selected RCP: (ERF page 342)
      !    RC-3A    F3115
      !    RC-3B    F3135
      !    RC-3C    F3155
      !    RC-3D    F3175
: 15. Monitor the ERF Computer and verify all parameters are normal for the selected RCP:
      !    RC-3A
      !    RC-3B
      !    RC-3C
      !    RC-3D
: 16. IF other RCPs are to be started, THEN repeat Steps 2 through 15 for each RCP to be started.
Completed by                                                          Date/Time    /
R69


stabilizes.c.For the selected RCP verify the following Annunciator is clear:
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs Location:              Simulator Approximate Time:      10 minutes          Actual Time: _________________
!RC-3A REACTOR COOLANT PUMP RC-3A VIBRATION HI (CB-1/2/3, A6, A4)
Reference(s):    K/A# 061000 A2.04 EOP-06, "LOSS OF ALL FEEDWATER" Handout(s)       EOP-06, Step 12.
!RC-3B REACTOR COOLANT PUMP RC-3B VIBRATION HI (CB-1/2/3, A6, B4)
Time Critical:      NO Alternate Path:    YES JPM Prepared by:      Jerry Koske                                  Date: 3/3/09 Page 1 of 6
!RC-3C REACTOR COOLANT PUMP RC-3C VIBRATION HI (CB-1/2/3, A6, C4)
!RC-3D REACTOR COOLANT PUMP RC-3D VIBRATION HI (CB-1/2/3, A6, D4)


C Continuous Use FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 13 OF 66  - Starting Reactor Coolant Pumps (Coupled)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs Operators Name: _____________________ Employee # ______________
PROCEDURE (continued)
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
()INITIALS R69 NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.14.Verify positive Controlled Bleedoff flow for the selected RCP: (ERF page 342)!RC-3A F3115
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
!RC-3B F3135
Reason, if unsatisfactory:
!RC-3C F3155
Tools & Equipment:            None Safety Considerations:        None Comments:                     Alternate Path Page 2 of 6
!RC-3D F3175 15.Monitor the ERF Computer and verify all parameters are normal for the selected RCP:
!RC-3A!RC-3B!RC-3C!RC-3D                                      16.IF other RCPs are to be started,THEN repeat Steps 2 through 15 for each RCP to be started.
Completed by Date/Time            /             


EOP-06 Page 11 of 41 Continuously Applicable or Non-Sequential Step R16  INSTRUCTIONS CONTINGENCY ACTIONS      12. Initiate AFW using FW-6 or FW-10, AFW Pumps, by performing step a, b or c: a. Feed S/Gs with AFW through the Feed Rings to maintain S/G level
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs TASK                  The candidate attempted to supply water to the steam STANDARD:            generators from Turbine Driven AFW Pump, FW-10, through the feed rings but was unsuccessful because FW-10 would not start. The Candidate established flow to both Steam Generators through the feed rings using Diesel Driven AFW Pump, FW-54.
INITIAL                      A reactor trip has occurred following a rupture of CONDITIONS:                   the Condensate Pumps' common discharge header.
FW-6 is out of service.
The CRS has entered EOP-6.
There are no Operators available to perform any local actions.
INITIATING CUE:      You have been directed to feed both steam generators from FW-10, via the feed rings in accordance with EOP-06, Step 12.
Page 3 of 6


35-85% NR (73-94% WR):
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs Critical Steps shown in gray STEP                    ELEMENT                              STANDARD NOTE to Examiner: If the candidate requests an EONT or other In-plant Operator to take any actions during the performance of this JPM, inform him that the EONT is not available.
: 1) Ensure BOTH of the Feed Reg Block Valves are  
1                Ensure BOTH of the Feed                CB-10,11 Reg Block Valves are                  GREEN lights ON.
closed:
* HCV-1103.                          [ SAT ]      [ UNSAT ]
* HCV-1104.
2                Start FW-10                            AI-66B Place YCV-1045 switch in OPEN, verfiy RED light ON Verify YCV-1045A and/or YCV-1045B OPEN-RED light ON Determines that FW-10 will not start. Goes to contingency action, 12.1.
3                Ensure HCV-1384 is closed.            CB-10,11 Control Switch in AFTER CLOSE, GREEN light ON.
[ SAT ]      [ UNSAT ]
4                Ensure BOTH of the Feed               CB-10,11 Reg Block Valves are                   GREEN lights ON.
closed:
* HCV-1103.                          [ SAT ]      [ UNSAT ]
* HCV-1104.
Page 4 of 6


closed:   HCV-1103  HCV-1104
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs STEP                      ELEMENT                              STANDARD 4                Start FW-54                            CB-10,11 Control switch to open.
: 2) Start at least one of the following AFW Pumps:
RED light ON.
FW-6  FW-10  3) Open HCV-1384, AFW/FW Header Cross-Connect
[ SAT ]      [ UNSAT ]
5                Ensure BOTH of the Feed                CB-10,11 header Isolation Valves are open:                                 RED lights ON GREEN lights OFF HCV-1386 HCV-1385 6                Manually control feed flow            CB-10,11 via BOTH of the Feed Reg              DCS Panel Bypass Valves:
* HCV-1105.                          Manually open HCV-1105 and
* HCV-1106.                          HCV-1106 to establish flow.
[ SAT ]      [ UNSAT ]
7                Verify AFW Flow established to        CB-10,11 or ERF both S/Gs.                            Flow indicated on meters or ERF computer.
[ SAT ]      [ UNSAT ]
8                Record Time.                          Record Time at step 12.1.a.5)
[ SAT ]      [ UNSAT ]
Termination Criteria:      Flow established from FW-54 to both Steam Generators Page 5 of 6


Valve. 4) Ensure BOTH of the Feed Header Isolation Valves are
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 INITIAL                  A reactor trip has occurred following a rupture of CONDITIONS:              the Condensate Pumps' common discharge header.
FW-6 is out of service.
The CRS has entered EOP-6.
There are no Operators available to perform any local actions.
INITIATING CUE:  You have been directed to feed both steam generators from FW-10, via the feed rings in accordance with EOP-06, Step 12.
Page 6 of 6


open:  HCV-1386  HCV-1385 12.1 IF FW-6 and FW-10 are NOT available,   
EOP-06 Page 11 of 41 INSTRUCTIONS                                  CONTINGENCY ACTIONS 812. Initiate AFW using FW-6 or FW-10,          12.1 IF FW-6 and FW-10 are NOT AFW Pumps, by performing step a, b              available, or c:                                          THEN initiate AFW using FW-54, Diesel AFW Pump, by performing
: a. Feed S/Gs with AFW through the step a or b:
Feed Rings to maintain S/G level 35-85% NR (73-94% WR):
: a. Feed S/Gs with AFW to the Feed Rings to maintain S/G levels
: 1)  Ensure BOTH of the Feed 35-85% NR (73-94% WR):
Reg Block Valves are closed:
: 1) Ensure HCV-1384, FW/AFW
* HCV-1103 Header Cross-Connect Valve,
* HCV-1104 is closed.
: 2)  Start at least one of the
: 2) Ensure BOTH of the Feed following AFW Pumps:
Reg Block Valves are closed:
* FW-6
* FW-10
* HCV-1103
* HCV-1104
: 3)  Open HCV-1384, AFW/FW Header Cross-Connect                    3) Start FW-54, Diesel AFW Valve.                                    Pump.
: 4)  Ensure BOTH of the Feed                4) Ensure BOTH of the Feed Header Isolation Valves are Header Isolation Valves are open:
open:
* HCV-1386
* HCV-1386
* HCV-1385
* HCV-1385 (continue)                                  (continue) 8 Continuously Applicable or Non-Sequential Step                                      R16


THEN initiate AFW using FW-54, Diesel AFW Pump, by performing
EOP-06 Page 12 of 41 INSTRUCTIONS                                  CONTINGENCY ACTIONS 812.a.    (continued)                          12.1.a (continued)
: 5)  Manually control feed flow              5) Manually control feed flow via via BOTH of the Feed Reg                  BOTH of the Feed Reg Bypass Valves:                            Bypass Valves:
* HCV-1105
* HCV-1105
* HCV-1106
* HCV-1106 Time:                                      Time:
: 6)  IF Auxiliary Feedwater flow            6) IF Auxiliary Feedwater flow is is established,                           established, THEN GO TO Step 15.                        THEN GO TO Step 15.
(continue)                                  (continue) 8  Continuously Applicable or Non-Sequential Step                                      R16


step a or b:
EOP-06 Page 13 of 41 INSTRUCTIONS                                  CONTINGENCY ACTIONS 8 12. (continued)                                12.1  (continued)
: a. Feed S/Gs with AFW to the Feed Rings to maintain S/G levels  
: b. Feed S/Gs with AFW to the Feed           b. Feed S/Gs with AFW to the AFW Rings via the alternate AFW                  Nozzles to maintain S/G levels Pump discharge path to maintain               35-85% NR (73-94% WR):
S/G levels 35-85% NR (73-94%
WR):                                          1) Close BOTH of the Feed Header Isolation Valves:
: 1)  Open BOTH of the following
* HCV-1386 valves (Room 19):
* HCV-1385
* FW-745, "MOTOR DRIVEN AUX FEED                      2) Open HCV-1384, FW/AFW PUMP FW-6 ALTERNATE                                Header Cross-Connect Valve.
DISCHARGE VALVE"
* FW-744,                              3) Start FW-54, Diesel AFW "TURB-DRIVEN AUX Pump.
FEED PUMP FW-10 ALTERNATE DISCHARGE VALVE"
: 4) IF AFAS has actuated, THEN set BOTH of the
: 2)  Ensure BOTH of the Feed following AFW Isolation Valve Reg Block Valves are Controllers to open closed:
(CB-10,11):
* HCV-1103
* HCV-1104
* HIC-1107B
* HIC-1108B (continue)                                    (continue) 8  Continuously Applicable or Non-Sequential Step                                      R16


35-85% NR (73-94% WR):
EOP-06 Page 14 of 41 INSTRUCTIONS                                  CONTINGENCY ACTIONS 812.b      (continued)                          12.1.b (continued)
: 1) Ensure HCV-1384, FW/AFW Header Cross-Connect Valve, is closed.
: 3)  Start at least one of the              5) Place control switches for following AFW Pumps:                      BOTH of the following AFW Isolation Valves in "CLOSE"
: 2) Ensure BOTH of the Feed Reg Block Valves are closed:
* FW-6
HCV-1103  HCV-1104
* FW-10                              (AI-66A/B):
: 3) Start FW-54, Diesel AFW Pump. 4) Ensure BOTH of the Feed Header Isolation Valves are
: 4)   Ensure BOTH of the Feed
* HCV-1107B
* HCV-1108B Header Isolation Valves are open:
: 6) Open BOTH of the following
* HCV-1385                            AFW Isolation Valves
* HCV-1386                            (AI-66A/B):
: 5)   Manually control feed flow
* HCV-1107A
* HCV-1108A via BOTH of the Feed Reg Bypass Valves:                        7) Manually control BOTH of the following AFW Isolation
* HCV-1105
* HCV-1106                            Valves (CB-10,11):
Time:
* HIC-1107B
* HIC-1108B
: 6)  IF Auxiliary Feedwater flow is established,                          Time:
THEN GO TO Step 15.
: 8) IF Auxiliary Feedwater flow is established, (continue)                              THEN GO TO Step 15.
(continue) 8  Continuously Applicable or Non-Sequential Step                                    R16


open:  HCV-1386  HCV-1385 (continue)  (continue)
EOP-06 Page 15 of 41 INSTRUCTIONS                                   CONTINGENCY ACTIONS 812.b      (continued)
EOP-06 Page 12 of 41 Continuously Applicable or Non-Sequential Step R16  INSTRUCTIONS CONTINGENCY ACTIONS      12.a. (continued)
: c. Feed S/Gs with AFW to the AFW Nozzles to maintain S/G levels 35-85% NR (73-94% WR):
: 5) Manually control feed flow via BOTH of the Feed Reg Bypass Valves:
: 1)   Start at least one of the following AFW Pumps:
HCV-1105  HCV-1106 Time:  12.1.a (continued)
* FW-6
: 5) Manually control feed flow via BOTH of the Feed Reg Bypass Valves:
* FW-10
HCV-1105  HCV-1106 Time:        6) IF Auxiliary Feedwater flow is established, THEN GO TO Step 15.
: 2)   Ensure HCV-1384, FW/AFW Header Cross-Connect Valve, is closed.
: 6) IF Auxiliary Feedwater flow is established, 
: 3)  IF AFAS has actuated, THEN set BOTH of the following AFW Isolation Valve Controllers to open (CB-10,11):
 
* HIC-1107B
THEN GO TO Step 15.
* HIC-1108B (continue) 8  Continuously Applicable or Non-Sequential Step                            R16
 
(continue)
 
(continue)
EOP-06 Page 13 of 41 Continuously Applicable or Non-Sequential Step R16  INSTRUCTIONS CONTINGENCY ACTIONS       12. (continued)
: b. Feed S/Gs with AFW to the Feed Rings via the alternate AFW Pump discharge path to maintain  
 
S/G levels 35-85% NR (73-94%  
 
WR): 1) Open BOTH of the following valves (Room 19):
FW-745, "MOTOR DRIVEN AUX FEED PUMP FW-6
 
ALTERNATE
 
DISCHARGE VALVE"   FW-744, "TURB-DRIVEN AUX
 
FEED PUMP FW-10


ALTERNATE
EOP-06 Page 16 of 41 INSTRUCTIONS                                  CONTINGENCY ACTIONS 812.c.      (continued)
: 4)    Place Control Switches for BOTH of the following AFW Isolation Valves in "CLOSE" (AI-66A/B):
* HCV-1107B
* HCV-1108B
: 5)    Open BOTH of the following AFW Isolation Valves (AI-66A/B):
* HCV-1107A
* HCV-1108A
: 6)    Manually control BOTH of the following AFW Isolation Valves (CB-10,11):
* HIC-1107B
* HIC-1108B Time:
: 13. IF Auxiliary Feedwater flow is established, THEN GO TO Step 15.
8  Continuously Applicable or Non-Sequential Step                            R16


DISCHARGE VALVE"  2) Ensure BOTH of the Feed Reg Block Valves are closed:   HCV-1103  HCV-1104 12.1 (continued)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Location:            Simulator Approximate Time:    10 minutes            Actual Time: _________________
: b. Feed S/Gs with AFW to the AFW Nozzles to maintain S/G levels 35-85% NR (73-94% WR):
Reference(s):   K/A 028000 A1.01 EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" Handout(s):     EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" Time Critical: NO Alternate Path:  NO JPM Prepared by:    Jerry Koske                                  Date: 3/3/09 Page 1 of 7
: 1) Close BOTH of the Feed Header Isolation Valves:
HCV-1386 HCV-1385
: 2) Open HCV-1384, FW/AFW Header Cross-Connect Valve.
: 3) Start FW-54, Diesel AFW Pump. 4) IF AFAS has actuated, THEN set BOTH of the following AFW Isolation Valve


Controllers to open (CB-10,11):
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Operators Name: _____________________ Employee # ______________
HIC-1107B  HIC-1108B (continue) (continue)  
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:        None Comments:
Page 2 of 7


EOP-06 Page 14 of 41 Continuously Applicable or Non-Sequential Step R16  INSTRUCTIONS CONTINGENCY ACTIONS      12.b (continued) 12.1.b (continued)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer TASK                The Candidate placed the Containment Hydrogen STANDARD            Analyzers in service and determined that the hydrogen concentration is below flammability limits.
: 3) Start at least one of the following AFW Pumps:
INITIAL              A LOCA occurred followed by a sustained core CONDITIONS:          uncovery. The core is now covered but radiation levels in containment indicate that some fuel damage may have occurred. The SAMG Evaluators in the TSC need to know the containment hydrogen concentration to perform core damage assessment.
FW-6  FW-10  4) Ensure BOTH of the Feed Header Isolation Valves are open:  HCV-1385  HCV-1386
INITIATING CUE:     You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachment 16 and sample the upper level of containment via HCV-820C and HCV-883C. Determine if Containment Hydrogen Concentration is above flammability limits.
: 5) Manually control feed flow via BOTH of the Feed Reg Bypass Valves:
Page 3 of 7
HCV-1105  HCV-1106 Time:    6) IF Auxiliary Feedwater flow is established, THEN GO TO Step 15.  


(continue)
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Open HCV-820C.                        AI-65A/B Control switch to OPEN.
: 5) Place control switches for BOTH of the following AFW Isolation Valves in "CLOSE" (AI-66A/B):
RED light ON.
HCV-1107B  HCV-1108B
[ SAT ]      [ UNSAT ]
: 6) Open BOTH of the following AFW Isolation Valves (AI-66A/B):
2              Open HCV-883C.                        AI-65A/B Control switch to OPEN.
HCV-1107A  HCV-1108A
RED light ON.
: 7) Manually control BOTH of the following AFW Isolation
[ SAT ]      [ UNSAT ]
3              Place all of the following           AI-43A/B switches in Override:                 Control switches to ORIDE.
HCV-820A/821A.                  RED lights ON.
HCV-883A/884A.
HCV-820B/821B.
HCV-883B/884B.                  [ SAT ]      [ UNSAT ]
4              Place recorders, HR-81A/B in          AI-65A/B service.                              Turn recorders on.
[ SAT ]      [ UNSAT ]
5              Ensure Range Selector                AI-65A/B switches are in 0-10%.              Selector switch in 0-10%
position.
[ SAT ]      [ UNSAT ]
6              Place the Hydrogen Analyzer          AI-65A/B Power On Selector Switches to        Switches to ANALYZE ANALYZE.                            position.
[ SAT ]      [ UNSAT ]
Page 4 of 7


Valves (CB-10,11):
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer STEP                    ELEMENT                              STANDARD 7              Ensure the Function Selector          AI-65A/B Switches are in SAMPLE.              Switches in SAMPLE position.
HIC-1107B  HIC-1108B Time:    8) IF Auxiliary Feedwater flow is established, THEN GO TO Step 15.
[ SAT ]      [ UNSAT ]
(continue)
8              Press REMOTE selector                AI-65A/B pushbuttons.                          Depress pushbuttons.
EOP-06 Page 15 of 41 Continuously Applicable or Non-Sequential Step R16  INSTRUCTIONS CONTINGENCY ACTIONS       12.b (continued)
[ SAT ]       [ UNSAT ]
: c. Feed S/Gs with AFW to the AFW Nozzles to maintain S/G levels 35-85% NR (73-94% WR):
9              Check the following:                   AI-65A/B Containment H2                Alarm Window ON.
: 1) Start at least one of the following AFW Pumps:
Sampling System Remote/Local Off Normal Annunciator in Alarm.
FW-6  FW-10       2) Ensure HCV-1384, FW/AFW Header Cross-Connect Valve, is  
0-10% Range Amber              AMBER light ON.
indicating light is ON.
The Sample Indicating          Light is ON.
light is ON.
[ SAT ]      [ UNSAT ]
10             Press Alarm Reset Push                AI-65A/B buttons.                              Depress push buttons.
[ SAT ]      [ UNSAT ]
CUE: 5 minutes have elapsed 11            Obtain hydrogen concentration          AI-65A/B reading.                              Report reading from meters is below flammability limits.
[ SAT ]      [ UNSAT ]
Page 5 of 7


closed. 3) IF AFAS has actuated, THEN set BOTH of the following AFW Isolation
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Termination Criteria:  Containment hydrogen concentration has been determined Page 6 of 7


Valve Controllers to open (CB-10,11):
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 INITIAL          A LOCA occurred followed by a sustained core CONDITIONS:       uncovery. The core is now covered but radiation levels in containment indicate that some fuel damage may have occurred. The SAMG Evaluators in the TSC need to know the containment hydrogen concentration to perform core damage assessment.
HIC-1107B  HIC-1108B (continue)
INITIATING CUE:  You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachment 16 and sample the upper level of containment via HCV-820C and HCV-883C. Determine if Containment Hydrogen Concentration is above flammability limits.
Page 7 of 7


EOP-06 Page 16 of 41 Continuously Applicable or Non-Sequential Step R16  INSTRUCTIONS CONTINGENCY ACTIONS      12.c. (continued)
EOP/AOP ATTACHMENTS Page 79 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS                                 CONTINGENCY ACTIONS
: 4) Place Control Switches for BOTH of the following AFW Isolation Valves in "CLOSE" (AI-66A/B):
: 1. Start the Hydrogen Analyzers, by performing the following steps:
HCV-1107B  HCV-1108B
: 5) Open BOTH of the following AFW Isolation Valves (AI-66A/B):
HCV-1107A  HCV-1108A
: 6) Manually control BOTH of the following AFW Isolation
 
Valves (CB-10,11):
HIC-1107B  HIC-1108B Time:
: 13. IF Auxiliary Feedwater flow is established, 
 
THEN GO TO Step 15.
 
EOP/AOP ATTACHMENTS Page 79 of 168 R26 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS   1. Start the Hydrogen Analyzers, by performing the following steps:
: a. Open ONE of the Containment Hydrogen Sampling Valves, HCV-820C/D/E/F/G/H.
: a. Open ONE of the Containment Hydrogen Sampling Valves, HCV-820C/D/E/F/G/H.
: b. Open ONE of the Containment Hydrogen Sampling Valves, HCV-883C/D/E/F/G/H.
: b. Open ONE of the Containment Hydrogen Sampling Valves, HCV-883C/D/E/F/G/H.
: c. Place ALL of the following switches in "O'RIDE":  
: c. Place ALL of the following switches in "O'RIDE":
  "H2 ANALYZER VA-81A ISOLATION VALVES OUTBD HCV-820A/821A"   "H2 ANALYZER VA-81B ISOLATION VALVES INBD  
          * "H2 ANALYZER VA-81A ISOLATION VALVES OUTBD HCV-820A/821A"
          * "H2 ANALYZER VA-81B ISOLATION VALVES INBD HCV-883A/884A"
          * "H2 ANALYZER VA-81A ISOLATION VALVES INBD HCV-820B/821B"
* H2 ANALYZER VA-81B ISOLATION VALVES OUTBD HCV-883B/884B" (continue)
R26


HCV-883A/884A"  "H2 ANALYZER VA-81A ISOLATION VALVES INBD
EOP/AOP ATTACHMENTS Page 80 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS                                 CONTINGENCY ACTIONS
 
: 1. (continued)
HCV-820B/821B"  H2 ANALYZER VA-81B ISOLATION VALVES OUTBD
 
HCV-883B/884B"  (continue) 
 
EOP/AOP ATTACHMENTS Page 80 of 168 R26 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS   1. (continued)
: d. Place the Hydrogen Analyzer Recorders, HR-81A/B, in service.
: d. Place the Hydrogen Analyzer Recorders, HR-81A/B, in service.
: e. Ensure the Hydrogen Analyzer Dual Range Selector Switches  
: e. Ensure the Hydrogen Analyzer Dual Range Selector Switches are in "0-10%".
 
are in "0-10%".
: f. Place the Hydrogen Analyzer Power On Selector Switches in "ANALYZE".
: f. Place the Hydrogen Analyzer Power On Selector Switches in "ANALYZE".
: g. Ensure the Function Selector Switches are in "SAMPLE".
: g. Ensure the Function Selector Switches are in "SAMPLE".
: h. Press the "REMOTE" selector push buttons.  
: h. Press the "REMOTE" selector push buttons.
 
(continue)
(continue)  
R26


EOP/AOP ATTACHMENTS Page 81 of 168 R26 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS   1. (continued)
EOP/AOP ATTACHMENTS Page 81 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS                                   CONTINGENCY ACTIONS
: 1.   (continued)
: i. Check the following indications:
: i. Check the following indications:
The "CONTAINMENT H 2 SAMPLING SYSTEM REMOTE/LOCAL OFF  
* The CONTAINMENT H2 SAMPLING SYSTEM REMOTE/LOCAL OFF NORMAL annunciator (A65A or B, Window 32) is IN ALARM
 
* H2 0-10% Range Amber indicating light is ON
NORMAL" annunciator (A65A  
* The Sample indicating light is ON
: j. Press the "ALARM RESET" push buttons.
: k. WHEN 5 minutes has elapsed since pressing the "ALARM RESET" push button, THEN a valid hydrogen concentration may be read.
End of Attachment 16 R26


or B, Window 32) is "IN
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV Location:            Simulator Approximate Time:    10 minutes            Actual Time: _________________
Reference(s):  K/A 000062 A4.01 AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV."
OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."
Handout(s):    AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV",
step 10.
OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."
Time Critical:  NO Alternate Path:  NO JPM Prepared by:    Jerry Koske                                  Date: 03/3/09 Page 1 of 8


ALARM"  H 2 0-10% Range Amber indicating light is "ON" The Sample indicating light is "ON"      j. Press the "ALARM RESET" push buttons.      k. WHEN 5 minutes has elapsed since pressing the "ALARM
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            None Safety Considerations:        None Comments:
Page 2 of 8


RESET" push button,
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV TASK                The candidate transferred the power supplies to vital STANDARD:            buses 1A3 and 1A4 from 345 KV to 161 KV following the restoration of 161 KV power in accordance with AOP-31, "161 KV GRID MALFUNCTIONS" and OI-EE-1, "NORMAL OPERATION OF 4160 VOLT SYSTEM, "
Attachment 1.
INITIAL                    The plant is operating at full power.
CONDITIONS:                A loss of 161 KV occurred due to a grid problem.
Buses 1A3 and 1A4 transferred to 345 KV.
AOP-31, section II was entered and appropriate actions taken.
The 161 KV grid problem has been fixed and 161 KV is available.
INITIATING CUE:      You are directed to restore normal 161 KV power to buses 1A3 and 1A4 using AOP-31, section II, step 10 and OI-EE-1, Attachment 1.
Page 3 of 8


THEN a valid hydrogen
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Ensure Lockout Relay 86/161          AI-22 is reset.                            86 Relay RESET.
[ SAT ]      [ UNSAT ]
2              Ensure all of the following          AI-24, AI-25, AI-46 Lockout Relays are reset:            Relays RESET.
86-1/T1A-4.
86-2/T1A-4.
86-1/T1A-3.
86-2/T1A-3.
86X/FT161.                      [ SAT ]      [ UNSAT ]
3              Read Caution.                        Read Caution on AOP-31 page 10.
[ SAT ]      [ UNSAT ]
CUE: System Operations has been notified.
4              Synchronize and Close at least        CB-20 one of the following breakers:        Insert Sync switch handle and Breaker 110.                    turn to ON.
Breaker 111.                    Breaker switch to AFTER CLOSE.
RED light ON.
[ SAT ]      [ UNSAT ]
5              Turn off Sync switch.                CB-20 Turn Sync switch handle to OFF.
[ SAT ]      [ UNSAT ]
Page 4 of 8


concentration may be read.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV STEP                    ELEMENT                              STANDARD 6              Enter OI-EE-1, Attachment 1.          Enters OI-EE-1, Attachment 1.
End of Attachment 16
7              Ensure both fast Transfer            CB-20 switches in manual:                  Both switches in MANUAL.
43/1A1-1A3.
43/1A2-1A4.                    [ SAT ]      [ UNSAT ]
8              Read Note                            Reads Note on middle of OI-EE-1, page 4
[ SAT ]      [ UNSAT ]
Note: Buses 1A3 and 1A4 may be transferred in either order.
9              Turn 1A33 Synchroscope ON.            CB-20 Insert Sync switch handle and turn to ON.
[ SAT ]      [ UNSAT ]
10              Verify incoming and running          CB-20 voltages are matched.                Verify voltages within 25 volts.
[ SAT ]      [ UNSAT ]
11              Verify Synchroscope at 12            CB-20 o'clock.                              Indicator at 12 o'clock.
[ SAT ]      [ UNSAT ]
12              Close Breaker 1A33.                  CB-20 Breaker 1A33 in AFTER CLOSE, RED light ON.
[ SAT ]      [ UNSAT ]
Page 5 of 8


oo
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV STEP                    ELEMENT                              STANDARD 13              Open Breaker 1A13                    CB-20 Breaker 1A13 in AFTER TRIP.
GREEN light ON
[ SAT ]      [ UNSAT ]
14              Turn Off Synchroscope.                CB-20 Sync switch handle to OFF Verify loads still energized
[ SAT ]      [ UNSAT ]
15              Turn 1A44 Synchroscope ON.            CB-20 Insert Sync switch handle and turn to ON.
[ SAT ]      [ UNSAT ]
16              Verify incoming and running          CB-20 voltages are matched.                Verify voltages within 25 volts.
[ SAT ]      [ UNSAT ]
17              Verify Synchroscope at 12            CB-20 o'clock.                              Indicator at 12 o'clock.
[ SAT ]      [ UNSAT ]
18              Close Breaker 1A44.                  CB-20 Breaker 1A44 in AFTER CLOSE, RED light ON.
[ SAT ]      [ UNSAT ]
Page 6 of 8


AOP-31 Page 20 of 28 R9 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS CONTINGENCY ACTIONS   10. WHEN 161 KV power is available, 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV STEP                    ELEMENT                              STANDARD 19              Open Breaker 1A24.                    CB-20 Breaker 1A24 in AFTER TRIP.
GREEN light ON.
[ SAT ]        [ UNSAT ]
20              Turn Off Synchroscope.                CB-20 Sync switch handle to OFF Verify loads still energized.
[ SAT ]        [ UNSAT ]
21              Verify conditions for fast            CB-20 transfer met:
All lock-outs on CB-20                  AMBER lights ON for all have amber light on.                    lock-out relays(vertical Appropriate 4160V                        panel).
breakers not in pull-to-              Control Switches not in lock.                                  PULL-TO-LOCK:
Power is available.                          o Breaker 1A13 o Breaker 1A24 Voltmeters show proper voltages.
[ SAT ]        [ UNSAT ]
22             Place Fast Transfer switches in CB-20 AUTO                                  Both Switches in AUTO.
43/1A1-1A3.
43/1A2-1A4.                    [ SAT ]        [ UNSAT ]
Termination Criteria:   Buses 1A3 and 1A4 powered from 161 KV Page 7 of 8


THEN restore normal power to Buses 1A3 and 1A4 by performing the
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 INITIAL                The plant is operating at full power.
CONDITIONS:            A loss of 161 KV occurred due to a grid problem.
Buses 1A3 and 1A4 transferred to 345 KV.
AOP-31, section II was entered and appropriate actions taken.
The 161 KV grid problem has been fixed and 161 KV is available.
INITIATING CUE:  You are directed to restore normal 161 KV power to buses 1A3 and 1A4 using AOP-31, section II, step 10 and OI-EE-1, Attachment 1.
Page 8 of 8


following steps:
AOP-31 Page 20 of 28 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS                                      CONTINGENCY ACTIONS
: 10. WHEN 161 KV power is available, THEN restore normal power to Buses 1A3 and 1A4 by performing the following steps:
: a. Ensure Lockout Relay 86/161 is reset (AI-22).
: a. Ensure Lockout Relay 86/161 is reset (AI-22).
: b. Ensure ALL of the following lockout relays are reset:
: b. Ensure ALL of the following lockout relays are reset:
86-1/T1A-4 (AI-25) 86-2/T1A-4 (AI-25) 86-1/T1A-3 (AI-24) 86-2/T1A-3 (AI-24) 86X/FT161 (AI-46)  
* 86-1/T1A-4 (AI-25)
* 86-2/T1A-4 (AI-25)
* 86-1/T1A-3 (AI-24)
* 86-2/T1A-3 (AI-24)
* 86X/FT161 (AI-46)
(continue)
R9


(continue)  
AOP-31 Page 21 of 28 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS                                          CONTINGENCY ACTIONS
: 10.  (continued)
    *************************************************************************************************
CAUTION System Operations should be notified prior to operating any switchyard breakers or disconnect switches to ensure all personnel are clear.
    *************************************************************************************************
: c. Synchronize and close at least one of the following breakers:
* Breaker 110
* Breaker 111
: d. Transfer buses 1A3 and 1A4 to 161 KV PER Attachment 1 of OI-EE-1, Normal Operation of 4160V System.
End of Section 4.0 R9


AOP-31 Page 21 of 28 R9 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS CONTINGENCY ACTIONS    10. (continued)  
FORT CALHOUN STATION                                                            OI-EE-1 OPERATING INSTRUCTION                                                      PAGE 4 OF 35 C
*************************************************************************************************
Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PREREQUISITES                                                              (%) INITIALS
CAUTION System Operations should be notified prior to operating any switchyard breakers or disconnect switches to ensure all personnel are clear.  
: 1. Procedure Revision Verification Revision No. 25                  Date: 3/31/09                              JEK
: 2. 161 KV is in service per OI-EG-2.                                            JEK
: 3. IF startup of Gen G1 is being performed, N/A THEN ensure OI-EE-1-CL-A has been completed per OP-1.
PROCEDURE
: 1. Ensure both Fast Transfer Switches are in MANUAL:
    !    43/1A1-1A3
    !    43/1A2-1A4 NOTE Steps 2 through 5 may be performed in any order.
: 2. Transfer 1A1, Non-Vital Bus, to 161 KV as follows:
: a. Turn on Synchroscope for 1A31.
: b. Verify Incoming and Running voltages are approximately matched.
: c. Verify Synchroscope is approximately at a 12 o'clock position.
: d. Close 1A31.
: e. Open 1A11.
: f. Turn off Synchroscope.
: 3. Transfer 1A2, Non-Vital Bus, to 161 KV as follows:
: a. Turn on Synchroscope for 1A42.
: b. Verify Incoming and Running voltages are approximately matched.
R25


*************************************************************************************************    c. Synchronize and close at least one of the following breakers:
FORT CALHOUN STATION                                                          OI-EE-1 OPERATING INSTRUCTION                                                    PAGE 5 OF 35 C
Breaker 110  Breaker 111
Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PROCEDURE (continued)                                                    (%) INITIALS 3  c. Verify Synchroscope is approximately at a 12 o'clock position.
: d. Transfer buses 1A3 and 1A4 to 161 KV PER Attachment 1 of OI-EE-1, Normal Operation of 4160V System.       End of Section 4.0
: d. Close 1A42.
: e. Open 1A22.
: f. Turn off Synchroscope.
: 4. Transfer 1A3, Vital Bus, to 161 KV as follows:
: a. Turn on Synchroscope for 1A33.
: b. Verify Incoming and Running voltages are approximately matched.
: c. Verify Synchroscope is approximately at a 12 o'clock position.
: d. Close 1A33.
: e. Open 1A13.
: f. Turn off Synchroscope.
: 5. Transfer 1A4, Vital Bus, to 161 KV as follows:
: a. Turn on Synchroscope for 1A44.
: b. Verify Incoming and Running voltages are approximately matched.
: c. Verify Synchroscope is approximately at a 12 o'clock position.
: d. Close 1A44.
: e. Open 1A24.
: f. Turn off Synchroscope.
R25


CContinuous UseFORT CALHOUN STATIONOI-EE-1OPERATING INSTRUCTIONPAGE 4 OF 35R25Attachment 1 - Feed Vital/Non-Vital Buses From 161 KVPREREQUISITES () INITIALS1.Procedure Revision VerificationRevision No.
FORT CALHOUN STATION                                                                    OI-EE-1 OPERATING INSTRUCTION                                                              PAGE 6 OF 35 C
Date:
Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PROCEDURE (continued)                                                              (%) INITIALS
2.161 KV is in service per OI-EG-2.
: 6. IF the following conditions for Fast Transfer are met,
3.IF startup of Gen G1 is being performed,THEN ensure OI-EE-1-CL-A has been completed per OP-1.              PROCEDURE1.Ensure both Fast Transfer Switches are in MANUAL:
      !    All lock-outs on CB-20 have amber light on
!43/1A1-1A3
      !    Appropriate 4160 volt breakers are not in pull-to-lock
!43/1A2-1A4
      !    Power is available to transfer to THEN place both Fast Transfer Switches in AUTO.
      !   43/1A1-1A3
      !   43/1A2-1A4 NOTE Under certain plant conditions, while supplying all 4160 volt buses, overheat of T1A3 or T1A4 could occur. To minimize this potential, loads between the 2 transformers should be balanced as much as practicable.
: 7. Balance loads between T1A3 and T1A4 as plant conditions allow.
Completed by                                                              Date/Time      /
R25


NOTESteps 2 through 5 may be performed in any order.2.Transfer 1A1, Non-Vital Bus, to 161 KV as follows:a.Turn on Synchroscope for 1A31.      b.Verify Incoming and Running voltages are approximately matched.      c.Verify Synchroscope is approximately at a 12 o'clock position.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment Location:          Simulator Approximate Time:  15 minutes            Actual Time: _________________
d.Close 1A31.
Reference(s):   K/A# 012000 A4.02 OP-ST-RPS-0005, "RPS POWER ADJUSTMENT" Handout(s):    OP-ST-RPS-0005, "RPS POWER ADJUSTMENT" RPS Scaling Amp Offset Measurement Record.
e.Open 1A11.
Time Critical: NO Alternate Path: NO JPM Prepared by:    Jerry Koske                                  Date: 3/23/09 Page 1 of 10
f.Turn off Synchroscope.
3.Transfer 1A2, Non-Vital Bus, to 161 KV as follows:a.Turn on Synchroscope for 1A42.      b.Verify Incoming and Running voltages are approximately matched.        - Feed Vital/Non-Vital Buses From 161 KVPROCEDURE  (continued)
()INITIALS CContinuous UseFORT CALHOUN STATIONOI-EE-1OPERATING INSTRUCTIONPAGE 5 OF 35R253c.Verify Synchroscope is approximately at a 12 o'clock position.
d.Close 1A42.
e.Open 1A22.
f.Turn off Synchroscope.
4.Transfer 1A3, Vital Bus, to 161 KV as follows:a.Turn on Synchroscope for 1A33.      b.Verify Incoming and Running voltages are approximately matched.      c.Verify Synchroscope is approximately at a 12 o'clock position.
d.Close 1A33.
e.Open 1A13.
f.Turn off Synchroscope.
5.Transfer 1A4, Vital Bus, to 161 KV as follows:a.Turn on Synchroscope for 1A44.      b.Verify Incoming and Running voltages are approximately matched.      c.Verify Synchroscope is approximately at a 12 o'clock position.
d.Close 1A44.
e.Open 1A24.
f.Turn off Synchroscope.
                      - Feed Vital/Non-Vital Buses From 161 KVPROCEDURE  (continued)
()INITIALS CContinuous UseFORT CALHOUN STATIONOI-EE-1OPERATING INSTRUCTIONPAGE 6 OF 35R256.IF the following conditions for Fast Transfer are met, !All lock-outs on CB-20 have amber light on
!Appropriate 4160 volt breakers are not in pull-to-lock
!Power is available to transfer toTHEN place both Fast Transfer Switches in AUTO.
!43/1A1-1A3
!43/1A2-1A4


NOTEUnder certain plant conditions, while supplying all 4160 volt buses, overheatof T1A3 or T1A4 could occur. To minimize this potential, loads between the 2 transformers should be balanced as much as practicable.7.Balance loads between T1A3 and T1A4 as plant conditions allow.              Completed by                                                                                            Date/Time            /         
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment Operators Name: _____________________ Employee # ______________
All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):
SATISFACTORY                  UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________
Reason, if unsatisfactory:
Tools & Equipment:            RPS Trip Unit Bypass Keys 1, 9 and 12 Safety Considerations:        None Comments:
Page 2 of 10


PAGE 1 OF 8 R12 
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment TASK              The Candidate performed OP-ST-RPS-0005, "RPS STANDARD:          POWER ADJUSTMENT", for RPS channels A and D and adjusted channel "D" NI Power and T Power to agree with XC-105, plant secondary calorimetric power measurement.
INITIAL                  The plant is operating at full power.
CONDITIONS:              Secondary Calorimetric measurement, XC-105, indicates the reactor is operating at 1497.5 MWt.
The STA has verified XC-105 is valid.
The prerequisites for OP-ST-RPS-0005. RPS POWER ADJUSTMENT, have been met.
INITIATING CUE:    You have been directed to perform OP-ST-RPS-0005, RPS POWER ADJUSTMENT, for channels A and D, and adjust any channels that need adjustment.
Page 3 of 10


Fort Calhoun Station Unit No. 1  
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment Critical Steps shown in gray STEP                  ELEMENT                              STANDARD 1              Record Channel T Scaling            AI-31A/B/C/D Amp Offsets from the RPS              Records Channel T Scaling Scaling Amplifier Offset              Amp Offsets for channels A Measurement Record (Control          and D on test data sheet 1.
Room File drawer) on Test Data Sheet 1 and verify the          [ SAT ]      [ UNSAT ]
Scaling Amp Offset values on the Power Range Safety Drawers.
2              Record Channel NI Scaling            AI-31A/B/C/D Amp Offsets from the RPS              Records Channel NI Scaling Scaling Amplifier Offset              Amp Offsets for channels A nd Measurement Record (Control          D on test data sheet 1 Room File drawer) on Test Data Sheet 1 and verify the          [ SAT ]      [ UNSAT ]
Scaling Amp Offset values on the Power Range Safety Drawers.
3              Record channels Initial T            AI-31A/B/C/D Power readings from RPSCIP            Records Initial T Power DVM on Test Data Sheet 1.            readings for channels A and D on test data sheet 1.
[ SAT ]      [ UNSAT ]
4              Record channels Initial NI            AI-31A/B/C/D Power readings from RPSCIP            Records Initial NI Power DVM on Test Data Sheet 1.            readings for channels A and D on test data sheet 1.
[ SAT ]      [ UNSAT ]
Page 4 of 10


OP-ST-RPS-0005
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP                    ELEMENT                              STANDARD 5              Subtract the Scaling Amp              AI-31A/B/C/D Offset from Initial T Power          Records Initial T Power reading for channels and              readings - scaling amp offset record on Test Data Sheet 1.          for channels A and D on test data sheet 1.
[ SAT ]      [ UNSAT ]
6              Subtract the Scaling Amp              AI-31A/B/C/D Offset from the Initial NI Power      Records Initial NI Power reading for channels and              readings - scaling amp offset record on Test Data Sheet 1.          for channels A and D on test data sheet 1.
[ SAT ]      [ UNSAT ]
7              Record channels Initial T Pwr        AI-31A/B/C/D Calibrate and Nuclear Pwr              Records Initial T Pwr Calibrate dial (Power Range            Calibrate and Nuclear Pwr Monitor Drawer) settings on            Calibrate dial settings for Test Data Sheet 1.                    channels A and D on test data sheet 1.
[ SAT ]      [ UNSAT ]
8              Determine Channel that need            Determines Channel "D" adjustment.                            differs with XC-105 by more than 1% and must be adjusted.
[ SAT ]      [ UNSAT ]
9              Place RPSCIP DVM Meter                AI-31D Input Switch to METER INPUT            Places DVM Meter Input position.                              Switch to METER INPUT position.
[ SAT ]      [ UNSAT ]
Page 5 of 10


SURVEILLANCE TEST
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP                    ELEMENT                              STANDARD 10            Push +10V pushbutton and              AI-31D verify DVM reads +9.800 to            Pushes +10V pushbutton and
              +10.200V.                              verifies reading.
[ SAT ]      [ UNSAT ]
11            Push -10V pushbutton and              AI-31D verify DVM reads -9.800 to            Pushes -10V pushbutton and
              -10.200V.                              verifies reading.
[ SAT ]      [ UNSAT ]
12            Push ZERO pushbutton and              AI-31D verify DVM reads -0.200 to            Pushes ZERO pushbutton and
              +0.200V.                              verifies reading.
[ SAT ]      [ UNSAT ]
13            Record current value of XC-            Enters 1497.5 MWt on Test 105 and calculate the Thermal          Data Sheet 1. Calculates the Power on Test Data Sheet 1.            Thermal Power as 99.8% and enters value on Test Data Sheet 1.
[ SAT ]      [ UNSAT ]
14            Enter Technical Specification          CUE: Another Operator has Limiting Condition for                logged into Technical Operation 2.15, Table 2-2,            Speciifications.
Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12.                    [ SAT ]      [ UNSAT ]
Page 6 of 10


RPS POWER ADJUSTMENT
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP                    ELEMENT                              STANDARD 15            Bypass trip units 1, 9 and 12.          CUE: Provide TU bypass keys to candidate.
AI-31D Inserts Keys in Trip Units 1, 9 and 12 and turns to BYPASS position.
[ SAT ]      [ UNSAT ]
16            Place the DVM selector switch          AI-31D to NUCLEAR PWR.                        Selects NUCLEAR PWR on DVM selector switch
[ SAT ]      [ UNSAT ]
17            Adjust the Power Range                  AI-31D Monitor NUCLEAR PWR                    Adjusts Potentiometer such CALIBRATE potentiometer                that DVM reading equals 99.8 until the DVM equals the                plus the NI scaling amp offset.
Thermal Power plus the NI Scaling Amp Offset.                    [ SAT ]      [ UNSAT ]
18            Place the DVM selector switch          AI-31D to T PWR.                              Selects T PWR on DVM selector switch
[ SAT ]      [ UNSAT ]
19            Adjust T PWR CALIBRATE                AI-31D potentiometer until the                Adjusts Potentiometer such NUCLEAR PWR-T PWR (%)                  that zero deviation indicated sigma meter is nulled                  on sigma meter.
(0 deviation).
[ SAT ]      [ UNSAT ]
Page 7 of 10


Change No. EC 42242 Reason for Change Added a precaution addr essing the fluctuating RPSCIP DVM readings. Converted from WordPerfect to Word. Requestor R.
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP                    ELEMENT                              STANDARD 20            Verify trip units are RESET,          AI-31D then remove the Bypass Keys            Trip Units 1, 9 and 12 not for Trip Units 1, 9 and 12.            bypassed with keys removed.
Lowery Preparer L Hautzinger Issue Date 07-17-08  3:00 pm
[ SAT ]      [ UNSAT ]
21            Exit Technical Specification          CUE: Another Operator has LCO 2.15, for trip units 1, 9 and      logged out of the Technical
: 12.                                    Specification.
[ SAT ]      [ UNSAT ]
22            Repeat Step 7.13 for all              Determined that Channel "D" channels to be adjusted.               was the only channel that needed to be adjusted.
[ SAT ]      [ UNSAT ]
23            Record channels Final                  AI-31A/B/C/D NUCLEAR PWR CALIBRATE                  Record Final NUCLEAR PWR Dial settings on Test Data            CALIBRATE Dial settings for Sheet 1.                              channels A and D.
[ SAT ]      [ UNSAT ]
24            Record channels Final T              AI-31A/B/C/D PWR CALIBRATE Dial settings            Record Final T PWR on Test Data Sheet 1.                  CALIBRATE Dial settings for channels A and D.
[ SAT ]      [ UNSAT ]
25            Record channels FINAL T              AI-31A/B/C/D Power readings on Test Data            Record Final T Power Sheet 1.                              readings for channels A and D.
[ SAT ]      [ UNSAT ]
Page 8 of 10


FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 2 OF 8 R12 RPS POWER ADJUSTMENT SAFETY RELATED
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP                    ELEMENT                              STANDARD 26            Record channels FINAL NI              AI-31A/B/C/D Power readings on Test Data            Record Final T Power Sheet 1.                              readings for channels A and D.
: 1. PURPOSE
[ SAT ]      [ UNSAT ]
CUE: Another Operator will complete this test for channels B and C.
Termination Criteria:  RPS channel 'D" NI Power and T Power have been adjusted to agree with XC-105 per OP-ST-RPS-0005.
Page 9 of 10


1.1 Instructions for adjusting T and NI Power indication.  
Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 INITIAL                The plant is operating at full power.
CONDITIONS:            Secondary Calorimetric measurement, XC-105, indicates the reactor is operating at 1497.5 MWt.
The STA has verified XC-105 is valid.
The prerequisites for OP-ST-RPS-0005. RPS POWER ADJUSTMENT, have been met.
INITIATING CUE:  You have been directed to perform OP-ST-RPS-0005, RPS POWER ADJUSTMENT, for channels A and D, and adjust any channels that need adjustment.
Page 10 of 10


1.2 This test in conjunction with OP-ST-SHI FT-0001 satisfies the requir ements of Technical Specifications, Section 3.1, Table 3-1, Item 1.b.
PAGE 1 OF 8 Fort Calhoun Station Unit No. 1 OP-ST-RPS-0005 SURVEILLANCE TEST RPS POWER ADJUSTMENT Change No.        EC 42242 Reason for Change Added a precaution addressing the fluctuating RPSCIP DVM readings. Converted from WordPerfect to Word.
: 2. REFERENCES/COMMITMENT DOCUMENTS
Requestor        R. Lowery Preparer          L Hautzinger Issue Date        07-17-08 3:00 pm R12


2.1 Technical Specifications:  
FORT CALHOUN STATION                                                          OP-ST-RPS-0005 SURVEILLANCE TEST                      CONTINUOUS USE                            PAGE 2 OF 8 RPS POWER ADJUSTMENT SAFETY RELATED
 
: 1. PURPOSE 1.1  Instructions for adjusting T and NI Power indication.
2.15, Table 2-2, Items 2, 3 and 9 3.1, Table 3-1, Item 1.a., Channel Check 3.1, Table 3-1, Item 1.b., Channel Adjustment  
1.2  This test in conjunction with OP-ST-SHIFT-0001 satisfies the requirements of Technical Specifications, Section 3.1, Table 3-1, Item 1.b.
 
: 2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:
2.2 SO-G-23, Surveillance Test Program  
* 2.15, Table 2-2, Items 2, 3 and 9
 
* 3.1, Table 3-1, Item 1.a., Channel Check
2.3 OI-NI-1, Nuclear Instrument ation System Normal Operation
* 3.1, Table 3-1, Item 1.b., Channel Adjustment 2.2 SO-G-23, Surveillance Test Program 2.3 OI-NI-1, Nuclear Instrumentation System Normal Operation
: 3. DEFINITIONS None
: 3. DEFINITIONS None
: 4. TEST EQUIPMENT None
: 4. TEST EQUIPMENT None
: 5. PRECAUTIONS AND LIMITATIONS
: 5. PRECAUTIONS AND LIMITATIONS 5.1  All anomalies and deficiencies shall be reported immediately to the immediate Supervisor and the Shift Manager, and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.
5.2  The System Engineer shall be notified within 24 hours of the completion of this test, of any marginal, unexpected or unacceptable results.
5.3  This Surveillance Test is performed on demand as necessary to provide for the adjustment of indicated RPS power.
5.4  This Surveillance Test is not required during Reactor Startup or Shutdown periods which includes Power Operation less than 25%.
R12


5.1 All anomalies and deficiencies shall be reported immediately to the immediate Supervisor and the Shift Manager, and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Techni cal Specifications, have not been exceeded.  
FORT CALHOUN STATION                                                              OP-ST-RPS-0005 SURVEILLANCE TEST                      CONTINUOUS USE                                PAGE 3 OF 8 5.5  Prior to making adjustments with power levels below 50% the Reactor Engineer or Manager-Operations is to be contacted for concurrence.
5.6  The Reactor Engineer shall be notified within 24 hours of the completion of this test of any marginal, unexpected, or unacceptable results.
5.7  RPS Trip Units may be bypassed per the following Limiting Conditions for Operation (LCO):
* Technical Specifications, Section 2.15, Table 2-2, Items 2, 3 and 9 5.8  RPSCIP DVM readings fluctuate, the operator should record a best estimate average of the fluctuating values for NI and DELTA T power. Recording NI or DELTA T power when the NI - DELTA T deviation meter reads zero is not an accurate way of determining the best estimate average for either reading. (CR 2007-4657)
: 6. PREREQUISITES                                                                INITIALS/DATE 6.1  Procedure Revision Verification:
12                                                            JEK    3/31/09 Revision No.                                                                        /
JEK 6.2  Reactor power is greater than 25% and stable.                                        / 3/31/09 CAUTION Careful consideration is required prior to adjusting the channels with lower -T power reading lower than actual power due to a flow stream anomaly. This is to ensure that -T power indication will not be excessively high in the event that the anomaly clears after adjustment is made.
6.3  IF a flow stream anomaly was confirmed AND plant conditions have stabilized, THEN the concurrence between the Manager Operations and Supervisor-Primary Systems is required prior to adjusting -T N/A power.                                                                              /
Manager-Ops N/A /
Sup-Primary Sys 6.4  IF Reactor power is less than 50%, THEN notify the Reactor Engineer N/A or Manager-Operations for concurrence on performing adjustments.                    /
6.5  No other test is in progress which could potentially affect this test, or if JEK    3/31/09 this test were performed, could have an effect on that test.                         /
R12


5.2 The System Engineer shall be notified within 24 hours of the completion of this test, of any marginal, unexpected or unacceptable results.  
FORT CALHOUN STATION                                                          OP-ST-RPS-0005 SURVEILLANCE TEST                      CONTINUOUS USE                              PAGE 4 OF 8 6.6  Shift Manager authorizes performance of this test:
SHIFT MANAGER Shift Manager                                                  Date/Time 3/31/09 / 0730
: 7. PROCEDURE                                                                        INITIALS 7.1  Record all four (4) Channel T Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range Safety Drawers.
7.2  Record all four (4) Channel NI Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range Safety Drawers.
7.3  Record all four (4) channels Initial T Power readings from RPSCIP DVM on Test Data Sheet 1.
7.4  Record all four (4) channels Initial NI Power readings from RPSCIP DVM on Test Data Sheet 1.
7.5  Subtract the Scaling Amp Offset from Initial T Power reading for all four (4) channels and record on Test Data Sheet 1.
7.6  Subtract the Scaling Amp Offset from the Initial NI Power reading for all four (4) channels and record on Test Data Sheet 1.
7.7  Record all four (4) channels Initial T Pwr Calibrate and Nuclear Pwr Calibrate dial (Power Range Monitor Drawer) settings on Test Data Sheet 1.
7.8  Perform the following for each RPS channel to be adjusted.                A    B  C  D 7.8.1    Place RPSCIP DVM Meter Input Switch to METER INPUT position.                                                      [ ] [ ] [ ] [ ]
7.8.2    Push +10V pushbutton and verify DVM reads +9.800 to
              +10.200V.                                                      [ ] [ ] [ ] [ ]
7.8.3    Push -10V pushbutton and verify DVM reads -9.800 to
              -10.200V.                                                      [ ] [ ] [ ] [ ]
7.8.4    Push ZERO pushbutton and verify DVM reads -0.200 to
              +0.200V.                                                       [ ] [ ] [ ] [ ]
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5.3 This Surveillance Test is performed on demand as necessary to provide for the adjustment of indicated RPS power.  
FORT CALHOUN STATION                                                        OP-ST-RPS-0005 SURVEILLANCE TEST                      CONTINUOUS USE                          PAGE 5 OF 8 7.9  Verify XC105 Is valid.                                                          STA STA 7.10 Ensure all XC105 inputs have either an active scan status or a conservative value input per RE-CPT-RX-0003.                                                STA STA 7.11 IF XC105 input has been removed from scan, THEN ensure a conservative N/A input for current plant conditions has been input per RE-CPT-RX-0003.
STA N/A SM 7.12 Record the current value of thermal power (XC105) and calculate the Thermal Power on Test Data Sheet 1.
NOTE: RPS Channels may be adjusted in any order, but only one channel may be done at a time.
7.13 Adjust one RPS Channel by performing the following:                    A    B  C  D 7.13.1    Enter Technical Specification Limiting Condition for Operation 2.15, Table 2-2, Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12.                                          [ ] [ ] [ ] [ ]
7.13.2    Bypass trip units 1, 9 and 12.                              [ ] [ ] [ ] [ ]
7.13.3   Place the DVM selector switch to NUCLEAR PWR.              [ ] [ ] [ ] [ ]
CAUTION Ensure the Nuclear Pwr Calibrate Potentiometer is used, not the Subchannel Gain Adjust Potentiometer.
7.13.4    Adjust the Power Range Monitor NUCLEAR PWR CALIBRATE potentiometer until the DVM equals the Thermal Power plus the NI Scaling Amp Offset.              [ ] [ ] [ ] [ ]
7.13.5    Place the DVM selector switch to T PWR.                    [ ] [ ] [ ] [ ]
7.13.6    Adjust T PWR CALIBRATE potentiometer until the NUCLEAR PWR-T PWR (%) sigma meter is nulled (0 deviation).                                              [ ] [ ] [ ] [ ]
7.13.7    Verify trip units are RESET, then remove the Bypass Keys for Trip Units 1, 9 and 12.                                 [ ] [ ] [ ] [ ]
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5.4 This Surveillance Test is not required during Reactor Startup or Shutdown periods which includes Power Operation less than 25%.  
FORT CALHOUN STATION                                                            OP-ST-RPS-0005 SURVEILLANCE TEST                        CONTINUOUS USE                            PAGE 6 OF 8 7.13.8  Exit Technical Specification LCO 2.15, for trip units 1, 9 and
: 12.                                                              [ ] [ ] [ ] [ ]
7.14 Repeat Step 7.13 for all channels to be adjusted.                        [ ] [ ] [ ] [ ]
7.15 Record all four (4) channels Final NUCLEAR PWR CALIBRATE Dial settings on Test Data Sheet 1.                                            [ ] [ ] [ ] [ ]
7.16 Record all four (4) channels Final T PWR CALIBRATE Dial settings on Test Data Sheet 1.                                                    [ ] [ ] [ ] [ ]
7.17 Record all four (4) channels FINAL T Power readings on Test Data Sheet 1.                                                                  [ ] [ ] [ ] [ ]
7.18 Record all four (4) channels FINAL NI Power readings on Test Data Sheet 1.                                                                  [ ] [ ] [ ] [ ]
Completed by                                                          Date/Time        /
: 8. RESTORATION 8.1  Shift Manager notified this test is completed:
Shift Manager                                                    Date/Time        /
: 9. ACCEPTANCE CRITERIA 9.1  Corrected RPS T Power and corrected RPS NI Power differ from the calculated %
Rated Power (Core Thermal Power) by less than 1%.
: 10. TEST RECORD 10.1 This entire procedure.
: 11. REVIEW 11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours following completion of this test.
Evaluated by                                                    Date/Time        /
STA Reviewed by                                                      Date/Time        /
Shift Manager R12


FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 3 OF 8 R12 5.5 Prior to making adjustment s with power levels below 50
FORT CALHOUN STATION                                                     OP-ST-RPS-0005 SURVEILLANCE TEST                     CONTINUOUS USE                       PAGE 7 OF 8 Test Data Sheet 1 - Calibration Record Thermal Power =                              &#xf7; 15 =                      %
% the Reactor Engineer or Manager-Operations is to be contacted for concurrence.
(XC105)
Parameter                        AI-31A          AI-31B          AI-31C    AI-31D Initial NI Power (DVM)
NI Scaling Amp Offset Initial NI Power, DVM minus scaling amp offset Initial NUCLEAR PWR CALIBRATE Dial Setting Final NUCLEAR PWR CALIBRATE Dial Setting Final NI Power (DVM)
Initial T Power (DVM)
T Scaling Amp Offset Initial T Power, DVM minus scaling amp offset Initial T PWR CALIBRATE Dial Setting Final T PWR CALIBRATE Dial Setting Final T Power (DVM)
R12


5.6 The Reactor Engineer shall be notified within 24 hours of the completion of this test of any marginal, unexpected, or unacceptable results.
FORT CALHOUN STATION                OP-ST-RPS-0005 SURVEILLANCE TEST    CONTINUOUS USE    PAGE 8 OF 8 Comment Sheet R12


5.7 RPS Trip Units may be bypassed per the following Limiting Conditions for Operation (LCO):  Technical Specifications, Section 2.15, Table 2-2, Items 2, 3 and 9
RPS Scaling Amp Offset Measurement Record.
CHANNEL              A        B          C          D NI Power Scaling Amp      0.2     0.3        0.3        0.2 Offset Delta T Power Scaling    0.3      0.2         0.3        0.3 Amp Offset


5.8 RPSCIP DVM readings fluct uate, the operator should record a best estimate average of the fluctuating values for NI and DELTA T power. Recording NI or DELTA T power when the NI - DELTA T deviation meter reads zero is not an accurate way of determining the best estimate average for ei ther reading. (CR 2007-4657)
Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Fort Calhoun                  Scenario No: 2009-2                  Revision: 3 Examiners:          _________________________                    Operators:  _________________________
: 6. PREREQUISITES
_________________________                                _________________________
_________________________                                _________________________
Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.
Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.
Event          Malf      Event                                        Event No.            No.      Type*                                      Description 1                          N-BOPO        Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min)                                  3.
2                          N-ATCO        Rotate Containment Cooling Units In accordance with OI-VA-1.
(10 min) 3                          C-ATCO        Dropped CEA - Tech Spec Entry.
LE CUE                      C-BOPO 4                          R-ATCO        AOP-05 shutdown to 70% Power.
N-BOPO 5                           I-ATCO        Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE                                    High.
6                          C-BOPO        Loss of 161 KV - Tech Spec Entry.
LE CUE 7                          C-ATCO        Another Dropped CEA - Manual Reactor Trip Required.
LE CUE 8                           M-ALL        Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
*        (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)        Actual Attributes
: 1. Total malfunctions (5-8)                                                        5
: 2. Malfunctions after EOP entry (1-2)                                              1
: 3. Abnormal events (2-4)                                                          3
: 4. Major transients (1-2)                                                          1
: 5. EOPs entered/requiring substantive actions (1-2)                               1
: 6. EOP contingencies requiring substantive actions (0-2)                          1
: 7. Critical tasks (2-3)                                                            2


6.1 Procedure Revision Verification:
Appendix D                          Operator Actions                          Form ES-D-2 Scenario No: 2009-2    Revision: 3                Event No.: 1         Page 2 of 13 Event


Revision No.
== Description:==
INITIALS/DATE
Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment 3.
Time    Position                        Applicants Actions or Behavior BOPO      Obtain copy of OI-CE-1, Attachment 3, Normal Rotation of Condenser Evacuation Pumps.
BOPO      Read Notes on page 12 of procedure.
BOPO      Direct EONT to ensure Seal Water Makeup is properly aligned:
FW-1351, Separator Tanks Condensate Seal Water Supplu Isolation Valve is Open FW-1349, Vacuum Pumps Separator Tanks Supply Header Isolation is Open DW-357 Condenser Vacuum Pumps Seal Water Supply Line Isolation Valve is Closed.
BOPO      Direct EONT to ensure Separator Tank level is within the gage glass and at least 8 inches.
BOPO      Start Condenser Evacuation Pump, FW-8C.
Note: ammeter will remain pegged for a relatively long time. This is normal.
BOPO      Verify proper operation of FW-8C.
BOPO      Direct EONT to throttle open VD-333, FW-43 Makeup Float bypass valve.
BOPO      Stop FW-8A by placing control switch in AFTER STOP.
BOPO      Direct EONT to close VD-317, FW-41 Makeup Float bypass valve.


