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{{#Wiki_filter:ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point 1 Examination Level: RO Date of Examination:
{{#Wiki_filter:ES-301, Rev. 9                               Administrative Topics Outline                                   Form ES-301-1 Facility: Nine Mile Point 1                                   Date of Examination:        December 11, 2006 Examination Level: RO                                         Operating Test Number:                 NA Administrative Topic                   Type        Describe activity to be performed (see Note)                     Code*
Operating Test Number:
Perform N1-ST-DO, Daily Checks (Partial)
NA December 11, 2006 Administrative Topic (see Note) Conduct of Operations Plant parameter Verification RO ADMIN 1 Conduct of Operations Configuration Control RO ADMIN 2 Equipment Control Use of Electrical Prints RO ADMIN 3 Radiation Control Radiation Hazards RO ADMIN 4 Type Code* D N N M, P NRC 2004 Describe activity to be performed Perform N1-ST-DO, Daily Checks (Partial)
Conduct of Operations                                    Record control room instrument readings for recirc loop Plant parameter                                        temperatures, reactor water level instruments and hotwell level.
Record control room instrument readings for recirc loop temperatures, reactor water level instruments and hotwell level. With tech spec readings out of spec for RPV water level and hotwell level, identify impact on Tech Spec related equipment.
Verification                                  D        With tech spec readings out of spec for RPV water level and hotwell level, identify impact on Tech Spec related equipment.
Readings are taken in the simulator and entered into the applicable sections of the Daily Checks.
RO ADMIN 1                                              Readings are taken in the simulator and entered into the applicable sections of the Daily Checks.
2.1 .I8 (2.9) Ability to make accurate / clear and concise logs I records I status boards I and reports. GAP-OPS-01; 3.10, N1-ST-DO section 6.0, 7.0 and 8.0 Determine Plant Impact of Mispositioned Liquid Poison Components Evaluate system lineup, determine both Liquid Poison Pumps are not available to inject. Identify the Tech Spec impact. 2.1 .I 1 (3.0) Knowledge of less than one hour technical specifications for systems. DWG C-18019-C; N1-OP-12, Tech Spec 3.1.2 RPS Logic Operation with EOP-3.1 RPS Jumpers Installed Identify and locate electrical drawings related to RPS circuits.
2.1 . I 8 (2.9) Ability to make accurate / clear and concise logs I records I status boards Iand reports.
Use the drawings to describe the effect of installing RPS jumpers on how scram signal is reset prior to initiating another manual scram, with the jumpers installed under failure to scram conditions. (Perform in simulator and supply with copies for candidate to mark-up).
GAP-OPS-01; 3.10, N1-ST-DO section 6.0, 7.0 and 8.0 Determine Plant Impact of Mispositioned Liquid Poison Components Conduct of Operations                        N          Evaluate system lineup, determine both Liquid Poison Pumps Configuration Control                                    are not available to inject. Identify the Tech Spec impact.
2.1 24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.
RO ADMIN 2 2.1. I 1 (3.0) Knowledge of less than one hour technical specifications for systems.
N1-EOP-3.1; Drawincl C-19859-C SH 4 and 7 Radiological Requirements Related Entry Into High Radiation Areas Given radiological conditions and a survey map related to an area to be inspected, ensure the appropriate radiological aspects of the job are met prior to performance of the inspection. 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
DWG C-18019-C; N1-OP-12, Tech Spec 3.1.2 RPS Logic Operation with EOP-3.1 RPS Jumpers Installed N          Identify and locate electrical drawings related to RPS circuits.
GAP-RPP-02; 3.1, 3,3.
Equipment Control                                        Use the drawings to describe the effect of installing RPS Use of Electrical Prints                                jumpers on how scram signal is reset prior to initiating another RO ADMIN 3                                              manual scram, with the jumpers installed under failure to scram conditions. (Perform in simulator and supply with copies for candidate to mark-up).
GAP-RPP-08; 3.2, 3.3 N0TE: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.
2.12 4 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.
* 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)revtous 2 exams ( 1, randomly selected) 1 012412006 10:29:08 AM 1of1 2006 Unit 1 NRC RO Admin Outline Submittal Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Perform N1 -ST-DO DAILY CHECKS (Partial)
N1-EOP-3.1; Drawincl C-19859-C SH 4 and 7 Radiological Requirements Related Entry Into High Radiation Control                                        Radiation Areas Radiation Hazards                          M, P        Given radiological conditions and a survey map related to an RO ADMIN 4                              NRC 2004        area to be inspected, ensure the appropriate radiological aspects of the job are met prior to performance of the inspection.
Task Number: Amrovals: Genpral Supervi6or Date Operations Training (Designee)
2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
Revision:
GAP-RPP-02; 3.1, 3,3. GAP-RPP-08; 3.2, 3.3 N0TE: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.
NRC 2006 NA EXAM SECURITY I General Supervisor Date Operations (Designee) NA EXAM SECURITY I Configuration Control Date Performer: (ROISRO) TrainerIEvaluator: Evaluation Method:
* Type Codes & Criteria (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs, ~ 4 for SROs & RO retakes)
X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:
(N)ew or (M)odified from bank ( - 1)
NO Start Time: Stop Time: Completion Time: JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
(P)revtous 2 exams (   1, randomly selected) 1012412006 10:29:08 AM                                   1of1 2006 Unit 1 NRC RO Admin Outline Submittal
 
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Perform N1-ST-DO DAILY CHECKS (Partial)                               Revision: NRC 2006 Task Number:
Amrovals:
NA EXAM SECURITY              I Genpral Supervi6or                     Date                  General Supervisor              Date Operations Training (Designee)                                 Operations (Designee)
NA EXAM SECURITY                       I Configuration Control                   Date Performer:                                             (ROISRO)
TrainerIEvaluator:
Evaluation Method:       X       Perform                       Simulate Evaluation Location:             Plant                 X       Simulator or other location Expected Completion Time: 20 min               Time Critical Task:   NO     Alternate Path Task: NO Start Time:                     Stop Time:                     Completion Time:
JPM Overall Rating:             Pass           Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Comments:
Evaluator Signature:
Evaluator Signature:                                                 Date:
Date: NRC RO ADMIN JPM 1 October 2006 Recommended Start Location: (Completion time based on the start location)
NRC RO ADMIN JPM 1           October 2006
If actual readings are to be taken, Simulator must be setup and used, otherwise perform in other designated area. Simulator Set-up:
 
IC-238 contains setup conditions for Admin JPMs
Recommended Start Location: (Completion time based on the start location)
: 1. TURN OFF PI MONITOR. JPM readings are taken with simulator in FREEZE. Establish 70% reactor power, 40 mlb/hr total recirc flow, align Feedwater Level Column to 72, and override reactor water level and hotwell level instruments as necessary to read those indicated in the Attachment. Override both hotwell indication to 55 inches and activate crywolf for alarms H2-2-7 and 3-7 for low level, Directions to the Instructor/Evaluator: Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM I CSO permission.
If actual readings are to be taken, Simulator must be setup and used, otherwise perform in other designated area.
Directions to Operators: Read Before Every JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Simulator Set-up:
IC-238 contains setup conditions for Admin JPMs 1. TURN OFF PI MONITOR. JPM readings are taken with simulator in FREEZE.
Establish 70% reactor power, 40 mlb/hr total recirc flow, align Feedwater Level Column to 72, and override reactor water level and hotwell level instruments as necessary to read those indicated in the Attachment. Override both hotwell indication to 55 inches and activate crywolf for alarms H2-2-7 and 3-7 for low level, Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM I CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance: During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker. Notes to Instructor  
Repositioning of devices will be simulated by discussion and acknowledged by my cues.
/ Evaluator:
Read Before Each Evaluated JPM Performance:
: 1. Critical steps are identified in grading areas PasslFail.
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
All steps are sequenced critical unless denoted by a "e". 2. During Evaluated JPM:
Read Before Each Traininq JPM Performance:
0 3. During Training JPM: Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated. NRC RO ADMlN JPM 1 October 2006
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a e.
: 2. During Evaluated JPM:
0   Self checking shall be demonstrated.
: 3. During Training JPM:
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
NRC RO ADMlN JPM 1       -2  -    October 2006


==References:==
==References:==
: 1. GAP-OPS-01; 3.10. 2. N1-ST-DO; 6.0, 7.0 and 8.0. 3. 2.1 .I8 (2.9) Ability to make accurate / clear and concise logs  
: 1. GAP-OPS-01; 3.10.
/ records / status boards  
: 2. N1-ST-DO; 6.0, 7.0 and 8.0.
/ and reports.
: 3. 2.1 . I 8 (2.9) Ability to make accurate / clear and concise logs / records / status boards / and reports.
Tools and Equipment:
Tools and Equipment:
: 1. None Task Standard:
: 1. None Task Standard:
Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
Initial Conditions:
Initial Conditions:
: 1. 2. 3. 4. The plant is operating at 75% power. Surveillance test N1 -ST-DO, DAILY CHECKS, is in progress ALL computer point readings are consistent with control room panel instrument readings.
: 1.       The plant is operating at 75% power.
Ask the operator for any questions.
: 2.        Surveillance test N1-ST-DO, DAILY CHECKS, is in progress
Initiating cue: "(Operator's name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment I sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO". 1. Provide repeat back of initiating cue. Evaluator A ckn o wle dge rep eat back providing correction if necessary RECORD START TIME 1. 2. 3. *Obtain a copy of the reference procedure and review/utilize the correct section. *Records section 6.0 Reactor Recirc Pump Inlet Temperature readings Compares reading and determines readings within 15°F Proper communications used for repeat back (GAP-OPS-01 ) N-ST-DO obtained. - Section 6.0, 7.0 and 8.0 referenced. NOTE: Completed N1-ST-DO is provided as an Attachment 2 to this JPM. Records Reactor Recirc Pump Inlet Temperature readings. Compares reading and determines readings within 15°F of each other.
: 3.        ALL computer point readings are consistent with control room panel instrument readings.
Checks YES block in Section 6.0, indicating the maximum difference in loop temperatures is < 15&deg;F. Sat/Unsat SatlUnsat Sa tlU nsat PasslFail PasslFail NRC RO ADMIN JPM 1 October 2006
: 4.        Ask the operator for any questions.
: 4. .Records section 7.0 readings.
Initiating cue:
: 5. .Compares YARWAY Chll - Ch12 (RPS Level Column) instrument readings to guide values. 6. .Performs GEMAC Chll - Ch12 variance check per Section 7.1. 7. .Records section 8.0 Condensate readings
(Operators name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment Isections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO.
: 8. Provides completed sections to SRO. Informs of out of spec readings. Recorded Section 7.0 "LOW-Low Level alarm" and "Feedwater Level Column selected to" checks agree with Attachment 1 without error. Recorded Section 7.0 instrument readings agree with Attachment 1 within k 1 inch. Record Total Recirc Flow per step 7.1.2 for GEMAC variance check. Determines YARWAY (RPS Level Column) instrument readings differ by 5" which is above the guide value of 4". Determines YARWAY (RPS Level Column) instruments OPERABLE. Indicates an ACR is required to have the calibration checked. Determines GEMAC variance is 6" Compares GEMAC variance to total recirc flow and determines on line between ALERT RANGE and INOP. Determines that GEMAC I1 or GEMAC 12 must be declared inoperable.
: 1. Provide repeat back of initiating       Proper communications used for repeat          Sat/Unsat cue. Evaluator A cknowle dge repeat        back (GAP-OPS-01 )
Reports out of specification readings to SRO. Records Condensate readings Determines Hotwell level is below 57 inches (Tech Spec Minimum)
back providing correction if necessary RECORD START TIME
Informs SRO Hotwell level is below 57 inches (Tech Spec Minimum).  
: 1. *Obtain a copy of the reference         N-ST-DO obtained.                             SatlUnsat procedure and review/utilize the      - Section 6.0, 7.0 and 8.0 referenced.
<Ref 2> is TS 3.1.8, HPCl is inoperable.
correct section.
SRO informed of out of spec readings.
NOTE: Completed N1-ST-DO is provided as an Attachment 2 to this JPM.
PasslFail PasslFail Sat/Unsat Sat/Unsat PasslFail Sat/Unsat SatlUnsat SatlUnsat PasslFail PasslFail Sat/Unsat PasslFail PasslFail PasslFail Sat/Unsat End of JPM TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
2 . *Records section 6.0 Reactor           Records Reactor Recirc Pump Inlet              Sa tlU nsat Recirc Pump Inlet Temperature         Temperature readings.
RECORD STOP TIME NRC RO ADMIN JPM 1 October 2006 Initial Conditions:
readings
: 1. The plant is operating at 75% power. 2. Surveillance test N1-ST-DO, DAILY CHECKS, is in progress 3. ALL computer point readings are consistent with control room panel
: 3. Compares reading and                    Compares reading and determines                 PasslFail determines readings within 15&deg;F      readings within 15&deg;F of each other.
: 4. Ask the operator for any questions. instrument readings.
Checks YES block in Section 6.0,               PasslFail indicating the maximum difference in loop temperatures is < 15&deg;F.
Initiating cue: "(Operator's name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment 1 sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO". NRC RO ADMlN JPM 1 October 2006 I Setup Attachment Override Value Settings Panel Meter Meter Reading Obtained K-Panel Flange Level Indicator (K Panel: ta ~ig~~ of ~$-~$~ Reactor Vessel Level Recorder (F Panel: 36-SSJ I 70'5 1 k:hes 1 E-Panel Vessel Level Indicator (E Panel iD59~) ~~ ~ ~ None Below -3 72.5 74 ft inches 1 75 1 k:hes K-Panel Vessel Level Indicator (K Panel: 36-96 ID5 Wide Range Level Indicator (FPane/: 36-94) I Ch 11 7.2 6 ft Ch 12 11 12 GEMAC Level Column (F ane el: 36-76A, I 77.5 I 69.5 1 79-80; 73 1 ~6~~~A} ~ RPS Level Column <Ref 1 > (F Panel: 36-76 ~~ 1 F NRC RO ADMIN JPM 1 October 2006  
NRC RO ADMIN JPM 1                 October 2006
- ATTACHMENT 1 (Cont) -- ANSWER KEY. DO NOT PROVIDE TO APPLICANT Reactor Recirc Pump Inlet Temperature RRP 11 Inlet Temp RRP 12 Inlet Temp RRP 13 Inlet Temp RRP 14 Inlet Temp RRP 15 Inlet Temp Maximum difference in loop temperatures 15&deg;F 7.0 Control Room Reactor Water Level Checks Low-Low Level Alarms IF YES, provide reason in Remarks Feedwater Level Column selected to (E Pane!] 520 OF 525 OF 520 OF 530 OF 520 OF YES No OYES BNO El11 12 I E-Panel Vessel Level Indicator
: 4. .Records section 7.0 readings. Recorded Section 7.0 LOW-LowLevel        PasslFail alarm and Feedwater Level Column selected to checks agree with Attachment 1 without error.
(*Panel) I 73 I inches I I K-Panel Vessel Level Indicator (K Panel: 36-96) I 76 I inches I I c-3 vet- 1 K-Panel Flange Level Indicator (K Panel: to ~ig~~ of I Reactor Vessel Level Recorder (F Pane/: 36-98) I 74 1 inches I I Wide Range Level Indicator (f Pane/: 36-94] I 6 I feet I If reading difference is greater than the guide valve, review previous readings for the instrument(s). If a single reading is the cause for the recorded value being greater than the guide value, verify that reading.
Recorded Section 7.0 instrument         PasslFail readings agree with Attachment 1 within k 1 inch.
If reading difference is still greater than guide value, consider the indicator OPERABLE and generate an ACR to have the calibration checked. If reading difference is grossly greater than guide value, consider the indicator INOPERABLE, enter applicable Tech Spec action and generate an ACR. See Section 7.1 ** If the difference between Yarway indicators Ll-36-09 and LI-36-10 is 6" or greater, *** THEN declare the following instruments inoperable and initiate the required Technical Specification actions (ESA for DER 1-2001-3027):
Sat/Unsat Record Total Recirc Flow per step 7.1.2 for GEMAC variance check.
LT-36-03C, LT-36-03D LT-36-04C, LT-36-04D LT-36-216, LT-36-21 D NRC RO ADMlN JPM 1 October 2006 ATTACHMENT 1 (Cont) ANSWER KEY.
: 5. .Compares YARWAY C h l l -        Determines YARWAY (RPS Level            Sat/Unsat Ch12 (RPS Level Column)            Column) instrument readings differ by 5 instrument readings to guide      which is above the guide value of 4.
DO NOT PROVIDE TO APPLICANT 7.1 GEMAC Variance Check 7.1 .I Calculate Variance Between Ch 12 and Ch 11 GEMAC Level Recorders.
values.
73 6 / / - Ch 12 Ch 11 Variance (in.) Ind. Verif 7.1.2 Record Total Recirc Flow 40 MllblHr {E init / date 7.1.3 Verify GEMAC 1111 2 Variance as a function of Total Recirc Flow is in the Acceptable Range as determined in the Graph below. (Note, ignore negative sign, if any.) 0 Yes (Sat) 4 No (Unsat), DER Required init / date If results are in ALERT range, generate DER for Engineering Evaluation.
Determines YARWAY (RPS Level             PasslFail Column) instruments OPERABLE.
If results are in INOP range, declare GEMAC 11 and/or 12 INOP. GEMAC LEVEL COLUMN 11 / 12 VARIANCE 10 9 8 v) w7 I 0 F6 55 -14 x3 n > 0, crr - 2 1 0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 Total Recirc Flow wlb/Hr) NRC RO ADMIN JPM 1 October 2006
Indicates an ACR is required to have the Sat/Unsat calibration checked.
: 6. .Performs GEMAC C h l l - Ch12    Determines GEMAC variance is 6         SatlUnsat variance check per Section 7.1.
Compares GEMAC variance to total         SatlUnsat recirc flow and determines on line between ALERT RANGE and INOP.
Determines that GEMAC I 1 or GEMAC       PasslFail 12 must be declared inoperable.
Reports out of specification readings to PasslFail SRO.
: 7.  .Records section 8.0              Records Condensate readings              Sat/Unsat Condensate readings Determines Hotwell level is below 57     PasslFail inches (Tech Spec Minimum)
Informs SRO Hotwell level is below 57   PasslFail inches (Tech Spec Minimum).
                                      <Ref 2> is TS 3.1.8, HPCl is inoperable. PasslFail
: 8. Provides completed sections to    SRO informed of out of spec readings. Sat/Unsat SRO. Informs of out of spec readings.
End of JPM TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
RECORD STOP TIME NRC RO ADMIN JPM 1               October 2006
 
Initial Conditions:
: 1. The plant is operating at 75% power.
: 2. Surveillance test N1-ST-DO, DAILY CHECKS, is in progress
: 3. ALL computer point readings are consistent with control room panel instrument readings.
: 4. Ask the operator for any questions.
Initiating cue:
(Operators name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment 1 sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO.
NRC RO ADMlN JPM 1     October 2006
 
I Setup Attachment Panel Meter                                                 Override      Meter Value          Reading Settings      Obtained 1 E-Panel Vessel Level Indicator (E Panel i D 5 9 ~ )
I   70'5   1   k:hes K-Panel Vessel Level Indicator (K Panel: 36-96 ID5 1     75
                                                                        ~~
1 ~
k:hes
                                                                                      ~
K-Panel Flange Level Indicator (K Panel: ta ~    i of g  ~  None
                                                                  ~            Below -3
    ~ $ - ~ $ ~                                                                ft Reactor Vessel Level Recorder      (F Panel: 36-SSJ            72.5        74 inches Wide Range Level Indicator   (FPane/: 36-94)                   7.2       6 ft I Ch 11          Ch 12         11     12 1 GEMAC Level Column ( F ane el: 36-76A,
    ~  6  ~ ~  ~ A  }
I   77.5       I   69.5   1   79-80; 73
                                    ~
RPS Level Column <Ref 1> (F Panel: 36-           76   ~~ 1  - 7 2 - F NRC RO ADMIN JPM 1             October 2006


Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Plant Impact of Mispositioned Liquid Poison Components Revision: NRC 2006 Task Number:
-    -                -
Ap prova Is : NA EXAM SECURITY I Operations (Designee)
ATTACHMENT 1 (Cont)
G e n $a I S u pe rvi sqfr Date General Supervisor Date Operations Training (Designee)  
ANSWER KEY. DO NOT PROVIDE TO APPLICANT Reactor Recirc Pump Inlet Temperature RRP 11 Inlet Temp                                                              520    OF RRP 12 Inlet Temp                                                              525    OF RRP 13 Inlet Temp                                                              520    OF RRP 14 Inlet Temp                                                              530    OF RRP 15 Inlet Temp                                                              520    OF Maximum difference in loop temperatures        15&deg;F                      YES        No 7.0      Control Room Reactor Water Level Checks Low-Low Level Alarms IF YES, provide reason in Remarks                                        OYES      BNO Feedwater Level Column selected to (E Pane!]                              El11        12 I E-Panel Vessel Level Indicator    (Panel)                    I    73    I inches    I I K-Panel Vessel Level Indicator    (K Panel: 36-96)            I    76    I inches    I K-Panel Flange Level Indicator (K Panel: to ~
/,&3b!mc.
I Reactor Vessel Level Recorder      (F Pane/: 36-98) i of g II ~ ~
NA EXAM SECURITY I Configuration Control Date Performer: (RO) TrainerIEvaluator: Evaluation Method:
c-3 74 vet-1 inches 1 I I Wide Range Level Indicator        ( f Pane/: 36-94]          I    6      I feet      I If reading difference is greater than the guide valve, review previous readings for the instrument(s). If a single reading is the cause for the recorded value being greater than the guide value, verify that reading. If reading difference is still greater than guide value, consider the indicator OPERABLE and generate an ACR to have the calibration checked. If reading difference is grossly greater than guide value, consider the indicator INOPERABLE, enter applicable Tech Spec action and generate an ACR.
X Perform Simulate Eva I ua t ion Location : Plant X Simulator or other location Expected Completion Time:
  **          See Section 7.1
15 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:
  ***        If the difference between Yarway indicators Ll-36-09 and LI-36-10 is 6" or greater, THEN declare the following instruments inoperable and initiate the required Technical Specification actions (ESA for DER 1-2001-3027):
JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
LT-36-03C, LT-36-03D LT-36-04C, LT-36-04D LT-36-216, LT-36-21D NRC RO ADMlN JPM 1              October 2006
Evaluators Signature:
 
Date: NRC RO ADMIN JPM 2 October 2006 Simulator or other designated location with prints and procedures available Simulator Set-up (if required):
ATTACHMENT 1 (Cont)
NA Directions to the Instructor/Evaluator: Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CSO permission. Directions to Operators: Read Before Every JPM Performance:
ANSWER KEY. DO NOT PROVIDE TO APPLICANT 7.1    GEMAC Variance Check 7.1. I Calculate Variance Between Ch 12 and Ch 11 GEMAC Level Recorders.
73        -    79      --      6                              /
Ch 12                    Ch 11          Variance (in.)
                                                                              /
Ind. Verif 7.1.2 Record Total Recirc Flow              40      MllblHr {E              init / date 7.1.3 Verify GEMAC 11112 Variance as a function of Total Recirc Flow is in the Acceptable Range as determined in the Graph below. (Note, ignore negative sign, if any.)
0 Yes (Sat)        4 No (Unsat), DER Required            init / date If results are in ALERT range, generate DER for Engineering Evaluation.
If results are in INOP range, declare GEMAC 11 and/or 12 INOP.
GEMAC LEVEL COLUMN 11 / 12 VARIANCE 10 9
8 v) w 7 I
F 6 0
5 5
            >
          -
0,
          - 1 4 crr x
n 3 2
1 0
0  5    10  15  20  25  30  35  40  45  50  55 60    65  70 Total Recirc Flow wlb/Hr)
NRC RO ADMIN JPM 1          October 2006
 
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Plant Impact of Mispositioned Liquid Poison Components             Revision: NRC 2006 Task Number:
Ap provaIs:
                                      /,&3b!mc.                NA EXAM SECURITY             I Ge n$a I S upervisqfr                Date                     General Supervisor             Date Operations Training (Designee)                                 Operations (Designee)
NA EXAM SECURITY                     I Configuration Control                 Date Performer:                                             (RO)
TrainerIEvaluator:
Evaluation Method:     X       Perform                       Simulate EvaIuat ion Location :         Plant                 X       Simulator or other location Expected Completion Time: 15 min Time Critical Task:           NO     Alternate Path Task: NO Start Time:                   Stop Time:                     Completion Time:
JPM Overall Rating:           Pass           Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:                                                 Date:
NRC RO ADMIN JPM 2           October 2006
 
Simulator or other designated location with prints and procedures available Simulator Set-up (if required):
NA Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec.
Operability, operational status, or the effects are unknown, obtain specific SM / CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.
Repositioning of devices will be simulated by discussion and acknowledged by my cues.
The Control Room Supervisor has determined that a verifier is not available and that additional  
Read Before Each Evaluated JPM Performance:
/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor  
Notes to Instructor / Evaluator:
/ Evaluator: 1. Critical steps are identified in grading areas Pass/Fail.
: 1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a   0   .
All steps are sequenced critical unless denoted by a ''0''. 2. During Evaluated JPM:
: 2. During Evaluated JPM:
: 3. During Training JPM: Self checking shall be demonstrated.
Self checking shall be demonstrated.
Self checking shall be demonstrated. Peer checking shall be demonstrated.  
: 3. During Training JPM:
Self checking shall be demonstrated.
Peer checking shall be demonstrated.


