ML110620274

Draft Operating Exam (Sections B and C) (Folder 2)

ML110620274
Person / Time
Site:	Peach Bottom
Issue date:	01/09/2011
From:	NRC Region 1
To:
Hansell S
Shared Package
ML102220201	List: IR 05000277/2011301 ML102880050 ML102880462 ML110210429 ML110620164 ML110620239 ML110620274 ML110630047 ML110630064 ML110630070 ML110630120 ML111580037 ML111661880
References
TAC U01769
Download: ML110620274 (289)

Text

EXELON NUCLEAR Nuclear Generation Group OJTfTPE MATERIAL COVERSHEET ach Bottom imerick II Common ~

~ JPM D QUALIFICATION MANUAL D OJT MODULE LICENSED OPERATOR TRAINING PLOR-241C LICENSED OPERATOR REQUALIFICATION 001 F. J. Bruns jav MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE ALTERNATE PATH (Failed Temperature Points)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _ _-' _ _ - - - - J _ __

I\lAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 10 NO. COMPLETION DATE:

COMIVIENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR241C Rev001.doc Page 1 of 4

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2880130201 / PLOR-241 C KIA: G2.1.45 URO: 4.3 SRO: 4.3 TASK DESCRIPTION: MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE - ALTERNATE PATH (Failed Temperature Points)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR241 C Rev001.doc Page 2 of 4

B. TOOLS AND EQUIPMENT

1. RT-0-40C-530-2, "Drywell Temperature Monitoring"

2. RT-0-40C-530-2, Data Sheet 1 with temperature values filled in with pOints 137 and 139 indicated as out of service and point 136 reading 132°F (AT2)

C. REFERENCES

1. RT-0-40C-530-2, Rev. 6, "Drywell Temperature Monitoring" D. TASK STANDARD

1. Satisfactory task completion is indicated when the operator has determined that Drywell Temperature requires entry into ON-120, High Drywell Temperature.

2. Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to Monitor Drywell Temperatures using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is experiencing a small steam leak into primary containment.

2. TI-80146, the drywell bulk average temperature indication, has failed.

3. Another operator has completed taking the temperatures required for Data Sheet 1 of RT-0-40C-530-2, "Drywell Temperature Monitoring".

G. INITIATING CUE The Control Room Supervisor directs you to penform RT-0-40C-530-2, "Drywell Temperature Monitoring", beginning with step 6.2.1 up through and including step 6.2.3, and report any required actions by documenting your results on the cue sheet in the space provided.

PLOR241C Rev001.doc Page 3 of 4

H. PERFORMANCE CHECKLIST q STEP NO STEP ACT STANDARD

• 1 Review Data Sheet 1 and recognize that P Recognize that the calculation of Bulk all of the temperature points in Zone Average temperature is INVALID. Place Number 4 are out of service (Step 6.2.1). an NIA in step 6.2.1.

2 Record the instrument used on the blank P Record "TI-2501, Point 136" in the provided in step 6.2.2.1. "Instrument Used" blank provided in step 6.2.2.1, then initial the step in the SAT column.

• 3 Record the value of TI-2501, Point 136 in P Record "132" in the blanks provided the provided blanks in steps 6.2.2.1 and before the first "oF" in steps 6.2.2.1 and 6.2.2.2. 6.2.2.2.

• 4 Calculate approximate Drywell Bulk P Calculate 132°F + 10°F = 142°F. Record Average Temperature as indicated in step "142" in the blank provided in step 6.2.2.2. 6.2.2.2, then initial the step in the SAT column.

• 5 Complete verification of Drywell Bulk P Initial the UNSAT Black Box beside Step Average Temperature less than 140°F. 6.2.3.

• 6 Report ON-120 "High Drywell P Report to the CRS that ON-120 should be Temperature" entry condition. entered due to Approximate Drywell Bulk Average Temperature greater than 140°F.

7 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the candidate informs the Control Room Supervisor of the ON-120, "High Drywell Temperature", entry condition, the evaluator will then terminate the exercise.

PLOR241C Rev001.doc Page 4 of4

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is experiencing a small steam leak into primary containment.

2. TI-80146, the drywell bulk average temperature indication, has failed.

3. Another operator has completed taking the temperatures required for Data Sheet 1 of RT-0 40C-530-2, "Drywell Temperature Monitoring".

INITIATING CUE The Control Room Supervisor directs you to perform RT 40C-530-2, "Drywell Temperature Monitoring",

beginning with step 6.2.1 up through and including step 6.2.3, and report any required actions by documenting your results on the cue sheet in the space provided.

RESULTS:

Exelon Nuclear RT-O-40C-530-2 Peach Bottom Rev. 6 unit 2 Page 1 of 11 Routine Test JWL: jwl RT-O-40C-530-2 DRYWELL TEMPERATURE MONITORING TEST FREQUENCY: Once/31 days (See Section 1.0) 1 CHECK why this procedure is being performed:

D Schedule D OVF D Retest Due To Unsat Test

~ Other Reason, !faifun of'11-80146 Approved By SMgt: C.$ Suvervisor Tolay C.!RS I Prrnted Name Time Date InTtials I INITIAL one of the following Test Results:

A: All R steps are SATISFACTORY B: One or More R steps are UNSATISFACTORY Refer to Section 9.0 for Corrective Action I I Performed By: I I Printed Name Time Date Initials RO/PRO Informed of Test Results: / I SMgt Informed of Test Results: / I UNSAT Notification:

SMgt Discretion: Plant Mgr or Others Notified By: / /

3 IF other portions of the test did NOT function properly, OR other discrepancies were noted THEN COMPLETE the following:

DESCRIBE discrepancies/actions taken: AR/ ETT No. 999999999 Pts 137, 139 aTe Out ojSeT1Jice, (ooS)

Reviewed/Approved Plant Staff: / /

Printed Name Time Date Initials D/W Chilled Water System Manager / /

RT-O-40C-530-2 Rev. 6 Page 2 of 11 1.0 PURPOSE This test checks the Drywell airspace for satisfactory operating temperature conditions as described in the PBAPS UFSAR, Sections 5.2.3.2 and 5.2.3.7. This procedure is performed once per day when Primary Containment is required IF TI-80146 "Drywell Bulk Average Temp Indicator" is out of service, and may be used in conjunction with ON-120 "High Drywell Temperature", T-223, "Drywell Cooler Fan Bypass", T-102 "Primary Containment Control",

and SAMP-2 "Containment and Radioactivity Release Control". This procedure also records Drywell Chiller performance data.

2.0 TEST EQUIPMENT None 3.0 PREREQUISITES 3.1 Test Initiation Initial 3.1.1 COMPLETE Section 1 of cover page. C.!RS 3.2 Document Review 3.2.1 ENSURE procedure is current revision. C.!RS 3.3 Equipment Configuration None 3.4 Required Redundant Safety Related Equipment None 3.5 Approval to Start Test 3.5.1 OBTAIN RO Permission to begin. 2if!!!l TotfaJJ  !/(O.

Time Date RO 4.0 PRECAUTIONS, LIMITATIONS, AND GENERAL INSTRUCTIONS 4.1 Plant Impact Statement 4.1.1 This test does not impact plant availability in any manner. This test may be performed in any Reactor Mode.

RT-O-40C-530-2 Rev. 6 Page 3 of 11 4.2 Precautions 4.2.1 IF all temperature points in a zone on TR-2501 or corresponding PMS computer points are out of service, THEN calculation of Drywell Bulk Average Temperature in Step 6.2.1 is INVALID.

4.2.2 IF calculation of Drywell Bulk Average Temperature is INVALID, THEN:

1. FOR ENTRY INTO ON-120 OR T-l02 (Step 6.2.2):

Use TI-2501 point 136 OR PR/TR-4805 to calculate APPROXIMATE Drywell Bulk Average Temperature.

2. TO DETERMINE WHEN TO INITIATE RPV BLOWDOWN:

Use hottest temperature of TI-2501 points 119 through 127 (excluding pt 125). IF TI 2501 is NOT available, THEN use PR/TR-4805. The hottest temperature on TI-2501 (or PR/TR-4805) is used in conjunction with T-I02, "Primary Containment Control" direction to determine when RPV blowdown is required.

3. DO NOT SPRAY THE DRYWELL:

Without an accurate Drywell Bulk Average Temperature calculation OR Engineering evaluation verifying that plant conditions are on the safe side of Drywell Spray Initiation Limit Curve.

4. TO DETERMINE IF DWCW CAN BE RESTORED TO THE DRYWELL COOLER FAN UNITS PER T-223:

IF Drywell Bulk Average Temperature CANNOT be determined, THEN obtain Engineering evaluation prior to placing Drywell Cooler Fans in service.

4.3 Limitations None 4.4 General Instructions 4.4.1 IF TI-80146 "Drywell Bulk Average Temp Indicator" is INOPERABLE, THEN Drywell temperature calculated in Step 6.2 determines entry conditions and/or action levels for ON-120 "High Drywell Temperature", T-I02 "Primary Containment Control" and SAMP-2 "Containment and Radioactivity Release Control".

4.4.2 IF any procedure step can NOT be completed OR produces an unexpected response, THEN stop the test AND return the equipment to a safe condition AND noti fy the RO or SMgl:.

RT-O-40C-530-2 Rev. 6 Page 4 of 11 4.4.3 IF any Black Box is initialed, THEN IMMEDIATELY return the equipment to a safe condition, notify Shift Management, and refer to Section 9, Corrective Actions.

4.4.4 IF procedure is aborted, THEN notify SMgt AND write "TEST ABORTED" in Section 3 of Cover Page.

4.4.5 All persons who initial steps in Sections 3.0, 6.0, or 7.0 are responsible for completing Section 10.0.

4.4.6 All applicable R steps are identified immediately in front of the initials.

5.0 ACCEPTANCE CRITERIA Calculated Drywell Bulk Average Temperature is less than 140°F.

6.0 PERFORMANCE STEPS Initial Sat UnSat NOTE IF this procedure is being performed in accordance with ON-120 "High Drywell Temperature", T-223, "Drywell Cooler Fan Bypass", T-102 "Primary Containment Control" or SAMP-2 "Containment and Radioactivity Release Control", THEN only Sections 6.1 and 6.2 must be performed.

6.1 Drywell Temperature Data Acquisition

< At Control Room Panel 20C012 >

NOTE IF the "log" function is available on TI-2501 "Drywell Temperature Indicator",

THEN required temperature points may be obtained by pressing "CLEAR, LOG, POINT, 119-166, RUN" to receive a printout of temperature points.

6 .1.1 RECORD required Dryw_ell temperature points from TI-2501 "Drywell Temperature Indicator" or points obtained from PMS computer on Data Sheet 1. !R,o.

RT-O-40C-530-2 Rev. 6 Page 5 of 11 6.2 Drywell Temperature Calculations NOTE IF all temperature points in a given zone on TI-2501 are out of service, THEN Drywell Bulk Average Temperature calculation on Data Sheet 1 will be INVALID AND EITHER TI-2501 Point 136 OR PR/TR-4805 must be used to calculate APPROXIMATE Drywell Bulk Average Temperature for entry into ON-120 and T-102. Refer to Precaution Step 4.2.2 for limitations on T-223, T-102 or SAMP-2 actions with Invalid Drywell Bulk Average Temperature.

6.2.1 IF TI 2501 or corresponding PMS computer points have at least 1 valid temperature point in each of Zones 1 through 5, THEN CALCULATE Drywell Bulk Average Temperature using calculation on Data Sheet 1. OTHERWISE, NIA this step.

6.2.2 IF TI-2501 or corresponding PMS computer points does NOT have at least 1 valid temperature point in each of Zones 1 through 5, ~~ CALCULATE APPROXIMATE Drywell Bulk Average Temperature as follows. OTHERWISE, RIA this step:

1. RECORD temperature reading from EITHER TI-2501 Point 136 OR PR/TR-4805 "Containment Temp" at Panel 20C003-02.

Instrument Used

2. ADD 10°F to temperature recorded in substep 1 above to determine APPROXIMATE Drywell Bulk Average Temperature.

6.2.3 VERIFY Drywell Bulk .Average Temperature is less than 140°F. R-CJ

RT-O-40C-530-2 Rev. 6 Page 6 of 11 6.3 Drywe1l Chiller Data Acquisition 6.3.1 RECORD Drywell Chiller data on Data Sheet 2 "DRYWELL CHILLER DATA".

7.0 PROCEDURE COMPLETXON 7.1 Independent Verification None 7.2 Records Completion Initial 7.2.1 COMPLETE Section 2 of Cover Page (and Section 3 if applicable) .

8.0 REFERENCES

8.1 Interfacing 8.1.1 ON-120, "High Drywell Temperature" 8.1. 2 T-223, "Drywell Cooler Fan Bypass" 8.1. 3 T-102, "Primary Containment Control" 8.1. 4 SAMP-2, "Containment and Radioactivity Release Control" 8.1. 5 ST-O-098-01N-2 8.2 Developmental 8.2.1 Prints M-327, Chilled Water System - Drywell Cooling M-382, Drywell Temperature Control Diagram M-390, Drywell Ventilation Flow Diagram 8.2.2 PBAPS UFSAR, Section 5.2.3.2 8.2.3 PBAPS UFSAR, Section 5.2.3.7 8.2.4 EWR P-50870, Drywell Average Air Temperature Limit 8.2.5 EWR P-50717, Drywell Bulk Average Air Temperature 8.2.6 Calculation ME-457, Calculation Method to Determine the Drywell Average Space Temperature 8.2.7 ON-120 Bases, High Drywell Temperature - Bases

RT-O-40C-530-2 Rev. 6 Page 7 of 11 8.2.8 T-102 Bases, Primary Containment Control-Bases 8.2.9 SAMP-2 Bases, Containment and Radioactivity Release-Bases 8.2.10 TRIP Curves, Tables, & Limits-Bases 8.2.11 Generic Letter (GL) 96-06, "Assurance of Equipment Operability and Containment Integrity during Design-Bases Accident Conditions" 9.0 CORRECTIVE ACTIONS 9.1 IF calculated Drywell Bulk Average Temperature is greater than 140°F BUT less than or equal to 145°F, THEN INITIATE corrective action to restore Drywell Bulk Average Temperature to below 140°F in accordance with ON-120 "High Drywell Temperature".