/    6.2 Reactor power is greater than 25% and stable.  /
Appendix D                          Operator Actions                        Form ES-D-2 Scenario No: 2009-2      Revision: 3            Event No.: 2          Page 3 of 13 Event
CAUTION Careful consideration is required prior to adjusting the channels with lower -T power reading lower than actual power due to a flow stream anomaly. This is to ensure that -T power indication will not be excessively high in the event that the anomaly clears after adjustment is made.
6.3 IF a flow stream anomaly was confirmed AND plant conditions have stabilized, THEN the concurrenc e between the Manager Operations and Supervisor-Primary Systems is required prior to adjusting -T power.   


/ Manager-Ops
== Description:==
Rotate Containment Cooling Units.
Time    Position                      Applicants Actions or Behavior CRS        Direct ATCO to place VA-3B in service and shutdown VA-7D in accordance with OI-VA-1, Attachment 1, step 2 and Attachment 2, step 4 .
(Start B shut down D following maintenance)
ATCO      Obtain a copy of OI-VA-1, Attachments 1 and 2.
ATCO      Momentarily place HCV-401B/D to OPEN.
ATCO      Ensure HCV-401C is closed.
ATCO      Momentarily place HCV-401A/C to CIRC.
ATCO      Throttle open HCV-401C maintaining CCW discharge header pressure at least 70 psig.
ATCO      Monitor:
FI-417, VA-1B flow TIC-421, VA-1B temperature PI-499, CCW Discharge Header Pressure TIC-2800, CCW Discharge header temperature TI-717 Fan VA-3B outlet temperature ATCO      Start VA-3B and monitor:
VA-3B Current PIC-701, Fan VA-3B DP PI-707 , Fan VA-3B filter DP PI-709, Fan VA-3B Cooling Coil DP TI-717 Fan VA-3B outlet temperature ATCO      Stop VA-7D ATCO      Throttle close HCV-403C maintaining CCW discharge header pressure less than 125 psig ATCO      Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3,A1,A1-U) in alarm ATCO      Momentarily place HCV-403A/C to ISOL ATCO      Momentarily place HCV-403B/D to CLOSE


/ Sup-Primary Sys 6.4 IF Reactor power is less than 50%, THEN notify the Reactor Engineer or Manager-Operations for concu rrence on performing adjustments.
Appendix D                          Operator Actions                            Form ES-D-2 Scenario No: 2009-2    Revision: 3              Event No.: 3            Page 4 of 13 Event
  /    6.5 No other test is in progress which c ould potentially affect this test, or if this test were performed, coul d have an effect on that test.  
  /
FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 4 OF 8 R12 6.6 Shift Manager authorizes performance of this test:


Shift Manager  Date/Time /
== Description:==
: 7. PROCEDURE
Dropped CEA - Tech Spec Entry.
Time     Position                        Applicants Actions or Behavior ATCO      Identify event from Dropped Rod and other alarms (CB-4 A20 E6, CB-4 A8 A5L, B1U, B1L, B2L, B5L, C1U, C2U, C5L).
ATCO      Determine that only one rod has dropped (rod #1, grp 4).
CRS        Enter AOP-02 (CEA AND CONTROL SYTEM MALFUNCTIONS),
Section III (Misaligned Group 4 CEA).
CRS        Read Caution and Notes. (May be performed after stabilizing plant.)
CRS        Direct ATCO to stop all CEA movement.
CRS        Direct BOP Operator to adjust turbine load to match reactor power.
BOPO      Reduce turbine load to match reactor power using T-cold indication.
CRS        Direct ATC to control pressurizer pressure (2075-2150 psia) and level (within 2% of programmed value).
ATCO      Control pressurizer pressure (2075-2150 psia) and level (within 2% of programmed value).
ATCO      Reset Charging Pump Bistables if needed to shutdown a Charging Pump that started automatically.
CRS        Direct ATC Operator to reset rod drop bistables.
ATCO      Reset rod drop bistables on:
RPS Linear Power Channels Power Range Control Channels CRS        Notify System Operations of the power reduction.
CRS        Notify Work Week Manager or Reactor Engineer.
Continued on Next Page


7.1 Record all four (4) Channel T Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range
Appendix D                          Operator Actions                              Form ES-D-2 Scenario No: 2009-2      Revision: 3              Event No.: 3              Page 5 of 13 Event


Safety Drawers.
== Description:==
INITIALS 
Dropped CEA - Tech Spec Entry, continued Time    Position                        Applicants Actions or Behavior CRS        LCO 2.10.2(4)e. - One full length CEA misaligned from any other CEA's in (TS)      its group by 18 inches or more.
Required Actions:
Reactor power must be reduced to less than 70% within one hour.
The CEA must be realigned or declared inoperable within one hour following the power reduction.
If the CEA is declared inoperable, the reactor must be in hot shutdown within an additional 5 hours.
CRS        Inform ATC and BOP operators that Tech Specs and AOP-02 require a power reduction to less than 70% within one hour using boration.
CRS        If Pressurizer pressure lowers to 2075 psia or less, then enter Technical Specification LCO 2.10.4(5) - DNBR Margin During Power Operation Above 15% of Rated Power.
Required Actions:
Restore Pressurizer Pressure greater than or equal to 2075 psia within 2 hours.
Or else, reduce power to less than 15% within the next 8 hours.


7.2 Record all four (4) Channel NI Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-2    Revision: 3              Event No.: 4 Page 6 of 13 Event


Safety Drawers.  
== Description:==
AOP-05 Emergency Shutdown to 70% Power.
Time    Position                      Applicants Actions or Behavior CRS      Direct ATCO and BOPO to commence a power reduction using AOP-05.
CRS      Read AOP-05 Notes on page 3 CRS      Direct ATCO to begin boration from the SIRWT ATCO      Begin boration by:
Ensuring one charging pump running Opening LCV-218-3,"Charging Pump Suction SIRWT Isolation Valve" Closing LCV-218-2, "VCT Outlet Valve" CRS      Notify System Operations that power will be reduced.
BOPO      Reduce turbine load using potentiometer as needed to control RCS T-cold per TDB Figure III.1, "T-ave Program."
ATCO/    Monitor and control RCS parameters during power reduction:
BOPO          T-cold 527-545&deg;F Pressurizer Level 45-60%
ATCO      Maximize heaters and spray by placing each control switch in ON:
225 KW Backup Htrs Bank 1 Group 1/2/3 150 KW Backup Htrs Bank 2 Group 4/5 150 KW Backup Htrs Bank 3 Group 8/9 225 KW Backup Htrs Bank 4 Group 10/11/12 ATCO      Adjust the selected Pressurizer Pressure controller setpoint pushbuttons to maintain 2100 psia, if required.
CRS      Direct the shift chemist to prepare to sample the RCS due to the power (TS)      reduction.
NOTE: Technical Specification 3.2 (Table 3-4) requires a sample be taken between 2-8 hours following a power change exceeding 15% power within a 1 hour period. The sample must be analyzed for Dose Equivalent I-131.
ATCO      May contact the Aux Building Operator to verify sufficient Waste Holdup Tank capacity for power reduction.


7.3 Record all four (4) channels Initial T Power readings from RPSCIP DVM on Test Data Sheet 1.
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-2      Revision: 3               Event No.: 5           Page 7 of 13 Event
7.4 Record all four (4) channels Initial NI Power readings from RPSCIP DVM on Test Data Sheet 1.
7.5 Subtract the Scaling Amp Offset from Initial T Power reading for all four (4) channels and record on Test Data Sheet 1.
7.6 Subtract the Scaling Amp Offset from the Initial NI Power reading for all four (4) channels and record on Test Data Sheet 1.
7.7 Record all four (4) channels Initial T Pwr Calibrate and Nuclear Pwr Calibrate dial (Power Range Monitor Draw er) settings on Test Data Sheet 1.
7.8 Perform the following for eac h RPS channel to be adjusted.
7.8.1 Place RPSCIP DVM Meter Input Switch to METER INPUT position. A      B    C    D 


[  ]  [  ]
== Description:==
[  ]  [  ]
Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails High.
7.8.2 Push +10V pushbutton and verify DVM reads +9.800 to  
Time    Position                        Applicants Actions or Behavior ATCO      Respond to Pressurizer Pressure Off-Normal HI/LO Channel Y Alarm.
+10.200V.
(CB-1,2,3/A4 B4)
[  ]  [  ]
ATCO      Identify and report high indication on controlling channel and lowering pressure on other channel.
[  ]  [  ]
ATCO/      Refer to ARP.
7.8.3 Push -10V pushbutton and verify DVM reads -9.800 to  
BOPO CRS        Direct ATCO to transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure.
-10.200V.
ATCO      Transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure, as directed.
[  ]  [  ]
ATCO      Monitor and control pressurizer pressure.
[  ]  [  ]
CRS        Notify Work Week Manager of the instrument failure.
7.8.4 Push ZERO pushbutton and verify DVM reads -0.200 to
+0.200V.   [  ]  [  ]
[  ]  [  ]


FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 5 OF 8 R12 7.9 Verify XC105 Is valid. STA    7.10 Ensure all XC105 inputs have either an active scan status or a conservative value input per RE-CPT-RX-0003.
Appendix D                          Operator Actions                              Form ES-D-2 Scenario No: 2009-2      Revision: 3              Event No.: 6              Page 8 of 13 Event
STA    7.11 IF XC105 input has been removed from scan, THEN ensure a conservative input for current plant conditions has been input per RE-CPT-RX-0003.
STA SM    7.12 Record the current value of therma l power (XC105) and calculate the Thermal Power on Test Data Sheet 1.
NOTE:  RPS Channels may be adjusted in any order, but only one channel may be done at a time.


7.13 Adjust one RPS Channel by performing the following:  
== Description:==
Loss of 161 KV - Tech Spec Entry.
Time    Position                        Applicants Actions or Behavior BOPO      Identify loss of 161 KV from numerous alarms on CB-20. (CB-20 A15 A1, A2, A3, D5) (CB-20 A17 A2, C4, D2) Determine and report that busses 1A3 and 1A4 have fast transferred and are powered.
CRS        Enter AOP-31, section II All 4160 busses fed from 22 KV Read Notes.
CRS/      Verify 2 FW pumps, 2 Condensate pumps and 2 Heater drain pumps BOPO      operating.
CRS/      Ensure Main Generator Terminal voltage less than 22,000 volts.
BOPO CRS/      Establish balanced 4160V Bus loading on T1A1 and T1A2 by ensuring all BOPO      of the following pumps are operating:
FW-2A, Condensate Pump FW-4A, Feed Pump FW-5A, Heater Drain Pump BOPO starts Heater Drain Pump, FW-5A CRS/      Verify 480 bus voltages greater than 430 volts BOPO CRS        Direct BOPO to match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 BOPO      Match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 (step 5 of AOP-31)
CRS        Direct that signs be placed at entrances to switchgear rooms Review EOP-02, EOP-07 and EOP-20 Continued on Next Page


7.13.1 Enter Technical Specific ation Limiting Condition for Operation 2.15, Table 2-2, Ite ms 2, 3 and 9 for RPS Trip Units 1, 9 and 12.
Appendix D                        Operator Actions                            Form ES-D-2 Scenario No: 2009-2     Revision: 3               Event No.: 6          Page 9 of 13 Event


A      B    C    D  
== Description:==
Loss of 161 KV - Tech Spec Entry., Continued.
CRS        LCO 2.7(2)c.- Loss of both service transformers T1A-3 and T1A-4 (TS)      inoperable due to a loss of the 161 KV incoming line.
Required Actions:
Verify both Diesel Generators are Operable.
Notify the NRC Operations center within four hours due to the loss of 161 KV.
Special Report must be submitted to the NRC within 48 hours.
LCO 2.0.1 - LCO action requirement cannot be met Due to the loss of 161 KV and D/G-1 being inoperable, Tech Spec 2.0.1 must be entered.
Required Actions:
Place the plant in hot shutdown within 6 hours.
However, taking the main generator off-line will result a loss of offsite power.
CRS        Report situation to station management.


[  ]  [  ]
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-2     Revision: 3               Event No.: 7           Page 10 of 13 Event
[  ]  [  ]
7.13.2 Bypass trip units 1, 9 and 12.  [ 
]  [  ]
[  ]  [  ]
7.13.3 Place the DVM selector switch to NUCLEAR PWR. [  ]  [  ]
[  ]  [  ]
CAUTION Ensure the Nuclear Pwr Calibrate Potentiometer is used, not the Subchannel Gain Adjust Potentiometer.
7.13.4 Adjust the Power Ra nge Monitor NUCLEAR PWR CALIBRATE potentiometer until the DVM equals the Thermal Power plus the NI Scaling Amp Offset.


[  ]  [  ]
== Description:==
[  ]  [  ]
Another Dropped CEA - Manual Reactor Trip Required.
7.13.5 Place the DVM selector switch to T PWR. [  ]  [ 
Time    Position                      Applicants Actions or Behavior ATCO      Report that another CEA has fallen into the core.
]  [  ]  [  ]
CRS      Direct ATCO to trip the reactor.
7.13.6 Adjust T PWR CALIBRATE potentiometer until the NUCLEAR PWR-T PWR (%) sigma meter is nulled (0 deviation).  
ATCO      Manually trip the reactor within 60 seconds of the second CEA drop.
(CT)
CRS      Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.
ATCO      Perform Reactivity Control Actions:
Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met.
BOPO      Verify Turbine Tripped:
Stop and Intercept Valves are Closed BOPO      Verify Generator Breakers Tripped:
Breakers 3451-4/5 Generator Field Breaker BOPO      Verify vital buses, 1A3 and 1A4, are energized.
Reports buses 1A3 and 1A4 are deenergized Directs EONT to Minimize DC loads per EOP/AOP Attachment 6 Reports that DG-2 is running but output breaker is open. DG-1 is out for maintenance BOPO      IF SIAS has initiated, THEN verify both Diesel Generators have started.
BOPO      Verify non-vital buses, 1A1 and 1A2, are energized.
Reports buses 1A1 and 1A2 are deenergized.
BOPO      Verify both 125VDC buses are energized.
BOPO      Verify Instrument air status:
Instrument Air pressure is at least 90 psig At least 1 air compressor running Reports that no compressors are running a IA pressure is lowering.


[  ]  [  ]
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-2    Revision: 3            Event No.: 7             Page 11 of 13 Event
[  ]  [  ]
7.13.7 Verify trip units are RESET, then remove the Bypass Keys for Trip Units 1, 9 and 12.
[  ]  [  ]
[  ]  [  ]


FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 6 OF 8 R12 7.13.8 Exit Technical Specification LCO 2.15, for trip units 1, 9 and
== Description:==
: 12.  [  ]  [  ]
Another Dropped CEA - Manual Reactor Trip Required, Continued.
[  ]  [  ]
Time    Position                      Applicants Actions or Behavior ATCO      Verify CCW and Raw water status:
7.14 Repeat Step 7.13 for all channels to be adjusted.  [  ]  [  ]  [  ]  [  ]
At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open.
7.15 Record all four (4) channels Final NUCLEAR PWR CALIBRATE Dial settings on Test Data Sheet 1.
Reports that no CCW or Raw Water Pumps are operating.
[  ]  [  ]
ATCO      Verify Inventory Control:
[  ]  [  ]
Pressurizer Level 30-70% trending toward 45-60%
7.16 Record all four (4) channels Final T PWR CALIBRATE Dial settings on Test Data Sheet 1.
Subcooling, at least 20&deg;F ATCO      Verify Pressure Control:
[  ]  [  ]
RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO      Verify Core Heat Removal:
[  ]  [  ]
RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10&deg;F Reports that no RCPs are operating.
7.17 Record all four (4) channels FINAL T Power readings on Test Data Sheet 1.   [  ]  [  ]
BOPO      Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):
[  ]  [  ]
Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%
7.18 Record all four (4) channels FINA L NI Power readings on Test Data Sheet 1.  [  ]  [  ]
No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF Close blowdown isolation valves, HCV-1387A/B and HCV-1388A/B Reports that No FEED Pumps or Condensate Pumps are operating.
[  ]  [  ]
Completed by  Date/Time  /
: 8. RESTORATION


8.1 Shift Manager notified this test is completed:  
Appendix D                        Operator Actions                          Form ES-D-2 Scenario No: 2009-2    Revision: 3            Event No.: 7          Page 12 of 13 Event


Shift Manager  Date/Time  /
== Description:==
: 9. ACCEPTANCE CRITERIA
Another Dropped CEA - Manual Reactor Trip Required, Continued.
Time    Position                      Applicants Actions or Behavior BOPO      Verify Steam Dump and Bypass Valves are controlling BOTH of the following:
T-cold 525-535&deg;F S/G Pressure 850-925 psia Reports that Steam Dump and Bypass valves are not operating.
Controls S/G pressure using HCV-1040 or MS-291 and MS-292 as needed.
ATCO      Verify containment conditions:
No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120&deg;F CRS      If bus 1A4 is repowered, then enter EOP-02, "LOSS OF OFFSITE POWER, LOSS OF FORCED CIRCULATION,"
If bus 1A4 is not powered, then enter EOP-07, "STATION BLACKOUT"


9.1 Corrected RPS T Power and corrected RPS NI Power differ from the calculated %
Appendix D                        Operator Actions                            Form ES-D-2 Scenario No: 2009-2      Revision: 3            Event No.: 8            Page 13 of 13 Event
Rated Power (Core Therma l Power) by less than 1%.
: 10. TEST RECORD


10.1 This entire procedure.
== Description:==
: 11. REVIEW
Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.
Time    Position                      Applicants Actions or Behavior BOPO      Report that CW-1C breaker failed to trip within 15 minutes of reactor trip.
(CT)      (This prevents D/G-2 breaker from closing) Direct EONT to manually trip the breaker for CW-1C.
(NOTE: EONT will trip breaker on Lead Examiner CUE).
CRS        When D/G-2 output breaker closes, Direct BOPO to verify bus 1A4 voltage.
CRS        If EOP-07 was entered, Transitions to EOP-02, "
Scenario ends when EOP-02 has been entered.


11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours following completion of this test.
FORT CALHOUN STATION                                                                                                            FC-95 FORM SHIFT TURNOVER LOG                                                                          Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 Days                      Nights      X PLANT STATUS:
Evaluated by  Date/Time  /
MODE:        1    X    2      3      Rx Power:          98.60%                        Rod Position: All Groups ARO Prcs (>2075 psia):        2091 psia   Tcold (<543&deg;F):              542.8            &deg;F Lpzr (48 - 60%):                60 % (Actual)
STA Reviewed by   Date/Time  /
Comments:
Shift Manager
SAFEGUARDS STATUS:
(Log any out-of-service safeguards equipment; include major fire protection equipment)
DG-1 RECENT TEMP MODS: (Within the last month)
TM Number            Date         Description None DEGRADED EQUIPMENT STATUS CR Number          Component/System            Reason Considered Degraded                                  Resolution 2009003571  DG-1                  Out of Service - Replacing contactors for 2CR relays.
SO-O-1 FC/FORM                                                    Page 1 of 3


FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 7 OF 8 R12 Test Data Sheet 1 - Calibration Record Thermal Power =
FORT CALHOUN STATION                                                                                         FC-95 FORM SHIFT TURNOVER LOG                                                    Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 RELEASES IN PROGRESS:                                                        YES          NO          RELEASE #
15 =  % (XC105) Parameter AI-31A AI-31B AI-31C AI-31D Initial NI Power (DVM)
Monitor Tank:          A        B                                                          X Waste Gas Decay Tank:          A      B    C        D                                  X
NI Scaling Amp Offset    Initial NI Power, DVM minus scaling amp offset Initial NUCLEAR PWR CALIBRATE Dial Setting Final NUCLEAR PWR CALIBRATE Dial Setting Final NI Power (DVM)
                                                  .
Initial T Power (DVM)     T Scaling Amp Offset Initial T Power, DVM minus scaling amp offset Initial T PWR CALIBRATE Dial Setting Final T PWR CALIBRATE Dial Setting Final T Power (DVM)    
Containment Pressure Reduction                                                            X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:
PROCEDURE or TEST                                                     REASON None CRS review and discuss procedures in progress (Initial)
INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):
ITEM / LOCATION              DATE                                    ACTION REQUIRED None TEMPORARY LIFTS:
TAGOUT #                EQUIPMENT                                          REASON None POST MAINTENANCE TESTING:
(Equipment, instrument or annunciator requiring PMT for operability)
AVAILABLE Component            YES NO                                  PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:
REPORT MADE EQUIP OOS                DATE/TIME              T.S. / ODCM / G-103              LCO          YES  NO N/A DG-1              3/31/2009 / 0540                TS 2.7(2)j                7 Day                    X SO-O-1 FC/FORM                                                    Page 2 of 3


FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 8 OF 8 R12 Comment Sheet
FORT CALHOUN STATION                                                                             FC-95 FORM SHIFT TURNOVER LOG                                            Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 REMARKS:
* Rotate Condenser Evacuation Pumps, FW-8C on and FW-8A Off per OI-CE-1, Attachment 3.
* Place VA-3A in service then shut down VA-7D per OI-VA-1, Attachments 1 and 2.
* RCS Boron 998            ppm Neutral Blend (gal acid /gal water)10 / 55 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________
Off going                                          On coming S.M.
C.R.S.
L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator                                                          ____
Security Key Transferred (Init)
SO-O-1 FC/FORM                                            Page 3 of 3


FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 5 OF 173 Continuous Use R68 Attachment 1 - Containment Cooling and Filtering Operat ion VA-3A & VA-3B PREREQUISITES
FORT CALHOUN STATION                                                                                         FC-75A FORM                                                                                                              R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 03/31/09        Shift (Circle one)            0600-1800                                1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.
()  INITIALS    1. Procedure Revision Verification Revision No.
Switch              Location            Annunciators in Alarm              Reason out-of-position/in alarm 43-1/D1              AI-30A                                                          DG-1 Out of Service 43-1/1AD1              AI-30A                                                                  ' ''
Date:
BKR 1AD1                CB-20                                                                  ' ''
: 2. OI-VA-1-CL-A has been completed per OP-1.
AI-30A/A30,B-4            DIESEL OFF AUTO                                  ' ''
: 3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment
AI-30A/A30,D-4              BKR OFF AUTO                                    ' ''
AI-30A/A30,E-3       BKR PROTECTION OFF-AUTO                                ' ''
AI-30A/A30, E-4            PANEL TROUBLE                                    ' ''
CB-1,2,3/A1 B-1U  CC WATER FROM COIL VA_1B NO FLOW                  VA-1B is not operating PROTECTED EQUIPMENT                        SIGN LOCATION                          REASON PROTECTED DG-2                        DG-2 Mode Selector Switch                    DG-1 Out of Service BRKR 1AD2


Cooling Coils is operable:
FORT CALHOUN STATION                                                                OI-VA-1 OPERATING PROCEDURE                            C                            PAGE 5 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PREREQUISITES                                                                  (9) INITIALS
VA-1A   VA-1B
: 1. Procedure Revision Verification JEK Revision No. 68              Date: 3/31/09
: 2. OI-VA-1-CL-A has been completed per OP-1.                                          JEK
: 3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment Cooling Coils is operable:
* VA-1A                                                                     X
* VA-1B                                                                     X    JEK
: 4. Electrical power is available to the desired fan(s):
: 4. Electrical power is available to the desired fan(s):
VA-3A, Cont Cooling & Filter Fan, 1B3A-7 VA-3B, Cont Cooling & Filter Fan, 1B4C-8  
* VA-3A, Cont Cooling & Filter Fan, 1B3A-7                                   X
* VA-3B, Cont Cooling & Filter Fan, 1B4C-8                                   X    JEK R68


FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 6 OF 173 Continuous Use R68 Attachment 1 - Containment Cooling and Filtering Operat ion VA-3A & VA-3B PROCEDURE   () INITIALS NOTES 1. Containment HEPA/Charc oal Filter Unit may be in service while painting or other activities in containment as long as volatile organic compound (VOC) to be released in containment does not exceed administrative limits specified in GM-RR-MX-1050. The administrative limits given in the coating procedure is determined to have negligible affect on filter performance. 2. HCV-724A, VA-3A Filtered Air Inlet Damper is permanently open and HCV-724B, VA-3A Unfiltered Air Inle t Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.
FORT CALHOUN STATION                                                                     OI-VA-1 OPERATING PROCEDURE                               C                               PAGE 6 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE                                                                           (9) INITIALS NOTES
CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
: 1. Containment HEPA/Charcoal Filter Unit may be in service while painting or other activities in containment as long as volatile organic compound (VOC) to be released in containment does not exceed administrative limits specified in GM-RR-MX-1050. The administrative limits given in the coating procedure is determined to have negligible affect on filter performance.
: 2. HCV-724A, VA-3A Filtered Air Inlet Damper is permanently open and HCV-724B, VA-3A Unfiltered Air Inlet Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.
CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
: 1. IF VA-3A, Containment Vent Fan, is to be started, THEN perform the following:
: 1. IF VA-3A, Containment Vent Fan, is to be started, THEN perform the following:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-1A as follows:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-1A as follows:
: 1) Momentarily place HCV-400B/D, Cntmt Clg Coil VA-1A AC Vlvs Control SW to OPEN.
: 1)       Momentarily place HCV-400B/D, Cntmt Clg Coil VA-1A AC Vlvs Control SW to OPEN.
: 2) Ensure HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr is closed.         3) Momentarily place HCV-400A/C, Cntmt Clg Coil VA-1A Isol Vlvs Control SW to CIRC.
: 2)       Ensure HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr is closed.
: 4) Throttle open HCV-400C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.  
: 3)       Momentarily place HCV-400A/C, Cntmt Clg Coil VA-1A Isol Vlvs Control SW to CIRC.
 
: 4)       Throttle open HCV-400C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 7 OF 173 Continuous Use R68 Attachment 1 - Containment Cooling and Filtering Operat ion VA-3A & VA-3B PROCEDURE (continued)  ()  INITIALS 1.a    5) Monitor the following parameters:
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FI-416, VA-1A Flow  TIC-420, VA-1A Temp  PI-499, CCW Discharge Header Press  TIC-2800, CCW Discharge Header Temp  TI-715, Fan VA-3A Outlt Temp (AI-44)


FORT CALHOUN STATION                                                                      OI-VA-1 OPERATING PROCEDURE                              C                                PAGE 7 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued)                                                                (9) INITIALS 1.a
: 5)      Monitor the following parameters:
* FI-416, VA-1A Flow
* TIC-420, VA-1A Temp
* PI-499, CCW Discharge Header Press
* TIC-2800, CCW Discharge Header Temp
* TI-715, Fan VA-3A Outlt Temp (AI-44)
CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
: b. Start VA-3A and monitor the following:
: b. Start VA-3A and monitor the following:
VA-3A amps   PIC-700, Fan VA-3A Diff Press (AI-44) PI-706, Fan VA-3A Filter Diff Press (AI-44) PI-708, Fan VA-3A Clg Coil Diff Press (AI-44) TI-715, Fan VA-3A Outlt Temp (AI-44)  
* VA-3A amps
 
* PIC-700, Fan VA-3A Diff Press (AI-44)
NOTE HCV-725A, VA-3B Filtered Air Inle t Damper is permanently open and HCV-725B, VA-3B Unfiltered Air Inlet Damper is permanently closed which  
* PI-706, Fan VA-3A Filter Diff Press (AI-44)
 
* PI-708, Fan VA-3A Clg Coil Diff Press (AI-44)
puts filters in service (EC 41115).
* TI-715, Fan VA-3A Outlt Temp (AI-44)
Control Solenoids are AIPE.         2. IF VA-3B, Cntmt Vent Fan, is to be started, THEN perform the following:
NOTE HCV-725A, VA-3B Filtered Air Inlet Damper is permanently open and HCV-725B, VA-3B Unfiltered Air Inlet Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.
: 2. IF VA-3B, Cntmt Vent Fan, is to be started, THEN perform the following:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-1B as follows:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-1B as follows:
: 1) Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B AC Vlvs Control SW to OPEN.
: 1)       Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B AC Vlvs Control SW to OPEN.
: 2) Ensure HCV-401C, Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr is closed.
: 2)       Ensure HCV-401C, Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr is closed.
FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 8 OF 173 Continuous Use R68 Attachment 1 - Containment Cooling and Filtering Operat ion VA-3A & VA-3B PROCEDURE (continued)  ()  INITIALS 2.a. 3) Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to CIRC.
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: 4) Throttle open HCV-401C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
: 5) Monitor the following parameters:
FI-417, VA-1B Flow  TIC-421, VA-1B Temp  PI-499, CCW Discharge Header Press  TIC-2800, CCW Discharge Header Temp  TI-717, FAN VA-3B Outlet Temp (AI-44)


FORT CALHOUN STATION                                                                      OI-VA-1 OPERATING PROCEDURE                                C                                PAGE 8 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued)                                                                (9) INITIALS 2.a.
: 3)      Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to CIRC.
: 4)      Throttle open HCV-401C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
: 5)      Monitor the following parameters:
* FI-417, VA-1B Flow
* TIC-421, VA-1B Temp
* PI-499, CCW Discharge Header Press
* TIC-2800, CCW Discharge Header Temp
* TI-717, FAN VA-3B Outlet Temp (AI-44)
CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
: b. Start VA-3B and monitor the following:
: b. Start VA-3B and monitor the following:
VA-3B amps   PIC-701, Fan VA-3B Diff Press (AI-44) PI-707, Fan VA-3B Filter Diff Press (AI-44) PI-709, Fan VA-3B Clg Coil Diff Press (AI-44) TI-717, Fan VA-3B Outlt Temp (AI-44)
* VA-3B amps
* PIC-701, Fan VA-3B Diff Press (AI-44)
* PI-707, Fan VA-3B Filter Diff Press (AI-44)
* PI-709, Fan VA-3B Clg Coil Diff Press (AI-44)
* TI-717, Fan VA-3B Outlt Temp (AI-44)
: 3. IF VA-3A is to be shutdown, THEN perform the following:
: 3. IF VA-3A is to be shutdown, THEN perform the following:
: a. Stop VA-3A, Cntmt Vent Fan. (AI-30A)
: a. Stop VA-3A, Cntmt Vent Fan. (AI-30A)
: b. IF CCW flow to the cooler is to be secured, THEN isolate CCW to VA-1A as follows: (CB-1/2/3)
: b. IF CCW flow to the cooler is to be secured, THEN isolate CCW to VA-1A as follows: (CB-1/2/3)
: 1) Throttle close HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.  
: 1)       Throttle close HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
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FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 9 OF 173 Continuous Use R68 Attachment 1 - Containment Cooling and Filtering Operat ion VA-3A & VA-3B PROCEDURE (continued)   () INITIALS 3.b. 2) Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3, A1, A-1U) in alarm.
FORT CALHOUN STATION                                                                   OI-VA-1 OPERATING PROCEDURE                             C                               PAGE 9 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued)                                                             (9) INITIALS 3.b.
: 3) Momentarily place Cntmt Clg Coil VA-1A Isol Vlvs Control SW HCV-400A/C to ISOL.
: 2)       Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3, A1, A-1U) in alarm.
: 4) Momentarily place Cntmt Clg Coil VA-1A Vlvs Control SW HCV-400B/D to CLOSE.
: 3)       Momentarily place Cntmt Clg Coil VA-1A Isol Vlvs Control SW HCV-400A/C to ISOL.
: 4)       Momentarily place Cntmt Clg Coil VA-1A Vlvs Control SW HCV-400B/D to CLOSE.
: 4. IF VA-3B is to be shutdown, THEN perform the following:
: 4. IF VA-3B is to be shutdown, THEN perform the following:
: a. Stop VA-3B, Cntmt Vent Fan (AI-30B).
: a. Stop VA-3B, Cntmt Vent Fan (AI-30B).
: b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-1B as follows:
: b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-1B as follows:
: 1) Throttle close Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr HCV-401C maintaining PI-499, CCW Discharge Header  
: 1)       Throttle close Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr HCV-401C maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
 
: 2)       Verify CC WATER FROM VA-1B NO FLOW (CB-1,2,3, A1, B-1U) in alarm.
Pressure, less than 125 psig.
: 3)       Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to ISOL.
: 2) Verify CC WATER FROM VA-1B NO FLOW (CB-1,2,3, A1, B-1U) in alarm.
: 4)       Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B Vlvs Control SW to CLOSE.
: 3) Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to ISOL.
: 4) Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B Vlvs Control SW to CLOSE.
: 5. Record filter operating times in OP-ST-SHIFT-0001.
: 5. Record filter operating times in OP-ST-SHIFT-0001.
Completed by Date/Time               /  
Completed by                                                           Date/Time       /
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FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 10 OF 173 Continuous Use R68 Attachment 2 - Containment C ooling Operation VA-7C & VA-7D PREREQUISITES
FORT CALHOUN STATION                                                                   OI-VA-1 OPERATING PROCEDURE                               C                             PAGE 10 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PREREQUISITES                                                                     (9) INITIALS
() INITIALS     1. Procedure Revision Verification:  
: 1. Procedure Revision Verification:
 
Revision No. 68            Date:   3/31/09                                    JEK
Revision No.
: 2. OI-VA-1-CL-A has been completed per OP-1.                                         JEK
Date:
: 3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment Cooling Coils is operable:
: 2. OI-VA-1-CL-A has been completed per OP-1.
* VA-8A                                                                     X X    JEK
: 3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment  
* VA-8B
 
: 4. Electrical power is available to the desired fan(s):
Cooling Coils is operable:
* VA-7C, Containment Air Cooling Fan, 1B3C-4C-3                               X
VA-8A   VA-8B
* VA-7D, Containment Air Cooling Fan, 1B3B-4B-4                             X    JEK PROCEDURE CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
: 4. Electrical power is available to the desired fan(s):  
 
VA-7C, Containment Air Cooling Fan, 1B3C-4C-3 VA-7D, Containment Air Cooling Fan, 1B3B-4B-4  
 
PROCEDURE         CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
: 1. IF VA-7C, Cntmt Vent Fan, is to be started, THEN perform the following:
: 1. IF VA-7C, Cntmt Vent Fan, is to be started, THEN perform the following:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-8A as follows:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-8A as follows:
: 1) Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A AC Vlvs Control SW to OPEN.
: 1)     Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A AC Vlvs Control SW to OPEN.
: 2) Ensure HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr is closed.         3) Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to CIRC.  
: 2)     Ensure HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr is closed.
: 3)     Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to CIRC.
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FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 11 OF 173 Continuous Use R68 Attachment 2 - Containment C ooling Operation VA-7C & VA-7D PROCEDURE (continued) () INITIALS     1.a. 4) Throttle open HCV-402C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
FORT CALHOUN STATION                                                                       OI-VA-1 OPERATING PROCEDURE                               C                               PAGE 11 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued)                                                                 (9) INITIALS 1.a.
: 5) Monitor the following parameters:
: 4)       Throttle open HCV-402C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
FI-418, VA-8A Flow TIC-422, VA-8A Temp PI-499, CCW Discharge Header Press TIC-2800, CCW Discharge Header Temp  
: 5)       Monitor the following parameters:
 
* FI-418, VA-8A Flow
CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
* TIC-422, VA-8A Temp
* PI-499, CCW Discharge Header Press
* TIC-2800, CCW Discharge Header Temp CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
: b. Start VA-7C and monitor the following (AI-30A):
: b. Start VA-7C and monitor the following (AI-30A):
VA-7C amps   PIC-702, Fan VA-7C Diff Press (AI-44) PI-710, Fan VA-7C Clg Coil Diff Press (AI-44) TI-719, Fan VA-7C Outlt Temp (AI-44)
* VA-7C amps
* PIC-702, Fan VA-7C Diff Press (AI-44)
* PI-710, Fan VA-7C Clg Coil Diff Press (AI-44)
* TI-719, Fan VA-7C Outlt Temp (AI-44)
: 2. IF VA-7D, Cntmt Vent Fan, is to be started, THEN perform the following:
: 2. IF VA-7D, Cntmt Vent Fan, is to be started, THEN perform the following:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-8B as follows:
: a. IF Containment Cooling is desired, THEN initiate CCW to VA-8B as follows:
: 1) Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B AC Vlvs Control SW to OPEN.
: 1)       Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B AC Vlvs Control SW to OPEN.
: 2) Ensure HCV-403C, Cntmt Clg Coil VA-8B OUTLT Isol Vlv Cntrlr is closed.
: 2)       Ensure HCV-403C, Cntmt Clg Coil VA-8B OUTLT Isol Vlv Cntrlr is closed.
: 3) Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to CIRC.
: 3)       Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to CIRC.
: 4) Throttle open HCV-403C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.  
: 4)       Throttle open HCV-403C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
 
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FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 12 OF 173 Continuous Use R68 Attachment 2 - Containment C ooling Operation VA-7C & VA-7D PROCEDURE (continued)  () INITIALS    2.a. 5) Monitor the following parameters:
FI-419, VA-8B Flow  TIC-423, VA-8B Temp  PI-499, CCW Discharge Header Press  TIC-2800, CCW Discharge Header Temp


CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
FORT CALHOUN STATION                                                                        OI-VA-1 OPERATING PROCEDURE                                C                                PAGE 12 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued)                                                                  (9) INITIALS 2.a.
: 5)      Monitor the following parameters:
* FI-419, VA-8B Flow
* TIC-423, VA-8B Temp
* PI-499, CCW Discharge Header Press
* TIC-2800, CCW Discharge Header Temp CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
: b. Start VA-7D and monitor the following (AI-30B):
: b. Start VA-7D and monitor the following (AI-30B):
VA-7D amps   PIC-703, Fan VA-7D Diff Press (AI-44) PI-711, Fan VA-7D Clg Coil Diff Press (AI-44) TI-721, Fan VA-7D Outlt Temp (AI-44)
* VA-7D amps
* PIC-703, Fan VA-7D Diff Press (AI-44)
* PI-711, Fan VA-7D Clg Coil Diff Press (AI-44)
* TI-721, Fan VA-7D Outlt Temp (AI-44)
: 3. IF VA-7C, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
: 3. IF VA-7C, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
: a. Stop VA-7C (AI-30A).
: a. Stop VA-7C (AI-30A).
: b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8A as follows:
: b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8A as follows:
: 1) Throttle close HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
: 1)       Throttle close HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
: 2) Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to ISOL.
: 2)       Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to ISOL.
: 3) Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A Vlvs Control SW to CLOSE.  
: 3)       Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A Vlvs Control SW to CLOSE.
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FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 13 OF 173 Continuous Use R68 Attachment 2 - Containment C ooling Operation VA-7C & VA-7D PROCEDURE (continued) () INITIALS     4. IF VA-7D, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
FORT CALHOUN STATION                                                               OI-VA-1 OPERATING PROCEDURE                           C                             PAGE 13 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued)                                                         (9) INITIALS
: 4. IF VA-7D, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
: a. Stop VA-7D (AI-30B).
: a. Stop VA-7D (AI-30B).
: b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8B as follows:
: b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8B as follows:
: 1) Throttle close HCV-403C, Cntmt Clg Coil VA-8B Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
: 1)     Throttle close HCV-403C, Cntmt Clg Coil VA-8B Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
: 2) Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to ISOL.
: 2)     Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to ISOL.
: 3) Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B Vlvs Control SW to CLOSE.  
: 3)     Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B Vlvs Control SW to CLOSE.
Completed by                                                    Date/Time          /
R68
 
FORT CALHOUN STATION                                                              OI-CE-1 OPERATING INSTRUCTION                                                      PAGE 11 OF 22 C
Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PREREQUISITES                                                                %  INITIALS
: 1. Procedure Revision Verification:
Revision No. 24                Date:    3/31/09                            JEK
: 2. Power is available for the selected condenser evacuation pump:
    ! FW-8A, Condenser Evacuation Pump, 1B3B-7
    ! FW-8B, Condenser Evacuation Pump, 1B4A-4
    ! FW-8C, Condenser Evacuation Pump, 1B3B-4B-2                            X      JEK R24
 
FORT CALHOUN STATION                                                                OI-CE-1 OPERATING INSTRUCTION                                                        PAGE 12 OF 22 C
Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE                                                                      %  INITIALS NOTES
: 1. The order of pump rotation is A-B-C.
: 2. Seal Water Makeup can be supplied from the Condensate System or the Demineralized Water System as follows:
: a. DW-357, Condenser Vacuum Pumps, FW-8A-8C Seal Water Supply Line Isolation Valve
        !  Normally used during startup (Pumps DW-40A/B must be running)
: b. FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve
        !  Normally used after a Condensate Pump is started
: c. FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve
        !  Normally used as a backup if the Condensate Storage Tank is full
: 1. IF a Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.
    !    FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve, is open
    !    FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve, is open
    !    DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line Isolation Valve (Col. B-5), is closed R24
 
FORT CALHOUN STATION                                                                OI-CE-1 OPERATING INSTRUCTION                                                          PAGE 13 OF 22 C
Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE (continued)                                                            %  INITIALS
: 2. IF no Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.
    !    FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve, is closed
    !    FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve, is closed
    !    DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line Isolation Valve (Col. B-5), is open
: 3. Ensure that the Separator Tank level reads within the gauge glass and at least eight inches prior to starting the Condenser Evacuation Pump.
: 4. Start the Standby Condenser Evacuation Pump (CB-10/11).
: 5. Verify proper operation of the Condenser Evacuation Pump started.
NOTE Condenser Evacuation Separator Tanks are continuously overflowed to minimize the build up of Ammonia in the system.
: 6. Commence continuous feed and bleed of the Condenser Evacuation Separator Tank by throttling open the bypass valve:
    !    VD-317, Separator Tank FW-41 Makeup Float Bypass Valve (FW-8A)
    !    VD-325, Separator Tank FW-42 Makeup Float Bypass Valve (FW-8B)
    !    VD-333, Separator Tank FW-43 Makeup Float Bypass Valve (FW-8C)
: 7. Place the control switch for the Condenser Evacuation Pump being placed in Standby in AFTER STOP (CB-10/11).
: 8. Stop the continuous feed and bleed of the Condenser Evacuation Separator Tank for the Condenser Evacuation Pump being placed in Standby by closing the bypass valve:
    !    VD-317
    !    VD-325
    !    VD-333 Completed by                                                        Date/Time      /
R24
 
Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Fort Calhoun                  Scenario No: 2009-4                  Revision: 5 Examiners:          _________________________                    Operators:  _________________________
_________________________                                _________________________
_________________________                                _________________________
Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.
Turnover: Maintain 50% operation. Rotate CCW Pumps.
Event          Malf      Event                                        Event No.            No.      Type*                                      Description 1                          N-ATCO        Rotate CCW Pumps.
(2 min) 2                          C-BOPO        Isolated Phase Bus Duct Cooling Fan Motor Trips.
LE CUE 3                          I-ATCO        Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE                      TS-CRS        Entry.
4                          I-BOPO        Steam header pressure transmitter, PT-910 Fails High.
LE CUE 5                          C - ATCO      10-15 gpm leak to containment - Tech Spec Entry.
LE CUE                      TS-CRS 6                          C - ATCO      Feedwater Pump Trips, Reactor Trip.
LE CUE 7                          C-BOPO        Blowdown fails to isolate automatically.
8                          M - ALL      Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE                                    Feedwater.
*        (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)        Actual Attributes
: 1. Total malfunctions (5-8)                                                        7
: 2. Malfunctions after EOP entry (1-2)                                              2
: 3. Abnormal events (2-4)                                                          2
: 4. Major transients (1-2)                                                          1
: 5. EOPs entered/requiring substantive actions (1-2)                                1
: 6. EOP contingencies requiring substantive actions (0-2)                          1
: 7. Critical tasks (2-3)                                                          2 or 3
 
Appendix D                        Operator Actions                        Form ES-D-2 Scenario No: 2009-4    Revision: 5              Event No.: 1          Page 2  of 12 Event
 
== Description:==
Rotate CCW Pumps.
Time    Position                        Applicants Actions or Behavior CRS        Directs ATCO to switch operating CCW pump from Pump AC-3A to Pump AC-3C.
ATCO      Obtains and reviews Procedure OI-CC-1, Attachment 2.
ATCO      Directs EONA to Room 69.
ATCO      Read Notes on top of page 9.
ATCO      Starts pump AC-3C.
CRS/      Logs into Technical Specification 2.4(1)b.
ATCO ATCO      Directs EONA to close AC-102, "Pump AC-3A discharge valve."
EONA reports that AC-102 is closed.
ATCO      Verify that PI-499, CCW Pump Discharge Header Pressure, indicates approximately 90 psig.
ATCO      Stops pump AC-3A.
ATCO      Ensures proper operation of pump AC-3C. Directs EONT to reopen Valve AC-102.
ATCO      Directs EONA to open AC-102, "Pump AC-3A discharge valve."
EONT reports that AC-102 is open.
CRS/      Exits Technical Specification 2.4(1)b.
ATCO
 
Appendix D                          Operator Actions                            Form ES-D-2 Scenario No: 2009-4      Revision: 5              Event No.: 2            Page 3 of 12 Event


Completed by Date/Time                /  
== Description:==
Isolated Phase Bus Duct Cooling Fan Motor Trips.
Time    Position                        Applicants Actions or Behavior BOPO      Respond to "ISO PHASE BUS AIR FLOW LO" alarm. ( CB-10,11/A10, A-6U)
BOPO      Determines that the Cooling Fan Motor is not operating.
BOPO      May attempt to restart the Cooling Fan.
CRS/       Direct Electrical Maintenance or EONT to change the belt to the other Bus BOPO      Duct Cooling Fan Motor.
BOPO      Check that generator output is less than 11,200 amps.
BOPO      May monitor each phase temperature.
Electrical Maintenance or the EONT reports that the belt has been changed over.
BOPO      Start the alternate Cooling Fan Motor.
BOPO      Verify low flow alarm clears.
CRS        May refer to AOP-27, "GENERATOR MALFUNCTIONS."


C Continuous Use FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 11 OF 22 R24 Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PREREQUISITES INITIALS1.Procedure Revision Verification:
Appendix D                          Operator Actions                              Form ES-D-2 Scenario No: 2009-4      Revision: 5                Event No.: 3            Page 4 of 12 Event
Revision No.
Date:
2.Power is available for the selected condenser evacuation pump:
!  FW-8A, Condenser Evacuation Pump, 1B3B-7
!  FW-8B, Condenser Evacuation Pump, 1B4A-4
!  FW-8C, Condenser Evacuation Pump, 1B3B-4B-2


C Continuous Use FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 12 OF 22 R24 Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE    INITIALS NOTES1.The order of pump rotation is A-B-C.2.Seal Water Makeup can be supplied from the Condensate System or the Demineralized Water System as follows:
== Description:==
a.DW-357, Condenser Vacuum Pumps, FW-8A-8C Seal Water Supply Line Isolation Valve
Pressurizer Pressure Safety Channel fails Low - Tech Spec Entry Time    Position                        Applicants Actions or Behavior ATCO      Respond to "PRESSURIZER SAFETY INJ SIGNAL LO-LO PRESSURE C/P102Y" (CB-1,2,3,/A4, C-5), "TM/LOW PRESSURE CHANNEL TRIP"(CB-4/A20, A-5) and "TM/LOW PRESSURE CHANNEL PRETRIP"(CB-4/A20, B-5)
!Normally used during startup (Pumps DW-40A/B must be running)b.FW-1351, Separator Tanks FW-41, 42 &  43 Condensate Seal Water Supply Isolation Valve
ATCO      Refer to ARPs.
!Normally used after a Condensate Pump is startedc.FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve
or BOPO ATCO      Check redundant channels and report failure of C/P102Y.
!Normally used as a backup if the Condensate Storage Tank is full1.IF a Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.
ATCO      Verify the following:
!FW-1351, Separator Tanks FW-41, 42 &  43 Condensate Seal Water
Pressurizer pressure RCS Cold Leg Temperatures Axial Shape Index Reactor Power, NI and Delta-T CRS        LCO 2.15(1) - The number of channels for the TM/LP and High Pressurizer (TS)      Pressure trips in service falls one below the total number of installed channels (see Table 2-2). And the number of channels for PPLS actuation in service falls one below the total number of installed channels. (see Table 2-3).
Requires Actions:
The Thermal Margin/ Low Pressure and High Pressurizer Pressure channels must be bypassed or tripped within one hour.
The channels may be bypassed for up to 48 hours, after that it must be placed in the tripped position.
CRS        Direct the ATCO to bypass channel "C" High Pressurizer Pressure trip unit
                    #8 and TM/LP trip unit #9 .
ATCO      Place channel "C" trip units #8 and #9 in bypass.
CRS        Notify Work Week Manager of instrument Failure.


Supply Isolation Valve, is open
Appendix D                          Operator Actions                              Form ES-D-2 Scenario No: 2009-4      Revision: 5              Event No.: 4              Page 5 of 12 Event
!FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43


Supply Header Isolation Valve, is open
== Description:==
!DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line
Steam header pressure transmitter, PT-910 Fails High.
Time    Position                        Applicants Actions or Behavior BOPO      Identify rapid decrease in RCS T-cold (VARIABLE OVERPOWER RESET DEMAND, CB-4, A20, C-7) will alarm if uncorrected).
ATCO/      If "VARIABLE OVERPOWER RESET DEMAND",(CB-4, A20, C-7)
BOPO      alarms, enter ARP CB-4/A20.
BOPO      Recognize PCV-910, "Main Steam Bypass Valve," being open (red light on CB-1,2,3).
BOPO      Determine that Steam Header Pressure Transmitter, PT-910 failed high.
CRS        Direct BOP to take manual control of PCV-910 and close it.
BOPO      Manually close PCV-910 BOPO      Monitor RCS T-cold.
ATCO      Monitor and control RCS parameters.
CRS        Notify Work Week Manager or I&C of the failure of PT-910.
CRS        If Pressurizer pressure lowers to 2075 psia or less, then enter Technical Specification LCO 2.10.4(5) - DNBR Margin During Power Operation Above 15% of Rated Power.
Required Actions:
Restore Pressurizer Pressure greater than or equal to 2075 psia within 2 hours.
Or else, reduce power to less than 15% within the next 8 hours.


Isolation Valve (Col. B-5), is closed
Appendix D                        Operator Actions                                Form ES-D-2 Scenario No: 2009-4      Revision: 5              Event No.: 5             Page 6 of 12 Event


C Continuous Use FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 13 OF 22  - Normal Rotation of Condenser Evacuation Pumps PROCEDURE (continued)
== Description:==
INITIALS R242.IF no Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.
10-15 gpm leak to containment - Tech Spec Entry.
!FW-1351, Separator Tanks FW-41, 42 &  43 Condensate Seal Water Supply Isolation Valve, is closed
Time    Position                        Applicants Actions or Behavior ATCO      Respond to RM-050 CNTMT PARTICULATE HIGH RADIATION Alarm. (AI-33C/A33C, 1)
!FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43
ATCO      Enter ARP. Verify high radiation on ratemeter.
ATCO      Check containment area monitors, report rising dose rates.
CRS/      Check for indication of RCS leakage into containment:
ATCO            Dewpoint Temperature Containment Pressure Containment Sump Level Pressurizer Level ATCO      Trend Pressurizer level, VCT level, charging and letdown and report to CRS.
CRS        Enter AOP-22, "REACTOR COOLANT LEAK", Section I, "Leak Rate Determination and Leak Isolation" CRS        Read Cautions and Notes.
CRS        Direct Shift Chemist to perform a rapid activity analysis of both S/Gs CRS        Ask Shift Manager to implement the Emergency Plan.
CRS/      Determine the RCS leak rate to be approximately 15 gpm.
ATCO CRS        Direct Shift Chemist to verify primary to secondary leakrate.
CRS        LCO 2.1.4(1) - Greater than 1 gpm unidentified leakage or greater than 10 (TS)      gpm identified leakage.
Required Actions:
Reduce leakage to within limits within 4 hours.
or else be in hot shutdown within an additional 6 hours and be in cold shutdown within 36 hours.
If Pressure Boundary Leakage is identified, then:
be in hot shutdown within 6 hours and be in cold shutdown within 36 hours.