==References:==
==References:==
: 1. P&ID C-18019-C
: 1. P&ID C-18019-C
: 2. N1-OP-I 2, Attchment2
: 2. N1-OP-I2, Attchment2
: 3. Tech Spec 3.1.2 Tools and Equipment:
: 3. Tech Spec 3.1.2 Tools and Equipment:
NRC RO ADMIN JPM 2 October 2006
NRC RO ADMIN JPM 2             October 2006
: 1. None Task Standard: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required. Initial Conditions:
: 1. N o n e Task Standard: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required.
Initial Conditions:
: 1. The plant is in operating at 100% power.
: 1. The plant is in operating at 100% power.
: 2. Red clearance is being applied to Liquid Poison Pump 12 for corrective maintenance on the pump. 3. You are the Independent Verifier for the red clearance. 4. The first clearance tag is found on Power Board 17B Breaker 42-38 and the breaker is disconnected and open.
: 2. Red clearance is being applied to Liquid Poison Pump 12 for corrective maintenance on the pump.
: 5. The next clearance tag is found on valve 41-07 and the valve is unlocked and closed. Initiating cue:  
: 3. You are the Independent Verifier for the red clearance.
"(Operator's name), determine plant impact of this configuration." Performance Steps Standard Grade
: 4. The first clearance tag is found on Power Board 17B Breaker 42-38 and the breaker is disconnected and open.
: 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary. RECORD START TIME 2. 2. 3. 4. 5. Consults reference documents to determine effect of the given component lineup. Identifies LP Pump 12 is unable to inject (inoperable), with PI3 178 42-38 open.
: 5. The next clearance tag is found on valve 41-07 and the valve is unlocked and closed.
Identifies LP Pump 11 is unable to inject (inoperable), with 41 -07 closed. Identifies tag applied to incorrect component.
Initiating cue:
Informs Control Room per GAP-OPS-01.
(Operators name), determine plant impact of this configuration.
Determines Tech Spec LCO conditions Proper communications used for repeat back (GAP-OPS-O1/
Performance Steps                                   Standard                               Grade
CNG-HU-1 .Ol-1001)
: 1. Provide repeat back of initiating cue. Proper communications used for repeat    SatlUnsat Evaluator Acknowledge repeat back        back (GAP-OPS-O1/ CNG-HU-1 .Ol-1001) providing correction if necessary.
Refers to any of the following documents to determine function of PB 17B breaker 42-38 and 41-07 N1-OP-12 P & ID C-18019-C Any other document that indicated power supply for LP Pump 12 and suction valve for LP Pump 11 are the affected com ponen ts Determines that with PB 17B BKR 42- 38 open and disconnected, LP Pump 12 is deenergized and inoperable.
RECORD START TIME
Determines that with 41-07 closed LP Pump 11 is inoperable because of loss of suction path.
: 2. Consults reference documents to                    Refers to any of the following         Sat/Unsat determine effect of the given component          documents to determine function of lineup.                                        PB 17B breaker 42-38 and 41-07 N1-OP-12 P & ID C-18019-C Any other document that indicated power supply for LP Pump 12 and suction valve for LP Pump 11 are the affected components
Determines that 41-1 1 should have been closed. Notifies CRS of improperly positioned com pone n ts and incorrect application of red clearance tag. Determines that these conditions SatlUnsat Sat/Unsat Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat NRC RO ADMIN JPM 2 October 2006 I Performance Steps Standard for liquid Poison are exceeded.
: 2. Identifies LP Pump 12 is unable to inject        Determines that with PB 17B BKR 42-    Pass/Fail (inoperable), with PI3 178 42-38 open.          38 open and disconnected, LP Pump 12 is deenergized and inoperable.
: 6. Refers to LCO 3.1.2 result in Tech Spec entry for the Liquid Poison system.
: 3. Identifies LP Pump 11 is unable to inject        Determines that with 41-07 closed LP   Pass/Fail (inoperable), with 41 -07 closed.                Pump 11 is inoperable because of loss of suction path.
Grade o Identifies LCO 3.1.2 Specification
: 4. Identifies tag applied to incorrect              Determines that 41-1 1 should have     Sat/Unsat component. Informs Control Room per            been closed.
: b. Sat/Unsat applies because the redundant component is also inoperable.
GAP-OPS-01.                                    Notifies CRS of improperly positioned Sat/Unsat com ponents and incorrect application of red clearance tag.
If a single pump was inoperable 7 days would be allowed to restore the inop Pump Since both are inoperable, specification e applies and an orderly shutdown must be initiated within one hour. 7. Determines that one subsystem must be Identifies the requirement to restore Pass/Fail restored to operable.
: 5. Determines Tech Spec LCO conditions              Determines that these conditions       Sat/Unsat NRC RO ADMIN JPM 2         October 2006
one of the redundant components to OPERABLE within one hour or an orderly shutdown is required End of JPM Terminating Cue: restored within one hour or an orderly shutdown is required. Determines both Liquid Poison subsystems are inoperable and one must be RECORD STOP TIME NRC RO ADMIN JPM 2 October 2006
 
: a. Com m u nications
I Performance Steps                                 Standard                               Grade for liquid Poison are exceeded.                  result in Tech Spec entry for the Liquid Poison system.
: b. Verification of Actions Per CNG-HU-1.01-1001 Per GAP-OPS-0 1 Per CNG-HU-1.01-1001 Per GAP-OPS-01
: 6. Refers to LCO 3.1.2                         o   Identifies LCO 3.1.2 Specification b. Sat/Unsat applies because the redundant component is also inoperable.
: c. Procedural CompliancelPlacekeeping Per CNG-HU-1.01-1001 Per N IP-PRO-01 Per GAP-OPS-01
If a single pump was inoperable 7 days would be allowed to restore the inop Pump Since both are inoperable, specification e applies and an orderly shutdown must be initiated within one hour.
: d. Safety Compliance Per N I P-OSH-01 Per Personnel Safety Manual
: 7. Determines that one subsystem must be             Identifies the requirement to restore Pass/Fail restored to operable.                           one of the redundant components to OPERABLE within one hour or an orderly shutdown is required End of JPM Terminating Cue:       Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required.
: e. Radiation Protection Compliance Per GAP-RPP-01 Per GAP-RPP-02 Sat/Unsat SatlUnsat SatlUnsat Sat/Unsat Sat/Unsat Overall Work Practice Competency Result PasslFail NOTE: 1. UNSAT in any competency area requires oral remediation of unsat area. 2. Fail in Overall Work Practice Competency Results requires review and evaluation of work practices using the Work Practices JPM (U1 using 01-REQ-SJE-WPJ-1-00 and U2 using 02-REQ-SJE-WPJ-2-00).
RECORD STOP TIME NRC RO ADMIN JPM 2           October 2006
NRC RO ADMIN JPM 2 October 2006 InGI Conditions:
: a. Com munications                              Per CNG-HU-1.01-1001                       Sat/Unsat Per GAP-OPS-0 1
: 1. 2. 3. 4. 5. The plant is operating at 100% power. Red clearance is being applied to LP PUMP 12 for corrective maintenance on the pump.
: b. Verification of Actions                      Per CNG-HU-1.01-1001                       SatlUnsat Per GAP-OPS-01
You are the Independent Verifier for the red clearance.
: c. Procedural CompliancelPlacekeeping           Per CNG-HU-1.01-1001                       SatlUnsat Per NIP-PRO-01 Per GAP-OPS-01
The first clearance tag is found on PB 17B Breaker 42-38 and the breaker is disconnected and open. The next clearance tag is found on valve 41-07 and the valve is closed. Initiating cue: "(Operator's name), determine plant impact of this configuration."
: d. Safety Compliance                           Per NIP-OSH-01                             Sat/Unsat Per Personnel Safety Manual
NRC RO ADMIN JPM 2 October 2006 JPM 2 Scorecard For Applicant Use - Determine plant impact of this configuration. Impact of Configuration on c System Impact on plant operation NRC RO ADMIN JPM 2 October 2006 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: N1 -EOP-3.1 RPS Jumper Operation Electrical Print Reading Revision:
: e. Radiation Protection Compliance             Per GAP-RPP-01                             Sat/Unsat Per GAP-RPP-02 Overall Work Practice Competency Result                                                   PasslFail NOTE:     1. UNSAT in any competency area requires oral remediation of unsat area.
NRC 2006 Task Number: N/A NA EXAMINATION SECURITY General Supervisor Operations Training (Designee) Operations (Designee)
: 2. Fail in Overall Work Practice Competency Results requires review and evaluation of work practices using the Work Practices JPM (U1 using 01-REQ-SJE-WPJ-1-00 and U2 using 02-REQ-SJE-WPJ-2-00).
NA EXAMINATION SECURITY Configuration Control Date Performer: (RO) Trai ne r/Eval ua tor: Evaluation Method:
NRC RO ADMIN JPM 2       October 2006
X Perform Simulate Eva1 ua t ion Location : Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:
 
NO Start Time: Stop Time: Completion Time: JPM Overall Rating:
I n G I Conditions:
Pass Fail NOTE: A JPM overall rating of fail shall be given if grade of unsat or individual competency area unsat requires a comment. critical step is graded as fail. Any Comments: Evaluator Signature: Date: NRC RO ADMIN JPM 3 Draft October 2006 Recommended Start Location: (Completion time based on the start location) For NRC Exam 2006, This Admin JPM is performed in Simulator.
: 1. The plant is operating at 100% power.
Simulator Set-up: None Directions to the Instructor/Evaluator:
: 2. Red clearance is being applied to LP PUMP 12 for corrective maintenance on the pump.
Directions to Operators: Read Before Every JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
: 3. You are the Independent Verifier for the red clearance.
Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.
: 4. The first clearance tag is found on PB 17B Breaker 42-38 and the breaker is disconnected and open.
The Control Room Supervisor has determined that a verifier is not available and that additional  
: 5. The next clearance tag is found on valve 41-07 and the valve is closed.
/ concurrent verification will not be provided; therefore it should not be requested. Read Before Each Training JPM Performance:
Initiating cue:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional  
(Operators name), determine plant impact of this configuration.
/ concurrent verifier.
NRC RO ADMIN JPM 2   October 2006
 
JPM 2 Scorecard For Applicant Use
                                            -
Determine plant impact of this configuration.
c Impact of Configuration on System Impact on plant operation NRC RO ADMIN JPM 2     October 2006
 
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: N1-EOP-3.1 RPS Jumper Operation Electrical Print Reading               Revision: NRC 2006 Task Number: N/A NA EXAMINATION SECURITY General Supervisor Operations Training (Designee)                       Operations (Designee)
NA EXAMINATION SECURITY Configuration Control         Date Performer:                           (RO)
Trainer/Evaluator:
Evaluation Method:     X       Perform                         Simulate Eva1uat ion Location :         Plant                 X         Simulator or other location Expected Completion Time: 20 min             Time Critical Task:       NO     Alternate Path Task:
NO Start Time:                   Stop Time:                     Completion Time:
JPM Overall Rating:           Pass           Fail NOTE: A JPM overall rating of fail shall be given if       critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:                                                     Date:
NRC RO ADMIN JPM 3 Draft             October 2006
 
Recommended Start Location: (Completion time based on the start location)
For NRC Exam 2006, This Admin JPM is performed in Simulator.
Simulator Set-up:
None Directions to the Instructor/Evaluator:
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.
Notes to Instructor I Evaluator:
Notes to Instructor I Evaluator:
: 1. 2. During Evaluated JPM:
: 1.       Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a 0 .
: 3. During Training JPM:
: 2.      During Evaluated JPM:
Critical steps are identified as PasslFail.
0   Self-verification shall be demonstrated.
All steps are sequenced critical unless denoted by a "0". 0 Self-verification shall be demonstrated.
: 3.      During Training JPM:
0 Self-verification shall be demonstrated.
0   Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.  
0   No other verification shall be demonstrated.


==References:==
==References:==
: 1. Drawing C-19859-C Sheet 4 and 7 2. N1-EOP-3.1, Alternate Control Rod Insertion
: 1. Drawing C-19859-C Sheet 4 and 7
: 3. K/A 2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings. Tools and Equipment:
: 2. N1-EOP-3.1, Alternate Control Rod Insertion
: 1. None. Task Standard: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.
: 3. K/A 2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.
NRC RO ADMIN JPM 3 Draft October 2006 Initial Conditions:
Tools and Equipment:
: 1. The plant is experiencing a failure to scram. 2. N1-EOP-3 has been entered. 3. EOP Director directs execution of EOP-3.1.
: 1. None.
Task Standard: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.
NRC RO ADMIN JPM 3 Draft               October 2006
 
Initial Conditions:
: 1. The plant is experiencing a failure to scram.
: 2. N1-EOP-3 has been entered.
: 3. EOP Director directs execution of EOP-3.1.
: 4. Repeated manual scrams will be attempted.
: 4. Repeated manual scrams will be attempted.
: 5. Ask the operator for any questions. Initiating cue: "(Operator's name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component (relays, contacts and switches) operation necessary to reset the RPS Channel 12 scram logic."
: 5. Ask the operator for any questions.
: 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 1. Obtain a copy of the necessary procedures and drawings 2. Using C-I 9859-C Sheet 7, locates trip circuits and jumpers. 3. Using C-19859-C Sheet 7, identifies the signals defeated when jumpers are installed. Proper communications used for repeat back (GAP-OPS-01)
Initiating cue: (Operators name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component (relays, contacts and switches) operation necessary to reset the RPS Channel 12 scram logic.
Sat/Unsat Obtains the following documents, as needed: N1-EOP-3.1 Sat/Unsat/NA Drawing Index, if needed Sat/Unsat/NA 0 Drawing C-I 9859-C Sheet 7 PasslFail Locates SCRAM BYPASS jumper PasslFail (EOP jumper 12) at drawing coordinate A-I to A-5, in REACTOR TRIP #I circuit. Locates SCRAM BYPASS jumper (EOP jumper 13) at drawing coordinate B-1 to B-5, in REACTOR TRIP #2 circuit. PasslFail Identifies that ALL AUTOMATIC PasslFail scram signal relay trip contacts are bypassed when jumper is installed. NOTE: The manual scram circuit is not bypassed by the jumpers. NRC RO ADMIN JPM 3 Draft October 2006
: 1. Provide repeat back of           Proper communications used for repeat        Sat/Unsat initiating cue. Evaluator       back (GAP-OPS-01)
: 4. Using C-19859-C Sheet 7, describes electrical component operation necessary to reset the scram. Indicates when jumper is installed in REACTOR TRIP  
Acknowledge repeat back providing correction if necessary RECORD START TIME
#I circuit, relay 12K51A (coordinate B-5) energizes and closes the following contacts:
: 1. Obtain a copy of the necessary             Obtains the following documents, as procedures and drawings                  needed:
0 PasslFail 12K51A L1-TI for GROUP 1 (coordinate D-2) 12K51A L2-T2 for GROUP 2 (coordinate E-2) 12K51A L3-T3 for GROUP 3 (coordinate F-2) 12K51A L4-T4 for GROUP 4 (coordinate G-2) 12K51A 7-8 for Backup Scram circuitry (coordinate H-2) 0 0 0 0 Indicates when jumper is installed in REACTOR TRIP  
N1-EOP-3.1                         Sat/Unsat/NA Drawing Index, if needed           Sat/Unsat/NA 0   Drawing C - I 9859-C Sheet 7         PasslFail
#2 circuit, relay 12K52A (coordinate C-5) energizes and closes the following contacts:
: 2. Using C - I 9859-C Sheet 7,                Locates SCRAM BYPASS jumper             PasslFail locates trip circuits and jumpers.        (EOP jumper 12) at drawing coordinate A-I to A-5, in REACTOR TRIP # I circuit.
0 PasslFail 12K52A L1-TI for GROUP 1 (coordinate D-2) 12K52A L2-T2 for GROUP 2 (coordinate E-2) 12K52A L3-T3 for GROUP 3 (coordinate F-2) 12K52A L4-T4 for GROUP 4 (coordinate G-2) 12K52A 7-8 for Backup Scram circuitry (coordinate H-2) 0 0 0 Indicates that depressing switch 1 S3, RESET REACTOR TRIP (SCRAM) pushbutton (coordinate C- 4), closes its 1 S3 7-8 contact and energizes relay 12K53 (coordinate C-5) (while reset button is depressed).
Locates SCRAM BYPASS jumper               PasslFail (EOP jumper 13) at drawing coordinate B-1 to B-5, in REACTOR TRIP #2 circuit.
SaVUnsat NRC RO ADMIN JPM 3 Draft October 2006 Indicates that Relay 12K53 Sat/Unsat energizing closes its 7-8 contact (coordinate D-4) and energizes relay 12K55 and 12K56 (coordinate D-5) in REACTOR MANUAL SCRAM circuit Indicates that Relay 12K55 energizing and closes the following contacts:
: 3. Using C-19859-C Sheet 7,                    Identifies that ALL AUTOMATIC             PasslFail identifies the signals defeated          scram signal relay trip contacts are when jumpers are installed.              bypassed when jumper is installed.
0 12K55 L1-TI for GROUP 1 (coordinate D-2) 12K55 L2-T2 for GROUP 2 (coordinate E-2) 12K55 L3-T3 for GROUP 3 (coordinate F-2) 12K55 L4-T4 for GROUP 4 (coordinate G-2) 12K55 7-8 for Backup Scram circuitry (coordinate H-2) 0 0 0 PasslFail Indicates that Relay 12K56 provides SatlUnsat a seal-in to keep 12K55 energized when 12K53 drops out after the scram reset pushbutton is released. Indicates that when all three contacts PasslFail in the four GROUP 1 through 4 circuits for 12K51A, 12K52A and 12K55 are closed the scram is reset (for channel 12). Four white lights on F and M panels are ON and the scram pilot solenoids are energized for RPS Channel 12.
NOTE: The manual scram circuit is not bypassed by the jumpers.
: 10. Reports JPM complete Reports JPM complete Sat/Unsat NRC RO ADMIN JPM 3 Draft October 2006 TERMINATING CUE: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained. RECORD STOP TIME October 2006 NRC RO ADMIN JPM 3 Draft Initial Conditions:
NRC RO ADMIN JPM 3 Draft             October 2006
: 1. The plant is experiencing a failure to scram. 2. N1-EOP-3 has been entered. 3. EOP Director directs execution of EOP-3.1.
: 4. Using C-19859-C Sheet 7,           Indicates when jumper is installed in       PasslFail describes electrical component    REACTOR TRIP #I         circuit, relay operation necessary to reset the  12K51A (coordinate B-5) energizes scram.                            and closes the following contacts:
0     12K51A L1-TI for GROUP 1 (coordinate D-2) 0    12K51A L2-T2 for GROUP 2 (coordinate E-2) 0    12K51A L3-T3 for GROUP 3 (coordinate F-2) 0    12K51A L4-T4 for GROUP 4 (coordinate G-2) 0    12K51A 7-8 for Backup Scram circuitry (coordinate H-2)
Indicates when jumper is installed in     PasslFail REACTOR TRIP #2 circuit, relay 12K52A (coordinate C-5) energizes and closes the following contacts:
0     12K52A L1-TI for GROUP 1 (coordinate D-2) 0    12K52A L2-T2 for GROUP 2 (coordinate E-2) 12K52A L3-T3 for GROUP 3 (coordinate F-2) 0    12K52A L4-T4 for GROUP 4 (coordinate G-2) 0    12K52A 7-8 for Backup Scram circuitry (coordinate H-2)
Indicates that depressing switch         SaVUnsat 1S3, RESET REACTOR TRIP (SCRAM) pushbutton (coordinate C-4), closes its 1S3 7-8 contact and energizes relay 12K53 (coordinate C-5) (while reset button is depressed).
NRC RO ADMIN JPM 3 Draft             October 2006
 
Indicates that Relay 12K53               Sat/Unsat energizing closes its 7-8 contact (coordinate D-4) and energizes relay 12K55 and 12K56 (coordinate D-5) in REACTOR MANUAL SCRAM circuit Indicates that Relay 12K55               PasslFail energizing and closes the following contacts:
0     12K55 L1-TI for GROUP 1 (coordinate D-2) 0    12K55 L2-T2 for GROUP 2 (coordinate E-2) 0    12K55 L3-T3 for GROUP 3 (coordinate F-2) 0    12K55 L4-T4 for GROUP 4 (coordinate G-2) 12K55 7-8 for Backup Scram circuitry (coordinate H-2)
Indicates that Relay 12K56 provides     SatlUnsat a seal-in to keep 12K55 energized when 12K53 drops out after the scram reset pushbutton is released.
Indicates that when all three contacts   PasslFail in the four GROUP 1 through 4 circuits for 12K51A, 12K52A and 12K55 are closed the scram is reset (for channel 12). Four white lights on F and M panels are ON and the scram pilot solenoids are energized for RPS Channel 12.
: 10. Reports JPM complete           Reports JPM complete                       Sat/Unsat NRC RO ADMIN JPM 3 Draft             October 2006
 
TERMINATING CUE: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.
RECORD STOP TIME NRC RO ADMIN JPM 3 Draft           October 2006
 
Initial Conditions:
: 1. The plant is experiencing a failure to scram.
: 2. N1-EOP-3 has been entered.
: 3. EOP Director directs execution of EOP-3.1.
: 4. Repeated manual scrams will be attempted.
: 4. Repeated manual scrams will be attempted.
: 5. Ask the operator for any questions.
: 5. Ask the operator for any questions.
Initiating cue: "(Operator's name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component operation necessary to reset the RPS Channel 12 scram logic." NRC RO ADMIN JPM 3 Draft October 2006
Initiating cue: (Operators name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component operation necessary to reset the RPS Channel 12 scram logic.
NRC RO ADMIN JPM 3 Draft           October 2006


Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Radiological Requirements Related to Entry Into Revision: NRC 2006 High Radiation Areas Task Number: N/A NA EXAMINATION SECURITY  
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Radiological Requirements Related to Entry Into             Revision: NRC 2006 High Radiation Areas Task Number: N/A
-- Genefal Supervisal/
        -    -                                              NA EXAMINATION SECURITY Genefal Supervisal/             Datd                       General Supervisor                         Date Operations Training (Designee)                             Operations (Designee)
Datd General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control           Date Performer:                               (RO)
NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)
Trainer/Evaluator:
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 10 minutes Time Critical Task: NO Alternate Path Task:
Evaluation Method:       X       Perform                             Simulate Evaluation Location:             Plant                     X         Simulator or other location Expected Completion Time: 10 minutes Time Critical Task: NO                 Alternate Path Task: NO Start Time:                     Stop Time:                         Completion Time:
NO Start Time: Stop Time:
JPM Overall Rating:             Pass             Fail NOTE: A JPM overall rating of fail shall be given if   critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Completion Time: JPM Overall Rating:
Comments:
Pass Fail NOTE: A JPM overall rating of fail shall be given if unsat or individual competency area unsat requires a comment.
Evaluator Signature:                                                           Date:
critical step is graded as fail. Any grade of Comments: Evaluator Signature: Date:
NRC RO ADMIN JPM 4                     October 2006
NRC RO ADMIN JPM 4 October 2006 Recommended Start Location: (Completion time based on the start location)
 