9.2 IF calculated Drywell Bulk l\verage Temperature is greater than 145°F, THEN ENTER T-102 "Primary Containment Control".

10.0 PARTICIPANTS RECORD Printed Name Initials

!Rtactor Operator  !.to. i i

RT-O-40C-530-2 Rev. 6 Page 8 of 11 DATA SHEET 1 Date _1_1_

DRYWELL TEMPERATURE CALCULAT:IONS Time PMS ZONE T:I-2501 TEMP SUM D:IV:IDE BY MtlLT:IPLY EQUALS Computer NO. PO:INT DEG VAL:ID NO. OF BY TEMP (See NO. of PTS. VAL:ID PTS. VOLUME FRACT:ION Point Note 1) FRACT:ION ID R020 119 160°F R021 120 175°F of of of R022 R023 1 121 122 192°F 210(5F - -= X .10 R024 123 187°F R025 124 205(5F R027 126 150°F R028 2 127 146°F of of X .26 of M027 135 120°F of of of H010 or H011 3 136 132°F

- -= X .57 R031 137 OOSoF R032 138 120°F

)F of of R033 4 139 OOSoF

- -= X .05 R034 163 231°F R035 5 164 230°F of  ::: of X .02 of R036 165 235°F R037 166 232°F SUM OF TEMPERATURE FRACT:IONS =

CALCULATED DRYWELL BULK AVERAGE TEMPERATURE OF Note 1: IF all temperature points in a zone are out of service l THEN calculation of Drywell Bulk Average temperature is :IN'VAL:ID.

1. FOR ENTRY :INTO ON-120 OR T-102 1 use TI-2501 point 136 OR PR/TR-4805 to calculate APPROXIMATE Drywell Bulk Average Temperature (per step 6.2.2).

2. TO DETERM:INE WHEN TO :IN:IT:IATE RPV BLOWDOWN 1 use hottest temperature of TI-2501 points 119 through 127 (excluding pt 125) OR PR/TR-4805 (if TI-2501 is unavailable) in conjunction with T-102, "Primary Containment Control" direction to determine when RPV blowdown is required.

3. DO NOT SPRAY THEDRYWELL. Without an accurate bulk average calculation, OR Engineering evaluation verifying that plant conditions are-on the safe side of Drywell Spray Initiation Limit Curve.

4. TO DETERMINE :IF DWCW CAN' BE RESTORED TO THE DRYWELL COOLER FAN' UNITS PER T-223: :IF Drywell Bulk Average Temperature CANNOT be determined, THEN obtain Engineering evaluation prior to placing Drywell Cooler Fans in service.

RT-O-40C-530-2 Rev. 6 Page 9 of 11 DATA SHEET 2 DRYWELL CHILLER DATA Date- - - - . Time REACTOR CONDITIONS RECIRCULATION PUMP SPEEDS TEMPERATURE of SPI-2-02-184-016A  %

PRESSURE PSIG SPI-2-02-184-016B  %

THERMAL PWR MWT DRYWELL CONDITIONS I ELECTRICAL PWR MWE TEMP. (PR/TR-4805) of TI-2S01 TE DESCRIPTION READING POINT # NO.

125 TE-2501 25 DRYWELL ANNULUS, EL. 194'-AZ 180 OF 128 TE-2501-28A 2AV026 DRYWELL DISCHARGE AREA TEMP, OF EL. 150'-AZ 345 --

129 TE-2501-29A 2BV026 DRYWELL, DISCHARGE AREA TEMP, OF EL. 150'-AZ 230 --

130 TE-2501-30A 2CV026 DRYWELL DISCHARGE AREA TEMP, OF EL. 150'-AZ 85 --

131 TE-2501-31A 2DV026 DRYWELL DISCHARGE AREA TEMP, OF EL. 150'-AZ 290 --

132 TE-2501-32A 2EV026 DRYWELL DISCHARGE AREA TEMP, OF EL. 150'-AZ 25 --

133 TE-2501-33A 2FV026 DRYWELL DISCHARGE AREA TEMP, OF EL. 120'-AZ 225 --

134 TE-2501-34A 2GV026 DRYWELL DISCHARGE AREA TEMP, OF EL. 120'-AZ 210 --

161 TE-2501 61 RETURN WATER TEMP TO DRYWELL OF CHILLERS --

162 TE-2501-62 CHILLED WATER TEMP TO DRYWELL OF PARAMETER INSTRUMENT NO. READING

, CHILLED WATER FLOW FI-20243 GPM

RT-O-40C-530-2 Rev. 6 Page 10 of 11 DATA SHEET 2 (Continued)

DRYWELL CHILLER DATA Date Time- - -

DRYWELL COOLER IN STANDBY OUT OF SERVICE FANS SERVICE FOR MAINTENANCE 2AV026A 2AV026B 2BV026A 2BV026B 2CV026A 2CV026B 2DV026A 2DV026B I 2EV026A 2EV026B 2FV026A 2FV026B 2GV026A 2GV026B DRYWELL RECIRC FANS IN STANDBY OUT OF SERVICE SERVICE FOR MAINTENANCE 2AV094A 2AV094B 2BV094A 2BV094B

RT-O-40C-530-2 Rev. 6 Page 11 of 11 DATA SHEET 2 (Continued)

DRYWELL CHILLER DATA Date

---

Time--------

DRYWELL CHILLER IN STANDBY OUT OF SERVICE UNITS SERVICE FOR MAINTENANCE A

B C

DRYWELL CHILLED IN STANDBY OUT OF SERVICE WATER PUMP SERVICE FOR MAINTENANCE A

B C

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET ll=:=odIll Peach Bottom ~ Common

~ JPM D QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-244C LICENSED OPERATOR REQUALIFICATION 001 M. J. Kelly jav PERFORM REACTOR COOLANT LEAKAGE SURVEILLANCE APPROVALS:

Signature I Title Date Signature / Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _ _-' _ _ _-' _ _ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR244C Rev001.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2690010201/ PLOR-244C KIA: G2.1 .25 LlRO: 2.8 SRO: 3.1 TASK DESCRIPTION: PERFORM REACTOR COOLANT LEAKAGE TEST A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" ..IPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this ..IPM, though listed in the task standard, is not to be given to the examinee.

PLOR244C RevOO1.doc Page 2 of 6

B. TOOLS AND EQUIPMENT

1. AT2 -In-progress ST-0-020-560-2, Rev. 12, "Reactor Coolant Leakage Tesf'

2. Calculator C. REFERENCES

1. ST-0-020-560-2, Rev. 12, "Reactor Coolant Leakage Tesf'

2. AT3 - ST 020-560-2 Data Sheet 1 ANSWER KEY D. TASK STANDARD

1. Satisfactory task completion is indicated when reactor coolant leakage has been calculated using Data Sheet 1 of ST-0-020-560-2 "Reactor Coolant Leakage Tesf'.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMII\IEE When given the initiating cue, perform necessary steps to calculate reactor coolant leakage using ST-0-020-560-2 "Reactor Coolant Leakage Tesf'. I will describe initial plant conditions and provide you access to the materials required to complete this task.

,-. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is at 100% power.

2. The Unit 2 Drywell Sump Monitoring System is operable.

3. Unit 2 Drywell Floor Drain Sump valves and pumps are lined up in accordance with SO 20A.1.A, "Floor Drain Sumps Startup and Normal Operation".

4. Unit 2 Drywell Equipment Drain Sump valves and pumps are lined up in accordance with SO 20C.1.D, "Equipment Drain Sumps Startup and Normal Operation".

5. AO 2A.16-2 "Manual Adjustment of Recirculation Pump Seal Second Stage Pressure" has NOT been performed.

6. The previous week's flow data readings of Drywell Floor and Equipment Drain Sumps have been entered on Data Sheet 1 of ST 020-560-2,"Reactor Coolant Leakage Test".

7. The current 4-hour Drywell Floor Drain and Equipment Drain sump integrator readings have already been documented on Data Sheet 1 of ST 020-560-2,"Reactor Coolant Leakage Tesf'.

8. All steps of ST-0-020-560-2,"Reactor Coolant Leakage Tesf', up to and including step 4.4.15, have been completed satisfactorily.

PLOR244C Rev001.doc Page 3 of 6

G. INITIATING CUE The Control Room Supervisor directs you to determine the Unit 2 reactor coolant leakage flow rate by performing steps 6.1 through 6.4 of ST-O-020-560-2,"Reactor Coolant Leakage Tesf'.

PLOR244C Rev001.doc Page 4 of 6

H. PERFORMANCE CHECKLIST II STEP NO STEP ACT STANDARD 1 Cue: Hand the Candidate AT2, in- P progress ST-0-020-560-2, "Reactor Coolant Leakage Test" with some data recorded on Data Sheet 1

• 2 Calculate and record Drywell Floor Drain P Subtract the latest Floor Drain Sump 4-hour integrator difference. Integrator reading from the previous 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reading. Place a "0" in column (a) of Data Sheet 1.

• 3 Calculate and record Drywell Floor Drain P Divide the number from column (a) of flow in gallons per minute. Data Sheet 1 by 12. Place a "0" in column (b) of Data Sheet 1.

• 4 Calculate and record the Drywell Floor P Add the six flow numbers from Column Drain 24-hour running average flow. (b) and divide by 6. Place a "0" in column (c) of Data Sheet 1.

• 5 Record 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> running average flow P Record a "0" in column (d) of Data Sheet Drywell Floor Drain for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago. 1.

• 6 Calculate and record the Drywell Floor P Subtract column (d) from column (c) on Drain 24-hour running average difference. Data Sheet 1. Place a "0" in column (e) on Data Sheet 1 .

• 7 Calculate and record Equipment Floor P Subtract the latest Equipment Drain Drain 4-hour integrator difference. Sump Integrator reading from the previous 4-hour reading. Place a "19" in column (f) of Data Sheet 1 .

• 8 Calculate and record Drywell Equipment P Divide the number from column (f) of Drain flow in gallons per minute. Data Sheet 1 by 12. Place a "1.58" in column (g) of Data Sheet 1.

Cue: If examinee stalls here (step 6.2.3 of the surveillance test) state "You have adequate information on task conditions."

• 9 Calculate and record Total Drywell P Add the six Floor Drain numbers from leakage. column (b) to the six Equipment Drain numbers from column (g) of Data Sheet 1.

Divide the above number by 6 and place

~ a "1.38" in column (h) of Data Sheet 1.

PLOR244C Rev001.doc Page 5 of 6

STEP NO STEP ACT STANDARD

• 10 Verify the following data is acceptable: P Verify all data is below the specified limits and initial "All Data Within Accep Crif' Column (b) is.:s 5.0 gpm Column of Data Sheet1 as SAT.

Column (e) is.:s 2.0 gpm Column (h) is .:s 25.0 gpm 11 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When step 6.4 of ST-O-020-560-2,"Reactor Coolant Leakage Tesf' has been completed the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR244C Rev001.doc Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is at 100% power.

2. The Unit 2 Drywell Sump Monitoring System is operable.

3. Unit 2 Drywell Floor Drain Sump valves and pumps are lined up*

in accordance with SO 20A.1.A, "Floor Drain Sumps Startup and Nornlal Operation".

4. Unit 2 Drywell Equipment Drain Sump valves and pumps are lined up in accordance with SO 20C.1.D, "Equipment Drain Sumps Startup and Normal Operation".

5. AO 2A.16-2 "Manual Adjustment of Recirculation Pump Seal Second Stage Pressure" has NOT been performed.

6. The previous week's flow data readings of Drywell Floor and Equipment Drain Sumps have been entered on Data Sheet 1 of ST-0-020-560-2," Reactor Coolant Leakage Test" .

7. The current 4-hour Drywell Floor Drain and Equipment Drain sump integrator readings have already been documented on Data Sheet 1 of ST-0-020-560-2,"Reactor Coolant Leakage Test".

8. All steps of ST-0-020-560-2,"Reactor Coolant Leakage Test", up to and including step 4.4.15, have been completed satisfactorily.

INITIATING CUE The Control Room Supervisor directs you to determine the Unit 2 reactor coolant leakage flow rate by performing steps 6.1 through 6.4 of ST-O-020-560-2,"Reactor Coolant Leakage Test".

Exelon Nuclear ST-O-020-560-2 Peach Bottom Rev. 12 Unit 2 Page 1 of 25 Surveillance Test DCM:dcm ST-O-020-560-2 REACTOR COOLANT LEAKAGE TEST TEST FREQUENCY: Once/4 hours TECH SPEC: SR 3.4.4.1 APPLICABILITY: Mode 1, 2, 3 1

CHECK why this procedure is being performed:

II Schedule [JOVF [J Retest Due To Unsat Test

[J Other Reason: ______________________________________________

Approved by SMgt: NIA _ 1 _ / - _-:--,.-_

Printed Name Time Date Initials

~ INITIAL one of the following Test Results:

A: All

• steps are SATISFACTORY B: One or More

• steps are UNSATISFACTORY Refer to Section 9.0 for Tech Spec LCO's I I Performed By:

Printed Name Time Date Initials ROIPRO Informed of Test Completion: N/A SMgt Informed of Test Results: _1_1 UNSAT Notification:

SMgt Discretion: plant Mgr or Others Notified By: _1_1 U IF other portions of the test did NOT function properly, OR other discrepancies were noted, THEN COMPLETE the following:

DESCRIBE discrepancies/actions taken: Issue#:

~ Reviewed/Approved Plant Staff:

Printed Name Time Date Initials

ST-0-020-560-2 Rev. 12 Page 2 of 25

~SB This test provides indication of Reactor coolant leakage via the Drywell Sump Collection system. This test satisfies Tech Spec eST SR 3.4.4.1. CM-2 BQUl:PMENT None Initial COMPLETE Section 1 of cover page. N/A

. 2 ) ? X t Review

~ ENSURE procedure is current revision. :1(.0.

~etuP/Check of Required Communications None

~ipment Configuration

~ VERIFY D/W Floor Drain Sump valves AND J<C.J pumps are lined up in accordance with SO 20A.l.A OR RECORD AIR OR Clearance Number iF system is out of service.

!B.O.

~ VERiFY D/W Equipment Drain Sump valves AND

~ pumps are lined up in accordance with SO 20C.l.D OR RECORD AIR OR Clearance Number iF system is out of service.