Supply Header Isolation Valve, is closed
Appendix D                          Operator Actions                            Form ES-D-2 Scenario No: 2009-4      Revision: 5              Event No.: 5            Page 7 of 12 Event
!DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line


Isolation Valve (Col. B-5), is open 3.Ensure that the Separator Tank level reads within the gauge glass and atleast eight inches prior to starting the Condenser Evacuation Pump.               4.Start the Standby Condenser Evacuation Pump (CB-10/11).
== Description:==
5.Verify proper operation of the Condenser Evacuation Pump started.
10-15 gpm leak to containment - Tech Spec Entry., continued.
NOTE Condenser Evacuation Separator Tan ks are continuously overflowed to minimize the build up of Ammonia in the system.6.Commence continuous feed and bleed of the Condenser Evacuation Separator Tank by throttling open the bypass valve:
Time    Position                        Applicants Actions or Behavior CRS        Direct ATCO to isolate letdown and charging.
!VD-317, Separator Tank FW-41 Ma keup Float Bypass Valve (FW-8A)
ATCO      Isolate letdown and charging and check leakage rate. Determines that the leak was not isolated.
!VD-325, Separator Tank FW-42 Ma keup Float Bypass Valve (FW-8B)
CRS/       Restore charging and letdown.
!VD-333, Separator Tank FW-43 Ma keup Float Bypass Valve (FW-8C) 7.Place the control switch for the Condenser Evacuation Pump being placed inStandby in AFTER STOP (CB-10/11).               8.Stop the continuous feed and bleed of the Condenser Evacuation Separator Tank for the Condenser Evacuation Pump being placed in Standby by
ATCO CRS        Refer to Attachment A, "Leak Location Guide", determine leak is to Containment.
ATCO      Check the rate of level rise in the quench tank.
CRS/      Direct the EONA to check the rate of level rise in the RCDT and Auxiliary ATCO      Building Sumps and to visually inspect the Auxiliary Building.
CRS/      Direct Radiation Protection to sample the Auxiliary Building atmosphere ATCO      and check the continuous air monitors.
CRS/      Direct the EONA or Chemist to close Sample Isolation Valves, HCV-2500, ATCO      2501, 2502 and 2503, in Room 60.
ATCO      Close RCS Sample Isolation Valves, HCV-2504A and HCV-2504B.
CRS/      Direct Chemistry to check the sampling lineups.
ATCO ATCO      Start all available Containment Vent Fans and ensure CCW is supplied to the cooling coils.
CRS/      Direct the EONA to place both Containment Sump Pumps in "PULL TO ATCO      LOCK."
ATCO      Close both Containment Sump Isolation Valves, HCV-506A and HCV-506B.
CRS        Direct plant shutdown using either OP-4, "LOAD CHANGE AND NORMAL POWER OPERATION" or AOP-05, "EMERGENCY SHUTDOWN". Will enter AOP-22, "Section II - Reactor Coolant Leak Less Than 40 gpm," after plant shutdown.


closing the bypass valve:
Appendix D                        Operator Actions                            Form ES-D-2 Scenario No: 2009-4    Revision: 5                Event No.: 6, 7      Page 8 of    12 Event
!VD-317!VD-325!VD-333 Completed by Date/Time              /             


FORT CALHOUN STATION OI-CC-1 OPERATING INSTRUCTION C PAGE 8 OF 73 Continuous Use R65 Attachment 2 - Rotating In service Pumps
== Description:==
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically.
Time    Position                        Applicants Actions or Behavior BOPO      Determine that the running Feedwater Pump has tripped.
CRS        Direct the ATCO to manually trip the reactor.
ATCO      Manually trip the reactor.
CRS        Enters EOP-00. Directs ATCO and BOPO to perform Standard Post Trip Actions.
ATCO      Perform Reactivity Control Actions:
Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met BOPO      Verify Turbine Tripped:
Stop and Intercept Valves are Closed BOPO      Verify Generator Breakers Tripped:
Breakers 3451-4/5 Generator Field Breaker BOPO      Verify vital buses, 1A3 and 1A4, are energized.
BOPO      IF SIAS has initiated, THEN verify both Diesel Generators have started.
BOPO      Verify non-vital buses, 1A1 and 1A2, are energized.
BOPO      Verify both 125VDC buses are energized.
BOPO      Verify Instrument air status:
Instrument Air pressure is at least 90 psig At least 1 air compressor running


PREREQUISITES
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-4      Revision: 5            Event No.: 6, 7          Page 9 of     12 Event
() INITIALS     1. Procedure Revision Verification


Revision No.
== Description:==
Date:
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically, continued Time    Position                      Applicants Actions or Behavior ATCO      Verify CCW and Raw water status:
: 2. Power is available for the selected pump:
At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open ATCO      Verify Inventory Control:
Pressurizer Level 30-70% trending toward 45-60%
Subcooling, at least 20&deg;F ATCO      Verify Pressure Control:
RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO      Verify Core Heat Removal:
RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10&deg;F BOPO      Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):
Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%
No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF BOPO      Determines DCS has not throttled blowdown flow, manually isolates (CT)      blowdown by closing HCV-1387A/B and HCV-1388A/B within 15 minutes of feedwater pump trip.
BOPO      Reports no running Main Feed Pumps. Establishes AFW Flow using Motor Driven AFW Pump, FW-6, or Turbine Driven AFW Pump, FW-10.


AC-3A, Component Cooling Water Pump, 1B3B-4  AC-3B, Component Cooling Water Pump, 1B4A1  AC-3C, Component Cooling Water Pump, 1B3C-4C-4
Appendix D                        Operator Actions                                Form ES-D-2 Scenario No: 2009-4     Revision: 5              Event No.: 6, 7         Page 10 of 12 Event
: 3. Verify operability of Diesel Generator s will meet Tech Spec 2.7 requirements prior to disabling CCW pumps.          PROCEDURE  NOTE The number of pumps in service can caus e fluctuations in CCW temperature.
This can affect letdown temperature and may cause small reactivity changes in the RCS. CAUTION At least two Component Cooling Heat Exchangers shall be in service at all times to protect against system over pressurization should a second pump


automatically start.
== Description:==
Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically, continued.
Time    Position                        Applicants Actions or Behavior BOPO      Verify Steam Dump and Bypass Valves are controlling BOTH of the following:
T-cold 525-535&deg;F S/G Pressure 850-925 psia ATCO      Verify containment conditions:
No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120&deg;F Reports that containment sump level is rising.
CRS        Performs diagnostic actions and enters EOP-03, "LOSS OF COOLANT ACCIDENT."
(Note: May also enter EOP-01, "REACTOR TRIP RECOVERY," and AOP-22, "Section II - Reactor Coolant Leak Less Than 40 gpm," since pressurizer pressure is greater than 1800 psia and stable or rising.)
 
Appendix D                        Operator Actions                                Form ES-D-2 Scenario No: 2009-4      Revision: 5            Event No.: 8              Page 11 of 12 Event
 
== Description:==
Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater.
Time    Position                        Applicants Actions or Behavior BOPO      Reports loss of AFW Flow.
CRS        Transitions to EOP-20, "FUNCTIONAL RECOVERY.", Success path, HR-1.
(NOTE: If EOP-01 entered previously, then may enter EOP-06, "LOSS OF ALL FEEDWATER," at this time.)
CRS        Confirm Standard Post Trip Actions.
CRS        Request Shift Manager to enter the Emergency Plan.
CRS        Monitor the floating steps.
ATCO      Trips all Reactor Coolant Pumps within 10 minutes of a total loss of (CT)      feedwater being diagnosed.
BOPO      Ensure Blowdown is isolated by ensuring the following valves are closed:
HCV-1387A/B HCV-1388A/B CRS        Direct Shift Chemist to perform a rapid activity analysis of both steam generators.
CRS        Refer to Safety Function Status Checks or Resource Assessment Trees and go to success path HR-1.
CRS        Direct ATCO to insert group N CEAs. (If entered EOP-20)
ATCO      Insert Group N CEAs, if directed.
ATCO      Monitor for establishment of natural circulation:
Delta-T less than 50&deg;F.
Difference between CETs and T-hot less than 10&deg;F.
T-hot and T-cold stable or lowering.
At least 20&deg;F subcooling.
BOPO      Begin a controlled plant cooldown using steam dump and bypass valves.
ATCO      Monitor RCS pressure per Attachment 2.
CRS        Determines that AFW flow cannot be established.
 
Appendix D                          Operator Actions                          Form ES-D-2 Scenario No: 2009-4      Revision: 5              Event No.: 8          Page 12 of  12 Event
 
== Description:==
Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater, Continued.
Time    Position                          Applicants Actions or Behavior CRS        Direct BOPO to establish Condensate pump feed to the Steam Generators.
BOPO      Establish condensate pump feed to the Steam Generators:
Place all FW Pump Control Switches in Pull-To-Lock Direct EONT to open All FW Pump discharge valves Ensure FW Pump Recirc valves are closed Start All FW Pump Lube Oil Pumps Reduce Steam Generator Pressure to less than 550 psia Direct EONT to ensure Condensate Pump Recirc Valve, FCV-1172, is closed ATCO      Maintain pressurizer pressure per EOP-AOP Attachment 2 and level 10-70%.
                    .
BOPO      When S/G pressure is less than 550 psig:
Block SGLS Ensure HCV-1385 and HCV-1386 are open Ensure HCV-1103 and HCV-1104 are closed Reduce pressure to achieve flow through FW bypass Valves, HCV-1105 and HCV-1106 NOTE: The next two steps are expected only if Wide Range Level in both Steam Generators falls below 27%.
CRS        IF WR Level in both S/Gs falls below 27%, THEN initiate Once through (CT)      Cooling using EOP-20, HR-4 (or EOP-06)
BOPO      IF directed to initiate Once through cooling then:
Deenergize all pressurizer heaters.
Initiate PPLS using test switches.
Ensure HPSI pumps running and injection valves open.
Ensure PORV Block valves are open.
Open both PORVs.
Scenario ends with the Steam Generators being fed by the Condensate Pumps or with Once Through Cooling Established.
 
FORT CALHOUN STATION                                                                                                                      FC-95 FORM SHIFT TURNOVER LOG                                                                                    Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 Days                    Nights        X PLANT STATUS:
MODE:        1    X    2      3    Rx Power:          49.00%                            Rod Position: Group 4 @ 88" Prcs (>2075 psia):        2108  psia  Tcold (<543&deg;F):              539.6            &deg;F Lpzr (48 - 60%):                          56 % (Actual)
Comments:
SAFEGUARDS STATUS:
(Log any out-of-service safeguards equipment; include major fire protection equipment)
RECENT TEMP MODS: (Within the last month)
TM Number              Date        Description None DEGRADED EQUIPMENT STATUS CR Number          Component/System            Reason Considered Degraded                                              Resolution 2009003501  AFW Pump FW-54        Out of Service - being repaired excessive vibration 2009003517  Feed Pump FW-2A      Out of Service - motor windings shorted                Motor off site for rewind 2009003521  Feed Pump FW-2C      Out of Service - Seal Leakage                          Seals being replaced SO-O-1 FC/FORM                                                      Page 1 of 3
 
FORT CALHOUN STATION                                                                                        FC-95 FORM SHIFT TURNOVER LOG                                                    Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 RELEASES IN PROGRESS:                                                        YES          NO          RELEASE #
Monitor Tank:          A        B                                                          X Waste Gas Decay Tank:          A      B    C        D                                  X
                                                  .
Containment Pressure Reduction                                                            X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:
PROCEDURE or TEST                                                      REASON None CRS review and discuss procedures in progress (Initial)
INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):
ITEM / LOCATION              DATE                                    ACTION REQUIRED None TEMPORARY LIFTS:
TAGOUT #                EQUIPMENT                                          REASON None POST MAINTENANCE TESTING:
(Equipment, instrument or annunciator requiring PMT for operability)
AVAILABLE Component            YES NO                                  PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:
REPORT MADE EQUIP OOS                DATE/TIME              T.S. / ODCM / G-103              LCO          YES  NO N/A None SO-O-1 FC/FORM                                                    Page 2 of 3
 
FORT CALHOUN STATION                                                                              FC-95 FORM SHIFT TURNOVER LOG                                              Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 REMARKS:
* Perform Normal Rotation of CCW Pumps per OI-CC-1, Attachment 2. Place AC-3C in service, shutdown AC-3A
*
* RCS Boron 1165          ppm Neutral Blend (gal acid /gal water)10/87 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________
Off going                                            On coming S.M.
C.R.S.
L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator                                                          ____
Security Key Transferred (Init)
SO-O-1 FC/FORM                                            Page 3 of 3
 
FORT CALHOUN STATION                                                                                          FC-75A FORM                                                                                                              R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 04/01/09        Shift (Circle one)            0600-1800                                1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.
Switch              Location              Annunciators in Alarm              Reason out-of-position/in alarm FW-4A CS            CB-10,11                                                          FW-4A Out of Service FW-30A              CB-10,11 FW-4C CS            CB-10,11                                                          FW-4C Out of Service FW-30C              CB-10,11 CB-10,11/A9 C-3L  FW SYSTEM VALVES TROUBLE                      FW-4A and FW-4C Isolated PROTECTED EQUIPMENT                        SIGN LOCATION                          REASON PROTECTED FW-6                          FW-6 CS and BKR                          FW-54 Out of Service FW-10                              YCV-1045 CS                                  ' ''
FW-4B                            CS and BRKR                          FW-4A and FW-4C OOS
 
FORT CALHOUN STATION                                                                  OI-CC-1 OPERATING INSTRUCTION                          C                                PAGE 8 OF 73 Continuous Use Attachment 2 - Rotating In service Pumps PREREQUISITES                                                                      (9) INITIALS
: 1. Procedure Revision Verification Revision No. 65                Date: 04/01/09                                  JEK
: 2. Power is available for the selected pump:
* AC-3A, Component Cooling Water Pump, 1B3B-4
* AC-3B, Component Cooling Water Pump, 1B4A1
* AC-3C, Component Cooling Water Pump, 1B3C-4C-4                              X    JEK
: 3. Verify operability of Diesel Generators will meet Tech Spec 2.7 requirements prior to disabling CCW pumps.                                                      JEK PROCEDURE NOTE The number of pumps in service can cause fluctuations in CCW temperature.
This can affect letdown temperature and may cause small reactivity changes in the RCS.
CAUTION At least two Component Cooling Heat Exchangers shall be in service at all times to protect against system over pressurization should a second pump automatically start.
: 1. Vent the pump to be started using the associated valve:
: 1. Vent the pump to be started using the associated valve:
AC-353, Comp Cooling Water Pump AC-3A Casing Vent Valve AC-356, Comp Cooling Water Pump AC-3B Casing Vent Valve AC-359, Comp Cooling Water Pump AC-3C Casing Vent Valve
* AC-353, Comp Cooling Water Pump AC-3A Casing Vent Valve
* AC-356, Comp Cooling Water Pump AC-3B Casing Vent Valve
* AC-359, Comp Cooling Water Pump AC-3C Casing Vent Valve                     X    JEK
: 2. Start the desired Component Cooling Water Pump:
: 2. Start the desired Component Cooling Water Pump:
AC-3A AC-3B AC-3C      
* AC-3A
* AC-3B
* AC-3C R65


FORT CALHOUN STATION OI-CC-1 OPERATING INSTRUCTION C PAGE 9 OF 73 Continuous Use R65 Attachment 2 - Rotating In service Pumps PROCEDURE (continued)   () INITIALS     NOTES 1. When stopping a Component Cooling Water Pump with two or more pumps operating, the pump discharge valve is closed to prevent check valve slamming. 2. The Component Cooling Water system contains a corrosion inhibitor, CORRSHIELD NT 4204 and should be considered a personnel hazard if a  
FORT CALHOUN STATION                                                               OI-CC-1 OPERATING INSTRUCTION                         C                               PAGE 9 OF 73 Continuous Use Attachment 2 - Rotating In service Pumps PROCEDURE (continued)                                                           (9) INITIALS NOTES
: 1. When stopping a Component Cooling Water Pump with two or more pumps operating, the pump discharge valve is closed to prevent check valve slamming.
: 2. The Component Cooling Water system contains a corrosion inhibitor, CORRSHIELD NT 4204 and should be considered a personnel hazard if a leak exists.
: 3. Log into Tech Spec 2.4(1)b 7 day LCO or 2.4(2)a 24 hour LCO as appropriate, for the CCW Pump inoperability.
: 4. Close the discharge valve for the Component Cooling Water Pump to be stopped:
* AC-102, Comp Cooling Water Pump AC-3A Discharge Valve
* AC-105, Comp Cooling Water Pump AC-3B Discharge Valve
* AC-108, Comp Cooling Water Pump AC-3C Discharge Valve
: 5. Verify PI-499, Pressure Indicator for CCW Pump Disch Header, pressure is approximately 90 psig.
: 6. Stop the Component Cooling Water Pump to be shutdown:
* AC-3A
* AC-3B
* AC-3C
: 7. Open discharge valve closed in Step 4.
Ind Verif
: 8. Exit appropriate Tech Spec LCO.
Completed by                                                          Date/Time        /
R65
 
Appendix D                                    Scenario Outline                                  Form ES-D-1 Facility: Fort Calhoun                  Scenario No: 2009-1 (SPARE)          Revision: 3 Examiners:          _________________________                    Operators:  _________________________
_________________________                                _________________________
_________________________                                _________________________
Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.
Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.
Event          Malf        Event                                        Event No.            No.        Type*                                      Description 1                          N-ATCO        Transfer Letdown Flow Control Valves.
(2 min) 2                          N-BOPO        Rotate EHC Pumps.
(14 min) 3                          I-ATCO        Power Range NI Channel B fails - Tech Spec Entry.
LE CUE 4                          C-BOPO        Running Bearing Cooling Water Pump, AC-9A, trips.
LE CUE 5                          I-ATCO        Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE                                    Entry 6                          C-All        Loss of Instrument Air.
LE CUE 7                          C-ATCO        Manual Reactor Trip Required.
8                          M-All        Steam Generator Safety Valve Fails Open.
LE CUE
*        (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)        Actual Attributes
: 1. Total malfunctions (5-8)                                                        5
: 2. Malfunctions after EOP entry (1-2)                                              1
: 3. Abnormal events (2-4)                                                          2
: 4. Major transients (1-2)                                                          1
: 5. EOPs entered/requiring substantive actions (1-2)                                1
: 6. EOP contingencies requiring substantive actions (0-2)                          1
: 7. Critical tasks (2-3)                                                            3
 
Appendix D                        Operator Actions                          Form ES-D-2 Scenario No: 2009-1    Revision: 3              Event No.: 1          Page 2    of 15 Event


leak exists. 3. Log into Tech Spec 2.4(1)b 7 day LCO or 2.4(2)a 24 hour LCO as appropriate, for the CCW Pump inoperability.
== Description:==
: 4. Close the discharge valve for the Component Cooling Water Pump to be stopped:  AC-102, Comp Cooling Water Pump AC-3A Discharge Valve AC-105, Comp Cooling Water Pump AC-3B Discharge Valve  AC-108, Comp Cooling Water Pump AC-3C Discharge Valve
Transfer Letdown Flow Control Valves Time    Position                      Applicants Actions or Behavior ATCO      Enter OI-CH-1, Attachment 2, "SHUTDOWN OF CHARGING AND LETDOWN."
: 5. Verify PI-499, Pressure Indicator for CCW Pump Disch Header, pressure is approximately 90 psig.           6. Stop the Component Cooling Water Pump to be shutdown:
ATCO      Bypass ion exchangers by placing TCV-211-2, Ion Exchangers Bypass Valve to "BYP IX" ATCO      Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.
ATCO      Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.
ATCO      Stop the operating charging pump, CH-1A. (May place on PULL-OUT.)
ACTO      Close Charging Isolation Valves, HCV-238 and HCV-239.
ATCO      Enter OI-CH-1, Attachment 1, "STARTUP OF CHARGING AND LETDOWN."
ATCO      Ensure LCV-218-2 VCT Outlet Valve is open with control switch in AUTO.
ATCO      Read caution on top of page 8.
ACTO      Ensure HCV-247, Charging to RC Loop 1A Isolation Valve is open.
ATCO      Ensure charging isolation valves open; HCV-247 AND HCV-238 AND/OR HCV-248 AND HCV-239.
ATCO      Place HC-101-3, Limiter Bypass Switch, in BYPASS.
ATCO      Place HIC-101-1/101-2 Letdown Throttle Valve Controller in MANUAL.
ATCO      Close LCV-101-1 and LCV-101-2 ATCO      Select LCV-101-2 on HC-101-2 selector switch ATCO      Place PIC-210, Letdown Pressure Controller, in MANUAL.
ATCO      Throttle PIC-210 to approximately 10% open.
ATCO      Verify position of Charging Pumps Mode Select Stby switch is CH-1B-1C.


AC-3A AC-3B AC-3C
Appendix D                        Operator Actions                            Form ES-D-2 Scenario No: 2009-1    Revision: 3            Event No.: 1              Page 3  of 15 Event
: 7. Open discharge valve closed in Step 4.
 
Ind Verif     8. Exit appropriate Tech Spec LCO.     
== Description:==
Transfer Letdown Flow Control Valves, continued.
ATCO      Start CH-1A.
ATCO      Open HCV-204 and TCV-202.
ATCO      Use HIC-101-1/101-2 to initiate letdown flow while adjusting PCV-210 to maintain approximately 300 psig.
ATCO      Balance charging and letdown flow.
ATCO      Place HC-101-3, Limiter Bypass Switch, in NORMAL.
ATCO      Go to OI-RC-8, Attachment 3. and ensure pressurizer level matches programmed level and PIC-210 200-400 psia.
ATCO      Adjust bias on HIC-101-1/101-2 until top scale indicates 50%.
ATCO      Place HIC-101-1/101-2 transfer switch to BAL, then to AUTO.
ATCO      Place PIC-210 to AUTO.
ATCO      Make adjustments to HIC-101-1/101-2 as needed.
ATCO      If Ion Exchangers were bypassed, then may place TCV-211-1 in AUTO/TO IX.
 
Appendix D                        Operator Actions                          Form ES-D-2 Scenario No: 2009-1    Revision: 3            Event No.: 2          Page 4 of 15 Event
 
== Description:==
Rotate EHC Pumps Time    Position                      Applicants Actions or Behavior CRS      Direct BOPO to rotate EHC Pumps.
BOPO      Enters OI-ST-12, Attachment 7, "NORMAL ROTATION OF ELECTROHYDRAULIC PUMPS."
BOPO      Read note in middle of page 13.
BOPO      Start standby EHC Pump, EHC-3B.
BOPO      Ensure EHC system pressure is stable on PI-2101.
BOPO      Ensure EHC-3B motor current is approximately 40 to 50 amps.
BOPO      Direct EONT to verify local parameters:
PI-5116 pressure approximately equal to PI-2101 pressure PI-5115 pressure approximately equal to PI-2101 pressure No bubbles visible in EHC-3B suction strainer BOPO      Stop EHC pump, EHC-3A. Ensure pump control switch in AFTERSTOP.
BOPO      Verify adequate EHC pressure being maintained.
 
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-1    Revision: 3              Event No.: 3            Page 5 of    15 Event
 
== Description:==
Power Range NI Channel B fails - Tech Spec Entry Time    Position                        Applicants Actions or Behavior ATCO      Identify the failure from the Nuclear Instrumentation Inoperable and other alarms. May enter ARP.
ATCO      Determine that Power Range NI Channel B Upper Detector has failed.
ATCO      Reset Rod Drop Bistables.
CRS      Enter AOP-15, "LOSS OF FLUX INDICATION OR FLOW STREAMING."
CRS      LCO 2.15(1) - The number of channels for the High Power Level, Thermal (TS)      Margin/Low Pressurizer Pressure and Axial Power Distribution trips fell one below the total number of installed channels.
Required Actions:
RPS channel B trip units 1, 9 and 12 must be placed in bypass within 1 hour.
Since this is a detector failure, they may remain in bypass for up to 7 days. (Note: They may enter 48 hour LCO until I&C confirms detector failure.)
If detector operability is not restored by the end of the 7 days, the reactor must be placed in hot shutdown within 12 hours.
CRS      Notify Manager - FCS, Manager - Operations or Supervisor - Operation of RPS trip unit bypass.
CRS      Obtain the keys and direct the ATC operator to place the 1, 2, 9, 10 and 12 trip units on channel B in bypass.
ATCO      Bypass trip units 1, 2, 9, 10 and 12 on RPS channel B.
ATCO      Enter channel bypass information in control room log.
or BOPO CRS      Inform Work Week Manager of NI Channel Failure.
 
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-1    Revision: 3            Event No.: 4             Page 6 of      15 Event
 
== Description:==
Running Bearing Cooling Water Pump, AC-9A, trips Time    Position                      Applicants Actions or Behavior BOPO      Respond to Cooling Water Pressure Low alarm (CB-10,11 A11 B6U).
BOPO      Report that AC-9A has tripped.
ATCO/     Refer to ARP CB-10, A11, B-6U BOPO BOPO      Check PI-1917, Turbine Bearing Water Temperature.
BOPO      Dispatch EONT to the Bearing Water Pumps.
Note: May receive ISO PHASE BUS TEMP HI alarm is starting backup pump is delayed.
CRS      Direct BOPO to start AC-9B.
BOPO      Start AC-9B.
CRS      Direct BOPO to verify status of Instrument Air System.
BOPO      Ensure that air compressor is operating and instrument air pressure normal or restoring.
BOPO      Direct EONT to check Breaker for AC-9A EONT reports breaker tripped, pump motor hot.
BOPO      May place AC-9A control switch in PULL TO LOCK.
CRS/      May Direct EONT to attempt to reset breaker.
BOPO      If Directed, EONT reports breaker will not reset.
CRS      Notify Work Week Manager.
BOPO      Direct EONT to check level in Bearing Water Head Tank.
EONT reports normal water level.
CRS      May refer to AOP-20.
 
Appendix D                          Operator Actions                              Form ES-D-2 Scenario No: 2009-1    Revision: 3                Event No.: 5              Page 7 of 15 Event
 
== Description:==
Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec Entry Time    Position                        Applicants Actions or Behavior ATCO      Responds to numerous alarms on CB-4, panel A-20 and CB-1,2,3, panel A4.
Reports that trip units 1, 9 and 12 on channel A are tripped.
ATCO/    Reviews ARP.
BOPO ATCO      Checks power, pressure and temperature indications and determines that the alarm is caused by failed T-hot channel (A/T122H).
CRS      LCO 2.15(2) - High Power Level, Thermal Margin/Low Pressurizer (TS)      Pressure and Axial Power Distribution Operable Channels have fallen to the minimum operable channels in TS Table 2.2.
Required Actions:
Because trip units 1, 9 and 12 are already bypassed on RPS channel B. The 1, 9 and 12 trip units on channel A must be placed in the tripped condition within one hour.
One of the channels must be repaired within 48 hours or else the plant must be placed in hot shutdown within the following 12 hours.
With NI channel B trip units bypassed and Delta-T channel A trip units tripped, power must be reduced to less than 70% (no time limit).
CRS      Either direct the ATC to use the Channel A Power Trip Test Interlock, PTTI, to place the trip units in the tripped condition by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID" or else notify I&C to trip the trip units with one hour.
ATCO      If directed, use the channel A PTTI to trip the trip units on channel A by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID."
CRS      Notifies Plant or Operations Management and the Work Week Manager or I&C of the failure.
 
Appendix D                        Operator Actions                                Form ES-D-2 Scenario No: 2009-1    Revision: 3              Event No.: 6              Page 8 of 15 Event
 
== Description:==
Loss of Instrument Air Time    Position                        Applicants Actions or Behavior BOPO      Respond to "PLANT AIR PRESS LO" alarm (CB-10,11/A21,B-6U)
Report that Plant Air Pressure is less than 96 psig, ARP directs entry into BOPO      AOP-17 CRS      Enter AOP-17, "LOSS OF INSTRUMENT AIR."
Caution BOPO that Feed Reg Valves, FCV-1101 and FCV-1102, fail as-is CRS      when Instrument Air Pressure lowers to 70-80 psig.
CRS      Read Notes on page 4 of AOP-17.
CRS/      Ensure all available Air Compressors Start.
BOPO Direct EONT to ensure proper operation of:
CA-1A/B/C, Air Compressors CRS/          CA-12, Air Dryer BOPO          CA-11A/B, Pre-Filters CA-13A/B, After-Filters CRS/      Direct all available Operators to search for the source of the air leak BOPO CRS/      Direct EONT to verify "Service Air System Automatic Isolation Valve",
BOPO      PCV-1753, closure when instrument air pressure drops to less than 80 psig.
CRS/      Direct EONT to verify "Air Dryers CA-31 & CA-12 Bypass Valve, PCV-BOPO      1752, opens when instrument air pressure drops to less than 78 psig.
CRS      Direct BOPO to isolate instrument air to containment.
Close "Instrument Air Containment Isolation Valves", PCV-1849A/B and BOPO      after verifying air pressure continues to drop, reopen PCV-1849A/B.
 
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-1     Revision: 3              Event No.: 6            Page 9 of 15 Event


Completed by Date/Time             /
== Description:==
Loss of Instrument Air, Continued Time     Position                      Applicants Actions or Behavior ATCO    Maintain RCS pressure 2075-2150 psia and Pressurizer Level 45-60% using charging.
CRS    Direct manual reactor trip when air pressure drops to less than 50 psig.
ATCO    Manually trip reactor when directed.
CRS    Direct BOPO to trip all Main Feedwater Pumps.
BOPO    Trip all Main Feedwater Pumps.


FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 5 OF 77 R76 Attachment 1 - Startup of Charging and Letdown PREREQUISITES
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-1     Revision: 3              Event No.: 7            Page 10 of  15 Event
: 1. Procedure Revision Verification


Revision No.
== Description:==
Date:
Manual Reactor Trip Required Time    Position                        Applicants Actions or Behavior CRS      Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.
() INITIALS
ATCO      Perform Reactivity Control Actions:
: 2. CVCS Checklist OI-CH-1-CL-A has been completed.
Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met.
: 3. Component Cooling Water is in operation per OI-CC-1.
BOPO      Verify Turbine Tripped:
: 4. Power is available for the following pumps:  
Stop and Intercept Valves are Closed BOPO      Verify Generator Breakers Tripped:
Breakers 3451-4/5 Generator Field Breaker BOPO      Verify vital buses, 1A3 and 1A4, are energized.
BOPO      IF SIAS has initiated, THEN verify both Diesel Generators have started.
BOPO      Verify non-vital buses, 1A1 and 1A2, are energized.
BOPO      Verify both 125VDC buses are energized.
BOPO      Verify Instrument air status:
Instrument Air pressure 90 at least 90 psig At least 1 air compressor running Reports instrument air pressure is low and continuing to lower.
ATCO      Verify CCW and Raw water status:
At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open ATCO      Verify Inventory Control:
Pressurizer Level 30-70% trending toward 45-60%
Subcooling, at least 20&deg;F


CH-1A, Charging Pump, 1B3A-4  CH-1B, Charging Pump, 1B4C-6  CH-1C, Charging Pump, 1B3B-4B-5
Appendix D                        Operator Actions                              Form ES-D-2 Scenario No: 2009-1     Revision: 3            Event No.: 7              Page 11 of     15 Event
: 5. Liquid Waste Disposal System is ava ilable to receive waste from CVCS per OI-WDL-1.           6. Charging pumps discharge accumulators precharge pressure has been set to approximately 60 to 90% of anticipated RCS pressure.          7. Charging pumps suction accumulators precharge pressure has been set at approximately 15 psig.          8. FT-236, Charging Pump Discharge Flow Transmitter, has been vented If the system has been shutdown for greater than two weeks or has been drained.          9. If the SIRWT has been drained to 80 in ches or less, the SIRWT suction header has been vented per OI-SI-1.          10. Ensure Letdown Valve CIAS Override Switches are in NORMAL position. (CB-1,2,3) 43-CIAS/HCV-204  43-CIAS/TCV-202


FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 6 OF 77 R76 Attachment 1 - Startup of Charging and Letdown PROCEDURE  NOTE Review SO-O-23 for appropriate Equipment/System Usage Cycles.
== Description:==
: 1. Start the selected Packing Cooling Pump a minimum of 30 minutes prior to starting a Charging Pump:
Manual Reactor Trip Required, continued Time    Position                      Applicants Actions or Behavior ATCO      Verify Pressure Control:
CH-1A-1, Charging Pump CH-1A Packing Cooling Pump  CH-1B-1, Charging Pump CH-1B Packing Cooling Pump  CH-1C-1, Charging Pump CH-1C Packing Cooling Pump  ()
RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO      Verify Core Heat Removal:
RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10&deg;F BOPO      Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):
Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%
No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF Close blowdown isolation valves, HCV-1387A/B and HCV-1388A/B Reports Feed Reg valves open, Feed Reg bypass valves closed and no Main Feed Pumps operating.
Establishes AFW flow to the AFW nozzles.
BOPO      Verify Steam Dump and Bypass Valves are controlling BOTH of the following:
T-cold 525-535&deg;F S/G Pressure 850-925 psia Reports that steam dump and bypass valves are closed due to loss of instrument air pressure. Operates HCV-1040 or MS-292 and MS-292 as required to maintain temperature and pressure bands.


INITIALS
Appendix D                      Operator Actions                          Form ES-D-2 Scenario No: 2009-1    Revision: 3            Event No.: 7           Page 12 of  15 Event
: 2. If desired by the SM to equalize t he boron concentration in the charging pump, flush a nominal 40 gallons of wa ter (approximately 2%) from the VCT using the desired charging pumps drain valve:
: a. Declare the affected charging pump inoperable:
CH-1A  CH-1B  CH-1C
: b. Place control switch for se lected pump into PULL-TO-LOCK:
CH-1A  CH-1B  CH-1C           c. Close the discharge valve for selected pump:
CH-193, Charging Pump CH-1A Discharge Valve  CH-192, Charging Pump CH-1B Discharge Valve  CH-190, Charging Pump CH-1C Discharge Valve


FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 7 OF 77 R76 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued)  ()  INITIALS     2    d. Open the selected charging pump drain valve during system filling to ensure of boron is equalized in the discharge piping:
== Description:==
CH-356, Charging Pump CH-1A Discharge Drain Valve to Waste Disposal System  CH-355, Charging Pump CH-1B Discharge Drain Valve to Waste Disposal System  CH-354, Charging Pump CH-1C Discharge Drain Valve to Waste Disposal System
Manual Reactor Trip Required, continued Time     Position                      Applicants Actions or Behavior ATCO      Verify containment conditions:
: e. When nominal 2% has been flushed from the VCT to waste, THEN close the selected charging pump drain valve:
No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120&deg;F CRS      Perform Diagnostic Actions and enters EOP-01.
CH-356 (for CH-1A)  CH-355 (for CH-1B)  CH-354 (for CH-1C)
: f. Open and backseat the selected charging pump Discharge Valve:
CH-193 (for CH-1A)  CH-192 (for CH-1B)  CH-190 (for CH-1C)


Ind Verif    g. Place control switch for selected pump into AFTER STOP:
Appendix D                        Operator Actions                            Form ES-D-2 Scenario No: 2009-1      Revision: 3             Event No.: 8             Page 13 of 15 Event
CH-1A  CH-1B  CH-1C          h. Repeat this step as necessary for each affected charging pump.
: 3. Ensure LCV-218-2, Volume Control Tank Outlet Valve, is open with its control switch in AUTO.
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 8 OF 77 R76 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued)  ()  INITIALS    CAUTION HCV-247, Charg to RC Loop 1A Isolation Valve must remain open to provide an alternate makeup path for charging and ensure CH-202, Ltdn to


Regen Ht Exch Isolation Valve will be able to relieve thermal expansion in  
== Description:==
Steam Generator Safety Valve Fails Open Time    Position                        Applicants Actions or Behavior ATCO      Reports RCS cooldown in progress.
BOPO      Reports S/G pressure is lowering.
CRS        Directs ATCO to perform emergency boration using EOP-00 contingency action.
ATCO      Performs Emergency Boration:
(CT)            Ensure FCV-269X/Y Closed Open HCV-268/265/258 Start Boric Acid Pumps, CH-4A/B Start Charging pumps, CH-1A/B/C Close LCV-218-2/3 and HCV-257/264 CRS        Perform diagnostic actions and transition to EOP-20, FUNCTIONAL RECOVERY PROCEDURE, due to a loss of instrument air and an excessive heat removal event.
CRS        Within EOP-20, go to success path MVA-IA and implement (continue to implement) AOP-17, LOSS OF INSTRUMENT AIR.
On                  Note: Water Plant Operator Reports Instrument air leak in the intake CUE                  structure.
CRS        Direct Water Plant Operator to isolate leak CRS        Direct BOPO to monitor instrument Air Pressure BOPO      Reports that Instrument air pressure is now increasing CRS        Within EOP-20, go to RCS Core and Heat Removal success path, HR-3.
CRS        Direct ATCO or BOPO to verify PPLS, Pressurizer Pressure Low Signal.
ATCO      Verify PPLS:
or              Ensure emergency boration in progress BOPO            Ensure acceptable SI flow per EOP/AOP Attachment 3 Verify 2 HPSI, 2 LPSI and all available charging pumps running


the Regenerative Heat Exchanger.
Appendix D                          Operator Actions                              Form ES-D-2 Scenario No: 2009-1      Revision: 3               Event No.: 8             Page 14 of  15 Event
: 4. Ensure HCV-247, Charg to RC Loop 1A Isolation Valve, is open.
: 5. Ensure at least one of the following co mbinations of charging isolation valves is open:  a. Charg to RC Loop 1A Isolation Valves HCV-247  HCV-238
: b. Charg to RC Loop 2A Isolation Valves HCV-248  HCV-239
: 6. At the Shift Managers discretion, place TCV-211-2, Ion Exchangers Bypass Valve to BYP IX.          7. Place HC-101-3, Limiter Bypass Switch, in BYPASS.
: 8. Place HIC-101-1/101-2, Letdn Throttle Valve Controller, in MANUAL.
: 9. Close the Letdown Ht Exch Throttle Valves:
LCV-101-1  LCV-101-2
: 10. Place HC-101-2, Ltdn Ht Exch Vlvs Se lector Sw in the desired position per the Shift Manager.          11. Place PIC-210, Letdown Pressure Cntrlr, in MANUAL.
: 12. Throttle PIC-210 to approximately 10% open.
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 9 OF 77 R76 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued)   ()  INITIALS    13. Position Charging Pumps Mode Select Stby switch to select the desired backup Charging Pumps start sequence:
CH-1A-1B  CH-1C-1A  CH-1B-1C


CAUTION Pressurizer Level deviation will start standby charging pumps not in  
== Description:==
Steam Generator Safety Valve Fails Open, continued Time    Position                          Applicants Actions or Behavior CRS/      Identify Most Affected Steam Generator by downward trends in any of the BOPO      following:
Steam pressure S/G level RCS T-cold BOPO      Reports that RC-2B is the affected Steam Generator.
BOPO      Manually closes MSIVs when steam header pressure reaches 700 psia.
BOPO      IF either S/G pressure is less than or equal to 500 psia, THEN ensure SGIS closes all of the following valves:
HCV-1041A, RC-2A MSIV HCV-1041C, RC-2A MSIV Bypass Valve HCV-1042A, RC-2B MSIV HCV-1042C, RC-2B MSIV Bypass Valve HCV-1105, Feed Reg Bypass Valve HCV-1106, Feed Reg Bypass Valve HCV-1103, Feed Reg Block Valve HCV-1104, Feed Reg Block Valve HCV-1386, RC-2A Feed Header Isolation Valve HCV-1385, RC-2B Feed Header Isolation Valve CRS        Direct BOPO to isolate Steam Generator, RC-2B BOPO      Isolate S/G RC-2B by closing or ensuring closed:
MSIV, HCV-1042A.
MSIV Bypass, HCV-1042C.
Air assisted S.G Safety Valve, MS-292.
BOPO      Isolate S/G RC-2B by closing or ensuring closed:
(CT)            Feed Reg Valve, FCV-1102 (may need to reset due to low instrument air pressure)
Feed Reg Bypass valve, HCV-1106 Feed Header Isolation Valve, HCV-1385 Feed Reg Block valve, HCV-1104 Blowdown Isolation Valves, HCV-1387A/B AFW Isolation valves, HCV-1108A/B


PULLOUT.
Appendix D                          Operator Actions                            Form ES-D-2 Scenario No: 2009-1      Revision: 3              Event No.: 8            Page 15 of      15 Event
: 14. Start the selected charging pump:  


CH-1A, Charging Pump  CH-1B, Charging Pump  CH-1C, Charging Pump
== Description:==
: 15. Open the following Letdown Isolation Valves:  
Steam Generator Safety Valve Fails Open, continued Time    Position                        Applicants Actions or Behavior BOPO      Isolate S/G RC-2B by closing or ensuring closed:
Direct EONT to close Packing leakoff line isolation valve, MS-298 Override and close steam to AFW pump-FW-10, YCV-1045B Blowdown Sample Isolation Valves, HCV-2507A/B BOPO      Verify the most affected S/G is isolated by downward trends in all of the following for the isolated S/G:
Steam pressure S/G level RCS T-cold CRS        Read the Cautions on page 335 of EOP-20 BOPO      Prepare to steam S/G RC-2A prior to reaching 27% WR level in RC-2B by one of the following:
Ensuring MSIV HCV-1041A is open Blocking SGLS and opening HCV-1041C, Main Steam Bypass Valve BOPO      Establish Steam Flow from RC-2A prior to Wide Range Level on Steam (CT)      Generator RC-2B falling to 27% by one of the following:
Opening Air assisted safety valve, MS-291 (OR)
Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and use steam dump and bypass valves. (OR)
Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and open atmospheric dump valve, HCV-1040 BOPO      Ensure Auxiliary Feedwater is being supplied to S/G, RC-2A.
Scenario ends with S/G RC-2B isolated and heat removal established using S/G RC-2A.


HCV-204, RC to Ltdn Ht Exch Isolation Valve  TCV-202, Ltdn to Regen Ht Exch Isolation Valve
FORT CALHOUN STATION                                                                                                                                  FC-95 FORM SHIFT TURNOVER LOG                                                                                            Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 Days                        Nights        X PLANT STATUS:
: 16. Using HIC-101-1/101-2 initiate Letdown flow while adjusting PCV-210 to maintain Letdown pressure approximately 300 psig.          17. Balance Charging and Letdown flows to maintain Pressurizer level.
MODE:         1    X      2        3      Rx Power:          98.60%                            Rod Position: All Groups ARO Prcs (>2075 psia):        2091    psia  Tcold (<543&deg;F):              542.8            &deg;F Lpzr (48 - 60%):                            60      % (Actual)
: 18. Place HC-101-3 in NORMAL.
Comments:
: 19. If desired, place the following controllers in AUTO:
SAFEGUARDS STATUS:
(Log any out-of-service safeguards equipment; include major fire protection equipment)
RECENT TEMP MODS: (Within the last month)
TM Number              Date            Description None DEGRADED EQUIPMENT STATUS CR Number          Component/System                Reason Considered Degraded                                          Resolution 2009003501  AFW Pump FW-54            Out of Service - being repaired excessive vibration 2009003517  Air Compressor CA-1A      Out of Service - motor windings shorted 2009003521  LCV-101-1                 Erratic flow control                                  LCV-101-2 will be placed into service while System Engineer investigates.
SO-O-1 FC/FORM                                                          Page 1 of 3


HIC-101-1/101-2 per OI-RC-8  PIC-210
FORT CALHOUN STATION                                                                                        FC-95 FORM SHIFT TURNOVER LOG                                                    Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 RELEASES IN PROGRESS:                                                        YES          NO          RELEASE #
: 20. If desired, place CVCS ion exchangers in service per OI-CH-2.
Monitor Tank:          A        B                                                          X Waste Gas Decay Tank:           A      B    C        D                                  X
: 21. If desired, check Letdown Pulsati on Dampener Pressures per OI-CH-1, Attachment 6.           22. Evaluate the evolution for appropriate Equipment/System Usage Cycles.
                                                  .
Completed by Date/Time            /  
Containment Pressure Reduction                                                            X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:
PROCEDURE or TEST                                                      REASON None CRS review and discuss procedures in progress (Initial)
INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):
ITEM / LOCATION              DATE                                    ACTION REQUIRED None TEMPORARY LIFTS:
TAGOUT #                EQUIPMENT                                          REASON None POST MAINTENANCE TESTING:
(Equipment, instrument or annunciator requiring PMT for operability)
AVAILABLE Component            YES NO                                  PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:
REPORT MADE EQUIP OOS                DATE/TIME              T.S. / ODCM / G-103              LCO          YES  NO N/A None SO-O-1 FC/FORM                                                    Page 2 of 3


FORT CALHOUN STATION OI-RC-8 OPERATING INSTRUCTION C PAGE 9 OF 20 Continuous Use R13 Attachment 3 - Transferring Letdown C ontroller from MANUAL to AUTOMATIC PREREQUISITES
FORT CALHOUN STATION                                                                                   FC-95 FORM SHIFT TURNOVER LOG                                                  Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 REMARKS:
() INITIALS      1. Procedure Revision Verification
* Transfer Letdown Flow Control from LCV-101-1 to LCV-101-2. Shutdown charging and letdown using OI-CH-1, Att 2.
* Reestablish charging and letdown using LCV-201-2 and CH-1A per OI-CH-1, Att 1 and OI-RC-8, Att 3.
* Perform Normal Rotation of EHC Pumps per OI-ST-12, Attachment 7.
RCS Boron 998            ppm Neutral Blend (gal acid /gal water)10 / 55 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________
Off going                                          On coming S.M.
C.R.S.
L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator                                                          ____
Security Key Transferred (Init)
SO-O-1 FC/FORM                                            Page 3 of 3


Revision No.
FORT CALHOUN STATION                                                                                          FC-75A FORM                                                                                                              R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 03/31/09        Shift (Circle one)            0600-1800                                1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.
Date:
Switch              Location              Annunciators in Alarm              Reason out-of-position/in alarm CA-1A CS            CB-10,11                                                              Out of Service A-33-1, F7      AIR COMPRESSOR CA-1A OFF NORMAL                            ' ''
: 2. 120 Volt AC System is in normal operation per OI-EE-4.
PROTECTED EQUIPMENT                        SIGN LOCATION                          REASON PROTECTED FW-6                            FW-6 CS and BKR                          FW-54 Out of Service FW-10                              YCV-1045 CS                                    ' ''
: 3. Instrument Air is in operation per OI-CA-1.
CA-1B                          CA-1B CS and BKR                        CA-1A Out of Service CA-1C                          CA-1C CS and BKR                                  ' ''
: 4. CB-1/2/3 Instrumentation and Alarms are operable.
PROCEDURE          1. Ensure Letdown Controller HIC-101-1/101-2, Letdn Throttle Valves Controller is in (M) MANUAL.
: 2. Manually adjust HIC-101-1/101-2 AND PI C-210, Letdown Press Cntrlr until the following parameters are met:
Indicated Pressurizer Level (red pen) matches the Programmed Level Setpoint (green pen) on LR-101X or LR-101Y, Pressurizer Level


Recorder. PIC-210 is maintaining 200 psi to 400 psi.
FORT CALHOUN STATION                                                              OI-CH-1 OPERATING INSTRUCTION                    CONTINUOUS USE                    PAGE 5 OF 77 Attachment 1 - Startup of Charging and Letdown PREREQUISITES                                                                (9) INITIALS
: 3. Adjust the bias on HIC-101-1/101-2 until the top scale indicates 50% (zero deviation; red pointer a ligned with the red dot).
: 1. Procedure Revision Verification Revision No. 76        Date: 3/31/09                                          JEK
: 4. Place HIC-101-1/101-2 Manual/Auto Tr ansfer Switch to BAL, then to AUTO.
: 2. CVCS Checklist OI-CH-1-CL-A has been completed.                                 JEK
: 5. IF necessary, THEN make fine adjustments to the bias of HIC-101-1/101-2 to ensure
: 3. Component Cooling Water is in operation per OI-CC-1.                           JEK
: 4. Power is available for the following pumps:
* CH-1A, Charging Pump, 1B3A-4                                            X
* CH-1B, Charging Pump, 1B4C-6                                            X
* CH-1C, Charging Pump, 1B3B-4B-5                                        X      JEK
: 5. Liquid Waste Disposal System is available to receive waste from CVCS per OI-WDL-1.                                                                      JEK
: 6. Charging pumps discharge accumulators precharge pressure has been set to approximately 60 to 90% of anticipated RCS pressure.                        JEK
: 7. Charging pumps suction accumulators precharge pressure has been set at approximately 15 psig.                                                         JEK
: 8. FT-236, Charging Pump Discharge Flow Transmitter, has been vented If the system has been shutdown for greater than two weeks or has been drained.        JEK
: 9. If the SIRWT has been drained to 80 inches or less, the SIRWT suction header has been vented per OI-SI-1.                                            N/A
: 10. Ensure Letdown Valve CIAS Override Switches are in NORMAL position.
(CB-1,2,3)
* 43-CIAS/HCV-204                                                        X
* 43-CIAS/TCV-202                                                        X    JEK R76


Pressurizer Level is maintained at setpoint.  
FORT CALHOUN STATION                                                              OI-CH-1 OPERATING INSTRUCTION                    CONTINUOUS USE                      PAGE 6 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE                                                                    (9) INITIALS NOTE Review SO-O-23 for appropriate Equipment/System Usage Cycles.
: 1. Start the selected Packing Cooling Pump a minimum of 30 minutes prior to starting a Charging Pump:
* CH-1A-1, Charging Pump CH-1A Packing Cooling Pump
* CH-1B-1, Charging Pump CH-1B Packing Cooling Pump                              N/A
* CH-1C-1, Charging Pump CH-1C Packing Cooling Pump
: 2. If desired by the SM to equalize the boron concentration in the charging pump, flush a nominal 40 gallons of water (approximately 2%) from the VCT  N/A using the desired charging pumps drain valve:
: a. Declare the affected charging pump inoperable:
N/A
* CH-1A
* CH-1B
* CH-1C
: b. Place control switch for selected pump into PULL-TO-LOCK:
* CH-1A
* CH-1B
* CH-1C
: c. Close the discharge valve for selected pump:
* CH-193, Charging Pump CH-1A Discharge Valve
* CH-192, Charging Pump CH-1B Discharge Valve
* CH-190, Charging Pump CH-1C Discharge Valve R76


Completed by Date/Time /  
FORT CALHOUN STATION                                                              OI-CH-1 OPERATING INSTRUCTION                  CONTINUOUS USE                      PAGE 7 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued)                                                        (9) INITIALS 2
: d. Open the selected charging pump drain valve during system filling to N/A ensure of boron is equalized in the discharge piping:
* CH-356, Charging Pump CH-1A Discharge Drain Valve to Waste Disposal System
* CH-355, Charging Pump CH-1B Discharge Drain Valve to Waste Disposal System
* CH-354, Charging Pump CH-1C Discharge Drain Valve to Waste Disposal System
: e. When nominal 2% has been flushed from the VCT to waste, THEN close the selected charging pump drain valve:
* CH-356 (for CH-1A)
* CH-355 (for CH-1B)
* CH-354 (for CH-1C)
: f. Open and backseat the selected charging pump Discharge Valve:
* CH-193 (for CH-1A)
* CH-192 (for CH-1B)
N/A
* CH-190 (for CH-1C)
N/A Ind Verif
: g. Place control switch for selected pump into AFTER STOP:
* CH-1A                                                            N/A
* CH-1B                                                          N/A
* CH-1C                                                            N/A N/A
: h. Repeat this step as necessary for each affected charging pump.
: 3. Ensure LCV-218-2, Volume Control Tank Outlet Valve, is open with its control switch in AUTO.
R76


C Continuous Use FORT CALHOUN STATION OI-ST-12 OPERATING INSTRUCTION PAGE 13 of 19 R23 Attachment 7 - Normal Rotation of Electrohydraulic Pumps PREREQUISITES () INITIALS1.Procedure Revision Verification Revision No.
FORT CALHOUN STATION                                                                     OI-CH-1 OPERATING INSTRUCTION                   CONTINUOUS USE                            PAGE 8 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued)                                                              (9) INITIALS CAUTION HCV-247, Charg to RC Loop 1A Isolation Valve must remain open to provide an alternate makeup path for charging and ensure CH-202, Ltdn to Regen Ht Exch Isolation Valve will be able to relieve thermal expansion in the Regenerative Heat Exchanger.
Date:
: 4. Ensure HCV-247, Charg to RC Loop 1A Isolation Valve, is open.
2.Standby EHC Pump is in AFTERSTOP. (CB-10) 3.Coordination established with Control Room and Turbine Building operator.               4.Turbine Plant Cooling Water System is operable and available to theapplicable Electrohydraulic Pump Oil Coolers EHC-6A/6B per OI-BW-1.                 5.Electrical Distribution is aligned per OI-EE-2.
: 5. Ensure at least one of the following combinations of charging isolation valves is open:
: a. Charg to RC Loop 1A Isolation Valves
* HCV-247
* HCV-238
: b. Charg to RC Loop 2A Isolation Valves
* HCV-248
* HCV-239
: 6. At the Shift Managers discretion, place TCV-211-2, Ion Exchangers Bypass Valve to BYP IX.
: 7. Place HC-101-3, Limiter Bypass Switch, in BYPASS.
: 8. Place HIC-101-1/101-2, Letdn Throttle Valve Controller, in MANUAL.
: 9. Close the Letdown Ht Exch Throttle Valves:
* LCV-101-1
* LCV-101-2
: 10. Place HC-101-2, Ltdn Ht Exch Vlvs Selector Sw in the desired position per the Shift Manager.
: 11. Place PIC-210, Letdown Pressure Cntrlr, in MANUAL.
: 12. Throttle PIC-210 to approximately 10% open.
R76


PROCEDURE NOTE The EHC Pumps are positive displacement pumps. Minimize time both pumps are in service since each pump tries to take the EHC System load causing
FORT CALHOUN STATION                                                                    OI-CH-1 OPERATING INSTRUCTION                    CONTINUOUS USE                          PAGE 9 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued)                                                              (9) INITIALS
: 13. Position Charging Pumps Mode Select Stby switch to select the desired backup Charging Pumps start sequence:
* CH-1A-1B
* CH-1C-1A
* CH-1B-1C CAUTION Pressurizer Level deviation will start standby charging pumps not in PULLOUT.
: 14. Start the selected charging pump:
* CH-1A, Charging Pump
* CH-1B, Charging Pump
* CH-1C, Charging Pump
: 15. Open the following Letdown Isolation Valves:
* HCV-204, RC to Ltdn Ht Exch Isolation Valve
* TCV-202, Ltdn to Regen Ht Exch Isolation Valve
: 16. Using HIC-101-1/101-2 initiate Letdown flow while adjusting PCV-210 to maintain Letdown pressure approximately 300 psig.
: 17. Balance Charging and Letdown flows to maintain Pressurizer level.
: 18. Place HC-101-3 in NORMAL.
: 19. If desired, place the following controllers in AUTO:
* HIC-101-1/101-2 per OI-RC-8
* PIC-210
: 20. If desired, place CVCS ion exchangers in service per OI-CH-2.
: 21. If desired, check Letdown Pulsation Dampener Pressures per OI-CH-1, Attachment 6.
: 22. Evaluate the evolution for appropriate Equipment/System Usage Cycles.
Completed by                                                            Date/Time        /
R76


pressure oscillations which could affect turbine valves.1.Start the Standby EHC Pump by placi ng its control switch in AFTER-START (CB-10/11):
FORT CALHOUN STATION                                                                OI-RC-8 OPERATING INSTRUCTION                                                          PAGE 9 OF 20 C
!EHC-3A!EHC-3B                          2.Ensure any pressure oscillations in the EHC System are dampened andstabilized indicating greater than 1500 psig on PI-2101 (CB-10).               3.Check just started EHC Pump Motor cu rrent is approximately 40 to 50 amps. (CB-10/11)
Continuous Use Attachment 3 - Transferring Letdown Controller from MANUAL to AUTOMATIC PREREQUISITES                                                                  (9) INITIALS
!EHC-3A!EHC-3B C Continuous Use FORT CALHOUN STATION OI-ST-12 OPERATING INSTRUCTION PAGE 14 of 19  - Normal Rotation of Electrohydraulic Pumps PROCEDURE (continued)
: 1. Procedure Revision Verification Revision No. 13        Date: 3/31/09                                          JEK
()INITIALS R234.Check proper local operation of EHC System as follows:
: 2. 120 Volt AC System is in normal operation per OI-EE-4.                             JEK
!Check PI-5116, Pump EHC-3A Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure
: 3. Instrument Air is in operation per OI-CA-1.                                        JEK
!Check PI-5115, Pump EHC-3B Discharge Pressure, is approximately
: 4. CB-1/2/3 Instrumentation and Alarms are operable.                                    JEK PROCEDURE
: 1. Ensure Letdown Controller HIC-101-1/101-2, Letdn Throttle Valves Controller is in (M) MANUAL.
: 2. Manually adjust HIC-101-1/101-2 AND PIC-210, Letdown Press Cntrlr until the following parameters are met:
* Indicated Pressurizer Level (red pen) matches the Programmed Level Setpoint (green pen) on LR-101X or LR-101Y, Pressurizer Level Recorder.
* PIC-210 is maintaining 200 psi to 400 psi.
: 3. Adjust the bias on HIC-101-1/101-2 until the top scale indicates 50% (zero deviation; red pointer aligned with the red dot).
: 4. Place HIC-101-1/101-2 Manual/Auto Transfer Switch to BAL, then to AUTO.
: 5. IF necessary, THEN make fine adjustments to the bias of HIC-101-1/101-2 to ensure Pressurizer Level is maintained at setpoint.
Completed by                                                          Date/Time      /
R13


equal to PI-2101A, EHC Supply Header Pressure
FORT CALHOUN STATION                                                                OI-ST-12 OPERATING INSTRUCTION                                                          PAGE 13 of 19 C
!For the pump started:-Verify no bubbles are visible in EHC-2A, Hydraulic Fluid Pump EHC-3A Suction Strainer, Bull
Continuous Use Attachment 7 - Normal Rotation of Electrohydraulic Pumps PREREQUISITES                                                                    (%) INITIALS
=s eye-Verify no bubbles are visible in EHC-2B, Hydraulic Fluid Pump EHC-3B Suction Strainer, Bull
: 1. Procedure Revision Verification Revision No. 23          Date: 3/31/09                                          JEK
=s eye                                      5.Stop EHC Pump to be placed in Standby by placing EHC Pump Control Switch  in AFTERSTOP
: 2. Standby EHC Pump is in AFTERSTOP. (CB-10)                                        JEK
!EHC-3A!EHC-3B                           6.IF Running EHC Pump fails to maintain adequate pressure,THEN Start Standby EHC Pump.
: 3. Coordination established with Control Room and Turbine Building operator.        JEK
Completed by Date/Time              /
: 4. Turbine Plant Cooling Water System is operable and available to the applicable Electrohydraulic Pump Oil Coolers EHC-6A/6B per OI-BW-1.              JEK
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 10 OF 77 R76 Attachment 2 - Shutdown of Charging and Letdown PREREQUISITES
: 5. Electrical Distribution is aligned per OI-EE-2.                                  JEK PROCEDURE NOTE The EHC Pumps are positive displacement pumps. Minimize time both pumps are in service since each pump tries to take the EHC System load causing pressure oscillations which could affect turbine valves.
: 1. Procedure Revision Verification
: 1. Start the Standby EHC Pump by placing its control switch in AFTER-START (CB-10/11):
      !   EHC-3A
      !   EHC-3B
: 2. Ensure any pressure oscillations in the EHC System are dampened and stabilized indicating greater than 1500 psig on PI-2101 (CB-10).
: 3. Check just started EHC Pump Motor current is approximately 40 to 50 amps.
(CB-10/11)
      !    EHC-3A
      !    EHC-3B R23


Revision No.
FORT CALHOUN STATION                                                                OI-ST-12 OPERATING INSTRUCTION                                                            PAGE 14 of 19 C
Date:
Continuous Use Attachment 7 - Normal Rotation of Electrohydraulic Pumps PROCEDURE (continued)                                                            (%) INITIALS
() INITIALS
: 4. Check proper local operation of EHC System as follows:
: 2. Zinc Injection is secured.
    !  Check PI-5116, Pump EHC-3A Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure
: 3. Tech Spec 2.2 has been referenced.
    !  Check PI-5115, Pump EHC-3B Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure
PROCEDURE  NOTE If CVCS is shutdown during RCP operation, Pressurizer Level will
    !  For the pump started:
        -    Verify no bubbles are visible in EHC-2A, Hydraulic Fluid Pump EHC-3A Suction Strainer, Bull=s eye
        -    Verify no bubbles are visible in EHC-2B, Hydraulic Fluid Pump EHC-3B Suction Strainer, Bull=s eye
: 5. Stop EHC Pump to be placed in Standby by placing EHC Pump Control Switch in AFTERSTOP
    !  EHC-3A
    !  EHC-3B
: 6. IF Running EHC Pump fails to maintain adequate pressure, THEN Start Standby EHC Pump.
Completed by                                                          Date/Time      /
R23


decrease at a rate equivalent to RCS Leakage and RCP Bleedoff flow.
FORT CALHOUN STATION                                                          OI-CH-1 OPERATING INSTRUCTION                  CONTINUOUS USE                  PAGE 10 OF 77 Attachment 2 - Shutdown of Charging and Letdown PREREQUISITES                                                            (9) INITIALS
: 1. Procedure Revision Verification 76                                                          JEK Revision No.            Date: 3/31/09
: 2. Zinc Injection is secured.                                                  JEK
: 3. Tech Spec 2.2 has been referenced.                                          JEK PROCEDURE NOTE If CVCS is shutdown during RCP operation, Pressurizer Level will decrease at a rate equivalent to RCS Leakage and RCP Bleedoff flow.
: 1. Place TCV-211-2, Ion Exchangers Bypass Valve, in BYP IX.
: 1. Place TCV-211-2, Ion Exchangers Bypass Valve, in BYP IX.
: 2. Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.
: 2. Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.
: 3. Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.
: 3. Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.
: 4. Stop all operating Charging Pumps:  
: 4. Stop all operating Charging Pumps:
 
* CH-1A, Charging Pump
CH-1A, Charging Pump CH-1B, Charging Pump CH-1C, Charging Pump
* CH-1B, Charging Pump
* CH-1C, Charging Pump
: 5. IF desired THEN place all Charging Pumps in PULL-OUT:
: 5. IF desired THEN place all Charging Pumps in PULL-OUT:
CH-1A, Charging Pump CH-1B, Charging Pump CH-1C, Charging Pump
* CH-1A, Charging Pump
: 6. Close the following charging isolation valves: (AR 13140)  
* CH-1B, Charging Pump
 
* CH-1C, Charging Pump
HCV-238, Charg to RC Loop 1A Isolation Valve HCV-239, Charg to RC Loop 2A Isolation Valve  
: 6. Close the following charging isolation valves: (AR 13140)
 
* HCV-238, Charg to RC Loop 1A Isolation Valve
FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 11 OF 77 R76 Attachment 2 - Shutdown of Charging and Letdown PROCEDURE (continued)          7. Stop the Packing Cooling Pumps a minimum of 30 minutes after stopping Charging Pump(s):
* HCV-239, Charg to RC Loop 2A Isolation Valve R76
CH-1A-1, Charging Pump CH-1A Packing Cooling Pump  CH-1B-1, Charging Pump CH-1B Packing Cooling Pump  CH-1C-1, Charging Pump CH-1C Packing Cooling Pump
: 8. Evaluate the evolution for appropriate Equipment/System Usage Cycles.   