Simulator or other designated location. Simulator Set-up:
Recommended Start Location: (Completion time based on the start location)
N /A Directions to the InstructodEvaluator:
Simulator or other designated location.
Simulator Set-up:
N/A Directions to the InstructodEvaluator:
RWPs and survey maps are to be provided.
RWPs and survey maps are to be provided.
Directions to Operators: Read Before Everv JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Directions to Operators:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Therefore, either another individual or I will act as the independent verifier or peer checker. Notes to Instructor  
Notes to Instructor / Evaluator:
/ Evaluator:
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a ".".
: 1. 2. 3. Critical steps are identified in grading areas PasslFail.
: 2. During Evaluated JPM:
All steps are sequenced critical unless denoted by a ".". During Evaluated JPM:
0   Self checking shall be demonstrated.
0 During Training JPM: 0 Self checking shall be demonstrated.
: 3. During Training JPM:
Self checking shall be demonstrated. Peer checking shall be demonstrated.
0  Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References
References
: 1. GAP-RPP-01; 3.5. 2. GAP-RPP-02; 3.3. 3. GAP-RPP-08; 3.2. 4. GAP-RPP-07; 3.2.5 5. KIA 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
: 1. GAP-RPP-01; 3.5.
: 2. GAP-RPP-02; 3.3.
: 3. GAP-RPP-08; 3.2.
: 4. GAP-RPP-07; 3.2.5
: 5. KIA 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
Tools and Equipment:
Tools and Equipment:
: 1. None. Task Standard: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded. NRC RO ADMIN JPM 4 October 2006 Initial Conditions:
: 1. None.
Task Standard: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.
NRC RO ADMIN JPM 4                     October 2006
 
Initial Conditions:
: 1. Unit 1 is operating at 100% power.
: 1. Unit 1 is operating at 100% power.
: 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
: 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
Line 214: Line 374:
: 4. RWP and survey map are provided.
: 4. RWP and survey map are provided.
: 5. Ask the operator for any questions.
: 5. Ask the operator for any questions.
Initiating cue: "(Operator's name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
Initiating cue:
RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard."
(Operators name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel. RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard.
: 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 2. 3. 4. 5. 6. Classify the area. Determine highest on contact and general area dose rates and location, based on survey map Determines highest contamination levels in the room. Determine RWP and Task Number required for entry. Determines insufficient delta exposure to enter without additional approval. Proper communications used for repeat back (GAP-OPS-01)
: 1. Provide repeat back of initiating     Proper communications used for repeat          SatlUnsat cue. Evaluator Acknowledge         back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME NOTE: A score card is attached to this JPM identifying the items for the performer to identify.
NOTE: A score card is attached to this JPM identifying the items for the performer to identify. Determines the area is a HIGH RADIATION AREA. Determines highest on contact dose rate to be 500 mremlhr at 12 SDC Pump. Determines highest general area dose rate to be 100 mrem/hr near BV 38-03, 12 SDC Pump and 11 SDC Heat Exchanger. Determines highest contamination level to be 8000 dpm/lOO cm2 at 12 SDC Pump, smear location  
: 2. Classify the area.                      Determines the area is a HIGH             PasslFail RADIATION AREA.
#7. Determines RWP I06001 Task 2 is correct for the job. Determine within delta exposure of 300 mrem and additional approvals required prior to performing the inspection. (GAP-RPP-08 3.2.2, minimum delta exposure of 300 mRem needed to enter HRA). Admin limit of 2000 mr, from GAP-RPP-07.
: 3. Determine highest on contact              Determines highest on contact dose         PasslFail and general area dose rates and          rate to be 500 mremlhr at 12 SDC location, based on survey map            Pump.
Determines highest general area           PasslFail dose rate to be 100 mrem/hr near BV 38-03, 12 SDC Pump and 11 SDC Heat Exchanger.
: 4. Determines highest                       Determines highest contamination          PasslFail contamination levels in the room.        level to be 8000 dpm/lOO cm2at 12 SDC Pump, smear location #7.
: 5. Determine RWP and Task                    Determines RWP I06001 Task 2 is           PasslFail Number required for entry.              correct for the job.
6 . Determines insufficient delta            Determine within delta exposure of         PasslFail exposure to enter without                300 mrem and additional approvals additional approval.                    required prior to performing the inspection. (GAP-RPP-08 3.2.2, minimum delta exposure of 300 mRem needed to enter HRA). Admin limit of 2000 mr, from GAP-RPP-07.
2000 - 1800 = 200 mrem delta 300 mrem delta is required.
2000 - 1800 = 200 mrem delta 300 mrem delta is required.
SatlUnsat PasslFail PasslFail PasslFail PasslFail PasslFail PasslFail NRC RO ADMIN JPM 4 October 2006 End of JPM TERMINATING CUE: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.
NRC RO ADMIN JPM 4                     October 2006
RECORD STOP TIME NRC RO ADMIN JPM 4 October 2006 Initial Conditions:
 
: 1. Unit 1 is operating at 100% power. 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance
End of JPM TERMINATING CUE: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.
: 3. Current exposure is 1800 mrem TEDE. 4. RWP and survey map are provided.
RECORD STOP TIME NRC RO ADMIN JPM 4               October 2006
 
Initial Conditions:
: 1. Unit 1 is operating at 100% power.
: 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
: 3. Current exposure is 1800 mrem TEDE.
: 4. RWP and survey map are provided.
: 5. Ask the operator for any questions.
: 5. Ask the operator for any questions.
on BV 38-03 SDC Pump 11 suction handwheel.
Initiating cue:
Initiating cue: "(Operator's name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
(Operators name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel. RWP and survey maps are provided.
RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard."
Address the radiological aspects of performing this job and record findings on scorecard.
NRC RO ADMlN JPM 4 October 2006 I Answer the following when performing this task:
NRC RO ADMlN JPM 4       October 2006
I 0 High Radiation Area 0 Locked High Radiation Area 0 Very High Radiation Area
 
: 2. Designate the highest on contact dose rate in the area and the location AND the I highest general area dose rate and location:
I             Answer the following when performing this task:                   I 0 High Radiation Area 0 Locked High Radiation Area 0 Very High Radiation Area 2.
0 Acceptable 0 Additional approval(s) required NRC RO ADMIN JPM 4 October 2006 NOTE: THIS IS THE EXAMINER SCORECARD.
Designate the highest on contact dose rate in the area and the location AND the I highest general area dose rate and location:
0 Acceptable 0 Additional approval(s) required NRC RO ADMIN JPM 4             October 2006
 
NOTE: THIS IS THE EXAMINER SCORECARD.
DO NOT PROVIDE TO THE CANDIDATE.
DO NOT PROVIDE TO THE CANDIDATE.
Answer the following when performing this task:
Answer the following when performing this task:
J High Radiation Area Locked High Radiation Area 500 mrem/hr on contact at 12 SDC Pump I00 mrem/hr near BV38-03 and I1 SDC Pump, 12 SDC Pump and I1 SDC Heat Exchanger (east side of HX). 3. PasslFail Designate the highest contamination levels in the room and location:
J High Radiation Area Locked High Radiation Area 500 mrem/hr on contact at 12 SDC Pump I00 mrem/hr near BV38-03 and I 1 SDC Pump, 12 SDC Pump and I 1 SDC Heat Exchanger (east side of HX).
8,000 dpm/lOOcmZ at 12 SDC Pump at smear location #7 4. Pass/Fail 1 Designate the RWP and task number required to be used: RWP # 106001 Task 2 (because task is in Contaminated High Radiation Area) 5. PasslFail Evaluate delta exposure for entry into the area: (check one): 0 Acceptable  
: 3. PasslFail Designate the highest contamination levels in the room and location:
/Additional approval(s) required NRC RO ADMlN JPM 4 October 2006 Map No. 1 RB 261' Shut-Down Cooling Room 1 25b Nine Mile Point 1 Unit One I WORK ON HTX 202-84 / WO 051895400  
8,000 dpm/lOOcmZ at 12 SDC Pump at smear location #7
'I L Rx Power 100 % I H, lnj. Rate 6 scfrn I 1 Floor <400 4K e20 1K 1K 2K V - U (PMP-3 149) FCV-3809 (o/h) I /I I / I / I I *250 75 @ 38-05 PIPE TAPS - 50 @ DO NOT LINGER SIGN, WHICH IS ALSO AT BOTTOM OF LADDER TO SCAFFOLD (SHIELDED)
: 4. Pass/Fail Designate the RWP and task number required to be used:
I I INSULATED PIPES WITHIN REACH OF THE LADDER TRAVEL PATH 3, A = General Area Unless Noted
1 RWP # 106001 Task 2 (because task is in Contaminated High Radiation Area)
: 4. .* = $~~~~t 2. @ =SmearLocation
: 5. PasslFail Evaluate delta exposure for entry into the area: (check one):
= Rope/Area " - Boundary 5. A = Neutron (rnRemlhr)
0 Acceptable
: 6. IA/sI =Air Sample 7. @ = LargeArea Wipe 8. =Area Rad Monitor 9. v#I = VAMP Number 7 = Readings in mRernlhr.
/Additional approval(s) required NRC RO ADMlN JPM 4             October 2006
p = Readings in mRadlhr. Remarks: All overhead doserates were by use of the teletector Survevor:
 
i HENRY Dose:
1    Nine Mile Point Unit One 1         RB 261' Shut-Down     I Cooling Room                                   1   Map No.
9 mRem I Reviewed Bv:
25b WORK ON HTX 202-84                       /
Date I 10/24/2006 8: 19:28AM Page 1 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk. Inspections, Maintenance and Surveillances in High Radiation Areas. TASK: 1 High Radiation Area (HRA) 7391 Dose Alarm 50 mRem Dose Rate Alarm 500 mRemlHr Backoff Dose 40 mRem Protective Clothing Requirements:
WO 051895400 Rx Power           100 %
No Protective Clothing Required.
I H, lnj. Rate       6     scfrn   I 1     Floor     <400 4K     e20 1K 1K
                                                                                                                'I L
V          2K
                                                        -                                       U (PMP-3 149)
FCV-3809(o/h)
I
            / I                                                 /
I I                                             /
I                                     I
                    *250                               -
50 @ DO NOT LINGER SIGN, 75                              WHICH IS ALSO AT BOTTOM
        @ 38-05 PIPE TAPS                            I OF LADDER TO SCAFFOLD                           I (SHIELDED)
INSULATED PIPES WITHIN REACH OF THE LADDER TRAVEL PATH
    "
5.
8.
A=
          = Rope/Area
        - Boundary Neutron (rnRemlhr)
          =Area Rad Monitor 2.
6.
9.
                                    @  =SmearLocation IA/sI =Air Sample v#I    = VAMP Number 3,
7.
A
                                                                  @
                                                                    = General Area Unless Noted    4.
                                                                        = LargeArea Wipe
                                                                                          .*      = $      ~    ~
7 = Readings in mRernlhr. p = Readings in mRadlhr.
                                                                                                                          ~      ~    t Remarks:                       All overhead doserates were by use of the teletector Survevor:             i HENRY               Dose: 9 mRem       I Reviewed Bv:                                         Date                           I
 
10/24/2006 8: 19:28AM                                                                                           Page 1 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.
7391 Inspections, Maintenance and Surveillances in High Radiation Areas.
TASK: 1                                   High Radiation Area (HRA)
Dose Alarm                 50     mRem                 Dose Rate Alarm                 500   mRemlHr Backoff Dose               40     mRem Protective Clothing Requirements:               No Protective Clothing Required.
TLD, Electronic Dosimeter If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.
TLD, Electronic Dosimeter If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.
Instructions:
Instructions:
: 1) RPS approval and survey required for system breech.
: 1) RPS approval and survey required for system breech.
: 2) Pre-job briefing by RP required.
: 2) Pre-job briefing by RP required. Work crew will provide work area locations
Work crew will provide work area locations
: 3) HEPA Vacuums & Ventilation Units are radiological engineering instruments: To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
: 3) HEPA Vacuums  
& Ventilation Units are radiological engineering instruments:
To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
: 4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry
: 4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry
: 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.
: 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.
ALARA Review Number:
ALARA Review Number:
Survey Data: Radiation Levels: Turbine Building HRAs Reactor Building HRAs Rad Waste Buiding HRAs Off Gas Building HRAs 2 - 200mRem/hr 2 - 250mRemlhr 2 - GOOmRem/hr 2 - 120mRem/hr Contamination Levels: ~400 - 10,000 dpm/lOOcm2 Airborne Levels: ~0.3 DAC SDecific areas as Der RP briefina and / or survev maw. Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back 1 OI2412OO6 8: 19:28AM Page 2 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas.
Survey Data:
Low Radiological Risk. Inspections, Maintenance and Surveillances in Contaminated High Radiation Areas. TASK: 2 High Radiation Area (HRA) 7391 Dose Alarm 50 mRem Backoff Dose 40 mRem Dose Rate Alarm 500 mRem/Hr Protective Clothing Requirements:
Radiation Levels:
Single Full Set Of Protective Clothing Hood, Cotton Liners, Rubber Gloves (I), Cotton Boots (I), Rubbers (1) Coveralls (I), TLD, Electronic Dosimeter Radiation Protection Tech. may change protective clothing, respirator, or other requirements as work locations and conditions change. Leather gloves may be worn instead of rubber gloves for safety reasons.
Turbine Building HRAs           2 - 200mRem/hr Reactor Building HRAs          2 - 250mRemlhr Rad Waste Buiding HRAs          2 - GOOmRem/hr Off Gas Building HRAs          2 - 120mRem/hr Contamination Levels:           ~400 - 10,000 dpm/lOOcm2 Airborne Levels:               ~ 0 . 3DAC SDecific areas as Der RP briefina and / or survev maw.
When Leather gloves are worn, SURGEON gloves or RUBBER MUST be worn underneath them. Instructions:
Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back
 
1OI2412OO6 8: 19:28AM                                                                                             Page 2 o f 2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.
7391 Inspections, Maintenance and Surveillances in Contaminated High Radiation Areas.
TASK: 2                                   High Radiation Area (HRA)
Dose Alarm                 50     mRem                   Dose Rate Alarm                 500   mRem/Hr Backoff Dose              40    mRem Protective Clothing Requirements:               Single Full Set Of Protective Clothing Hood, Cotton Liners, Rubber Gloves (I),       Cotton Boots (I),   Rubbers (1)
Coveralls (I), TLD, Electronic Dosimeter Radiation Protection Tech. may change protective clothing, respirator, or other requirements as work locations and conditions change.
Leather gloves may be worn instead of rubber gloves for safety reasons. When Leather gloves are worn, SURGEON gloves or RUBBER MUST be worn underneath them.
Instructions:
: 1) RPS approval and survey required for system breech.
: 1) RPS approval and survey required for system breech.
: 2) Pre-job briefing by RP required.
: 2) Pre-job briefing by RP required. Work crew will provide work area locations
Work crew will provide work area locations
: 3) HEPA Vacuums & Ventilation Units are radiological engineering instruments: To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
: 3) HEPA Vacuums  
: 4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry.
& Ventilation Units are radiological engineering instruments:
: 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.
To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
: 4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry. 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.
ALARA Review Number:
ALARA Review Number:
Survey Data: Radiation Levels:
Survey Data:
Turbine Building HRAs Reactor Building HRAs Rad Waste Buiding HRAs Off Gas Building HRAs 2 - 200mRem/hr 2 - 250mRem/hr 2 - GOOmRem/hr 2 - 120mRem/hr Contamination Levels:  
Radiation Levels:
~400 - 10,000 dpm/lOOcrn2 Airborne Levels:  
Turbine Building HRAs           2 - 200mRem/hr Reactor Building HRAs          2 - 250mRem/hr Rad Waste Buiding HRAs          2 - GOOmRem/hr Off Gas Building HRAs          2 - 120mRem/hr Contamination Levels:           ~ 4 0 -0 10,000 dpm/lOOcrn2 Airborne Levels:               ~ 0 . 3DAC Specific areas as per RP briefing and / or survey maps.
~0.3 DAC Specific areas as per RP briefing and / or survey maps.
Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back
Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back c Conduct of Operations SRO ADMIN 1 ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 N Conduct of Operations SRO ADMIN 2 I N Equipment Control SRO ADMIN 3 I N Radiation Control SRO ADMIN 4 D Emergency Plan SRO ADMIN 5 Date of Examination:
 
Operating Test Number:
c ES-301, Rev. 9                               Administrative Topics Outline                                 Form ES-301-1 Date of Examination:         December 11, 2006 Operating Test Number:               NA Describe activity to be performed 9ssess Reportability Requirements For Transient Plant Conduct of Operations                  N          Conditions SRO ADMIN 1                                        Given a series of plant events, determine the verbal reporting requirements per 10CFR50.72. (CR NM-2006-4134) 2.1 .I8 (3.0) Ability to make accurate/ clear and concise logs/ records/
NA December 11, 2006 Describe activity to be performed 9ssess Reportability Requirements For Transient Plant Conditions Given a series of plant events, determine the verbal reporting requirements per 10CFR50.72. (CR NM-2006-4134) 2.1 .I8 (3.0) Ability to make accurate/ clear and concise logs/ records/ status boards1 and reports. 10CFR50.72, NUREG 1022 REV 2 Reactivity Management Events and RMR Review Given plant conditions review an RMR. RMR is not to be approved, based on predicted power/flow map operating point. Determine the reactivity event severity level and the appropriate compensatory actions and notifications.
status boards1and reports.
10CFR50.72, NUREG 1022 REV 2 I
Conduct of Operations                  N Reactivity Management Events and RMR Review Given plant conditions review an RMR. RMR is not to be approved, based on predicted power/flow map operating point. Determine the SRO ADMIN 2                                        reactivity event severity level and the appropriate compensatory actions and notifications.
2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics I reactor behavior I and instrument interpretation.
2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics I reactor behavior I and instrument interpretation.
GAP-OPS-05 section 3.13 Determine Thermal Limits with Inoperable Pressure Regulator Given plant parameters including an inoperable reactor pressure regulator, determine the adjusted thermal limit values. Core Operating Limit Report graphs and 3D Monicore printout is used to evaluate conditions against the adjusted thermal limits. 2.2.22 (4.1) Knowledge of limiting conditions for operations and safety limits. N1-RESP-1, Core Operating Limits Report and Tech Spec 3.1.7 Determine Actions Required For an Inoperable Effluent Radiation Monitor Given plant conditions, determine operability of an effluent radiation monitor and apply action statements contained in the station ODCM. 2.3.1 1 (3.2) Ability to control radiation releases.
GAP-OPS-05 section 3.13 I
ODCM (CR NM-2004-976)
Equipment Control                      N Determine Thermal Limits with Inoperable Pressure Regulator Given plant parameters including an inoperable reactor pressure SRO ADMIN 3                                        regulator, determine the adjusted thermal limit values. Core Operating Limit Report graphs and 3D Monicore printout is used to evaluate conditions against the adjusted thermal limits.
~ Classify Emergency Event and Perform PARs Given plant conditions at an existing Site Area Emergency, determine the plant conditions now meet General Emergency conditions. Reclassify the event and determine PARs, based on conditions provided. (Time Critical)
2.2.22 (4.1) Knowledge of limiting conditions for operations and safety limits.
NRC 2002 SRO JPM A4 2.4.44 (4.0)
N1-RESP-1, Core Operating Limits Report and Tech Spec 3.1.7 Determine Actions Required For an Inoperable Effluent Radiation Control                      D            Radiation Monitor SRO ADMIN 4                                        Given plant conditions, determine operability of an effluent radiation monitor and apply action statements contained in the station ODCM.
Knowledge of emergency plan protective action recommendations.
(CR NM-2004-976) 2.3.11 (3.2) Ability to control radiation releases.
ODCM
                                                    ~
Classify Emergency Event and Perform PARs Emergency Plan                                      Given plant conditions at an existing Site Area Emergency, SRO ADMIN 5                                          determine the plant conditions now meet General Emergency conditions. Reclassify the event and determine PARs, based on conditions provided. (Time Critical) NRC 2002 SRO JPM A4 2.4.44 (4.0) Knowledge of emergency plan protective action recommendations.
EAL Matrix 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
EAL Matrix 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, (N)ew or (M)odifred from bank
* Type Codes & Criteria (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs,     4 for SROs & RO retakes)
(- 1) (P)revious 2 exams 1 randomlv selected) 4 for SROs & RO retakes) 10123/2006 3: 19:02 PM 2006 Unit 1 NRC SRO Admin Outline Submittal 1 of1 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Assess Reportability Requirements Revision:
(N)ew or (M)odifred from bank ( - 1)
NRC 2006 Task Number: NA NA EXAMINATION SECURITY Date General Supervisor Date Operations Training (Designee) Operations (Designee)
(P)revious 2 exams     1 randomlv selected) 10123/2006 3:19:02 PM                                         1 of1 2006 Unit 1 NRC SRO Admin Outline Submittal
NA EXAMINATION SECURITY Configuration Control Date Pe dormer: (SRO) Tra i ne r/Eval ua tor: Evaluation Method:
 
X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time:
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Assess Reportability Requirements                                   Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY Date                   General Supervisor                   Date Operations Training (Designee)                       Operations (Designee)
25 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time: JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments: Evaluator Signature: Date:
NA EXAMINATION SECURITY Configuration Control         Date Pedormer:                                             (SRO)
NRC SRO ADMIN JPM 1 1 October 2006 Recommended Start Location: (Completion time based on the start location) Simulator or other designated area.
Tra iner/Evaluator:
Simulator Set-up: NIA Directions to the InstructorIEvaluator:
Evaluation Method:     X       Perform                       Simulate Evaluation Location:           Plant                 X       Simulator or other location Expected Completion Time: 25 min Time Critical Task:         NO     Alternate Path Task: NO Start Time:                     Stop Time:                   Completion Time:
None Directions to Operators: Read Before Everv JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
JPM Overall Rating:             Pass           Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Comments:
Evaluator Signature:                                                 Date:
NRC SRO ADMIN JPM 1         1     October 2006
 
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
NIA Directions to the InstructorIEvaluator:
None Directions to Operators:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
During this Training JPM, the use of applicable methods of verification and checking are expected.
Notes to Instructor I Evaluator: 1. Critical steps are identified in grading areas PasslFail.
Therefore, either another individual or I will act as the independent verifier or peer checker.
All steps are sequenced critical unless denoted by a "0''. 2. During Evaluated JPM:
Notes to Instructor I Evaluator:
0 3. During Training JPM:
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a 0   .
0 0 Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.  
: 2. During Evaluated JPM:
0   Self checking shall be demonstrated.
: 3. During Training JPM:
0   Self checking shall be demonstrated.
0  Peer checking shall be demonstrated.