~equired Redundant Safety Related Equipment

!B.O.

None

~Other Prerequisite Activities I~ ENSURE required previous weeks last six 4

~ hour flow data readings of Drywell Floor and Equipment Drain Sumps on Data Sheet 1 have been entered. !B.O.

~pproval to Start Test None

ST-O-020-560-2 Rev. 12 Page 3 of 25 GENERAL INSTRUCTIONS impact plant availability in any is NOT required when Reactor is

~ecautions None

~mitations Instructions IF any of the following occur REQUEST Chemistry to initiate ST-C-095-819-2, Drywell Atmosphere Radiation Monitor Operational and Surveillance Log.

CM-l The Drywell Sump Monitor~ng System is defined as the D!W Floor Drain OR D!W Equipment Drain System, but only IF the D!W Floor Drain Sump is overflowing.

T e Drywell Sump Monitoring System is declared

. operable. (Verify compliance with Tech Spec 3.4.4 AND 3.4.5).

~ floor drain leakage has risen by 1.5 gpm

~~ the corresponding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> running average on the previous day. (At the same time 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago).

ST-O-020-560-2 Rev. 12 Page 4 of 25 RECAUTIONS, LIMITATIONS, AND GENERAL INSTRUCTIONS (Continued)

With minimal inleakage to he sumps, there may be insufficient level for the sump pumps to operate.

~ IF there is an unexpected change OR trend in the

~ integrator 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> difference reading, (column a or f), THEN notify Shift Management AND iderthefollowing :

@ . OBTAIN current sump pump run time from pump breaker, (Ref. NOM-C-6.3 RWEO round sheets), AND review for any abnormal run times.

lEW flow recorder, FR-2-20-528, for any abnormal flow conditions.

ERFORM RT-O-020-l00-2, "Determination Of Rate And Location Of Drywell Leakage".

IF a sump pump low flo~T c ltion exists, THEN the flow integrater FQ-2-20-527(530} may NOT be accurately monitoring flow rate.

IF it has been determined that a pump low flow condition exists, (ie., stuck open check valve, low capacity pump), THEN CREATE an Issue AND NOTIFY Shift Management. (Verify compliance with Tech Spec. 3.4.4 AND 3.4.5)

Test frequency is every 4 hrs but sumps may fill and pump out every 2 to 3 hrs, there will be 4 hr periods pumps may operate and some periods they may operate twice. IF a flow calculation appears to be 1/2 previous reading, this may be due to the sump being pumped once during one period and twice during another. This can cause flow to appear to be twice that of previous period. In this case, flow can be compared to that calculated 8 hrs before to determine if flow has changed significantly.

D/W Floor Drain Leakage is considered unidentified leakage and D/W Equipment Drain Leakage is considered identified leakage in normal line-up.

ST-O-020 560-2 Rev. 12 Page 5 of 25 PREC~ LIMITATIONS, AND GENERAL INSTRUCTIONS (Continued)

~

D/W Floor Drain Sump capacity is 500 gallons. D/W Equipment Drain Sump capacity is 500 gallons.

(Actual volume of the Equipment Drain Sump is less due to the volume of cooling coils contained in the Equipment Drain Sump. For details see print M-519.) CM-3 IF the D/W Floor Drain System OR D/W Equipment Drain System is out of service, THEN all leakage (with the exception of Recirc Pump seal vent flow) is considered unidentified. (Verify compliance with Tech Spec. 3.4.4 AND 3.4.5)

IF the D/W Floor Drain Sump is out of service, AND the D/W Equipment Sump is to be used to monitor unidentified leakage, THEN both D/W Floor Drain and Equipment Drain Sump HI-HI Level Alarms need to be operable.

IF leak rates over periods other than 4 hrs are needed use Data Sheet 2.

IF any procedure step can NOT be completed OR produces an unexpe:cted response THEN STOP the test AND NOTIFY the RO AND SMgt.

IF any Black Box is initialed THEN STOP the test AND NOTIFY the RO AND SMgt.

IF procedure is aborted, THEN NOTIFY SMgt AND WRITE "TEST ABORTED" in Section 3 of Cover Page.

All persons who initial steps in Sections 3.0, 6.0, or 7.0 are responsible for completing Section 10.0.

Initial blanks designated as IV are provided for Independent Verification.

All applicable

• steps are identified immediately in front of the initials.

ST-O-020-560-2 Rev. 12 Page 6 of 25

~CEPTANCE CRI~A e following have NOT been exceeded on Data Sheet 1:

rywell Floor Drain Leakage less than or equal to 5.0 gpm (b).

otal Leakage less than or equal to 25.0 gpm (Averaged over ny 24 hr period) (h).

rywell Floor Drain 24 hr running average difference less than r equal to 2.0 gpm in Mode 1 (e).

~ PERFO,RMANC_E

____ __ST_EP_S________

__ r-__ ~~------------------~

F the D/W Floor Drain AND D/W Equipment Drain Systems are in normal line up, THEN erform Sections 6.1 through 6.4.

IF the D/W Floor Drain System is out of service, THEN perform Section 6.5 AND determine if a Tech Spec Action (TSA) entry is required. (Refer to Tech Spec 3.4.4 and 3.4.5)

IF the D/W Equipment Drain System is out of service, THEN the Equipment Sump will overflow, as designed, to the Floor Drain Sump. All leakage (with the exception of Recirc Pump seal vent flow) will be considered unidentified leakage.

G Obtaining D/W Floor Drain System Readings The following step re performed every four hours and data is recorded on Data Sheet 1. Data for columns on Data Sheets are indicated by small letters.

t Control Room Panel 20C004A >

t;j .. 1 RECORD indication of FQ-2-20-527 "D/W Floor Drain" in "Flow Integ Reading" column on Data Sheet 1.

6.1.2 CALCULATE AND RECORD (a) "4 hr Integrator difference" as follows:

Flow Previous 4 hr Integ 4 hr = (a) Integ Reading Integ Diff Reading

ST-O-020-560-2 Rev. 12 Page 7 of 25 6.0 PERFORMANCE STEPS (Continued) 6.1. 3 CALCULATE AND RECORD "Flow gpm" as follows (b):

( Accep Crit: less than or equal to 5.0 gpm )

Flow gpm (b) = Present 4 hr Integ Diff (a) 12 6.1. 4 CALCULATE AND RECORD "24 hr Runn Avg Flow" as follows (c):

24 hr Runn Avg (c) = Present Flow (b) + Previous 5 Flows (b)

Flow 6 6.1.5 RECORD "24 hr Runn Avg Flow for 24 hrs ago" (d) from "24 hr Run Avg Flow" (c) corresponding to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> previously.

6.1. 6 CALCULATE AND RECORD "24 hr runn avg Diff" (e) as follows:

( Accep Crit: IN Mode 1 ONLY less than or equal to 2.0 gpm )

24 hr 24 hr Runn Runn' 24 hr Avg (c) Avg (d) = Runn (e)

Flow Flow Avg 24 hrs Diff ago NOTE Steps 6.2, 6.3 and 6.4 are performed every four hours and data is recorded on Data Sheet 1. Data for columns on Data Sheets are indicated by small letters.

6.2 Obtaining D/W Equipment Drain System Readings

< At Control Room Panel 20C004A >

6.2.1 RECORD indication of FQ-2-20-530 "D/W Equip Drain" in "Flow Integ Reading" column on Data Sheet 1.

6.2.2 CALCULATE AND RECORD "4 hr Integ Diff" (f) as follows:

Integ Previous 4 hr Reading 4 hr = Integ (f)

Integ Diff Reading

ST-O-020-560-2 Rev. 12 Page 8 of 25 6.0 PERFORMANCE STEPS (Continued)

NOTES

1. 3.0 gpm shall be added to the D/W Equipment Drain Reading value when ONE Recirc Pump seal is vented to CRW in accordance with AO 2A.16-2, "Manual Adjustment Of Recirculating Pump Seal Second Stage Pressure".

2. 6.0 gpm shall be added to the D/W Equipment Drain Reading value when TWO Recirc Pump seals are vented to CRW in accordance with AO 2A.16-2, "Manual Adjustment Of Recirculating Pump Seal Second Stage Pressure".

3. IF D/W Equipment Drain Monitoring is out of service, the above input values will still be considered identified leakage AND calculated accordingly.

6.2.3 CALCULATE AND RECORD "Flow gpm" (g) as follows:

Flow gpm (g) = Present 4 hr Inteq Diff (f) + 3.0 gpm (6.0) gpm 12 6.3 Total Leakage Calculation 6.3.1 CALCULATE AND RECORD "Total Leakage" (h) as follows:

( Accep Crit: less than or equal to 25.0 gpm A + B =C 6

Where: A = Present + previous 5 Floor Drain Flows (b)

B Present + previous 5 Equip Drain Flows (g)

C = Total Average Flow (h) 6.4 Acceptance Criteria Verification 6.4.1 VERIFY data in the following columns are within Acceptance Criteria limits AND INITIAL Data Sheet 1, THEN proceed to Section 7.0.

1. (b) less than or equal to 5.0 gpm

2. (e) less than or equal to 2.0 gpm

3. (h) less than or equal to 25.0 gpm

ST-O-020-560-2 Rev. 12 Page 9 of 25 6.0 PERFORMANCE STEPS (Continued)

NOTES

1. IF the D/W Floor Drain System AND D/W Equipment Drain System are in normal line up, THEN Step 6.5 does NOT apply.

2. Step 6.5 is performed if the D/W Floor Drain System is expected to be out of service for greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Otherwise, Step 6.5 is N/A.

3. IF the D/W Equipment Drain System is out of service, THEN the Equipment Sump will overflow, as designed, to the Floor Drain Sump. All leakage (with the exception of Recirc Pump seal vent flow) will be considered unidentified leakage.

6.5 Leakage Detection When D/W Floor Drain System is Out of Service NOTE The following shall be considered, when performing this section:

A Tech Spec Action (TSA) entry is required.

(Refer to Tech Spec. 3.4.4 AND 3.4.5).

rrhe HI-HI Alarms for both D/W Floor Drain AND Equipment Drain Sumps neE:d to be operable.

The HI-HI Alarms are being used as indication that RCS unidentified leakage, total leakage and unidentified leakage are within limits.

This is being accomplished by calculated values based on previous flow rates to determine when the HI-HI Alarms will occur.

(Ref. SR 3.4.4.1 Bases B3.4-23 AND Reg. Guide

1. 45)

IF a HI-HI Alarm occurs outside the estimated/calculated values, THEN the potential exists that leakage has changed AND Shift Management shall bE~ notified.

< At Control Room Panel 20C004A >

6.5.1 PLACE 2A/BP097 Drywell Floor Drain Sump Pump Control Switches to the "OFF" position.

ST-O-020 560-2 Rev. 12 Page 10 of 25 6.0 PERFORMANCE STEPS (Continued) 6.5.2 RECORD the following:

Date/Time (OFF) ----------_/-----

FQ-2-20-527 Reading NOTE The following steps are an attempt to bring the Drywell Floor Drain Sumps to an overflow condition by using the D/W Equipment Drain Sump Input. This is being done so the D/W Equipment Drain Sump monitoring system can be used to monitor unidentified leakage.

(Refer to Tech Spec Bases Background Section B-3.4-24) 6.5.3 PLACE the 2A/BP098 D/W Equipment Drain Sump Pump Control Switches to the "OFF" position.

6.5.4 RECORD the following:

Date/Time (OFF) Tl = ----------_/-----

FQ-2-20 530 Reading 6.5.5 CALCULATE AND RECORD the following:

(For Equipment Drain Sump HI-HI Level Alarm) 440 Gallons + Avg. of 6 Est. Time for Previous 4 hr = HI-HI Level Flow (g) Alarm (T 2 ) ::;;

Min.

6.5.6 CALCULATE AND RECORD the estimated time (TEST,) for the D/W Equipment Drain Sump HI-HI Level Alarm to be reached.

+ Time/Date NOTE IF the D/W Equipment Drain Sump HI-HI Level Alarm did NOT occur during the estimated time, THEN contact Shift Management for further direction.

6.5.7 RECORD the actual time that the HI-HI Level Alarm was reached. T3 = / Time/Date

ST-O-020-560-2 Rev. 12 Page 11 of 25 6.0 PERFORMANCE STEPS (Continued) 6.5.8 CALCULATE AND RECORD the following:

(For Floor Drain HI-HI Level Alarm)

Avg. of 6 Avg. of 6 528 Gallons + Previous Previous 24 4 Hr Flow + Hr Runn Avg =- - -

( g) Flow (c) Mins.

6.5.9 CALCULATE AND RECORD the estimated time (T~)for the D/W Floor Drain Sump HI-HI Alarm to be reached.

+ T3  ;::: TEST2 - - _ / _ - - Time/Date NOTE WHEN the D/W Floor Drain Sump HI-HI alarm occurs, the sump level is approximately 2" from top of overflow.

6.5.10 RECORD the actual time that the Floor Drain HI-HI level occurs. Ts Time/Date 6.5.11 CALCULATE AND RECORD the following:

Avg. of 6 Avg. of 6 88 Gallons + Previous Previous 24 4 Hr Flow + Hr Runn Avg =--

( g) Flow (c) Mins.

6.5.12 RECORD calculated time when overflow of both D/W Equipment Drain Sump and D/W Floor Drain Sump will occur.

- - _ / _ - - Time/Date NOTE Once T7 has been reached, the D/W Equipment Drain Sump System is now monitoring all D/W leakage (with the exception of Recirc Pump seal vent flow) as unidentified leakage.

6.5.13 WHEN T7has been reached, THEN RECORD integrator reading from FQ-2-20-530 AND PLACE in column on Data Sheet 1, for approximate date and time.

6.5.14 PLACE 2A/BP098 D/W Equipment Drain Sump Pump Control Switches to the "AUTO" position.

ST-O-020-560-2 Rev. 12 Page 12 of 25 6.0 PERFORMANCE STEPS (Continued) 6.5.15 VERIFY both pumps start AND D/W Equipment Drain flow is indicated on FR-2-20-528 (red pen).

6.5.16 VERIFY both pumps "AUTO" stop AND HI-HI alarm is clear.

NOTE Steps 6.5.17 through 6.5.28 are performed every four hours and recorded on Data Sheet 1.