Completed by Date/Time             /}}
FORT CALHOUN STATION                                                              OI-CH-1 OPERATING INSTRUCTION                    CONTINUOUS USE                      PAGE 11 OF 77 Attachment 2 - Shutdown of Charging and Letdown PROCEDURE (continued)
: 7. Stop the Packing Cooling Pumps a minimum of 30 minutes after stopping Charging Pump(s):
* CH-1A-1, Charging Pump CH-1A Packing Cooling Pump
* CH-1B-1, Charging Pump CH-1B Packing Cooling Pump
* CH-1C-1, Charging Pump CH-1C Packing Cooling Pump
: 8. Evaluate the evolution for appropriate Equipment/System Usage Cycles.
Completed by                                                       Date/Time       /
R76}}

Revision as of 07:09, 14 November 2019

2009-03 - Final Op Test
ML091030682
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/27/2009
From: Brian Larson
Operations Branch IV
To:
Omaha Public Power District
References
50-285/09-301, ES-301, ES-301-1 50-285/09-301
Download: ML091030682 (401)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun______________ Date of Examination: __3/30/09_____

Examination Level: RO Revision Number: 2 Administrative Topic Type Describe activity to be performed (see Note) Code*

A-1 M, R Calculate Shutdown Margin with inoperable CEA Conduct of Operations KA 2.1.37 (RO Imp 4.3)

A-2 N, R Determine Pressurizer Level During Cooldown Conduct of Operations KA 2.1.25 (RO Imp 3.9)

A-3 N, R Determine Equipment Lost by Tagout of an MCC Equipment Control KA 2.2.41 (RO Imp 3.5)

A-4 D RCA Entry and Exit with PCM Alarms Radiation Control KA 2.3.13 (RO Imp 3.4)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Fort Calhoun_______________ Date of Examination: _3/30/09____

Examination Level: SRO Revision Number: 2 Administrative Topic Type Describe activity to be performed (see Note) Code*

A-5 M, R Review Shutdown Margin Calculation with inoperable CEA Conduct of Operations KA 2.1.37 (SRO Imp 4.6)

A-6 M, R Determine Shift Staffing Conduct of Operations KA 2.1.5 (SRO Imp 3.9)

A-7 D, R Determine RW System Operability Equipment Control KA 2.2.37 (SRO Imp 4.6)

A-8 D, R Authorize Release of Monitor Tank WD-22B Radiation Control KA 2.3.6 (SRO Imp 3.6)

A-9 M, R Emergency Classification and PARs Emergency Procedures/Plan KA's 2.4.41 (SRO Imp 4.6) and 2.4.44 (SRO Imp 4.4)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__

Exam Level: RO Revision Number.: 2

@

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test S, N, A 1 S-2. 004000 A4.08 / Establish Charging Flow via the HPSI Header S, N 2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump S, A, L,M 4P S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S S-6 028000 A1.01 / Operate the Containment Hydrogen Analyzer S, D 5 S-7 062000 A4.01 / Transfer 4160 volt busses from 345 KV to 161 S, D 6 KV S-8. 012000 A4.02 / RPS Power Adjustment S, N 7

@

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire E,A,D 8 Pump

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__

Exam Level: ISRO Revision Number.: 2

@

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1. 001000 A4.03 / Control Element Assembly Movement Test S, N, A 1 S-2. 004000 A4.08 / Establish Charging Flow via the HPSI Header S, N 2 S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-4. 003000 A4.06 / Start a Reactor Coolant Pump S, A, L,M 4P S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S S-7 062000 A4.01 / Transfer 4160 volt busses from 345 KV to 161 S, D 6 KV S-8. 012000 A4.02 / RPS Power Adjustment S, N 7

@

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire E,A,D 8 Pump

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Fort Calhoun_____________________ Date of Examination: 3/30/09__

Exam Level: USRO Revision Number.: 2

@

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-3 006000 A1.11 / Simultaneous Hot and Cold Leg Injection S,A, M, EN, L 3 S-5 061000 A2.04 / Initiate AFW to SGs S, EN, A, N, L 4S

@

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 022000 A2.05 / Provide Raw Water Backup Cooling to E,R,M 5 Containment Coolers P-2 000055 EA1.07 / Energize 480 volt buses from 13.8 KV E, N 6 P-3 086000 A2.04 / Local Emergency Manual Start of the Diesel Fire E,A,D 8 Pump

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-2 Revision: 3 Examiners: _________________________ Operators: _________________________

_________________________ _________________________

_________________________ _________________________

Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.

Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.

Event Malf Event Event No. No. Type* Description 1 N-BOPO Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min) 3.

2 N-ATCO Rotate Containment Cooling Units In accordance with OI-VA-1.

(10 min) 3 C-ATCO Dropped CEA - Tech Spec Entry.

LE CUE C-BOPO 4 R-ATCO AOP-05 shutdown to 70% Power.

N-BOPO 5 I-ATCO Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE High.

6 C-BOPO Loss of 161 KV - Tech Spec Entry.

LE CUE 7 C-ATCO Another Dropped CEA - Manual Reactor Trip Required.

LE CUE 8 M-ALL Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 5
2. Malfunctions after EOP entry (1-2) 1
3. Abnormal events (2-4) 3
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 2

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-4 Revision: 4 Examiners: _________________________ Operators: _________________________

_________________________ _________________________

_________________________ _________________________

Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.

Turnover: Maintain 50% operation. Rotate CCW Pumps.

Event Malf Event Event No. No. Type* Description 1 N-ATCO Rotate CCW Pumps.

(2 min) 2 C-BOPO Isolated Phase Bus Duct Cooling Fan Motor Trips.

LE CUE 3 I-ATCO Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE TS-CRS Entry.

4 C - ATCO 10-15 gpm leak to containment - Tech Spec Entry.

LE CUE TS-CRS 5 I-BOPO Steam header pressure transmitter, PT-910 Fails High.

LE CUE 6 C - ATCO Feedwater Pump Trips, Reactor Trip.

LE CUE 7 C-BOPO Blowdown fails to isolate automatically.

8 M - ALL Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE Feedwater.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 7
2. Malfunctions after EOP entry (1-2) 2
3. Abnormal events (2-4) 2
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 2 or 3

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-1 (SPARE) Revision: 3 Examiners: _________________________ Operators: _________________________

_________________________ _________________________

_________________________ _________________________

Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.

Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.

Event Malf Event Event No. No. Type* Description 1 N-ATCO Transfer Letdown Flow Control Valves.

(2 min) 2 N-BOPO Rotate EHC Pumps.

(14 min) 3 I-ATCO Power Range NI Channel B fails - Tech Spec Entry.

LE CUE 4 C-BOPO Running Bearing Cooling Water Pump, AC-9A, trips.

LE CUE 5 I-ATCO Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE Entry 6 C-All Loss of Instrument Air.

LE CUE 7 C-ATCO Manual Reactor Trip Required.

8 M-All Steam Generator Safety Valve Fails Open.

LE CUE

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 5
2. Malfunctions after EOP entry (1-2) 1
3. Abnormal events (2-4) 2
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 3

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Fort Calhoun Date of Exam: 3/30/09 Revision Number.: 3 A E Scenarios P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW POSITION T N I T POSITION POSITION POSITI A I

ON M C L U A T C A B C A B C A B C A B M(*)

N Y R T O R T O R T O R T O R I U T P S C P S C P S C P S C P E O O O O O O O O RX 4 1 1 1 0 NOR 1,2,4 3 1 1 1 USRO- I/C 3,5,6,7 2,5,7 7 4 4 2 1,2 MAJ 8 8 2 2 2 1 TS 3,6 2 0 2 2 RX 4 1 1 1 0 NOR 2 1 2 1 2 1 ISRO-1,2 I/C 3,5,7 2,3,4,5,6,7 9 4 4 2 MAJ 8 8 2 2 2 1 TS 3,4 2 0 2 2 RX 1 1 0 NOR 1,4 1 3 1 1 1 RO-1,2 I/C 3,6 3,4,6 5 4 4 2 MAJ 8 8 2 2 2 1 TS 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

______________________________________________________________________________

ES-301 Competencies Checklist Form ES-301-6 Facility: Fort Calhoun Date of Examination: 3/30/09 Revision No: 3 APPLICANTS USRO-1,2 ISRO-1,2 RO-1,2 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Position (A-ATCO, C B A C B A B-BOPO,C-CRS)

Interpret/Diagnose 3,5, 2,5, 3,5, 2,3, 6,8 3,4 6,7, 6,7, 7 4,5, Events and Conditions 8 8 6,8 Comply With and 3,4, 2,5, 2,3, 3,4, 3,4 1,3 6,7, 6,7, 4,5, 6,7, ,6, ,4, Use Procedures (1) 8 8 7 8 7 6,8 Operate Control 2,5, 2,4, 1,3 1,3 6,7, 5,8 ,4, ,4, Boards (2) 8 6,7 6,8 Communicate 3,4, 2,5, 3,4, 3,4, 1,3 1,3 6,7, 6,7, 5,7, 5,6, ,4, ,4, and Interact 8 8 8 7,8 6,8 6,8 Demonstrate 3,4, 3,4, 6,7, 5,6, Supervisory Ability (3) 8 7,8 Comply With and 3,6 3,4 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs Approximate Time: 20 minutes Actual Time: _________________

Reference(s): K/A 2.1.37 RO Importance 4.3 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" Handout(s) TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09 Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: TDB, ruler. calculator Safety Considerations: None Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs TASK The candidate has calculated the shutdown margin in STANDARD: accordance with TDB-V.9 and determined that it is inadequate.

INITIAL The plant is operating at 60% power with group 4 CEAs CONDITIONS: at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).

The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.

INITIATING CUE: You have been requested to perform an instantaneous shutdown margin calculation using TDB-V.9 to determine if technical specification requirement for shutdown margin is being met.

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 JPM Title: Calculate Shutdown Margin with inoperable CEAs Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain a copy of TDB-V.9. After candidate locates TDB-V.9 in the Technical Data Book, provide a copy of TDB-V.9 Part I.

[ SAT ] [ UNSAT ]

2 Obtain a copy of TDB section Obtains copy of TDB-II.

II, Reactivity Curves.

[ SAT ] [ UNSAT ]

3 Determines part I of TDB-V.9. Performs calculation using part procedure should be used. 1.

[ SAT ] [ UNSAT ]

4 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin. +0.7 [between +0.6, +0.8]

[ SAT ] [ UNSAT ]

5 Determines if SDM is Determines Shutdown Margin adequate. is inadequate

[ SAT ] [ UNSAT ]

Termination Criteria: Shutdown Margin determination has been made and TDB V.9, Part One has been filled out.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-1 Rev 3 INITIAL The plant is operating at 60% power with group 4 CEAs CONDITIONS: at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).

The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU INITIATING CUE: You have been requested to perform an instantaneous shutdown margin calculation using TDB-V.9 to determine if technical specification requirement for shutdown margin is being met.

Operator Name: _________________________________

Shutdown Margin adequate? (circle one) YES NO Page 5 of 5

PAGE 1 OF 16 Fort Calhoun Station Unit 1 TDB-V.9 TECHNICAL DATA BOOK SHUTDOWN MARGIN WORKSHEET Change No. EC 40685 Reason for Change Added new power defect figure to TDB-II; base percent power on 1500 MWth. Made editorial changes for consistency.

Requestor M. Rybenski Preparer D. Weis Issue Date 05-18-08 8:30 pm R39

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 2 OF 16 SHUTDOWN MARGIN WORKSHEET PART I - Instantaneous Shutdown Margin for use prior to a Reactor Trip or immediately following a Reactor trip. No changes are assumed for either boron or xenon, since this worksheet is only applicable for calculation of an instantaneous shutdown margin.

NOTE: Enter values exactly as determined from the figures in the Technical Data Book and carry the algebraic signs through the calculations.

Condition

1. Present Date/Time: /
2. Reactor Power (before trip):  %
3. CEA Positions: Group 1 inches Group 2 inches Group 3 inches Group 4 inches
4. Reactor Coolant System Boron Concentration prior to shutdown: (Boron concentration analysis must have been performed within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more recently if boration or dilution has occurred.)

ppm 4

5. Burnup (Take the most recent burnup from the Control Room Log and add 30 MWD/MTU per EFPD.)

MWD/MTU 5

Calculation of Shutdown Margin

6. Enter Regulating Group Worth, based on burnup (Step 5) and CEA positions (Step 3) using TDB Figure II.B.2.

% TDB Figure used:

6 R39

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 3 OF 16

7. Enter Shutdown Group Worths, based on burnup (Step 5) using TDB Figure II.B.1.a.
a. Shutdown Group B  %
b. Shutdown Group A  %
c. Total Shutdown Worth

+ =  %

7.a 7.b 7.c

8. Determine Power Defect Enter Power Defect based on Reactor power level (Step 2) and burnup (Step 5) using TDB Figure II.C.2.a or Figure II.C.2.b.

%

8

9. Determination of Stuck CEA Allowance (3 cases)

NOTE: Consider dropped CEAs which can not be verified to be fully inserted as inoperable.

(Enter N/A if this case is not applicable.)

a. Case I - All CEAs are assumed to be operable. (No known inoperable CEAs)

Assume the highest worth CEAs will stick out of the core upon a Reactor trip.

Enter the value of the most reactive CEA, based on burnup (Step 5), from TDB Figure II.B.1.b., lines (1) thru (3) for the pre-trip configuration. Select the higher value.

%

9.a R39

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 4 OF 16 NOTE: The worth of one inoperable CEA is dependent on the configuration of the withdrawn group(s) and the inoperable CEA.

9

b. Case II - One CEA is known to be inoperable (per Technical Specification 2.10.2(4) a.)

(Enter N/A if this case is not applicable.)

Account for this defective CEA (and the highest worth stuck CEA) by entering only the value from lines (4) thru (17) of TDB Figure II.B.1.b. for the inoperable CEA, based on burnup (Step 5). Select the higher value.

%

9.b NOTE: The worth of more than one inoperable CEA is calculated by multiplying the most conservative Stuck CEA plus Ejected CEA Worth (TDB Figure II.B.1.b.

lines 4-17 by the number of inoperable CEAs.

NOTE: The values of lines (4) thru (17) of TDB Figure II.B.1.b. Include the total reactivity associated with the known inoperable CEA and the highest worth CEA which is assumed to stick out of the core upon a Reactor trip.

c. Case III - More than one CEA is known to be inoperable (per Technical Specification 2.10.2.(4)a.).

(Enter N/A if this case is not applicable.)

(1) Enter total number of CEAs which are known to be inoperable per Technical Specification 2.10.2.(4) a.).

9.c(1)

(2) Enter the most conservative defective CEA worth from TDB Figure II.B.1.b.

Lines (4) thru (17) depending on defective CEA(s) location, based on burnup (Step 5). Select the higher value.

%

9.c(2)

- (# )X(  %) =  %

9.c(1) 9.c(2) 9.c R39

FORT CALHOUN STATION TDB-V.9 TECHNICAL DATA BOOK PAGE 5 OF 16 9

d. Enter total available CEA worth from TDB Figure II.B.1.a. based on burnup (Step 5)

%

9.d

e. Determine the maximum stuck CEA worth by selecting the minimum of either 9.c or 9.d and record that value.

%

9.e

f. Enter value from 9.a or 9.b or 9.e as appropriate  %

9.f

10. Calculation of the Total Instantaneous Shutdown Margin (SDMI):

SDMI = Stuck CEAs + Power Defect - S/D CEAs worth - Regulating CEA worth SDMI =  % +  % -  % -  % =  % Total 9.f 8 7.c 6 10

11. Calculate difference from required 3.6% p Shutdown Margin.

(  % ) + 3.6% =  %

10 11 NOTE: A 3.6% shutdown margin must be maintained in a Hot Shutdown condition, Tc > 210 F (Technical Specification 2.10.2(1) and TDB-VI Item 13.0).

12. Shutdown Margin check:
a. If Step 11 is less than or equal to zero, the shutdown margin is adequate.
b. If Step 11 is greater than zero, use OI-ERFCS-1, to determine the number of gallons of acid to add.

REMARKS Completed by Date/Time /

R39

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown Approximate Time: 10 minutes Actual Time: _________________

Reference(s): K/A# 2.1.25 RO Importance 3.9 TDB-III.1.a, "TEMPERATURE CORRECTION FOR PRESSURIZER LEVEL INDICATORS LI-101X/Y".

TDB-III.2, "ACTUAL LEVEL IN PRESSURIZER VS. INDICATED LEVEL IN PRESSURIZER.

Handouts(s): None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/24/09 Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: TDB, Ruler, Steam Tables Safety Considerations:

Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown TASK The candidate has determined the actual pressurizer STANDARD level from LI-101Y using TDB-III.1.a and from LI-106 using TDB-III.2 and has recommended that the pressurizer heaters not be turned off.

INITIAL The RCS is being cooled down per OP-3A. RCS CONDITIONS pressure is at 250 psia.

A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.

The pressurizer level indications are as follows:

o LI-101X = 48%

o LI-101Y = 50%

o LI-106 = 34%

INITIATING CUE: The CRS has directed you to determine actual pressurizer level using both LI-101Y and LI-106 and recommend if the pressurizer heaters need to be turned off?

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-2 Rev 3 JPM Title: Determine Pressurizer Level During Cooldown Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to TDB-III.1.a and Level based on LR-101Y is determines that the actual approximately 40% (39 - 40%)

pressurizer level based on LR-101Y. [ SAT ] [ UNSAT ]

2 Refers to TDB-III.2 and Level based on LI-106 is determines that the actual approximately 40% (39 - 41%)

pressurizer level based on LI-106. [ SAT ] [ UNSAT ]

3 Determines if heaters need to Determines that heaters do not be turned off. have to be turned off because actual level is above 32%

[ SAT ] [ UNSAT ]

Termination Criteria: Actual level has been determined both channels and a determination has been made on the need to turn off the heaters.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-2 Rev 3 INITIAL The RCS is being cooled down per OP-3A. RCS CONDITIONS pressure is at 250 psia.

A dummy level signal has been placed on pressurizer level channel LI-101X and it is selected as the controlling channel.

The pressurizer level indications are as follows:

o LI-101X = 48%

o LI-101Y = 50%

o LI-106 = 34%

INITIATING CUE: The CRS has directed you to determine actual pressurizer level using both LI-101Y and LI-106 and recommend if the pressurizer heaters need to be turned off?

NAME: ________________________________________

Actual Level based on LR-101Y: ______________%

Actual Level based on LI-106: _______________%

Do Heaters Need to be turned off: YES NO Page 5 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.

Approximate Time: 20 minutes Actual Time: _________________

Reference(s): K/A# 2.2.15 RO Importance 3.9 P&ID Figure 8.1-1 (File 12234)

Handout(s) None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/05/09 Page 1 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.

Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: P&ID Books Safety Considerations:

Comments:

Page 2 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.

TASK The candidate has referred to plant electrical drawing STANDARD: Figure 8.1-1 (File 12234) and has listed the electrical loads powered from MCC-3B2. In addition, the candidate has provided a list of the breakers that would need to be ensured closed to supply power from bus 1B3C to FW-54 Fuel Oil Transfer Pump, FO-37.

INITIAL The plant is operating at full power.

CONDITIONS:

You are working in the Operations Control Center (OCC).

Maintenance is requesting that MCC-3B2 be taken out of service for some equipment repairs.

The OCC Supervisor is working on a change to procedure EOP-07, "STATION BLACKOUT" INITIATING CUE: The OCC Supervisor has directed you to determine what equipment would be affected by tagout of MCC-3B2.

The OCC Supervisor has directed you to list the breakers that you would need to ensure closed to be able to supply power to FW-54 Fuel Oil Transfer Pump, FO-37, if bus 1B3C were energized from 13.8 KV and FW-54's shaft driven generator, EE-54, failed.

Page 3 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.

Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to P&ID to determine Note:

affected equipment. If candidate requests copy of the ELDL, "Electrical Load Distribution List",

Inform him that the ELDL is not available.

Uses P&ID Figure 8.1-1 (File 12234) to determine affected equipment.

[ SAT ] [ UNSAT ]

2 Provides list of affected List includes:

equipment. VD-7A AC-9A EHC-3A EE2G-1A VD-5A CF-4 CF-5 CF-7A VA-151C VA-158A,C,E,G,H,K,M LO-7 LO-6 LO-2 VA-766

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 JPM Title: Determine equipment lost by tagout of an MCC.

STEP ELEMENT STANDARD 3 Refers to P&ID to determine Uses P&ID Figure 8.1-1 (File breakers that must be ensured 12234) to determine breakers closed to supply power from that must be ensured closed.

bus 1B3C to FO-37.

[ SAT ] [ UNSAT ]

4 Provides list of breakers Breakers include:

BT-1B3C BT-1B4C 1B4C-1 EE-55 Feeder breaker on MCC-4C5 FO-37 Feeder Breaker on MCC-4C6 Note: he may also list Auto Transfer Switch, EE-55, position, but this is not required.

[ SAT ] [ UNSAT ]

Termination Criteria: List of affected equipment from MCC-3B2 has been provided and a list of breakers that must be ensured closed to power FO-37 from bus 1B3C has been provided.

Page 5 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 INITIAL The plant is operating at full power.

CONDITIONS:

You are working in the Operations Control Center (OCC).

Maintenance is requesting that MCC-3B2 be taken out of service for some equipment repairs.

The OCC Supervisor is working on a change to procedure EOP-07, "STATION BLACKOUT" INITIATING CUE: The OCC Supervisor has directed you to determine what equipment would be affected by tagout of MCC-3B2.

The OCC Supervisor has directed you to list the breakers that you would need to ensure closed to be able to supply power to FW-54 Fuel Oil Transfer Pump, FO-37, if bus 1B3C were energized from 13.8 KV and FW-54's shaft driven generator, EE-54, failed.

Page 6 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 Operator Name:_______________________________________

Equipment affected by tagout of MCC-3B2:

Page 7 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-3 Rev 2 Operator Name:_______________________________________

Breakers that must be ensured closed to power FO-37 from bus 1B3C:

Page 8 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Approximate Time: 12 minutes Actual Time: _________________

Reference(s): K/A# 2.3.7 RO Importance 3.5 GET-Radiation Worker Training.

Standing Order G-101, "RADIATION WORKER PRACTICES."

Handouts: None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/05/09 Page 1 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: EAD, TLD, PCM-1, G-M with pancake probe Safety Considerations:

Comments: Can be conducted in GET trailer or during actual RCA Entry Page 2 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms TASK The candidate has entered and started to exit the STANDARD: Radiation Control Area (RCA). After receiving an alarm on the first PCM-1 that was used to monitor for contamination, he used a different PCM-1 to monitor again for contamination. After receiving the second alarm, he contacted Radiation Protection and frisked himself using a pancake probe, as directed. After determining that he was not contaminated, he exited the RCA.

INITIAL The plant is operating at full power. Charging Pump, CONDITIONS: CH-1A is running but its motor current is higher than expected. The CRS is planning to place CH-1B in service and shutdown CH-1A.

INITIATING CUE: The CRS has directed you to enter the RCA and place the Packing Cooling Pump for CH-1B in service. After starting the pump, you are to return to the Control Room.

Page 3 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Critical Steps shown in gray STEP ELEMENT STANDARD 1 Review the RWP. Reads RWP.

[ SAT ] [ UNSAT ]

2 Determine Radiological Checks survey maps or Conditions. discusses radiological conditions with RP personnel.

[ SAT ] [ UNSAT ]

3 Obtains Dosimetry. Obtain TLD and EAD.

[ SAT ] [ UNSAT ]

4 Sign on to appropriate RWP. Insert EAD in reader. Scan PID and RWP number.

[ SAT ] [ UNSAT ]

5 Enter RCA. RCA Entered.

[ SAT ] [ UNSAT ]

6 CUE: The Packing Cooling Pump for CH-1B has been started , exit the RCA.

NOTE: Do not actually enter room 6 for ALARA reasons.

7 Exits RCA. Returns to RCA access point.

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms STEP ELEMENT STANDARD 8 Monitor for personnel Monitor for contamination contamination prior to exiting using PCM-1.

RCA.

[ SAT ] [ UNSAT ]

CUE: After examinee has completed counting on a PCM-1, tell him to assume that the PCM-1 alarmed-zone 6.

9 Monitor for contamination a Monitor for contamination second time. again using a different PCM-1.

[ SAT ] [ UNSAT ]

CUE: After examinee has completed counting on another PCM-1, tell him to assume that this PCM-1 also alarmed- zone 6.

10 Contact RP. RP Contacted.

[ SAT ] [ UNSAT ]

CUE: RP directs you to monitor for contamination using frisker.

11 Uses Frisker to monitor for Slowly moves pancake probe contamination. over hands, shoes and body surface.

CUE: Frisker cpm as read.

[ SAT ] [ UNSAT ]

Page 5 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms Termination Criteria: RCA has been exited.

Page 6 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 JPM Title: RCA Entry and Exit with PCM Alarms NOTE to RP Tech As a part of this candidates NRC license exam, he must enter and exit the RCA.

During RCA exit, he has been given verbal Cues that he has received a zone 6 alarm on two separate PCM-1 monitors.

As a part of this JPM, we would like you to direct him to perform a whole body frisk on himself.

Page 7 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-4 Rev 2 INITIAL The plant is operating at full power. Charging Pump, CONDITIONS: CH-1A is running but its motor current is higher than expected. The CRS is planning to place CH-1B in service and shutdown CH-1A.

INITIATING CUE: The CRS has directed you to enter the RCA and place the Packing Cooling Pump for CH-1B in service. After starting the pump, you are to return to the Control Room.

Page 8 of 8

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 JPM Title: Review Shutdown Margin Calculation with inoperable CEAs Approximate Time: 25 minutes Actual Time: _________________

Reference(s): K/A 2.1.37 SRO Importance 4.6 TDB-V.9, "SHUTDOWN MARGIN WORKSHEET" TDB-II, "REACTIVITY CURVES" Handout(s): Completed TDB-V.9 Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: TDB, ruler, calculator Safety Considerations:

Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 TASK The candidate reviewed the Shutdown Margin STANDARD: calculation that was prepared by the STA and found 2 errors in the calculation, corrected the errors and determined that the Shutdown Margin is inadequate.

INITIAL The plant is operating at 60% power with group 4 CONDITIONS: CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).

The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.

INITIATING CUE: The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has directed you to review the shutdown margin calculation and, if there are any mistakes, correct them.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

Provide Shutdown Margin Calculation to candidate with initiating cue.

1 Reviews shutdown margin Determines that there was an calculation. error in step 7.a due to reading the value from the wrong row.

5.238 (Shutdown Group A+B worth was entered instead of shutdown group B worth).

[ SAT ] [ UNSAT ]

2 Determines that in step 8, the 100% power defect was used instead of the 60% power defect.

[ SAT ] [ UNSAT ]

3 Performs calculation of the Difference calculated on line difference between actual and 11 of TDB-V.9, section 1 is required shutdown margin +0.7 [between +0.6, +0.8].

using corrected values.

[ SAT ] [ UNSAT ]

4 Determines if SDM is Determines Shutdown Margin adequate. is inadequate.

[ SAT ] [ UNSAT ]

Termination Criteria: The SRO has determined that shutdown margin is not adequate and has corrected the SDM calculation.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-5 Rev 3 INITIAL The plant is operating at 60% power with group 4 CONDITIONS: CEAs at 110 inches withdrawn. Group A CEA #36 and Group 2 CEA #24 have been declared inoperable (untrippable).

The RCS boron concentration is 400 ppm. The burnup is 12000 MWD/MTU.

INITIATING CUE: The STA has performed a shutdown margin calculation and determined that Shutdown Margin is adequate. The Shift Manager has directed you to review the shutdown margin calculation and, if there are any mistakes, correct them.

Operator Name: _________________________________

Shutdown Margin adequate? (circle one) YES NO

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Approximate Time: 15 minutes Actual Time: _________________

Reference(s): K/A# 2.1.5 SRO Importance 3.9 Technical Specifications Table 5.2-1 SO-O-1, "CONDUCT OF OPERATIONS" SO-G-52, "PLANT STAFF WORKING HOURS" SO-G-28, "STATION FIRE PLAN" Handout(s): None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09 Page 1 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations:

Comments:

Page 2 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing TASK The candidate has reviewed the staffing suggestions STANDARD: made by his STA and his AON and has determined that either a qualified STA or a qualified CRS must be called in and be in position within two hours. He has also determined that the AON cannot also serve as Control Room Communicator due to Fire Brigade manning requirements.

INITIAL The plant is operating at full power.

CONDITIONS:

You are the Shift Manager. Your crew consists of:

o you o a CRS o a STA (who is also CRS qualified) o two RO's o an EONA, o an EONT, o an AON (who is also Communicator qualified) o a Control Room Communicator.

Half way through your shift, your CRS and your Control Room Communicator became sick and needed to go home.

INITIATING CUE: Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.

Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.

Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.

Page 3 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Critical Steps shown in gray STEP ELEMENT STANDARD 1 Determine if the STA may fill Refers to Technical both the CRS and the STA Specifications Table 5.2-1 and position for the remainder of Standing Order SO-O-1.

the shift.

Determines that 2 SROs and an STA are required and this suggestion is not acceptable.

[ SAT ] [ UNSAT ]

2 Determine if the AON may fill Refers to Technical both the AON and the Control Specifications Table 5.2-1 and Room Communicator position Standing Order SO-G-28.

for the remainder of the shift.

Determines that an AON, an EONT and a communicator are required for the Fire Brigade.

[ SAT ] [ UNSAT ]

3 Determine what actions must Determines that the CRS must be taken and when these turnover to the CRS qualified actions must be taken. STA and that immediate action must be taken to call in another qualified STA or another qualified CRS and another plant Operator or Communicator and the called in Operators must be in position within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

[ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 JPM Title: Determine Shift Staffing Termination Criteria: Candidate has determined shift staffing requirements, actions that must be taken and required time frame for these actions.

Page 5 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-6 Rev 3 INITIAL The plant is operating at full power.

CONDITIONS:

You are the Shift Manager. Your crew consists of:

o you o a CRS o a STA (who is also CRS qualified) o two RO's o an EONA, o an EONT, o an AON (who is also Communicator qualified) o a Control Room Communicator.

Half way through your shift, your CRS and your Control Room Communicator became sick and needed to go home.

INITIATING CUE: Your STA suggests that he can serve as both CRS and STA for the remainder of the shift since he is qualified for both positions.

Your AON suggests that he can serve as both AON and Control Room Communicator for the remainder of the shift since he is qualified for both positions.

Determine if each of these suggestions is acceptable. If not, specify what actions must be taken and when they must be taken.

NAME:_____________________________________________

Can the STA serve as both CRS and STA? YES NO Can the AON serve as both AON and Control Room Communicator YES NO What action, if any, must be taken? When must it be taken?

Page 6 of 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability Approximate Time: 12 minutes Actual Time: _________________

Reference(s): K/A# 2.2.22 SRO Importance 4.7 TDB VIII, "EQUIPMENT OPERABILITY GUIDANCE" Technical Specification 2.4 Technical Specification 2.0.1 Handout(s): None Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 02/20/09 Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations:

Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability TASK The candidate has reviewed TDB-VIII and Technical STANDARD: Specifications and has determined that the action statement for Technical Specification 2.0.1 applies. The plant must be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

INITIAL The plant is operating at full power.

CONDITIONS:

It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.

INITIATING CUE: Determine the applicable Technical Specification and required actions, if any, to be taken.

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 JPM Title: Determine RW System Operability Critical Steps shown in gray STEP ELEMENT STANDARD 1 Refers to TDB-VIII. Enters TDB-VIII.

[ SAT ] [ UNSAT ]

2 Refers to Table 2-1 to Determines that T.S. 2.0.1 determine applicable LCO. applies with these conditions.

[ SAT ] [ UNSAT ]

3 Determines Tech Spec. 2.0.1 Plant must be in Hot Shutdown required Action Statement. within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

[ SAT ] [ UNSAT ]

Termination Criteria: Technical Specification 2.0.1 has been entered.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-7 Rev 1 INITIAL The plant is operating at full power.

CONDITIONS:

It has been determined that RW/CCW Backup Header Isolation Valves, HCV-2893 and HCV-2894, are both inoperable. They are both closed and cannot be opened.

INITIATING CUE: Determine the applicable Technical Specification and required actions, if any, to be taken.

Name: ________________________________________

Technical Specification Entered, if any:

Required Action, if any:

Page 5 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B Approximate Time: 10 minutes Actual Time: _________________

Reference(s): K/A# 2.3.6 SRO Importance 3.8 OI-WDL-3, "LIQUID WASTE DISPOSAL RELEASE" FC-211, "WASTE LIQUID TANK RELEASE PERMIT" Handout(s): Partially filled out OI-WDL-3 Approved FC-211 Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/23/09 Page 1 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: Calculator Safety Considerations:

Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B TASK The SRO candidate reviewed OI-WDL-3 and the FC-211 STANDARD: release permit and determined that the EONA used the wrong maximum release rate when filling out OI-WDL-3 and that the chemist specified the wrong flow rate in the release permit, section VII. Special Instructions. The release was not authorized as written.

INITIAL The plant is operating at full power.

CONDITIONS: Three Circulating Water Pumps are running.

Two Raw Water Pumps are operating.

All Radiation Monitors are operable.

A release of Monitor Tank, WD-22B is planned.

INITIATING CUE: You are the Shift Manager. The EONA has given you a copy of OI-WDL-3 and a Release Permit for the release of WD-22B. Review the permit and, if acceptable, authorize the release. If not acceptable, make any required corrections.

Page 3 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 JPM Title: Authorize Release of Monitor Tank WD-22B Critical Steps shown in gray STEP ELEMENT STANDARD 1 Reviews partially filled out OI- Examines procedure and WDL-3 and associated FC-211 Release Permit.

Release Permit.

[ SAT ] [ UNSAT ]

2 Determines that the maximum Maximum release rate should release rate and administrative be 84.6 gpm. Administrative release rate recorded on the release rate should be 76.1 procedure do not agree with gpm.

the Release Permit.

[ SAT ] [ UNSAT ]

3 Determines that the Chemist Unloader should be set to has used the wrong flow rate allow a flow rate of 76.1 gpm.

on the FC-211 release rate, section VII. Special Instructions, item B. [ SAT ] [ UNSAT ]

4 Release Authorization. Does not authorize release as written.

Corrects maximum (84.6 gpm) and administrative (76.1 gpm) release rates.

[ SAT ] [ UNSAT ]

Termination Criteria: Candidate has reviewed the procedure and release permit and has refused to authorize the release as written.

Page 4 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-8 Rev 3 INITIAL The plant is operating at full power.

CONDITIONS: Three Circulating Water Pumps are running.

Two Raw Water Pumps are operating.

All Radiation Monitors are operable.

A release of Monitor Tank, WD-22B is planned.

INITIATING CUE: You are the Shift Manager. The EONA has given you a copy of OI-WDL-3 and a Release Permit for the release of WD-22B. Review the permit and, if acceptable, authorize the release. If not acceptable, make any required corrections.

Page 5 of 5

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs Approximate Time: 20 minutes Actual Time: _________________

Reference(s): K/A# 2.4.41 SRO Importance 4.6 K/A# 2.4.44 SRO Importance 4.4 EPIP-OSC-1, "EMERGENCY CLASSIFICATION" EPIP-EOF-7, "PROTECTIVE ACTION GUIDELINES TDB-IV.8, "AREA MONITORING SETPOINTS" EAGLE 6.0.0 Users Manual Handouts(s): FC-1188 EAGLE OUTPUT Time Critical: YES (Cue# 2)

Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/25/09 Page 1 of 7

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: SRO , Time Critical - 15 minutes after determining EAL Page 2 of 7

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs TASK The SRO candidate reviewed the plant conditions, STANDARD: referred to EPIP-OSC-1 and TDB-IV.8 and classified the event as a SITE AREA EMERGENCY, EAL 7.3.

Within 15 minutes of classifying the event, the candidate used the EAL and the data from the EAGLE output to determine there are no Protective Action Recommendations and completed page one of form FC-1188 so that offsite notifications can be made.

INITIAL A refueling outage is in progress.

CONDITIONS: Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack.

High radiation alarms were received on RM-085 and RM-087.

RM-085 is reading 1200 mrem/hr.

RM-087 is reading 1100 mrem/hr.

Radiation levels on RM-052 and RM-062 are also rising.

There is no precipitation.

Your Shift HP is running EAGLE INITIATING CUE: You are the Shift Manager. Determine the appropriate EAL, if any, in accordance with EPIP-OSC-1.

CUE #2: ***** TIME CRITICAL*****

Your Shift HP has run EAGLE and has provided you with the output. You are directed to complete page 1 of form FC-1188 so your Communicator can make the required notifications.

Page 3 of 7

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs Critical Steps shown in gray STEP ELEMENT STANDARD Examiner Note:

Provide only the initiating cue to the candidate at this time.

1 Refer to Emergency Plan. Refer to EPIP-OSC-1.

[ SAT ] [ UNSAT ]

2 Classify the event. This Event should be classified as a SITE AREA EMERGENCY, EAL 7.3, "MAJOR IRRADIATED FUEL ACCIDENT" RM-087 is reading more than 1000 times its normal refueling shutdown value per TDB-IV.8

[ SAT ] [ UNSAT ]

Examiner Note: Provide cue#2, EAGLE output and Blank FC-1188 form to candidate. Note the time Start Time:______________

Page 4 of 7

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: A-9 Rev 4 JPM Title: Emergency Classification and PARs STEP ELEMENT STANDARD 3 Determine Protective Action ***** TIME CRITICAL *****

Recommendations and fill out Form FC-1188 must be filled form FC-1188 for notifications. out within 15 minutes and must contain the following information:

Initial Declaration Site Area EAL 7.3 Wind from 122° Wind Speed10 MPH No Precipitation Temperature difference 1°C/100m Stability Class "E" There is an airborne release There are no PARs Plant Status: shutdown Approval Signature, date and time.

End Time:____________

Elapsed Time:__________

[ SAT ] [ UNSAT ]

Termination Criteria: PARS have been determined and FC-1188 has been filled out within 15 minutes of classifying the event.

Page 5 of 7

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 4 INITIAL A refueling outage is in progress.

CONDITIONS: Spent fuel assemblies were being moved using FH-12 when a fuel assembly fell from FH-12 and landed on a spent fuel rack.

High radiation alarms were received on RM-085 and RM-087.

RM-085 is reading 1200 mrem/hr.

RM-087 is reading 1100 mrem/hr.

Radiation levels on RM-052 and RM-062 are also rising.

There is no precipitation.

Your Shift HP is running EAGLE INITIATING CUE: You are the Shift Manager. Determine the appropriate EAL, if any, in accordance with EPIP-OSC-1.

Name:_________________________________________________

Event Classification (circle one)

NONE Notice of Unusual Event Alert Site Area Emergency General Emergency EAL# ___________________

Page 6 of 7

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:A-9 Rev 4 CUE #2: ***** TIME CRITICAL*****

Your Shift HP has run EAGLE and has provided you with the output. You are directed to complete page 1 of form FC-1188 so your Communicator can make the required notifications.

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FORT CALHOUN STATION FC-1188 GENERAL FORM R22 PAGE 1 OF 2 FORT CALHOUN STATION - EMERGENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactors Call Back #:

THE COMMAND AND CONTROL POSITION MUST:

  • Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed.
  • Ensure that all offsite notifications are performed as required.
1. [ ] Initial Declaration - for Initial declaration of any emergency classification

[ ] Hourly - When completing Hourly updates, one hour from time of the most recent event notification and on an hourly basis until event termination.

[ ] PAR Change - Any change in Protective Action Recommendations (PARs) and a new classification is not being declared.

[ ] Termination Classification: [ ] NOUE [ ] Alert [ ] Site Area [ ] General EAL #:

Time Event Declared: Time Event Terminated:

OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)

2. Wind From Weather Wind Speed MPH (Use Precipitation: [ ] Yes [ ] No Degrees (10m): Slowest 10m):

Temperature Difference °C/100m (use most positive T)

Stability Class -[ ] A [ ]B [ ]C [ ]D [ ]E [ ]F [ ] G+

-1.9 >-1.9 to -1.7 >-1.7 to -1.5 >-1.5 to -0.5 >-0.5 to 1.5 >1.5 to 4.0 > 4.0

3. There [ ] is [ ] no release of radioactive effluent to the environment

[ ] was [ ] an airborne that is the result of or associated with this event

[ ] will be [ ] a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS

4. Protective Action Recommendations (PARs)

None Evacuate Sectors Shelter Sectors 0-2 Miles 2-5 Miles 5-10 Miles

5. Prognosis: [ ] Stable [ ] Unstable Plant Status: [ ] at Power [ ] Shutdown
6. Remarks Approved: Date: Time:

FORT CALHOUN STATION FC-1188 GENERAL FORM R22 PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers) 3 Name of contact (optional)

State of Iowa State of Nebraska Harrison County Pottawattamie County Washington County Record any comments, difficulties or observations you had while making this notification NOTE 1: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a T of +2.0 and a stability class F. For all other conditions, use a T of -1.0 and a stability class D.

FORT CALHOUN STATION FC-1188 GENERAL FORM KEY R22 PAGE 1 OF 2 FORT CALHOUN STATION - EMERGENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactors Call Back #:

THE COMMAND AND CONTROL POSITION MUST:

  • Ensure initiation and completion of the FC-1188 form, but may obtain assistance from other personnel as needed.
  • Ensure that all offsite notifications are performed as required.
1. [ X] Initial Declaration - for Initial declaration of any emergency classification

[ ] Hourly - When completing Hourly updates, one hour from time of the most recent event notification and on an hourly basis until event termination.

[ ] PAR Change - Any change in Protective Action Recommendations (PARs) and a new classification is not being declared.

[ ] Termination Classification: [ ] NOUE [ ] Alert [X ] Site Area [ ] General EAL #: 7.3 Time Event Declared: Time Event Terminated:

OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)

2. Wind From Weather Wind Speed MPH (Use Precipitation: [ ] Yes [X] No Degrees (10m): 122 Slowest 10m): 10 Temperature Difference °C/100m (use most positive T)

Stability Class -[ ] A [ ]B [ ]C [ ]D [X ] E [ ]F [ ] G+

-1.9 >-1.9 to -1.7 >-1.7 to -1.5 >-1.5 to -0.5 >-0.5 to 1.5 >1.5 to 4.0 > 4.0

3. There [X ] is [ ] no release of radioactive effluent to the environment

[ ] was [X] an airborne that is the result of or associated with this event

[ ] will be [ ] a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS

4. Protective Action Recommendations (PARs)

None Evacuate Sectors Shelter Sectors 0-2 Miles X 2-5 Miles X 5-10 Miles X

5. Prognosis: [X ] Stable [ ] Unstable Plant Status: [ ] at Power [X ] Shutdown
6. Remarks Approved: Date: Time:

FORT CALHOUN STATION FC-1188 GENERAL FORM R22 PAGE 2 OF 2 Notify the following agencies: (refer to Emergency Phone Book for alternate phone numbers) 3 Name of contact (optional)

State of Iowa State of Nebraska Harrison County Pottawattamie County Washington County Record any comments, difficulties or observations you had while making this notification NOTE 1: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a T of +2.0 and a stability class F. For all other conditions, use a T of -1.0 and a stability class D.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Location: Auxiliary Building (RCA) and Room 81 Approximate Time: 30 minutes Actual Time: _________________

Reference(s): K/A 022000 A2.05 AOP-11, "LOSS OF COMPONENT COOLING WATER" OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" Handout(s): AOP-11, "LOSS OF COMPONENT COOLING WATER", Step 12.

OI-AOV-1, "AIR OPERATED VALVE MANUAL OPERATION" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: This JPM requires entry into the RCA.

Climbing of a ladder may be required.

Comments:

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers TASK The Candidate placed Raw Water Backup cooling in STANDARD: service for Containment Cooling Coil, VA-1A and Shutdown Cooling Heat Exchanger, AC-4B in accordance with AOP-11.

INITIAL A LOCA occurred 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.

CONDITIONS: EOP-AOP Attachment 8, "COOLED SI FLOW WITH RAS" has been implemented.

15 minutes ago, a total loss of CCW occurred.

The CRS is implementing AOP-11.

Containment temperature is 120°F.

The river level is 990 feet.

INITIATING CUE: The CRS has directed you to establish Raw Water Backup to Containment Cooling Coil, VA-1A, per AOP-11 step 12.c. and OI-AOV-1.

CUE #2: The CRS has directed you to establish Raw Water Backup to Shutdown Cooling Heat Exchanger, AC-4B, per AOP-11 step 12.h.

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Critical Steps shown in gray STEP ELEMENT STANDARD 1 Obtain copies of AOP-11 and Cue: Provide copies of AOP-OI-AOV-1. 11, step 12 and OI-AOV-1.

[ SAT ] [ UNSAT ]

2 Place CNTMT CLG COIL CUE: Control Room VA-1A AC VLVS CONTROL Operator reports that HCV-SW HCV-400B/D in CLOSE. 400B/D is in CLOSE.

[ SAT ] [ UNSAT ]

3 Unlock and release the Room-69 hand-jacks from BOTH of the Remove the locking following RW Interface mechanisms and covers from Valves: BOTH HCV-400E and HCV-HCV-400E, CNTMT 400F. Use the ratchet to VA-1A COOLING COIL release the handjacks by RAW WATER INLET turning the locking nut VALVE. CLOCKWISE until it reaches HCV-400F, CNTMT the bottom.

VA-1A COOLING COIL BACK-UP RAW WATER [ SAT ] [ UNSAT ]

OUTLET VALVE.

CUE: Another Operator will make the entry in the Locked Components Log.

4 Locally open both VA-1A RW Room-69 Interface Valves, HCV-400E/F IA-HCV-400E-TV 4-way by placing the following valves manual control valve in OPEN.

to OPEN:

IA-HCV-400E-TV, 4- IA-HCV-400F-TV 4-way WAY MANUAL manual control valve in OPEN.

CONTROL VALVE.

IA-HCV-400F-TV, 4-WAY MANUAL CONTROL VALVE. [ SAT ] [ UNSAT ]

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers STEP ELEMENT STANDARD Note to Examiner: Provide Cue #2 to Candidate.

5 Close Both AC-4B CCW CUE: The Control Room Isolation Valves: Operator reports that HCV-HCV-481 481 and HCV-485 are closed.

HCV-485 6 Unlock and release the Corridor 4 hand-jacks from BOTH of the following RW Interface Unlock and release the hand-Valves (Corridor 4): jacks from both:

HCV-483A, HCV-483A SHUTDOWN HCV-483B COOLING HT EXCH AC-4B BACK-UP RAW WATER INLET VALVE HCV-483B, [ SAT ] [ UNSAT ]

SHUTDOWN COOLING HT EXCH AC-4B BACK-UP RAW WATER OUTLET VALVE 7 Locally open both AC-4B RW Corridor 4 Interface Valves,HCV-483A/B, by placing the following valves IA-HCV-483A-TV 3-way to OPEN: manual control valve in OPEN.

IA-HCV-483A-TV, 3-WAY MANUAL IA-HCV-483B-TV 3-way CONTROL VALVE manual control valve in OPEN.

IA-HCV-483B-TV, 3-WAY MANUAL CONTROL VALVE [ SAT ] [ UNSAT ]

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 JPM Title: Provide Raw Water Backup Cooling to Containment Coolers Termination Criteria: Raw Water Backup Cooling is being provided to VA-1A and AC-4B.

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 INITIAL A LOCA occurred 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.

CONDITIONS: EOP-AOP Attachment 8, "COOLED SI FLOW WITH RAS" has been implemented.

15 minutes ago, a total loss of CCW occurred.

The CRS is implementing AOP-11.

Containment temperature is 120°F.

The river level is 990 feet.

INITIATING CUE: The CRS has directed you to establish Raw Water Backup to Containment Cooling Coil, VA-1A, per AOP-11 step 12.c. and OI-AOV-1.

Page 7 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-1 Rev 3 CUE #2: The CRS has directed you to establish Raw Water Backup to Shutdown Cooling Heat Exchanger, AC-4B, per AOP-11 step 12.h.

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AOP-11 Page 20 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. IF CCW can NOT be restored, THEN align RW to desired components as follows:
a. IF SIAS/CIAS has occurred, THEN ensure ALL of the following switches are in OVRRD:
  • HC-2809/11/14/15, SI PUMP AC VALVES SIAS OVERRIDE SWITCH
  • HC-2808/10/12/13, SI PUMP AC VALVES SIAS OVERRIDE SWITCH
  • HC-400/403, CNTMT CLR AC VLVS CIAS OVERRIDE SWITCH
b. Ensure BOTH RW/CCW Backup Header Isolation Valves are open:
  • HCV-2893
  • HCV-2894 (continue)

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AOP-11 Page 21 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)

NOTE The RW Interface Valves are locally opened and closed using a local IA Supply Valve.

Positions on the local valve correspond to the position of the RW Interface Valve.

CAUTIONS

1. To prevent Raw Water Pump damage, maintain flowrates between 1700 and 8500 gpm per pump.
2. Backup cooling should not be used on Containment Cooling Coils with river level less than 983.5 ft or Containment temperatures greater than 150°F.

Flashing and potential water hammer in the Containment Coils may be present with Raw Water aligned under low river conditions (<983.5 ft) and at higher temperatures.

3. To prevent seal degradation, it is desirable to align RW to operating HPSI, LPSI and CS Pumps. During Shutdown Cooling operations, it should be aligned within one hour. However, after a RAS, a loss of cooling water can be tolerated with no loss of pump performance.
c. IF VA-3A, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1A by performing the following steps:
1) Place CNTMT CLG COIL VA-1A AC VLVS CONTROL SW HCV-400B/D in CLOSE.

(continue)

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AOP-11 Page 22 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.c. (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
  • HCV-400E, CNTMT VA-1A COOLING COIL RAW WATER INLET VALVE
  • HCV-400F, CNTMT VA-1A COOLING COIL BACK-UP RAW WATER OUTLET VALVE
3) Locally open both VA-1A RW Interface Valves, HCV-400E/F by placing the following valves to OPEN (Room 69):
  • IA-HCV-400E-TV, 4-WAY MANUAL CONTROL VALVE
  • IA-HCV-400F-TV, 4-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 23 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
d. IF VA-3B, Containment Vent Fan, is in service, THEN establish RW Flow to VA-1B by performing the following steps:
1) Place CNTMT CLG COIL VA-1B AC VLVS CONTROL SW HCV-401B/D in CLOSE.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
  • HCV-401E, CNTMT VA-1B COOLING COIL BACK-UP RAW WATER INLET VALVE
  • HCV-401F, CNTMT VA-1B COOLING COIL BACK-UP RAW WATER OUTLET VALVE (continue)

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AOP-11 Page 24 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.d (continued)

3) Locally open both VA-1B RW Interface Valves, HCV-401E/F by placing the following valves in OPEN (Room 69):
  • IA-HCV-401E-TV, 4-WAY MANUAL CONTROL VALVE
  • IA-HCV-401F-TV, 4-WAY MANUAL CONTROL VALVE
e. IF VA-7C, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8A by performing the following steps:
1) Place CNTMT CLG COIL VA-8A AC VLVS CONTROL SW HCV-402B/D in CLOSE.

(continue)

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AOP-11 Page 25 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.e (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
  • HCV-402E, CNTMT VA-8A COOLING COIL BACK-UP RAW WATER INLET VALVE
  • HCV-402F, CNTMT VA-8A COOLING COIL BACK-UP RAW WATER OUTLET VALVE
3) Locally open both VA-8A RW Interface Valves, HCV-402E/F by placing the following valves to OPEN (Room 69):
  • IA-HCV-402E-TV, 4-WAY MANUAL CONTROL VALVE
  • IA-HCV-402F-TV, 4-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 26 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
f. IF VA-7D, Containment Vent Fan, is in service, THEN establish RW Flow to VA-8B by performing the following steps:
1) Place CNTMT CLG COIL VA-8B AC VLVS CONTROL SW HCV-403B/D in CLOSE.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 69):
  • HCV-403E, RAW WATER RETURN HEADER TO CONT AIR CLNG &

FILTERING ISOLATION VALVE

  • HCV-403F, CNTMT VA-8B COOLING COIL BACK-UP RAW WATER OUTLET VALVE (continue)

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AOP-11 Page 27 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.f (continued)

3) Locally open both VA-8B RW Interface Valves, HCV-403E/F by placing the following valves to OPEN (Room 69):
  • IA-HCV-403E-TV, 4-WAY MANUAL CONTROL VALVE
  • IA-HCV-403F-TV, 4-WAY MANUAL CONTROL VALVE
g. IF AC-4A, SDC HX, is in service, THEN establish RW flow to AC-4A by performing the following steps:
1) Close BOTH AC-4A CCW Isolation Valves:
  • HCV-480
  • HCV-484 (continue)

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AOP-11 Page 28 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.g (continued)

NOTE The operator may need assistance during performance of the next step as the handwheel may be difficult to reach. Climbing on wall-mounted accumulators to reach the handwheel should be avoided.

2) Unlock and release the hand-jacks from BOTH of the following SDC HX RW Interface Valves (Corridor 4):
3) Locally open both AC-4A RW Interface Valves by placing the following valves to OPEN (Corridor 4):
  • IA-HCV-482A-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-482B-TV, 3-WAY MANUAL CONTROL VALVE R14

AOP-11 Page 29 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
h. IF AC-4B, SDC HX, is in service, THEN establish RW flow to AC-4B by performing the following steps:
1) Close BOTH AC-4B CCW Isolation Valves:
  • HCV-481
  • HCV-485
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Corridor 4):

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AOP-11 Page 30 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.h (continued)

3) Locally open both AC-4B RW Interface Valves, HCV-483A/B, by placing the following valves to OPEN (Corridor 4):
  • IA-HCV-483A-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-483B-TV, 3-WAY MANUAL CONTROL VALVE
i. IF VA-46A, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46A, by performing the following steps:

NOTE Manual isolation of RW direct cooling is required when LAS-2898 alarms.