==References:==
==References:==
: 1. NIP-IRG-01
: 1. NIP-IRG-01
: 2. 10CFR50.72
: 2. 10CFR50.72
: 3. NUREG 1022 Rev 2, Section 3.2.6 4. EAL Matrix
: 3. NUREG 1022 Rev 2, Section 3.2.6
: 4. EAL Matrix
: 5. CR NM-2006-4134 Plant Event Unit 2 Log Entry 9/5/06 1130 Tools and Equipment:
: 5. CR NM-2006-4134 Plant Event Unit 2 Log Entry 9/5/06 1130 Tools and Equipment:
: 1. None Task Standard:
: 1. None Task Standard:
Determine notification requirements.
Determine notification requirements.
NRC SRO ADMlN JPM 1 2 October 2006
NRC SRO ADMlN JPM 1               2       October 2006
- Initial Conditions:
 
The plant is operating at 100% power. Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short. While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs.
      -
No other systems are affected. After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm. Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and Nl-OP-43C, Plant Shutdown is being implemented. Reactor power is now at 50%. Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited. After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches. Plant conditions are stabilized and a normal cool down occurs.
Initial Conditions:
Psig Initiating cue: "(Operator's name), identify the applicable verbal notification requirements, the reason that they apply and the associated time limitations for reporting under that category".
The plant is operating at 100% power.
: 1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 2 *Obtain a copy of the any of the 0 Reference materials obtained. reference documents related to regulatory notifications.
Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.
These are likely to include the following:
While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.
NIP-IRG-01 10CFR50.72 and 73 NUREG1022 EAL Matrix Note: Invalid isolation during maintenance is illustrated in NUREG 1022, Rev 2, section 3.2.6 System Actuation on page 52, example 7. NRC SRO ADMIN JPM 1 3 October 2006
After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.
: 3. Locate and identify applicability of 0 50.72 (b)(3)(iv)(B)(2) Determines actuation of isolation logic is not reportable under 50.72 (b)( 3)( iv)( B)( 2) because the actuation is not due to a valid signal.
Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and Nl-OP-43C, Plant Shutdown is being implemented.
LER is not a verbal reporting 0 requirement.
Reactor power is now at 50%.
: 4. Locate and identify applicability of 0 50.72(a)(I
Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited.
)(i). Declaration of an Emergency Class. 5. Locate and identify applicability of 0 50,72(b)(Z)(i).
After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 Psig Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches.
Non-emergency four hour report. Initiation of a plant shutdown required by Tech Specs. (If not already reported with the 50,72(a)(l)(i).
Plant conditions are stabilized and a normal cool down occurs.
0 6. Locate and identify applicability of 0 50.72(b)(2)( iv)( B) Non- emergency four hour report. Actuation of RPS when the reactor is critical. 7. Locate and identify applicability of 50.72(b)(3)( iv)( B)(5) Non- emergency eight hour report.
Initiating cue:
Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection. LER is required under 50.73 (b)(Z)(iv). Identification of this requirement is not required. Identifies leak rate above 10 gpm requires EAL 2.1.1 UNUSUAL EVENT must be declared. Identify reportability per 50.72(a)(I  
(Operators name), identify the applicable verbal notification requirements, the reason that they apply and the associated time limitations for reporting under that category.
)(i) and (a)(3), within 15 minutes of declaration, immediately after notifying State and local agencies and not later than one hour after the time of declaration. Refer to Tech Spec 3.2.5.a.1 and determines that with specification not being met, the required action to comply with Tech Spec is to be cold shutdown within 24 hours. The plant shutdown being performed is required by Tech Specs. Identify reportability per 50.72(b)( 2)(i) within four hours, if not already reported. Identify reportability per 50.72(b)(Z)(iv)(B) within 4 hours, if not already reported. Identify reportability per 50.72(b)(3)(iv)(B)(S) within 8 hours, if not already reported. End of JPM TERMINATING CUE: Determine notification requirements. RECORD STOP TIME PasslFail SatlUnsatlNA PasslFail SatlUnsat PasslFail PasslFail PasslFail NRC SRO ADMIN JPM 1 4 October 2006 Applicant Cue Sheet Initial Conditions:
: 1. Provide repeat back of initiating       Proper communications used for repeat         Sat/Unsat cue. Evaluator Acknowledge           back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 2   *Obtain a copy of the any of the     0     Reference materials obtained.
e 0 e e e e e e e e e 0 0 e e The plant is operating at 100% power. Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short. While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs.
reference documents related to regulatory notifications. These are likely to include the following:
No other systems are affected.
NIP-IRG-01 10CFR50.72 and 73 NUREG1022 EAL Matrix Note: Invalid isolation during maintenance is illustrated in NUREG 1022, Rev 2, section 3.2.6 System Actuation on page 52, example 7.
After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm. Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and N 1 -0P-43C, Plant Shutdown is being implemented.
NRC SRO ADMIN JPM 1           3       October 2006
Reactor power is now at 50%. Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited. After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 psig Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches. Plant conditions are stabilized and a normal cool down occurs. Initiating cue: "(Operator's name), identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category".
: 3. Locate and identify applicability of 0 Determines actuation of isolation          PasslFail 50.72 (b)(3)(iv)(B)(2)                 logic is not reportable under 50.72 (b)(3)(iv)(B)(2) because the actuation is not due to a valid signal.
NRC SRO ADMlN JPM 1 5 October 2006 Attachment 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reporta bil ity Rea u i rernen t 50.72 (b)(3)(iv)(B)(2). General containment isolation signals.
LER is not a verbal reporting       0 LER is required under 50.73              SatlUnsatlNA requirement.                           (b)(Z)(iv). Identification of this requirement is not required.
50.72(a)(l)(i) and (a)(3). Declaration of an Emergency Class 50.72(b)(2)(i). Initiation of a plant shutdown required by Tech Specs 50.72( b)(2)(iv)(B).
: 4. Locate and identify applicability of 0 Identifies leak rate above 10 gpm          PasslFail 50.72(a)(I )(i). Declaration of an    requires EAL 2.1.1 UNUSUAL Emergency Class.                      EVENT must be declared.
Identify reportability per 50.72(a)(I )(i) and (a)(3), within 15 minutes of declaration, immediately after notifying State and local agencies and not later than one hour after the time of declaration.
5 . Locate and identify applicability of 0 Refer to Tech Spec 3.2.5.a.1 and           SatlUnsat 50,72(b)(Z)(i). Non-emergency          determines that with specification not four hour report. Initiation of a      being met, the required action to plant shutdown required by Tech        comply with Tech Spec is to be cold Specs. (If not already reported        shutdown within 24 hours. The plant with the 50,72(a)(l)(i).              shutdown being performed is required by Tech Specs.
0 Identify reportability per 50.72(b)(       PasslFail 2)(i) within four hours, if not already reported.
: 6. Locate and identify applicability of  0 Identify reportability per                 PasslFail 50.72(b)(2)( iv)(B) Non-              50.72(b)(Z)(iv)(B) within 4 hours, if emergency four hour report.            not already reported.
Actuation of RPS when the reactor is critical.
Actuation of RPS when the reactor is critical.
50.72( b)(3)(iv)(B)(5).
: 7. Locate and identify applicability of    Identify reportability per                  PasslFail 50.72(b)(3)( iv)(B)(5) Non-            50.72(b)(3)(iv)(B)(S) within 8 hours, if emergency eight hour report.          not already reported.
Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.
Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.
Time Limit NOT REPORTABLE Within 15 minutes of declaration, immediately after notifying state and local agencies and not later than one hour after the time of declaration Within 4 hours, if not previously reported.
End of JPM TERMINATING CUE: Determine notification requirements.
Within 4 hours, if not previously reported.
RECORD STOP TIME NRC SRO ADMIN JPM 1          4        October 2006
Within 8 hours, if not previously reported.
 
Reason (Event) Category Amlies Containment Purge Isolation during maintenance activity. Also, only affects one system.
Applicant Cue Sheet Initial Conditions:
Declaration of UE 2.1 .I Initiation of a plant shutdown required by Tech Specs 3.2.5.a.1. Unidentified leakage is above 5 gpm. Automatic reactor trip when the reactor is critical.
e  The plant is operating at 100% power.
Manual initiation of Emergency Condensers to control pressure.
0  Containment purge is in progress e  Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic e  WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.
Intentional manual actions are valid initiations. Also, the HPCl mode (feedwater coolant injection) is actuated.
e  While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.
NRC SRO ADMIN JPM 1 6 October 2006 Attachment 2 JPM Scorecard For Applicant Use dentify the applicable verbal reportability requirements, the reason that :hey apply and the associated time limitations for reporting under that :at eg o ry Re porta b i I i ty Reau iremen t Time Limit qeason (Event) Category 4pplies NRC SRO ADMIN JPM 1 7 October 2006 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Review Reactivity Maneuver Request and Classify Reactivity Events Revision:
e  After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.
NRC 2006 Task Number: NA Approvals:
e  Drywell pressure stabilizes below the scram setpoint e  Actions to comply with Tech Specs as a result of the leakage are initiated and N 1-0P-43C, Plant Shutdown is being implemented.
NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee)
e  Reactor power is now at 50%.
Operations (Designee)
e  Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited.
NA EXAMINATION SECURITY Configuration Control Date Pe rfo r me r : Trainer/Evaluator: Evaluation Method:
e  After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams 0  All rods fully insert 0  Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 psig e  Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches.
X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time:
e  Plant conditions are stabilized and a normal cool down occurs.
20 min Time Critical Task: NO Alternate Path Task: NO (SW Start Time: Stop Time: Completion Time:
Initiating cue:
JPM Overall Rating:
(Operators name), identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category.
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments: Evaluator Signature: Date:
NRC SRO ADMlN JPM 1  5      October 2006
NRC SRO ADMIN JPM 2 1 October 2006 Recommended Start Location: (Completion time based on the start location) Simulator or other designated area. Simulator Set-up:
 
Attachment 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability                  Time Limit            Reason (Event) Category Reauirernent                                          Amlies 50.72 (b)(3)(iv)(B)(2).        NOT                  Containment Purge Isolation General containment            REPORTABLE            during maintenance activity. Also, isolation signals.                                    only affects one system.
50.72(a)(l)(i) and (a)(3).      Within 15 minutes    Declaration of UE 2.1 .I Declaration of an              of declaration, Emergency Class                immediately after notifying state and local agencies and not later than one hour after the time of declaration 50.72(b)(2)(i). Initiation of a Within 4 hours, if    Initiation of a plant shutdown plant shutdown required by      not previously        required by Tech Specs Tech Specs                      reported.            3.2.5.a.1. Unidentified leakage is above 5 gpm.
50.72( b)(2)(iv)(B).            Within 4 hours, if    Automatic reactor trip when the Actuation of RPS when the      not previously        reactor is critical.
reactor is critical.            reported.
50.72( b)(3)(iv)(B)(5). Event  Within 8 hours, if    Manual initiation of Emergency or condition results in valid  not previously        Condensers to control pressure.
actuation of BWR isolation      reported.            Intentional manual actions are condenser system and                                  valid initiations. Also, the HPCl feedwater coolant injection.                          mode (feedwater coolant injection) is actuated.
NRC SRO ADMIN JPM 1     6     October 2006
 
Attachment 2 JPM Scorecard For Applicant Use dentify the applicable verbal reportability requirements, the reason that
:hey apply and the associated time limitations for reporting under that
:at ego ry ReportabiIity              Time Limit         qeason (Event) Category Reauirement                                      4pplies NRC SRO ADMIN JPM 1   7       October 2006
 
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Review Reactivity Maneuver Request and Classify Reactivity Events   Revision: NRC 2006 Task Number: NA Approvals:
NA EXAMINATION SECURITY General Supervisor                   Date Operations Training (Designee)                       Operations (Designee)
NA EXAMINATION SECURITY Configuration Control         Date Perfor m er :                                         (SW Trainer/Evaluator:
Evaluation Method:     X       Perform                       Simulate Evaluation Location:           Plant                 X       Simulator or other location Expected Completion Time: 20 min Time Critical Task:         NO     Alternate Path Task: NO Start Time:                   Stop Time:                     Completion Time:
JPM Overall Rating:           Pass           Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:                                                   Date:
NRC SRO ADMIN JPM 2           1     October 2006
 
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
NIA Directions to the Instructor/Evaluator:
NIA Directions to the Instructor/Evaluator:
Applicant is to be provided with 3D Monicore printout data and RMR for review and approval.
Applicant is to be provided with 3D Monicore printout data and RMR for review and approval. A 5 Loop Power to Flow Map is also required.
A 5 Loop Power to Flow Map is also required.
Directions to Operators:
Directions to Operators: Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
The Control Room Supervisor has determined that a verifier is not available and that additional  
Read Before Each Evaluated JPM Performance:
/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor I Evaluator:
Notes to Instructor I Evaluator:
: 1. Critical steps are identified in grading areas PasslFail.
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
All steps are sequenced critical unless denoted by a "*". 2. During Evaluated JPM:
: 2. During Evaluated JPM:
: 3. During Training JPM: Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.  
Self checking shall be demonstrated.
: 3. During Training JPM:
Self checking shall be demonstrated.
Peer checking shall be demonstrated.


==References:==
==References:==
: 1. GAP-OPS-05 Tools and Equipment:
: 1. GAP-OPS-05 Tools and Equipment:
: 1. None Task Standard:
: 1. None Task Standard:
Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR.
Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map.
Identifies and initiates actions for Reactivity Events. NRC SRO ADMIN JPM 2 2 October 2006 Initial Conditions:
Applicant does not approve the RMR. Identifies and initiates actions for Reactivity Events.
PART 1 0 The plant is operating at rated power.
NRC SRO ADMIN JPM 2               2       October 2006
An intended plant maneuver to raise rod line is being planned.
 
A Reactivity Maneuver request is provided for review. Initiating cue: PART 1 "(Operator's name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.
Initial Conditions:
PART 2 (After actions are complete for RMR) The following events occur: Loud abnormal noises are reported from the Main Turbine.
PART 1 The plant is operating at rated power.
Power is rapidly reduced to 75% with Recirc Flow. After power is reduced to 75% the Main Turbine automatically trips. EOPs are entered and implemented. ERVs actuate. Turbine Bypass Valves were observed to remain closed throughout the transient. Control Rod 18-19 is at position 04. All other control rods are at position 02. PART 2 "(Operator's name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided".
0    An intended plant maneuver to raise rod line is being planned.
: 1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 02. Obtain a copy of the any of the 0 Reference materials obtained. reference documents.
A Reactivity Maneuver request is provided for review.
PART 1 03. Reviews RMR and supporting 3D 0 Determines predicted results cause PasslFail Monicore predictor case. operation outside ELLLA Operating Limit (PFR Line) of Power Flow Map. (PFR is > 1 .O) Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. (PFR is > 1 .O) NRC SRO ADMIN JPM 2 3 October 2006 PasslFail Grade PART 2 04. Refer to GAP-OPS-05 section 0 Identifies the emergency power PasslFail 3.13 to classify reactivity event severity levels. reduction OR unplanned scram as Severity Level 4 (4-1 Rapid Downpower 10.5% RTP or shutdown due to emergent issues)
Initiating cue:
PART 1 (Operators name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.
PART 2 (After actions are complete for RMR)
The following events occur:
Loud abnormal noises are reported from the Main Turbine.
Power is rapidly reduced to 75% with Recirc Flow.
After power is reduced to 75% the Main Turbine automatically trips.
EOPs are entered and implemented.
ERVs actuate.
Turbine Bypass Valves were observed to remain closed throughout the transient.
Control Rod 18-19 is at position 04.
All other control rods are at position 02.
PART 2 (Operators name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided.
: 1. Provide repeat back of initiating         Proper communications used for repeat       Sat/Unsat cue. Evaluator Acknowledge             back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
: 02. Obtain a copy of the any of the         0   Reference materials obtained.
reference documents.
PART 1
: 03. Reviews RMR and supporting 3D           0   Determines predicted results cause     PasslFail Monicore predictor case.                   operation outside ELLLA Operating Limit (PFR Line) of Power Flow Map. (PFR is > 1.O)
PasslFail Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. (PFR is > 1 .O)
NRC SRO ADMIN JPM 2             3     October 2006
 
Grade PART 2
: 04. Refer to GAP-OPS-05 section       0   Identifies the emergency power           PasslFail 3.13 to classify reactivity event     reduction OR unplanned scram as severity levels.                      Severity Level 4 (4-1 Rapid Downpower 10.5% RTP or shutdown due to emergent issues)
OR 4-9 Unplanned Reactor Scram While Critical.
OR 4-9 Unplanned Reactor Scram While Critical.
May also identify other SL-4 Sat/Unsat events, such as 4-1 1, with rods at 02 and 04, following the scram. Identifies the Main Turbine Trip with PasslFail Bypass Valve failure to operate as Severity Level 2 (2-1 Main Turbine Trip With Bypass System failure). NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram. All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram. Sat/Unsat u Identifies CR (DER) is required for severity level 1,2,3 and 4 events. 13. Report completion.
May also identify other SL-4         Sat/Unsat events, such as 4-1 1, with rods at 02 and 04, following the scram.
u Reports completion. Sat/Unsat TERMINATING CUE: Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR.
Identifies the Main Turbine Trip with     PasslFail Bypass Valve failure to operate as Severity Level 2 (2-1 Main Turbine Trip With Bypass System failure).
Identifies and initiates actions for Reactivity Events. RECORD STOP TIME NRC SRO ADMIN JPM 2 4 October 2006 Applicant Cue Sheet Initial Conditions PART 1 The plant is operating at rated power.
NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram.
All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram.
u     Identifies CR (DER) is required for     Sat/Unsat severity level 1,2,3 and 4 events.
: 13. Report completion.               u     Reports completion.                     Sat/Unsat TERMINATING CUE: Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR. Identifies and initiates actions for Reactivity Events.
RECORD STOP TIME NRC SRO ADMIN JPM 2           4       October 2006
 
Applicant Cue Sheet Initial Conditions PART 1 The plant is operating at rated power.
An intended plant maneuver to raise rod line is being planned.
An intended plant maneuver to raise rod line is being planned.
A Reactivity Maneuver request is provided for review. Initiating cue:
A Reactivity Maneuver request is provided for review.
PART 1 "(Operator's name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided".
Initiating cue:
PART 2 (After actions are complete for RMR) The following events occur:
PART 1 (Operators name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.
Loud abnormal noises are reported from the Main Turbine. Power is rapidly reduced to 75% with Recirc Flow. After power is reduced to 75% the Main Turbine automatically trips. EOPs are entered and implemented.
PART 2 (After actions are complete for RMR)
ERVs actuate. Turbine Bypass Valves were observed to remain closed throughout the transient . Control Rod 18-19 is at position 04. All other control rods are at position 02. PART 2 "(Operator's name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided".
The following events occur:
NRC SRO ADMIN JPM 2 5 October 2006 Attachment 1 JPM Scorecard KEY Document any findings and conclusions for PART 1 and PART 2 events. ACTIONS Determines predicted results cause operation outside ELLLA Operating Limit (PFR Line > 1 .O) of Power Flow Map. Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. Identifies the emergency power reduction or unplanned scram as Severity Level 4. Identifies the Main Turbine Trip with Bypass Valve failure to operate as Severity Level 2 NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram.
Loud abnormal noises are reported from the Main Turbine.
All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram. Identifies CR (DER) is required for severity level 1,2,3 and 4 events. Explanation 100% power and 83.9% core flow (1 12.3% rod line) results in operation above ELLLA. (PFR  
Power is rapidly reduced to 75% with Recirc Flow.
>I .O) GAP-OPS-05 Attachment 1 Item 2 evaluates the RMR for maintaining operation within allowable regions of the power to flow map. Since this maneuver does not accomplish this, the RMR should not be approved.
After power is reduced to 75% the Main Turbine automatically trips.
GAP-OPS-05 section 3.1 3 SL 4. Example 4-1 Rapid Downpower 2 0.5% RTP or shutdown due to emergent issues OR 4-9 Unplanned Reactor Scram While Critical.
EOPs are entered and implemented.
GAP-OPS-05 section 3.13 Example 2-1 Main Turbine Trip With Bypass System failure. GAP-OP-05 section 3.13.2 NRC SRO ADMIN JPM 2 6 October 2006 Attachment 2 JPM Scorecard For Applicant Use 3ocument any findings and conclusions for PART 1 and PART 2 events. 4ct ions Exdanation NRC SRO ADMIN JPM 2 7 October 2006
ERVs actuate.
: 10. Determine "Adjusted LHGR limit" 0 Determines adjusted value to be PasslFail value for step 9.2.10, with pressure regulator out of service and thermal power between 45% and 90% from the COLR. 0.860, from COLR Section 3.1 and Figure 3, as follows: For 70% 5 P < 90% MFLPD Limit  
Turbine Bypass Valves were observed to remain closed throughout the transient .
= FRTP = 1591/1850  
Control Rod 18-19 is at position 04.
= 0.8600 0 Enters 0.860 as "Adjusted LHGR Sat/Unsat limit" value for step 9.2.10. 11. Determine "Actual MFLPD Value" Determines actual MFLPD value to PasslFail from 3D Monicore printout. be 0.735, from printout. Enters 0.735 as "Actual Sat/Unsat MFLPDValue" for step 9.2.10 12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met. less than adjusted limit and that the MFLPD thermal limit is met. 0 Records MFLPD and location in step SatlUnsat 9.2.1 1 as 0.735 and 41-38. Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout.
All other control rods are at position 02.
0 Records step 9.2.13 as NA, since Sat/Unsat FPAPDR is < 1 .O. 13. Report completion. Reports completion. Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator.
PART 2 (Operators name), based on the plant events that occur identify any internal classification and administrative actions related to the events.
Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.
Document findings and conclusions on scorecard provided.
RECORD STOP TIME NRC SRO ADMIN JPM 3 5 October 2006 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Thermal Limits with Inoperable Pressure Regulator Revision:
NRC SRO ADMIN JPM 2     5     October 2006
NRC 2006 Task Number:
 
NA NA EXAMINATION SECURITY Da General Supervisor Date Operations Training (Designee) Operations (Designee)
Attachment 1 JPM Scorecard KEY Document any findings and conclusions for PART 1 and PART 2 events.
NA EXAMINATION SECURITY Configuration Control Date Trai ne r/Eval uator: Evaluation Method:
ACTIONS                                         Explanation Determines predicted results                     100% power and 83.9% core flow cause operation outside                          (112.3% rod line) results in ELLLA Operating Limit (PFR                      operation above ELLLA. (PFR >I    .O)
X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time:
Line > 1.O) of Power Flow Map.
25 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:
GAP-OPS-05 Attachment 1 Item 2 Does NOT approve the RMR                        evaluates the RMR for maintaining based on failure to maintain                    operation within allowable regions of plant operation within                          the power to flow map. Since this allowable regions of the power                  maneuver does not accomplish this, to flow map.                                    the RMR should not be approved.
JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments: Evaluator Signature:
GAP-OPS-05 section 3.13 SL 4.
Date: NRC SRO ADMIN JPM 3 1 October 2006 Recommended Start Location: (Completion time based on the start location)
Identifies the emergency                        Example 4-1 Rapid Downpower 2 power reduction or unplanned                    0.5% RTP or shutdown due to scram as Severity Level 4.                      emergent issues OR 4-9 Unplanned Reactor Scram While Critical.
Simulator or other designated area. Simulator Set-up:
GAP-OPS-05 section 3.13 Example Identifies the Main Turbine                      2-1 Main Turbine Trip With Bypass Trip with Bypass Valve failure                  System failure.
N /A Directions to the Instructor/Evaluator:
to operate as Severity Level 2 NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram. All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram.
Applicant is to be provided with NI-RESP-1 for recording data. Applicant must have access to Core Operating Limits Report, Tech Specs, 3D Monicore printout data and N1-OP-31 Directions to Operators: Read Before Everv JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
Identifies CR (DER) is required                  GAP-OP-05 section 3.13.2 for severity level 1,2,3 and 4 events.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
NRC SRO ADMIN JPM 2 6   October 2006
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional  
 
/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:
Attachment 2 JPM Scorecard For Applicant Use 3ocument any findings and conclusions for PART 1 and PART 2 events.
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
4ct ions                                 Exdanation NRC SRO ADMIN JPM 2   7   October 2006
Notes to Instructor  
: 10. Determine Adjusted LHGR limit     0 Determines adjusted value to be         PasslFail value for step 9.2.10, with           0.860, from COLR Section 3.1 and pressure regulator out of service     Figure 3, as follows:
/ Evaluator:
and thermal power between 45%
1, 2. During Evaluated JPM:
and 90% from the COLR.                 For 70% 5 P < 90% MFLPD Limit =
FRTP
                                          = 1591/1850 = 0.8600 0 Enters 0.860 as Adjusted LHGR         Sat/Unsat limit value for step 9.2.10.
: 11. Determine Actual MFLPD Value         Determines actual MFLPD value to       PasslFail from 3D Monicore printout.             be 0.735, from printout.
Enters 0.735 as Actual                 Sat/Unsat MFLPDValue for step 9.2.10
: 12. Determines COLR thermal limit         Evaluates actual MFLPD value to be     PasslFail restriction for MCPR is met.           less than adjusted limit and that the MFLPD thermal limit is met.
0 Records MFLPD and location in step     SatlUnsat 9.2.1 1 as 0.735 and 41-38.
Records FPAPDR in step 9.2.12 as       Sat/Unsat 0.855 from printout.
0 Records step 9.2.13 as NA, since       Sat/Unsat FPAPDR is < 1.O.
: 13. Report completion.                     Reports completion.                     Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.
RECORD STOP TIME NRC SRO ADMIN JPM 3           5       October 2006
 
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Thermal Limits with Inoperable Pressure Regulator   Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY Da                     General Supervisor                   Date Operations Training (Designee)                         Operations (Designee)
NA EXAMINATION SECURITY Configuration Control         Date Trai ner/Evaluator:
Evaluation Method:     X       Perform                         Simulate Evaluation Location:           Plant                   X       Simulator or other location Expected Completion Time: 25 min Time Critical Task:           NO     Alternate Path Task: NO Start Time:                   Stop Time:                     Completion Time:
JPM Overall Rating:           Pass             Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:                                                   Date:
NRC SRO ADMIN JPM 3           1     October 2006
 
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
Applicant is to be provided with NI-RESP-1 for recording data. Applicant must have access to Core Operating Limits Report, Tech Specs, 3D Monicore printout data and N1-OP-31 Directions to Operators:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
1, Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
: 2. During Evaluated JPM:
0    Self checking shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
Critical steps are identified in grading areas PasslFail.
Self checking shall be demonstrated.
All steps are sequenced critical unless denoted by a "*". 0 Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.  
Peer checking shall be demonstrated.