6.5.17 RECORD indication of FQ-2 20-527 "D/W Floor Drain" in "Flow Integ Reading" column on Data Sheet 1.

6.5.18 RECORD indication of FQ-2-20 530 "D/W Equip Drain" in "Flow Integ Reading" column on Data Sheet 1.

NOTE While the Equipment Sump is monitoring ALL leakage (with the exception of Recirc Pump seal vent flow) as "Unidentified", columns (f) and (g) are applicable ONLY for calculating Recirc Pump seal vent flow.

6.5.19 CALCULATE "4 hr Integ Diff" as follows:

Flow Previous 4 hr Integ 4 hr = Integ Reading Integ Diff (Equip) Reading (Equip) 6.5.20 RECORD "4 hr Inte9 Diff" into "4 hr Integ Diff" (a) column.

ST-O-020-560-2 Rev. 12 Page 13 of 25 6.0 PERFORMANCE STEPS (Continued)

NOTES

1. 3.0 gpm shall be added to the D/W Equipment Drain Reading value when ONE Recirc Pump seal is vented to CRW in accordance with AO 2A.16 2, "Manual Adjustment Of Recirculating Pump Seal Second Stage Pressure".

2. 6.0 gpm shall be added to the D/W Equipment Drain Reading value when TWO Recirc Pump seals are vented to CRW in accordance with AO 2A.16-2, "Manual Adjustment Of Recirculating Pump Seal Second Stage Pressure".

3. IF D/W Equipment Drain Monitoring is out of service, the above input values will still be considered identified leakage AND calculated accordingly.

6.5.21 IF any Recirc Pump seals are being vented to CRW, THEN RECORD appropriate value as identified leakage in column (f). OTHERWISE, NIA column (f).

NOTE Due to the pumping down of the D/W Equipment Drain Sumps from the HI-HI level, an initial flow of greater than 5.0 gpm for the first 4 hr reading may be recorded after returning the sump pumps to operation.

6.5.22 CALCULATE AND RECORD "Flow gpm" as follows (b):

(Accep Crit: less than or equal to 5.0 gpm)

Flow gpm (b) = Present 4 hr Integ Diff (a) 12

ST-O-020-560-2 Rev. 12 Page 14 of 25 6.0 PERFORMANCE STEPS (Continued)

NOTE In an effort to obtain accurate values for the following calculations, it may be necessary to use data that was obtained prior to the systems being removed from service. (I.E. prior to the TSA when calculating average flows.)

6.5.23 CALCULATE AND RECORD "24 Hr Runn Avg Flow" as follows (c) :

24 hr Runn Avg (c) = Present Flow (b) + Previous 5 Flows (b)

Flow 6 6.5.24 RECORD "24 Hr Runn Avg Flow for 24 hrs ago" (d) from "24 hr Run Avg Flow" (c) corresponding to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> previously.

6.5.25 CALCULATE AND RECORD "24 hr Runn Avg Diff" (e) as follows:

( Accep Crit: IN Mode 1 ONLY less than or equal to 2.0 gpm )

24 hr 24 hr Runn Runn 24 hr Avg (c) Avg (d) = Runn (e)

Flow Flow Avg 24 hrs Diff ago

ST-O-020-560-2 Rev. 12 Page 15 of 25 6.0 PERFORMANCE STEPS (Continued)

NOTES

1. 3.0 gpm shall be added to the D/W Equipment Drain Reading value when ONE Recirc Pump seal is vented to CRW in accordance with AO 2A.16-2, "Manual Adjustment Of Recirculating Pump Seal Second Stage Pressure".

2. 6.0 gpm shall be added to the D/W Equipment Drain Reading value when TWO Recirc Pump seals are vented to CRW in accordance with AO 2A.16-2, "Manual Adjustment Of Recirculating Pump Seal Second Stage Pressure".

3. IF D/W Equipment Drain Monitoring is out of service, the above input values will still be considered identified leakage AND calculated accordingly.

6.5.26 IF any Recirc Pump seals are being OR have been vented to CRW within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, THEN RECORD appropriate value as identified leakage in column (g). OTHERWISE, N/A column (g).

6.5.27 CALCULATE AND RECORD "Total Leakage" (h) as follows:

( Accep Crit: less than or equal to 25.0 gpm A + B = C 6

Where: A = Present + previous 5 Floor Drain Flows (b)

B = Present + previous 5 Equip Drain Flows (g)

C = Total Average Flow (h) 6.5.28 VERIFY DATA in the following columns are within Acceptance Criteria limits AND INITIAL Data Sheet 1.

1. (b) less than or equal to 5.0 gpm

2. (e) less than or equal to 2.0 gpm

3. (h) less than or equal to 25.0 gpm

ST-O-020 560-2 Rev. 12 Page 16 of 25 6.0 PERFORMANCE STEPS (Continued) 6.5.29 IF D/W Floor Drain Sump Pumps are to be returned to service, THEN perform the following:

NOTE Due to the pumping down of the D/W Floor Drain Sumps from the HI-HI level, an initial flow of greater than 5.0 gpm for the first 4 hr reading may be recorded after returning the sump pumps to operation.

1. RECORD integrator reading from FQ-2-20-527 AND place in column on Data Sheet 1, for approximate data and time.

2. PLACE 2A/BP097 Drywell Floor Drain Sump Pump Control Switches to the "AUTO" position.

3. VERIFY both pumps start AND Drywell Floor Drain Sump flow is indicated on FR-2 20-528 (black pen) .

4. VERIFY both pumps "AUTO" stop AND HI-HI alarm is clear.

7.0 PROCEDURE COMPLETION 7.1 Independent Verification 7.1.1 VERIFY ALL Floor Drain and Equipment Drain calculations CORRECT AND INITIAL Data Sheet 1.

7.2 Records Completion Initial 7.2.1 TRANSCRIBE last six 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> flow data readings of D/W Floor Drain and Equipment Drain Sumps onto Data Sheet 1 for next weeks Surveillance Test.

7.2.2 COMPLETE Section 2 of Cover Page (and Section 3 if applicable) .

ST-O-020-560-2 Rev. 12 Page 17 of 25

8.0 REFERENCES

8.1 Governing 8.1.1 Tech Spec SR 3.4.4.1 8.1.2 CM-ll NRC Inspection Report 50-277/88-13; 50-278/88-13, Closeout of Unresolved Item 50 277/84-23-01; 50-278/84-18-01 (T01737) 8.1. 3 CM-2, Letter to NRC from G. A. Hunger, Jr. dated Sept. 29, 1994 transmitting TSCR 93-16 (T03736) 8.1. 4 CM-3, Response to NRC violation 95-26 02 (T03837) 8.2 Interfacing 8.2.1 ST-C-095-819-2, Dr~~ell Atmosphere Radiation Monitor Operational and Surveillance Log 8.2.2 RT-O-020-100-2, Determination Of Rate And Location Of Drywell Leakage 8.3 Developmental 8.3.1 M-368, Radwaste Liquid Collection System 8.3.2 M-519, Plumbing and Drainage Print (D/W Sump Detail) 8.3.3 NRC Licensing IE Bulletin 78-10B 8.3.4 This procedure supersedes ST 9.17-2 8.3.5 Attachment 1, Simplified Drawing of Sump Pump Pit and Level Probe Arrangement 9.0 TECH SPEC LIMITING CONDITIONS FOR OPERATION (LeOs)

Section 3.4.4

ST-O-020-560-2 Rev. 12 Page 18 of 25 10.0 PARTICIPANTS RECORD Printed Name Initials i

I i

~

ST-O-020-560-2 Rev. 12 Page 19 of 25 DATA SHEET 1 DRYWELL_FLOOR AND EQUIPMENT DRAIN SUMP LEAKAGE Date Day/ Floor Drain Sump (al (b) {el (d) tel Equip Drain (I) (g) (h) All Data All time 4hr Flow 24Hr 24Hrs 24hr Sump 4hr Flow Total Within CaIcs Flow Integ gpm Runn Runn Runnavg Integ gpm Leakage Accep Veri!

Integ Diff Avg, Avg. Flow Diff Flow Dill 24hr Crtt Correct Reading Flow for Integ avg (Initial) 5gpm 24Hrs 2gpm Reading Sat unsat (Initial)

Ago SaI/OOOO

-.l-.l_

Sat/0400 SatlO8OO Satl1200 SaUl600 Satl2000

>IV"

..J ...L Sun/OOOO 904078 U 1400780 t * .....

IV Sun/04OO I n IV Sun/0800 I II IV Sun/1200 I II IV Sunll600 I n IV Sun/2000 I IV

II] ST-O-020-560-2 Rev. 12 Page 20 of 25 DATA SHEET 1 (Continued)

DRYWELL FLOOR AND EQUIPMENT DRAIN StlMP LEAKAGE Dale Day I Roor Drain Sump (a) (b) (e) (d) (e) Equip Drain (I) (g) (h) All Data All time 4hr Row 24Hr 24hr 24hr Sump 4hr Flow Total Within Cales Flow Integ gpm Runn RunnAvg. Runnavg Integ gpm Leakage Accep Veri!

Integ Reading Oil!

. Avg.

Row Flow For .

Dill Aow Integ Dill 24hr avg ent (Initial)

Correct 5gpm 24Hrs S:2gpm Reading §m~ (Initial)

Ago S:25 gpm

...-1._L MonIOOOO

&....I IV MonI0400

&....I -IV MonI08OO

&....I IV MonIl200

' - &....I -IV Mon/1600

' - &....I IV Mooi2000

' - &....I -- IV

_1....L TuelOOOO

' - &....I -IV Tue/04OO TuelO8OO

' - &....I

&....I IV IV

lI1 ST-O-020-560-2 Rev. 12 Page 21 of 25 DATA SHEET 1 (Continued)

DRYWELL FLOOR AND EQUIPMENT DRAIN SUMP LEAKAGE Date Day! Floor Drain Sump (a) (b) (e) (d) (e) Equip Drain (f) (9) (h) All Data All time 4hr Row 24Hr 24hr 24hr Sump 4hr Flow Total Within CaIcs Row Inleg gpm Rum Runn Avg. Runn avg Integ gpm Leakage Accep Vent Inleg Reading Diff

. Avg.

Flow Flow for .

DiH Row Integ Oiff 24 hr avg Crit (Initial)

Correct s5gpm 24Hrs s 2gpm Reading Sat unsal (Initial)

Ago ,; 25 gpm

--1--1_

Tuell200 Tuel600 ......

IV TueI2000

...... IV

--1--1_

WedIOOOO IV WedI0400 IV WedI0800 IV Wedll200 ......

IV Wedll600 IV

-IV Wedl2000

...... IV

~

ST-O-020-560-2 Rev. 12 Page 22 of 25 DATA SHEET 1 (Continued)

DRYW'ELL FLOOR AND EQUiPMENT DRAiN SUMP LEAKAGE I

Date Dayf Roor Drain Sump (a) (b) (e) (dl (e) Equip Drain (t) (g) (hl All Data All lime 4hr Flow 24Hr 24hr 24hr Sump 4hr Flow Total Within Cales Flow Integ gpm Runn RunnAvg. Runnavg Integ gpm Leakage Accep Veri!

Integ Reading Oiff

. Avg.

Row Flow lor Dil! Flow Integ Diff 24hr avg Grit (Initial)

Correct s5gpm 24Hrs s2gpm Reading Sat unsat (Initial)

Ago s 25 ThufOOOO gpm

..... -IV

..... 1_

ThulO4OO ,

-IV ThufOSOO -IV Thuf1200

-IV Thuf1600 .....

Thu/2000

..... IV

-IV 1_

FrifOOOO

..... -IV FriI0400 Frif0800

..... IV

-IV

~

ST-O-020-560 Rev. 12 Page 23 of 25 DATA SHEET 1 (Continued)

DRYWELL FLOOR AND EQUIPMENT DRAIN SUMP LEAKAGE Date Day! Floor Drain Sump (a) (b) (e) (d) (e) Equip Drain (f) (g) (h) AIiDala All time 4hr Flow 24 Hr 24 hr 24 hr Sump 4hr Flow Tolal Within Cales Flow Integ gpm Runn RunnAvg. Runnavg Integ gpm Leakage Accep Verif Integ Reading Diff

. Avg.

Flow Flow for24Hrs .

Diff Flow Integ Diff 24hr avg Grit (Initial)

Correct 5:5gpm Ago 5: 2 9pm Reeding .§m unsal (Initial) 5:25 1_

Frill200 gpm Fril1600 IV FriI2000 IV 1_

SatlOOOO IV IV Sal10400 Sal10800 IV Satl1200 IV 8a1l1600 IV

-- IV Sati2000 IV DATA SHEET 2 DRYWELL FLOOR OR EQUIPMENT DRAIN SUMP LEAKAGE

~

ST-O-020-560-2 Rev. 12 Page 24 of 25 Leakage Calculation GPM = Integrator Difference OR GPM = Integrator Difference X 20 3 X hours Minutes Time Time Time Integrator Integrator Integrator Leakage Sump Date Start Stop Difference Start Stop Difference Flow

~

ST-O-020-560-2 Rev. 12 Page 25 of 25 Attachment 1 SIMPLIFIED DRAWING OF SUMP PUMP PIT AND LEVEL PROBE ARRANGEMENT.

DRYWELLEQUWMffiNT&FLOORDRMNSU~S LEVELS~CHPROBES rumT2&3 stJBP1LE ROOM SVMP CAPACITY

_CALLONS EACH FLOOR DRArN SUMPPUMP ....... RECEPTACUi (l)@SOOPM EQUIPMENT (RATED) DRAIN RECEPTACLE EI. 120'-6'" ': i DRYWELL u

• i OVEItFLOW EL. 119'.0" l'1N. FL DRYWBLLFlN. FL. m... 119'*II W

+

~~e.1I9*"' II I I I -------~---------

M 8.118'.0" SINGLEPUMPSTART- lli"lI9-0"

• I I r- 4" ilL. IIS'-S'" tJI¥ I'IJMP(S) STOP - STOP us'.o"

• 4" fof, SHORT RADIUS EL80W ~

GROlIND PROBE - e. 117'.0" j BOTTOMOFPn,:

EL 117'-3"

~I I ., K 4" BOL. EL. 117',10314" BOL. EL. 111'-9314" "'"

l"Bc!ween SUMP PUMP PIT CAPACITY

'SGALLON!