1) Close HCV-2898A/B, CCW Valves.

(continue)

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AOP-11 Page 31 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.i (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 81):
  • HCV-2898C, CONTROL ROOM VA UNIT VA-46A RAW WATER INLET VALVE
  • HCV-2898D, CONTROL ROOM VA UNIT VA-46A RAW WATER OUTLET VALVE
3) Open BOTH HCV-2898C/D, VA-46A RW Valves by placing the following valves to OPEN (Room 81):
  • IA-HCV-2898C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2898D-TV, 3-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 32 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
j. IF VA-46B, Control Room Ventilation Fan, is in service, THEN establish RW flow to VA-46B by performing the following steps:

NOTE Manual isolation of RW direct cooling is required when LAS-2899 alarms.

1) Close HCV-2899A/B, VA-46B CCW Valves.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 81):
  • HCV-2899C, CONTROL ROOM VA UNIT VA-46B RAW WATER INLET VALVE
  • HCV-2899D, CONTROL ROOM VA UNIT VA-46B RAW WATER OUTLET VALVE (continue)

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AOP-11 Page 33 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.j (continued)

3) Open BOTH HCV-2899C/D, VA-46B RW Valves by placing the following valves to OPEN (Room 81):
  • IA-HCV-2899C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2899D-TV, 3-WAY MANUAL CONTROL VALVE
k. IF SI-3A, CS Pump, is in service, THEN establish RW flow to SI-3A by performing the following steps:
1) Close HCV-2813A/B, Spray Pump SI-3A Bearing Cooler CCW Valves.

(continue)

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AOP-11 Page 34 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.k (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
  • HCV-2813C, CNTMT SPRAY PUMP SI-3A BRG CLR RAW WATER INLET VALVE
  • HCV-2813D, CNTMT SPRAY PUMP SI-3A BRG CLR RAW WATER OUTLET VALVE
3) Locally open HCV-2813C/D, Spray Pump SI-3A Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
  • IA-HCV-2813C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2813D-TV, 3-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 35 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
l. IF SI-1A, LPSI Pump, is in service, THEN establish RW flow to SI-1A by performing the following steps:
1) Close HCV-2808A/B, LPSI Pump SI-1A Bearing Cooler CCW Valves.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
  • HCV-2808C, LPSI PUMP SI-1A BRG CLR RAW WATER INLET VALVE
  • HCV-2808D, LPSI PUMP SI-1A BRG CLR RAW WATER OUTLET VALVE (continue)

R14

AOP-11 Page 36 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.l (continued)

3) Open HCV-2808C/D, SI-1A Bearing Cooler CCW Valves by placing the following valves to OPEN (Room 21):
  • IA-HCV-2808C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2808D-TV, 3-WAY MANUAL CONTROL VALVE
m. IF SI-2A, HPSI Pump, is in service, THEN establish RW flow to SI-2A by performing the following steps:
1) Close HCV-2810A/B, HPSI Pump SI-2A Bearing Cooler CCW Valves.

(continue)

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AOP-11 Page 37 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.m (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
  • HCV-2810C, HPSI PUMP SI-2A BRG CLR RAW WATER INLET VALVE
  • HCV-2810D, HPSI PUMP SI-2A BRG CLR RAW WATER OUTLET VALVE
3) Open HCV-2810C/D, SI-2A Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
  • IA-HCV-2810C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2810D-TV, 3-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 38 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
n. IF SI-2C, HPSI Pump, is in service, THEN establish RW flow to SI-2C by performing the following steps:
1) Close HCV-2812A/B, HPSI Pump SI-2C Bearing Cooler CCW Valves.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 21):
  • HCV-2812C, HPSI PUMP SI-2C BRG CLR RAW WATER INLET VALVE
  • HCV-2812D, HPSI PUMP SI-2C BRG CLR RAW WATER OUTLET VALVE (continue)

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AOP-11 Page 39 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.n (continued)

3) Open HCV-2812C/D, SI-2C Bearing Cooler RW Valves by placing the following valves to OPEN (Room 21):
  • IA-HCV-2812C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2812D-TV, 3-WAY MANUAL CONTROL VALVE
o. IF SI-3B, Containment Spray Pump, is in service, THEN establish RW flow to SI-3B by performing the following steps:
1) Close HCV-2814A/B, Spray Pump SI-3B Bearing Cooler CCW Valves.

(continue)

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AOP-11 Page 40 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.o (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
  • HCV-2814C, CNTMT SPRAY PUMP SI-3B BRG CLR RAW WATER INLET VALVE
  • HCV-2814D, CNTMT SPRAY PUMP SI-3B BRG CLR RAW WATER OUTLET VALVE
3) Open HCV-2814C/D, SI-3B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
  • IA-HCV-2814C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2814D-TV, 3-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 41 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
p. IF SI-3C, Containment Spray Pump, is in service, THEN establish RW flow to SI-3C by performing the following steps:
1) Close HCV-2815A/B, Spray Pump SI-3C Bearing Cooler CCW Valves.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
  • HCV-2815C, CNTMT SPRAY PUMP SI-3C BRG CLR RAW WATER INLET VALVE
  • HCV-2815D, CNTMT SPRAY PUMP SI-3C BRG CLR RAW WATER OUTLET VALVE (continue)

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AOP-11 Page 42 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.p (continued)

3) Open HCV-2815C/D, SI-3C Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
  • IA-HCV-2815C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2815D-TV, 3-WAY MANUAL CONTROL VALVE
q. IF SI-1B, LPSI Pump, is in service, THEN establish RW flow to SI-1B by performing the following steps:
1) Close HCV-2809A/B, LPSI Pump SI-1B Bearing Cooler CCW Valves.

(continue)

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AOP-11 Page 43 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.q (continued)

2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
  • HCV-2809C, LPSI PUMP SI-1B BRG CLR RAW WATER INLET VALVE
  • HCV-2809D, LPSI PUMP SI-1B BRG CLR RAW WATER OUTLET VALVE
3) Open HCV-2809C/D, SI-1B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
  • IA-HCV-2809C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2809D-TV, 3-WAY MANUAL CONTROL VALVE (continue)

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AOP-11 Page 44 of 49 INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)
r. IF SI-2B, HPSI Pump, is in service, THEN establish RW flow to SI-2B by performing the following steps:
1) Close HCV-2811A/B, HPSI Pump SI-2B Bearing Cooler CCW Valves.
2) Unlock and release the hand-jacks from BOTH of the following RW Interface Valves (Room 22):
  • HCV-2811C, HPSI PUMP SI-2B BRG CLR RAW WATER INLET VALVE
  • HCV-2811D, HPSI PUMP SI-2B BRG CLR RAW WATER OUTLET VALVE (continue)

R14

AOP-11 Page 45 of 49 INSTRUCTIONS CONTINGENCY ACTIONS 12.r (continued)

3) Open HCV-2811C/D, SI-2B Bearing Cooler RW Valves by placing the following valves to OPEN (Room 22):
  • IA-HCV-2811C-TV, 3-WAY MANUAL CONTROL VALVE
  • IA-HCV-2811D-TV, 3-WAY MANUAL CONTROL VALVE
s. IF SIAS relays are tripped, THEN override the open signals on RW/CCW Heat Exchanger Isolation Valves by placing BOTH of the following switches in OVERRIDE:
  • HC-4350, AC-1A AND AC-1C RW VALVES SIAS OVERRIDE
  • HC-4351, AC-1B AND AC-1D RW VALVES SIAS OVERRIDE R14

WP12 Fort Calhoun Station Unit No. 1 OI-AOV-1 OPERATING INSTRUCTION Title: AIR OPERATED VALVE MANUAL OPERATION FC-68 Number: EC 43771 Reason for Change: Provided guidance for handjacking HCV-341.

Requestor: K. Kingston Preparer: L. Hautzinger ISSUED: 07-31-08 3:00 pm R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 1 OF 69 AIR OPERATED VALVE MANUAL OPERATION SAFETY RELATED ATT PURPOSE PAGE 1 - Operation of Raw Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2 - Operation of Component Cooling Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . 13 3 - Operation of Safety Injection Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 4 - Operation of Chemical Volume Control System Air Operated Valves . . . . . . . . . . . . . . . . . . . 50 5 - Operation of Turbine Plant Cooling Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . 51 6 - Operation of Containment Instrument Air Supply Outboard Pressure Control Valve . . . . . . . . 54 7 - Operation of Main Steam Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 8 - Operation of Feed Water Heater Level Control Air Operated Valves . . . . . . . . . . . . . . . . . . . 58 9 - Operation of Feed Water Air Operated Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 PRECAUTIONS

1. This procedure contains attachments to manually operate AOVs (Air Operated Valves) throughout the plant. Consideration should always be given to current plant conditions prior to operation of any of these valves manually.
2. This procedure should only be used with proper planning and pre-operation briefings.

Contact the AOV Engineer with concerns prior to its use.

3. This procedure is for guidance only and should not be used to mitigate plant transients unless authorized by the Shift Manger.
4. Inoperability of a Raw Water Header, Raw Water Pump(s) and/or a Raw Water Heat Exchanger requires entry into Technical Specification LCO(s). The LCO entry is dependent on river temperature.

R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 2 OF 69 REFERENCES/COMMITMENTS

1. Technical Specifications:

! 2.3: Emergency Core Cooling System

! 2.4: Containment Cooling

2. Drawings File Description 11405-M-100 10454 Raw Water System 11405-M-40 44354 Component Cooling System 11405-M-259 10465 Potable Water System
3. Others:

! EA-FC-95-012, Effect of Post-DBA CCW Temperature Transient on Components

! OPPD Calculation FC07259, Rev. 0; FCS RW/CCW Gothic Model

! OPPD Calculation FC07238, Rev. 0; FCS RW/CCW Gothic Analyses - Additional Configurations APPENDICES None R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 3 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PREREQUISITES (%) INITIALS 1 Procedure Revision Verification:

Revision No. Date:

PROCEDURE NOTES

1. To minimize RW Pump operation in the run-out condition, the four CCW Heat Exchanger Discharge Isolation Valves are set in a throttled position via the measured exposed valve stem. This throttling is intended to assist the restricting orifaces in limiting flow to approximately 3000-3500 gpm flow through one Hx with one pump running. The measured exposed valve stem is recorded in OI-RW-1-CL-A.
2. At the Shift Manager's discretion this throttled position may be adjusted to meet system and/or plant requirements. If so the new measured exposed valve stem shall be documented in the Control Room Log, OI-RW-1-CL-A, and on a new caution tag hung on the valves(s) adjusted.

If the throttle position is adjusted, the System Engineer should be notified in a timely manner to evaluate system flow conditions (i.e., the need for performance of SE-EQT-RW-0001). The Caution Tag may be removed after OI-RW-1-CL-A has been updated.

3. The four CCW Hx Discharge Isolation Valves are equipped with a handjack to limit the open position of the valve disc. These valves are handjacked closed when the HX is removed from service for maintenance/cleaning.

R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 4 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS CAUTIONS

1. Limit the time one RW Pump operates in the run out condition (Flows greater than 7500 gpm) to reduce the potential of pump degradation.
2. Adjustment of the throttle position may cause limit switch contact mismatch for remote valve position indication.
1. If handjacking HCV-2880B, HCV-2881B, HCV-2882B, OR HCV-2883B Closed, complete the following steps:
a. Ensure the Raw Water Discharge Valve is Closed:

! HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve

! HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve

! HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve

! HCV-2883B, Comp CoolingValve

b. Loosen the Handjacks stem nut and run it up to contact the bottom face of the handwheel:

! HCV-2880B

! HCV-2881B

! HCV-2882B

! HCV-2883B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 5 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS CAUTION Do not force the handwheel if excessive resistance is met before the Handjacks stem nut contacts the bonnet of the actuator housing. It is possible that the valve disc is being forced into or beyond the valve seat.

This condition can cause the valve to be stuck in the closed position.

1 c. Turn the handwheel clockwise until the handjacks stem nut contacts the bonnet of the actuator housing:

! HCV-2880B

! HCV-2881B

! HCV-2882B

! HCV-2883B

d. If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer.
2. If removing the valve handjacks from a RW Discharge Valve, perform the following:
a. Turn handwheel counter-clockwise until the measured valve stem matches the stem position recorded in OI-RW-1-CL-A:

! HCV-2880B, Comp Cooling Ht Exch AC-1A Raw Water Outlet Valve

! HCV-2881B, Comp Cooling Ht Exch AC-1B Raw Water Outlet Valve

! HCV-2882B, Comp Cooling Ht Exch AC-1C Raw Water Outlet Valve

! HCV-2883B, Comp Cooling Ht Exch AC-1D Raw Water Outlet Valve

b. Run the Handjacks stem nut down until it contacts the bonnet of the actuator housing:

! HCV-2880B

! HCV-2881B

! HCV-2882B

! HCV-2883B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 6 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 2 c. Verify the exposed threaded shaft measurement and adjust as necessary:

! HCV-2880B

! HCV-2881B

! HCV-2882B

! HCV-2883B

d. Stroke the valve(s) as necessary to verify proper operation and position indication:

! HCV-2880B

! HCV-2881B

! HCV-2882B

! HCV-2883B NOTES

1. The Declutching pin will automatically move out of the outer slot when the hand wheel is pushed in.
2. When the worm gear is fully engaging the gear segment, the pin will drop into the inner slot.
3. If handjacking HCV-2880A, HCV-2881A, HCV-2882A, or HCV-2883A is desired, complete the following for the applicable valves:
a. Engage the handwheel by pushing in and turning clockwise:

! HCV-2880A

! HCV-2881A

! HCV-2882A

! HCV-2883A

b. Place the valve in the desired position:

! HCV-2880A

! HCV-2881A

! HCV-2882A

! HCV-2883A R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 7 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

4. If removing the handjack, complete the following for the applicable valve:
a. Simultaneously press declutching spring to push the pin out, and turn the hand wheel counterclockwise until the worm gear disengages the gear segment:

! HCV-2880A, Comp Cooling Ht Exch AC-1A Raw Water Inlet Valve

! HCV-2881A, Comp Cooling Ht Exch AC-1B Raw Water Inlet Valve

! HCV-2882A, Comp Cooling Ht Exch AC-1C Raw Water Inlet Valve

! HCV-2883A, Comp Cooling Ht Exch AC-1D Raw Water Inlet Valve NOTE The pin engages the outer slot to keep the handwheel in the engaged position.

b. Allow the spring to move the handwheel all of the way out, and release the pin:

! HCV-2880A

! HCV-2881A

! HCV-2882A

! HCV-2883A

c. Stroke the valve(s) as necessary to verify proper operation and position indication:

! HCV-2880A

! HCV-2881A

! HCV-2882A

! HCV-2883A R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 8 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

5. If hand jacking HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, HCV-2893, OR HCV-2894, perform the following:
a. Ensure selected valve is Closed:

! HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2893, Raw Water to CCW Isolation Valve

! HCV-2894, Raw Water to CCW Isolation Valve

b. Loosen the nut on the hand jack stem for selected valves:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 9 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 5 c. Turn the hand wheel CLOCKWISE, counting each turn, until handwheel stop contacts diaphragm for selected valves:

! HCV-2877A, Turns:___________

! HCV-2877B, Turns:___________

! HCV-2878A, Turns:___________

! HCV-2878B, Turns:___________

! HCV-2879A, Turns:___________

! HCV-2879B, Turns:___________

! HCV-2893, Turns:___________

! HCV-2894, Turns:___________

d. Tighten the hand jack locking nut against diaphragm housing for selected valves:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894

e. Record the number of turns on the danger/caution tag end, and in the tag removal notes of the clearance for selected valves:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 10 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

6. If removing the handjack from HCV-2877A/B, HCV-2878A/B, or HCV-2879A/B, perform the following:
a. Ensure air drain on filter regulator for selected valve(s) is closed:

! HCV-2877A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2877B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2878A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2878B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2879A, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2879B, Comp Clg Ht Exchs AC-1A-D Raw Water Inlet Header Isolation Valve

! HCV-2893, Raw Water to CCW Isolation Valve

! HCV-2894, Raw Water to CCW Isolation Valve

b. Ensure Air Supply Isolation Valve(s) for selected Valve is open:

! HCV-2877A

! HCV-2878B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 11 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS NOTE On removing power from the valve, the solenoid will fail the valve open.

6 c. Ensure selected valve has a Closed signal:

! HCV-2877A

! HCV-2878B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894

d. Loosen the Locking nut on selected valve handwheel stem:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894

e. Turn handwheel COUNTER-CLOCKWISE the number of turns recorded in step 5.c for selected valves:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 12 OF 69 C

Continuous Use Attachment 1 - Operation of Raw Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 6 f. Tighten lock nut on valve stem against diaphragm housing for selected valve:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894

g. Stroke valve as needed to ensure proper operation and indication for selected valve:

! HCV-2877A

! HCV-2877B

! HCV-2878A

! HCV-2878B

! HCV-2879A

! HCV-2879B

! HCV-2893

! HCV-2894 Completed by Date/Time /

R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 13 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision No. Date:

PROCEDURE CAUTION Operating a valve hand jack against spring pressure may cause valve damage.

1. If hand jacking HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exchs AC-1A-D CCW Valves, Closed, complete the following:
a. Ensure valve to be hand jacked is Closed:

! HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve

! HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve

! HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve

! HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve

! HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve

! HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve

b. Align and insert J-hook into slot on the manual operator side of the valve

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 14 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 1 c. Loosen hose clamp and remove J-hook from the air operator side of the valve:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B

d. Re-tighten hose clamp around slot to prevent J-hook from entering slot:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B

2. If removing hand jack from HCV-489A, HCV-490A/B, HCV-491B, or HCV-492A/B, Comp Cooling Ht Exch AC-1A CCW Valves, complete the following:
a. Ensure valve has a Closed signal:

! HCV-489A, Comp Cooling Ht Exch AC-1A CCW Inlet Valve

! HCV-490A, Comp Cooling Ht Exch AC-1B CCW Inlet Valve

! HCV-490B, Comp Cooling Ht Exch AC-1B CCW Outlet Valve

! HCV-491B, Comp Cooling Ht Exch AC-1C CCW Outlet Valve

! HCV-492A, Comp Cooling Ht Exch AC-1D CCW Inlet Valve

! HCV-492B, Comp Cooling Ht Exch AC-1D CCW Outlet Valve

b. Ensure that the valve is manually hand jacked in the Closed position:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 15 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 2 c. Loosen hose clamp and insert J-hook into slot on air operator side of the valve:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B

d. Re-tighten the hose clamp around J-hook and the slot:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B

e. Remove J-hook from the slot on the manual operator side of the valve:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B

f. Stroke valve as necessary to verify proper operation and position indication:

! HCV-489A

! HCV-490A

! HCV-490B

! HCV-491B

! HCV-492A

! HCV-492B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 16 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

3. If hand jacking HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:
a. Ensure valve to be hand jacked is Closed:

! HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve

! HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve

b. Align notch in pointer to hole in gear on manual operator and insert pin.

! HCV-489B

! HCV-491A

c. Loosen hose clamp and remove J-hook from the air operator side of the valve.

! HCV-489B

! HCV-491A

d. Re-tighten hose clamp around slot to prevent J-hook from entering slot.

! HCV-489B

! HCV-491A

4. If removing hand jack from HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve, or HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve, Closed, complete the following:
a. Ensure valve has a Closed signal:

! HCV-489B, Comp Cooling Ht Exch AC-1A CCW Outlet Valve

! HCV-491A, Comp Cooling Ht Exch AC-1C CCW Inlet Valve

b. Ensure that the valve is manually hand jacked in the closed position.

! HCV-489B

! HCV-491A R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 17 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 4 c. Loosen hose clamp and insert J-hook into slot on air operator side of the valve.

! HCV-489B

! HCV-491A

d. Re-tighten the hose clamp around J-hook and the slot.

! HCV-489B

! HCV-491A

e. Remove pin from manual operator.

! HCV-489B

! HCV-491A

f. Stroke the valve as necessary to verify proper operation and position indication.

! HCV-489B

! HCV-491A

5. If hand jacking HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
a. Ensure HCV-497 is Open.
b. Loosen stem nut.
c. Turn handwheel clockwise until handwheel stem pusher plate contacts diaphragm plate.
d. Tighten stem nut.
6. If removing hand jack from HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve, complete the following:
a. Ensure HCV-497 has an Open signal.
b. Loosen stem nut.

R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 18 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 6 c. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing.

d. Tighten stem nut.
e. Stroke HCV-497 Comp Clg Ht Exchs AC-1A-D CCW Bypass Line Isolation Valve as necessary to verify proper operation and position indication.
7. If hand jacking HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard Isolation Valves, Open, complete the following:
a. Ensure that the valve to be hand jacked is Open:

! HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve

! HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet Header Outboard Isolation Valve

! HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet Header Outboard Isolation Valve

! HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW Outlet Header Outboard Isolation Valve

b. Turn handwheel counter-clockwise until handwheel contacts stem nut:

! HCV-425B

! HCV-425D

! HCV-467B

! HCV-467D

c. If excessive resistence is met before handwheel contacts stem nut, contact System Engineer.

R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 19 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

8. If removing hand jack from HCV-425B/D, SI Leakage Coolers SI-4A-D Combined CCW Inlet/Outlet Header Outboard Isolation Valves, or HCV-467B/D, Det Well Cooling Coils VA-14A&B Combined CCW Inlet/Outlet Header Outboard Isolation Valves, complete the following:
a. Ensure valve has an Open signal:

! HCV-425B, SI Leakage Coolers SI-4A-D Combined CCW Inlet Header Outboard Isolation Valve

! HCV-425D, SI Leakage Coolers SI-4A-D Combined CCW Outlet Header Outboard Isolation Valve

! HCV-467B, Det Well Cooling Coils VA-14A&B Combined CCW Inlet Header Outboard Isolation Valve

! HCV-467D, Det Well Cooling Coils VA-14A&B Combined CCW Outlet Header Outboard Isolation Valve

b. Turn handwheel clockwise until handwheel contacts upper diaphragm casing:

! HCV-425B

! HCV-425D

! HCV-467B

! HCV-467D

c. Stroke valve as necessary to verify proper operation and position indication:

! HCV-425B

! HCV-425D

! HCV-467B

! HCV-467D R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 20 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

9. If hand jacking HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, Closed, complete the following:
a. Ensure valve that is to be hand jacked is Closed:

! HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve

! HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet Outboard Isolation Valve

b. Loosen stem nut:

! HCV-438B

! HCV-438D

c. Turn handwheel CLOCKWISE until handwheel stem pusher plate contacts diaphragm plate:

! HCV-438B

! HCV-438D

d. Tighten stem nut:

! HCV-438B

! HCV-438D

10. If removing hand jack from HCV-438B/D, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply/Return Valves, complete the following:
a. Ensure valve has a Closed signal:

! HCV-438B, Reactor Coolant Pump RC-3A-3D Lube Oil and Seal Coolers Comp Cooling Water Supply Valve

! HCV-438D, RCP RC-3A-D Lube Oil and Seal Clrs CCW Outlet Outboard Isolation Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 21 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 10 b. Loosen stem nut:

! HCV-438B

! HCV-438D

c. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts upper diaphragm casing:

! HCV-438B

! HCV-438D

d. Tighten stem nut:

! HCV-438B

! HCV-438D

e. Stroke valve as necessary to verify proper operation and position indication:

! HCV-438B

! HCV-438D

11. If hand jacking HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &

DW-46B-2 Outlet/Inlet Valves, Open, complete the following:

a. Ensure that the valve to be hand jacked is Open:

! HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &

DW-46B-2 Inlet Valve

! HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &

DW-46B-2 Outlet Valve

b. Push in handwheel and turn CLOCKWISE until worm-gear fully engages the gear segment:

! HCV-2895A

! HCV-2895B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 22 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 11 c. Verify declutching pin has dropped into inner slot on handwheel:

! HCV-2895A

! HCV-2895B

12. IF removing Handjack from HCV-2895A/B, Waste Evap WD-21 & Ht Exchs DW-46A-2 & DW-46B-2 Outlet/Inlet Valves:
a. Ensure valve has an OPEN signal:

! HCV-2895A, Waste Evap WD-21 & Ht Exchs DW-46A-2 &

DW-46B-2 Inlet Valve

! HCV-2895B, Waste Evap WD-21 & Ht Exchs DW-46A-2 &

DW-46B-2 Outlet Valve

b. Press declutching spring to push out declutching pin:

! HCV-2895A

! HCV-2895B

c. Turn Handwheel COUNTER-CLOCKWISE until worm gear disengages the gear segment:

! HCV-2895A

! HCV-2895B

d. Allow spring to move handwheel all the way out and release declutching pin into outer slot on handwheel shaft:

! HCV-2895A

! HCV-2895B

e. Stroke valve as necessary to verify proper operation and position indication:

! HCV-2895A

! HCV-2895B R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 23 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

13. If locally Closing of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following on the applicable valves:
a. Place the control valve to Close for:

! IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve

! IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual Control Valve

! IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control Valve

! IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual Control Valve

! IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control Valve

! IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual Control Valve

! IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control Valve

! IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual Control Valve

b. Verify valve strokes fully Closed for:

! HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet Valve

! HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet Valve

! HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet Valve

! HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet Valve

! HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet Valve

! HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet Valve

! HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet Valve

! HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 24 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 13 c. Use rachet to replace Handjack by turning COUNTER-CLOCKWISE until it reaches the top:

! HCV-400E

! HCV-400F

! HCV-401E

! HCV-401F

! HCV-402E

! HCV-402F

! HCV-403E

! HCV-403F

d. Reinstall cover and locking device:

! HCV-400E

! HCV-400F

! HCV-401E

! HCV-401F

! HCV-402E

! HCV-402F

! HCV-403E

! HCV-403F

e. Verify locking device is installed:

! HCV-400E

! HCV-400F

! HCV-401E

! HCV-401F

! HCV-402E

! HCV-402F

! HCV-403E

! HCV-403F Ind Verif R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 25 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 13 f. Remove selected valve from the Locked Component Deviation Log:

! HCV-400E

! HCV-400F

! HCV-401E

! HCV-401F

! HCV-402E

! HCV-402F

! HCV-403E

! HCV-403F CAUTION The following steps may drain CCW from this portion of the system.

14. If locally Opening of HCV-400E/F, HCV-401E/F, HCV-402E/F, HCV-403E/F is desired, perform the following for the applicable valves:
a. Ensure CCW isolation valves for selected unit(s) are closed:

! HCV-400B, Cntmt Clg Coil VA-1A AC Inlet Valve Valve

! HCV-400D, Cntmt Clg Coil VA-1A AC Outlet Valve

! HCV-401B, Cntmt Clg Coil VA-1B AC Inlet Valve Valve

! HCV-401D, Cntmt Clg Coil VA-1B AC Outlet Valve

! HCV-402B, Cntmt Clg Coil VA-8A AC Inlet Valve Valve

! HCV-402D, Cntmt Clg Coil VA-8A AC Outlet Valve

! HCV-403B, Cntmt Clg Coil VA-8BAC Inlet Valve Valve

! HCV-403D, Cntmt Clg Coil VA-8B AC Outlet Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 26 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 14 b. Remove the locking mechanism and cover from the valve and place valve information in the Locked Component Deviation Log for the selected valve:

! HCV-400E, Cntmt VA-1A Cooling Coil Back-up Raw Water Inlet Valve

! HCV-400F, Cntmt VA-1A Cooling Coil Back-up Raw Water Outlet Valve

! HCV-401E, Cntmt VA-1B Cooling Coil Back-up Raw Water Inlet Valve

! HCV-401F, Cntmt VA-1B Cooling Coil Back-up Raw Water Outlet Valve

! HCV-402E, Cntmt VA-1C Cooling Coil Back-up Raw Water Inlet Valve

! HCV-402F, Cntmt VA-1C Cooling Coil Back-up Raw Water Outlet Valve

! HCV-403E, Cntmt VA-1D Cooling Coil Back-up Raw Water Inlet Valve

! HCV-403F, Cntmt VA-1D Cooling Coil Back-up Raw Water Outlet Valve

c. Use the ratchet to release handjack by turning the locking nut CLOCKWISE until it reaches the bottom:

! HCV-400E

! HCV-400F

! HCV-401E

! HCV-401F

! HCV-402E

! HCV-402F

! HCV-403E

! HCV-403F R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 27 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 14 d. Place the Control Valve to Open:

! IA-HCV-400E-TV, Raw Water Inlet Valve HCV-400E Manual Control Valve

! IA-HCV-400F-TV, Raw Water Outlet Valve HCV-400F Manual Control Valve

! IA-HCV-401E-TV, Raw Water Inlet Valve HCV-401E Manual Control Valve

! IA-HCV-401F-TV, Raw Water Outlet Valve HCV-401F Manual Control Valve

! IA-HCV-402E-TV, Raw Water Inlet Valve HCV-402E Manual Control Valve

! IA-HCV-402F-TV, Raw Water Outlet Valve HCV-402F Manual Control Valve

! IA-HCV-403E-TV, Raw Water Inlet Valve HCV-403E Manual Control Valve

! IA-HCV-403F-TV, Raw Water Outlet Valve HCV-403F Manual Control Valve

e. Verify the valve strokes Open:

! HCV-400E

! HCV-400F

! HCV-401E

! HCV-401F

! HCV-402E

! HCV-402F

! HCV-403E

! HCV-403F R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 28 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS

15. If handjacking HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valves, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, perform the following:
a. Ensure isolation valves are closed for selected valve by taking the air control valve to Close:

! IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve

! IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve

! IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve

! IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way Manual Control Valve

b. Loosen required stem nut on selected valves:

! HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve

! HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet Valve

! HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve

! HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet Valve

c. Unlock and turn hand wheel CLOCKWISE until the handwheel stem pusher plate contacts the diaphragm on selected valves:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D

d. Tighten stem nut on handjacked valve:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 29 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 15 e. Place locking Device on hand wheel for selected valve:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D

f. Independently verify valve is Locked Closed:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D Ind Verif

g. Remove selected valve from the Locked Component Deviation Log:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D

16. If handjacking HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:

NOTE HCV-2898A/B and HCV-2899A/B can only be hand jacked in the open position.

a. Ensure the valve to be handjacked is open:

! HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve

! HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve

! HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve

! HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 30 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 16 b. Loosen stem nut for selected valves:

! HCV-2898A

! HCV-2898B

! HCV-2899A

! HCV-2899B

c. Turn hand wheel COUNTER-CLOCKWISE until the handwheel is fully backseated for selected valves:

! HCV-2898A

! HCV-2898B

! HCV-2899A

! HCV-2899B

d. Tighten stem nut for selected valves:

! HCV-2898A

! HCV-2898B

! HCV-2899A

! HCV-2899B

17. If removing handjack from HCV-2898A/B, Control Room VA Unit VA-46A Inlet/Outlet Valves, or HCV-2899A/B, Control Room VA Unit VA-46B Inlet/Outlet Valves, complete the following:

NOTE Can verify the handjack removed for HCV-2898A/B and HCV-2899A/B by verifying the hand wheel in the full CLOCKWISE position.

a. Ensure the selected valve has an open signal:

! HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve

! HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve

! HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve

! HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 31 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 17 b. Loosen stem nut on selected valves:

! HCV-2898A

! HCV-2898B

! HCV-2899A

! HCV-2899B

c. Turn hand wheel CLOCKWISE until the handwheel contacts the top of the diaphram casing for selected valves:

! HCV-2898A

! HCV-2898B

! HCV-2899A

! HCV-2899B

d. Tighten stem nut on selected valves:

! HCV-2898A

! HCV-2898B

! HCV-2899A

! HCV-2899B CAUTION The following steps may drain CCW from this portion of the system.

18. If removing Handjack from HCV-2898C/D, Control Room VA Unit VA-46A Raw Water Inlet/Outlet Valve, or HCV-2899C/D, Control Room VA Unit VA-46B Raw Water Inlet/Outlet Valves, complete the following:
a. Ensure CCW isolation valves for the selected unit are Closed:

! HCV-2898A, Control Room VA Unit VA-46A CCW Inlet Valve

! HCV-2898B, Control Room VA Unit VA-46A CCW Outlet Valve

! HCV-2899A, Control Room VA Unit VA-46B CCW Inlet Valve

! HCV-2899B, Control Room VA Unit VA-46B CCW Outlet Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 32 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 18 b. Ensure the hand jacked valves have a Closed signal:

! IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve

! IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve

! IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve

! IA-HCV-2899D-TV, Raw Water Outlet Valve HCV-2899D 3-Way Manual Control Valve

c. Loosen Stem nut on selected Hand jacked valves:

! HCV-2898C, Control Room VA Unit VA-46A Raw Water Inlet Valve

! HCV-2898D, Control Room VA Unit VA-46A Raw Water Outlet Valve

! HCV-2899C, Control Room VA Unit VA-46B Raw Water Inlet Valve

! HCV-2899D, Control Room VA Unit VA-46B Raw Water Outlet Valve

d. Unlock handwheel and place valve information in the Locked Component Deviation Log for the selected valve:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D

e. Turn handwheel COUNTER-CLOCKWISE until handwheel stem pusher plate contacts the upper diaphragm casing for selected valves:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 33 OF 69 C

Continuous Use Attachment 2 - Operation of Component Cooling Water Air Operated Valves PROCEDURE (continued) (T) INITIALS 18 f. Tighten stem nut on selected valves:

! HCV-2898C

! HCV-2898D

! HCV-2899C

! HCV-2899D

g. Open selected valve by turning air valve to the Open position:

! IA-HCV-2898C-TV, Raw Water Inlet Valve HCV-2898C 3-Way Manual Control Valve

! IA-HCV-2898D-TV, Raw Water Outlet Valve HCV-2898D 3-Way Manual Control Valve

! IA-HCV-2899C-TV, Raw Water Inlet Valve HCV-2899C 3-Way Manual Control Valve

! IA-HCV-2899D-TV, Raw Water Inlet Valve HCV-2899D 3-Way Manual Control Valve Completed by Date/Time /

R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 34 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision No. Date:

PROCEDURE

1. If Handjacking LCV-383-1, or LCV-383-2, perform the following:
a. Ensure valve to be Handjacked is Closed:

! LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve

! LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve

b. Loosen stem nut on valve to be handjacked:

! LCV-383-1

! LCV-383-2

c. Turn Handwheel CLOCKWISE, counting the number of turns, until the handwheel stem pusher plate contacts the diaphragm plate on the valve to be Handjacked:

! LCV-383-1

! LCV-383-2

d. Record number of turns for Handjacked valve:

! LCV-383-1, Turns__________

! LCV-383-2, Turns__________

e. Tighten stem nut on hand jacked valve:

! LCV-383-1

! LCV-383-2 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 35 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

2. If removing handjack from LCV-383-1, or LCV-383-2, perform the following:
a. Ensure that the Handjacked valve has a Closed signal:

! LCV-383-1, SIRWT SI-5 Outlet Header Level Control Valve

! LCV-383-2, SIRWT SI-5 Outlet Header Level Control Valve

b. Loosen stem nut on Handjacked valve:

! LCV-383-1

! LCV-383-2

c. Turn Handwheel on Handjacked valve COUNTER-CLOCKWISE the number of turns recorded in step 1.d:

! LCV-383-1

! LCV-383-2

d. Tighten the stem nut for handjacked valve:

! LCV-383-1

! LCV-383-2

e. Stroke valve as necessary to verify proper operation and position indication.

! LCV-383-1

! LCV-383-2

3. If handjacking HCV-753, HCV-754, HCV-749, or HCV-750, perform the following:
a. Enure the valve to be handjacked is Closed:

! HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve

! HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve

! HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve

! HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 36 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS 3 b. Align the holes on the manual operator end of stem on valve to be handjacked.

! HCV-753

! HCV-754

! HCV-749

! HCV-750

c. Insert Pin into hole on valve to be handjacked:

! HCV-753

! HCV-754

! HCV-749

! HCV-750

d. Remove Pin from the air actuator assembly end on valve to be handjacked:

! HCV-753

! HCV-754

! HCV-749

! HCV-750

4. If removing the handjack from HCV-753, HCV-754, HCV-749, HCV-750, perform the following:
a. Ensure that the Handjacked valve has a Closed signal:

! HCV-753, Cntmt Purge Supply Fan VA-24A Discharge Valve

! HCV-754, Cntmt Purge Supply Fan VA-24B Discharge Valve

! HCV-749, Cntmt Purge Disch Unit VA-33A Inlet Valve

! HCV-750, Cntmt Purge Disch Unit VA-33B Inlet Valve

b. Insert the Pin on the Air actuator assembly end for handjacked valve

! HCV-753

! HCV-754

! HCV-749

! HCV-750 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 37 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS 4 c. Remove the Pin from the manual operator end of stem for handjacked valve:

! HCV-753

! HCV-754

! HCV-749

! HCV-750

d. Stroke valve as necessary to verify proper operation and position indication for handjacked valve

! HCV-753

! HCV-754

! HCV-749

! HCV-750

5. If handjacking HCV-341, HCV-344 or HCV-345, perform the following:
a. Ensure that the valve to be handjacked is Closed:

! HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve

! HCV-344, Containment Spray Header Isolation Valve

! HCV-345, Containment Spray Header Isolation Valve

b. Using handwheel, align hole in manual operator for valve to be handjacked:

! HCV-341

! HCV-344

! HCV-345

c. Insert pin into hole in manual operator for valve to be handjacked:

! HCV-341

! HCV-344

! HCV-345 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 38 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

6. If removing handjack from HCV-341, HCV-344, or HCV-345, perform the following:
a. Ensure valve that is Handjacked has a Closed signal:

! HCV-341, Shutdown Clg Ht Exchs AC-4A & B Outlet Temperature Control Valve

! HCV-344, Containment Spray Header Isolation Valve

! HCV-345, Containment Spray Header Isolation Valve

b. Remove Pin from Manual operator for handjacked valve:

! HCV-341

! HCV-344

! HCV-345

c. Ensure handwheel in its neutral position for valve that was handjacked:

! HCV-341

! HCV-344

! HCV-345

d. Stroke valve as necessary to verify proper operation and position indication for handjacked valve:

! HCV-341

! HCV-344

! HCV-345 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 39 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

7. If handjacking HCV-482 A/B, OR HCV-483 A/B Shutdown Cooling Heat Exchanger Back Up Raw Water Valves, perform the following:
a. Enure the valve to be hand jacked is Closed:

! HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve

! HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Outlet Valve

! HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Inlet Valve

! HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Outlet Valve

b. Ensure Instrument Air supply Insolation Valve is Open for selected valve:

! IA-HCV-482A-B, HCV-482A Instrument Air Supply Isolation Valve

! IA-HCV-482B-B, HCV-482B Instrument Air Supply Isolation Valve

! IA-HCV-483A-B, HCV-483A Instrument Air Supply Isolation Valve

! IA-HCV-483B-B, HCV-483B Instrument Air Supply Isolation Valve

c. Place Raw Water Manual control valve in the Closed position for the selected valve:

! IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve

! IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual Control Valve

! IA-HCV-483A-TV, Raw Water Inlet Valve HCV-843A Manual Control Valve

! IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual Control Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 40 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

7. d. Loosen the Hand Jack Stem Nut, and back it up to the bottom of the hand wheel for the selected valve:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B CAUTION Do Not Force the hand wheel if excessive resistance is met before the handjack stem nut contacts the bonnet of the actuator housing. It is possible that the valve disk is being forced into the valve seat.

e. Turn the hand wheel CLOCKWISE until the handjack stem nut contacts the bonnet of the actuator housing for the selected valve:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B

f. If excessive resistance is met before the stem nut contacts the bonnet of the actuator housing, contact the System Engineer for the selected valve:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B

g. Lock hand wheel for the selected valve:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B Ind Verif R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 41 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

7. h. Remove selected valve from the Locked Component Deviation Log:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B CAUTION The following steps may drain CCW from this portion of the system.

8. If removing the handjack from HCV-482A, HCV-482B, HCV-483A, HCV-483B, perform the following:
a. Ensure CCW isolation valves for selected heat exchanger(s) are closed:

! HCV-480, Shtdn Ht Exch AC-4A AC Inlet Valve

! HCV-484, Shtdn Ht Exch AC-4A AC Outlet Valve

! HCV-481, Shtdn Ht Exch AC-4B AC Inlet Valve

! HCV-485, Shtdn Ht Exch AC-4B AC Outlet Valve

b. Ensure that the Handjacked valve has a Closed signal:

! HCV-482A, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Inlet Valve

! HCV-482B, Shutdown Cooling Ht Exch AC-4A Back-Up Raw Water Outlet Valve

! HCV-483A, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Inlet Valve

! HCV-483B, Shutdown Cooling Ht Exch AC-4B Back-Up Raw Water Outlet Valve

c. Ensure Instrument Air Isolation valve is Open for selected valve:

! IA-HCV-482A-B, Instrument Air Supply Isolation Valve

! IA-HCV-482B-B, Instrument Air Supply Isolation Valve

! IA-HCV-483A-B, Instrument Air Supply Isolation Valve

! IA-HCV-483B-B, Instrument Air Supply Isolation Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 42 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

8. d. Unlock and turn Hand wheel COUNTER-CLOCKWISE until valve stem travel stops for selected valve:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B

e. Contact the Control Room and have selected valve entered into the Locked Component Deviation Log:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B

f. Run the hand jack stem nut down until it contacts the Bonnet of the actuator housing for the selected valve:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B

g. Place the raw water manual control valve for the selected valve in the OPEN position for the selected valve:

! IA-HCV-482A-TV, Raw Water Inlet Valve HCV-482A Manual Control Valve

! IA-HCV-482B-TV, Raw Water Outlet Valve HCV-482B Manual Control Valve

! IA-HCV-483A-TV, Raw Water Inlet Valve HCV-483A Manual Control Valve

! IA-HCV-483B-TV, Raw Water Outlet Valve HCV-483B Manual Control Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 43 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

8. h. Ensure selected valve is in the Open position:

! HCV-482A

! HCV-482B

! HCV-483A

! HCV-483B

9. If handjacking HCV-2908, HCV-2918, or HCV-2928 HPSI Pump Discharge Valves, perform the following:
a. Ensure the valve to be Handjacked is Closed:

! HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve

! HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve

! HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve

b. Remove the Handjack Locking pin from the Valve stem for the selected valve:

! HCV-2928

! HCV-2908

! HCV-2918

c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:

! HCV-2928

! HCV-2908

! HCV-2918

d. Attach the Hand wheel locking pin to the hand wheel for the selected valve:

! HCV-2928

! HCV-2908

! HCV-2918 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 44 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

10. If removing the handjack from HCV-2908, HCV-2918, or HCV-2928, perform the following:
a. Ensure that the Handjacked valve has a Closed signal:

! HCV-2928, HPSI Pump SI-2A Discharge Isolation Valve

! HCV-2908, HPSI Pump SI-2B Discharge Isolation Valve

! HCV-2918, HPSI Pump SI-2C Discharge Isolation Valve

b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:

! HCV-2928

! HCV-2908

! HCV-2918

c. Insert the Handjack locking pin in the valve stem for the selected valve:

! HCV-2928

! HCV-2908

! HCV-2918

d. Contact the Control Room that the hand jack has been removed for the selected valve:

! HCV-2928

! HCV-2908

! HCV-2918 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 45 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

11. If handjacking HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves:
a. Ensure valve to be Handjacked is Closed:

! HCV-2907, HPSI Pump SI-2B Suction Isolation Valve

! HCV-2917, HPSI Pump SI-2C Suction Isolation Valve

! HCV-2927, HPSI Pump SI-2A Suction Isolation Valve

! HCV-2938, LPSI Pump SI-1B Discharge Valve

! HCV-2948, LPSI Pump SI-1A Discharge Valve

! HCV-2957, Containment Spray Pump SI-3A Suction Valve

! HCV-2958, Containment Spray Pump SI-3A Discharge Valve

! HCV-2967, Containment Spray Pump SI-3B Suction Valve

! HCV-2968, Containment Spray Pump SI-3B Discharge Valve

! HCV-2977, Containment Spray Pump SI-3C Suction Valve

! HCV-2978, Containment Spray Pump SI-3C Discharge Valve

b. Remove the Handjack Locking pin from the Valve stem for the selected valve:

! HCV-2907

! HCV-2917

! HCV-2927

! HCV-2938

! HCV-2948

! HCV-2957

! HCV-2958

! HCV-2967

! HCV-2968

! HCV-2977

! HCV-2978 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 46 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

11. c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:

! HCV-2907

! HCV-2917

! HCV-2927

! HCV-2938

! HCV-2948

! HCV-2957

! HCV-2958

! HCV-2967

! HCV-2968

! HCV-2977

! HCV-2978

d. Attach the Hand wheel locking pin to the hand wheel for the selected valve:

! HCV-2907

! HCV-2917

! HCV-2927

! HCV-2938

! HCV-2948

! HCV-2957

! HCV-2958

! HCV-2967

! HCV-2968

! HCV-2977

! HCV-2978 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 47 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

12. If Removing the Handjack from HCV-2907, HCV-2917, HCV-2927, HCV-2938, HCV-2948, HCV-2957, HCV-2958, HCV-2967, HCV-2968, HCV-2977, HCV-2978, complete the following for the selected valves.
a. Ensure the valve to be Handjacked has a Closed signal.

! HCV-2907, HPSI Pump SI-2B Suction Isolation Valve

! HCV-2917, HPSI Pump SI-2C Suction Isolation Valve

! HCV-2927, HPSI Pump SI-2A Suction Isolation Valve

! HCV-2938, LPSI Pump SI-1B Discharge Valve

! HCV-2948, LPSI Pump SI-1A Discharge Valve

! HCV-2957, Containment Spray Pump SI-3A Suction Valve

! HCV-2958, Containment Spray Pump SI-3A Discharge Valve

! HCV-2967, Containment Spray Pump SI-3B Suction Valve

! HCV-2968, Containment Spray Pump SI-3B Discharge Valve

! HCV-2977, Containment Spray Pump SI-3C Suction Valve

! HCV-2978, Containment Spray Pump SI-3C Discharge Valve

b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:

! HCV-2907

! HCV-2917

! HCV-2927

! HCV-2938

! HCV-2948

! HCV-2957

! HCV-2958

! HCV-2967

! HCV-2968

! HCV-2977

! HCV-2978 R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 48 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

12. c. Insert the Handjack locking pin in the valve stem for the selected valve:

! HCV-2907

! HCV-2917

! HCV-2927

! HCV-2938

! HCV-2948

! HCV-2957

! HCV-2958

! HCV-2967

! HCV-2968

! HCV-2977

! HCV-2978

d. Contact the Control Room that the hand jack has been removed for the selected valve:

! HCV-2907

! HCV-2917

! HCV-2927

! HCV-2938

! HCV-2948

! HCV-2957

! HCV-2958

! HCV-2967

! HCV-2968

! HCV-2977

! HCV-2978

13. If Handjacking HCV-2937, or HCV-2947, complete the following for the selected valve:
a. Ensure the selected valve is Closed:

! HCV-2937, LPSI Pump SI-1B Suction Valve

! HCV-2947, LPSI Pump SI-1A Suction Valve R12

FORT CALHOUN STATION OI-AOV-1 OPERATING INSTRUCTION PAGE 49 OF 69 C

Continuous Use Attachment 3 - Operation of Safety Injection Air Operated Valves PROCEDURE (continued) (T) INITIALS

13. b. Remove the Handjack Locking pin from the Valve stem for the selected valve:

! HCV-2937

! HCV-2947

c. Turn the valve hand wheel CLOCKWISE until the shaft sleeve contacts the valve yoke on the selected valve:

! HCV-2937

! HCV-2947

14. If REMOVING Handjack from HCV-2937, or HCV-2947, perform the following:
a. Ensure the selected valve has a CLOSED signal:

! HCV-2937, LPSI Pump SI-1B Suction Valve

! HCV-2947, LPSI Pump SI-1A Suction Valve

b. Turn the handwheel COUNTER-CLOCKWISE until the shaft sleeve contacts the valve yoke for the selected valve:

! HCV-2937

! HCV-2947

c. Insert the handjack locking pin in the valve stem for the selected valve:

! HCV-2937

! HCV-2947

d. Contact the Control Room that the hand jack has been removed for the selected valve.

Completed by Date/Time /

R12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM Title: Energize 480 volt buses from 13.8 KV Location: Switchgear Rooms Approximate Time: 20 minutes Actual Time: _________________

Reference(s): K/A 000055 EA1.07 EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV" Handout(s): EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/25/09

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: Be careful not to bump equipment in switchgear rooms Comments:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 TASK The candidate energized 480V buses 1B3C and 1B3C-STANDARD: 4C from the 13.8 KV supply in accordance with EOP/AOP Attachment 5, "Energizing 480 V Buses From 13.8 KV."

INITIAL A station blackout has occurred.

CONDITIONS: Both 161 KV and 345 KV supplies to the station have been lost.

Both Diesel Generators have failed to start.

Energy Marketing reports that 13.8 KV power is available to the plant.

INITIATING CUE: You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP Attachment

5. The Control Room Operators have completed steps 1 and 2.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 Critical Steps shown in gray STEP ELEMENT STANDARD 1 Trip ALL of the following 480 V East Switchgear room breakers : Trip breakers.

1B3C, "T1B-3C MAIN Verify breaker position SECONDARY FEED TO indicators display "OPEN."

480 VAC BUS 1B3C."

1B3C-2, "MCC-3C2 AUX BUILDING (CORR.

26)."

1B3C-7, "TURBINE BUILDING CRANE HE-3."

1B3C-6, "CONTAINMENT SPRAY PUMP SI-3A."

1B3C-3, "OUTDOOR LIGHTING XFMR T1C-3B."

1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)."

1B3C-8, "AIR COMPRESSORCA-1A FEED TO LOCAL CONTACTOR." [ SAT ] [ UNSAT ]

2 Trip ALL of the following 480 V breakers: East Switchgear room 1B3C-4C-2, "BREAKER Trip breakers.

UNIT MCC-3C4C-2 Verify breaker position TURBINE BLDG indicators display "OPEN."

(MEZZANINE)."

1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C." [ SAT ] [ UNSAT ]

1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C."

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP ELEMENT STANDARD 3 Trip listed 1B4C 480 V West Switchgear room Breakers.

CUE: After candidate identifies location of bus 1B4C, "Another Operator will trip the breakers."

[ SAT ] [ UNSAT ]

4 Place ALL of the following East Upper Electrical breakers in "OFF" Penetration Room MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF MCC breakers placed in OFF VALVE." position.

MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF STRESS TEST DISC SWITCH."

MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER."

MCC-3C1-A3R, HE DS/STRESS GALL-DS, ROOM 66 HOIST &

STRESS GALLERY TEST DISC SWITCHES.

MCC-3C1-A4L, "SPARE.

MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER."

MCC-3C1-A05, "TRANSFORMER T1B- [ SAT ] [ UNSAT ]

3C COOLING FANS."

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP ELEMENT STANDARD 5 Energize bus 1B3C: CUE: After Candidate identifies the correct handle Obtain the circuit breaker at the AOP-06 cabinet, "You handle from the Shift Manager have obtained the circuit or the AOP-06 Cabinet. breaker handle."

[ SAT ] [ UNSAT ]

6 Close breaker 1B3C-4, East Switchgear room "EMERG. FEED TO BUS 1B3C Close breaker 1B3C-4 and FROM 13.8KV/480V XFMR verify breaker position T1B-3C-1." indicators display CLOSED.

[ SAT ] [ UNSAT ]

7 Check that Bus 1B3C is Checks indication on VG-energized. 1/1B3C Voltmeters T1B-3C Secondary Phase (1,2,3) (Line to GND) and amber lights for each phase.

CUE: Equal voltage indicated on all three phases and all three amber lights ON with equal intensity.

[ SAT ] [ UNSAT ]

8 Close BT-1B3C, "BUS TIE East Switchgear room 1B3C & 1B3C-4C NORMALLY Close breaker BT-1B3C and CLOSED." verify breaker position indicators display CLOSED.

[ SAT ] [ UNSAT ]

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 STEP ELEMENT STANDARD 9 Close BT-1B4C, "BUS TIE CUE: Another Operator will 1B4C & 1B3C-4C NORMALLY close breaker BT-1B4C, OPEN." place Battery Charger #3 in service and transfer DC control power.

Termination Criteria: 480 volt buses 1B3C and 1B3C-4C are energized from 13.8 KV.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 INITIAL A station blackout has occurred.

CONDITIONS: Both 161 KV and 345 KV supplies to the station have been lost.

Both Diesel Generators have failed to start.

Energy Marketing reports that 13.8 KV power is available to the plant.

INITIATING CUE: You have been directed to energize 480 volt buses 1B3C, 1B3C-4C and 1B4C using EOP/AOP Attachment

5. The Control Room Operators have completed steps 1 and 2.

EOP/AOP ATTACHMENTS Page 17 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

1. Trip BOTH of the following 4160 V breakers:
2. Place the following control switches in PULL-TO-LOCK:
  • CA-1A, Air Compressor
  • AC-3C, CCW pump
  • VA-3B, Containment Vent Fan
  • SI-3A, CS Pump
  • VA-7C, Containment Vent Fan R26

EOP/AOP ATTACHMENTS Page 18 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

3. Trip ALL of the following 480 V breakers (East Switchgear Room):
  • 1B3C, "T1B-3C MAIN SECONDARY FEED TO 480 VAC BUS 1B3C"
  • 1B3C-2, "MCC-3C2 AUX BUILDING (CORR. 26)"
  • 1B3C-7, "TURBINE BUILDING CRANE HE-3"
  • 1B3C-5, "MCC-3C3 SERVICE BLDG (3RD FLOOR)"

EOP/AOP ATTACHMENTS Page 19 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

4. Trip ALL of the following 480 V breakers (East Switchgear Room):
  • 1B3C-4C-2, "BREAKER UNIT MCC-3C4C-2 TURBINE BLDG (MEZZANINE)"
  • 1B3C-4C-3, "BREAKER UNIT CONTAINMENT COOLING FAN VA-7C"
  • 1B3C-4C-4, "BREAKER UNIT COMPONENT COOLING WATER PUMP AC-3C" R26

EOP/AOP ATTACHMENTS Page 20 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

5. Trip ALL of the following 480 V breakers (West Switchgear Room):
  • 1B4C, "T1B-4C MAIN SECONDARY FEED TO 480 VAC BUS 1B4C"
  • 1B4C-8, "CONTAINMENT COOLING & FILTER FAN VA-3B"
  • 1B4C-3, "MCC-4C2 AUX BLDG (CORR 4)"
  • 1B4C-4, "MCC-4C3 TURB BLDG (MEZZANINE)"
  • 1B4C-7, "MCC-4C4 INTAKE STRUCTURE"

PUMP SI-2B"

AREA (RM 57W)"

  • 1B4C-1, "MCC-4C5 MOTOR CONTROL CENTER TURBINE BUILDING" R26

EOP/AOP ATTACHMENTS Page 21 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

6. Place ALL of the following breakers in "OFF" (East Upper Electrical Penetration Room):
  • MCC-3C1-A01, "PCV-102-1 PZR POWER OPERATED RELIEF VALVE"
  • MCC-3C1-A2R, "AUX BLDG ROOF-DS, AUX BLDG ROOF STRESS TEST DISC SWITCH"
  • MCC-3C1-A3L, "MPP-58/EE-98 MOTOR PROTECTION PANEL TRANSFORMER"
  • MCC-3C1-A3R, HE-12-DS/STRESS GALL-DS, ROOM 66 HOIST & STRESS GALLERY TEST DISC SWITCHES
  • MCC-3C1-A4L, "SPARE
  • MCC-3C1-A4R, "EE-4Q INVERTER "C" EE-8K BYPASS TRANSFORMER"
  • MCC-3C1-A05, "TRANSFORMER T1B-3C COOLING FANS" R26

EOP/AOP ATTACHMENTS Page 22 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

7. Energize Bus 1B3C by performing the following steps:
a. Obtain the circuit breaker handle from the Shift Manager or the AOP-06 Cabinet.
b. Close breaker 1B3C-4, "EMERG.

FEED TO BUS 1B3C FROM 13.8KV/480V XFMR T1B-3C-1" (East Switchgear Room).

8. Check that Bus 1B3C is energized.
9. Close BOTH of the following 480 V breakers:
  • BT-1B3C, "BUS TIE 1B3C &

1B3C-4C NORMALLY CLOSED" (East Switchgear Room)

  • BT-1B4C, "BUS TIE 1B4C &

1B3C-4C NORMALLY OPEN" (West Switchgear Room)

R26

EOP/AOP ATTACHMENTS Page 23 of 168 Attachment 5 Energizing 480 V Buses From 13.8 KV INSTRUCTIONS CONTINGENCY ACTIONS

10. Place Battery Charger 3 in service by performing the following steps:
a. Ensure breaker 1B3C-1, "MCC-3C1 ELECT PENET.

AREA (RM 57E)", is closed (East Switchgear Room).

b. Open BOTH Battery Charger 3 breakers (West Switchgear Room):
  • EE-8E-CB1, BATT CHARGER 3 (EE-8E) AC INPUT BREAKER
  • EE-8E-CB2, BATT CHARGER 3 (EE-8E)DC OUTPUT BREAKER
c. Place the "VOLTAGE SELECTOR" switch in "FLOAT" (EE-8E).

(continue)

R26

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Location: Intake Structure Approximate Time: 10 minutes Actual Time: _________________

Reference(s): K/A# 086000 A2.04 OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRAINER OPERATION."

Handout(s): OI-FP-1, Attachment 3, "FP-1B, DIESEL FIRE PUMP AND FP-6B DIESEL FIRE PUMP STRAINER OPERATION."

Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/05/09 Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: Potential tripping hazards. Do Not operate any controls.

Comments: Alternate Path Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump TASK The Candidate performed a local emergency start of STANDARD: Diesel Fire Pump, FP-1B. The candidate manually opened the Fuel Oil Solenoid Valve and the Cooling Water Bypass valve and started the pump using a Starter Contactor because Manual Start number 1 and 2 were both unsuccessful.

INITIAL The Electric Fire Pump, FP-1A, is out of service.

CONDITIONS: Transformer deluge has activated due to a fire.

The Diesel Fire Pump, FP-1B, did not start automatically.

INITIATING CUE: You are directed to perform a local emergency manual start of the diesel fire pump in accordance with OI-FP-1, Attachment 3, step 3.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner: Provide candidate with a copy of OI-FP-1, Attachment 3.

1 Ensure the following are on: AI-183 AI-183-CB1, Fire Pump FP-1B Batt 1 Switch. Battery 1 is ON.

AI-183-CB2, Fire Pump FP-1B Batt 2 Switch. Battery 2 is ON.

[ SAT ] [ UNSAT ]

2 Place HC/FP-1B-MS, Diesel AI-183 Fire Pump FP-1B Local Control Switch, to Manual 1. Select Manual #1.

[ SAT ] [ UNSAT ]

3 Press HC/FP-1B-1, "Fire Pump AI-183 FP-1B Crank 1 Start Button.

Push Crank 1 Start Button.

[ SAT ] [ UNSAT ]

CUE: Engine did not turn over or start 4 Place HC/FP-1B-MS, Diesel AI-183 Fire Pump FP-1B Local Control Switch, to Manual 2. Select Manual #2.

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump STEP ELEMENT STANDARD 5 Press HC/FP-1B-1, "Fire Pump AI-183 FP-1B Crank 2 Start Button.

Push Crank 2 Start Button.

[ SAT ] [ UNSAT ]

CUE: Engine did not turn over or start 6 Open FO-169, Fuel Oil South side of Engine Solenoid Valve.

Turn Knob clockwise to full-in position.

[ SAT ] [ UNSAT ]

7 Open FP-161, Pressure control South side of Engine valve FP-162 bypass valve.

Cooling water bypass valve to OPEN.

[ SAT ] [ UNSAT ]

8 Read Caution Read Caution on page 24

[ SAT ] [ UNSAT ]

9 Engage the starter using either North side of Engine of the two starter contactors.

Raise lever knob on either:

YS/FP-1B-1.

YS/FP-1B-1.

CUE: Engine has started and is running.

Release lever.

[ SAT ] [ UNSAT ]

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 JPM Title: Local Emergency Manual Start of the Diesel Fire Pump Termination Criteria: Diesel Fire Pump has been started Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 2 INITIAL The Electric Fire Pump, FP-1A, is out of service.

CONDITIONS: Transformer deluge has activated due to a fire.

The Diesel Fire Pump, FP-1B, did not start automatically.

INITIATING CUE: You are directed to perform a local emergency manual start of the diesel fire pump in accordance with OI-FP-1, Attachment 3, step 3.

Page 7 of 7

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 18 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PREREQUISITES (T) INITIALS

1. Procedure Revision Verification Revision No. 68 Date: 3/31/09 JEK PROCEDURE NOTE Prior to declaring FP-1B inoperable the Fire Protection System Engineer or designee shall analyze Room 19 Fire Protection System per SO-G-58 to minimize risk to safety related cable trays.
1. IF removing FP-1B, Diesel Fire Pump, from service, THEN complete the following:
a. Notify the Control Room this system is being removed from service.
b. Ensure the requirements of SO-G-103 are met and log into any required Action Statements in the Control Room Log.

Shift Mgr

c. A Fire Impairment has been issued for removing FP-1B from service.

NOTE The following will alarm when FP-1B is placed in PULL OUT:

! ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10,11/A13, B-3L)

d. Place FP-1B control switch in PULL-OUT (CB-10/11).
e. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, in OFF (AI-183).
f. Close FP-153, Diesel Fire Pump FP-1B Discharge to Main Header.
g. Verify FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed.

R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 19 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS

1. h. Ensure FP-154, From Screenwash Header Crosstie Valve, is closed.

CAUTION A leak greater than the makeup of the Jockey Pump will cause an inadvertent start of FP-1A when draining FP-1B header.

i. IF necessary to drain header, THEN open FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve.
2. IF returning Diesel Fire Pump FP-1B to service, THEN complete the following:

CAUTION Security must be present at the Screen F enclosure and remain there until Sluice Gate CW-14F is closed or CW-1C is placed back in service.

a. Ensure one of the following Suction Well flow paths is aligned as follows

! CW-14E, Circ Water Pump CW-1C Screen Sluice Gate, is open

! CW-14F, Circ Water Pump CW-1C Screen Sluice Gate, is open

! CW-16B, Circ Water Pumps interconnection Sluice Gate and CW-14C, Traveling Screen Sluice Gate, are open

! CW-16B, Circ Water Pumps interconnection Sluice Gate and CW-14D, Traveling Screen Sluice Gate, are open Shift Mgr

b. Ensure FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed.

R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 20 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS CAUTION If FP-1A control switch is taken to pull-to-lock to prevent inadvertent starting a Dedicated Operator must be stationed at the control switch (Ref. SO-G-103)

2. c. If desired by the Shift Mgr/CRS to prevent an inadvertent start of FP-1A:
1) Station a Dedicated Operator at the FP-1A control switch with instructions to immediately return the control switch to AFTER STOP should water be needed for the Fire Protection System. This would be indicated by receipt of a fire suppression system flow alarm, initiation of manual fire suppression activities using fire hose stations or confirmation of a fire in a protected area.

Dedicated Operator NOTE The following will alarm when FP-1A is placed in PULL OUT:

! MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD TRIP (CB-10,11/A13, B-4U)

2) Place FP-1A control switch (CB-10/11) in pullout.

CAUTION Slowly throttling open FP-502 while maintaining Fire Main pressure greater than 116 psig will prevent inadvertent starting of Electric Fire Pump FP-1A on low pressure.

d. IF maintenance was performed on FP-6B, Diesel Driven Fire Pump FP-1B Strainer, THEN ensure maintenance personnel are available and standing by prior to pressurization.

R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 21 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS

2. e. Slowly throttle open FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, to pressurize line to FP-1B.
f. Verify Fire Main pressure is greater than 116 psig.
g. Open and Lock Open FP-153, Diesel Fire Pump FP-1B Discharge to Main Header.
h. Close FP-502.
i. Return FP-1A to auto if required by:

NOTE The following alarm will reset when FP-1A is placed in AFTER STOP:

! MTR DRIVEN FIRE PUMP OFF NORMAL OVERLOAD TRIP (CB-10,11/A13, B-4U)

1) Place FP-1A control switch (CB-10/11) in AFTER STOP.
2) Secure the Dedicated Operator for FP-1A.
j. Place FP-1B control switch in AFTER-STOP (CB-10/11).

R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 22 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS NOTE The following alarm will reset when HC/FP-1B-MS is placed in AUTO:

! ENGINE DRIVEN FIRE PUMP OFF NORM ENGINE FAIL OR DC POWER FAIL (CB-10/11/A13, B-3L)

2. k. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to AUTO (AI-183).
l. Ensure minimum Level of 75% indicated level of diesel fuel in FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank, by completing the following:
1) Unlock and open FO-231, Diesel Tank FO-27 Sightglass Root Valve.
2) Allow level in the sightglass to settle at its equilibrium point.
m. Record FO-27, Diesel Fire Pump FP-1B Fuel Oil Storage Tank level:

Level (33" min.)

1) Close and Lock FO-231.
n. Independently verify the following valve positions: [AR 06498]

! FO-231, Diesel Tank FO-27 Sightglass Root Valve, is Locked Closed

! FP-156, Diesel Fire Pump Strainer FP-6B Drain Valve, is closed

! FP-153, Diesel Fire Pump FP-1B Discharge to Main Headers, is Locked Open

! FP-502, Fire Pump Disch Valve FP-153 Bypass Valve, is closed

! FP-1B CS, Diesel Fire Pump Control Switch, is in AFTER STOP (CB-10/11)

! HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, is in AUTO (AI-183)

Ind Verif

o. Notify Control Room Operator the system has been returned to service.

[AR 06498]

R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 23 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS

2. p. Exit from any Action Statements entered in the Control Room Log.
q. Clear the Fire Impairment issued for FP-1B.
3. IF Local Emergency Manual Starting of the Diesel Fire Pump (AI-183) is required, THEN complete the following:
a. Ensure the following are ON:

! AI-183-CB1, Fire Pump FP-1B Batt 1 Switch

! AI-183-CB2, Fire Pump FP-1B Batt 2 Switch

b. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to MANUAL 1.
c. Press HC/FP-1B-1, Fire Pump FP-1B Crank 1 Start Button.
d. IF Engine does not start, THEN perform the following:
1) Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to MANUAL 2.
2) Press HC/FP-1B-2, Fire Pump FP-1B Crank 2 Start Button.
e. IF the Engine has not started, THEN perform the following:
1) Open FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, by turning the knob in (clockwise).
2) Open FP-161, Pressure Control Valve FP-162 Bypass Valve.

R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 24 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS CAUTION As soon as the engine is running in Step 3), release the lever.

3.e 3) Engage the starter by raising the lever knob on either of the two starter contactors:

! YS/FP-1B-1, Diesel Fire Pump FP-1B #1 Starter Contactor

! YS/FP-1B-2, Diesel Fire Pump FP-1B #2 Starter Contactor

4. IF securing from Local Emergency Manual Starting of the Diesel Fire Pump (AI-183),

THEN complete the following:

a. Place HC/FP-1B-MS, Diesel Fire Pump FP-1B Local Control Switch, to OFF.
b. Ensure FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve, is closed (by turning the knob out counter-clockwise).
c. Ensure FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed.
d. Independently verify the following valve positions: [AR 06498]

! FP-161, Pressure Control Valve FP-162 Bypass Valve, is closed

! FO-169, Diesel Fire Pump FP-1B Fuel Oil Solenoid Valve (by turning the knob out counter-clockwise)

Ind Verif R68

FORT CALHOUN STATION OI-FP-1 OPERATING INSTRUCTION PAGE 25 OF 186 C

Continuous Use Attachment 3 - FP-1B, Diesel Fire Pump and FP-6B Diesel Fire Pump Strainer Operation PROCEDURE (continued) (T) INITIALS

5. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO or MANUAL, THEN complete one of the following:
a. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in AUTO, THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to AUTO.

CAUTION If the Fire Pumps are in AUTO-STANDBY and FP-1B is not operating, placing FP-6B control box toggle switch in MANUAL will depressurize the Fire Main and start both Fire Pumps.

b. IF placing FP-6B, Diesel Fire Pump FP-1B Strainer, in MANUAL, THEN place HC/FP-6B, Fire Pump Strainer FP-6B Mode Selector Switch, to MANUAL.

Completed by Date/Time /

Reviewed by Shift Manager [AR 06498]

R68

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test Location: Simulator Approximate Time: 18 minutes Actual Time: _________________

Reference(s): K/A: 001000 A4.03 OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)

PARTIAL MOVEMENT TEST" OI-RR-1, "REACTOR REGULATING SYSTEM NORMAL OPERATION" Handout(s): OP-ST-CEA-0003, "CONTROL ELEMENT ASSEMBLY (CEA)

PARTIAL MOVEMENT TEST" Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/3/09 Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations:

Comments: Alternate Path Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test TASK The candidate performed the CEA partial movement STANDARD: check for group 3 CEAs using OP-ST-CEA-003. While inserting one of the CEAs, the CEA continued to insert after releasing the IN-OUT-HOLD switch. The candidate stopped the uncontrolled motion by placing the Mode Selector Switch in OFF.

INITIAL The plant is operating at full power with all CEAs fully CONDITIONS: withdrawn.

INITIATING CUE: You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.

All prerequisites have been met.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test Critical Steps shown in gray STEP ELEMENT STANDARD 1 Record the initial position of Records position of CEAs each group 3 CEA. 2,3,4 and 5 as 128 inches on OP-ST-CEA-003, attachment 1.

[ SAT ] [ UNSAT ]

2 Rotate the Mode selector CB-4 switch to Manual Individual Places Mode Selector Switch position. (M/M) to the Manual Individual Position (M/I).

[ SAT ] [ UNSAT ]

3 Rotate the Group Selector CB-4 Switch (M/G) to the group Rotate Group Selector Switch containing the CEA to be (M/G) to the "Group 3" moved. position.

[ SAT ] [ UNSAT ]

4 Verify on the DCS display CB-4 CEA_ALL that the group button Ensure CEA-ALL is displayed is DARK GREY. and that Group 3 is DARK GREY.

[ SAT ] [ UNSAT ]

5 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to CEA position.

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test STEP ELEMENT STANDARD 6 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA position is 122 inches or less. Then Pull IN-OUT-HOLD switch until CEA is fully withdrawn.

[ SAT ] [ UNSAT ]

7 Record Information on Note to Examiner: This step Attachment 1. may be completed after all CEAs have been exercised.

Record inserted to and returned to position for CEA on Attachment 1.

[ SAT ] [ UNSAT ]

8 Rotate the Rod Selector Switch CB-4 to the CEA to be moved. Rotate Rod Selector Switch to next CEA position.

[ SAT ] [ UNSAT ]

9 Insert CEA a minimum of 6 CB-4 inches then return to normal Push IN-OUT-HOLD switch in position. until CEA position is 122 inches or less.

[ SAT ] [ UNSAT ]

NOTE: CEA will continue to insert Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 JPM Title: Control Element Assembly Movement Test STEP ELEMENT STANDARD 10 Immediately place Mode CB-4 Selector Switch in OFF. Immediately return Mode Selector Switch to OFF position before the CEA has been inserted to less than 108 inches. Verify CEA motion has stopped.

[ SAT ] [ UNSAT ]

11 Notify Shift Manager of failure. Notified Shift Manager of uncontrolled CEA motion.

[ SAT ] [ UNSAT ]

12 Verify position of all CEAs. CB-4 Verifies position off all CEAs using Primary and Secondary CEA Position Indication.

[ SAT ] [ UNSAT ]

CUE: The Shift Manager has directed that this surveillance test be terminated.

Termination Criteria: The Mode Selector Switch is in the OFF position and the test has been terminated by the Shift Manager.

Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 2 INITIAL The plant is operating at full power with all CEAs fully CONDITIONS: withdrawn.

INITIATING CUE: You have been directed to perform the CEA Partial Movement Check for group 3 CEAs (2, 3, 4 and 5) using OP-ST-CEA-0003.

All prerequisites have been met.

Page 7 of 7

PAGE 1 OF 9 Fort Calhoun Station Unit No. 1 OP-ST-CEA-0003 SURVEILLANCE TEST CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK Change No. EC 34712 Reason for Change These changes are intended to facilitate use of the GARDEL core monitoring program and to allow operator, STA, and RE to use the program for the performance of various core monitoring and testing functions.

Requestor T. Heng Preparer T. Heng Issue Date 06-06-08 3:00 pm R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 2 OF 9 CONTROL ELEMENT ASSEMBLY (CEA) PARTIAL MOVEMENT CHECK SAFETY RELATED

1. PURPOSE To satisfy, at least quarterly when the Reactor is critical, the requirements of Technical Specification 3.2, Table 3-5, Item 2.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:
  • 3.2, Table 3-5, Minimum Frequencies for Equipment Tests
  • 2.10.2 (4), Full Length CEA Position During Power Operation
  • 2.10.2 (6), Shutdown CEA Insertion Limit During Power Operation
  • 2.10.2 (7), Regulating CEA Insertion Limits During Hot Standby and Power Operation
  • 2.15, Table 2-5, Instrumentation Operating Requirements for Other Safety Feature Functions 2.2 USAR, Section 7 2.3 SO-G-23, Surveillance Test Program 2.4 Ongoing Commitment Documents
  • AR 04922, LIC-87-0013
  • AR 08779, LIC-88-0765 (LER-88-018)
  • AR 14801, LIC-93-0294 (LER-93-016)
3. DEFINITIONS None
4. EQUIPMENT LIST None
5. PRECAUTIONS AND LIMITATIONS 5.1 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted in the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 3 OF 9 5.2 Manipulation of all controls as defined in 10CFR55 shall be done by, or under the direct supervision of, a NRC licensed operator.

5.3 Only one method of positive reactivity addition shall be used at any one time.

5.4 During all rod motion, nuclear instrumentation and RCS temperature shall be observed for response.

5.5 Be alert for any abnormal noise or indications when CEDMs are in operation.

5.6 Power Dependent Insertion Limits shall not be violated by more than one (1) CEA at a time during this test.

5.7 Shutdown CEAs shall not be inserted below the exercise limit.

5.8 Each CEA shall be returned to its pretest position prior to testing other CEAs.

5.9 CEAs within a Group should be kept within two (2) inches of each other per OI-RR-1, unless specifically required otherwise by this procedure.

5.10 The Reactor shall not be placed in the Automatic mode.

5.11 No maintenance shall be conducted within this Surveillance Test other than that specifically directed by this procedure.

5.12 Any time the Mode Selector Switch is in any position other than OFF, all available rod position indications shall be monitored, Synchros, SCEAPIS, ERF (page 302), and Core Mimic. [AR 14801]

5.13 If a CEA position abnormality occurs, verify the position of all CEAs. [AR 14801]

5.14 The following annunciators may Alarm during the performance of this Surveillance test:

  • REGULATING GROUP WITHDRAWAL PROHIBIT (CB-4, A8, A-1L)
  • PDIL GR 1 COMPUTER (CB-4, A8, A-3U)
  • PPDIL GR 1 COMPUTER (CB-4, A8, A-4U)
  • PDIL GR 2 COMPUTER (CB-4, A8, A-3L)
  • PPDIL GR 2 COMPUTER (CB-4, A8, A-4L)
  • ROD DRIVE POWER INTERRUPT (CB-4, A8, A-5U)
  • ROD POSITION DEVIATION LOW LIMIT (CB-4, A8, B-1U)
  • ROD POSITION DEVIATION LOW-LOW LIMIT (CB-4, A8, B-1L)
  • PDIL GR 3 COMPUTER (CB-4, A8, B-3U)
  • PPDIL GR 3 COMPUTER (CB-4, A8, B-4U)
  • VLPM ALARM OR TROUBLE (CB-1,2,3, A6, D-3)

R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 4 OF 9 5.15 The following DCS alarms may occur during the performance of this Surveillance Test:

  • ROD BLOCK
  • PPDIL
  • PDIL
  • ISH
6. PREREQUISITES INITIALS/DATE 6.1 Procedure Revision Verification:

Revision No. 13 JEK / 3/31/09 6.2 Reactor is critical. JEK / 3/31/09 6.3 No other test is in progress which could potentially affect this test, or if JEK 3/31/09 this test were performed, could have an effect on that test. /

6.4 A prejob briefing has been conducted prior to the start of this test. JEK / 3/31/09 6.5 Primary Synchro CEA Position Indicating System is operable.

[AR 14801] JEK / 3/31/09 6.6 Shift Manager authorizes performance of this test:

Shift Manager SHIFT MANAGER Date/Time 3/31/09 / 0730

7. PROCEDURE NOTE: Step 7.1 can be performed at anytime and repeated as necessary.

7.1 IF this Surveillance Test is turned over, a prejob briefing must be N/A conducted prior to the continuation of this test. /

CAUTION [AR 04922]

When the Reactor is critical, this Surveillance Test must be performed within the specified Technical Specification time interval regardless of rod configuration or use.

7.2 IF not in an All-Rods-Out configuration, THEN contact the Reactor Engineer prior to commencing this test for guidance to ensure the requirements of Technical Specification 3.2, Table 3-5, Item 2 are met. [AR 04922]

N/A

[AR 08779]

R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 5 OF 9 7.3 Record Initial Position of all CEAs on Attachment 1.

7.4 Rotate the Mode Selector Switch (M/M) to the Manual Individual (M/I) position.

7.5 Rotate the Group Selector Switch (M/G) to the Group containing the CEA to be moved.

7.6 If available, verify on SCEAPIS (DCS) display CEA_ALL that the group button is DARK GREY for the group selected.

7.7 Rotate the Rod Selector Switch to the CEA to be moved.

NOTE: If Group 4 CEAs are being used for ASI control, movement of 6 inches in a single direction may be credited. The returned to position may not necessarily be the initial position. Note the time of Group 4 movement for ASI control on the Comment Sheet if applicable.

7.8 Insert or withdraw the CEA, as applicable, a minimum of six (6) inches, THEN return the CEA to its Initial Position.

NOTE: Step 7.9 may be completed after all CEAs within a Group have been exercised, after all CEAs have been exercised, OR after exercising each CEA.

7.9 Record Inserted/Withdrawn To AND Return To information on Test Data Sheet, THEN initial Attachment 1.

7.10 Repeat Steps 7.5 through 7.9 for all CEAs listed on Attachment 1.

7.11 Rotate Mode Selector Switch (M/M) to the OFF position.

7.12 Independently verify each CEA returned to its initial position listed on Attachment 1.

Ind Verif Completed By: Date/Time /

8. RESTORATION 8.1 Shift Manager notified this test is completed:

Shift Manager Date/Time /

9. ACCEPTANCE CRITERIA 9.1 All CEAs have been moved a minimum of six (6) inches.

R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 6 OF 9

10. TEST RECORD 10.1 This entire procedure.
11. REVIEW NOTE: The Reactor Engineer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of this test of any unexpected results.

11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of this test.

Evaluated by Date/Time /

STA Reviewed by Date/Time /

Shift Manager R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 7 OF 9 Attachment 1 - CEA Partial Movement Check Test Data Sheet Initial Inserted/ Ind Verif CEA Returned to Position Withdrawn Initials Initials Remarks No. (Inches)

(inches) (inches) 30 31 32 33 34 35 36 37 14 15 16 17 6

8 10 12 22 23 24 25 26 27 28 29 2

R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 8 OF 9 Attachment 1 - CEA Partial Movement Check Test Data Sheet Initial Inserted/ Ind Verif CEA Returned to Position Withdrawn Initials Initials Remarks No. (Inches)

(inches) (inches) 3 4

5 38 39 40 41 1

Completed By: Date/Time /

R13

FORT CALHOUN STATION OP-ST-CEA-0003 SURVEILLANCE TEST PAGE 9 OF 9 Comment Sheet R13

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header Location: Simulator Approximate Time: 12 minutes Actual Time: _________________

Reference(s): K/A# 004000 A4.08 AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."

Handout(s): AOP-33, Attachment B, "CHARGING FROM THE HPSI HEADER."

Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations:

Comments:

Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header TASK The candidate established Charging flow to the RCS STANDARD: using the Loop 2A High Pressure Safety Injection (HPSI) header following the identification of a leak in the charging line.

INITIAL The plant is operating at full power. AOP-33 has been CONDITIONS: entered due to a leak in the charging header. Charging and letdown have been isolated and the leak has stopped.

INITIATING CUE: The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop 2A injection valve, HCV-318, per AOP-33, Attachment B.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header Critical Steps shown in gray STEP ELEMENT STANDARD 1 Close CH-194, "CHARGING Direct EONA to close CH-194.

PUMPS CH-1A/B/C DISCHARGE HEADER [ SAT ] [ UNSAT ]

CONTAINMENT OUTBOARD ISOLATION VALVE" (Room CUE: EONA reports that CH-13). 194 is closed.

2 Open HCV-308, Charging CB-1,2,3 Pump HPSI Header Isolation Hold HCV-308 Control Switch Valve. in OPEN until GREEN light goes OFF. Then Release and allow it to return to NORM.

Verify RED light ON and GREEN light OFF.

[ SAT ] [ UNSAT ]

3 Ensure HCV-2987, HPSI AI-30A Header Isolation Valve, is RED light is ON and GREEN open. light is OFF.

[ SAT ] [ UNSAT ]

4 Ensure HCV-307, HPSI Header AI-30B Isolation Valve, is open. RED light ON.

GREEN light OFF.

[ SAT ] [ UNSAT ]

5 Ensure HCV-305, SI-2A and AI-30B SI-2C Discharge Cross- RED light ON.

Connect Valve, is open. GREEN light OFF.

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header STEP ELEMENT STANDARD 6 Ensure HCV-304, SI-2B and AI-30A SI-2C Discharge Cross- RED light ON.

Connect Valve, is open. GREEN light OFF.

[ SAT ] [ UNSAT ]

7 Ensure HCV-306, HPSI Header AI-30A Isolation Valve, is open. RED light ON.

GREEN light OFF.

[ SAT ] [ UNSAT ]

8 Close the SI Tank Leakage AI-30A Cooler Pressure Control Valves Place Control Switch in on the loop in which the HPSI MANUAL valve(s) will be opened, If required, adjust PCV-2949 PCV-2949. Controller such that needle indicates 100% (full right).

GREEN light ON.

RED light OFF.

[ SAT ] [ UNSAT ]

9 Open HCV-318 (Loop 2A). AI-30B HCV-318 Control Switch to OPEN. RED light ON, GREEN light OFF.

(Note: may also PULLOUT switch, but not required)

[ SAT ] [ UNSAT ]

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 JPM Title: Establish Charging Flow via the HPSI Header STEP ELEMENT STANDARD 10 Ensure a charging pump CB-1,2,3 suction source is available. Ensure LCV-218-2 open RED light ON and VCT level indicated on chart or indicator.

OR Ensure LCV-218-3 open RED light ON.

[ SAT ] [ UNSAT ]

11 Operate any available CB-1,2,3 Charging Pumps as necessary Start at least one charging to maintain PZR level within pump, CH-1A/B/C by taking 4% of programmed level. Control switch out of Pull-To-Lock, taking to AFTER-START and verifying RED light ON.

[ SAT ] [ UNSAT ]

Termination Criteria: A charging pump is supplying water to the RCS via the HPSI header.

Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-2 Rev 3 INITIAL The plant is operating at full power. AOP-33 has been CONDITIONS: entered due to a leak in the charging header. Charging and letdown have been isolated and the leak has stopped.

INITIATING CUE: The CRS has directed you to reestablish charging pump flow via the HPSI header using HPSI loop 2A injection valve, HCV-318, per AOP-33, Attachment B.

Page 7 of 7

AOP-33 Page 21 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS NOTE Charging through the HPSI Header will result in the addition of approximately 100 gallons of water at refueling boron concentration into the RCS.

1. Close CH-194, "CHARGING PUMPS CH-1A/B/C DISCHARGE HEADER CONTAINMENT OUTBOARD ISOLATION VALVE" (Room 13).
2. Open HCV-308, Charging Pump HPSI Header Isolation Valve.
3. Ensure ALL of the following valves are open:
  • HCV-305, SI-2A and SI-2C Discharge Cross-Connect Valve
  • HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve

AOP-33 Page 22 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS

4. Close the SI Tank Leakage Cooler Pressure Control Valves on the loop in which the HPSI valve(s) will be opened in Step 5:

Loop 1B

  • PCV-2909 Loop 1A
  • PCV-2929 Loop 2A
  • PCV-2949 Loop 2B
  • PCV-2969
5. Open at least one of the following HPSI Loop Injection Valves:
  • HCV-312 (Loop 1B)
  • HCV-315 (Loop 1A)
  • HCV-318 (Loop 2A)
  • HCV-321 (Loop 2B)

R7

AOP-33 Page 23 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS NOTE Using the SIRWT as a suction source will inject water with refueling boron concentration into the RCS.

6. Ensure a charging pump suction source is available.

NOTE Charging flow can be verified on the associated HPSI flow indicator(s) for the HPSI Loop Valve(s) in use, or on ERF (Page 323).

7. Operate any available Charging Pumps as necessary to maintain PZR level within 4% of programmed level.
8. IF Charging Header repairs are possible 8.1 IF Charging Header repairs are NOT with the Plant in its current operating possible with the Plant in its current mode, operating mode, THEN direct Maintenance to repair leak. THEN place the Plant in desired mode PER ONE of the following procedures:
  • OP-4, Load Change and Normal Power Operations R7

AOP-33 Page 24 of 52 Attachment B Charging Via the HPSI Header INSTRUCTIONS CONTINGENCY ACTIONS

9. WHEN the Charging Header has been repaired, THEN return the CVCS to normal operation PER OI-CH-1, Startup of Charging and Letdown.
10. WHEN the CVCS has been returned to normal, THEN IMPLEMENT Attachment E, HPSI Piping Flush, to flush all safety injection piping used in this procedure.
11. WHEN HPSI piping flush is completed, THEN GO TO Section 5.0, Exit Conditions.

End of Attachment B R7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection Location: Simulator Approximate Time: 15 minutes Actual Time: _________________

Reference(s): K/A# 006000 A1.11 EOP/AOP Attachment 9, "SIMULTANEOUS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" Handout(s): EOP/AOP Attachment 9, "SIMULTANEOUS HOT AND COLD LEG INJECTION" EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR" Time Critical: YES - 30 Minutes Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/25/09 Page 1 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: Time Critical (30 Minutes), Alternate Path Page 2 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection TASK The candidate began to initiate Simultaneous Hot and STANDARD: Cold Leg injection 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a LOCA occurred using EOP/AOP Attachment 9, SIMULTANEOUS HOT AND COLD LEG INJECTION. Upon recognizing that HCV-305 could not be closed, the Candidate transitioned to EOP/AOP Attachment 10, SIMULTANEOUS HOT AND COLD LEG INJECTION WITHOUT INSTRUMENT AIR, and successfully provided sufficient flow to both a RCS hot leg and the cold legs.

INITIAL A large LOCA occurred 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago.

CONDITIONS: A RAS (Recirculation Actuation Signal) was received 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

HPSI pumps, SI-2A and SI-2B, are operating.

There are no signs of containment sump blockage.

All systems are operating as expected.

INITIATING CUE: ***** TIME CRITICAL *****

The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection in accordance with EOP/AOP Attachment 9.

Page 3 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection Critical Steps shown in gray STEP ELEMENT STANDARD Note to Examiner:

Do Not provide Attachment 10 to candidate until he makes the transition in JPM step 9.

1 Read Cautions on page 44 of Reads both Cautions.

EOP/AOP Attachments.

[ SAT ] [ UNSAT ]

2 Verify conditions in step 1. Verifies:

A LOCA exists.

RCS Pressure is less than 140 psia 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> have elapsed.

[ SAT ] [ UNSAT ]

3 Open at least one of the CB-1,2,3 Charging Pumps HPSI Header Isolation Valves: At least one valves control HCV-308. switch to OPEN with RED light HCV-2988. ON.

[ SAT ] [ UNSAT ]

4 Open at least one of the CB-1,2,3 following PZR Auxiliary Spray Isolation Valves: At least one valves control

  • HCV-240. switch to OPEN with RED light
  • HCV-249. ON.

[ SAT ] [ UNSAT ]

Page 4 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD NOTE: A rapid loss of instrument air pressure occurs due to the rupture of Auxiliary Building air riser "AS."

CUE: If candidate addresses loss of instrument air, inform him that another Operator has responded to the loss of Instrument Air.

5 If only one HPSI Pump is AI-30A/B available, GO TO Attachment

11. Verifies that 2 HPSI Pumps are operating and stays in Attachment 9

[ SAT ] [ UNSAT ]

6 Read Caution on page 45. Reads Caution

[ SAT ] [ UNSAT ]

7 Ensure ALL of the following CB-1,2,3 Charging Isolation Valves are For each valve:

closed: GREEN light ON.

  • HCV-238. RED light OFF.
  • HCV-239. Determines that HCV-247 and
  • HCV-247. HCV-248 are closed but that
  • HCV-248. HCV-238 and HCV-239 are open.

Does not go to attachment 11 because HCV-247 and HCV-248 are closed.

[ SAT ] [ UNSAT ]

Page 5 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 8 IF ANY of the following HPSI Reads step 6.

Discharge Cross-Connect Valves can NOT be closed Note: May determine that because of a loss of Instrument instrument air is not Air: available and immediately HCV-305 transition to EOP/AOP HCV-306 Attachment 10.

THEN Go To Attachment 10 9 IF HPSI Pump, SI-2A, is AI-30B operating,THEN close HCV- Key Switch to CLOSE.

305, SI-2A and SI-2C GREEN light ON.

Discharge Cross-Connect RED light OFF.

Valve.

Determines that HCV-305 will not close due to a loss of instrument air.

[ SAT ] [ UNSAT ]

10 Transitions to EOP/AOP Transitions to EOP/AOP Attachment 10. Attachment 10.

[ SAT ] [ UNSAT ]

NOTE to Examiner: Provide a copy of EOP/AOP Attachment 10 to Candidate.

11 Reviews Cautions. Reads both Cautions.

[ SAT ] [ UNSAT ]

Page 6 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 12 Verify conditions in step 1. Verifies:

A LOCA exists.

RCS Pressure is less than 140 psia 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> have elapsed.

[ SAT ] [ UNSAT ]

13 Verify open at least one of the CB-1,2,3 Charging Pumps HPSI Header Isolation Valves: At least one valves RED light HCV-308. ON.

HCV-2988.

[ SAT ] [ UNSAT ]

14 Verify open at least one of the CB-1,2,3 following PZR Auxiliary Spray Isolation Valves: At least one valves RED light

  • HCV-240. ON.
  • HCV-249.

[ SAT ] [ UNSAT ]

15 If only one HPSI Pump is AI-30A/B available, GO TO Attachment

11. Verifies that 2 HPSI Pumps are operating and stays in Attachment 10

[ SAT ] [ UNSAT ]

16 Read Caution on page 49. Reads Caution

[ SAT ] [ UNSAT ]

Page 7 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 17 Ensure ALL of the following CB-1,2,3 Charging Isolation Valves are For each valve:

closed: GREEN light ON.

  • HCV-238. RED light OFF.
  • HCV-239. Determines that HCV-247 and
  • HCV-247. HCV-248 are closed but that
  • HCV-248. HCV-238 and HCV-239 are open.

Stays in Attachment 10

[ SAT ] [ UNSAT ]

18 Close ALL of the following AI-30A/B HPSI Loop Injection Valves:

  • HCV-315. Control Switches to CLOSE
  • HCV-318. (pull out, counter-clockwise)
  • HCV-312. until GREEN lights ON.
  • HCV-321. RED light OFF.

[ SAT ] [ UNSAT ]

19 Close HCV-2987, HPSI Header AI-30A/B Isolation Valve.

Control Switch to CLOSE.

GREEN light ON.

RED light OFF.

[ SAT ] [ UNSAT ]

Page 8 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 JPM Title: Simultaneous Hot and Cold Leg Injection STEP ELEMENT STANDARD 20 IF evidence of containment AI-30A/B sump blockage does NOT exist, THEN throttle the HPSI Throttle one or more of the Loop Injection Valves until ALL following valves:

of the following criteria are HCV-314.

satisfied: HCV-317.

Charging flow is greater HCV-311.

than180 gpm (FIA-236). HCV-320.

Total HPSI flow is Verify greater than 200 gpm greater than 200 gpm. total flow on FI-313, FI-316, FI-319 and FI-322.

CB-1,2,3 Verify greater than 180 gpm flow on FIA-236.

Note: Plant computer may also be used to verify flows.

[ SAT ] [ UNSAT ]

Termination Criteria: Simultaneous Hot and Cold Leg Injection has been established with greater than 180 gpm flow through charging (Hot Leg) and greater than 200 gpm flow through the HPSI Header (Cold Legs).

Page 9 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 5 INITIAL A large LOCA occurred 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago.

CONDITIONS: A RAS (Recirculation Actuation Signal) was received 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

HPSI pumps, SI-2A and SI-2B, are operating.

There are no signs of containment sump blockage.

All systems are operating as expected.

INITIATING CUE: ***** TIME CRITICAL *****

The Control Room Supervisor has directed you to initiate Simultaneous Hot and Cold Leg Injection in accordance with EOP/AOP Attachment 9.

Page 10 of 10

EOP/AOP ATTACHMENTS Page 44 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS

CAUTIONS

1. Closing HPSI Loop Valves may cause a reduction in RCS pressure and subcooling.
2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.
1. Verify that ALL of the following criteria 1.1 IF all of the criteria are NOT satisfied, are satisfied: THEN continue efforts to initiate SDC.
  • RCS pressure is less than 140 psia
  • Five and one-half hours may elapse before SDC can be established
2. Open at least one of the Charging Pumps HPSI Header Isolation Valves:
  • HCV-308
  • HCV-2988 R26

EOP/AOP ATTACHMENTS Page 45 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS

3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
  • HCV-240
  • HCV-249
4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.

CAUTION Closing HCV-247 isolates a CVCS relief valve.

5. Ensure ALL of the following Charging 4.1 IF ANY of the following Charging Isolation Valves are closed: Isolation Valves are open:
  • HCV-238
  • HCV-247
  • HCV-239
  • HCV-248
  • HCV-247
  • HCV-248 THEN GO TO Attachment 11, Alternate Hot Leg Injection.

R26

EOP/AOP ATTACHMENTS Page 46 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS

6. IF ANY of the following HPSI Discharge Cross-Connect Valves can NOT be closed because of a loss of Instrument Air:
  • HCV-305
  • HCV-304 THEN GO TO Attachment 10, Simultaneous Hot and Cold Leg Injection without Instrument Air.
7. IF HPSI Pump, SI-2A is operating, 7.1 IF HPSI Pump, SI-2A is NOT THEN close HCV-305, SI-2A and operating, SI-2C Discharge Cross-Connect Valve. THEN close HCV-304, SI-2B and SI-2C Discharge Cross-Connect Valve.
8. Close ALL of the following HPSI Loop Injection Valves:
  • HCV-315
  • HCV-318
  • HCV-312
  • HCV-321
9. Close HCV-2987, HPSI Header Isolation Valve.

R26

EOP/AOP ATTACHMENTS Page 47 of 168 Attachment 9 Simultaneous Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS

10. IF evidence of containment sump 10.1 IF evidence of containment sump blockage does NOT exist, blockage does NOT exist, THEN throttle the HPSI Loop Injection AND all of the criteria are NOT Valves until ALL of the following satisfied:

criteria are satisfied: THEN GO TO Attachment 11, Alternate Hot leg Injection.

  • Charging flow is greater than 80 gpm (FIA-236) 10.2 IF evidence of containment sump
  • Total HPSI flow is greater than 200 gpm blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time.

End of Attachment 9 R26

EOP/AOP ATTACHMENTS Page 48 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS

CAUTIONS

1. Closing HPSI Loop Valves may cause a reduction in RCS pressure and subcooling.
2. Simultaneous hot and cold leg injection must be implemented between five and one-half and six hours after a LOCA with RCS pressure less than 140 psia if SDC can not be established.
1. Verify that ALL of the following criteria 1.1 IF all of the criteria are NOT satisfied, are satisfied: THEN continue efforts to initiate SDC.
  • RCS pressure is less than 140 psia
  • Five and one-half hours may elapse before SDC can be established
2. Open at least one of the Charging Pump HPSI Header Isolation Valves:
  • HCV-308
  • HCV-2988 R26

EOP/AOP ATTACHMENTS Page 49 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS

3. Open at least one of the following PZR Auxiliary Spray Isolation Valves:
  • HCV-240
  • HCV-249
4. IF only one HPSI Pump is available, THEN GO TO Attachment 11, Alternate Hot Leg Injection.

CAUTION Closing HCV-247 isolates a CVCS relief valve.

5. Ensure ALL of the following Charging 4.1 IF ANY of the following Charging Isolation Valves are closed: Isolation Valves are open:
  • HCV-238
  • HCV-247
  • HCV-239
  • HCV-248
  • HCV-247
  • HCV-248 THEN GO TO Attachment 11, Alternate Hot Leg Injection.

R26

EOP/AOP ATTACHMENTS Page 50 of 168 Attachment 10 Simultaneous Hot and Cold Leg Injection Without Instrument Air INSTRUCTIONS CONTINGENCY ACTIONS

6. Close ALL of the following HPSI Loop Injection Valves:
  • HCV-315
  • HCV-318
  • HCV-312
  • HCV-321
7. Close HCV-2987, HPSI Header Isolation Valve.
8. IF evidence of containment sump 8.1 IF evidence of containment sump blockage does NOT exist, blockage does NOT exist, THEN throttle the HPSI Loop Injection AND all of the criteria are NOT Valves until ALL of the following satisfied:

criteria are satisfied: THEN GO TO Attachment 11, Alternate Hot leg Injection.

  • Charging flow is greater than 180 gpm (FIA-236) 8.2 IF evidence of containment sump
  • Total HPSI flow is greater than 200 gpm blockage exists, THEN throttle HPSI Loop Injection Valves PER Attachment 26, Curve 3 - Total Hot Leg and Cold Leg Injection vs Time.

End of Attachment 10 R26

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump Location: Simulator Approximate Time: 7 minutes Actual Time: _________________

Reference(s): K/A# 003000 A4.06 OI-RC-9, "REACTOR COOLANT PUMP OPERATION" Handout(s): OI-RC-9, "REACTOR COOLANT PUMP OPERATION" Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump TASK The Candidate started Reactor Coolant Pump RC-3A in STANDARD: accordance with OI-RC-9, "REACTOR COOLANT PUMP OPERATION." The Candidate then tripped the pump when the motor current did not fall below 425 amps within the time specified in the procedure.

INITIAL The plant is in hot shutdown.

CONDITIONS: Reactor Coolant Pump, RC-3C, is running.

RC-3A is scheduled to be started.

The motor on RC-3A is cold.

There is no one in containment.

INITIATING CUE: You are directed to place RC-3A in service in accordance with OI-RC-9, Attachment 1.

All prerequisites are met.

Page 3 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump Critical Steps shown in gray STEP ELEMENT STANDARD NOTE to Examiner:

Simulator Operator has inserted the seized rotor malfunction for RC-3A and has also failed the overcurrent relays for the pump's motor.

1 Read the note and cautions Reads the Note and Cautions on page 8 of OI-RC-9

[ SAT ] [ UNSAT ]

2 Setup ERF Display for RC-3A. ERF Type [440] [DSP]

RC-3A Page displays.

[ SAT ] [ UNSAT ]

3 Station operator to respond to CUE: Operator is at AI-270.

vibration alarms.

[ SAT ] [ UNSAT ]

4 Read Note Reads first note on page 9.

Determines it is not applicable.

[ SAT ] [ UNSAT ]

5 Verify controlled Bleed-off flow. ERF page 342 Verify positive bleed-off flow.

[ SAT ] [ UNSAT ]

6 Read Note Reads second note on page 9.

Determines it is not applicable.

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump STEP ELEMENT STANDARD 7 Ensure RCS Pressure and Verifies RCS Pressure above RCP NPSH. 225 psia.

Use Figure TDB III.7.a to verify NPSH.

[ SAT ] [ UNSAT ]

8 OI-RC-9, Attachment 1 steps 6 Records N/A for steps and 7 because a RCP is running.

[ SAT ] [ UNSAT ]

9 Read Note Reads note near top of page 10

[ SAT ] [ UNSAT ]

10 Ensure 86/RC-3A reset. CB-1/2/3 86/RC-3A AMBER light ON.

[ SAT ] [ UNSAT ]

11 Verify RCP Reverse rotation is CB-1/2/3 cleared. ANN A-6, A5 is clear.

[ SAT ] [ UNSAT ]

12 Read Note and Caution. Reads note and caution near bottom of page 10

[ SAT ] [ UNSAT ]

13 Start RC-3A oil lift pump. CB-1/2/3 RC-3A-1 to AFTER START and RED light ON.

[ SAT ] [ UNSAT ]

Page 5 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump STEP ELEMENT STANDARD 14 Verify ARRD oil flow for RC-3A. ERF Page 342.

Note: Page 342 does not display ARRD oil flow for RC-3A.

[ SAT ] [ UNSAT ]

CUE: The oil lift pump has been running for two minutes 15 Start RC-3A. CB-1/2/3 RC-3A CS in AFTER START and RED light ON.

[ SAT ] [ UNSAT ]

16 Monitor Amps. CB-1/2/3 Determines that RC-3A's ammeter did not drop below 425 amps within 17 seconds.

[ SAT ] [ UNSAT ]

17 Trip RC-3A CB-1/2/3 RC-3A CS in AFTER STOP and RED light OFF.

[ SAT ] [ UNSAT ]

18 Monitor RC-3A motor amps. CB-1/2/3 Verifies zero amps on ammeter.

[ SAT ] [ UNSAT ]

Page 6 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 JPM Title: Start a Reactor Coolant Pump STEP ELEMENT STANDARD 19 Report RC-3A problem to CRS Reports RC-3A problem and need to manually trip pump to CRS

[ SAT ] [ UNSAT ]

Termination Criteria: RC-3A has been tripped.

Page 7 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 INITIAL The plant is in hot shutdown.

CONDITIONS: Reactor Coolant Pump, RC-3C, is running.

RC-3A is scheduled to be started.

The motor on RC-3A is cold.

There is no one in containment.

INITIATING CUE: You are directed to place RC-3A in service in accordance with OI-RC-9, Attachment 1.

All prerequisites are met.

Page 8 of 8

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 6 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PREREQUISITES (T) INITIALS NOTES

1. Attachment 7 provides guidance for starting RCPs for sweeping steam generator tubes.
2. Attachment 6 provides recovery guidance from the possibility of a slug of water with reduced boron concentration in an idle RCS loop.
1. Procedure Revision Verification Revision No. 69 Date: 3/31/09 JEK
2. The Reactor is Shutdown (Mode 3, Mode 4 or Mode 5). JEK
3. Communications have been established between the Control Room and locally at each Reactor Coolant Pump, as needed, prior to Reactor Coolant Pump start. JEK
4. Applicable sections of Checklist OI-RC-9-CL-A have been completed for each RCP to be run. JEK
5. A minimum Reactor Coolant System pressure per TDB-III.7.a or TDB-III.7.d, RCS Pressure and Temperature Limits, has been established to ensure JEK adequate Reactor Coolant Pump Net Positive Suction Head (NPSH).
6. The Component Cooling Water System is in operation to each Reactor Coolant Pump to be run per OI-CC-1. JEK
7. The Red Motor Heater Lights for each non-operating Reactor Coolant Pump are energized. JEK
8. The ERF Computer is operable per OI-ERFCS-1. JEK
9. If the RCP has been idle for a long outage OR for maintenance, a general visual inspection of the RCP should be performed prior to starting. JEK
10. The Reactor Coolant Pump Motor upper and lower oil reservoirs are filled to levels as specified in Tables 1 through 4. JEK
11. Instrumentation and alarms associated with RCPs to be run are operable. JEK R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 7 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PREREQUISITES (continued) (T) INITIALS

12. 4.16 KV Buses for RCPs to be run (1A1, 1A2, 1A3 and 1A4) are energized. JEK
13. RCPs to be operated are coupled per MM-RR-RC-0008. JEK PROCEDURE NOTE Controlled Bleedoff Flow can be established within 24 hrs of starting the first RCP.
1. Open all the following valves:

! RC-308, RC-3A Reactor Coolant Pump Controlled Bleedoff Isolation Valve O

! RC-309, RC-3B Reactor Coolant Pump Controlled Bleedoff Isolation Valve O

! RC-310, RC-3C Reactor Coolant Pump Controlled Bleedoff Isolation Valve O

! RC-311, RC-3D Reactor Coolant Pump Controlled Bleedoff Isolation Valve O JEK R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 8 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS NOTE High vibration alarms should be anticipated when starting RCPs.

CAUTIONS

1. IF the Steam Generator secondary side temperature is greater than 30°F above the RCS cold leg temperature, the effects of heat input from the secondary side, and the subsequent effects on heatup rate, must be evaluated/considered.
2. If no RCP is running, and Tc is less than 350°F, then a Reactor Coolant Pump shall NOT be started unless the following conditions are satisfied:

! Actual PZR level is less than or equal to 50% per TDB-III.1.a

! RCS pressure must be less than the Maximum Pressure for First Start RCP (TDB-III.7.a curve 3)

3. When starting a RCP, ensure RCS Pressure is greater than 225 psia to reduce the possibility of seal failure.
4. Each RCP shall be monitored continuously on the ERF Computer throughout each starting period.
2. Set up one ERF Display Screen to monitor the selected Reactor Coolant Pump and Motor parameters as follows:

! RC-3A page 440

! RC-3B page 441

! RC-3C page 442

! RC-3D page 443

3. Station an operator at AI-270 (Room 57) to respond to vibration alarms.

OI-RC-13 provides alarm response guidance. JEK R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 9 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.

4. Verify positive Controlled Bleedoff Flow for the selected RCP on ERF (page 342):

! RC-3A

! RC-3B

! RC-3C

! RC-3D NOTE When starting the first Reactor Coolant Pump, use TR-346, Shutdown Cooling Inlet/Outlet Temp, black pen LPSI Suction Temp indication to verify NPSH requirements are met.

5. Ensure RCS Pressure is greater than 225 psia for RCP seal protection (ensures RCS Pressure is greater than minimum NPSH Pressure per TDB-III.7.a and TDB-III.7.d, RCS Pressure and Temperature Limits).
6. Ensure RCS Pressure is less than the Maximum Pressure for First RCP Start curve per TDB-III.7.a, RCS Pressure and Temperature Limits. (NA if an RCP is running).
7. Ensure actual corrected level per TDB-III.1.a Pressurizer level is less than 50%. (NA if an RCP is running).

R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 10 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS NOTE IF Lockout Relays are NOT RESET, THEN Electrical Maintenance shall be contacted for an inspection of the affected relay(s).

8. Ensure the Lockout Relay Switch for the selected RCP is in RESET and the Amber indicating light is ON:

! 86/RC-3A, Pump RC-3A Motor Current Diff

! 86/RC-3B, Pump RC-3B Motor Current Diff

! 86/RC-3C, Pump RC-3C Motor Current Diff

! 86/RC-3D, Pump RC-3D Motor Current Diff

9. For the selected RCP verify the following Annunciator is clear:

! RC-3A REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)

! RC-3B REACTOR COOLANT PUMP RC-3B REVERSE ROTATION (CB-1/2/3, A6, B5)

! RC-3C REACTOR COOLANT PUMP RC-3C REVERSE ROTATION (CB-1/2/3, A6, C5)

! RC-3D REACTOR COOLANT PUMP RC-3D REVERSE ROTATION (CB-1/2/3, A6, D5)

NOTE The Oil Lift Pump shall not be run for longer than 10 minutes before starting the Reactor Coolant Pump.

CAUTION Prior to starting a RCP when personnel are in Containment, the Containment Coordinator shall be notified, OR an announcement made on the Gaitronics.

10. Place the Oil Lift Pump for the selected RCP to AFTER START:

! RC-3A-1, Oil Lift Pump

! RC-3B-1, Oil Lift Pump

! RC-3C-1, Oil Lift Pump

! RC-3D-1, Oil Lift Pump R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 11 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS

11. Verify adequate ARRD Lube Oil Flow for the selected RCP. ERF indication shall read NORMAL: (ERF page 342)

! RC-3A F3181

! RC-3B F3184

! RC-3C F3187

! RC-3D F3190

12. Startup sequence for selected RCP:
a. Run the oil lift pump for the selected RCP a minimum of two minutes.

! RC-3A-1, Oil Lift Pump

! RC-3B-1, Oil Lift Pump

! RC-3C-1, Oil Lift Pump

! RC-3D-1, Oil Lift Pump

b. Place the selected RCP control switch in AFTER START:

! RC-3A, RC Pump

! RC-3B, RC Pump

! RC-3C, RC Pump

! RC-3D, RC Pump

c. IF the Reactor Coolant Pump motor amps fail to drop below 425 amps within the time listed below, THEN place the control switch in AFTER STOP:

! RC-3A - seventeen (17) seconds

! RC-3B - nineteen (19) seconds

! RC-3C - seventeen (17) seconds

! RC-3D - seventeen (17) seconds R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 12 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS

13. Verify the following for the selected RCP:
a. Oil Lift Pump stops (Green indicating light ON):

! RC-3A-1

! RC-3B-1

! RC-3C-1

! RC-3D-1

b. For the selected RCP verify the following Annunciator is clear:

! RC-3A REACTOR COOLANT PUMP RC-3A REVERSE ROTATION (CB-1/2/3, A6, A5)

! RC-3B REACTOR COOLANT PUMP RC-3B REVERSE ROTATION (CB-1/2/3, A6, B5)

! RC-3C REACTOR COOLANT PUMP RC-3C REVERSE ROTATION (CB-1/2/3, A6, C5)

! RC-3D REACTOR COOLANT PUMP RC-3D REVERSE ROTATION (CB-1/2/3, A6, D5)

NOTE RCP Vibration Hi annunciator may be erratic until pump speed/flow stabilizes.

c. For the selected RCP verify the following Annunciator is clear:

! RC-3A REACTOR COOLANT PUMP RC-3A VIBRATION HI (CB-1/2/3, A6, A4)

! RC-3B REACTOR COOLANT PUMP RC-3B VIBRATION HI (CB-1/2/3, A6, B4)

! RC-3C REACTOR COOLANT PUMP RC-3C VIBRATION HI (CB-1/2/3, A6, C4)

! RC-3D REACTOR COOLANT PUMP RC-3D VIBRATION HI (CB-1/2/3, A6, D4)

R69

FORT CALHOUN STATION OI-RC-9 OPERATING INSTRUCTION PAGE 13 OF 66 C

Continuous Use Attachment 1 - Starting Reactor Coolant Pumps (Coupled)

PROCEDURE (continued) (T) INITIALS NOTE At low RCS Pressure, verification of positive Controlled Bleedoff Flow may NOT be possible.

14. Verify positive Controlled Bleedoff flow for the selected RCP: (ERF page 342)

! RC-3A F3115

! RC-3B F3135

! RC-3C F3155

! RC-3D F3175

15. Monitor the ERF Computer and verify all parameters are normal for the selected RCP:

! RC-3A

! RC-3B

! RC-3C

! RC-3D

16. IF other RCPs are to be started, THEN repeat Steps 2 through 15 for each RCP to be started.

Completed by Date/Time /

R69

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs Location: Simulator Approximate Time: 10 minutes Actual Time: _________________

Reference(s): K/A# 061000 A2.04 EOP-06, "LOSS OF ALL FEEDWATER" Handout(s) EOP-06, Step 12.

Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/3/09 Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments: Alternate Path Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs TASK The candidate attempted to supply water to the steam STANDARD: generators from Turbine Driven AFW Pump, FW-10, through the feed rings but was unsuccessful because FW-10 would not start. The Candidate established flow to both Steam Generators through the feed rings using Diesel Driven AFW Pump, FW-54.

INITIAL A reactor trip has occurred following a rupture of CONDITIONS: the Condensate Pumps' common discharge header.

FW-6 is out of service.

The CRS has entered EOP-6.

There are no Operators available to perform any local actions.

INITIATING CUE: You have been directed to feed both steam generators from FW-10, via the feed rings in accordance with EOP-06, Step 12.

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs Critical Steps shown in gray STEP ELEMENT STANDARD NOTE to Examiner: If the candidate requests an EONT or other In-plant Operator to take any actions during the performance of this JPM, inform him that the EONT is not available.

1 Ensure BOTH of the Feed CB-10,11 Reg Block Valves are GREEN lights ON.

closed:

  • HCV-1103. [ SAT ] [ UNSAT ]
  • HCV-1104.

2 Start FW-10 AI-66B Place YCV-1045 switch in OPEN, verfiy RED light ON Verify YCV-1045A and/or YCV-1045B OPEN-RED light ON Determines that FW-10 will not start. Goes to contingency action, 12.1.

3 Ensure HCV-1384 is closed. CB-10,11 Control Switch in AFTER CLOSE, GREEN light ON.

[ SAT ] [ UNSAT ]

4 Ensure BOTH of the Feed CB-10,11 Reg Block Valves are GREEN lights ON.

closed:

  • HCV-1103. [ SAT ] [ UNSAT ]
  • HCV-1104.

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM Title: Initiate AFW to SGs STEP ELEMENT STANDARD 4 Start FW-54 CB-10,11 Control switch to open.

RED light ON.

[ SAT ] [ UNSAT ]

5 Ensure BOTH of the Feed CB-10,11 header Isolation Valves are open: RED lights ON GREEN lights OFF HCV-1386 HCV-1385 6 Manually control feed flow CB-10,11 via BOTH of the Feed Reg DCS Panel Bypass Valves:

  • HCV-1105. Manually open HCV-1105 and
  • HCV-1106. HCV-1106 to establish flow.

[ SAT ] [ UNSAT ]

7 Verify AFW Flow established to CB-10,11 or ERF both S/Gs. Flow indicated on meters or ERF computer.

[ SAT ] [ UNSAT ]

8 Record Time. Record Time at step 12.1.a.5)

[ SAT ] [ UNSAT ]

Termination Criteria: Flow established from FW-54 to both Steam Generators Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 INITIAL A reactor trip has occurred following a rupture of CONDITIONS: the Condensate Pumps' common discharge header.

FW-6 is out of service.

The CRS has entered EOP-6.

There are no Operators available to perform any local actions.

INITIATING CUE: You have been directed to feed both steam generators from FW-10, via the feed rings in accordance with EOP-06, Step 12.