==References:==
==References:==
: 1. Core Operating Limits Report (COLR)
: 1. Core Operating Limits Report (COLR)
: 2. N1 -RESP-1 Daily Thermal Limit Surveillance
: 2. N1-RESP-1 Daily Thermal Limit Surveillance
: 3. Tech Spec 3.1.7 4. N1-OP-31, H.5.0 and H.3.0 Tools and Equipment:
: 3. Tech Spec 3.1.7
: 1. None Task Standard NRC SRO ADMIN JPM 3 2 October 2006 limit is exceeded and Tech-Spec 3.1.7 actions required.lnitial Cond'itions:
: 4. N1-OP-31, H.5.0 and H.3.0 Tools and Equipment:
The plant is operating at power Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue: "(Operator's name), using the 3D Monicore printout provided complete N1-RESP-1, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13". 1. Provide repeat back of initiating cue. Evaluator Acknowledge back (GAP-OPS-01) Proper communications used for repeat I NRC SRO ADMIN JPM 3 3 October 2006 repeat back providing corr&tion if necessary RECORD START TIME *2. Obtain a copy of the any of the 0 reference documents.
1 . None Task Standard NRC SRO ADMIN JPM 3               2       October 2006
: 03. Candidate may reference N 1  
 
-0P- 0 31, H.3.0. 4. Record data in N1-RESP-1 by 0 obtaining information from 3D Monicore printout. Reference materials obtained. Refers to N1-OP-31, H.3.0 for direction for operation with one pressure regulator inoperable.
limit is exceeded and Tech-Spec 3.1.7 actions required.lnitial Conditions:
Refer to Core Operating Limits Report for applicable MFLPD and MFLCPR thermal limit restrictions.
The plant is operating at power Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue:
IF unable to meet COLR thermal limit restrictions, THEN perform the following: Enter applicable Tech Spec (3.1.7) Notify Reactor Engineering to obtain direction to achieve compliance with applicable thermal limit restrictions. Records Core Thermal Power in step 9.2.2 as 1591 MWth and 86.0%. Records Total Core Flow in step 9.2.3 as 48.023 Mlbm/hr and 71 .I % Records step 9.2.4 as NA, since all RRPs are operating.
(Operators name), using the 3D Monicore printout provided complete N1-RESP-1, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13.
Sat/Unsat Sat/Unsat/NA Sat/Unsat PasslFail PasslFail Sat/Unsat SatlUnsat Sat/Unsat
: 1. Provide repeat back of initiating     Proper communications used for repeat      Sat/Unsat cue. Evaluator Acknowledge         back (GAP-OPS-01) repeat back providing corr&tion if necessary RECORD START TIME
: 5. Determine "Adjusted MCPR limit" value for step 9.2.6.1, with pressure regulator out of service and thermal power between 45%
* 2 . Obtain a copy of the any of the     0   Reference materials obtained.
and 90% from the COLR.
reference documents.
: 6. Determine "Actual MCPR Value" from 3D Monicore printout.
: 03. Candidate may reference N 1-0P-       0   Refers to N1-OP-31, H.3.0 for        Sat/Unsat/NA 31, H.3.0.                               direction for operation with one pressure regulator inoperable.
: 7. Determines COLR thermal limit restriction for MCPR is not met. 8. Enter Tech Spec 3.1.7.c 9. Record data in N1-RESP-I by obtaining information from 3D Monicore printout.
I    Refer to Core Operating Limits   Sat/Unsat Report for applicable MFLPD and MFLCPR thermal limit restrictions.
0 0 0 0 0 0 0 0 0 0 Records MAPRAT and location in step 9.2.5 as 0.775 and 41-38 Records step 9.2.6 as NA, since all RRPs are operating. Determines adjusted value to be 1.809, from COLR Section 2.1 and Figure 2b, as follows: For 70% 5 P < 90% MCPR Limit = (Rated 0 L M C P R)/F RTP Rated OLMCPR= MCPRlim*Kf
IF unable to meet COLR thermal limit restrictions, THEN perform the following:
= 1.53*1.017
Enter applicable Tech Spec       PasslFail (3.1.7)
= 1.556 = 1.5561.860
Notify Reactor Engineering to     PasslFail obtain direction to achieve compliance with applicable thermal limit restrictions.
= 1.809 Enters 1.809 as "Adjusted MCPR limit" value for step 9.2.6.1 Determines actual MCPR value to be 1.753, from printout. Enters 1.753 as "Actual MCPR Value" for step 9.2.6.1 Evaluates actual MCPR value to be less than adjusted limit and that the MCPR thermal limit is NOT met. Recognize entry into Tech Spec 3.1.7 specification
: 4. Record data in N1-RESP-1 by            0  Records Core Thermal Power in         Sat/Unsat obtaining information from 3D          step 9.2.2 as 1591 MWth and Monicore printout.                    86.0%.
: c. Identifies "action shall be initiated within 15 minutes to restore operation to the prescribed limit. If all operating MCPRs are not returned within 2 hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit". Notifies Reactor Engineering to obtain direction to achieve compliance with applicable limits. (OP-31 H.3.2.2) Records MFLCPR and location in step 9.2.7 as 1.032 and 29-14. Records step 9.2.8 as NA, since all RRPs are operating. Records Power to Flow Ratio (PFR) step 9.2.9 as 0.933.
Records Total Core Flow in step       SatlUnsat 9.2.3 as 48.023 Mlbm/hr and 71 .I   %
Sat/Unsat PasslFail SaVUnsat PasslFail Sa t/U n sa t PasslFail PasslFail PasslFail PasslFail SatlUnsat Sat/Unsat NRC SRO ADMIN JPM 3 4 October 2006 Grade 10. Determine "Adjusted LHGR limit" Determines adjusted value to be PasslFail value for step 9.2.10, with pressure regulator out of service and thermal power between 45% and 90% from the COLR. 0.860, from COLR Section 3.1 and Figure 3, as follows:
Records step 9.2.4 as NA, since all   Sat/Unsat RRPs are operating.
For 70% 5 P < 90% MFLPD Limit = FRTP = 1591/1850  
NRC SRO ADMIN JPM 3              3        October 2006
= 0.8600 Enters 0.860 as "Adjusted LHGR Sat/Unsat limit" value for step 9.2.10.
 
: 11. Determine "Actual MFLPD Value" Determines actual MFLPD value to PasslFail from 3D Monicore printout.
0 Records MAPRAT and location in            Sat/Unsat step 9.2.5 as 0.775 and 41-38 0 Records step 9.2.6 as NA, since all RRPs are operating.
be 0.735, from printout. Enters 0.735 as "Actual MFLPD Sat/Unsat Value"for step 9.2.10
: 5. Determine Adjusted MCPR limit    Determines adjusted value to be          PasslFail value for step 9.2.6.1, with        1.809, from COLR Section 2.1 and pressure regulator out of service  Figure 2b, as follows:
: 12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met. less than adjusted limit and that the MFLPD thermal limit is met. Records MFLPD and location in step SatlUnsat 9.2.1 1 as 0.735 and 41-38. Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout. Records step 9.2.13 as NA, since Sat/Unsat FPAPDR is  
and thermal power between 45%
< 1.0. 13. Report completion. Reports completion. Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.
and 90% from the COLR.             For 70% 5 P < 90% MCPR Limit =
RECORD STOP TIME NRC SRO ADMlN JPM 3 5 October 2006 Applicant Cue Sheet Initial Conditions: The plant is opera ing a : power 0 Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue: "(Operator's name), using the 3D Monicore printout provided complete N1 -RESP-1 , Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.1 3". NRC SRO ADMIN JPM 3 6 October 2006 H. OFF-NORMAL PROCEDURE (Cont) 3.0 c. Operation With One Pressure Requlator Inoperable 3.1 IF operating without a backup pressure regulator, see the Core Operating Limits Report (COLR) section for operation without a backup pressure regulator for IF unable to meet the COLR thermal limit restrictions, THEN perform the following:
(Rated 0LMC PR)/FRTP Rated OLMCPR= MCPRlim*Kf
3.2.1 .............................................
                                      = 1.53*1.017 = 1.556
applicable MFLPD and MFLCPR thermal limit restrictions
                                      = 1.5561.860 = 1.809 SaVUnsat 0 Enters 1.809 as Adjusted MCPR limit value for step 9.2.6.1
(-1 :t 3.2 Enter applicable Tech Spec LCO for Fuel Rod Thermal Limits  
: 6. Determine Actual MCPR Value    0 Determines actual MCPR value to be        PasslFail from 3D Monicore printout.         1.753, from printout.
..........................
0 Enters 1.753 as Actual MCPR             Sat/Unsat Value for step 9.2.6.1
3.2.2 Notify Reactor Engineering to obtain direction to achieve compliance with ..............................................................
: 7. Determines COLR thermal limit      Evaluates actual MCPR value to be         PasslFail restriction for MCPR is not met. less than adjusted limit and that the MCPR thermal limit is NOT met.
the applicable thermal limit restrictions
: 8. Enter Tech Spec 3.1.7.c           0 Recognize entry into Tech Spec            PasslFail 3.1.7 specification c.
(-) 4.0 This Section Deleted. Page 66 N 1 -0 P-31 Rev 21 PAGE 1 CORE PARAMETERS 3 DM/ P11 20-OCT-2006 13:39 CALCULATED PREDICTOR LOG 20-OCT-2006 13:40 PRINTED POWER MWT CASE ID FTFF1061020133947 RESTART FMLD1061020084721 FIT - FULL CORE 1.0034 FLOW MLB/HR FPAPDR SUBC BTU/LB PR PSIa 1012.63 XE WORTH % -2.33 LOAD LINE  
0 Identifies action shall be initiated     PasslFail within 15 minutes to restore operation to the prescribed limit. If all operating MCPRs are not returned within 2 hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit.
0 Notifies Reactor Engineering to PasslFail obtain direction to achieve compliance with applicable limits.
(OP-31 H.3.2.2)
: 9. Record data in N1-RESP-I by      0 Records MFLCPR and location in           SatlUnsat obtaining information from 3D      step 9.2.7 as 1.032 and 29-14.
Monicore printout.
0  Records step 9.2.8 as NA, since all RRPs are operating.
Records Power to Flow Ratio (PFR)       Sat/Unsat step 9.2.9 as 0.933.
NRC SRO ADMIN JPM 3       4       October 2006
 
Grade
: 10. Determine Adjusted LHGR limit       Determines adjusted value to be         PasslFail value for step 9.2.10, with           0.860, from COLR Section 3.1 and pressure regulator out of service     Figure 3, as follows:
and thermal power between 45%
and 90% from the COLR.                 For 70% 5 P < 90% MFLPD Limit =
FRTP
                                          = 1591/1850 = 0.8600 Enters 0.860 as Adjusted LHGR         Sat/Unsat limit value for step 9.2.10.
: 11. Determine Actual MFLPD Value         Determines actual MFLPD value to       PasslFail from 3D Monicore printout.             be 0.735, from printout.
Enters 0.735 as Actual MFLPD           Sat/Unsat Valuefor step 9.2.10
: 12. Determines COLR thermal limit         Evaluates actual MFLPD value to be     PasslFail restriction for MCPR is met.           less than adjusted limit and that the MFLPD thermal limit is met.
Records MFLPD and location in step     SatlUnsat 9.2.1 1 as 0.735 and 41-38.
Records FPAPDR in step 9.2.12 as       Sat/Unsat 0.855 from printout.
Records step 9.2.13 as NA, since       Sat/Unsat FPAPDR is < 1.0.
: 13. Report completion.                     Reports completion.                   Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.
RECORD STOP TIME NRC SRO ADMlN JPM 3           5       October 2006
 
Applicant Cue Sheet Initial Conditions:
The plant is opera ing a : power 0   Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue:
(Operators name), using the 3D Monicore printout provided complete N1-RESP-1 , Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13.
NRC SRO ADMIN JPM 3 6   October 2006
 
c.
H. OFF-NORMAL PROCEDURE             (Cont) 3.0 Operation With One Pressure Requlator Inoperable 3.1     IF operating without a backup pressure regulator, see the Core Operating Limits Report (COLR) section for operation without a backup pressure regulator for applicable MFLPD and MFLCPR thermal limit restrictions.............................................                (-1
:t 3.2     IF unable to meet the COLR thermal limit restrictions, THEN perform the following:
3.2.1  Enter applicable Tech Spec LCO for Fuel Rod Thermal Limits..........................
3.2.2   Notify Reactor Engineering to obtain direction to achieve compliance with the applicable thermal limit restrictions ..............................................................   (-)
4.0 This Section Deleted.
Page 66                                                                     N1-0P-31 Rev 21
 
PAGE       1 CORE PARAMETERS                       3DM/P11                     20-OCT-2006 1 3 : 3 9 CALCULATED PREDICTOR LOG               20-OCT-2006 1 3 : 4 0 PRINTED POWER MWT                                                       CASE ID F T F F 1 0 6 1 0 2 0 1 3 3 9 4 7 FLOW    MLB/HR                                                  RESTART FMLD1061020084721 FPAPDR                                                            FIT - FULL CORE SUBC     BTU/LB                                       1.0034 PR       PSIa                       XE WORTH % - 2 . 3 3        LOAD LINE  


==SUMMARY==
==SUMMARY==
CORE MWD/sT 26190.6 XE/RATED 1.01 CORE POWER 86. Os CYCLE MWD/sT AVE VF 0.371 CORE FLOW 71.1%@ MCPR ff:":;: PFR @ 0.933 LOAD LINE 107.5% T STEP HOURS CORRECTION FACTORS: MFLCPR=
1.017 MFLPD= 1.000 MAPRAT= 1.000 OPTION: PRE-ARTS 5 LOOPS ON MANUAL FLOW MCPRLIM= 1.530 0.887 4 9-14 0.735 @1 4 y;E@41%- 4 0.862 37 7 :F:11bl-12 0.732 37 4 0.772 37 5 0.859 23 5 Q 0-7 KfZ MOST LIMITING LOCATIONS (NON-SYMMETRIC)
LOC MFLPD LOC PCRAT LOC 0.879 0.878 0.868 0.868 0.863 0.863 0.862 0.861 51 L 47 43 39 35 31 27 L L L 23 19 15 11 L L 07 03 0.772 37 4 0.859 29 7 33-14 0.726 39 4 31-16 0.723 35 4 0.764 39 4 0.859 43 9 27-18 0.723 37 4 0.760 33 5 0.859 43-24-11 39-24 0.722 41 9 0.756 33 5 0.857 37 5 41-22 0.721 27 9 0.755 35 4 0.857 33 5 39-20 0.720 33 4 0.751 43 5 0.856 41 7 37-22 0.716 43 9 0.751 27 8 0.856 29 5 35-26 0.715 33 4 0.750 43 5 0.855 33 7 08 00 06 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT
*=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 00 0.154 24 02 0.276 23 04 0.574 22 36 06 0.737 21 P 08 0.840 20 10 0.928 19
* 12 0.976 18 06 14 0.982 17 16 1.107 16 18 1.160 15 20 1.178 14 00 00 36 22 1.217 13 24 1.253 12 26 1.262 11 28 1.255 10 30 1.285 09 32 1.293 08 34 1.271 07 C 36 1.292 06 36 38 1.304 05 40 1.272 04 42 1.171 03 44 0.928 02 46 0.285 01 L L L L L L 08 02 06 10 14 18 22 26 30 34 38 42 46 50 


Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Actions for Service Water Radiation Monitor Low Flow Revision: NRC 2006 Task Number:
CORE      MWD/sT 1012.63 26190.6        XE/RATED        1.01      CORE POWER                8 6 . Os Q AVE VF CYCLE MWD/sT MCPR T STEP HOURS ff:":;:        PFR      @
NA NA EXAMINATION SECURITY General Supervisor Date Operations (Designee) NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)
0.371 0.933 CORE FLOW LOAD LINE 71.1%@
TrainedEvaluator: Evaluation Method:
107.5%
X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:
0-7      K f Z CORRECTION FACTORS: MFLCPR= 1 . 0 1 7 MFLPD= 1.000 MAPRAT= 1.000 OPTION: PRE-ARTS              5 LOOPS ON      MANUAL FLOW      MCPRLIM= 1 . 5 3 0 MOST LIMITING LOCATIONS (NON-SYMMETRIC)
NO Start Time:
LOC    MFLPD          LOC                                PCRAT            LOC 0.887 4 9-14          0 . 7 3 5 @1      4    y;E@41%-          4    0.862        37 7
Stop Time: Completion Time: JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if or individual competency area unsat requires a comment. critical step is graded as fail. Any grade of unsat Comments: Evaluator Signature: Date:
:F:11bl-12            0.732        37  4    0.772      37 5    0.859        23 5 0.879      33-14    0.726        39  4    0.772      37 4    0.859        29 7 0.878      31-16    0.723        35  4    0.764      39 4    0.859        43 9 0.868      27-18    0.723        37  4    0.760      33 5    0.859        43-24-11 0.868      39-24    0.722        41  9    0.756      33 5    0.857        37 5 0.863      41-22    0.721        27  9    0.755      35 4    0.857        33 5 0.863      39-20    0.720        33  4    0.751      43 5    0.856        41 7 0.862      37-22    0.716        43    9    0.751      27 8    0.856        29 5 0.861      35-26    0.715        33  4    0.750      43 5    0.855          33 7 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE                  CORE AVE AXIAL 51                                                                          NOTCH REL PW LOC L                                                                          00        0.154          24 47                                                                            02        0.276          23 04        0.574          22 43                                    36                                      06        0.737          21 L                                                P                        08        0.840          20 39                                                                            10        0.928          19
NRC SRO ADMIN JPM 4 1 October 2006 Recommended Start Location: (Completion time based on the start location) Simulator or other designated area. Simulator Set-up:
* 12        0.976          18 35                          08                  06                            14        0.982          17 L                                                                        16        1.107          16 31                                                                            18        1.160          15 20        1.178          14 27        00  00                    00                    36                22        1.217          13 L                                                                        24        1.253          12 23                                                                            26        1.262          11 28        1.255          10 19                          06                  08                            30        1.285          09 L                                                                        32        1.293          08 15                                                                            34        1.271          07 C                                  36        1.292          06 11                                    36                                    38        1.304          05 L                                                                        40        1.272          04 07                                                                          42        1.171          03 44        0.928          02 03                                                                          46        0.285          01 L        L            L          L        L        L 02  06  10  14      18  22    26    30  34  38    42  46  50
 
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Actions for Service Water Radiation Monitor Low Flow               Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY General Supervisor                         Date Operations (Designee)
NA EXAMINATION SECURITY Configuration Control           Date Performer:                                               (SRO)
TrainedEvaluator:
Evaluation Method:       X       Perform                             Simulate Evaluation Location:             Plant                   X           Simulator or other location Expected Completion Time:       20 min Time Critical Task:         NO       Alternate Path Task: NO Start Time:                     Stop Time:                         Completion Time:
JPM Overall Rating:             Pass               Fail NOTE:     A JPM overall rating of fail shall be given if   critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:                                                           Date:
NRC SRO ADMIN JPM 4               1       October 2006
 
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
N/A Directions to the InstructorlEvaiuator:
N/A Directions to the InstructorlEvaiuator:
None Directions to Operators:
None Directions to Operators:
Read Before Everv JPM Performance:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
The Control Room Supervisor has determined that a verifier is not available and that additional  
Read Before Each Evaluated JPM Performance:
/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Read Before Each Traininq JPM Performance:
Notes to Instructor  
During this Training JPM, the use of applicable methods of verification and checking are expected.
/ Evaluator:
Therefore, either another individual or I will act as the independent verifier or peer checker.
: 1. 2. During Evaluated JPM:
Notes to Instructor / Evaluator:
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
: 2. During Evaluated JPM:
Self checking shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
Critical steps are identified in grading areas PasslFail.
0   Self checking shall be demonstrated.
All steps are sequenced critical unless denoted by a "*". 0 Self checking shall be demonstrated.
Peer checking shall be demonstrated.
Self checking shall be demonstrated. Peer checking shall be demonstrated.  


==References:==
==References:==
: 1. 2. 3. 4. 5. 6. ARP HI; HI-4-5. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. 16. DER NM-2003-5168, ODCM Entry Due to SW RM Low Flow. DER NM-2004-976, Unplanned LCO - SW RM Low Flow.
: 1. ARP H I ; HI-4-5.
K/A 2.3.1 1 (3.2) Ability to control radiation releases.
: 2. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. 16.
2.4.45 (3.6) Ability to prioritize and interpret the significance of each annunciator or alarm. Tools and Equipment:
: 3. DER NM-2003-5168, ODCM Entry Due to SW RM Low Flow.
: 1. None Task Standard: Determine actions per ARP HI-4-5 and ODCM in response to service water radiation monitor low flow condition. NRC SRO ADMIN JPM 4 2 October 2006 Initial Conditions:
: 4. DER NM-2004-976, Unplanned LCO - SW RM Low Flow.
: 1. 2. 3. 4. 5. 6. 7. 8. The plant is operating at 100&deg;/~ power. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (1 2) hours. HI-4-5, LQ PROCESS RAD MON, has alarmed.
: 5. K/A 2.3.1 1 (3.2) Ability to control radiation releases.
Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
: 6. 2.4.45 (3.6) Ability to prioritize and interpret the significance of each annunciator or alarm.
Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB). Sample flow cannot be adjusted.
Tools and Equipment:
Ask the operator for any questions.
: 1. None Task Standard: Determine actions per ARP HI-4-5 and ODCM in response to service water radiation monitor low flow condition.
Initiating cue: "(Operator's name), determine the appropriate actions in response to these conditions." 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 1. .Obtain a copy of the reference procedure and reviewlutilize the correct section. 2. .Per ARP HI 5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then: a. *Notify Radiation Protection Instrument Support for repair. b..lnitiate LCO sampling (C h em is try). 3. .Reference ODCM and takes appropriate actions. Proper communications used for repeat back (GAP-OPS-01)
NRC SRO ADMIN JPM 4               2       October 2006
ARP HI-4-5 obtained. Operator Actions referenced. ODCM obtained. DLCO 3.6.14 referenced.
 