ANSWER KEY - DO NOT HAND OUT TO CANDIDATE DATA SHEET 1 DRYWELL FLOOR AND EQUIPMENT DRAIN SUMP LEAKAGE Date Day! Floor Drain (a) (b) (e) (d) (e) Equip Drain (f) (g) (h) All Data All time Sump 4hr Flow 24 Hr 24 Hrs 24 hr Sump 4hr Flow Total Within Cales Integ gpm Runn Runn Runn avg Integ gpm Leakage Accep Verif Flow Integ Dill

. Avg.

Flow Avg. Flow for Dill Flow Integ Dill 24hr avg Crit (Initial)

Correct Reading :O:5gpm 24Hrs :0:2 gpm Reading Sat unsat (Initial)

Ago :0:25 gpm SaVOOOO NtA NtA NtA NtA NtA NtA NtA NtA NtA NtJ\ NtA ,'/

_LL 0 . ,  ;.

," '. NtP; .... :,

SaV0400 NtA NtA NtA" N/A NtA NlA NlA  : ' NtA '}

0 0 1.42

" ,NtA' ,'. NtA . NIA"' N/A:

SaV0800 N/A "VA 0 0 NtA "VA 1.33 NlA NlA '. '.' .

SaV1200 NtA NtA NlA NlA ;', (iliA NlA, iNlA, NiA 0 0 1.42 SaVI600 *. NlA .... NlA N/A . NIt< NlA NlA NlA NlA 0 0 .N/A 1.67 >

1\ ..... *'NlA SaV2000 904078 NlA 0 0 NlA NlA 1400761 NlA 0.83 NtA

" ,).,

. .N/A Sun/oooo 904078 0 0 0 0 0 1400780 19 1.58 1.38 iJOIl)5t~ , 19Q. a""""j IV Sun/04OO

,-0 IV sun/oaoo

,-0 IV Sun/1200

,-0 IV Sun/I600

,-0 IV Sun/2000

,-0 IV ANSWER KEY - DO NOT HAND OUT TO CANDIDATE

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET I X I I Peach Bottom I DII Limerick I I II Common I

~ JPM D QUALIFICATION MANUAL D OJT MODULE LICENSED OPERATOR TRAINING PLOR-258C LICENSED OPERATOR REQUALIFICATION 001 M. J. Kelly jav PRO DUTIES FOR A LIQUID RADWASTE DISCHARGE APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: _ _-----'1_ _------'1_ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 10#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR258C Rev001.doc Page 1 of 4

EXELON NUCLEAR PEACH BOnOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2730130202/ PLOR-258C KIA: 2.3.11 URO: 3.8 SRO: 4.3 TASK DESCRIPTION: Ability to control radiation releases.

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are deSigned to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard. is not to be given to the examinee.

PLOR258C Rev001.doc Page 2 of 4

B. TOOLS AND EQUIPMENT

1. AT2 -In progress ST-C-09S-S0S-2, Rev. 13, completed through step 6.12.S.

C. REFERENCES

1. ST-C-09S-S0S-2. Rev. 13, "Liquid Radwaste Discharge",

D. TASK STANDARD 1, Satisfactory task completion is indicated when section 6.13 has been completed in its entirety.

2. Estimated time to complete: 12 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to set-up the plant in preparation for a Liquid Radwaste discharge. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Both units are operating at 100% power.

2. The Floor Drain Sample Tank (FDST) needs to be discharged.

3. Chemistry and Shift Management have completed ST -C-09S-S0S-2, "Liquid Radwaste Discharge" through step 6.12.S.

4. Six Circulating Water Pumps are in operation.

S. The discharge Canal-To-Intake Pond crosstie gate is closed.

6. The PRO review and set-up has not been completed.

G. INITIATING CUE You are the PRO. Complete section 6.13 of ST-C-09S-S0S-2 illiquid Radwaste Discharge" in preparation for a liquid radwaste discharge.

PLOR258C Rev001.doc Page 3 of 4

H. PERFORMANCE CHECKLIST fl STEP STEP ACT STANDARD NO 1 Record actua.l number of operating P Verifies six Circulating Pumps are Circulating Pumps. operating from Task Conditions/Prerequisite information, record and initial step 6.13.1.

• 2 Set the HI Trip Setpoint. P Manually adjust the HI Setpoint Pot setting for RIS-0-17-350 to ~ 3.81, and record and initial step 6.13.2.

• 3 Set the HI HI Trip Setpoint. P Manually adjust the HI HI Setpoint Pot setting for RIS-0-17-350 to ~ 3.84, and record and initial step 6.13.3.

4 Mark step 6.13.4 uN/A" P Step 6.13.4 is reviewed and marked liN/A".

5 Review PRO steps. P Visually verify all the PRO steps in section 6.13 are complete, and initial step 6.13.5 SAT.

6 Record your name and initials. P Print your name and initials in Section 10.0.

7 Inform Control Room Supervision of P Inform Control Room Supervision of completion of task. completion of section 6.13 of ST-C-095 805-2 "Liquid Radwaste Discharge".

8 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When Section 6.13 of ST-C-095-805-2 has been completed, terminate the exercise.

PLOR258C RevO01.doc Page 4 of 4

TASK CONDITIONS/PREREQUISITES

1. Both units are operating at 100% power.

2. The Floor Drain Sample Tank (FDST) needs to be discharged.

3. Chemistry and Shift Management have completed ST-C-09S-S0S-2, ilLiquid Radwaste Discharge ll through step 6.12.S.

4. Six Circulating Water Pumps are in operation.

S. The discharge Canal-To-Intake Pond crosstie gate is closed.

6. The PRO review and set-up has not been completed.

INITIATING CUE You are the PRO. Complete section 6.13 of ST-C-09S-S0S-2 ilLiquid Radwaste Discharge ll in preparation for a liquid radwaste discharge.

Exelon Nuclear ST-C-095-B05-2 Peach Bottom Rev. 13 Unit 2 & 3 Page 1 of 27 Surveillance Test RLA:rla ST-C-095-805-2 LIQUID RADWASTE DISCHARGE TEST FREQUENCY: Unscheduled (See Section 1.0)

TECH SPEC: 5.5.1 AND ODCMS Sections 4.8.B.1.1, 4.8.B.1.2, 4.B.B.1.3, 4.8.B.3.1, 4.8.B.3.2, Table 4.8.B.1. Func. 1 AND Func. 4,4.8.B.4.3, 4.B.B.4.4, AND 4.B.B.4.5 APPLICABILITY: At all times TANK To Be DISCHARGED: SOURCE: j'f})gI CSAR No: 176-10 Approved By SMgt: ______~N/A~--_

Printed Name Time Date Initials 2 INITIAL one of the following Test Results:

A: All

• steps are B: One OR More

• steps are SATISFACTORY UNSATISFACTORY Refer to Section 9.0 for Tech Spec LCO's

, i Performed By: C/iem lJ'ecfi Current lJ'ocfaJl. C/I.

(CT) Printed Name Time Date Initials Reviewed By: / /

(SMgt) Printed Name Time Date Initials Completed By: / /

(CTR) Printed Name Time Date Initials UNSAT Notification:

(N/A IF SAT) SMgt Discretion: Plant Mgr OR Others Noti ed By: / /

(N/A IF SAT) 3 IF other portions of the test did NOT function properly, OR other discrepancies were noted, THEN COMPLETE the following:

DESCRIBE discrepancies/actions taken: A/R OR ETT #: _________

4 Reviewed/Approved CHEM Staff: __________________ ______ --/--1-- __ ~~ __

Printed Name Time Date Initials

ST-C-09S-80S-2 Rev. 13 Page 2 of 27 0 URPOSE This procedure prescribes normal methods to be used for the discharge of planned batch releases of liquid radioactive waste to the discharge canal. Also provided is the mechanism to verify initial conditions, complete required calculations AND record specified data associated with radioactive liquid effluents.

This procedure satisfies Offsite Dose Calculation Manual (ODCM) surveillance requirements for 4.8.B.l.l, 4.8.B.l.2, 4.8.B.l.3, 4.8.B.3.1, 4.8.B.3.2, Table 4.8.B.l.Func. 1 AND Func. 4, 4.8.B.4.3, 4.8.B.4.4, AND 4.8.B.4:.S. This procedure may be TC'ed. However, a thorough review of the UFSAR (for example, Section 9.2, Liquid Radioactive Waste System) must be completed as part of the TC process. WHEN TCing OR revising this document, THEN ensure that the requirements of the procedure, as described in the UFSAR, are satisfied.

0 E S T EQUZPMENT None.

~REREQOISITES Initial

~ocument Review

~ ENSURE procedure is current revision.

C/I.

CT

~ OBTAIN CY-PB-120-401 " Liquid Radioactive

~ Waste" for tank to be released. C.T.

CT

~ther Prerequisite Activities

~ RECORD the tank to be discharged Source

~ AND CSAR No. in Section 1 of this test's cover sheet. C.T.

CT

~est Initiation

~ This test has been initiated in accordance

~ with CY-PB-120-401.

~quipment Configuration None.

0 e q u i r e d Redundant Safety Related Equipment None.

0 P P r o v a l to Start Test None.

ST-C-095-805-2 Rev. 13 Page 3 of 27

~CAUTIONS. LIMITATIONS. AND GENERAL INSTRUCTIONS

~lant Impact Statement

/~ This procedure does NOT impact plant availability in

~ any manner AND may be performed in any Reactor Mode.

~recautions None.

~imitations

, ~ IF the discharge Canal-To-Intake pond Crosstie is

~ OPEN, THEN the following alarms shall be clear prior to AND during release:

~arm Panel 204 Window F-4 "OUTER SCREEN

~~~RUCTURE HI HI DIFF WTR LVL"

~larm Panel 304 Window F-4 "OUTER SCREEN

~ ~TRUCTURE HI HI DIFF WTR LVL"

@ IF the discharge Canal-To-Intake pond Crosstie is OPEN, THEN a minimum of three circulating water pumps must be in operation during the release of radioactive liquid to the discharge canal.

IF the release is terminated for lack of dilution flow, THEN it only may be restarted WHEN the calculated release conditions are reestablished.

~eneral Instructions

~ The Chemistry Technician (CT) initiates this test as required by CY-PB-120-401 criteria AND performs all CT initialed steps. The CT forwards this test to Shift Supervisor (SMgt) for review AND approval; completing all SMgt initialed steps. SMgt THEN forwards test to Plant Reactor Operator (PRO). The PRO performs all PRO initial steps AND forwards to Radwaste Operator (RWO). The RWO THEN performs all RWO initialed steps AND forwards this test to SMgt for review of all Operations' responsible steps.

The SMgt places this test in the Chemistry bin in the Main Control Room for retrieval AND review by Chemistry Technician Reviewer (CTR).

ST-C-095-805-2 Rev. 13 Page 4 of 27

~PRECAUTZONS. LIMZTATZONS. AND GENERAL ZNSTRUCTZONS (Continued)

~ IF any procedure step CANNOT be completed OR

~ produces an unexpected response, THEN STOP the test AND RETURN the equipment to a safe condition AND NOTIFY the RO OR SMgt AND Chemistry Supervision.

~ IF any Black Box is initialed, THEN STOP the test

~ AND RETURN the equipment to a safe condition AND NOTIFY the RO OR SMgt AND Chemistry Supervision.

@ This procedure shall be aborted 1IIIEII it is discovered that a Tank is NOT going to be released.

~ ZF procedure is aborted, THEN NOTZFY SMgt AND WRZTE "TEST ABORTED" in Section 3 of Cover Page.

@ A I I persons who initial steps in Sections 3.0, 6.0, OR 7.0 are responsible for completing Section 10.0.

~ All applicable

• steps are identified immediately in

~ front of the initials.

~CEPTANCE CRZTZRIA The following conditions must be met:

Copy of Gamma Isotopic Analysis Report attached to this rocedure.

Tank to be released has been processed through one OR more of these systems: Waste Collector Filter AND Demineralizer, Floor Drain Filter, Fuel Pool Filter Demineralizer, Chemical/Oily Waste Cleanup. (Epicore oil/water emulsion),

Laundry Drain Filter OR Projected Body Dose for Month is less than 0.12 mRem AND Projected Organ Dose for Month is less than 0.40 mRem.

RIS-0-17 350 "Rad Waste Effluent" Rad Monitor operable.

FR-0-20-441 "RWS Low Purity waste" Flow Recorder/Monitor operable.

FS-0-20-493 "RWS Low Purity Waste" High Flow Trip Set Pot AND associated Flow Control Valve are operable.

~Actual No. of Circ Pumps Providing Dilution is greater than

~ ~R equal to the Required No. of Circ Pumps providing Dilution.

~RIS-0-17-350 HI Trip Setpoint is less than OR equal to

~ ~equired HI Trip CPS.

ST-C-09S-80S-2 Rev. 13 Page 5 of 27 CCEPTANCE CRITERIA (Continued)

RIS-O-17-3S0 HI HI Trip Setpoint is less than OR equal to Required HI HI Trip CPS.

~ctual Maximum Release Rate GPM is less than OR equal to the

~~equired Maximum Release Rate value.

~ctual  % Setting for Discharge is less than OR equal to the

~~equired Maximum % Setting for Discharge.

Sample retained for Monthly Composite.

Every release Start AND Stop Time has been recorded on the appropriate data chart.

Initial

~~_ unSat Steps 6.1 and 6.2 may be performed in any order or concurrently.

~CORD chemistry data obtained in the

~;erformance of CY-PB-120-401, the tank source AND the associated CSAR No. on Data Sheet 1 C rr below. CM-l .L.

CT

~CORD the tank sourc 7 AND its associated CSAR C.er.

~;o. on all other appllcable data sheets. CM-l CT

ST-C-095-805-2 Rev. 13 Page 6 of 27

~ERFORMANCE STEPS (Continued) Initial Sat Unsat

~he water placed in OBT061 to be

~n~idered "Processed", THEN an RW-PB-625 1 Attachment 41 (as directed from RW-PB-591) will be given to Chemistry for attachment to ST-C-095-805-2.

~ the water placed in OBT061 considered

~nprocessedlt, THEN an RW-5921 Exhibit 9.1 will be given to Chemistry for attachment to ST-C-095-805-2.

~the water placed in OBT061 is "Post

~ush" demineralized water, THEN no further documentation will be given to Chemistry for ST-C-095 805-2, since the contents of the tank will be processed by the Laundry Drain Tank filter.

~dry Drain Tank water that is NOT

~~~essed by the Epicore Water Emulsion System shall be dispositioned in accordance with RW-592, "Transfer of Unprocessed Waste Water to the liB" Laundry Drain Tank". In this case the Laundry Drain Tank contents l

wi either be considered "Unprocessed" water or will be considered "Processed" by the Laundry Drain Filter, as determined by Chemistry/Radwaste Management.