Page 6 of 6

EOP-06 Page 11 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812. Initiate AFW using FW-6 or FW-10, 12.1 IF FW-6 and FW-10 are NOT AFW Pumps, by performing step a, b available, or c: THEN initiate AFW using FW-54, Diesel AFW Pump, by performing

a. Feed S/Gs with AFW through the step a or b:

Feed Rings to maintain S/G level 35-85% NR (73-94% WR):

a. Feed S/Gs with AFW to the Feed Rings to maintain S/G levels
1) Ensure BOTH of the Feed 35-85% NR (73-94% WR):

Reg Block Valves are closed:

1) Ensure HCV-1384, FW/AFW
  • HCV-1103 Header Cross-Connect Valve,
  • HCV-1104 is closed.
2) Start at least one of the
2) Ensure BOTH of the Feed following AFW Pumps:

Reg Block Valves are closed:

  • FW-6
  • FW-10
  • HCV-1103
  • HCV-1104
3) Open HCV-1384, AFW/FW Header Cross-Connect 3) Start FW-54, Diesel AFW Valve. Pump.
4) Ensure BOTH of the Feed 4) Ensure BOTH of the Feed Header Isolation Valves are Header Isolation Valves are open:

open:

  • HCV-1386
  • HCV-1386
  • HCV-1385
  • HCV-1385 (continue) (continue) 8 Continuously Applicable or Non-Sequential Step R16

EOP-06 Page 12 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.a. (continued) 12.1.a (continued)

5) Manually control feed flow 5) Manually control feed flow via via BOTH of the Feed Reg BOTH of the Feed Reg Bypass Valves: Bypass Valves:
  • HCV-1105
  • HCV-1105
  • HCV-1106
  • HCV-1106 Time: Time:
6) IF Auxiliary Feedwater flow 6) IF Auxiliary Feedwater flow is is established, established, THEN GO TO Step 15. THEN GO TO Step 15.

(continue) (continue) 8 Continuously Applicable or Non-Sequential Step R16

EOP-06 Page 13 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 8 12. (continued) 12.1 (continued)

b. Feed S/Gs with AFW to the Feed b. Feed S/Gs with AFW to the AFW Rings via the alternate AFW Nozzles to maintain S/G levels Pump discharge path to maintain 35-85% NR (73-94% WR):

S/G levels 35-85% NR (73-94%

WR): 1) Close BOTH of the Feed Header Isolation Valves:

1) Open BOTH of the following
  • HCV-1386 valves (Room 19):
  • HCV-1385
  • FW-745, "MOTOR DRIVEN AUX FEED 2) Open HCV-1384, FW/AFW PUMP FW-6 ALTERNATE Header Cross-Connect Valve.

DISCHARGE VALVE"

  • FW-744, 3) Start FW-54, Diesel AFW "TURB-DRIVEN AUX Pump.

FEED PUMP FW-10 ALTERNATE DISCHARGE VALVE"

4) IF AFAS has actuated, THEN set BOTH of the
2) Ensure BOTH of the Feed following AFW Isolation Valve Reg Block Valves are Controllers to open closed:

(CB-10,11):

  • HCV-1103
  • HCV-1104
  • HIC-1107B
  • HIC-1108B (continue) (continue) 8 Continuously Applicable or Non-Sequential Step R16

EOP-06 Page 14 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.b (continued) 12.1.b (continued)

3) Start at least one of the 5) Place control switches for following AFW Pumps: BOTH of the following AFW Isolation Valves in "CLOSE"
  • FW-6
  • FW-10 (AI-66A/B):
4) Ensure BOTH of the Feed
  • HCV-1107B
  • HCV-1108B Header Isolation Valves are open:
6) Open BOTH of the following
  • HCV-1385 AFW Isolation Valves
  • HCV-1386 (AI-66A/B):
5) Manually control feed flow
  • HCV-1107A
  • HCV-1108A via BOTH of the Feed Reg Bypass Valves: 7) Manually control BOTH of the following AFW Isolation
  • HCV-1105
  • HCV-1106 Valves (CB-10,11):

Time:

  • HIC-1107B
  • HIC-1108B
6) IF Auxiliary Feedwater flow is established, Time:

THEN GO TO Step 15.

8) IF Auxiliary Feedwater flow is established, (continue) THEN GO TO Step 15.

(continue) 8 Continuously Applicable or Non-Sequential Step R16

EOP-06 Page 15 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.b (continued)

c. Feed S/Gs with AFW to the AFW Nozzles to maintain S/G levels 35-85% NR (73-94% WR):
1) Start at least one of the following AFW Pumps:
  • FW-6
  • FW-10
2) Ensure HCV-1384, FW/AFW Header Cross-Connect Valve, is closed.
3) IF AFAS has actuated, THEN set BOTH of the following AFW Isolation Valve Controllers to open (CB-10,11):
  • HIC-1107B
  • HIC-1108B (continue) 8 Continuously Applicable or Non-Sequential Step R16

EOP-06 Page 16 of 41 INSTRUCTIONS CONTINGENCY ACTIONS 812.c. (continued)

4) Place Control Switches for BOTH of the following AFW Isolation Valves in "CLOSE" (AI-66A/B):
  • HCV-1107B
  • HCV-1108B
5) Open BOTH of the following AFW Isolation Valves (AI-66A/B):
  • HCV-1107A
  • HCV-1108A
6) Manually control BOTH of the following AFW Isolation Valves (CB-10,11):
  • HIC-1107B
  • HIC-1108B Time:
13. IF Auxiliary Feedwater flow is established, THEN GO TO Step 15.

8 Continuously Applicable or Non-Sequential Step R16

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Location: Simulator Approximate Time: 10 minutes Actual Time: _________________

Reference(s): K/A 028000 A1.01 EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" Handout(s): EOP/AOP Attachment 16, "CONTAINMENT HYDROGEN ANALYZER STARTUP" Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/3/09 Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer TASK The Candidate placed the Containment Hydrogen STANDARD Analyzers in service and determined that the hydrogen concentration is below flammability limits.

INITIAL A LOCA occurred followed by a sustained core CONDITIONS: uncovery. The core is now covered but radiation levels in containment indicate that some fuel damage may have occurred. The SAMG Evaluators in the TSC need to know the containment hydrogen concentration to perform core damage assessment.

INITIATING CUE: You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachment 16 and sample the upper level of containment via HCV-820C and HCV-883C. Determine if Containment Hydrogen Concentration is above flammability limits.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Critical Steps shown in gray STEP ELEMENT STANDARD 1 Open HCV-820C. AI-65A/B Control switch to OPEN.

RED light ON.

[ SAT ] [ UNSAT ]

2 Open HCV-883C. AI-65A/B Control switch to OPEN.

RED light ON.

[ SAT ] [ UNSAT ]

3 Place all of the following AI-43A/B switches in Override: Control switches to ORIDE.

HCV-820A/821A. RED lights ON.

HCV-883A/884A.

HCV-820B/821B.

HCV-883B/884B. [ SAT ] [ UNSAT ]

4 Place recorders, HR-81A/B in AI-65A/B service. Turn recorders on.

[ SAT ] [ UNSAT ]

5 Ensure Range Selector AI-65A/B switches are in 0-10%. Selector switch in 0-10%

position.

[ SAT ] [ UNSAT ]

6 Place the Hydrogen Analyzer AI-65A/B Power On Selector Switches to Switches to ANALYZE ANALYZE. position.

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer STEP ELEMENT STANDARD 7 Ensure the Function Selector AI-65A/B Switches are in SAMPLE. Switches in SAMPLE position.

[ SAT ] [ UNSAT ]

8 Press REMOTE selector AI-65A/B pushbuttons. Depress pushbuttons.

[ SAT ] [ UNSAT ]

9 Check the following: AI-65A/B Containment H2 Alarm Window ON.

Sampling System Remote/Local Off Normal Annunciator in Alarm.

0-10% Range Amber AMBER light ON.

indicating light is ON.

The Sample Indicating Light is ON.

light is ON.

[ SAT ] [ UNSAT ]

10 Press Alarm Reset Push AI-65A/B buttons. Depress push buttons.

[ SAT ] [ UNSAT ]

CUE: 5 minutes have elapsed 11 Obtain hydrogen concentration AI-65A/B reading. Report reading from meters is below flammability limits.

[ SAT ] [ UNSAT ]

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 JPM Title: Operate the Containment Hydrogen Analyzer Termination Criteria: Containment hydrogen concentration has been determined Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 2 INITIAL A LOCA occurred followed by a sustained core CONDITIONS: uncovery. The core is now covered but radiation levels in containment indicate that some fuel damage may have occurred. The SAMG Evaluators in the TSC need to know the containment hydrogen concentration to perform core damage assessment.

INITIATING CUE: You are directed to place the Hydrogen analyzers in service per the EOP/AOP Attachment 16 and sample the upper level of containment via HCV-820C and HCV-883C. Determine if Containment Hydrogen Concentration is above flammability limits.

Page 7 of 7

EOP/AOP ATTACHMENTS Page 79 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS

1. Start the Hydrogen Analyzers, by performing the following steps:
a. Open ONE of the Containment Hydrogen Sampling Valves, HCV-820C/D/E/F/G/H.
b. Open ONE of the Containment Hydrogen Sampling Valves, HCV-883C/D/E/F/G/H.
c. Place ALL of the following switches in "O'RIDE":
  • "H2 ANALYZER VA-81A ISOLATION VALVES OUTBD HCV-820A/821A"
  • "H2 ANALYZER VA-81B ISOLATION VALVES INBD HCV-883A/884A"
  • "H2 ANALYZER VA-81A ISOLATION VALVES INBD HCV-820B/821B"
  • H2 ANALYZER VA-81B ISOLATION VALVES OUTBD HCV-883B/884B" (continue)

R26

EOP/AOP ATTACHMENTS Page 80 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued)
d. Place the Hydrogen Analyzer Recorders, HR-81A/B, in service.
e. Ensure the Hydrogen Analyzer Dual Range Selector Switches are in "0-10%".
f. Place the Hydrogen Analyzer Power On Selector Switches in "ANALYZE".
g. Ensure the Function Selector Switches are in "SAMPLE".
h. Press the "REMOTE" selector push buttons.

(continue)

R26

EOP/AOP ATTACHMENTS Page 81 of 168 Attachment 16 Containment Hydrogen Analyzer Startup INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued)
i. Check the following indications:
  • The CONTAINMENT H2 SAMPLING SYSTEM REMOTE/LOCAL OFF NORMAL annunciator (A65A or B, Window 32) is IN ALARM
  • H2 0-10% Range Amber indicating light is ON
  • The Sample indicating light is ON
j. Press the "ALARM RESET" push buttons.
k. WHEN 5 minutes has elapsed since pressing the "ALARM RESET" push button, THEN a valid hydrogen concentration may be read.

End of Attachment 16 R26

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV Location: Simulator Approximate Time: 10 minutes Actual Time: _________________

Reference(s): K/A 000062 A4.01 AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV."

OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."

Handout(s): AOP-31,Section II, "ALL 4160 V BUSES FED FROM 22 KV",

step 10.

OI-EE-1, Attachment 1, "FEED VITAL/NON-VITAL BUSES FROM 161 KV."

Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 03/3/09 Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: None Safety Considerations: None Comments:

Page 2 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV TASK The candidate transferred the power supplies to vital STANDARD: buses 1A3 and 1A4 from 345 KV to 161 KV following the restoration of 161 KV power in accordance with AOP-31, "161 KV GRID MALFUNCTIONS" and OI-EE-1, "NORMAL OPERATION OF 4160 VOLT SYSTEM, "

Attachment 1.

INITIAL The plant is operating at full power.

CONDITIONS: A loss of 161 KV occurred due to a grid problem.

Buses 1A3 and 1A4 transferred to 345 KV.

AOP-31, section II was entered and appropriate actions taken.

The 161 KV grid problem has been fixed and 161 KV is available.

INITIATING CUE: You are directed to restore normal 161 KV power to buses 1A3 and 1A4 using AOP-31, section II, step 10 and OI-EE-1, Attachment 1.

Page 3 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV Critical Steps shown in gray STEP ELEMENT STANDARD 1 Ensure Lockout Relay 86/161 AI-22 is reset. 86 Relay RESET.

[ SAT ] [ UNSAT ]

2 Ensure all of the following AI-24, AI-25, AI-46 Lockout Relays are reset: Relays RESET.

86-1/T1A-4.

86-2/T1A-4.

86-1/T1A-3.

86-2/T1A-3.

86X/FT161. [ SAT ] [ UNSAT ]

3 Read Caution. Read Caution on AOP-31 page 10.

[ SAT ] [ UNSAT ]

CUE: System Operations has been notified.

4 Synchronize and Close at least CB-20 one of the following breakers: Insert Sync switch handle and Breaker 110. turn to ON.

Breaker 111. Breaker switch to AFTER CLOSE.

RED light ON.

[ SAT ] [ UNSAT ]

5 Turn off Sync switch. CB-20 Turn Sync switch handle to OFF.

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV STEP ELEMENT STANDARD 6 Enter OI-EE-1, Attachment 1. Enters OI-EE-1, Attachment 1.

7 Ensure both fast Transfer CB-20 switches in manual: Both switches in MANUAL.

43/1A1-1A3.

43/1A2-1A4. [ SAT ] [ UNSAT ]

8 Read Note Reads Note on middle of OI-EE-1, page 4

[ SAT ] [ UNSAT ]

Note: Buses 1A3 and 1A4 may be transferred in either order.

9 Turn 1A33 Synchroscope ON. CB-20 Insert Sync switch handle and turn to ON.

[ SAT ] [ UNSAT ]

10 Verify incoming and running CB-20 voltages are matched. Verify voltages within 25 volts.

[ SAT ] [ UNSAT ]

11 Verify Synchroscope at 12 CB-20 o'clock. Indicator at 12 o'clock.

[ SAT ] [ UNSAT ]

12 Close Breaker 1A33. CB-20 Breaker 1A33 in AFTER CLOSE, RED light ON.

[ SAT ] [ UNSAT ]

Page 5 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV STEP ELEMENT STANDARD 13 Open Breaker 1A13 CB-20 Breaker 1A13 in AFTER TRIP.

GREEN light ON

[ SAT ] [ UNSAT ]

14 Turn Off Synchroscope. CB-20 Sync switch handle to OFF Verify loads still energized

[ SAT ] [ UNSAT ]

15 Turn 1A44 Synchroscope ON. CB-20 Insert Sync switch handle and turn to ON.

[ SAT ] [ UNSAT ]

16 Verify incoming and running CB-20 voltages are matched. Verify voltages within 25 volts.

[ SAT ] [ UNSAT ]

17 Verify Synchroscope at 12 CB-20 o'clock. Indicator at 12 o'clock.

[ SAT ] [ UNSAT ]

18 Close Breaker 1A44. CB-20 Breaker 1A44 in AFTER CLOSE, RED light ON.

[ SAT ] [ UNSAT ]

Page 6 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 JPM Title: Transfer 4160V Buses from 345 KV to 161 KV STEP ELEMENT STANDARD 19 Open Breaker 1A24. CB-20 Breaker 1A24 in AFTER TRIP.

GREEN light ON.

[ SAT ] [ UNSAT ]

20 Turn Off Synchroscope. CB-20 Sync switch handle to OFF Verify loads still energized.

[ SAT ] [ UNSAT ]

21 Verify conditions for fast CB-20 transfer met:

All lock-outs on CB-20 AMBER lights ON for all have amber light on. lock-out relays(vertical Appropriate 4160V panel).

breakers not in pull-to- Control Switches not in lock. PULL-TO-LOCK:

Power is available. o Breaker 1A13 o Breaker 1A24 Voltmeters show proper voltages.

[ SAT ] [ UNSAT ]

22 Place Fast Transfer switches in CB-20 AUTO Both Switches in AUTO.

43/1A1-1A3.

43/1A2-1A4. [ SAT ] [ UNSAT ]

Termination Criteria: Buses 1A3 and 1A4 powered from 161 KV Page 7 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 2 INITIAL The plant is operating at full power.

CONDITIONS: A loss of 161 KV occurred due to a grid problem.

Buses 1A3 and 1A4 transferred to 345 KV.

AOP-31, section II was entered and appropriate actions taken.

The 161 KV grid problem has been fixed and 161 KV is available.

INITIATING CUE: You are directed to restore normal 161 KV power to buses 1A3 and 1A4 using AOP-31, section II, step 10 and OI-EE-1, Attachment 1.

Page 8 of 8

AOP-31 Page 20 of 28 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS CONTINGENCY ACTIONS

10. WHEN 161 KV power is available, THEN restore normal power to Buses 1A3 and 1A4 by performing the following steps:
a. Ensure Lockout Relay 86/161 is reset (AI-22).
b. Ensure ALL of the following lockout relays are reset:
  • 86-1/T1A-4 (AI-25)
  • 86-2/T1A-4 (AI-25)
  • 86-1/T1A-3 (AI-24)
  • 86-2/T1A-3 (AI-24)
  • 86X/FT161 (AI-46)

(continue)

R9

AOP-31 Page 21 of 28 Section II - All 4160 V Buses Fed From 22 KV INSTRUCTIONS CONTINGENCY ACTIONS

10. (continued)

CAUTION System Operations should be notified prior to operating any switchyard breakers or disconnect switches to ensure all personnel are clear.

c. Synchronize and close at least one of the following breakers:
  • Breaker 110
  • Breaker 111
d. Transfer buses 1A3 and 1A4 to 161 KV PER Attachment 1 of OI-EE-1, Normal Operation of 4160V System.

End of Section 4.0 R9

FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION PAGE 4 OF 35 C

Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PREREQUISITES (%) INITIALS

1. Procedure Revision Verification Revision No. 25 Date: 3/31/09 JEK
2. 161 KV is in service per OI-EG-2. JEK
3. IF startup of Gen G1 is being performed, N/A THEN ensure OI-EE-1-CL-A has been completed per OP-1.

PROCEDURE

1. Ensure both Fast Transfer Switches are in MANUAL:

! 43/1A1-1A3

! 43/1A2-1A4 NOTE Steps 2 through 5 may be performed in any order.

2. Transfer 1A1, Non-Vital Bus, to 161 KV as follows:
a. Turn on Synchroscope for 1A31.
b. Verify Incoming and Running voltages are approximately matched.
c. Verify Synchroscope is approximately at a 12 o'clock position.
d. Close 1A31.
e. Open 1A11.
f. Turn off Synchroscope.
3. Transfer 1A2, Non-Vital Bus, to 161 KV as follows:
a. Turn on Synchroscope for 1A42.
b. Verify Incoming and Running voltages are approximately matched.

R25

FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION PAGE 5 OF 35 C

Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PROCEDURE (continued) (%) INITIALS 3 c. Verify Synchroscope is approximately at a 12 o'clock position.

d. Close 1A42.
e. Open 1A22.
f. Turn off Synchroscope.
4. Transfer 1A3, Vital Bus, to 161 KV as follows:
a. Turn on Synchroscope for 1A33.
b. Verify Incoming and Running voltages are approximately matched.
c. Verify Synchroscope is approximately at a 12 o'clock position.
d. Close 1A33.
e. Open 1A13.
f. Turn off Synchroscope.
5. Transfer 1A4, Vital Bus, to 161 KV as follows:
a. Turn on Synchroscope for 1A44.
b. Verify Incoming and Running voltages are approximately matched.
c. Verify Synchroscope is approximately at a 12 o'clock position.
d. Close 1A44.
e. Open 1A24.
f. Turn off Synchroscope.

R25

FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION PAGE 6 OF 35 C

Continuous Use Attachment 1 - Feed Vital/Non-Vital Buses From 161 KV PROCEDURE (continued) (%) INITIALS

6. IF the following conditions for Fast Transfer are met,

! All lock-outs on CB-20 have amber light on

! Appropriate 4160 volt breakers are not in pull-to-lock

! Power is available to transfer to THEN place both Fast Transfer Switches in AUTO.

! 43/1A1-1A3

! 43/1A2-1A4 NOTE Under certain plant conditions, while supplying all 4160 volt buses, overheat of T1A3 or T1A4 could occur. To minimize this potential, loads between the 2 transformers should be balanced as much as practicable.

7. Balance loads between T1A3 and T1A4 as plant conditions allow.

Completed by Date/Time /

R25

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment Location: Simulator Approximate Time: 15 minutes Actual Time: _________________

Reference(s): K/A# 012000 A4.02 OP-ST-RPS-0005, "RPS POWER ADJUSTMENT" Handout(s): OP-ST-RPS-0005, "RPS POWER ADJUSTMENT" RPS Scaling Amp Offset Measurement Record.

Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/23/09 Page 1 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment: RPS Trip Unit Bypass Keys 1, 9 and 12 Safety Considerations: None Comments:

Page 2 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment TASK The Candidate performed OP-ST-RPS-0005, "RPS STANDARD: POWER ADJUSTMENT", for RPS channels A and D and adjusted channel "D" NI Power and T Power to agree with XC-105, plant secondary calorimetric power measurement.

INITIAL The plant is operating at full power.

CONDITIONS: Secondary Calorimetric measurement, XC-105, indicates the reactor is operating at 1497.5 MWt.

The STA has verified XC-105 is valid.

The prerequisites for OP-ST-RPS-0005. RPS POWER ADJUSTMENT, have been met.

INITIATING CUE: You have been directed to perform OP-ST-RPS-0005, RPS POWER ADJUSTMENT, for channels A and D, and adjust any channels that need adjustment.

Page 3 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment Critical Steps shown in gray STEP ELEMENT STANDARD 1 Record Channel T Scaling AI-31A/B/C/D Amp Offsets from the RPS Records Channel T Scaling Scaling Amplifier Offset Amp Offsets for channels A Measurement Record (Control and D on test data sheet 1.

Room File drawer) on Test Data Sheet 1 and verify the [ SAT ] [ UNSAT ]

Scaling Amp Offset values on the Power Range Safety Drawers.

2 Record Channel NI Scaling AI-31A/B/C/D Amp Offsets from the RPS Records Channel NI Scaling Scaling Amplifier Offset Amp Offsets for channels A nd Measurement Record (Control D on test data sheet 1 Room File drawer) on Test Data Sheet 1 and verify the [ SAT ] [ UNSAT ]

Scaling Amp Offset values on the Power Range Safety Drawers.

3 Record channels Initial T AI-31A/B/C/D Power readings from RPSCIP Records Initial T Power DVM on Test Data Sheet 1. readings for channels A and D on test data sheet 1.

[ SAT ] [ UNSAT ]

4 Record channels Initial NI AI-31A/B/C/D Power readings from RPSCIP Records Initial NI Power DVM on Test Data Sheet 1. readings for channels A and D on test data sheet 1.

[ SAT ] [ UNSAT ]

Page 4 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP ELEMENT STANDARD 5 Subtract the Scaling Amp AI-31A/B/C/D Offset from Initial T Power Records Initial T Power reading for channels and readings - scaling amp offset record on Test Data Sheet 1. for channels A and D on test data sheet 1.

[ SAT ] [ UNSAT ]

6 Subtract the Scaling Amp AI-31A/B/C/D Offset from the Initial NI Power Records Initial NI Power reading for channels and readings - scaling amp offset record on Test Data Sheet 1. for channels A and D on test data sheet 1.

[ SAT ] [ UNSAT ]

7 Record channels Initial T Pwr AI-31A/B/C/D Calibrate and Nuclear Pwr Records Initial T Pwr Calibrate dial (Power Range Calibrate and Nuclear Pwr Monitor Drawer) settings on Calibrate dial settings for Test Data Sheet 1. channels A and D on test data sheet 1.

[ SAT ] [ UNSAT ]

8 Determine Channel that need Determines Channel "D" adjustment. differs with XC-105 by more than 1% and must be adjusted.

[ SAT ] [ UNSAT ]

9 Place RPSCIP DVM Meter AI-31D Input Switch to METER INPUT Places DVM Meter Input position. Switch to METER INPUT position.

[ SAT ] [ UNSAT ]

Page 5 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP ELEMENT STANDARD 10 Push +10V pushbutton and AI-31D verify DVM reads +9.800 to Pushes +10V pushbutton and

+10.200V. verifies reading.

[ SAT ] [ UNSAT ]

11 Push -10V pushbutton and AI-31D verify DVM reads -9.800 to Pushes -10V pushbutton and

-10.200V. verifies reading.

[ SAT ] [ UNSAT ]

12 Push ZERO pushbutton and AI-31D verify DVM reads -0.200 to Pushes ZERO pushbutton and

+0.200V. verifies reading.

[ SAT ] [ UNSAT ]

13 Record current value of XC- Enters 1497.5 MWt on Test 105 and calculate the Thermal Data Sheet 1. Calculates the Power on Test Data Sheet 1. Thermal Power as 99.8% and enters value on Test Data Sheet 1.

[ SAT ] [ UNSAT ]

14 Enter Technical Specification CUE: Another Operator has Limiting Condition for logged into Technical Operation 2.15, Table 2-2, Speciifications.

Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12. [ SAT ] [ UNSAT ]

Page 6 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP ELEMENT STANDARD 15 Bypass trip units 1, 9 and 12. CUE: Provide TU bypass keys to candidate.

AI-31D Inserts Keys in Trip Units 1, 9 and 12 and turns to BYPASS position.

[ SAT ] [ UNSAT ]

16 Place the DVM selector switch AI-31D to NUCLEAR PWR. Selects NUCLEAR PWR on DVM selector switch

[ SAT ] [ UNSAT ]

17 Adjust the Power Range AI-31D Monitor NUCLEAR PWR Adjusts Potentiometer such CALIBRATE potentiometer that DVM reading equals 99.8 until the DVM equals the plus the NI scaling amp offset.

Thermal Power plus the NI Scaling Amp Offset. [ SAT ] [ UNSAT ]

18 Place the DVM selector switch AI-31D to T PWR. Selects T PWR on DVM selector switch

[ SAT ] [ UNSAT ]

19 Adjust T PWR CALIBRATE AI-31D potentiometer until the Adjusts Potentiometer such NUCLEAR PWR-T PWR (%) that zero deviation indicated sigma meter is nulled on sigma meter.

(0 deviation).

[ SAT ] [ UNSAT ]

Page 7 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP ELEMENT STANDARD 20 Verify trip units are RESET, AI-31D then remove the Bypass Keys Trip Units 1, 9 and 12 not for Trip Units 1, 9 and 12. bypassed with keys removed.

[ SAT ] [ UNSAT ]

21 Exit Technical Specification CUE: Another Operator has LCO 2.15, for trip units 1, 9 and logged out of the Technical

12. Specification.

[ SAT ] [ UNSAT ]

22 Repeat Step 7.13 for all Determined that Channel "D" channels to be adjusted. was the only channel that needed to be adjusted.

[ SAT ] [ UNSAT ]

23 Record channels Final AI-31A/B/C/D NUCLEAR PWR CALIBRATE Record Final NUCLEAR PWR Dial settings on Test Data CALIBRATE Dial settings for Sheet 1. channels A and D.

[ SAT ] [ UNSAT ]

24 Record channels Final T AI-31A/B/C/D PWR CALIBRATE Dial settings Record Final T PWR on Test Data Sheet 1. CALIBRATE Dial settings for channels A and D.

[ SAT ] [ UNSAT ]

25 Record channels FINAL T AI-31A/B/C/D Power readings on Test Data Record Final T Power Sheet 1. readings for channels A and D.

[ SAT ] [ UNSAT ]

Page 8 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM Title: RPS Power Adjustment STEP ELEMENT STANDARD 26 Record channels FINAL NI AI-31A/B/C/D Power readings on Test Data Record Final T Power Sheet 1. readings for channels A and D.

[ SAT ] [ UNSAT ]

CUE: Another Operator will complete this test for channels B and C.

Termination Criteria: RPS channel 'D" NI Power and T Power have been adjusted to agree with XC-105 per OP-ST-RPS-0005.

Page 9 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 INITIAL The plant is operating at full power.

CONDITIONS: Secondary Calorimetric measurement, XC-105, indicates the reactor is operating at 1497.5 MWt.

The STA has verified XC-105 is valid.

The prerequisites for OP-ST-RPS-0005. RPS POWER ADJUSTMENT, have been met.

INITIATING CUE: You have been directed to perform OP-ST-RPS-0005, RPS POWER ADJUSTMENT, for channels A and D, and adjust any channels that need adjustment.

Page 10 of 10

PAGE 1 OF 8 Fort Calhoun Station Unit No. 1 OP-ST-RPS-0005 SURVEILLANCE TEST RPS POWER ADJUSTMENT Change No. EC 42242 Reason for Change Added a precaution addressing the fluctuating RPSCIP DVM readings. Converted from WordPerfect to Word.

Requestor R. Lowery Preparer L Hautzinger Issue Date 07-17-08 3:00 pm R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 2 OF 8 RPS POWER ADJUSTMENT SAFETY RELATED

1. PURPOSE 1.1 Instructions for adjusting T and NI Power indication.

1.2 This test in conjunction with OP-ST-SHIFT-0001 satisfies the requirements of Technical Specifications, Section 3.1, Table 3-1, Item 1.b.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:
  • 2.15, Table 2-2, Items 2, 3 and 9
  • 3.1, Table 3-1, Item 1.a., Channel Check
  • 3.1, Table 3-1, Item 1.b., Channel Adjustment 2.2 SO-G-23, Surveillance Test Program 2.3 OI-NI-1, Nuclear Instrumentation System Normal Operation
3. DEFINITIONS None
4. TEST EQUIPMENT None
5. PRECAUTIONS AND LIMITATIONS 5.1 All anomalies and deficiencies shall be reported immediately to the immediate Supervisor and the Shift Manager, and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

5.2 The System Engineer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of this test, of any marginal, unexpected or unacceptable results.

5.3 This Surveillance Test is performed on demand as necessary to provide for the adjustment of indicated RPS power.

5.4 This Surveillance Test is not required during Reactor Startup or Shutdown periods which includes Power Operation less than 25%.

R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 3 OF 8 5.5 Prior to making adjustments with power levels below 50% the Reactor Engineer or Manager-Operations is to be contacted for concurrence.

5.6 The Reactor Engineer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of this test of any marginal, unexpected, or unacceptable results.

5.7 RPS Trip Units may be bypassed per the following Limiting Conditions for Operation (LCO):

  • Technical Specifications, Section 2.15, Table 2-2, Items 2, 3 and 9 5.8 RPSCIP DVM readings fluctuate, the operator should record a best estimate average of the fluctuating values for NI and DELTA T power. Recording NI or DELTA T power when the NI - DELTA T deviation meter reads zero is not an accurate way of determining the best estimate average for either reading. (CR 2007-4657)
6. PREREQUISITES INITIALS/DATE 6.1 Procedure Revision Verification:

12 JEK 3/31/09 Revision No. /

JEK 6.2 Reactor power is greater than 25% and stable. / 3/31/09 CAUTION Careful consideration is required prior to adjusting the channels with lower -T power reading lower than actual power due to a flow stream anomaly. This is to ensure that -T power indication will not be excessively high in the event that the anomaly clears after adjustment is made.

6.3 IF a flow stream anomaly was confirmed AND plant conditions have stabilized, THEN the concurrence between the Manager Operations and Supervisor-Primary Systems is required prior to adjusting -T N/A power. /

Manager-Ops N/A /

Sup-Primary Sys 6.4 IF Reactor power is less than 50%, THEN notify the Reactor Engineer N/A or Manager-Operations for concurrence on performing adjustments. /

6.5 No other test is in progress which could potentially affect this test, or if JEK 3/31/09 this test were performed, could have an effect on that test. /

R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 4 OF 8 6.6 Shift Manager authorizes performance of this test:

SHIFT MANAGER Shift Manager Date/Time 3/31/09 / 0730

7. PROCEDURE INITIALS 7.1 Record all four (4) Channel T Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range Safety Drawers.

7.2 Record all four (4) Channel NI Scaling Amp Offsets from the RPS Scaling Amplifier Offset Measurement Record (Control Room File drawer) on Test Data Sheet 1 and verify the Scaling Amp Offset values on the Power Range Safety Drawers.

7.3 Record all four (4) channels Initial T Power readings from RPSCIP DVM on Test Data Sheet 1.

7.4 Record all four (4) channels Initial NI Power readings from RPSCIP DVM on Test Data Sheet 1.

7.5 Subtract the Scaling Amp Offset from Initial T Power reading for all four (4) channels and record on Test Data Sheet 1.

7.6 Subtract the Scaling Amp Offset from the Initial NI Power reading for all four (4) channels and record on Test Data Sheet 1.

7.7 Record all four (4) channels Initial T Pwr Calibrate and Nuclear Pwr Calibrate dial (Power Range Monitor Drawer) settings on Test Data Sheet 1.

7.8 Perform the following for each RPS channel to be adjusted. A B C D 7.8.1 Place RPSCIP DVM Meter Input Switch to METER INPUT position. [ ] [ ] [ ] [ ]

7.8.2 Push +10V pushbutton and verify DVM reads +9.800 to

+10.200V. [ ] [ ] [ ] [ ]

7.8.3 Push -10V pushbutton and verify DVM reads -9.800 to

-10.200V. [ ] [ ] [ ] [ ]

7.8.4 Push ZERO pushbutton and verify DVM reads -0.200 to

+0.200V. [ ] [ ] [ ] [ ]

R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 5 OF 8 7.9 Verify XC105 Is valid. STA STA 7.10 Ensure all XC105 inputs have either an active scan status or a conservative value input per RE-CPT-RX-0003. STA STA 7.11 IF XC105 input has been removed from scan, THEN ensure a conservative N/A input for current plant conditions has been input per RE-CPT-RX-0003.

STA N/A SM 7.12 Record the current value of thermal power (XC105) and calculate the Thermal Power on Test Data Sheet 1.

NOTE: RPS Channels may be adjusted in any order, but only one channel may be done at a time.

7.13 Adjust one RPS Channel by performing the following: A B C D 7.13.1 Enter Technical Specification Limiting Condition for Operation 2.15, Table 2-2, Items 2, 3 and 9 for RPS Trip Units 1, 9 and 12. [ ] [ ] [ ] [ ]

7.13.2 Bypass trip units 1, 9 and 12. [ ] [ ] [ ] [ ]

7.13.3 Place the DVM selector switch to NUCLEAR PWR. [ ] [ ] [ ] [ ]

CAUTION Ensure the Nuclear Pwr Calibrate Potentiometer is used, not the Subchannel Gain Adjust Potentiometer.

7.13.4 Adjust the Power Range Monitor NUCLEAR PWR CALIBRATE potentiometer until the DVM equals the Thermal Power plus the NI Scaling Amp Offset. [ ] [ ] [ ] [ ]

7.13.5 Place the DVM selector switch to T PWR. [ ] [ ] [ ] [ ]

7.13.6 Adjust T PWR CALIBRATE potentiometer until the NUCLEAR PWR-T PWR (%) sigma meter is nulled (0 deviation). [ ] [ ] [ ] [ ]

7.13.7 Verify trip units are RESET, then remove the Bypass Keys for Trip Units 1, 9 and 12. [ ] [ ] [ ] [ ]

R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 6 OF 8 7.13.8 Exit Technical Specification LCO 2.15, for trip units 1, 9 and

12. [ ] [ ] [ ] [ ]

7.14 Repeat Step 7.13 for all channels to be adjusted. [ ] [ ] [ ] [ ]

7.15 Record all four (4) channels Final NUCLEAR PWR CALIBRATE Dial settings on Test Data Sheet 1. [ ] [ ] [ ] [ ]

7.16 Record all four (4) channels Final T PWR CALIBRATE Dial settings on Test Data Sheet 1. [ ] [ ] [ ] [ ]

7.17 Record all four (4) channels FINAL T Power readings on Test Data Sheet 1. [ ] [ ] [ ] [ ]

7.18 Record all four (4) channels FINAL NI Power readings on Test Data Sheet 1. [ ] [ ] [ ] [ ]

Completed by Date/Time /

8. RESTORATION 8.1 Shift Manager notified this test is completed:

Shift Manager Date/Time /

9. ACCEPTANCE CRITERIA 9.1 Corrected RPS T Power and corrected RPS NI Power differ from the calculated %

Rated Power (Core Thermal Power) by less than 1%.

10. TEST RECORD 10.1 This entire procedure.
11. REVIEW 11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following completion of this test.

Evaluated by Date/Time /

STA Reviewed by Date/Time /

Shift Manager R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 7 OF 8 Test Data Sheet 1 - Calibration Record Thermal Power = ÷ 15 =  %

(XC105)

Parameter AI-31A AI-31B AI-31C AI-31D Initial NI Power (DVM)

NI Scaling Amp Offset Initial NI Power, DVM minus scaling amp offset Initial NUCLEAR PWR CALIBRATE Dial Setting Final NUCLEAR PWR CALIBRATE Dial Setting Final NI Power (DVM)

Initial T Power (DVM)

T Scaling Amp Offset Initial T Power, DVM minus scaling amp offset Initial T PWR CALIBRATE Dial Setting Final T PWR CALIBRATE Dial Setting Final T Power (DVM)

R12

FORT CALHOUN STATION OP-ST-RPS-0005 SURVEILLANCE TEST CONTINUOUS USE PAGE 8 OF 8 Comment Sheet R12

RPS Scaling Amp Offset Measurement Record.

CHANNEL A B C D NI Power Scaling Amp 0.2 0.3 0.3 0.2 Offset Delta T Power Scaling 0.3 0.2 0.3 0.3 Amp Offset

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-2 Revision: 3 Examiners: _________________________ Operators: _________________________

_________________________ _________________________

_________________________ _________________________

Initial Conditions: 100% Power DG-1 Out of Service replacing contactors for 2CR relays.

Turnover: Rotate Condenser Evacuation Pumps, then rotate Containment Cooling Units.

Event Malf Event Event No. No. Type* Description 1 N-BOPO Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment (2 min) 3.

2 N-ATCO Rotate Containment Cooling Units In accordance with OI-VA-1.

(10 min) 3 C-ATCO Dropped CEA - Tech Spec Entry.

LE CUE C-BOPO 4 R-ATCO AOP-05 shutdown to 70% Power.

N-BOPO 5 I-ATCO Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails LE CUE High.

6 C-BOPO Loss of 161 KV - Tech Spec Entry.

LE CUE 7 C-ATCO Another Dropped CEA - Manual Reactor Trip Required.

LE CUE 8 M-ALL Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 5
2. Malfunctions after EOP entry (1-2) 1
3. Abnormal events (2-4) 3
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 2

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 1 Page 2 of 13 Event

Description:

Rotate Condenser Evacuation Pumps per OI-CE-1, Attachment 3.

Time Position Applicants Actions or Behavior BOPO Obtain copy of OI-CE-1, Attachment 3, Normal Rotation of Condenser Evacuation Pumps.

BOPO Read Notes on page 12 of procedure.

BOPO Direct EONT to ensure Seal Water Makeup is properly aligned:

FW-1351, Separator Tanks Condensate Seal Water Supplu Isolation Valve is Open FW-1349, Vacuum Pumps Separator Tanks Supply Header Isolation is Open DW-357 Condenser Vacuum Pumps Seal Water Supply Line Isolation Valve is Closed.

BOPO Direct EONT to ensure Separator Tank level is within the gage glass and at least 8 inches.

BOPO Start Condenser Evacuation Pump, FW-8C.

Note: ammeter will remain pegged for a relatively long time. This is normal.

BOPO Verify proper operation of FW-8C.

BOPO Direct EONT to throttle open VD-333, FW-43 Makeup Float bypass valve.

BOPO Stop FW-8A by placing control switch in AFTER STOP.

BOPO Direct EONT to close VD-317, FW-41 Makeup Float bypass valve.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 2 Page 3 of 13 Event

Description:

Rotate Containment Cooling Units.

Time Position Applicants Actions or Behavior CRS Direct ATCO to place VA-3B in service and shutdown VA-7D in accordance with OI-VA-1, Attachment 1, step 2 and Attachment 2, step 4 .

(Start B shut down D following maintenance)

ATCO Obtain a copy of OI-VA-1, Attachments 1 and 2.

ATCO Momentarily place HCV-401B/D to OPEN.

ATCO Ensure HCV-401C is closed.

ATCO Momentarily place HCV-401A/C to CIRC.

ATCO Throttle open HCV-401C maintaining CCW discharge header pressure at least 70 psig.

ATCO Monitor:

FI-417, VA-1B flow TIC-421, VA-1B temperature PI-499, CCW Discharge Header Pressure TIC-2800, CCW Discharge header temperature TI-717 Fan VA-3B outlet temperature ATCO Start VA-3B and monitor:

VA-3B Current PIC-701, Fan VA-3B DP PI-707 , Fan VA-3B filter DP PI-709, Fan VA-3B Cooling Coil DP TI-717 Fan VA-3B outlet temperature ATCO Stop VA-7D ATCO Throttle close HCV-403C maintaining CCW discharge header pressure less than 125 psig ATCO Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3,A1,A1-U) in alarm ATCO Momentarily place HCV-403A/C to ISOL ATCO Momentarily place HCV-403B/D to CLOSE

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 3 Page 4 of 13 Event

Description:

Dropped CEA - Tech Spec Entry.

Time Position Applicants Actions or Behavior ATCO Identify event from Dropped Rod and other alarms (CB-4 A20 E6, CB-4 A8 A5L, B1U, B1L, B2L, B5L, C1U, C2U, C5L).

ATCO Determine that only one rod has dropped (rod #1, grp 4).

CRS Enter AOP-02 (CEA AND CONTROL SYTEM MALFUNCTIONS),

Section III (Misaligned Group 4 CEA).

CRS Read Caution and Notes. (May be performed after stabilizing plant.)

CRS Direct ATCO to stop all CEA movement.

CRS Direct BOP Operator to adjust turbine load to match reactor power.

BOPO Reduce turbine load to match reactor power using T-cold indication.

CRS Direct ATC to control pressurizer pressure (2075-2150 psia) and level (within 2% of programmed value).

ATCO Control pressurizer pressure (2075-2150 psia) and level (within 2% of programmed value).

ATCO Reset Charging Pump Bistables if needed to shutdown a Charging Pump that started automatically.

CRS Direct ATC Operator to reset rod drop bistables.

ATCO Reset rod drop bistables on:

RPS Linear Power Channels Power Range Control Channels CRS Notify System Operations of the power reduction.

CRS Notify Work Week Manager or Reactor Engineer.

Continued on Next Page

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 3 Page 5 of 13 Event

Description:

Dropped CEA - Tech Spec Entry, continued Time Position Applicants Actions or Behavior CRS LCO 2.10.2(4)e. - One full length CEA misaligned from any other CEA's in (TS) its group by 18 inches or more.

Required Actions:

Reactor power must be reduced to less than 70% within one hour.

The CEA must be realigned or declared inoperable within one hour following the power reduction.

If the CEA is declared inoperable, the reactor must be in hot shutdown within an additional 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

CRS Inform ATC and BOP operators that Tech Specs and AOP-02 require a power reduction to less than 70% within one hour using boration.

CRS If Pressurizer pressure lowers to 2075 psia or less, then enter Technical Specification LCO 2.10.4(5) - DNBR Margin During Power Operation Above 15% of Rated Power.

Required Actions:

Restore Pressurizer Pressure greater than or equal to 2075 psia within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Or else, reduce power to less than 15% within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 4 Page 6 of 13 Event

Description:

AOP-05 Emergency Shutdown to 70% Power.

Time Position Applicants Actions or Behavior CRS Direct ATCO and BOPO to commence a power reduction using AOP-05.

CRS Read AOP-05 Notes on page 3 CRS Direct ATCO to begin boration from the SIRWT ATCO Begin boration by:

Ensuring one charging pump running Opening LCV-218-3,"Charging Pump Suction SIRWT Isolation Valve" Closing LCV-218-2, "VCT Outlet Valve" CRS Notify System Operations that power will be reduced.

BOPO Reduce turbine load using potentiometer as needed to control RCS T-cold per TDB Figure III.1, "T-ave Program."

ATCO/ Monitor and control RCS parameters during power reduction:

BOPO T-cold 527-545°F Pressurizer Level 45-60%

ATCO Maximize heaters and spray by placing each control switch in ON:

225 KW Backup Htrs Bank 1 Group 1/2/3 150 KW Backup Htrs Bank 2 Group 4/5 150 KW Backup Htrs Bank 3 Group 8/9 225 KW Backup Htrs Bank 4 Group 10/11/12 ATCO Adjust the selected Pressurizer Pressure controller setpoint pushbuttons to maintain 2100 psia, if required.

CRS Direct the shift chemist to prepare to sample the RCS due to the power (TS) reduction.

NOTE: Technical Specification 3.2 (Table 3-4) requires a sample be taken between 2-8 hours following a power change exceeding 15% power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. The sample must be analyzed for Dose Equivalent I-131.

ATCO May contact the Aux Building Operator to verify sufficient Waste Holdup Tank capacity for power reduction.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 5 Page 7 of 13 Event

Description:

Controlling Pressurizer Pressure Transmitter, PT-103Y, Fails High.

Time Position Applicants Actions or Behavior ATCO Respond to Pressurizer Pressure Off-Normal HI/LO Channel Y Alarm.

(CB-1,2,3/A4 B4)

ATCO Identify and report high indication on controlling channel and lowering pressure on other channel.

ATCO/ Refer to ARP.

BOPO CRS Direct ATCO to transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure.

ATCO Transfer pressurizer pressure control to channel X or take manual control of pressurizer pressure, as directed.

ATCO Monitor and control pressurizer pressure.

CRS Notify Work Week Manager of the instrument failure.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 6 Page 8 of 13 Event

Description:

Loss of 161 KV - Tech Spec Entry.

Time Position Applicants Actions or Behavior BOPO Identify loss of 161 KV from numerous alarms on CB-20. (CB-20 A15 A1, A2, A3, D5) (CB-20 A17 A2, C4, D2) Determine and report that busses 1A3 and 1A4 have fast transferred and are powered.

CRS Enter AOP-31, section II All 4160 busses fed from 22 KV Read Notes.

CRS/ Verify 2 FW pumps, 2 Condensate pumps and 2 Heater drain pumps BOPO operating.

CRS/ Ensure Main Generator Terminal voltage less than 22,000 volts.

BOPO CRS/ Establish balanced 4160V Bus loading on T1A1 and T1A2 by ensuring all BOPO of the following pumps are operating:

FW-2A, Condensate Pump FW-4A, Feed Pump FW-5A, Heater Drain Pump BOPO starts Heater Drain Pump, FW-5A CRS/ Verify 480 bus voltages greater than 430 volts BOPO CRS Direct BOPO to match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 BOPO Match flags on breakers 110, 111, 1A31, 1A33, 1A42, 1A44 (step 5 of AOP-31)

CRS Direct that signs be placed at entrances to switchgear rooms Review EOP-02, EOP-07 and EOP-20 Continued on Next Page

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 6 Page 9 of 13 Event

Description:

Loss of 161 KV - Tech Spec Entry., Continued.

CRS LCO 2.7(2)c.- Loss of both service transformers T1A-3 and T1A-4 (TS) inoperable due to a loss of the 161 KV incoming line.

Required Actions:

Verify both Diesel Generators are Operable.

Notify the NRC Operations center within four hours due to the loss of 161 KV.

Special Report must be submitted to the NRC within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

LCO 2.0.1 - LCO action requirement cannot be met Due to the loss of 161 KV and D/G-1 being inoperable, Tech Spec 2.0.1 must be entered.

Required Actions:

Place the plant in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

However, taking the main generator off-line will result a loss of offsite power.

CRS Report situation to station management.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 7 Page 10 of 13 Event

Description:

Another Dropped CEA - Manual Reactor Trip Required.

Time Position Applicants Actions or Behavior ATCO Report that another CEA has fallen into the core.

CRS Direct ATCO to trip the reactor.

ATCO Manually trip the reactor within 60 seconds of the second CEA drop.

(CT)

CRS Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.

ATCO Perform Reactivity Control Actions:

Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met.

BOPO Verify Turbine Tripped:

Stop and Intercept Valves are Closed BOPO Verify Generator Breakers Tripped:

Breakers 3451-4/5 Generator Field Breaker BOPO Verify vital buses, 1A3 and 1A4, are energized.

Reports buses 1A3 and 1A4 are deenergized Directs EONT to Minimize DC loads per EOP/AOP Attachment 6 Reports that DG-2 is running but output breaker is open. DG-1 is out for maintenance BOPO IF SIAS has initiated, THEN verify both Diesel Generators have started.

BOPO Verify non-vital buses, 1A1 and 1A2, are energized.

Reports buses 1A1 and 1A2 are deenergized.

BOPO Verify both 125VDC buses are energized.

BOPO Verify Instrument air status:

Instrument Air pressure is at least 90 psig At least 1 air compressor running Reports that no compressors are running a IA pressure is lowering.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 7 Page 11 of 13 Event

Description:

Another Dropped CEA - Manual Reactor Trip Required, Continued.

Time Position Applicants Actions or Behavior ATCO Verify CCW and Raw water status:

At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open.

Reports that no CCW or Raw Water Pumps are operating.

ATCO Verify Inventory Control:

Pressurizer Level 30-70% trending toward 45-60%

Subcooling, at least 20°F ATCO Verify Pressure Control:

RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO Verify Core Heat Removal:

RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10°F Reports that no RCPs are operating.

BOPO Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):

Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%

No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF Close blowdown isolation valves, HCV-1387A/B and HCV-1388A/B Reports that No FEED Pumps or Condensate Pumps are operating.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 7 Page 12 of 13 Event

Description:

Another Dropped CEA - Manual Reactor Trip Required, Continued.

Time Position Applicants Actions or Behavior BOPO Verify Steam Dump and Bypass Valves are controlling BOTH of the following:

T-cold 525-535°F S/G Pressure 850-925 psia Reports that Steam Dump and Bypass valves are not operating.

Controls S/G pressure using HCV-1040 or MS-291 and MS-292 as needed.

ATCO Verify containment conditions:

No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120°F CRS If bus 1A4 is repowered, then enter EOP-02, "LOSS OF OFFSITE POWER, LOSS OF FORCED CIRCULATION,"

If bus 1A4 is not powered, then enter EOP-07, "STATION BLACKOUT"

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-2 Revision: 3 Event No.: 8 Page 13 of 13 Event

Description:

Circulating Water Pump, CW-1C, Breaker fails to open preventing DG from loading onto bus 1A4 - Station Blackout.

Time Position Applicants Actions or Behavior BOPO Report that CW-1C breaker failed to trip within 15 minutes of reactor trip.

(CT) (This prevents D/G-2 breaker from closing) Direct EONT to manually trip the breaker for CW-1C.

(NOTE: EONT will trip breaker on Lead Examiner CUE).

CRS When D/G-2 output breaker closes, Direct BOPO to verify bus 1A4 voltage.

CRS If EOP-07 was entered, Transitions to EOP-02, "

Scenario ends when EOP-02 has been entered.

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 Days Nights X PLANT STATUS:

MODE: 1 X 2 3 Rx Power: 98.60% Rod Position: All Groups ARO Prcs (>2075 psia): 2091 psia Tcold (<543°F): 542.8 °F Lpzr (48 - 60%): 60 % (Actual)

Comments:

SAFEGUARDS STATUS:

(Log any out-of-service safeguards equipment; include major fire protection equipment)

DG-1 RECENT TEMP MODS: (Within the last month)

TM Number Date Description None DEGRADED EQUIPMENT STATUS CR Number Component/System Reason Considered Degraded Resolution 2009003571 DG-1 Out of Service - Replacing contactors for 2CR relays.

SO-O-1 FC/FORM Page 1 of 3

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 RELEASES IN PROGRESS: YES NO RELEASE #

Monitor Tank: A B X Waste Gas Decay Tank: A B C D X

.

Containment Pressure Reduction X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:

PROCEDURE or TEST REASON None CRS review and discuss procedures in progress (Initial)

INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):

ITEM / LOCATION DATE ACTION REQUIRED None TEMPORARY LIFTS:

TAGOUT # EQUIPMENT REASON None POST MAINTENANCE TESTING:

(Equipment, instrument or annunciator requiring PMT for operability)

AVAILABLE Component YES NO PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:

REPORT MADE EQUIP OOS DATE/TIME T.S. / ODCM / G-103 LCO YES NO N/A DG-1 3/31/2009 / 0540 TS 2.7(2)j 7 Day X SO-O-1 FC/FORM Page 2 of 3

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 REMARKS:

  • Rotate Condenser Evacuation Pumps, FW-8C on and FW-8A Off per OI-CE-1, Attachment 3.
  • Place VA-3A in service then shut down VA-7D per OI-VA-1, Attachments 1 and 2.
  • RCS Boron 998 ppm Neutral Blend (gal acid /gal water)10 / 55 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________

Off going On coming S.M.

C.R.S.

L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator ____

Security Key Transferred (Init)

SO-O-1 FC/FORM Page 3 of 3

FORT CALHOUN STATION FC-75A FORM R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 03/31/09 Shift (Circle one) 0600-1800 1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.

Switch Location Annunciators in Alarm Reason out-of-position/in alarm 43-1/D1 AI-30A DG-1 Out of Service 43-1/1AD1 AI-30A '

BKR 1AD1 CB-20 '

AI-30A/A30,B-4 DIESEL OFF AUTO '

AI-30A/A30,D-4 BKR OFF AUTO '

AI-30A/A30,E-3 BKR PROTECTION OFF-AUTO '

AI-30A/A30, E-4 PANEL TROUBLE '

CB-1,2,3/A1 B-1U CC WATER FROM COIL VA_1B NO FLOW VA-1B is not operating PROTECTED EQUIPMENT SIGN LOCATION REASON PROTECTED DG-2 DG-2 Mode Selector Switch DG-1 Out of Service BRKR 1AD2

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 5 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PREREQUISITES (9) INITIALS

1. Procedure Revision Verification JEK Revision No. 68 Date: 3/31/09
2. OI-VA-1-CL-A has been completed per OP-1. JEK
3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment Cooling Coils is operable:
  • VA-1A X
  • VA-1B X JEK
4. Electrical power is available to the desired fan(s):
  • VA-3A, Cont Cooling & Filter Fan, 1B3A-7 X
  • VA-3B, Cont Cooling & Filter Fan, 1B4C-8 X JEK R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 6 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (9) INITIALS NOTES

1. Containment HEPA/Charcoal Filter Unit may be in service while painting or other activities in containment as long as volatile organic compound (VOC) to be released in containment does not exceed administrative limits specified in GM-RR-MX-1050. The administrative limits given in the coating procedure is determined to have negligible affect on filter performance.
2. HCV-724A, VA-3A Filtered Air Inlet Damper is permanently open and HCV-724B, VA-3A Unfiltered Air Inlet Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.

CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)

1. IF VA-3A, Containment Vent Fan, is to be started, THEN perform the following:
a. IF Containment Cooling is desired, THEN initiate CCW to VA-1A as follows:
1) Momentarily place HCV-400B/D, Cntmt Clg Coil VA-1A AC Vlvs Control SW to OPEN.
2) Ensure HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr is closed.
3) Momentarily place HCV-400A/C, Cntmt Clg Coil VA-1A Isol Vlvs Control SW to CIRC.
4) Throttle open HCV-400C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 7 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued) (9) INITIALS 1.a

5) Monitor the following parameters:
  • FI-416, VA-1A Flow
  • TIC-420, VA-1A Temp
  • TI-715, Fan VA-3A Outlt Temp (AI-44)

CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.

b. Start VA-3A and monitor the following:
  • VA-3A amps
  • PIC-700, Fan VA-3A Diff Press (AI-44)
  • PI-706, Fan VA-3A Filter Diff Press (AI-44)
  • PI-708, Fan VA-3A Clg Coil Diff Press (AI-44)
  • TI-715, Fan VA-3A Outlt Temp (AI-44)

NOTE HCV-725A, VA-3B Filtered Air Inlet Damper is permanently open and HCV-725B, VA-3B Unfiltered Air Inlet Damper is permanently closed which puts filters in service (EC 41115). Control Solenoids are AIPE.

2. IF VA-3B, Cntmt Vent Fan, is to be started, THEN perform the following:
a. IF Containment Cooling is desired, THEN initiate CCW to VA-1B as follows:
1) Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B AC Vlvs Control SW to OPEN.
2) Ensure HCV-401C, Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr is closed.

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 8 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued) (9) INITIALS 2.a.

3) Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to CIRC.
4) Throttle open HCV-401C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
5) Monitor the following parameters:
  • FI-417, VA-1B Flow
  • TIC-421, VA-1B Temp
  • TI-717, FAN VA-3B Outlet Temp (AI-44)

CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.

b. Start VA-3B and monitor the following:
  • VA-3B amps
  • PIC-701, Fan VA-3B Diff Press (AI-44)
  • PI-707, Fan VA-3B Filter Diff Press (AI-44)
  • PI-709, Fan VA-3B Clg Coil Diff Press (AI-44)
  • TI-717, Fan VA-3B Outlt Temp (AI-44)
3. IF VA-3A is to be shutdown, THEN perform the following:
a. Stop VA-3A, Cntmt Vent Fan. (AI-30A)
b. IF CCW flow to the cooler is to be secured, THEN isolate CCW to VA-1A as follows: (CB-1/2/3)
1) Throttle close HCV-400C, Cntmt Clg Coil VA-1A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 9 OF 173 Continuous Use Attachment 1 - Containment Cooling and Filtering Operation VA-3A & VA-3B PROCEDURE (continued) (9) INITIALS 3.b.

2) Verify CC WATER FROM VA-1A NO FLOW (CB-1,2,3, A1, A-1U) in alarm.
3) Momentarily place Cntmt Clg Coil VA-1A Isol Vlvs Control SW HCV-400A/C to ISOL.
4) Momentarily place Cntmt Clg Coil VA-1A Vlvs Control SW HCV-400B/D to CLOSE.
4. IF VA-3B is to be shutdown, THEN perform the following:
a. Stop VA-3B, Cntmt Vent Fan (AI-30B).
b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-1B as follows:
1) Throttle close Cntmt Clg Coil VA-1B Outlt Isol Vlv Cntrlr HCV-401C maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
2) Verify CC WATER FROM VA-1B NO FLOW (CB-1,2,3, A1, B-1U) in alarm.
3) Momentarily place HCV-401A/C, Cntmt Clg Coil VA-1B Isol Vlvs Control SW to ISOL.
4) Momentarily place HCV-401B/D, Cntmt Clg Coil VA-1B Vlvs Control SW to CLOSE.
5. Record filter operating times in OP-ST-SHIFT-0001.