TBL D3.6.14-1 referenced. Notifies Radiation Protection Instrument Support to initiate repairs. Directs Chemistry to perform DLCO sampling per TBL D 3.6.14-1 InstrumentlB action (d); twelve (12) hour grab samples to be collected/analyzed for SW effluent. Determines SW Radiation Monitor is inoperable.
Initial Conditions:
References ODCM DLCO 3.6.14.a and TABLE D 3.6.14-1 Instrument 1 B and note (d) applies. Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action Sat/Unsat SatlUnsat Sat/Unsat PasslFail PasslFail SatlUnsat PasslFail NRC SRO ADMIN JPM 4 3 October 2006 shown in TBL D 3.6.14-1. Determines action (d) applies. PasslFail Effluent releases via this pathway can continue provided that at least once per twelve (12) hours grab samples are collected and analyzed SW effluent.
: 1. The plant is operating at 100&deg;/~power.
Initiates CR for unplanned LCO entry. Sat/Unsat End of JPM TERMINATING CUE:
: 2. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.
SW Radiation Monitor flow adjusted and restored to operable status. RECORD STOP TIME NRC SRO ADMIN JPM 4 4 October 2006 Initial Conditions:
: 3. HI-4-5, LQ PROCESS RAD MON, has alarmed.
: 1. The plant is operating at 100% power. 2. High wind conditions (20-25 mph with higher gusts) are present and are
: 4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
: 5. Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.
: 6. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).
7 . Sample flow cannot be adjusted.
8 . Ask the operator for any questions.
Initiating cue:
(Operators name), determine the appropriate actions in response to these conditions.
: 1. Provide repeat back of initiating       Proper communications used for            Sat/Unsat cue. Evaluator Acknowledge           repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
: 1. .Obtain a copy of the reference       ARP HI-4-5 obtained.                      SatlUnsat procedure and reviewlutilize the Operator Actions referenced.
correct section.
ODCM obtained.
DLCO 3.6.14 referenced.
TBL D3.6.14-1 referenced.
: 2. .Per ARP H I 5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then:
: a. *Notify Radiation Protection       Notifies Radiation Protection              Sat/Unsat Instrument Support for repair. Instrument Support to initiate repairs.
b..lnitiate LCO sampling             Directs Chemistry to perform DLCO         PasslFail (Chem istry).                      sampling per TBL D 3.6.14-1 InstrumentlB action (d); twelve (12) hour grab samples to be collected/analyzed for SW effluent.
: 3. .Reference ODCM and takes              Determines SW Radiation Monitor is         PasslFail appropriate actions.                  inoperable.
References ODCM DLCO 3.6.14.a             SatlUnsat and TABLE D 3.6.14-1 Instrument 1B and note (d) applies.
Determines less than the minimum number of radioactive liquid effluent     PasslFail monitoring channels for service water effluent and takes action NRC SRO ADMIN JPM 4         3       October 2006
 
shown in TBL D 3.6.14-1.
Determines action (d) applies.         PasslFail Effluent releases via this pathway can continue provided that at least once per twelve (12) hours grab samples are collected and analyzed SW effluent.
Initiates CR for unplanned LCO         Sat/Unsat entry.
End of JPM TERMINATING CUE: SW Radiation Monitor flow adjusted and restored to operable status.
RECORD STOP TIME NRC SRO ADMIN JPM 4         4       October 2006
 
Initial Conditions:
: 1. The plant is operating at 100% power.
: 2. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.
: 3. HI-4-5, LQ PROCESS RAD MON, has alarmed.
: 3. HI-4-5, LQ PROCESS RAD MON, has alarmed.
: 4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
: 4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
: 5. Operator reports an EQUIP FAIL Light is shown for the Service Water
: 5. Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.
: 6. Chemistry reports alarm is caused by low sample flow. Flows are reading
: 6. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).
: 7. Sample flow cannot be adjusted.
: 7. Sample flow cannot be adjusted.
: 8. Ask the operator for any questions. expected to continue for the next twelve (12) hours. Discharge Monitor at the J Panel. 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB). Initiating cue: "(Operator's name), determine the appropriate actions in response to these conditions . " NRC SRO ADMIN JPM 4 5 October 2006 Attachment 1 JPM Scorecard KEY 1 Determine the appropriate actions in response to these conditions.
: 8. Ask the operator for any questions.
I Action Direct Chemistry to initiate required LCO sampling Determines SW Radiation Monitor is inoperable.
Initiating cue:
Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in TBL D 3.6.14-1.
(Operators name), determine the appropriate actions in response to these conditions .
Determines action identified in note (d) applies. Effluent releases via this pathway can continue provided that at least once per twelve (1 2) hours grab samples are collected and analyzed SW effluent.
NRC SRO ADMIN JPM 4   5   October 2006
Required By (Document)
 
ARP H 1-4-5 ODCM DLCO 3.6.14 TABLE D 3.6.14-1.
Attachment 1 JPM Scorecard KEY 1 Determine the appropriate actions in response to these conditions.
ODCM DLCO 3.6.14 TABLE NOTE (d) NRC SRO ADMIN JPM 4 6 October 2006 I Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.
I Action                                         Required By (Document)
Action qequired By (Document) 7 October 2006 NRC SRO ADMlN JPM 4 
Direct Chemistry to initiate                   ARP H 1-4-5 required LCO sampling Determines SW Radiation Monitor is inoperable.
Determines less than the                       ODCM DLCO 3.6.14 TABLE D minimum number of                             3.6.14-1.
radioactive liquid effluent monitoring channels for service water effluent and takes action shown in TBL D 3.6.14-1.
Determines action identified in note (d) applies. Effluent                 ODCM DLCO 3.6.14 TABLE releases via this pathway                     NOTE (d) can continue provided that at least once per twelve (1 2) hours grab samples are collected and analyzed SW effluent.
NRC SRO ADMIN JPM 4   6   October 2006


CONSTELLATION ENERGY GROUP OPERATOR JOB PERFORMANCE MEASURE Title: Emergency Classification With PARS Task Number: N/A Revision:
I Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.
NRC 2006 NA EXAMINATION SECURITY I Genejal Supervisor  
Action                                      qequired By (Document)
/ Date ' General Supervisor Date Operations Training (Designee) Operations (Designee)
NRC SRO ADMlN JPM 4    7    October 2006
V4-z &k3& NA EXAMINATION SECURITY Configuration Control Date Performer:
 
PRO) Trainer/Evaluator:
CONSTELLATION ENERGY GROUP OPERATOR JOB PERFORMANCE MEASURE Title:   Emergency Classification With PARS                                       Revision: NRC 2006 Task Number: N/A V4-z&k3&
Evaluation Method: X Evaluation Location:
Genejal Supervisor /           Date   '   I NA EXAMINATION SECURITY General Supervisor                       Date Operations Training (Designee)                         Operations (Designee)
Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: YES Alternate Path Task: NO Perform Simulate Start Time: Stop Time: Completion Time: JPM Overall Rating: Pass Fail - NOTE: A JPM overall rating of fail shall be given if critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
NA EXAMINATION SECURITY Configuration Control           Date Performer:                                             PRO)
Evaluators Signature: Date:
Trainer/Evaluator:
SRO ADMIN JPM 5 October 2006 Recommended Start Location: (Completion time based on the start location)
Evaluation Method:     X         Perform                          Simulate Evaluation Location:             Plant                 X         Simulator or other location Expected Completion Time:       20 min Time Critical Task:       YES     Alternate Path Task: NO Start Time:                     Stop Time:                       Completion Time:
Any appropriate location with proper references. Simulator Set-up (if required):
JPM Overall Rating:             Pass           Fail
-
NOTE: A JPM overall rating of fail shall be given if       critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:                                                     Date:
SRO ADMIN JPM 5               October 2006
 
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with proper references.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
None Directions to the Instructor/Evaluator:
None Directions to Operators: Read Before Every JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
None Directions to Operators:
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.
Read Before Every JPM Performance:
The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:
For the performance of this JPM, I will function as the SM,CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor  
Notes to Instructor / Evaluator:
/ Evaluator:
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a
: 1. 2. During Evaluated JPM:
    ".".
: 3. During Training JPM: Critical steps are identified in grading areas PasslFail.
: 2. During Evaluated JPM:
All steps are sequenced critical unless denoted by a ".". 0 Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.
Self checking shall be demonstrated.
References
: 3. During Training JPM:
0    Self checking shall be demonstrated.
Peer checking shall be demonstrated.
 
==References:==
: 1. EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations
: 1. EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations
: 2. EPIP-EPP-20, Emergency Notifications
: 2. EPIP-EPP-20, Emergency Notifications
: 3. EAL Matrix SRO ADMIN JPM 5 October 2006 Tools and Equipment:
: 3. EAL Matrix SRO ADMIN JPM 5                   October 2006
 
Tools and Equipment:
: 1. EAL Matrix Task Standard:
: 1. EAL Matrix Task Standard:
Given a set of plant conditions, classify the emergency (within 15 min.), and complete the Part 1 Notification Fact sheet including PARS (within 15 min.) Initial Conditions:
Given a set of plant conditions, classify the emergency (within 15 min.), and complete the Part 1 Notification Fact sheet including PARS (within 15 min.)
: 1. 2. 3. The plant is under accident conditions.
Initial Conditions:
A Site Area Emergency has been declared based on plant conditions. The Chemistry Technician has reported the following release data:
: 1.     The plant is under accident conditions.
0 0 0 Dose assessment for ground level release rate is 58 Curies per second (Ci/second)
: 2.      A Site Area Emergency has been declared based on plant conditions.
Dose assessment for elevated level release rate is 502 Cilsecond Wind speed is 8 mph Wind direction is from the East South East (1 50") Pascal Stability Class is E Initiating Cues : "(Operator's name), Take the required actions as the Emergency Director."
: 3.      The Chemistry Technician has reported the following release data:
Grade Performance Steps Standard Evaluator Note: Inform the Candidate that this is a Time-Critical task
Dose assessment for ground level release rate is 58 Curies per second (Ci/second) 0    Dose assessment for elevated level release rate is 502 Cilsecond 0    Wind speed is 8 mph 0    Wind direction is from the East South East (150)
: 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary.
Pascal Stability Class is E Initiating Cues :
(Operators name), Take the required actions as the Emergency Director.
Performance Steps                                       Standard                                       Grade Evaluator Note: Inform the Candidate that this is a Time-Critical task
: 1. Provide repeat back of initiating cue.             Proper communications used for repeat        Sat/Unsat Evaluator Acknowledge repeat back                 back (GAP-OPS-Ol/Operations Manual) providing correction if necessary.
RECORD TASK 1 CRITICAL START TIME
RECORD TASK 1 CRITICAL START TIME
: 2. Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.
: 2. Obtain a copy of the reference procedure           The candidate may reference anylall of        SaVUnsat and reviewhtilize the correct section of the       the following:
: 3. Using given plant data and EPIP-EPP-08 Attachment 1 Table 1 .I and Table 1.2, determine that a General Emergency exists based upon calculated total release (ground release + elevated release).
procedure.                                         EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1 EPIP-EPP-18 EPIP-EPP-20 Att. 1A
RECORD TASK 1 CRITICAL STOP/
: 3. Using given plant data and EPIP-EPP-08             General Emergency is declared, within 15      PasslFail Attachment 1 Table 1 .Iand Table 1.2,             minutes of recorded start time for Task 1.
TASK 2 CRITICAL START TIME 4. Review meteorological data and EPIP- EPP-08 and/or EPIP-EPP-20 to determine SRO ADMIN JPM 5 Proper communications used for repeat back (GAP-OPS-Ol/Operations Manual) The candidate may reference anylall of the following: EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1 EPIP-EPP-18 EPIP-EPP-20 Att. 1A General Emergency is declared, within 15 minutes of recorded start time for Task 1. PAR'S made and indicated on Part I Notification Fact Sheet to evacuate ERPA's 1, 2, 3, 26, and 27 and shelter all October 2006 Sat/Unsat SaVUnsat PasslFail PasslFail PAR's. remaining ERPA's, within 15 minutes of recorded start time for Task 2. RECORD TASK 2 CRITICAL STOP TIME Terminating Cue: RECORD STOP TIME The event is classified as a General Emergency and PAR's are made. SRO ADMIN JPM 5 October 2006 Initial Conditions:
determine that a General Emergency exists based upon calculated total release (ground release + elevated release).
: 1. 2. 3. The plant is under accident conditions. A Site Area Emergency has been declared based on plant conditions.
RECORD TASK 1 CRITICAL STOP/ TASK 2 CRITICAL START TIME
The Chemistry Technician has reported the following release data:
: 4. Review meteorological data and EPIP-               PARS made and indicated on Part I            PasslFail EPP-08 and/or EPIP-EPP-20 to determine             Notification Fact Sheet to evacuate ERPAs 1, 2, 3, 26, and 27 and shelter all SRO ADMIN JPM 5              October 2006
 
PARs.                                     remaining ERPAs, within 15 minutes of recorded start time for Task 2.
RECORD TASK 2 CRITICAL STOP TIME Terminating Cue: The event is classified as a General Emergency and PARs are made.
RECORD STOP TIME SRO ADMIN JPM 5               October 2006
 
Initial Conditions:
: 1. The plant is under accident conditions.
: 2. A Site Area Emergency has been declared based on plant conditions.
: 3. The Chemistry Technician has reported the following release data:
Dose assessment for ground level release rate is 58 Curies per second (Cilsecond)
Dose assessment for ground level release rate is 58 Curies per second (Cilsecond)
Dose assessment for elevated level release rate is 502 Cilsecond. Wind speed is 8 mph Wind direction is from the East South East (1 50') Pascal Stability Class is E Initiating Cues: "(Operator's name), Take the required actions as the Emergency Director."
Dose assessment for elevated level release rate is 502 Cilsecond.
SRO ADMIN JPM 5 October 2006}}
Wind speed is 8 mph Wind direction is from the East South East (150)
Pascal Stability Class is E Initiating Cues:
(Operators name), Take the required actions as the Emergency Director.
SRO ADMIN JPM 5     October 2006}}

Revision as of 08:04, 23 November 2019

Draft - Section a Operating Exam (Folder 2)
ML070820563
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/24/2006
From: Shortell T
Constellation Energy Group
To: Caruso J
Operations Branch I
Shared Package
ML060800077 List:
References
Download: ML070820563 (69)
v • d • e


Text

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point 1 Date of Examination: December 11, 2006 Examination Level: RO Operating Test Number: NA Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform N1-ST-DO, Daily Checks (Partial)

Conduct of Operations Record control room instrument readings for recirc loop Plant parameter temperatures, reactor water level instruments and hotwell level.

Verification D With tech spec readings out of spec for RPV water level and hotwell level, identify impact on Tech Spec related equipment.

RO ADMIN 1 Readings are taken in the simulator and entered into the applicable sections of the Daily Checks.

2.1 . I 8 (2.9) Ability to make accurate / clear and concise logs I records I status boards Iand reports.

GAP-OPS-01; 3.10, N1-ST-DO section 6.0, 7.0 and 8.0 Determine Plant Impact of Mispositioned Liquid Poison Components Conduct of Operations N Evaluate system lineup, determine both Liquid Poison Pumps Configuration Control are not available to inject. Identify the Tech Spec impact.

RO ADMIN 2 2.1. I 1 (3.0) Knowledge of less than one hour technical specifications for systems.

DWG C-18019-C; N1-OP-12, Tech Spec 3.1.2 RPS Logic Operation with EOP-3.1 RPS Jumpers Installed N Identify and locate electrical drawings related to RPS circuits.

Equipment Control Use the drawings to describe the effect of installing RPS Use of Electrical Prints jumpers on how scram signal is reset prior to initiating another RO ADMIN 3 manual scram, with the jumpers installed under failure to scram conditions. (Perform in simulator and supply with copies for candidate to mark-up).

2.12 4 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.

N1-EOP-3.1; Drawincl C-19859-C SH 4 and 7 Radiological Requirements Related Entry Into High Radiation Control Radiation Areas Radiation Hazards M, P Given radiological conditions and a survey map related to an RO ADMIN 4 NRC 2004 area to be inspected, ensure the appropriate radiological aspects of the job are met prior to performance of the inspection.

2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

GAP-RPP-02; 3.1, 3,3. GAP-RPP-08; 3.2, 3.3 N0TE: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)revtous 2 exams ( 1, randomly selected) 1012412006 10:29:08 AM 1of1 2006 Unit 1 NRC RO Admin Outline Submittal

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Perform N1-ST-DO DAILY CHECKS (Partial) Revision: NRC 2006 Task Number:

Amrovals:

NA EXAM SECURITY I Genpral Supervi6or Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAM SECURITY I Configuration Control Date Performer: (ROISRO)

TrainerIEvaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC RO ADMIN JPM 1 October 2006

Recommended Start Location: (Completion time based on the start location)

If actual readings are to be taken, Simulator must be setup and used, otherwise perform in other designated area.

Simulator Set-up:

IC-238 contains setup conditions for Admin JPMs 1. TURN OFF PI MONITOR. JPM readings are taken with simulator in FREEZE.

Establish 70% reactor power, 40 mlb/hr total recirc flow, align Feedwater Level Column to 72, and override reactor water level and hotwell level instruments as necessary to read those indicated in the Attachment. Override both hotwell indication to 55 inches and activate crywolf for alarms H2-2-7 and 3-7 for low level, Directions to the Instructor/Evaluator:

Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM I CSO permission.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a e.
2. During Evaluated JPM:

0 Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

NRC RO ADMlN JPM 1 -2 - October 2006

References:

1. GAP-OPS-01; 3.10.
2. N1-ST-DO; 6.0, 7.0 and 8.0.
3. 2.1 . I 8 (2.9) Ability to make accurate / clear and concise logs / records / status boards / and reports.

Tools and Equipment:

1. None Task Standard:

Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

Initial Conditions:

1. The plant is operating at 75% power.
2. Surveillance test N1-ST-DO, DAILY CHECKS, is in progress
3. ALL computer point readings are consistent with control room panel instrument readings.
4. Ask the operator for any questions.

Initiating cue:

(Operators name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment Isections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO.

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator A cknowle dge repeat back (GAP-OPS-01 )

back providing correction if necessary RECORD START TIME

1. *Obtain a copy of the reference N-ST-DO obtained. SatlUnsat procedure and review/utilize the - Section 6.0, 7.0 and 8.0 referenced.

correct section.

NOTE: Completed N1-ST-DO is provided as an Attachment 2 to this JPM.

2 . *Records section 6.0 Reactor Records Reactor Recirc Pump Inlet Sa tlU nsat Recirc Pump Inlet Temperature Temperature readings.

readings

3. Compares reading and Compares reading and determines PasslFail determines readings within 15°F readings within 15°F of each other.

Checks YES block in Section 6.0, PasslFail indicating the maximum difference in loop temperatures is < 15°F.

NRC RO ADMIN JPM 1 October 2006

4. .Records section 7.0 readings. Recorded Section 7.0 LOW-LowLevel PasslFail alarm and Feedwater Level Column selected to checks agree with Attachment 1 without error.

Recorded Section 7.0 instrument PasslFail readings agree with Attachment 1 within k 1 inch.

Sat/Unsat Record Total Recirc Flow per step 7.1.2 for GEMAC variance check.

5. .Compares YARWAY C h l l - Determines YARWAY (RPS Level Sat/Unsat Ch12 (RPS Level Column) Column) instrument readings differ by 5 instrument readings to guide which is above the guide value of 4.

values.

Determines YARWAY (RPS Level PasslFail Column) instruments OPERABLE.

Indicates an ACR is required to have the Sat/Unsat calibration checked.

6. .Performs GEMAC C h l l - Ch12 Determines GEMAC variance is 6 SatlUnsat variance check per Section 7.1.

Compares GEMAC variance to total SatlUnsat recirc flow and determines on line between ALERT RANGE and INOP.

Determines that GEMAC I 1 or GEMAC PasslFail 12 must be declared inoperable.

Reports out of specification readings to PasslFail SRO.

7. .Records section 8.0 Records Condensate readings Sat/Unsat Condensate readings Determines Hotwell level is below 57 PasslFail inches (Tech Spec Minimum)

Informs SRO Hotwell level is below 57 PasslFail inches (Tech Spec Minimum).

<Ref 2> is TS 3.1.8, HPCl is inoperable. PasslFail

8. Provides completed sections to SRO informed of out of spec readings. Sat/Unsat SRO. Informs of out of spec readings.

End of JPM TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

RECORD STOP TIME NRC RO ADMIN JPM 1 October 2006

Initial Conditions:

1. The plant is operating at 75% power.
2. Surveillance test N1-ST-DO, DAILY CHECKS, is in progress
3. ALL computer point readings are consistent with control room panel instrument readings.
4. Ask the operator for any questions.

Initiating cue:

(Operators name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment 1 sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO.

NRC RO ADMlN JPM 1 October 2006

I Setup Attachment Panel Meter Override Meter Value Reading Settings Obtained 1 E-Panel Vessel Level Indicator (E Panel i D 5 9 ~ )

I 70'5 1 k:hes K-Panel Vessel Level Indicator (K Panel: 36-96 ID5 1 75

~~

1 ~

k:hes

~

K-Panel Flange Level Indicator (K Panel: ta ~ i of g ~ None

~ Below -3

~ $ - ~ $ ~ ft Reactor Vessel Level Recorder (F Panel: 36-SSJ 72.5 74 inches Wide Range Level Indicator (FPane/: 36-94) 7.2 6 ft I Ch 11 Ch 12 11 12 1 GEMAC Level Column ( F ane el: 36-76A,

~ 6 ~ ~ ~ A }

I 77.5 I 69.5 1 79-80; 73

~

RPS Level Column <Ref 1> (F Panel: 36- 76 ~~ 1 - 7 2 - F NRC RO ADMIN JPM 1 October 2006

- - -

ATTACHMENT 1 (Cont)

ANSWER KEY. DO NOT PROVIDE TO APPLICANT Reactor Recirc Pump Inlet Temperature RRP 11 Inlet Temp 520 OF RRP 12 Inlet Temp 525 OF RRP 13 Inlet Temp 520 OF RRP 14 Inlet Temp 530 OF RRP 15 Inlet Temp 520 OF Maximum difference in loop temperatures 15°F YES No 7.0 Control Room Reactor Water Level Checks Low-Low Level Alarms IF YES, provide reason in Remarks OYES BNO Feedwater Level Column selected to (E Pane!] El11 12 I E-Panel Vessel Level Indicator (Panel) I 73 I inches I I K-Panel Vessel Level Indicator (K Panel: 36-96) I 76 I inches I K-Panel Flange Level Indicator (K Panel: to ~

I Reactor Vessel Level Recorder (F Pane/: 36-98) i of g II ~ ~

c-3 74 vet-1 inches 1 I I Wide Range Level Indicator ( f Pane/: 36-94] I 6 I feet I If reading difference is greater than the guide valve, review previous readings for the instrument(s). If a single reading is the cause for the recorded value being greater than the guide value, verify that reading. If reading difference is still greater than guide value, consider the indicator OPERABLE and generate an ACR to have the calibration checked. If reading difference is grossly greater than guide value, consider the indicator INOPERABLE, enter applicable Tech Spec action and generate an ACR.

    • See Section 7.1
      • If the difference between Yarway indicators Ll-36-09 and LI-36-10 is 6" or greater, THEN declare the following instruments inoperable and initiate the required Technical Specification actions (ESA for DER 1-2001-3027):

LT-36-03C, LT-36-03D LT-36-04C, LT-36-04D LT-36-216, LT-36-21D NRC RO ADMlN JPM 1 October 2006

ATTACHMENT 1 (Cont)

ANSWER KEY. DO NOT PROVIDE TO APPLICANT 7.1 GEMAC Variance Check 7.1. I Calculate Variance Between Ch 12 and Ch 11 GEMAC Level Recorders.

73 - 79 -- 6 /

Ch 12 Ch 11 Variance (in.)

/

Ind. Verif 7.1.2 Record Total Recirc Flow 40 MllblHr {E init / date 7.1.3 Verify GEMAC 11112 Variance as a function of Total Recirc Flow is in the Acceptable Range as determined in the Graph below. (Note, ignore negative sign, if any.)

0 Yes (Sat) 4 No (Unsat), DER Required init / date If results are in ALERT range, generate DER for Engineering Evaluation.

If results are in INOP range, declare GEMAC 11 and/or 12 INOP.

GEMAC LEVEL COLUMN 11 / 12 VARIANCE 10 9

8 v) w 7 I

F 6 0

5 5

>

-

0,

- 1 4 crr x

n 3 2

1 0

0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 Total Recirc Flow wlb/Hr)

NRC RO ADMIN JPM 1 October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Plant Impact of Mispositioned Liquid Poison Components Revision: NRC 2006 Task Number:

Ap provaIs:

/,&3b!mc. NA EXAM SECURITY I Ge n$a I S upervisqfr Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAM SECURITY I Configuration Control Date Performer: (RO)

TrainerIEvaluator:

Evaluation Method: X Perform Simulate EvaIuat ion Location : Plant X Simulator or other location Expected Completion Time: 15 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature: Date:

NRC RO ADMIN JPM 2 October 2006

Simulator or other designated location with prints and procedures available Simulator Set-up (if required):

NA Directions to the Instructor/Evaluator:

Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec.