~ tank to be discharged has NOT been processed

~hrough a Radwaste system, as specified in ODCMS 3.8.B.4, THEN CALCULATE AND RECORD Projected Body Dose AND Projected Organ Dose for Month on Data Sheet 1. OTHERWISE, NIA the applicable blocks for this step AND on Data Sheet 1. C.~

(ODCMS 3.8.B.4)

CT

~ VERZPT Projected Organ Dose is less than 0.40 mRem.

• 9{fYl CT CJ J2f VERIFY Projected Body Dose is less than 0.12 mRem.

9{fYl CT CJ

ST-C-095-805-2 Rev. 13 Page 7 of 27 DATA SHEET 1 TANK TO BE I

DISCHARGED SOURCE: :rtD9I CSAR No. 176 - 10 i

REASON FOR DISCHARGE Water Inventorg Contro{

fi111i SiliIl RECIRCULATION TIME (minutes) 45 ANALYSIS ANALYSIS LIMIT FOR REMARKS RESULT DISCHARGE CONDUCTIVITY 0.91 uS/cm < 2500 uS/cm [V] ~

pH 9(9{ 4.0 - 10.0 [A] ~

TEMPERATURE  ;,t,4.5 C AS READl ,,~

TURBIDITY 0.861 NTU < 30 NTU [V] ~

~

GAMMA SCAN TOTAL ACTIVITY 4.85 n 7 ,uCi /mL <1 E-4 ,uCi/mL [F]

ESTIMATED BODY DOSE 0 mRem 0.05 mRem [V] ~

ESTIMATED ORGAN DOSE 0 mRem 0.15 mRem [V] ~

THE FOLLOWING IS REQUIRED FOR RELEASE OF UNPROCESSED TANKS ONLY (ODCM ACCEPTANCE CRITERIA)

~

PROJECTED BODY DOSE FOR MONTH W/f4. mRem 0.12 mRem [D]

PROJECTED ORGAN DOSE FOR MONTH W/f4. mRem 0.40 mRem [D] ~

[F] =: ZF THE ACTIVITY IS LESS THAN OR EQUAL TO 1.0E-3, THEN A VARIANCE MAY BE GRANTED, OTHERWiSE ZF THE ACTIVITY IS GREATER THAN 1.0E-3, THEN A VARIANCE MAY NOT BE GRANTED UNLESS A PROJECTED DOSE IS CALCULATED, COMPARED TO THE REGULATORY LIMITS, AND COMMUNICATED TO THE CONTROL ROOM.

[V] AN ADMINISTRATIVE LIMIT FOR WHICH A VARIANCE MAY BE OBTAINED FROM CHEMISTRY SUPERVISION OR ON-CALL INDIVIDUAL.

[AJ CORRECTION OF pH FOR RELEASES MAY BE MADE BY DILUTION. pH IS NOT REQUIRED AND pH LIMIT DOES NOT APPLY ZF CONDUCTIVITY OF TANK IS LESS THAN 2.5 ~S/cm.

[D] THIS LIMIT APPLIES ONLY TO RELEASES WHEN THE SAMPLED TANK'S CONTENTS HAVE NOT BEEN PROCESSED THROUGH AT LEAST ONE RADWASTE SUBSYSTEM OR EQUIVALENT PER ODCMS BASES B 3.8.

(See CY-PB-120-401) 1 Required on tanks to be released WHEN the conductivity is greater than OR equal to 2.5 ~S/cm

ST-C-095 B05-2 Rev. 13 Page B of 27

~PERrORMANCE STEPS (Continued) Initial Sat UnSat

~RIFY tank sample results recorded on Data

~ ~heet 1 are Satisfactory for release to C.T.

discharge canal per CY-PB-120-401.

CT ariances may NOT be granted for any projected dose limit which has been exceeded.

IF a variance is Required AND NOT granted, THEN this test should be aborted.

~F any chemical analysis exceeds its Limit

~ ~or Discharge, THEN RECORD "Variance Required" in remarks section of Data Sheet 1 AND obtain approval for Discharge with a "variance". OTHERWISE, N/A this Step. CM-2 CT IF a "variance" was required for discharge, THEN CONTACT Chemistry Supervision OR on-call individual for Variance AND RECORD Name of Chemistry Supervisor OR responsible Staff person granting "Variance(s)"

below:

(IF a variance is NOT required, THEN N/A these spaces for this step.)

9{jYl

________________ _______ _--1--_1--

Name Time Date CT

~TTACH a copy of the Gamma Isotopic Analysis

~:eport to this test. (ODCMS 4.B.B.1.1, 4,B.B.1.2, 4.B.B.l.3, Table 4.B.B.l Func. 1 & 4)

• C.T. CJ CT

ST-C-095-805-2 Rev. 13 Page 9 of 27

~~BRFORMANCE STEPS (Continued) Initial Sat UnSat

~RiFY a portion of sample (approx 1 Liter) c/I.

~ ;etained for Monthly composite.

CT Chemistry Management approved computer programs may be used, AND is the preferred method, to perform the worker verification for the calculation of the values for the alarm setpoints (Section 6.8) AND the radwaste discharge pump high AND low flow setpoints (Section 6.10) .

~BTAiN the Background Count Rate for RIS-0-17 350 in counts per second (CPS) from the PRO AND CALCULATE RIS-O 17-350 uRad Waste Effluent" Monitor HI Trip AND HI HI Trip Settings using formulas below. (Calculations are in accordance with ODCM.)

~ CALCULATE Monitor Net CPS.

o. 532 x_6_____ 3.19 Well Counter Monitor Net CPS net cpm/mL c.cI.

o CALCULATE Gross CPS 50 + 3.19

- - - - - -::: 53.19 CT RIS-O-17-350 CPS Monitor Net CPS Gross CPS Background Count Rate c.rI.

CT

~ DETERH%NE log CPS from Gross cPS.

log ) = 1.73 c.rI.

Gross CPS log CPS CT

ST-C-095-805-2 Rev. 13 Page 10 of 27

~PERFORMANCB STEPS (Continued) Initial Sat unSat

~ CALCULATE Adjusted Log CPS 1.37 x 1.73 =--:...;;;..2.3~7_ _ __

Log CPS Adjusted Log CPS C/I.

CT

~ CALCULATE RIS-O 17-350 HI Trip

~ Setpoint AND RECORD results as Required RIS-O 17-350 HI Trip Value on Data Sheet 3. (ODCMS 3.8.B.3.C) 1.44 + 2.37 3.81

-Hi-Trip

- - Setting Adjustment Log CPS C/I.

CT CALCULATE RIS-0-17-350 HI HI Trip Setpoint AND RECORD results as Required RIS-0-17-350 HI HI Trip Value on Data Sheet 3. (ODCMS 3.8.B.3.C)

1. 47 + - -2.37 3.84

=- - - - - - - - -

Adjustment Log CPS Hi Hi Trip Setting C/I.

CT Chemistry Management computer programs may be used, AND is the preferred method, to perform the worker verification for the calculation of the values for the alarm setpoints (Section 6.8) AND the radwaste discharge pump high AND low flow set points (Section 6.10).

PERFORM a Worker Verification of calculations made in Section 6.8.

Any discrepancies between the results of section 6.8 AND the worker verification shall be resolved prior to the release of the affected tank. O/I.

CT

ST-C-095-S05-2 Rev. 13 Page 11 of 27

~ERFORMANCE STEPS (Continued) Initial Sat UnSat

~ALCULATE the Maximum Allowed Tank Release Rate

~; follows: (ODCMS 4.S.B.1.1)

~ OBTAIN position of Discharge Canal

~ To-Intake cross tie gate from the PRO AND CIRCLE the position (OPEN OR CLOSED) in Section 1.0 of Data C/I.

Sheet 2.

CT

~ Crosstie Gate is CLOSED, THEN

~PERFORM the following to complete Data Sheet 2 AND Data Sheet 3, OTHERWISE, N/A the spaces in this step.

~ORD "N/A" in spaces of

~~tion 2.0 of Data Sheet 2. C.~

CT

~AXH the Actual Number of Circ Pumps Operating from the PRO AND RECORD this number in Sections 3.0 AND 5.0 of Data Sheet 2 AND ENTER "1" for the "Required No. of Circ Pumps Operating" on Data Sheet 3. C/I.

CT

~ the Crosstie Gate is OPEN,

~;~EN PERFORM the following to complete Data Sheet 2 AND Data Sheet 3, OTHERWISE, N/A the spaces in this step.

~BTAIN the River-To-Intake

~ ~ond Differential Level Readings from the PRO AND RECORD in Section 2.0 of Data Sheet 2.

CT

ST-C-095 805-2 Rev. 13 Page 12 of 27

~ERFORMANCE STEPS (Continued) Initial Sat UnSat

~BTAIN the Actual Number of

~~irc Pumps Operating from the PRO AND RECORD in Section 3.0 of Data Sheet 2. Also RECORD "3" for the "Required No. of Circ. Pumps Operating" on Data Sheet 3. (A minimum of three circ pumps must be operating. )