Completed by Date/Time /

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 10 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PREREQUISITES (9) INITIALS

1. Procedure Revision Verification:

Revision No. 68 Date: 3/31/09 JEK

2. OI-VA-1-CL-A has been completed per OP-1. JEK
3. IF Containment Cooling is desired, THEN CCW is in service and at least one of the following Containment Cooling Coils is operable:
  • VA-8A X X JEK
  • VA-8B
4. Electrical power is available to the desired fan(s):
  • VA-7C, Containment Air Cooling Fan, 1B3C-4C-3 X
  • VA-7D, Containment Air Cooling Fan, 1B3B-4B-4 X JEK PROCEDURE CAUTION During Power Operations either VA-3A and VA-7C OR VA-3B and VA-7D must be maintained operable. (SAO 07-003 and CR 2007-3052)
1. IF VA-7C, Cntmt Vent Fan, is to be started, THEN perform the following:
a. IF Containment Cooling is desired, THEN initiate CCW to VA-8A as follows:
1) Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A AC Vlvs Control SW to OPEN.
2) Ensure HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr is closed.
3) Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to CIRC.

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 11 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (9) INITIALS 1.a.

4) Throttle open HCV-402C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.
5) Monitor the following parameters:
  • FI-418, VA-8A Flow
  • TIC-422, VA-8A Temp
  • TIC-2800, CCW Discharge Header Temp CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
b. Start VA-7C and monitor the following (AI-30A):
  • VA-7C amps
  • PIC-702, Fan VA-7C Diff Press (AI-44)
  • PI-710, Fan VA-7C Clg Coil Diff Press (AI-44)
  • TI-719, Fan VA-7C Outlt Temp (AI-44)
2. IF VA-7D, Cntmt Vent Fan, is to be started, THEN perform the following:
a. IF Containment Cooling is desired, THEN initiate CCW to VA-8B as follows:
1) Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B AC Vlvs Control SW to OPEN.
2) Ensure HCV-403C, Cntmt Clg Coil VA-8B OUTLT Isol Vlv Cntrlr is closed.
3) Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to CIRC.
4) Throttle open HCV-403C maintaining PI-499, CCW Discharge Header Pressure, greater than or equal to 70 psig.

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 12 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (9) INITIALS 2.a.

5) Monitor the following parameters:
  • FI-419, VA-8B Flow
  • TIC-423, VA-8B Temp
  • TIC-2800, CCW Discharge Header Temp CAUTION Running a fan for an extended period with the CCW isolated to the cooling coil can cause the water to heatup inside the coil and possibly lift or cause the reliefs to weep.
b. Start VA-7D and monitor the following (AI-30B):
  • VA-7D amps
  • PIC-703, Fan VA-7D Diff Press (AI-44)
  • PI-711, Fan VA-7D Clg Coil Diff Press (AI-44)
  • TI-721, Fan VA-7D Outlt Temp (AI-44)
3. IF VA-7C, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
a. Stop VA-7C (AI-30A).
b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8A as follows:
1) Throttle close HCV-402C, Cntmt Clg Coil VA-8A Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
2) Momentarily place HCV-402A/C, Cntmt Clg Coil VA-8A Isol Vlvs Control SW to ISOL.
3) Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A Vlvs Control SW to CLOSE.

R68

FORT CALHOUN STATION OI-VA-1 OPERATING PROCEDURE C PAGE 13 OF 173 Continuous Use Attachment 2 - Containment Cooling Operation VA-7C & VA-7D PROCEDURE (continued) (9) INITIALS

4. IF VA-7D, Cntmt Vent Fan, is to be shutdown, THEN perform the following:
a. Stop VA-7D (AI-30B).
b. IF CCW Flow to the cooler is to be secured, THEN isolate CCW to VA-8B as follows:
1) Throttle close HCV-403C, Cntmt Clg Coil VA-8B Outlt Isol Vlv Cntrlr maintaining PI-499, CCW Discharge Header Pressure, less than 125 psig.
2) Momentarily place HCV-403A/C, Cntmt Clg Coil VA-8B Isol Vlvs Control SW to ISOL.
3) Momentarily place HCV-403B/D, Cntmt Clg Coil VA-8B Vlvs Control SW to CLOSE.

Completed by Date/Time /

R68

FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 11 OF 22 C

Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PREREQUISITES  % INITIALS

1. Procedure Revision Verification:

Revision No. 24 Date: 3/31/09 JEK

2. Power is available for the selected condenser evacuation pump:

! FW-8A, Condenser Evacuation Pump, 1B3B-7

! FW-8B, Condenser Evacuation Pump, 1B4A-4

! FW-8C, Condenser Evacuation Pump, 1B3B-4B-2 X JEK R24

FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 12 OF 22 C

Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE  % INITIALS NOTES

1. The order of pump rotation is A-B-C.
2. Seal Water Makeup can be supplied from the Condensate System or the Demineralized Water System as follows:
a. DW-357, Condenser Vacuum Pumps, FW-8A-8C Seal Water Supply Line Isolation Valve

! Normally used during startup (Pumps DW-40A/B must be running)

b. FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve

! Normally used after a Condensate Pump is started

c. FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve

! Normally used as a backup if the Condensate Storage Tank is full

1. IF a Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.

! FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve, is open

! FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve, is open

! DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line Isolation Valve (Col. B-5), is closed R24

FORT CALHOUN STATION OI-CE-1 OPERATING INSTRUCTION PAGE 13 OF 22 C

Continuous Use Attachment 3 - Normal Rotation of Condenser Evacuation Pumps PROCEDURE (continued)  % INITIALS

2. IF no Condensate Pump is running, THEN ensure Seal Water Makeup is aligned as follows.

! FW-1351, Separator Tanks FW-41, 42 & 43 Condensate Seal Water Supply Isolation Valve, is closed

! FW-1349, Vacuum Pumps FW-8A-8C Separator Tanks FW-41-43 Supply Header Isolation Valve, is closed

! DW-357,Condenser Vacuum Pumps FW-8A-8C Seal Water Supply Line Isolation Valve (Col. B-5), is open

3. Ensure that the Separator Tank level reads within the gauge glass and at least eight inches prior to starting the Condenser Evacuation Pump.
4. Start the Standby Condenser Evacuation Pump (CB-10/11).
5. Verify proper operation of the Condenser Evacuation Pump started.

NOTE Condenser Evacuation Separator Tanks are continuously overflowed to minimize the build up of Ammonia in the system.

6. Commence continuous feed and bleed of the Condenser Evacuation Separator Tank by throttling open the bypass valve:

! VD-317, Separator Tank FW-41 Makeup Float Bypass Valve (FW-8A)

! VD-325, Separator Tank FW-42 Makeup Float Bypass Valve (FW-8B)

! VD-333, Separator Tank FW-43 Makeup Float Bypass Valve (FW-8C)

7. Place the control switch for the Condenser Evacuation Pump being placed in Standby in AFTER STOP (CB-10/11).
8. Stop the continuous feed and bleed of the Condenser Evacuation Separator Tank for the Condenser Evacuation Pump being placed in Standby by closing the bypass valve:

! VD-317

! VD-325

! VD-333 Completed by Date/Time /

R24

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-4 Revision: 5 Examiners: _________________________ Operators: _________________________

_________________________ _________________________

_________________________ _________________________

Initial Conditions: 50% Power, Diesel Driven AFW Pump, FW-54, Out of Service, Main Feed Pumps, FW-4A and FW-4C, Out of Service.

Turnover: Maintain 50% operation. Rotate CCW Pumps.

Event Malf Event Event No. No. Type* Description 1 N-ATCO Rotate CCW Pumps.

(2 min) 2 C-BOPO Isolated Phase Bus Duct Cooling Fan Motor Trips.

LE CUE 3 I-ATCO Pressurizer Pressure Safety Channel fails Low - Tech Spec LE CUE TS-CRS Entry.

4 I-BOPO Steam header pressure transmitter, PT-910 Fails High.

LE CUE 5 C - ATCO 10-15 gpm leak to containment - Tech Spec Entry.

LE CUE TS-CRS 6 C - ATCO Feedwater Pump Trips, Reactor Trip.

LE CUE 7 C-BOPO Blowdown fails to isolate automatically.

8 M - ALL Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of LE CUE Feedwater.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 7
2. Malfunctions after EOP entry (1-2) 2
3. Abnormal events (2-4) 2
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 2 or 3

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 1 Page 2 of 12 Event

Description:

Rotate CCW Pumps.

Time Position Applicants Actions or Behavior CRS Directs ATCO to switch operating CCW pump from Pump AC-3A to Pump AC-3C.

ATCO Obtains and reviews Procedure OI-CC-1, Attachment 2.

ATCO Directs EONA to Room 69.

ATCO Read Notes on top of page 9.

ATCO Starts pump AC-3C.

CRS/ Logs into Technical Specification 2.4(1)b.

ATCO ATCO Directs EONA to close AC-102, "Pump AC-3A discharge valve."

EONA reports that AC-102 is closed.

ATCO Verify that PI-499, CCW Pump Discharge Header Pressure, indicates approximately 90 psig.

ATCO Stops pump AC-3A.

ATCO Ensures proper operation of pump AC-3C. Directs EONT to reopen Valve AC-102.

ATCO Directs EONA to open AC-102, "Pump AC-3A discharge valve."

EONT reports that AC-102 is open.

CRS/ Exits Technical Specification 2.4(1)b.

ATCO

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 2 Page 3 of 12 Event

Description:

Isolated Phase Bus Duct Cooling Fan Motor Trips.

Time Position Applicants Actions or Behavior BOPO Respond to "ISO PHASE BUS AIR FLOW LO" alarm. ( CB-10,11/A10, A-6U)

BOPO Determines that the Cooling Fan Motor is not operating.

BOPO May attempt to restart the Cooling Fan.

CRS/ Direct Electrical Maintenance or EONT to change the belt to the other Bus BOPO Duct Cooling Fan Motor.

BOPO Check that generator output is less than 11,200 amps.

BOPO May monitor each phase temperature.

Electrical Maintenance or the EONT reports that the belt has been changed over.

BOPO Start the alternate Cooling Fan Motor.

BOPO Verify low flow alarm clears.

CRS May refer to AOP-27, "GENERATOR MALFUNCTIONS."

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 3 Page 4 of 12 Event

Description:

Pressurizer Pressure Safety Channel fails Low - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Respond to "PRESSURIZER SAFETY INJ SIGNAL LO-LO PRESSURE C/P102Y" (CB-1,2,3,/A4, C-5), "TM/LOW PRESSURE CHANNEL TRIP"(CB-4/A20, A-5) and "TM/LOW PRESSURE CHANNEL PRETRIP"(CB-4/A20, B-5)

ATCO Refer to ARPs.

or BOPO ATCO Check redundant channels and report failure of C/P102Y.

ATCO Verify the following:

Pressurizer pressure RCS Cold Leg Temperatures Axial Shape Index Reactor Power, NI and Delta-T CRS LCO 2.15(1) - The number of channels for the TM/LP and High Pressurizer (TS) Pressure trips in service falls one below the total number of installed channels (see Table 2-2). And the number of channels for PPLS actuation in service falls one below the total number of installed channels. (see Table 2-3).

Requires Actions:

The Thermal Margin/ Low Pressure and High Pressurizer Pressure channels must be bypassed or tripped within one hour.

The channels may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, after that it must be placed in the tripped position.

CRS Direct the ATCO to bypass channel "C" High Pressurizer Pressure trip unit

  1. 8 and TM/LP trip unit #9 .

ATCO Place channel "C" trip units #8 and #9 in bypass.

CRS Notify Work Week Manager of instrument Failure.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 4 Page 5 of 12 Event

Description:

Steam header pressure transmitter, PT-910 Fails High.

Time Position Applicants Actions or Behavior BOPO Identify rapid decrease in RCS T-cold (VARIABLE OVERPOWER RESET DEMAND, CB-4, A20, C-7) will alarm if uncorrected).

ATCO/ If "VARIABLE OVERPOWER RESET DEMAND",(CB-4, A20, C-7)

BOPO alarms, enter ARP CB-4/A20.

BOPO Recognize PCV-910, "Main Steam Bypass Valve," being open (red light on CB-1,2,3).

BOPO Determine that Steam Header Pressure Transmitter, PT-910 failed high.

CRS Direct BOP to take manual control of PCV-910 and close it.

BOPO Manually close PCV-910 BOPO Monitor RCS T-cold.

ATCO Monitor and control RCS parameters.

CRS Notify Work Week Manager or I&C of the failure of PT-910.

CRS If Pressurizer pressure lowers to 2075 psia or less, then enter Technical Specification LCO 2.10.4(5) - DNBR Margin During Power Operation Above 15% of Rated Power.

Required Actions:

Restore Pressurizer Pressure greater than or equal to 2075 psia within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Or else, reduce power to less than 15% within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 5 Page 6 of 12 Event

Description:

10-15 gpm leak to containment - Tech Spec Entry.

Time Position Applicants Actions or Behavior ATCO Respond to RM-050 CNTMT PARTICULATE HIGH RADIATION Alarm. (AI-33C/A33C, 1)

ATCO Enter ARP. Verify high radiation on ratemeter.

ATCO Check containment area monitors, report rising dose rates.

CRS/ Check for indication of RCS leakage into containment:

ATCO Dewpoint Temperature Containment Pressure Containment Sump Level Pressurizer Level ATCO Trend Pressurizer level, VCT level, charging and letdown and report to CRS.

CRS Enter AOP-22, "REACTOR COOLANT LEAK",Section I, "Leak Rate Determination and Leak Isolation" CRS Read Cautions and Notes.

CRS Direct Shift Chemist to perform a rapid activity analysis of both S/Gs CRS Ask Shift Manager to implement the Emergency Plan.

CRS/ Determine the RCS leak rate to be approximately 15 gpm.

ATCO CRS Direct Shift Chemist to verify primary to secondary leakrate.

CRS LCO 2.1.4(1) - Greater than 1 gpm unidentified leakage or greater than 10 (TS) gpm identified leakage.

Required Actions:

Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

or else be in hot shutdown within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

If Pressure Boundary Leakage is identified, then:

be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 5 Page 7 of 12 Event

Description:

10-15 gpm leak to containment - Tech Spec Entry., continued.

Time Position Applicants Actions or Behavior CRS Direct ATCO to isolate letdown and charging.

ATCO Isolate letdown and charging and check leakage rate. Determines that the leak was not isolated.

CRS/ Restore charging and letdown.

ATCO CRS Refer to Attachment A, "Leak Location Guide", determine leak is to Containment.

ATCO Check the rate of level rise in the quench tank.

CRS/ Direct the EONA to check the rate of level rise in the RCDT and Auxiliary ATCO Building Sumps and to visually inspect the Auxiliary Building.

CRS/ Direct Radiation Protection to sample the Auxiliary Building atmosphere ATCO and check the continuous air monitors.

CRS/ Direct the EONA or Chemist to close Sample Isolation Valves, HCV-2500, ATCO 2501, 2502 and 2503, in Room 60.

ATCO Close RCS Sample Isolation Valves, HCV-2504A and HCV-2504B.

CRS/ Direct Chemistry to check the sampling lineups.

ATCO ATCO Start all available Containment Vent Fans and ensure CCW is supplied to the cooling coils.

CRS/ Direct the EONA to place both Containment Sump Pumps in "PULL TO ATCO LOCK."

ATCO Close both Containment Sump Isolation Valves, HCV-506A and HCV-506B.

CRS Direct plant shutdown using either OP-4, "LOAD CHANGE AND NORMAL POWER OPERATION" or AOP-05, "EMERGENCY SHUTDOWN". Will enter AOP-22, "Section II - Reactor Coolant Leak Less Than 40 gpm," after plant shutdown.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 6, 7 Page 8 of 12 Event

Description:

Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically.

Time Position Applicants Actions or Behavior BOPO Determine that the running Feedwater Pump has tripped.

CRS Direct the ATCO to manually trip the reactor.

ATCO Manually trip the reactor.

CRS Enters EOP-00. Directs ATCO and BOPO to perform Standard Post Trip Actions.

ATCO Perform Reactivity Control Actions:

Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met BOPO Verify Turbine Tripped:

Stop and Intercept Valves are Closed BOPO Verify Generator Breakers Tripped:

Breakers 3451-4/5 Generator Field Breaker BOPO Verify vital buses, 1A3 and 1A4, are energized.

BOPO IF SIAS has initiated, THEN verify both Diesel Generators have started.

BOPO Verify non-vital buses, 1A1 and 1A2, are energized.

BOPO Verify both 125VDC buses are energized.

BOPO Verify Instrument air status:

Instrument Air pressure is at least 90 psig At least 1 air compressor running

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 6, 7 Page 9 of 12 Event

Description:

Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically, continued Time Position Applicants Actions or Behavior ATCO Verify CCW and Raw water status:

At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open ATCO Verify Inventory Control:

Pressurizer Level 30-70% trending toward 45-60%

Subcooling, at least 20°F ATCO Verify Pressure Control:

RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO Verify Core Heat Removal:

RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10°F BOPO Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):

Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%

No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF BOPO Determines DCS has not throttled blowdown flow, manually isolates (CT) blowdown by closing HCV-1387A/B and HCV-1388A/B within 15 minutes of feedwater pump trip.

BOPO Reports no running Main Feed Pumps. Establishes AFW Flow using Motor Driven AFW Pump, FW-6, or Turbine Driven AFW Pump, FW-10.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 6, 7 Page 10 of 12 Event

Description:

Feedwater Pump Trips, Reactor Trip, Blowdown fails to isolate automatically, continued.

Time Position Applicants Actions or Behavior BOPO Verify Steam Dump and Bypass Valves are controlling BOTH of the following:

T-cold 525-535°F S/G Pressure 850-925 psia ATCO Verify containment conditions:

No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120°F Reports that containment sump level is rising.

CRS Performs diagnostic actions and enters EOP-03, "LOSS OF COOLANT ACCIDENT."

(Note: May also enter EOP-01, "REACTOR TRIP RECOVERY," and AOP-22, "Section II - Reactor Coolant Leak Less Than 40 gpm," since pressurizer pressure is greater than 1800 psia and stable or rising.)

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 8 Page 11 of 12 Event

Description:

Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater.

Time Position Applicants Actions or Behavior BOPO Reports loss of AFW Flow.

CRS Transitions to EOP-20, "FUNCTIONAL RECOVERY.", Success path, HR-1.

(NOTE: If EOP-01 entered previously, then may enter EOP-06, "LOSS OF ALL FEEDWATER," at this time.)

CRS Confirm Standard Post Trip Actions.

CRS Request Shift Manager to enter the Emergency Plan.

CRS Monitor the floating steps.

ATCO Trips all Reactor Coolant Pumps within 10 minutes of a total loss of (CT) feedwater being diagnosed.

BOPO Ensure Blowdown is isolated by ensuring the following valves are closed:

HCV-1387A/B HCV-1388A/B CRS Direct Shift Chemist to perform a rapid activity analysis of both steam generators.

CRS Refer to Safety Function Status Checks or Resource Assessment Trees and go to success path HR-1.

CRS Direct ATCO to insert group N CEAs. (If entered EOP-20)

ATCO Insert Group N CEAs, if directed.

ATCO Monitor for establishment of natural circulation:

Delta-T less than 50°F.

Difference between CETs and T-hot less than 10°F.

T-hot and T-cold stable or lowering.

At least 20°F subcooling.

BOPO Begin a controlled plant cooldown using steam dump and bypass valves.

ATCO Monitor RCS pressure per Attachment 2.

CRS Determines that AFW flow cannot be established.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-4 Revision: 5 Event No.: 8 Page 12 of 12 Event

Description:

Pipe from EFWST to FW-6 and FW-10 breaks. Total Loss of Feedwater, Continued.

Time Position Applicants Actions or Behavior CRS Direct BOPO to establish Condensate pump feed to the Steam Generators.

BOPO Establish condensate pump feed to the Steam Generators:

Place all FW Pump Control Switches in Pull-To-Lock Direct EONT to open All FW Pump discharge valves Ensure FW Pump Recirc valves are closed Start All FW Pump Lube Oil Pumps Reduce Steam Generator Pressure to less than 550 psia Direct EONT to ensure Condensate Pump Recirc Valve, FCV-1172, is closed ATCO Maintain pressurizer pressure per EOP-AOP Attachment 2 and level 10-70%.

.

BOPO When S/G pressure is less than 550 psig:

Block SGLS Ensure HCV-1385 and HCV-1386 are open Ensure HCV-1103 and HCV-1104 are closed Reduce pressure to achieve flow through FW bypass Valves, HCV-1105 and HCV-1106 NOTE: The next two steps are expected only if Wide Range Level in both Steam Generators falls below 27%.

CRS IF WR Level in both S/Gs falls below 27%, THEN initiate Once through (CT) Cooling using EOP-20, HR-4 (or EOP-06)

BOPO IF directed to initiate Once through cooling then:

Deenergize all pressurizer heaters.

Initiate PPLS using test switches.

Ensure HPSI pumps running and injection valves open.

Ensure PORV Block valves are open.

Open both PORVs.

Scenario ends with the Steam Generators being fed by the Condensate Pumps or with Once Through Cooling Established.

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 Days Nights X PLANT STATUS:

MODE: 1 X 2 3 Rx Power: 49.00% Rod Position: Group 4 @ 88" Prcs (>2075 psia): 2108 psia Tcold (<543°F): 539.6 °F Lpzr (48 - 60%): 56 % (Actual)

Comments:

SAFEGUARDS STATUS:

(Log any out-of-service safeguards equipment; include major fire protection equipment)

RECENT TEMP MODS: (Within the last month)

TM Number Date Description None DEGRADED EQUIPMENT STATUS CR Number Component/System Reason Considered Degraded Resolution 2009003501 AFW Pump FW-54 Out of Service - being repaired excessive vibration 2009003517 Feed Pump FW-2A Out of Service - motor windings shorted Motor off site for rewind 2009003521 Feed Pump FW-2C Out of Service - Seal Leakage Seals being replaced SO-O-1 FC/FORM Page 1 of 3

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 RELEASES IN PROGRESS: YES NO RELEASE #

Monitor Tank: A B X Waste Gas Decay Tank: A B C D X

.

Containment Pressure Reduction X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:

PROCEDURE or TEST REASON None CRS review and discuss procedures in progress (Initial)

INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):

ITEM / LOCATION DATE ACTION REQUIRED None TEMPORARY LIFTS:

TAGOUT # EQUIPMENT REASON None POST MAINTENANCE TESTING:

(Equipment, instrument or annunciator requiring PMT for operability)

AVAILABLE Component YES NO PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:

REPORT MADE EQUIP OOS DATE/TIME T.S. / ODCM / G-103 LCO YES NO N/A None SO-O-1 FC/FORM Page 2 of 3

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 04/01/09, 0600 REMARKS:

  • Perform Normal Rotation of CCW Pumps per OI-CC-1, Attachment 2. Place AC-3C in service, shutdown AC-3A
  • RCS Boron 1165 ppm Neutral Blend (gal acid /gal water)10/87 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________

Off going On coming S.M.

C.R.S.

L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator ____

Security Key Transferred (Init)

SO-O-1 FC/FORM Page 3 of 3

FORT CALHOUN STATION FC-75A FORM R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 04/01/09 Shift (Circle one) 0600-1800 1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.

Switch Location Annunciators in Alarm Reason out-of-position/in alarm FW-4A CS CB-10,11 FW-4A Out of Service FW-30A CB-10,11 FW-4C CS CB-10,11 FW-4C Out of Service FW-30C CB-10,11 CB-10,11/A9 C-3L FW SYSTEM VALVES TROUBLE FW-4A and FW-4C Isolated PROTECTED EQUIPMENT SIGN LOCATION REASON PROTECTED FW-6 FW-6 CS and BKR FW-54 Out of Service FW-10 YCV-1045 CS '

FW-4B CS and BRKR FW-4A and FW-4C OOS

FORT CALHOUN STATION OI-CC-1 OPERATING INSTRUCTION C PAGE 8 OF 73 Continuous Use Attachment 2 - Rotating In service Pumps PREREQUISITES (9) INITIALS

1. Procedure Revision Verification Revision No. 65 Date: 04/01/09 JEK
2. Power is available for the selected pump:
  • AC-3A, Component Cooling Water Pump, 1B3B-4
  • AC-3B, Component Cooling Water Pump, 1B4A1
  • AC-3C, Component Cooling Water Pump, 1B3C-4C-4 X JEK
3. Verify operability of Diesel Generators will meet Tech Spec 2.7 requirements prior to disabling CCW pumps. JEK PROCEDURE NOTE The number of pumps in service can cause fluctuations in CCW temperature.

This can affect letdown temperature and may cause small reactivity changes in the RCS.

CAUTION At least two Component Cooling Heat Exchangers shall be in service at all times to protect against system over pressurization should a second pump automatically start.

1. Vent the pump to be started using the associated valve:
  • AC-353, Comp Cooling Water Pump AC-3A Casing Vent Valve
  • AC-356, Comp Cooling Water Pump AC-3B Casing Vent Valve
  • AC-359, Comp Cooling Water Pump AC-3C Casing Vent Valve X JEK
2. Start the desired Component Cooling Water Pump:
  • AC-3A
  • AC-3B
  • AC-3C R65

FORT CALHOUN STATION OI-CC-1 OPERATING INSTRUCTION C PAGE 9 OF 73 Continuous Use Attachment 2 - Rotating In service Pumps PROCEDURE (continued) (9) INITIALS NOTES

1. When stopping a Component Cooling Water Pump with two or more pumps operating, the pump discharge valve is closed to prevent check valve slamming.
2. The Component Cooling Water system contains a corrosion inhibitor, CORRSHIELD NT 4204 and should be considered a personnel hazard if a leak exists.
3. Log into Tech Spec 2.4(1)b 7 day LCO or 2.4(2)a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO as appropriate, for the CCW Pump inoperability.
4. Close the discharge valve for the Component Cooling Water Pump to be stopped:
  • AC-102, Comp Cooling Water Pump AC-3A Discharge Valve
  • AC-105, Comp Cooling Water Pump AC-3B Discharge Valve
  • AC-108, Comp Cooling Water Pump AC-3C Discharge Valve
5. Verify PI-499, Pressure Indicator for CCW Pump Disch Header, pressure is approximately 90 psig.
6. Stop the Component Cooling Water Pump to be shutdown:
  • AC-3A
  • AC-3B
  • AC-3C
7. Open discharge valve closed in Step 4.

Ind Verif

8. Exit appropriate Tech Spec LCO.

Completed by Date/Time /

R65

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2009-1 (SPARE) Revision: 3 Examiners: _________________________ Operators: _________________________

_________________________ _________________________

_________________________ _________________________

Initial Conditions: 100% Power. Diesel Driven AFW Pump, FW-54, is out of service. Air Compressor, CA-1A, is out of service.

Turnover: Transfer Letdown Control Valves from LCV-101-1 to LCV-101-2. After that rotate running EHC Pumps.

Event Malf Event Event No. No. Type* Description 1 N-ATCO Transfer Letdown Flow Control Valves.

(2 min) 2 N-BOPO Rotate EHC Pumps.

(14 min) 3 I-ATCO Power Range NI Channel B fails - Tech Spec Entry.

LE CUE 4 C-BOPO Running Bearing Cooling Water Pump, AC-9A, trips.

LE CUE 5 I-ATCO Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec LE CUE Entry 6 C-All Loss of Instrument Air.

LE CUE 7 C-ATCO Manual Reactor Trip Required.

8 M-All Steam Generator Safety Valve Fails Open.

LE CUE

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 5
2. Malfunctions after EOP entry (1-2) 1
3. Abnormal events (2-4) 2
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 3

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 1 Page 2 of 15 Event

Description:

Transfer Letdown Flow Control Valves Time Position Applicants Actions or Behavior ATCO Enter OI-CH-1, Attachment 2, "SHUTDOWN OF CHARGING AND LETDOWN."

ATCO Bypass ion exchangers by placing TCV-211-2, Ion Exchangers Bypass Valve to "BYP IX" ATCO Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.

ATCO Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.

ATCO Stop the operating charging pump, CH-1A. (May place on PULL-OUT.)

ACTO Close Charging Isolation Valves, HCV-238 and HCV-239.

ATCO Enter OI-CH-1, Attachment 1, "STARTUP OF CHARGING AND LETDOWN."

ATCO Ensure LCV-218-2 VCT Outlet Valve is open with control switch in AUTO.

ATCO Read caution on top of page 8.

ACTO Ensure HCV-247, Charging to RC Loop 1A Isolation Valve is open.

ATCO Ensure charging isolation valves open; HCV-247 AND HCV-238 AND/OR HCV-248 AND HCV-239.

ATCO Place HC-101-3, Limiter Bypass Switch, in BYPASS.

ATCO Place HIC-101-1/101-2 Letdown Throttle Valve Controller in MANUAL.

ATCO Close LCV-101-1 and LCV-101-2 ATCO Select LCV-101-2 on HC-101-2 selector switch ATCO Place PIC-210, Letdown Pressure Controller, in MANUAL.

ATCO Throttle PIC-210 to approximately 10% open.

ATCO Verify position of Charging Pumps Mode Select Stby switch is CH-1B-1C.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 1 Page 3 of 15 Event

Description:

Transfer Letdown Flow Control Valves, continued.

ATCO Start CH-1A.

ATCO Open HCV-204 and TCV-202.

ATCO Use HIC-101-1/101-2 to initiate letdown flow while adjusting PCV-210 to maintain approximately 300 psig.

ATCO Balance charging and letdown flow.

ATCO Place HC-101-3, Limiter Bypass Switch, in NORMAL.

ATCO Go to OI-RC-8, Attachment 3. and ensure pressurizer level matches programmed level and PIC-210 200-400 psia.

ATCO Adjust bias on HIC-101-1/101-2 until top scale indicates 50%.

ATCO Place HIC-101-1/101-2 transfer switch to BAL, then to AUTO.

ATCO Place PIC-210 to AUTO.

ATCO Make adjustments to HIC-101-1/101-2 as needed.

ATCO If Ion Exchangers were bypassed, then may place TCV-211-1 in AUTO/TO IX.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 2 Page 4 of 15 Event

Description:

Rotate EHC Pumps Time Position Applicants Actions or Behavior CRS Direct BOPO to rotate EHC Pumps.

BOPO Enters OI-ST-12, Attachment 7, "NORMAL ROTATION OF ELECTROHYDRAULIC PUMPS."

BOPO Read note in middle of page 13.

BOPO Start standby EHC Pump, EHC-3B.

BOPO Ensure EHC system pressure is stable on PI-2101.

BOPO Ensure EHC-3B motor current is approximately 40 to 50 amps.

BOPO Direct EONT to verify local parameters:

PI-5116 pressure approximately equal to PI-2101 pressure PI-5115 pressure approximately equal to PI-2101 pressure No bubbles visible in EHC-3B suction strainer BOPO Stop EHC pump, EHC-3A. Ensure pump control switch in AFTERSTOP.

BOPO Verify adequate EHC pressure being maintained.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 3 Page 5 of 15 Event

Description:

Power Range NI Channel B fails - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Identify the failure from the Nuclear Instrumentation Inoperable and other alarms. May enter ARP.

ATCO Determine that Power Range NI Channel B Upper Detector has failed.

ATCO Reset Rod Drop Bistables.

CRS Enter AOP-15, "LOSS OF FLUX INDICATION OR FLOW STREAMING."

CRS LCO 2.15(1) - The number of channels for the High Power Level, Thermal (TS) Margin/Low Pressurizer Pressure and Axial Power Distribution trips fell one below the total number of installed channels.

Required Actions:

RPS channel B trip units 1, 9 and 12 must be placed in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Since this is a detector failure, they may remain in bypass for up to 7 days. (Note: They may enter 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> LCO until I&C confirms detector failure.)

If detector operability is not restored by the end of the 7 days, the reactor must be placed in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

CRS Notify Manager - FCS, Manager - Operations or Supervisor - Operation of RPS trip unit bypass.

CRS Obtain the keys and direct the ATC operator to place the 1, 2, 9, 10 and 12 trip units on channel B in bypass.

ATCO Bypass trip units 1, 2, 9, 10 and 12 on RPS channel B.

ATCO Enter channel bypass information in control room log.

or BOPO CRS Inform Work Week Manager of NI Channel Failure.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 4 Page 6 of 15 Event

Description:

Running Bearing Cooling Water Pump, AC-9A, trips Time Position Applicants Actions or Behavior BOPO Respond to Cooling Water Pressure Low alarm (CB-10,11 A11 B6U).

BOPO Report that AC-9A has tripped.

ATCO/ Refer to ARP CB-10, A11, B-6U BOPO BOPO Check PI-1917, Turbine Bearing Water Temperature.

BOPO Dispatch EONT to the Bearing Water Pumps.

Note: May receive ISO PHASE BUS TEMP HI alarm is starting backup pump is delayed.

CRS Direct BOPO to start AC-9B.

BOPO Start AC-9B.

CRS Direct BOPO to verify status of Instrument Air System.

BOPO Ensure that air compressor is operating and instrument air pressure normal or restoring.

BOPO Direct EONT to check Breaker for AC-9A EONT reports breaker tripped, pump motor hot.

BOPO May place AC-9A control switch in PULL TO LOCK.

CRS/ May Direct EONT to attempt to reset breaker.

BOPO If Directed, EONT reports breaker will not reset.

CRS Notify Work Week Manager.

BOPO Direct EONT to check level in Bearing Water Head Tank.

EONT reports normal water level.

CRS May refer to AOP-20.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 5 Page 7 of 15 Event

Description:

Loop Two Hot Leg RTD, TT-122H, Fails High - Tech Spec Entry Time Position Applicants Actions or Behavior ATCO Responds to numerous alarms on CB-4, panel A-20 and CB-1,2,3, panel A4.

Reports that trip units 1, 9 and 12 on channel A are tripped.

ATCO/ Reviews ARP.

BOPO ATCO Checks power, pressure and temperature indications and determines that the alarm is caused by failed T-hot channel (A/T122H).

CRS LCO 2.15(2) - High Power Level, Thermal Margin/Low Pressurizer (TS) Pressure and Axial Power Distribution Operable Channels have fallen to the minimum operable channels in TS Table 2.2.

Required Actions:

Because trip units 1, 9 and 12 are already bypassed on RPS channel B. The 1, 9 and 12 trip units on channel A must be placed in the tripped condition within one hour.

One of the channels must be repaired within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or else the plant must be placed in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With NI channel B trip units bypassed and Delta-T channel A trip units tripped, power must be reduced to less than 70% (no time limit).

CRS Either direct the ATC to use the Channel A Power Trip Test Interlock, PTTI, to place the trip units in the tripped condition by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID" or else notify I&C to trip the trip units with one hour.

ATCO If directed, use the channel A PTTI to trip the trip units on channel A by placing the "Test Enable" switch in "ENABLE" and the "Test Select" switch in "CAL MID."

CRS Notifies Plant or Operations Management and the Work Week Manager or I&C of the failure.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 6 Page 8 of 15 Event

Description:

Loss of Instrument Air Time Position Applicants Actions or Behavior BOPO Respond to "PLANT AIR PRESS LO" alarm (CB-10,11/A21,B-6U)

Report that Plant Air Pressure is less than 96 psig, ARP directs entry into BOPO AOP-17 CRS Enter AOP-17, "LOSS OF INSTRUMENT AIR."

Caution BOPO that Feed Reg Valves, FCV-1101 and FCV-1102, fail as-is CRS when Instrument Air Pressure lowers to 70-80 psig.

CRS Read Notes on page 4 of AOP-17.

CRS/ Ensure all available Air Compressors Start.

BOPO Direct EONT to ensure proper operation of:

CA-1A/B/C, Air Compressors CRS/ CA-12, Air Dryer BOPO CA-11A/B, Pre-Filters CA-13A/B, After-Filters CRS/ Direct all available Operators to search for the source of the air leak BOPO CRS/ Direct EONT to verify "Service Air System Automatic Isolation Valve",

BOPO PCV-1753, closure when instrument air pressure drops to less than 80 psig.

CRS/ Direct EONT to verify "Air Dryers CA-31 & CA-12 Bypass Valve, PCV-BOPO 1752, opens when instrument air pressure drops to less than 78 psig.

CRS Direct BOPO to isolate instrument air to containment.

Close "Instrument Air Containment Isolation Valves", PCV-1849A/B and BOPO after verifying air pressure continues to drop, reopen PCV-1849A/B.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 6 Page 9 of 15 Event

Description:

Loss of Instrument Air, Continued Time Position Applicants Actions or Behavior ATCO Maintain RCS pressure 2075-2150 psia and Pressurizer Level 45-60% using charging.

CRS Direct manual reactor trip when air pressure drops to less than 50 psig.

ATCO Manually trip reactor when directed.

CRS Direct BOPO to trip all Main Feedwater Pumps.

BOPO Trip all Main Feedwater Pumps.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 7 Page 10 of 15 Event

Description:

Manual Reactor Trip Required Time Position Applicants Actions or Behavior CRS Enters EOP-00. Directs ATCO and BOPO to perform standard post trip actions.

ATCO Perform Reactivity Control Actions:

Verify power lowering Verify negative startup rate Verify no more than one CEA not inserted Monitor for an uncontrolled RCS Cooldown Notify CRS that Reactivity Control is Met.

BOPO Verify Turbine Tripped:

Stop and Intercept Valves are Closed BOPO Verify Generator Breakers Tripped:

Breakers 3451-4/5 Generator Field Breaker BOPO Verify vital buses, 1A3 and 1A4, are energized.

BOPO IF SIAS has initiated, THEN verify both Diesel Generators have started.

BOPO Verify non-vital buses, 1A1 and 1A2, are energized.

BOPO Verify both 125VDC buses are energized.

BOPO Verify Instrument air status:

Instrument Air pressure 90 at least 90 psig At least 1 air compressor running Reports instrument air pressure is low and continuing to lower.

ATCO Verify CCW and Raw water status:

At least one CCW pump running CCW Pump Discharge Pressure > 60 psig At least 1 RW Pump running IF CCW Pump Discharge Pressure > 40 psig, THEN verify HCV-438A/B/C/D are open ATCO Verify Inventory Control:

Pressurizer Level 30-70% trending toward 45-60%

Subcooling, at least 20°F

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 7 Page 11 of 15 Event

Description:

Manual Reactor Trip Required, continued Time Position Applicants Actions or Behavior ATCO Verify Pressure Control:

RCS Pressure 1800-2300 psia trending toward 2050-2150 psia PORVs closed ATCO Verify Core Heat Removal:

RCP NPSH adequate per Attachment 2 At least 1 RCP running Core Delta-T less than or equal to 10°F BOPO Ensure Main Feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR):

Both Feed Reg Valves ramped closed Both Feed Reg Bypass Valves ramped 40-45%

No more than 1 Main Feed Pump is operating No more than one Condensate pump is operating No Heater Drain Pumps are operating 43/FW Switch is in OFF Close blowdown isolation valves, HCV-1387A/B and HCV-1388A/B Reports Feed Reg valves open, Feed Reg bypass valves closed and no Main Feed Pumps operating.

Establishes AFW flow to the AFW nozzles.

BOPO Verify Steam Dump and Bypass Valves are controlling BOTH of the following:

T-cold 525-535°F S/G Pressure 850-925 psia Reports that steam dump and bypass valves are closed due to loss of instrument air pressure. Operates HCV-1040 or MS-292 and MS-292 as required to maintain temperature and pressure bands.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 7 Page 12 of 15 Event

Description:

Manual Reactor Trip Required, continued Time Position Applicants Actions or Behavior ATCO Verify containment conditions:

No unexpected rise in Containment sump level No Containment Area Rad Monitor Alarms No Containment or Stack radiation monitors,RM-051/52/62, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, alarms No S/G blowdown or Condenser offgas radiation monitor, RM-054A/54B/57, upward trends Containment pressure < 3 psig AND Containment Temp < 120°F CRS Perform Diagnostic Actions and enters EOP-01.

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 8 Page 13 of 15 Event

Description:

Steam Generator Safety Valve Fails Open Time Position Applicants Actions or Behavior ATCO Reports RCS cooldown in progress.

BOPO Reports S/G pressure is lowering.

CRS Directs ATCO to perform emergency boration using EOP-00 contingency action.

ATCO Performs Emergency Boration:

(CT) Ensure FCV-269X/Y Closed Open HCV-268/265/258 Start Boric Acid Pumps, CH-4A/B Start Charging pumps, CH-1A/B/C Close LCV-218-2/3 and HCV-257/264 CRS Perform diagnostic actions and transition to EOP-20, FUNCTIONAL RECOVERY PROCEDURE, due to a loss of instrument air and an excessive heat removal event.

CRS Within EOP-20, go to success path MVA-IA and implement (continue to implement) AOP-17, LOSS OF INSTRUMENT AIR.

On Note: Water Plant Operator Reports Instrument air leak in the intake CUE structure.

CRS Direct Water Plant Operator to isolate leak CRS Direct BOPO to monitor instrument Air Pressure BOPO Reports that Instrument air pressure is now increasing CRS Within EOP-20, go to RCS Core and Heat Removal success path, HR-3.

CRS Direct ATCO or BOPO to verify PPLS, Pressurizer Pressure Low Signal.

ATCO Verify PPLS:

or Ensure emergency boration in progress BOPO Ensure acceptable SI flow per EOP/AOP Attachment 3 Verify 2 HPSI, 2 LPSI and all available charging pumps running

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 8 Page 14 of 15 Event

Description:

Steam Generator Safety Valve Fails Open, continued Time Position Applicants Actions or Behavior CRS/ Identify Most Affected Steam Generator by downward trends in any of the BOPO following:

Steam pressure S/G level RCS T-cold BOPO Reports that RC-2B is the affected Steam Generator.

BOPO Manually closes MSIVs when steam header pressure reaches 700 psia.

BOPO IF either S/G pressure is less than or equal to 500 psia, THEN ensure SGIS closes all of the following valves:

HCV-1041A, RC-2A MSIV HCV-1041C, RC-2A MSIV Bypass Valve HCV-1042A, RC-2B MSIV HCV-1042C, RC-2B MSIV Bypass Valve HCV-1105, Feed Reg Bypass Valve HCV-1106, Feed Reg Bypass Valve HCV-1103, Feed Reg Block Valve HCV-1104, Feed Reg Block Valve HCV-1386, RC-2A Feed Header Isolation Valve HCV-1385, RC-2B Feed Header Isolation Valve CRS Direct BOPO to isolate Steam Generator, RC-2B BOPO Isolate S/G RC-2B by closing or ensuring closed:

MSIV, HCV-1042A.

MSIV Bypass, HCV-1042C.

Air assisted S.G Safety Valve, MS-292.

BOPO Isolate S/G RC-2B by closing or ensuring closed:

(CT) Feed Reg Valve, FCV-1102 (may need to reset due to low instrument air pressure)

Feed Reg Bypass valve, HCV-1106 Feed Header Isolation Valve, HCV-1385 Feed Reg Block valve, HCV-1104 Blowdown Isolation Valves, HCV-1387A/B AFW Isolation valves, HCV-1108A/B

Appendix D Operator Actions Form ES-D-2 Scenario No: 2009-1 Revision: 3 Event No.: 8 Page 15 of 15 Event

Description:

Steam Generator Safety Valve Fails Open, continued Time Position Applicants Actions or Behavior BOPO Isolate S/G RC-2B by closing or ensuring closed:

Direct EONT to close Packing leakoff line isolation valve, MS-298 Override and close steam to AFW pump-FW-10, YCV-1045B Blowdown Sample Isolation Valves, HCV-2507A/B BOPO Verify the most affected S/G is isolated by downward trends in all of the following for the isolated S/G:

Steam pressure S/G level RCS T-cold CRS Read the Cautions on page 335 of EOP-20 BOPO Prepare to steam S/G RC-2A prior to reaching 27% WR level in RC-2B by one of the following:

Ensuring MSIV HCV-1041A is open Blocking SGLS and opening HCV-1041C, Main Steam Bypass Valve BOPO Establish Steam Flow from RC-2A prior to Wide Range Level on Steam (CT) Generator RC-2B falling to 27% by one of the following:

Opening Air assisted safety valve, MS-291 (OR)

Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and use steam dump and bypass valves. (OR)

Ensure MSIV, HCV-1041A or MSIV Bypass,HCV-1041C is open and open atmospheric dump valve, HCV-1040 BOPO Ensure Auxiliary Feedwater is being supplied to S/G, RC-2A.

Scenario ends with S/G RC-2B isolated and heat removal established using S/G RC-2A.

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 Days Nights X PLANT STATUS:

MODE: 1 X 2 3 Rx Power: 98.60% Rod Position: All Groups ARO Prcs (>2075 psia): 2091 psia Tcold (<543°F): 542.8 °F Lpzr (48 - 60%): 60  % (Actual)

Comments:

SAFEGUARDS STATUS:

(Log any out-of-service safeguards equipment; include major fire protection equipment)

RECENT TEMP MODS: (Within the last month)

TM Number Date Description None DEGRADED EQUIPMENT STATUS CR Number Component/System Reason Considered Degraded Resolution 2009003501 AFW Pump FW-54 Out of Service - being repaired excessive vibration 2009003517 Air Compressor CA-1A Out of Service - motor windings shorted 2009003521 LCV-101-1 Erratic flow control LCV-101-2 will be placed into service while System Engineer investigates.

SO-O-1 FC/FORM Page 1 of 3

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 RELEASES IN PROGRESS: YES NO RELEASE #

Monitor Tank: A B X Waste Gas Decay Tank: A B C D X

.

Containment Pressure Reduction X PROCEDURES and SURVEILLANCE IN PROGRESS/OVERDUE:

PROCEDURE or TEST REASON None CRS review and discuss procedures in progress (Initial)

INSTRUMENT / ANNUNCIATE STATUS (REQUIRING COMPENSATORY ACTION):

ITEM / LOCATION DATE ACTION REQUIRED None TEMPORARY LIFTS:

TAGOUT # EQUIPMENT REASON None POST MAINTENANCE TESTING:

(Equipment, instrument or annunciator requiring PMT for operability)

AVAILABLE Component YES NO PMT REQUIRED FOR OPERABILITY None TECHNICAL SPECIFICATION LCO'S and ODCM / SO-G-103 RESTRICTIONS:

REPORT MADE EQUIP OOS DATE/TIME T.S. / ODCM / G-103 LCO YES NO N/A None SO-O-1 FC/FORM Page 2 of 3

FORT CALHOUN STATION FC-95 FORM SHIFT TURNOVER LOG Rev. 29 Modes 1, 2, or 3 03/31/09, 0600 REMARKS:

  • Transfer Letdown Flow Control from LCV-101-1 to LCV-101-2. Shutdown charging and letdown using OI-CH-1, Att 2.
  • Reestablish charging and letdown using LCV-201-2 and CH-1A per OI-CH-1, Att 1 and OI-RC-8, Att 3.
  • Perform Normal Rotation of EHC Pumps per OI-ST-12, Attachment 7.

RCS Boron 998 ppm Neutral Blend (gal acid /gal water)10 / 55 Additions this shift:2 additions of 20 gallons or demineralized water to raise reactor power CRS review ERF alarms and discuss with oncoming CRS: __________

Off going On coming S.M.

C.R.S.

L.O. 1 L.O. 2 STA Fire Brigade Leader Communicator ____

Security Key Transferred (Init)

SO-O-1 FC/FORM Page 3 of 3

FORT CALHOUN STATION FC-75A FORM R4 PROTECTED DQUIPMENT AND OUT-OF-NORMAL SWITCH POSITION/ANNUNCIATOR IN ALARM LIST Date: 03/31/09 Shift (Circle one) 0600-1800 1800-0600 NOTE: the Out-of-Normal position switch and Annunciator Alarm list must include a detailed reason justifying why the switch is in the current position or why the annunciator is in alarm. If the condition is due to an ongoing Surveillance Test or Operating Instruction, then the specific procedure number and step must be listed.

Switch Location Annunciators in Alarm Reason out-of-position/in alarm CA-1A CS CB-10,11 Out of Service A-33-1, F7 AIR COMPRESSOR CA-1A OFF NORMAL '

PROTECTED EQUIPMENT SIGN LOCATION REASON PROTECTED FW-6 FW-6 CS and BKR FW-54 Out of Service FW-10 YCV-1045 CS '

CA-1B CA-1B CS and BKR CA-1A Out of Service CA-1C CA-1C CS and BKR '

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 5 OF 77 Attachment 1 - Startup of Charging and Letdown PREREQUISITES (9) INITIALS

1. Procedure Revision Verification Revision No. 76 Date: 3/31/09 JEK
2. CVCS Checklist OI-CH-1-CL-A has been completed. JEK
3. Component Cooling Water is in operation per OI-CC-1. JEK
4. Power is available for the following pumps:
5. Liquid Waste Disposal System is available to receive waste from CVCS per OI-WDL-1. JEK
6. Charging pumps discharge accumulators precharge pressure has been set to approximately 60 to 90% of anticipated RCS pressure. JEK
7. Charging pumps suction accumulators precharge pressure has been set at approximately 15 psig. JEK
8. FT-236, Charging Pump Discharge Flow Transmitter, has been vented If the system has been shutdown for greater than two weeks or has been drained. JEK
9. If the SIRWT has been drained to 80 inches or less, the SIRWT suction header has been vented per OI-SI-1. N/A
10. Ensure Letdown Valve CIAS Override Switches are in NORMAL position.

(CB-1,2,3)

  • 43-CIAS/HCV-204 X
  • 43-CIAS/TCV-202 X JEK R76

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 6 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (9) INITIALS NOTE Review SO-O-23 for appropriate Equipment/System Usage Cycles.

1. Start the selected Packing Cooling Pump a minimum of 30 minutes prior to starting a Charging Pump:
2. If desired by the SM to equalize the boron concentration in the charging pump, flush a nominal 40 gallons of water (approximately 2%) from the VCT N/A using the desired charging pumps drain valve:
a. Declare the affected charging pump inoperable:

N/A

b. Place control switch for selected pump into PULL-TO-LOCK:
c. Close the discharge valve for selected pump:

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 7 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued) (9) INITIALS 2

d. Open the selected charging pump drain valve during system filling to N/A ensure of boron is equalized in the discharge piping:
  • CH-356, Charging Pump CH-1A Discharge Drain Valve to Waste Disposal System
  • CH-355, Charging Pump CH-1B Discharge Drain Valve to Waste Disposal System
  • CH-354, Charging Pump CH-1C Discharge Drain Valve to Waste Disposal System
e. When nominal 2% has been flushed from the VCT to waste, THEN close the selected charging pump drain valve:
f. Open and backseat the selected charging pump Discharge Valve:

N/A

N/A Ind Verif

g. Place control switch for selected pump into AFTER STOP:
h. Repeat this step as necessary for each affected charging pump.
3. Ensure LCV-218-2, Volume Control Tank Outlet Valve, is open with its control switch in AUTO.

R76

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 8 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued) (9) INITIALS CAUTION HCV-247, Charg to RC Loop 1A Isolation Valve must remain open to provide an alternate makeup path for charging and ensure CH-202, Ltdn to Regen Ht Exch Isolation Valve will be able to relieve thermal expansion in the Regenerative Heat Exchanger.

4. Ensure HCV-247, Charg to RC Loop 1A Isolation Valve, is open.
5. Ensure at least one of the following combinations of charging isolation valves is open:
a. Charg to RC Loop 1A Isolation Valves
  • HCV-247
  • HCV-238
b. Charg to RC Loop 2A Isolation Valves
  • HCV-248
  • HCV-239
6. At the Shift Managers discretion, place TCV-211-2, Ion Exchangers Bypass Valve to BYP IX.
7. Place HC-101-3, Limiter Bypass Switch, in BYPASS.
8. Place HIC-101-1/101-2, Letdn Throttle Valve Controller, in MANUAL.
9. Close the Letdown Ht Exch Throttle Valves:
  • LCV-101-1
  • LCV-101-2
10. Place HC-101-2, Ltdn Ht Exch Vlvs Selector Sw in the desired position per the Shift Manager.
11. Place PIC-210, Letdown Pressure Cntrlr, in MANUAL.
12. Throttle PIC-210 to approximately 10% open.

R76

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 9 OF 77 Attachment 1 - Startup of Charging and Letdown PROCEDURE (continued) (9) INITIALS

13. Position Charging Pumps Mode Select Stby switch to select the desired backup Charging Pumps start sequence:
  • CH-1B-1C CAUTION Pressurizer Level deviation will start standby charging pumps not in PULLOUT.
14. Start the selected charging pump:
15. Open the following Letdown Isolation Valves:
  • HCV-204, RC to Ltdn Ht Exch Isolation Valve
  • TCV-202, Ltdn to Regen Ht Exch Isolation Valve
16. Using HIC-101-1/101-2 initiate Letdown flow while adjusting PCV-210 to maintain Letdown pressure approximately 300 psig.
17. Balance Charging and Letdown flows to maintain Pressurizer level.
18. Place HC-101-3 in NORMAL.
19. If desired, place the following controllers in AUTO:
  • HIC-101-1/101-2 per OI-RC-8
  • PIC-210
20. If desired, place CVCS ion exchangers in service per OI-CH-2.
21. If desired, check Letdown Pulsation Dampener Pressures per OI-CH-1, Attachment 6.
22. Evaluate the evolution for appropriate Equipment/System Usage Cycles.

Completed by Date/Time /

R76

FORT CALHOUN STATION OI-RC-8 OPERATING INSTRUCTION PAGE 9 OF 20 C

Continuous Use Attachment 3 - Transferring Letdown Controller from MANUAL to AUTOMATIC PREREQUISITES (9) INITIALS

1. Procedure Revision Verification Revision No. 13 Date: 3/31/09 JEK
2. 120 Volt AC System is in normal operation per OI-EE-4. JEK
3. Instrument Air is in operation per OI-CA-1. JEK
4. CB-1/2/3 Instrumentation and Alarms are operable. JEK PROCEDURE
1. Ensure Letdown Controller HIC-101-1/101-2, Letdn Throttle Valves Controller is in (M) MANUAL.
2. Manually adjust HIC-101-1/101-2 AND PIC-210, Letdown Press Cntrlr until the following parameters are met:
  • Indicated Pressurizer Level (red pen) matches the Programmed Level Setpoint (green pen) on LR-101X or LR-101Y, Pressurizer Level Recorder.
  • PIC-210 is maintaining 200 psi to 400 psi.
3. Adjust the bias on HIC-101-1/101-2 until the top scale indicates 50% (zero deviation; red pointer aligned with the red dot).
4. Place HIC-101-1/101-2 Manual/Auto Transfer Switch to BAL, then to AUTO.
5. IF necessary, THEN make fine adjustments to the bias of HIC-101-1/101-2 to ensure Pressurizer Level is maintained at setpoint.

Completed by Date/Time /

R13

FORT CALHOUN STATION OI-ST-12 OPERATING INSTRUCTION PAGE 13 of 19 C

Continuous Use Attachment 7 - Normal Rotation of Electrohydraulic Pumps PREREQUISITES (%) INITIALS

1. Procedure Revision Verification Revision No. 23 Date: 3/31/09 JEK
2. Standby EHC Pump is in AFTERSTOP. (CB-10) JEK
3. Coordination established with Control Room and Turbine Building operator. JEK
4. Turbine Plant Cooling Water System is operable and available to the applicable Electrohydraulic Pump Oil Coolers EHC-6A/6B per OI-BW-1. JEK
5. Electrical Distribution is aligned per OI-EE-2. JEK PROCEDURE NOTE The EHC Pumps are positive displacement pumps. Minimize time both pumps are in service since each pump tries to take the EHC System load causing pressure oscillations which could affect turbine valves.
1. Start the Standby EHC Pump by placing its control switch in AFTER-START (CB-10/11):

! EHC-3A

! EHC-3B

2. Ensure any pressure oscillations in the EHC System are dampened and stabilized indicating greater than 1500 psig on PI-2101 (CB-10).
3. Check just started EHC Pump Motor current is approximately 40 to 50 amps.

(CB-10/11)

! EHC-3A

! EHC-3B R23

FORT CALHOUN STATION OI-ST-12 OPERATING INSTRUCTION PAGE 14 of 19 C

Continuous Use Attachment 7 - Normal Rotation of Electrohydraulic Pumps PROCEDURE (continued) (%) INITIALS

4. Check proper local operation of EHC System as follows:

! Check PI-5116, Pump EHC-3A Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure

! Check PI-5115, Pump EHC-3B Discharge Pressure, is approximately equal to PI-2101A, EHC Supply Header Pressure

! For the pump started:

- Verify no bubbles are visible in EHC-2A, Hydraulic Fluid Pump EHC-3A Suction Strainer, Bull=s eye

- Verify no bubbles are visible in EHC-2B, Hydraulic Fluid Pump EHC-3B Suction Strainer, Bull=s eye

5. Stop EHC Pump to be placed in Standby by placing EHC Pump Control Switch in AFTERSTOP

! EHC-3A

! EHC-3B

6. IF Running EHC Pump fails to maintain adequate pressure, THEN Start Standby EHC Pump.

Completed by Date/Time /

R23

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 10 OF 77 Attachment 2 - Shutdown of Charging and Letdown PREREQUISITES (9) INITIALS

1. Procedure Revision Verification 76 JEK Revision No. Date: 3/31/09
2. Zinc Injection is secured. JEK
3. Tech Spec 2.2 has been referenced. JEK PROCEDURE NOTE If CVCS is shutdown during RCP operation, Pressurizer Level will decrease at a rate equivalent to RCS Leakage and RCP Bleedoff flow.
1. Place TCV-211-2, Ion Exchangers Bypass Valve, in BYP IX.
2. Close TCV-202, Ltdn to Regen Ht Exch Isolation Valve.
3. Close HCV-204, RC to Ltdn Ht Exch Isolation Valve.
4. Stop all operating Charging Pumps:
5. IF desired THEN place all Charging Pumps in PULL-OUT:
6. Close the following charging isolation valves: (AR 13140)
  • HCV-238, Charg to RC Loop 1A Isolation Valve
  • HCV-239, Charg to RC Loop 2A Isolation Valve R76

FORT CALHOUN STATION OI-CH-1 OPERATING INSTRUCTION CONTINUOUS USE PAGE 11 OF 77 Attachment 2 - Shutdown of Charging and Letdown PROCEDURE (continued)

7. Stop the Packing Cooling Pumps a minimum of 30 minutes after stopping Charging Pump(s):
8. Evaluate the evolution for appropriate Equipment/System Usage Cycles.

Completed by Date/Time /

R76

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