Operability, operational status, or the effects are unknown, obtain specific SM / CSO permission.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a 0 .
2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. P&ID C-18019-C
2. N1-OP-I2, Attchment2
3. Tech Spec 3.1.2 Tools and Equipment:

NRC RO ADMIN JPM 2 October 2006

1. N o n e Task Standard: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required.

Initial Conditions:

1. The plant is in operating at 100% power.
2. Red clearance is being applied to Liquid Poison Pump 12 for corrective maintenance on the pump.
3. You are the Independent Verifier for the red clearance.
4. The first clearance tag is found on Power Board 17B Breaker 42-38 and the breaker is disconnected and open.
5. The next clearance tag is found on valve 41-07 and the valve is unlocked and closed.

Initiating cue:

(Operators name), determine plant impact of this configuration.

Performance Steps Standard Grade

1. Provide repeat back of initiating cue. Proper communications used for repeat SatlUnsat Evaluator Acknowledge repeat back back (GAP-OPS-O1/ CNG-HU-1 .Ol-1001) providing correction if necessary.

RECORD START TIME

2. Consults reference documents to Refers to any of the following Sat/Unsat determine effect of the given component documents to determine function of lineup. PB 17B breaker 42-38 and 41-07 N1-OP-12 P & ID C-18019-C Any other document that indicated power supply for LP Pump 12 and suction valve for LP Pump 11 are the affected components
2. Identifies LP Pump 12 is unable to inject Determines that with PB 17B BKR 42- Pass/Fail (inoperable), with PI3 178 42-38 open. 38 open and disconnected, LP Pump 12 is deenergized and inoperable.
3. Identifies LP Pump 11 is unable to inject Determines that with 41-07 closed LP Pass/Fail (inoperable), with 41 -07 closed. Pump 11 is inoperable because of loss of suction path.
4. Identifies tag applied to incorrect Determines that 41-1 1 should have Sat/Unsat component. Informs Control Room per been closed.

GAP-OPS-01. Notifies CRS of improperly positioned Sat/Unsat com ponents and incorrect application of red clearance tag.

5. Determines Tech Spec LCO conditions Determines that these conditions Sat/Unsat NRC RO ADMIN JPM 2 October 2006

I Performance Steps Standard Grade for liquid Poison are exceeded. result in Tech Spec entry for the Liquid Poison system.

6. Refers to LCO 3.1.2 o Identifies LCO 3.1.2 Specification b. Sat/Unsat applies because the redundant component is also inoperable.

If a single pump was inoperable 7 days would be allowed to restore the inop Pump Since both are inoperable, specification e applies and an orderly shutdown must be initiated within one hour.

7. Determines that one subsystem must be Identifies the requirement to restore Pass/Fail restored to operable. one of the redundant components to OPERABLE within one hour or an orderly shutdown is required End of JPM Terminating Cue: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required.

RECORD STOP TIME NRC RO ADMIN JPM 2 October 2006

a. Com munications Per CNG-HU-1.01-1001 Sat/Unsat Per GAP-OPS-0 1
b. Verification of Actions Per CNG-HU-1.01-1001 SatlUnsat Per GAP-OPS-01
c. Procedural CompliancelPlacekeeping Per CNG-HU-1.01-1001 SatlUnsat Per NIP-PRO-01 Per GAP-OPS-01
d. Safety Compliance Per NIP-OSH-01 Sat/Unsat Per Personnel Safety Manual
e. Radiation Protection Compliance Per GAP-RPP-01 Sat/Unsat Per GAP-RPP-02 Overall Work Practice Competency Result PasslFail NOTE: 1. UNSAT in any competency area requires oral remediation of unsat area.
2. Fail in Overall Work Practice Competency Results requires review and evaluation of work practices using the Work Practices JPM (U1 using 01-REQ-SJE-WPJ-1-00 and U2 using 02-REQ-SJE-WPJ-2-00).

NRC RO ADMIN JPM 2 October 2006

I n G I Conditions:

1. The plant is operating at 100% power.
2. Red clearance is being applied to LP PUMP 12 for corrective maintenance on the pump.
3. You are the Independent Verifier for the red clearance.
4. The first clearance tag is found on PB 17B Breaker 42-38 and the breaker is disconnected and open.
5. The next clearance tag is found on valve 41-07 and the valve is closed.

Initiating cue:

(Operators name), determine plant impact of this configuration.

NRC RO ADMIN JPM 2 October 2006

JPM 2 Scorecard For Applicant Use

-

Determine plant impact of this configuration.

c Impact of Configuration on System Impact on plant operation NRC RO ADMIN JPM 2 October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: N1-EOP-3.1 RPS Jumper Operation Electrical Print Reading Revision: NRC 2006 Task Number: N/A NA EXAMINATION SECURITY General Supervisor Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate Eva1uat ion Location : Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:

NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC RO ADMIN JPM 3 Draft October 2006

Recommended Start Location: (Completion time based on the start location)

For NRC Exam 2006, This Admin JPM is performed in Simulator.

Simulator Set-up:

None Directions to the Instructor/Evaluator:

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor I Evaluator:

1. Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a 0 .
2. During Evaluated JPM:

0 Self-verification shall be demonstrated.

3. During Training JPM:

0 Self-verification shall be demonstrated.

0 No other verification shall be demonstrated.

References:

1. Drawing C-19859-C Sheet 4 and 7
2. N1-EOP-3.1, Alternate Control Rod Insertion
3. K/A 2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.

Tools and Equipment:

1. None.

Task Standard: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.

NRC RO ADMIN JPM 3 Draft October 2006

Initial Conditions:

1. The plant is experiencing a failure to scram.
2. N1-EOP-3 has been entered.
3. EOP Director directs execution of EOP-3.1.
4. Repeated manual scrams will be attempted.
5. Ask the operator for any questions.

Initiating cue: (Operators name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component (relays, contacts and switches) operation necessary to reset the RPS Channel 12 scram logic.

1. Provide repeat back of Proper communications used for repeat Sat/Unsat initiating cue. Evaluator back (GAP-OPS-01)

Acknowledge repeat back providing correction if necessary RECORD START TIME

1. Obtain a copy of the necessary Obtains the following documents, as procedures and drawings needed:

N1-EOP-3.1 Sat/Unsat/NA Drawing Index, if needed Sat/Unsat/NA 0 Drawing C - I 9859-C Sheet 7 PasslFail

2. Using C - I 9859-C Sheet 7, Locates SCRAM BYPASS jumper PasslFail locates trip circuits and jumpers. (EOP jumper 12) at drawing coordinate A-I to A-5, in REACTOR TRIP # I circuit.

Locates SCRAM BYPASS jumper PasslFail (EOP jumper 13) at drawing coordinate B-1 to B-5, in REACTOR TRIP #2 circuit.

3. Using C-19859-C Sheet 7, Identifies that ALL AUTOMATIC PasslFail identifies the signals defeated scram signal relay trip contacts are when jumpers are installed. bypassed when jumper is installed.

NOTE: The manual scram circuit is not bypassed by the jumpers.

NRC RO ADMIN JPM 3 Draft October 2006

4. Using C-19859-C Sheet 7, Indicates when jumper is installed in PasslFail describes electrical component REACTOR TRIP #I circuit, relay operation necessary to reset the 12K51A (coordinate B-5) energizes scram. and closes the following contacts:

0 12K51A L1-TI for GROUP 1 (coordinate D-2) 0 12K51A L2-T2 for GROUP 2 (coordinate E-2) 0 12K51A L3-T3 for GROUP 3 (coordinate F-2) 0 12K51A L4-T4 for GROUP 4 (coordinate G-2) 0 12K51A 7-8 for Backup Scram circuitry (coordinate H-2)

Indicates when jumper is installed in PasslFail REACTOR TRIP #2 circuit, relay 12K52A (coordinate C-5) energizes and closes the following contacts:

0 12K52A L1-TI for GROUP 1 (coordinate D-2) 0 12K52A L2-T2 for GROUP 2 (coordinate E-2) 12K52A L3-T3 for GROUP 3 (coordinate F-2) 0 12K52A L4-T4 for GROUP 4 (coordinate G-2) 0 12K52A 7-8 for Backup Scram circuitry (coordinate H-2)

Indicates that depressing switch SaVUnsat 1S3, RESET REACTOR TRIP (SCRAM) pushbutton (coordinate C-4), closes its 1S3 7-8 contact and energizes relay 12K53 (coordinate C-5) (while reset button is depressed).

NRC RO ADMIN JPM 3 Draft October 2006

Indicates that Relay 12K53 Sat/Unsat energizing closes its 7-8 contact (coordinate D-4) and energizes relay 12K55 and 12K56 (coordinate D-5) in REACTOR MANUAL SCRAM circuit Indicates that Relay 12K55 PasslFail energizing and closes the following contacts:

0 12K55 L1-TI for GROUP 1 (coordinate D-2) 0 12K55 L2-T2 for GROUP 2 (coordinate E-2) 0 12K55 L3-T3 for GROUP 3 (coordinate F-2) 0 12K55 L4-T4 for GROUP 4 (coordinate G-2) 12K55 7-8 for Backup Scram circuitry (coordinate H-2)

Indicates that Relay 12K56 provides SatlUnsat a seal-in to keep 12K55 energized when 12K53 drops out after the scram reset pushbutton is released.

Indicates that when all three contacts PasslFail in the four GROUP 1 through 4 circuits for 12K51A, 12K52A and 12K55 are closed the scram is reset (for channel 12). Four white lights on F and M panels are ON and the scram pilot solenoids are energized for RPS Channel 12.

10. Reports JPM complete Reports JPM complete Sat/Unsat NRC RO ADMIN JPM 3 Draft October 2006

TERMINATING CUE: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.

RECORD STOP TIME NRC RO ADMIN JPM 3 Draft October 2006

Initial Conditions:

1. The plant is experiencing a failure to scram.
2. N1-EOP-3 has been entered.
3. EOP Director directs execution of EOP-3.1.
4. Repeated manual scrams will be attempted.
5. Ask the operator for any questions.

Initiating cue: (Operators name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component operation necessary to reset the RPS Channel 12 scram logic.

NRC RO ADMIN JPM 3 Draft October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Radiological Requirements Related to Entry Into Revision: NRC 2006 High Radiation Areas Task Number: N/A

- - NA EXAMINATION SECURITY Genefal Supervisal/ Datd General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 10 minutes Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC RO ADMIN JPM 4 October 2006

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated location.

Simulator Set-up:

N/A Directions to the InstructodEvaluator:

RWPs and survey maps are to be provided.

Directions to Operators:

Read Before Everv JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a ".".
2. During Evaluated JPM:

0 Self checking shall be demonstrated.

3. During Training JPM:

0 Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References

1. GAP-RPP-01; 3.5.
2. GAP-RPP-02; 3.3.
3. GAP-RPP-08; 3.2.
4. GAP-RPP-07; 3.2.5
5. KIA 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

Tools and Equipment:

1. None.

Task Standard: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.

NRC RO ADMIN JPM 4 October 2006

Initial Conditions:

1. Unit 1 is operating at 100% power.
2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
3. Current exposure is 1800 mrem TEDE.
4. RWP and survey map are provided.
5. Ask the operator for any questions.

Initiating cue:

(Operators name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel. RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard.

1. Provide repeat back of initiating Proper communications used for repeat SatlUnsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME NOTE: A score card is attached to this JPM identifying the items for the performer to identify.
2. Classify the area. Determines the area is a HIGH PasslFail RADIATION AREA.
3. Determine highest on contact Determines highest on contact dose PasslFail and general area dose rates and rate to be 500 mremlhr at 12 SDC location, based on survey map Pump.

Determines highest general area PasslFail dose rate to be 100 mrem/hr near BV 38-03, 12 SDC Pump and 11 SDC Heat Exchanger.

4. Determines highest Determines highest contamination PasslFail contamination levels in the room. level to be 8000 dpm/lOO cm2at 12 SDC Pump, smear location #7.
5. Determine RWP and Task Determines RWP I06001 Task 2 is PasslFail Number required for entry. correct for the job.

6 . Determines insufficient delta Determine within delta exposure of PasslFail exposure to enter without 300 mrem and additional approvals additional approval. required prior to performing the inspection. (GAP-RPP-08 3.2.2, minimum delta exposure of 300 mRem needed to enter HRA). Admin limit of 2000 mr, from GAP-RPP-07.

2000 - 1800 = 200 mrem delta 300 mrem delta is required.

NRC RO ADMIN JPM 4 October 2006

End of JPM TERMINATING CUE: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.

RECORD STOP TIME NRC RO ADMIN JPM 4 October 2006

Initial Conditions:

1. Unit 1 is operating at 100% power.
2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
3. Current exposure is 1800 mrem TEDE.
4. RWP and survey map are provided.
5. Ask the operator for any questions.

Initiating cue:

(Operators name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel. RWP and survey maps are provided.

Address the radiological aspects of performing this job and record findings on scorecard.

NRC RO ADMlN JPM 4 October 2006

I Answer the following when performing this task: I 0 High Radiation Area 0 Locked High Radiation Area 0 Very High Radiation Area 2.

Designate the highest on contact dose rate in the area and the location AND the I highest general area dose rate and location:

0 Acceptable 0 Additional approval(s) required NRC RO ADMIN JPM 4 October 2006

NOTE: THIS IS THE EXAMINER SCORECARD.

DO NOT PROVIDE TO THE CANDIDATE.

Answer the following when performing this task:

J High Radiation Area Locked High Radiation Area 500 mrem/hr on contact at 12 SDC Pump I00 mrem/hr near BV38-03 and I 1 SDC Pump, 12 SDC Pump and I 1 SDC Heat Exchanger (east side of HX).

3. PasslFail Designate the highest contamination levels in the room and location:

8,000 dpm/lOOcmZ at 12 SDC Pump at smear location #7

4. Pass/Fail Designate the RWP and task number required to be used:

1 RWP # 106001 Task 2 (because task is in Contaminated High Radiation Area)

5. PasslFail Evaluate delta exposure for entry into the area: (check one):

0 Acceptable

/Additional approval(s) required NRC RO ADMlN JPM 4 October 2006

1 Nine Mile Point Unit One 1 RB 261' Shut-Down I Cooling Room 1 Map No.

25b WORK ON HTX 202-84 /

WO 051895400 Rx Power 100 %

I H, lnj. Rate 6 scfrn I 1 Floor <400 4K e20 1K 1K

'I L

V 2K

- U (PMP-3 149)

FCV-3809(o/h)

I

/ I /

I I /

I I

  • 250 -

50 @ DO NOT LINGER SIGN, 75 WHICH IS ALSO AT BOTTOM

@ 38-05 PIPE TAPS I OF LADDER TO SCAFFOLD I (SHIELDED)

INSULATED PIPES WITHIN REACH OF THE LADDER TRAVEL PATH

"

5.

8.

A=

= Rope/Area

- Boundary Neutron (rnRemlhr)

=Area Rad Monitor 2.

6.

9.

@ =SmearLocation IA/sI =Air Sample v#I = VAMP Number 3,

7.

A

@

= General Area Unless Noted 4.

= LargeArea Wipe

.* = $ ~ ~

7 = Readings in mRernlhr. p = Readings in mRadlhr.

~ ~ t Remarks: All overhead doserates were by use of the teletector Survevor: i HENRY Dose: 9 mRem I Reviewed Bv: Date I

10/24/2006 8: 19:28AM Page 1 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.

7391 Inspections, Maintenance and Surveillances in High Radiation Areas.

TASK: 1 High Radiation Area (HRA)

Dose Alarm 50 mRem Dose Rate Alarm 500 mRemlHr Backoff Dose 40 mRem Protective Clothing Requirements: No Protective Clothing Required.

TLD, Electronic Dosimeter If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.

Instructions:

1) RPS approval and survey required for system breech.
2) Pre-job briefing by RP required. Work crew will provide work area locations
3) HEPA Vacuums & Ventilation Units are radiological engineering instruments: To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry
5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.

ALARA Review Number:

Survey Data:

Radiation Levels:

Turbine Building HRAs 2 - 200mRem/hr Reactor Building HRAs 2 - 250mRemlhr Rad Waste Buiding HRAs 2 - GOOmRem/hr Off Gas Building HRAs 2 - 120mRem/hr Contamination Levels: ~400 - 10,000 dpm/lOOcm2 Airborne Levels: ~ 0 . 3DAC SDecific areas as Der RP briefina and / or survev maw.

Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back

1OI2412OO6 8: 19:28AM Page 2 o f 2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.

7391 Inspections, Maintenance and Surveillances in Contaminated High Radiation Areas.

TASK: 2 High Radiation Area (HRA)

Dose Alarm 50 mRem Dose Rate Alarm 500 mRem/Hr Backoff Dose 40 mRem Protective Clothing Requirements: Single Full Set Of Protective Clothing Hood, Cotton Liners, Rubber Gloves (I), Cotton Boots (I), Rubbers (1)

Coveralls (I), TLD, Electronic Dosimeter Radiation Protection Tech. may change protective clothing, respirator, or other requirements as work locations and conditions change.

Leather gloves may be worn instead of rubber gloves for safety reasons. When Leather gloves are worn, SURGEON gloves or RUBBER MUST be worn underneath them.

Instructions:

1) RPS approval and survey required for system breech.
2) Pre-job briefing by RP required. Work crew will provide work area locations
3) HEPA Vacuums & Ventilation Units are radiological engineering instruments: To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry.
5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.

ALARA Review Number:

Survey Data:

Radiation Levels:

Turbine Building HRAs 2 - 200mRem/hr Reactor Building HRAs 2 - 250mRem/hr Rad Waste Buiding HRAs 2 - GOOmRem/hr Off Gas Building HRAs 2 - 120mRem/hr Contamination Levels: ~ 4 0 -0 10,000 dpm/lOOcrn2 Airborne Levels: ~ 0 . 3DAC Specific areas as per RP briefing and / or survey maps.

Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back

c ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Date of Examination: December 11, 2006 Operating Test Number: NA Describe activity to be performed 9ssess Reportability Requirements For Transient Plant Conduct of Operations N Conditions SRO ADMIN 1 Given a series of plant events, determine the verbal reporting requirements per 10CFR50.72. (CR NM-2006-4134) 2.1 .I8 (3.0) Ability to make accurate/ clear and concise logs/ records/

status boards1and reports.

10CFR50.72, NUREG 1022 REV 2 I

Conduct of Operations N Reactivity Management Events and RMR Review Given plant conditions review an RMR. RMR is not to be approved, based on predicted power/flow map operating point. Determine the SRO ADMIN 2 reactivity event severity level and the appropriate compensatory actions and notifications.

2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics I reactor behavior I and instrument interpretation.

GAP-OPS-05 section 3.13 I

Equipment Control N Determine Thermal Limits with Inoperable Pressure Regulator Given plant parameters including an inoperable reactor pressure SRO ADMIN 3 regulator, determine the adjusted thermal limit values. Core Operating Limit Report graphs and 3D Monicore printout is used to evaluate conditions against the adjusted thermal limits.

2.2.22 (4.1) Knowledge of limiting conditions for operations and safety limits.

N1-RESP-1, Core Operating Limits Report and Tech Spec 3.1.7 Determine Actions Required For an Inoperable Effluent Radiation Control D Radiation Monitor SRO ADMIN 4 Given plant conditions, determine operability of an effluent radiation monitor and apply action statements contained in the station ODCM.

(CR NM-2004-976) 2.3.11 (3.2) Ability to control radiation releases.

ODCM

~

Classify Emergency Event and Perform PARs Emergency Plan Given plant conditions at an existing Site Area Emergency, SRO ADMIN 5 determine the plant conditions now meet General Emergency conditions. Reclassify the event and determine PARs, based on conditions provided. (Time Critical) NRC 2002 SRO JPM A4 2.4.44 (4.0) Knowledge of emergency plan protective action recommendations.

EAL Matrix 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)odifred from bank ( - 1)

(P)revious 2 exams 1 randomlv selected) 10123/2006 3:19:02 PM 1 of1 2006 Unit 1 NRC SRO Admin Outline Submittal

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Assess Reportability Requirements Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Pedormer: (SRO)

Tra iner/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 25 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC SRO ADMIN JPM 1 1 October 2006

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated area.

Simulator Set-up:

NIA Directions to the InstructorIEvaluator:

None Directions to Operators:

Read Before Everv JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a 0 .
2. During Evaluated JPM:

0 Self checking shall be demonstrated.

3. During Training JPM:

0 Self checking shall be demonstrated.

0 Peer checking shall be demonstrated.

References:

1. NIP-IRG-01
2. 10CFR50.72
3. NUREG 1022 Rev 2, Section 3.2.6
4. EAL Matrix
5. CR NM-2006-4134 Plant Event Unit 2 Log Entry 9/5/06 1130 Tools and Equipment:
1. None Task Standard:

Determine notification requirements.

NRC SRO ADMlN JPM 1 2 October 2006

-

Initial Conditions:

The plant is operating at 100% power.

Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.

While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.

After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.

Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and Nl-OP-43C, Plant Shutdown is being implemented.

Reactor power is now at 50%.

Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited.

After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 Psig Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches.

Plant conditions are stabilized and a normal cool down occurs.

Initiating cue:

(Operators name), identify the applicable verbal notification requirements, the reason that they apply and the associated time limitations for reporting under that category.

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 2 *Obtain a copy of the any of the 0 Reference materials obtained.

reference documents related to regulatory notifications. These are likely to include the following:

NIP-IRG-01 10CFR50.72 and 73 NUREG1022 EAL Matrix Note: Invalid isolation during maintenance is illustrated in NUREG 1022, Rev 2, section 3.2.6 System Actuation on page 52, example 7.

NRC SRO ADMIN JPM 1 3 October 2006

3. Locate and identify applicability of 0 Determines actuation of isolation PasslFail 50.72 (b)(3)(iv)(B)(2) logic is not reportable under 50.72 (b)(3)(iv)(B)(2) because the actuation is not due to a valid signal.

LER is not a verbal reporting 0 LER is required under 50.73 SatlUnsatlNA requirement. (b)(Z)(iv). Identification of this requirement is not required.

4. Locate and identify applicability of 0 Identifies leak rate above 10 gpm PasslFail 50.72(a)(I )(i). Declaration of an requires EAL 2.1.1 UNUSUAL Emergency Class. EVENT must be declared.

Identify reportability per 50.72(a)(I )(i) and (a)(3), within 15 minutes of declaration, immediately after notifying State and local agencies and not later than one hour after the time of declaration.

5 . Locate and identify applicability of 0 Refer to Tech Spec 3.2.5.a.1 and SatlUnsat 50,72(b)(Z)(i). Non-emergency determines that with specification not four hour report. Initiation of a being met, the required action to plant shutdown required by Tech comply with Tech Spec is to be cold Specs. (If not already reported shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The plant with the 50,72(a)(l)(i). shutdown being performed is required by Tech Specs.

0 Identify reportability per 50.72(b)( PasslFail 2)(i) within four hours, if not already reported.

6. Locate and identify applicability of 0 Identify reportability per PasslFail 50.72(b)(2)( iv)(B) Non- 50.72(b)(Z)(iv)(B) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if emergency four hour report. not already reported.

Actuation of RPS when the reactor is critical.

7. Locate and identify applicability of Identify reportability per PasslFail 50.72(b)(3)( iv)(B)(5) Non- 50.72(b)(3)(iv)(B)(S) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if emergency eight hour report. not already reported.

Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.

End of JPM TERMINATING CUE: Determine notification requirements.

RECORD STOP TIME NRC SRO ADMIN JPM 1 4 October 2006

Applicant Cue Sheet Initial Conditions:

e The plant is operating at 100% power.