CT

~Sing Section 4.0 of Data

~~~eet 2, DETERMINE the No. Of Circ. Pumps Providing Dilution AND RECORD this value in Section 5.0. 9{f51 CT

ST-C-095-805-2 Rev. 13 Page 13 of 27 DATA SHEET 2 CALCC'LATION OF NUMBER OF CIRC POMPS PROVIDING DILUTION (PRE-RELEASE DATA)

TANK TO BE DISCHARGE SOURCE: 11Jff CSAR No. 176 10 1.0 Discharge Canal-To-Intake POSITION: OPEN OR . \;L?S~D';>

cross tie gate (Circle current pu"' .............. u.u.)

Traveling Screens Outer Screens dL 2.0 RIVER-TO-INTAKE POND < At Control Room >

DIFFERENTIAL LEVEL READINGS DLI-2207 @ DLI-3207 @

consoM 20C007A Console 30C007A 1.9l 9{j.9l "H 2 O "H2 O 6

3.0 NUMBER OF CIRC POMPS OPERATING 4.0 USING THE CHART BELOW DETERMINE THE NUMBER OF PUMPS PROVIDING D:ILUTION FOR THIS RELEASE. TAD THE ACTUAL NUMBER OF C:IRC PUMPS OPERATING PROM SECTION 3.0 OF TB:IS DATA SHEET, READ DOWN THE COLUMN TO THE B:IGHEST D:IFFERENTl:AL LBVBL RECORDED IN SBCTION 2.0 OF THIS DATA SBBBT, MOVB ACROSS THE ROW AND Fl:ND THE NUMBER OF eIRC PUMPS PROVl:DING DILUTl:ON. l:F EITHER DLI-2207 OR DL:I-3207 ARE INOPERABLE, THEN TAD THE NUMBER OF Cl:RC PUMPS OPERATING PROM SBCTl:ON 3.0 AND SUBTRACT 2.

ACTUAL NUMBER OF CIRC PUMPS OPERATING No. OF CIRC PUMPS PROVIDING DILUTION 3 4 5 6 d LEVEL II

---

--- -- 0 1.8 5 WATER

- - -- 0 - 2.4 1.8 - 10 4

---

0 - 2.7 2.4 - 10 - -- 3 0 - 3.1 2.7 - 10 -- - --- 2 3.1 - 10 -- - ---- ---- 1 5.0 No. OF CIRC PUMPS PROVIDING DILUTION 6

ST-C-095-805-2 Rev. 13 Page 14 of 27

@ ~RMANCB: STEPS (Continued)

Sat Initial UnSat

~OBTAIN the Max Discharge Flow (gpm) from

~ ~he Gamma Isotopic Analys Report AND ENTER for maximum rate to discharge c.tI. .

canal on Data Sheet *4. ---

CT

~ALCULATE the High AND Low Flow Set Points as

~directed below: (Calculations are in accordance wi th the ODCM.)

XF the calculated value is greater than 100%, THEN RECORD 100% for the setting values.

~ DETElUtXNE Maximum Allowable discharge

~ settings as follows AND RECORD as "High Flow" AND "Low Flow" in applicable spaces on Data Sheet 4. (ODCMS 3.B.B.3c)

~igh Flow Discharge 1.2 X Max Release Rate 3DO GPM = 100  %

3.0 Setting efT.

CT

~ow Flow Discharge 1.2 X Max Release Rate 3DO GPM  %

0.15 Setting c.rI.

CT

ST-C-095-805-2 Rev. 13 Page 15 of 27

~ERFORMANCE STEPS (Continued) Initial Sat UnSat Chemistry Management approved computer programs may be used, AND is the preferred method, to perform the worker verification for the calculation of the values for the alarm setpoints (Section 6.8) AND the radwaste discharge pump high AND low flow set points (Section 6.10).

~ PERFORM a Worker Verification of calculations made in Section 6.10. Any discrepancies between the results of section 6.10 AND the worker verification shall be resolved prior to the release of the affected tanks. O/I.

CT

~REVIEW all CT responsible steps in Sections 6.1 through 6.10 for completeness, RECORD name AND initials in Section 10.0, Participants Record, SIGN cover sheet of this test at "Performed By:"

AND FORWARD this procedure to SMgt. c.rr.

CT

~gt Review AND Signature

, ~ VERIFY all CT steps to this point have

~ been Initialed AND completed Satisfactorily. S.!lvf.

SMgt

~ VERIFY, using an appropriate calculating

~ device, the calculations performed in Section 6.8 AND Section 6.10 by the CT are correct AND that the correct results have been recorded on Data Sheet 3 AND Data Sheet 4. S.!lvf.

~ VERIFY SMgt that the sample tank named on the

~ cover sheet of this test is intended to be released. S.!lvf.

~ GRANT SMgt Permission to operate HV-0-20C-144

~ "Waste Sample PP Disch To Pond" AND HV 0-20C-146 "Outer Block Valve for Waste Sample Tank Disch to River". OTHERWISE, N/A this step. S.!M. _ _

SMgt

ST-C-095-805-2 Rev. 13 Page 16 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat

~ VERIFY RIS-0-17-350 "Rad Waste

~ Effluent" Rad Monitor is operable.

(ODCMS 3.8.B. 3a)

• S.M.

SMgt CJ

~ VERIFY FS-0-20-493 "RWS Low Purity

~ Waste" High Flow Trip Set Pot AND associated Flow Control Valve are operable (This means that there are NO ETTs OR AIRs against this equipment).

(ODCMS 3.8.B.3c)

• S.M. CJ o RECORD name AND initials in Section SMgt S.M.

o 10.0, Participants Record.

SMgt FORWARD this test to the PRO. S.M.

SMgt DATA SHEET 3 TAN'K TO BE DISCHARGED SOURCE: ;FtJJ9I CSAR No. 176-10 PLANT SYSTEM REQUIRED PARAMETERS FOR LIQUID RADWASTE RELEASE REQUIRED VALUE Required No. of Circ. Pumps Operating 1 PUMPS Required RIS-0-17-350 HI Trip Setpoint POT 3.81 SETTING Required RIS-0-17-350 HI HI Trip Setpoint POT 3.84 SETTING

ST-C-095-S05-2 Rev. 13 Page 17 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat 6.13 PRO Review AND set-up of Plant in Preparation For Discharge 6.13.1 RECORD the Actual No. of Circ. Pumps Operating below AND VERIFY the Actual No. of Circ. Pumps Operating is greater than OR equal to the required No. of Circ. Pumps as recorded on Data Sheet 3.

(ODCMS 4.S.B.1.1)

Actual No. of Circ. Pumps Operating

-Cl PRO 6.13.2 SET RIS-O-17-350 HI Trip Setpoint to less than OR equal to Required value from Data Sheet 3 AND RECORD Actual Setpoint POT value below: (ODCMS 3.S.B.3.c)

Actual HI Trip Pot Setting

• -Cl PRO 6.13.3 SET RIS-O-17 350 HI HI Trip Setpoint to less than OR equal to Required value AND RECORD the Actual HI HI Setpoint Pot value below: (ODCMS 3.S.B.3.c)

Actual HI HI Trip Pot Setting PRO Cl 6.13.4 IF the discharge Canal-To-Intake Pond crosstie gate is OPEN, THEN VERIFY the following. OTHERWISE, NIA the spaces in this step.

1. Alarm Panel 204 Window F-4 "OUTER SCREEN STRUCTURE HI HI DIFF WTR LVL" is CLEAR.

PRO

2. Alarm Panel 304 Window F-4 "OUTER SCREEN STRUCTURE HI HI DIFF WTR LVL" is CLEAR.

PRO

ST-C-095-805-2 Rev. 13 Page 18 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat 6.13.5 REVIEW all PRO steps! to this point! in Section 6.13 for completeness.

PRO 6.13.6 RECORD name AND initials in Section 10.0, Participants Record, AND FORWARD this test to the Radwaste Operator (RWO) .

PRO DATA SHEET 4 TANK TO BE DISCHARGED SOURCE: !Ff})S'I CSAR No. 176-10 RADWASTE SYSTEM REQUIRED PARAMETERS PRIOR TO LIQUID RADWASTE RELEASE REQUIRED VALUE FS-0-20-493 "RWS Low Purity Waste" High Flow Trip Set Pot 100  %

FS-0-20-493 "RWS Low Purity Waste" Low Flow Trip Set Pot 100  %

MAXIMUM Release Rate to Discharge Canal 300 GPM 6.14 RWO ESTABLISHMENT OF RADWASTE DISCHARGE (At Radwaste Control Room Panel 00C077) 6.14.1 VERIFY tank to be discharged! as written in Section 1 of the coversheet, is the same tank intended to be released.

RWO CJ 6.14.2 VERIFY tank to be discharged has been processed through one OR more of these systems: Waste Collector Filter AND Demineralizer, Floor Drain Filter, Fuel Pool Filter Demineralizer, AND Chemical/Oily Waste Cleanup (EPICORE Oil/Water Emulsion), Laundry Drain Filter OR Projected Body Dose AND Projected Organ Dose for the Month have been recorded on Data Sheet 1.

(ODCMS 3.8.B.4)

• CJ

ST-C-095-805-2 Rev. 13 Page 19 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat RWO 6.14.3 SET FS-0-20-493 "RWS Low Purity Waste" High Flow Trip Set Pot to less than OR equal to Required Maximum % Setting for High Flow Discharge as found on Data Sheet 4 above, AND RECORD the Actual Setting below:

Actual FS-0-20-493 High Flow Trip Set Pot Setting

• -CJ RWO 6.14.4 SET FS-0-20-493 "RWS Low Purity Waste" Low Flow Trip Set Pot to less than OR equal to Required Maximum % Setting for Low Flow Discharge, as found on Data Sheet 4 above, AND RECORD the Actual Setting below:

Actual FS-O 20 493 Low Flow Trip Set Pot Setting

• -CJ RWO 6.14.5 RECORD RR-0-17-337 OR RIS-0-17-350 before Discharge CPS below:

CPS RWO 6.14.6 COMMENCE release of the sampled AND analyzed tank as follows:

6.14.6.1 If Sampled and analyzed tank was the Floor Drain Sample Tank, perform SO 20A.1.E and perform a concurrent verification RWO that AO-0-20-227/ "Floor Drain Sample Pumps Disch Valve to River" is opened CV in step 4.20. Otherwise, N/A this step.

ST-C-095-805-2 Rev. 13 Page 20 of 27 6.0 PBRFORMANCB STBPS (Continued) Initial Sat unSat 6.14.6.2 If Sampled and analyzed tank was the 'A' Waste Sample Tank, perform SO 20C.7.N and perform a concurrent verification RWO that AO-0-20 142A, "Discharge Valve for 'A' Waste Sample Pump" is opened CV in step 4.20. Otherwise, N/A this step.

6.14.6.3 If Sampled and analyzed tank was the 'B' Waste Sample Tank, perform SO 20C.7.N and perform a concurrent verification RWO that AO-0-20 142B, "Discharge Valve for

'B' Waste Sample Pump" CV in step 4.20. Otherwise, N/A this step.

6.14.6.4 If Sampled and analyzed tank was 'B' Laundry Drain Tank, perform SO 20B.7.A and perform a concurrent verification RWO that AO-O-20-191, "Laundry Dr Tk Pumps Disch to Laundry Drain Filter" is CV opened in step 4.3.11.

Otherwise, N/A this step.

ST-C-095-B05-2 Rev. 13 Page 21 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat NOTE

1. Portions of the following Section must be completed during the release.

2. IF the release is terminated early for lack of dilution flow, THEN it may only be restarted WHEN the original release conditions are re-established.

3. The following Steps may be repeated, as applicable, for each release start AND stop time.

4. The RIS-O-17-350 Trip Setpoints recorded on Data Sheet 3 correspond to 125% (HI) AND 135% (HI-HI) of the radiation monitor reading expected during the release. Typically, any appreciable change in the radiation monitor readings during the release is unusual AND should be reported to SMgt.

6.14.7 RECORD each release Start Time, Start Date, Stop Time, Stop Date, Start Tank

%, Stop Tank %, the FR-O-20-441 Flow (GPM) reading AND the RR-O-17-337 (CPS)

OR RIS-O-17-350 (CPS) as required in chart below: (N/A spaces NOT used.)

(ODCMS 4.B.B.2.1, 4.B.B.3.1, 4.B.B.3.2)

"'i~~",

~{:.. TIME DATE TANK LEVEL FR-O-20-441 RR-O-17-337 OR RIS-O-17-350 START  %

GPM CPS STOP  %

RWO CJ

ST-C-095-805-2 Rev. 13 Page 22 of 27 6.0 PERFORMANCE STEPS (Continued) Initial

-==_ UnSat TIME DATE TANK LEVEL FR-O-20 441 RR-O-17-337 OR

.', '., RIS-O-17-350 START  %

GPM CPS STOP  %

• I RWO 1<"<;r~J;:B~~~:s< TIME DATE TANK LEVEL FR-O-20-441 RR-O-17-337 OR

,. RIS-O-17-350 START  %

GPM CPS STOP  %

• I I RWO 6.14.8 RECORD below the actual maximum Release Rate GPM value from FR-O-20-441 observed during the release AND VERIFY the actual Release Rate is less than OR equal to the value recorded on Data Sheet 4.

(ODCMS 3.8.B.3.C)

Actual Maximum Release Rate FR-O-20 441 GPM * -Cl RWO 6.14.9 IF this release is NOT immediately followed by another discharge, THEN PERFORM the following post release steps. OTHERWISE, N/A these Steps.

1. RECORD RR-O 17 337 recorder CPS Reading BEFORE FLUSH.

___ CPS RWO

ST-C-095-805-2 Rev. 13 Page 23 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat

2. PERFORM SO 20C.5.B "Liquid Radwaste Discharge Radiation Monitor Flushing. "

RWO

3. RECORD RR-0-17 337 recorder CPS Reading after flush.

CPS RWO 6.14.10 IF a waste Sample Tank was Released, THEN PERFORM the following. OTHERWISE N/A these Steps:

1. CLOSE HV-0-20C 144 "Waste Sample PP DI SCH To Pond".

RWO

2. CLOSE HV-0-20C-146 "Outer Block Valve For Waste Sample Tank Disch To River" .

RWO 6.14.11 REVIEW all RWO Steps, to this step, in Section 6.14 for accuracy AND completeness.

RWO 6.14.12 RECORD name AND initials in Section 10.0, Participants Record, AND FORWARD this test to SMgt for review.

RWO 6.15 SMgt REVIEW OF OPERATIONS' PERFORMANCE AFTER DISCHARGE 6.15.1 REVIEW this test to this point for completeness paying attention to the Steps requiring PRO AND RWO data entry AND initials.

SMgt 6.15.2 SIGN coversheet of this test at "Revi ewed By: n SMgt 6.15.3 PLACE this test in the Chemistry bin located in the Main Control Room.

SMgt

ST-C-095-805-2 Rev. 13 Page 24 of 27 6.0 PERFORMANCE STEPS (Continued) Initial Sat UnSat 6.16 CHEMISTRY TECHNICIAN REVIEWER (CTR) COMPLETE THE TEST.

6.16.1 VERIFY sample Retained (approximately 1 Liter) for Monthly Radwaste Composite per ST-C-095-833-2, "P-32, FE-55, SR-89 and SR-90, and Tritium Analysis in Liquid Radwaste". (ODCMS Table 4.8.1)

CTR CJ NOTE AWST or BWST volume is 25488 gallons. FDST volume is 19844 gallons. BLDT volume is 1072 gallons.

6.16.2 USE data from this release, as applicable, to update OpenEMS records in the computer.

CTR 6.16.3 ENSURE all data for the applicable waste tank has been entered into the Chemistry Data Management System (DMS).

CTR 7.0 PROCEDURE COMPLETION Initial 7.1 Independent Verification None.

7.2 Records Completion 7.2.1 REVIEW all Sections of this test AND VERIFY these are complete.

CTR 7.2.2 VERIFY copy of the Gamma Isotopic Analysis Report attached to this test.

CTR 7.2.3 COMPLETE Section 2 of this test's coversheet by signing at "Completed By:" (AND Section 3 IF applicable)

AND FORWARD this test to Chemistry Supervision OR Staff for review.

CTR

~

ST-C-095-805-2 Rev. 13 Page 25 of 27

8.0 REFERENCES

8.1 Governing 8.1.1 ODCMS 3.8.B.3 8.1. 2 ODCMS 3.8.B.4 8.1. 3 ODCMS 4.8.B.1.1 8.1. 4 ODCMS 4.8.B.1.2 8.1.5 ODCMS 4.8.B.1.3 8.1. 6 ODCMS 4.8.B.3.1 8.1.7 ODCMS 4.8.B.3.2 8.1.8 ODCMS Table 4.8.B.1 8.1.9 ODCMS 4.8.B.4.3 8.1.10 ODCMS 4.2.B.4.4 8.1.11 ODCMS 4.8.B.4.5 8.1.12 ODCMS Bases B 3.8 8.1.13 CM-1, Licensed Event Report 2-91-036 8.1.14 CM-21 NRC Inspection Report Doc No. 76070103 8.2 Interfacing 8.2.1 PBAPS Offsite Dose Calculation Manual (ODCM) 8.2.2 CY-PB-120-4011 Liquid Radioactive Waste 8.2.3 ST-C-095-833 2, P-32, FE-55, SR-89 and 90, and Tritium Analysis in Liquid Radwaste 8.2.4 SO 20A.1.El Floor Drain Sample Tank Release to the Conowingo Pond 8.2.5 SO 20C.7.N, Waste Sample Tank Release to Conowingo Pond 8.2.6 SO 20B.7.A Laundry Drain Tank Release to Conowingo Pond 8.2.7 RW-PB-591 1 Transfer of Processed Waste Water to the "B" Laundry Drain Tank 8.2.8 RW-PB-592, Transfer of Unprocessed Waste Water to the "B" Laundry Drain Tank

ST-C-095-805-2 Rev. 13 Page 26 of 27

8.0 REFERENCES

(Continued) 8.2.9 SO 20C.5.B, Liquid Radwaste Discharge Radiation Monitor Flushing 8.3 Developmental 8.3.1 CH-600, Determination of Gamma Isotopic Activity with the Canberra Gamma Spectrometers 8.3.2 10 CFR 20 Appendix B, Table 2, Column 2 8.3.3 10 CFR 50 8.3.4 LS-AA-I04, "Exelon 50.59 Review Process" 8.3.5 NPDES Permit No. PA0009733 8.3.6 UFSAR Section 9.2.4.2.4 8.3.7 UFSAR Section 9.2.4.3 8.3.8 UFSAR Section 9.2.5 8.3.9 UFSAR Section 9.2.7 8.3.10 Prints E-540-55, Sht.l, Console 20C007A Condensate Enhancement Arrangement M-370, Shts. 1, 2, & 3, Radwaste Process & Disposal System-Liquid M-371, Sht 5, Radwaste Process and Disposal-Solid 9.0 ODCMS LIMITING CONDITIONS FOR OPERATION (LCOs)

Section 3.8.B

ST-C-095-805-2 Rev. 13 Page 27 of 27 10.0 PARTICIPANTS RECORD Printed Name Initial.s cliem tIec/i C/I.

Otlier tIec/i O/I. i Shift :Manager S.:M. I i