0 Containment purge is in progress e Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic e WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.

e While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.

e After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.

e Drywell pressure stabilizes below the scram setpoint e Actions to comply with Tech Specs as a result of the leakage are initiated and N 1-0P-43C, Plant Shutdown is being implemented.

e Reactor power is now at 50%.

e Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited.

e After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams 0 All rods fully insert 0 Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 psig e Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches.

e Plant conditions are stabilized and a normal cool down occurs.

Initiating cue:

(Operators name), identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category.

NRC SRO ADMlN JPM 1 5 October 2006

Attachment 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Time Limit Reason (Event) Category Reauirernent Amlies 50.72 (b)(3)(iv)(B)(2). NOT Containment Purge Isolation General containment REPORTABLE during maintenance activity. Also, isolation signals. only affects one system.

50.72(a)(l)(i) and (a)(3). Within 15 minutes Declaration of UE 2.1 .I Declaration of an of declaration, Emergency Class immediately after notifying state and local agencies and not later than one hour after the time of declaration 50.72(b)(2)(i). Initiation of a Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if Initiation of a plant shutdown plant shutdown required by not previously required by Tech Specs Tech Specs reported. 3.2.5.a.1. Unidentified leakage is above 5 gpm.

50.72( b)(2)(iv)(B). Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if Automatic reactor trip when the Actuation of RPS when the not previously reactor is critical.

reactor is critical. reported.

50.72( b)(3)(iv)(B)(5). Event Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if Manual initiation of Emergency or condition results in valid not previously Condensers to control pressure.

actuation of BWR isolation reported. Intentional manual actions are condenser system and valid initiations. Also, the HPCl feedwater coolant injection. mode (feedwater coolant injection) is actuated.

NRC SRO ADMIN JPM 1 6 October 2006

Attachment 2 JPM Scorecard For Applicant Use dentify the applicable verbal reportability requirements, the reason that

hey apply and the associated time limitations for reporting under that
at ego ry ReportabiIity Time Limit qeason (Event) Category Reauirement 4pplies NRC SRO ADMIN JPM 1 7 October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Review Reactivity Maneuver Request and Classify Reactivity Events Revision: NRC 2006 Task Number: NA Approvals:

NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Perfor m er : (SW Trainer/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC SRO ADMIN JPM 2 1 October 2006

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated area.

Simulator Set-up:

NIA Directions to the Instructor/Evaluator:

Applicant is to be provided with 3D Monicore printout data and RMR for review and approval. A 5 Loop Power to Flow Map is also required.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. GAP-OPS-05 Tools and Equipment:
1. None Task Standard:

Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map.

Applicant does not approve the RMR. Identifies and initiates actions for Reactivity Events.

NRC SRO ADMIN JPM 2 2 October 2006

Initial Conditions:

PART 1 The plant is operating at rated power.

0 An intended plant maneuver to raise rod line is being planned.

A Reactivity Maneuver request is provided for review.

Initiating cue:

PART 1 (Operators name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.

PART 2 (After actions are complete for RMR)

The following events occur:

Loud abnormal noises are reported from the Main Turbine.

Power is rapidly reduced to 75% with Recirc Flow.

After power is reduced to 75% the Main Turbine automatically trips.

EOPs are entered and implemented.

ERVs actuate.

Turbine Bypass Valves were observed to remain closed throughout the transient.

Control Rod 18-19 is at position 04.

All other control rods are at position 02.

PART 2 (Operators name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided.

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
02. Obtain a copy of the any of the 0 Reference materials obtained.

reference documents.

PART 1

03. Reviews RMR and supporting 3D 0 Determines predicted results cause PasslFail Monicore predictor case. operation outside ELLLA Operating Limit (PFR Line) of Power Flow Map. (PFR is > 1.O)

PasslFail Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. (PFR is > 1 .O)

NRC SRO ADMIN JPM 2 3 October 2006

Grade PART 2

04. Refer to GAP-OPS-05 section 0 Identifies the emergency power PasslFail 3.13 to classify reactivity event reduction OR unplanned scram as severity levels. Severity Level 4 (4-1 Rapid Downpower 10.5% RTP or shutdown due to emergent issues)

OR 4-9 Unplanned Reactor Scram While Critical.

May also identify other SL-4 Sat/Unsat events, such as 4-1 1, with rods at 02 and 04, following the scram.

Identifies the Main Turbine Trip with PasslFail Bypass Valve failure to operate as Severity Level 2 (2-1 Main Turbine Trip With Bypass System failure).

NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram.

All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram.

u Identifies CR (DER) is required for Sat/Unsat severity level 1,2,3 and 4 events.

13. Report completion. u Reports completion. Sat/Unsat TERMINATING CUE: Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR. Identifies and initiates actions for Reactivity Events.

RECORD STOP TIME NRC SRO ADMIN JPM 2 4 October 2006

Applicant Cue Sheet Initial Conditions PART 1 The plant is operating at rated power.

An intended plant maneuver to raise rod line is being planned.

A Reactivity Maneuver request is provided for review.

Initiating cue:

PART 1 (Operators name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.

PART 2 (After actions are complete for RMR)

The following events occur:

Loud abnormal noises are reported from the Main Turbine.

Power is rapidly reduced to 75% with Recirc Flow.

After power is reduced to 75% the Main Turbine automatically trips.

EOPs are entered and implemented.

ERVs actuate.

Turbine Bypass Valves were observed to remain closed throughout the transient .

Control Rod 18-19 is at position 04.

All other control rods are at position 02.

PART 2 (Operators name), based on the plant events that occur identify any internal classification and administrative actions related to the events.

Document findings and conclusions on scorecard provided.

NRC SRO ADMIN JPM 2 5 October 2006

Attachment 1 JPM Scorecard KEY Document any findings and conclusions for PART 1 and PART 2 events.

ACTIONS Explanation Determines predicted results 100% power and 83.9% core flow cause operation outside (112.3% rod line) results in ELLLA Operating Limit (PFR operation above ELLLA. (PFR >I .O)

Line > 1.O) of Power Flow Map.

GAP-OPS-05 Attachment 1 Item 2 Does NOT approve the RMR evaluates the RMR for maintaining based on failure to maintain operation within allowable regions of plant operation within the power to flow map. Since this allowable regions of the power maneuver does not accomplish this, to flow map. the RMR should not be approved.

GAP-OPS-05 section 3.13 SL 4.

Identifies the emergency Example 4-1 Rapid Downpower 2 power reduction or unplanned 0.5% RTP or shutdown due to scram as Severity Level 4. emergent issues OR 4-9 Unplanned Reactor Scram While Critical.

GAP-OPS-05 section 3.13 Example Identifies the Main Turbine 2-1 Main Turbine Trip With Bypass Trip with Bypass Valve failure System failure.

to operate as Severity Level 2 NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram. All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram.

Identifies CR (DER) is required GAP-OP-05 section 3.13.2 for severity level 1,2,3 and 4 events.

NRC SRO ADMIN JPM 2 6 October 2006

Attachment 2 JPM Scorecard For Applicant Use 3ocument any findings and conclusions for PART 1 and PART 2 events.

4ct ions Exdanation NRC SRO ADMIN JPM 2 7 October 2006

10. Determine Adjusted LHGR limit 0 Determines adjusted value to be PasslFail value for step 9.2.10, with 0.860, from COLR Section 3.1 and pressure regulator out of service Figure 3, as follows:

and thermal power between 45%

and 90% from the COLR. For 70% 5 P < 90% MFLPD Limit =

FRTP

= 1591/1850 = 0.8600 0 Enters 0.860 as Adjusted LHGR Sat/Unsat limit value for step 9.2.10.

11. Determine Actual MFLPD Value Determines actual MFLPD value to PasslFail from 3D Monicore printout. be 0.735, from printout.

Enters 0.735 as Actual Sat/Unsat MFLPDValue for step 9.2.10

12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met. less than adjusted limit and that the MFLPD thermal limit is met.

0 Records MFLPD and location in step SatlUnsat 9.2.1 1 as 0.735 and 41-38.

Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout.

0 Records step 9.2.13 as NA, since Sat/Unsat FPAPDR is < 1.O.

13. Report completion. Reports completion. Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.

RECORD STOP TIME NRC SRO ADMIN JPM 3 5 October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Thermal Limits with Inoperable Pressure Regulator Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY Da General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Trai ner/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 25 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC SRO ADMIN JPM 3 1 October 2006

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated area.

Simulator Set-up:

N/A Directions to the Instructor/Evaluator:

Applicant is to be provided with NI-RESP-1 for recording data. Applicant must have access to Core Operating Limits Report, Tech Specs, 3D Monicore printout data and N1-OP-31 Directions to Operators:

Read Before Everv JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1, Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".

2. During Evaluated JPM:

0 Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. Core Operating Limits Report (COLR)
2. N1-RESP-1 Daily Thermal Limit Surveillance
3. Tech Spec 3.1.7
4. N1-OP-31, H.5.0 and H.3.0 Tools and Equipment:

1 . None Task Standard NRC SRO ADMIN JPM 3 2 October 2006

limit is exceeded and Tech-Spec 3.1.7 actions required.lnitial Conditions:

The plant is operating at power Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue:

(Operators name), using the 3D Monicore printout provided complete N1-RESP-1, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13.

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing corr&tion if necessary RECORD START TIME
  • 2 . Obtain a copy of the any of the 0 Reference materials obtained.

reference documents.

03. Candidate may reference N 1-0P- 0 Refers to N1-OP-31, H.3.0 for Sat/Unsat/NA 31, H.3.0. direction for operation with one pressure regulator inoperable.

I Refer to Core Operating Limits Sat/Unsat Report for applicable MFLPD and MFLCPR thermal limit restrictions.

IF unable to meet COLR thermal limit restrictions, THEN perform the following:

Enter applicable Tech Spec PasslFail (3.1.7)

Notify Reactor Engineering to PasslFail obtain direction to achieve compliance with applicable thermal limit restrictions.

4. Record data in N1-RESP-1 by 0 Records Core Thermal Power in Sat/Unsat obtaining information from 3D step 9.2.2 as 1591 MWth and Monicore printout. 86.0%.

Records Total Core Flow in step SatlUnsat 9.2.3 as 48.023 Mlbm/hr and 71 .I  %

Records step 9.2.4 as NA, since all Sat/Unsat RRPs are operating.

NRC SRO ADMIN JPM 3 3 October 2006

0 Records MAPRAT and location in Sat/Unsat step 9.2.5 as 0.775 and 41-38 0 Records step 9.2.6 as NA, since all RRPs are operating.

5. Determine Adjusted MCPR limit Determines adjusted value to be PasslFail value for step 9.2.6.1, with 1.809, from COLR Section 2.1 and pressure regulator out of service Figure 2b, as follows:

and thermal power between 45%

and 90% from the COLR. For 70% 5 P < 90% MCPR Limit =

(Rated 0LMC PR)/FRTP Rated OLMCPR= MCPRlim*Kf

= 1.53*1.017 = 1.556

= 1.5561.860 = 1.809 SaVUnsat 0 Enters 1.809 as Adjusted MCPR limit value for step 9.2.6.1

6. Determine Actual MCPR Value 0 Determines actual MCPR value to be PasslFail from 3D Monicore printout. 1.753, from printout.

0 Enters 1.753 as Actual MCPR Sat/Unsat Value for step 9.2.6.1

7. Determines COLR thermal limit Evaluates actual MCPR value to be PasslFail restriction for MCPR is not met. less than adjusted limit and that the MCPR thermal limit is NOT met.
8. Enter Tech Spec 3.1.7.c 0 Recognize entry into Tech Spec PasslFail 3.1.7 specification c.

0 Identifies action shall be initiated PasslFail within 15 minutes to restore operation to the prescribed limit. If all operating MCPRs are not returned within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit.

0 Notifies Reactor Engineering to PasslFail obtain direction to achieve compliance with applicable limits.

(OP-31 H.3.2.2)

9. Record data in N1-RESP-I by 0 Records MFLCPR and location in SatlUnsat obtaining information from 3D step 9.2.7 as 1.032 and 29-14.

Monicore printout.

0 Records step 9.2.8 as NA, since all RRPs are operating.

Records Power to Flow Ratio (PFR) Sat/Unsat step 9.2.9 as 0.933.

NRC SRO ADMIN JPM 3 4 October 2006

Grade

10. Determine Adjusted LHGR limit Determines adjusted value to be PasslFail value for step 9.2.10, with 0.860, from COLR Section 3.1 and pressure regulator out of service Figure 3, as follows:

and thermal power between 45%

and 90% from the COLR. For 70% 5 P < 90% MFLPD Limit =

FRTP

= 1591/1850 = 0.8600 Enters 0.860 as Adjusted LHGR Sat/Unsat limit value for step 9.2.10.

11. Determine Actual MFLPD Value Determines actual MFLPD value to PasslFail from 3D Monicore printout. be 0.735, from printout.

Enters 0.735 as Actual MFLPD Sat/Unsat Valuefor step 9.2.10

12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met. less than adjusted limit and that the MFLPD thermal limit is met.

Records MFLPD and location in step SatlUnsat 9.2.1 1 as 0.735 and 41-38.

Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout.

Records step 9.2.13 as NA, since Sat/Unsat FPAPDR is < 1.0.

13. Report completion. Reports completion. Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.

RECORD STOP TIME NRC SRO ADMlN JPM 3 5 October 2006

Applicant Cue Sheet Initial Conditions:

The plant is opera ing a : power 0 Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue:

(Operators name), using the 3D Monicore printout provided complete N1-RESP-1 , Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13.

NRC SRO ADMIN JPM 3 6 October 2006

c.

H. OFF-NORMAL PROCEDURE (Cont) 3.0 Operation With One Pressure Requlator Inoperable 3.1 IF operating without a backup pressure regulator, see the Core Operating Limits Report (COLR) section for operation without a backup pressure regulator for applicable MFLPD and MFLCPR thermal limit restrictions............................................. (-1

t 3.2 IF unable to meet the COLR thermal limit restrictions, THEN perform the following:

3.2.1 Enter applicable Tech Spec LCO for Fuel Rod Thermal Limits..........................

3.2.2 Notify Reactor Engineering to obtain direction to achieve compliance with the applicable thermal limit restrictions .............................................................. (-)

4.0 This Section Deleted.

Page 66 N1-0P-31 Rev 21

PAGE 1 CORE PARAMETERS 3DM/P11 20-OCT-2006 1 3 : 3 9 CALCULATED PREDICTOR LOG 20-OCT-2006 1 3 : 4 0 PRINTED POWER MWT CASE ID F T F F 1 0 6 1 0 2 0 1 3 3 9 4 7 FLOW MLB/HR RESTART FMLD1061020084721 FPAPDR FIT - FULL CORE SUBC BTU/LB 1.0034 PR PSIa XE WORTH % - 2 . 3 3 LOAD LINE

SUMMARY

CORE MWD/sT 1012.63 26190.6 XE/RATED 1.01 CORE POWER 8 6 . Os Q AVE VF CYCLE MWD/sT MCPR T STEP HOURS ff:":;: PFR @

0.371 0.933 CORE FLOW LOAD LINE 71.1%@

107.5%

0-7 K f Z CORRECTION FACTORS: MFLCPR= 1 . 0 1 7 MFLPD= 1.000 MAPRAT= 1.000 OPTION: PRE-ARTS 5 LOOPS ON MANUAL FLOW MCPRLIM= 1 . 5 3 0 MOST LIMITING LOCATIONS (NON-SYMMETRIC)

LOC MFLPD LOC PCRAT LOC 0.887 4 9-14 0 . 7 3 5 @1 4 y;E@41%- 4 0.862 37 7

F:11bl-12 0.732 37 4 0.772 37 5 0.859 23 5 0.879 33-14 0.726 39 4 0.772 37 4 0.859 29 7 0.878 31-16 0.723 35 4 0.764 39 4 0.859 43 9 0.868 27-18 0.723 37 4 0.760 33 5 0.859 43-24-11 0.868 39-24 0.722 41 9 0.756 33 5 0.857 37 5 0.863 41-22 0.721 27 9 0.755 35 4 0.857 33 5 0.863 39-20 0.720 33 4 0.751 43 5 0.856 41 7 0.862 37-22 0.716 43 9 0.751 27 8 0.856 29 5 0.861 35-26 0.715 33 4 0.750 43 5 0.855 33 7 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL 51 NOTCH REL PW LOC L 00 0.154 24 47 02 0.276 23 04 0.574 22 43 36 06 0.737 21 L P 08 0.840 20 39 10 0.928 19
  • 12 0.976 18 35 08 06 14 0.982 17 L 16 1.107 16 31 18 1.160 15 20 1.178 14 27 00 00 00 36 22 1.217 13 L 24 1.253 12 23 26 1.262 11 28 1.255 10 19 06 08 30 1.285 09 L 32 1.293 08 15 34 1.271 07 C 36 1.292 06 11 36 38 1.304 05 L 40 1.272 04 07 42 1.171 03 44 0.928 02 03 46 0.285 01 L L L L L L 02 06 10 14 18 22 26 30 34 38 42 46 50

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Actions for Service Water Radiation Monitor Low Flow Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY General Supervisor Date Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)

TrainedEvaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: Date:

NRC SRO ADMIN JPM 4 1 October 2006

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated area.

Simulator Set-up:

N/A Directions to the InstructorlEvaiuator:

None Directions to Operators:

Read Before Everv JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

0 Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. ARP H I ; HI-4-5.
2. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. 16.
3. DER NM-2003-5168, ODCM Entry Due to SW RM Low Flow.
4. DER NM-2004-976, Unplanned LCO - SW RM Low Flow.
5. K/A 2.3.1 1 (3.2) Ability to control radiation releases.
6. 2.4.45 (3.6) Ability to prioritize and interpret the significance of each annunciator or alarm.

Tools and Equipment:

1. None Task Standard: Determine actions per ARP HI-4-5 and ODCM in response to service water radiation monitor low flow condition.

NRC SRO ADMIN JPM 4 2 October 2006

Initial Conditions:

1. The plant is operating at 100°/~power.
2. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.
3. HI-4-5, LQ PROCESS RAD MON, has alarmed.
4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
5. Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.
6. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).

7 . Sample flow cannot be adjusted.

8 . Ask the operator for any questions.

Initiating cue:

(Operators name), determine the appropriate actions in response to these conditions.

1. Provide repeat back of initiating Proper communications used for Sat/Unsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
1. .Obtain a copy of the reference ARP HI-4-5 obtained. SatlUnsat procedure and reviewlutilize the Operator Actions referenced.

correct section.

ODCM obtained.

DLCO 3.6.14 referenced.

TBL D3.6.14-1 referenced.

2. .Per ARP H I 5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then:
a. *Notify Radiation Protection Notifies Radiation Protection Sat/Unsat Instrument Support for repair. Instrument Support to initiate repairs.

b..lnitiate LCO sampling Directs Chemistry to perform DLCO PasslFail (Chem istry). sampling per TBL D 3.6.14-1 InstrumentlB action (d); twelve (12) hour grab samples to be collected/analyzed for SW effluent.

3. .Reference ODCM and takes Determines SW Radiation Monitor is PasslFail appropriate actions. inoperable.

References ODCM DLCO 3.6.14.a SatlUnsat and TABLE D 3.6.14-1 Instrument 1B and note (d) applies.

Determines less than the minimum number of radioactive liquid effluent PasslFail monitoring channels for service water effluent and takes action NRC SRO ADMIN JPM 4 3 October 2006

shown in TBL D 3.6.14-1.

Determines action (d) applies. PasslFail Effluent releases via this pathway can continue provided that at least once per twelve (12) hours grab samples are collected and analyzed SW effluent.

Initiates CR for unplanned LCO Sat/Unsat entry.

End of JPM TERMINATING CUE: SW Radiation Monitor flow adjusted and restored to operable status.

RECORD STOP TIME NRC SRO ADMIN JPM 4 4 October 2006

Initial Conditions:

1. The plant is operating at 100% power.
2. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.
3. HI-4-5, LQ PROCESS RAD MON, has alarmed.
4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
5. Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.
6. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).
7. Sample flow cannot be adjusted.
8. Ask the operator for any questions.

Initiating cue:

(Operators name), determine the appropriate actions in response to these conditions .

NRC SRO ADMIN JPM 4 5 October 2006

Attachment 1 JPM Scorecard KEY 1 Determine the appropriate actions in response to these conditions.

I Action Required By (Document)

Direct Chemistry to initiate ARP H 1-4-5 required LCO sampling Determines SW Radiation Monitor is inoperable.

Determines less than the ODCM DLCO 3.6.14 TABLE D minimum number of 3.6.14-1.

radioactive liquid effluent monitoring channels for service water effluent and takes action shown in TBL D 3.6.14-1.

Determines action identified in note (d) applies. Effluent ODCM DLCO 3.6.14 TABLE releases via this pathway NOTE (d) can continue provided that at least once per twelve (1 2) hours grab samples are collected and analyzed SW effluent.

NRC SRO ADMIN JPM 4 6 October 2006

I Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.

Action qequired By (Document)

NRC SRO ADMlN JPM 4 7 October 2006

CONSTELLATION ENERGY GROUP OPERATOR JOB PERFORMANCE MEASURE Title: Emergency Classification With PARS Revision: NRC 2006 Task Number: N/A V4-z&k3&

Genejal Supervisor / Date ' I NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: PRO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: YES Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail

-

NOTE: A JPM overall rating of fail shall be given if critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature: Date:

SRO ADMIN JPM 5 October 2006

Recommended Start Location: (Completion time based on the start location)

Any appropriate location with proper references.

Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM,CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a

".".

2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

0 Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations
2. EPIP-EPP-20, Emergency Notifications
3. EAL Matrix SRO ADMIN JPM 5 October 2006

Tools and Equipment:

1. EAL Matrix Task Standard:

Given a set of plant conditions, classify the emergency (within 15 min.), and complete the Part 1 Notification Fact sheet including PARS (within 15 min.)

Initial Conditions:

1. The plant is under accident conditions.
2. A Site Area Emergency has been declared based on plant conditions.
3. The Chemistry Technician has reported the following release data:

Dose assessment for ground level release rate is 58 Curies per second (Ci/second) 0 Dose assessment for elevated level release rate is 502 Cilsecond 0 Wind speed is 8 mph 0 Wind direction is from the East South East (150)

Pascal Stability Class is E Initiating Cues :

(Operators name), Take the required actions as the Emergency Director.

Performance Steps Standard Grade Evaluator Note: Inform the Candidate that this is a Time-Critical task

1. Provide repeat back of initiating cue. Proper communications used for repeat Sat/Unsat Evaluator Acknowledge repeat back back (GAP-OPS-Ol/Operations Manual) providing correction if necessary.

RECORD TASK 1 CRITICAL START TIME

2. Obtain a copy of the reference procedure The candidate may reference anylall of SaVUnsat and reviewhtilize the correct section of the the following:

procedure. EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1 EPIP-EPP-18 EPIP-EPP-20 Att. 1A

3. Using given plant data and EPIP-EPP-08 General Emergency is declared, within 15 PasslFail Attachment 1 Table 1 .Iand Table 1.2, minutes of recorded start time for Task 1.

determine that a General Emergency exists based upon calculated total release (ground release + elevated release).

RECORD TASK 1 CRITICAL STOP/ TASK 2 CRITICAL START TIME

4. Review meteorological data and EPIP- PARS made and indicated on Part I PasslFail EPP-08 and/or EPIP-EPP-20 to determine Notification Fact Sheet to evacuate ERPAs 1, 2, 3, 26, and 27 and shelter all SRO ADMIN JPM 5 October 2006

PARs. remaining ERPAs, within 15 minutes of recorded start time for Task 2.

RECORD TASK 2 CRITICAL STOP TIME Terminating Cue: The event is classified as a General Emergency and PARs are made.

RECORD STOP TIME SRO ADMIN JPM 5 October 2006

Initial Conditions:

1. The plant is under accident conditions.
2. A Site Area Emergency has been declared based on plant conditions.
3. The Chemistry Technician has reported the following release data:

Dose assessment for ground level release rate is 58 Curies per second (Cilsecond)

Dose assessment for elevated level release rate is 502 Cilsecond.

Wind speed is 8 mph Wind direction is from the East South East (150)

Pascal Stability Class is E Initiating Cues:

(Operators name), Take the required actions as the Emergency Director.

SRO ADMIN JPM 5 October 2006

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