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET D QUALIFICATION MANUAL D OJT MODULE LICENSED OPERATOR TRAINING PLOR-351C CENSED OPERATOR REQUALIFICATION 000 J. A. Verbillis jav Take Actions for Accidents Involving the Transportation of Radioactive Material APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _--' _ _ _-' _ _ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR351C RevOOO.doc Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK-JPM DESIGNATOR: 2991880102 PLOR 351 C KIA: G 2.1.18 SRO: 3.8 TASK DESCRIPTION: Take Actions for Accidents Involving the Transportation of Radioactive Material A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR351 C RevOOO.doc Page 2 of 5

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. OP-AA-1 06-1 02, Rev 4 "Accidents Involving the Transportation of Rad Materials" D. TASK STANDARD

1. Satisfactory task completion is indicated when the candidate has correctly identified the MINIMUM required notifications based on conditions provided.

2. Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to complete Attachment 1 of OP-AA 106-102 and identify the minimum required notifications for the accident/incident using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. A phone notification has been received regarding a Transportation event involving a shipment of Radioactive Materials which originated at the station.

2. The shipper's vehicle inadvertently forced a Maryland resident's vehicle to exit the highway at high speed, where upon the resident's vehicle impacted a large tree.

3. The Maryland resident was transported to the Upper Chesapeake Regional Hospital with life-threatening injuries sustained when their vehicle impacted the tree.

4. NO damage to the shipper's vehicle.

5. NO damage to the Radioactive material in transient.

6. Detailed notes have been recorded by the Shift Manager from which you are to complete Attachment 1 of OP-AA-1 06-1 02.

7. The Shift Manager will complete the required notifications for an Event of Potential Public Interest.

PLOR351 C RevOOO.doc Page 3 of 5

G. INITIATING CUE The Shift Manager provides you with the detailed notes and directs you to (1) complete Attachment 1 of OP-AA-1 06-102, (2) determine if the event is a Transportation Accident or Incident, and (3) identify the MINIMUM required notifications required by OP-AA-1 06-1 02. In addition to completing Attachment 1, document your determinations on the CUE SHEET provided unless otherwise specified by your evaluator.

PLOR351C RevOOO.doc Page 4 of 5

H. PERFORMANCE CHECKLIST

" STEP STEP ACT STANDARD NO 1 Use the provided notes to complete OP P Candidate completes OP-AA-1 06-1 02 AA-1 06-1 02 Attachment 1. Attachment 1. Refer to JPM Att 2 for an example.

• 2 Determine that the situation is a P Candidate determines event to be TRANSPORTATION INCIDENT. TRANSPORTATION INCIDENT based on OP-AA-1 06-1 02 Para 2.2.

• 3 Determine that the Duty Station Manager P Candidate determines Station Duty is to be NOTIFIED. Manager notification required by OP-AA 106-102 Para 4.3.1 .

• 4 Determine that the Nuclear Duty Officer is P Candidate determines NDO notification to be NOTI FI ED. required by OP-AA-1 06-1 02 Para 4.3.2.

• 5 Determine that the Station Radiation P Candidate determines RPM or designee Protection Manager or designee is to be notification required by OP-AA-1 06-1 02 NOTIFIED. Para 4.3.3.

• • • NOTE to EVALUATOR ***

Candidate may engage in discussion/speculation re: Exelon Nuclear Response Team. If so, inform candidate that this is NOT required. Likewise, notification of agencies listed in Attachment 2 is NOT REQUIRED. IF candidate identifies that the additional notifications are REQUIRED, this should be critiqued as being ABOVE THE MINIMUM.

6 Determine that the Station AND P Candidate determines Station AND Corporate Communications Departments Corporate Communications Departments are to be NOTI FI ED. are to be NOTIFIED as indicated in OP AA-1 06-1 02 Para 4.3.5.1.

Note that this is NOT a critical step, as the procedure indicates that a response maybe required.

7 As an evaluator, ensure you have positive P Positive control established.

control of all exam material provided to the examinee (Task Conditions /

Prerequisites) AND procedures AND any Data Sheets or scrap paper used for calculations.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the required notifications have been determined and documented, the evaluator will terminate the exercise.

PLOR351 C RevOOO.doc Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. A phone notification has been received regarding a Transportation event involving a shipment of Radioactive Materials which originated at the station.

2. The shipper's vehicle inadvertently forced a Maryland resident's vehicle to exit the highway at high speed, where upon the resident's vehicle impacted a large tree.

3. The Maryland resident was transported to the Upper Chesapeake Regional Hospital with life-threatening injuries sustained when their vehicle impacted the tree.

4. NO damage to the shipper's vehicle.

5. NO damage to the radioactive material in transient.

6. Detailed notes have been recorded by the Shift Manager from which you are to complete Attachment 1 of OP-AA-1 06-1 02.

7. The Shift Manager will complete the required notifications for an Event of Potential Public Interest.

INITIATING CUE The Shift Manager provides you with the detailed notes and directs you to (1) complete Attachment 1 of OP-AA-1 06-1 02, (2) determine if the event is a Transportation Accident or Incident, and (3) identify the MINIMUM required notifications required by OP AA-106-102. In addition to completing Attachment 1, document your determinations on the CUE SHEET provided unless otherwise specified by your evaluator.

Document Here:

YOURNAME: ________________________

(1) Circle: ACCIDENT or INCIDENT (2) REQUIRED Notifications:

The following information was relayed by Tom Hall, calling from the ChemTrec Emergency Center (1300 Wilson Blvd. Arlington Va. (800) 2628200). Call was received today at 10:15 AM.

There has been a transportation event involving a truck that is transporting Hazardous Material (Low-level Radioactive Waste) from the Peach Bottom APS.

The event occurred today at 08:15 AM in the town of Bel Air, Maryland (Harford County) near the intersection of Rt 1 Bypass and Business Rt 1.

The event involves a Transport Truck and a passenger car. There is serious injury to the driver of the car, who has been transported by the Bel Air Volunteer Fire Company to the Upper Chesapeake Regional Hospital in Bel Air. The injuries are life-threatening, and the individual is not expected to survive. The individual was NOT contaminated with radioactive material. The driver of the truck is uninjured.

The accident occurred when the truck slid sideways due to road conditions, and bumped the car, which then exited the highway at a high rate of speed and hit a tree. The driver of the automobile was ejected from the car. The driver of the truck immediately stopped to render aide and call 9-1-1. There was no damage to the truck or the materials being shipped. The truck and driver are still on the scene at the request of the local authorities.

Weather conditions at the time of the accident were light snow and 32 OF air temperature.

First responders were the Bel Air Volunteer Fire Company and the Harford County Sheriff's Department; the Maryland State Police are now also on the scene.

Particulars about the shipment include:

Exelon Nuclear Shipment Number is PW-1O-456.

This is NOT a RAMQC shipment.

The material is Low Level RAM Waste The UN ID number is UN-3321.

There was NO damage to the shipment.

There was NO release of radioactivity.

There was NO impact to any member of the public in any way associated with the shipment.

OP-AA-106-102 Revision 4 Attachment 1 Transportation Accident I Incident Notification Form Page 1 of 2 Date I Time Of This Call. Current 'lJate / 'lime = 1015 Date I Time of the Event. Current 'lJate / 'lime = 0815 Name of Caller. Tom:Jla((

Company Name and Address Of Caller.

Telephone Number Of Caller (On Exelon Nuclear Shipment Number.

Is this a RAMQC Shipment Incident Location.

(As specific as possible, including State, County, Road, Intersection)

If in Illinois and if known:

Section Townshi Vehicles Involved.

or YES D or NOX YES D or NOX YES D or NOX YES D or POTENTIAL 0 or NO X

OP-AA-1 06-1 02 Revision 4 Attachment 1 Transportation Accident I Incident Notification Form Page 2 of 2 Has An Evacuation Of The General YES D or POTENTIAL D or NO X Public Lasting One Or More hours Occurred?

Has the Flight Pattern Of An Aircraft YES D or POTENTIAL Been Altered?

Were Package(s) Impacted By Fire?

YES D or

. (Package defined on Radioactive

. Shi ment Notification Form Was there a Loss of Package(s)

YESD Integrity?

If YES, then does the potential exist for a s read of contamination?

NOTE: If ALL of the abov then a trans Name of Emergency Contacted Or At the

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET I X I Peach Bottom I DI Limerick DII Common I

~ JPM D QUALIFICATION MANUAL D OJT MODULE LICENSED OPERATOR TRAINING PLOR-263C LICENSED OPERATOR REQUALIFICATION 002 M. J. Kelly jav Determine Electrical Safety Personal Protective Equipment for Racking Out a 4kV Circuit Breaker APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: ____-' ___---' _ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE ID#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR263C Rev002.doc Page 1 of 5

EXELON NUCLEAR PEACH BOnOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK-JPM DESIGNATOR: 2991780301 I PLOR-263C KIA: 2.1.26 SRO: 3.6 TASK DESCRIPTION: Knowledge of industrial safety procedures (such as rotating equipment.

electrical. high temperature. high pressure. caustic, chlorine. oxygen and hydrogen).

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR263C Rev002.doc Page 2 of 5

B. TOOLS AND EQUIPMENT

1. SA-AA-129 "Electrical Safety" C. REFERENCES

1. SA-AA-129, Rev. 7, "Electrical Safety" D. TASK STANDARD

1. Satisfactory task completion is indicated when the minimum required Electrical Safety personal protective equipment (PPE) has been determined for racking out a 4kV breaker using SA-AA-129 "Electrical Safety".

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to determine the minimum required Electrical Safety personal protective equipment (PPE) using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES The breaker for the 2A CRD pump needs to be racked out at the E12 switchgear.

G. INITIATING CUE As the Work Execution Control Supervisor, determine the MINIMUM Electrical Safety personal protective equipment (PPE) required for racking out the 2A CRD pump breaker from the E12 switchgear using SA-AA-129 "Electrical Safety". Document your determination on the CUE SHEET.

PLOR263C RevO02.doc Page 3 of 5

H. PERFORMANCE CHECKLIST

" STEP NO STEP ACT STANDARD 1 Review SA-AA-129 "Electrical Safety". P Reviews SA-AA-129 "Electrical Safety".

(Cue: Hand the Examinee a copy of SA References AITACHMENT 4 - Electrical AA-129 "Electrical Safety".) Safe Work Practices Hazard Assessment.

• 2 Determine that Class 3 clothing is P Uses AITACHMENT 4 - Electrical Safe required. Work Practices Hazard Assessment, of SA-AA-129, Item 3, for racking in/out a (Cue: NlA) 4KV switchgear breaker.

• 3 Determine that eye protection is required. P Same as Step 2, above (Cue: N/A)

• 4 Determine that flash hood is required. P Same as Step 2, above (Cue: N/A)

• 5 Determine that a face shield is required. P Same as Step 2, above (Cue: N/A)

• 6 Determine that a hard hat is required. P Same as Step 2, above (Cue: N/A)

• 7 Determine that Class 1 Gloves with Glove P SA-AA-129, step 4.1.6 Protectors are required.

(Cue: N/A) 8 Inform evaluator of completion of the P Communicate that the task has been task. completed.

9 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate PLOR263C Rev002.doc Page 4 of 5

I. TERMINATING CUE When the minimum Electrical Safety personal protective equipment (PPE) for racking out a 4kV breaker using SA-AA-129 "Electrical Safety" has been determined, the evaluator will then terminate the exercise.

PLOR263C RevO02.doc Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. The breaker for the 2A CRD pump needs to be racked out at the E12 switchgear.

INITIATING CUE As the Work Execution Control Supervisor, determine the MINIMUM Electrical Safety personal protective equipment (PPE) required for racking out the 2A CRD pump breaker from the E12 switchgear using SA-AA-129 IIElectrical Safetyll. Document your determination on this CUE SHEET.

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET each Bottom Limerick Common QUALIFICATION MANUAL OJT MODULE PLOR-221C LICENSED OPERATOR REQUALIFICATION 001 jay Determine Technical Specification Action, Make Manual Log Entry APPROVALS:

Signature Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature J Title Date EFFECTIVE DATE: _ _~/_ _---,I_ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 10#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR221 C RevOO1.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK-JPM DESIGNATOR: 34101703021 PLOR 221C KIA: 2.2.23 SRO: 4.6 TASK DESCRIPTION: Determine Required Actions and/or Compensatory Measures Related to Tech Spec or TRM Conditions, ODeM A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from

'functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR221 C Rev001.doc Page 2 of 6

B. TOOLS AND EQUIPMENT

1. AT4, Blank Technical Specification Action Log (OP-PB-1 08-1 04, At 1).

2. AT2, Simulated IR for Conditions in JPM C. REFERENCES

1. Technical Specification 3.1.7, Amend 277, II Stand by Liquid Control (SLC) System ll

2. OP-PB-1 08-1 04, Rev 1 "Regulatory Compliance Action Logs" D. TASK STANDARD

1. Satisfactory task completion is indicated when the Technical Specification Action Log entries have been completed.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to be taken for information obtained from the chemistry department, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is operating at rated power.

2. A Chemistry Tech has just reported that a sample on the Unit 2 Standby Liquid Control Tank shows the concentration of boron in solution at 9.84% weight and a temperature of 72 deg. F.

3. Chemistry has initiated IR# 1127359.

4. All other Tech Spec plant equipment is operable.

5. The Unified Control Room Log Computer is not operating.

6. The next sequential TSA number is "009."

G. INITIATING CUE The Control Room Supervisor directs you to determine the impact of this condition and make a manual Tech Spec Action Log entry, if required. Submit any required forms to the Shift Manager for review.

PLOR221 C Rev001.doc Page 3 of 6

H. PERFORMANCE CHECKLIST II STEP NO STEP ACT STANDARD 1 Obtain a copy of Tech Specs. P A copy of Tech Specs is obtained.

• 2 Determine the Tech Spec action. P Review Tech Spec 3.1.7 and determine that Condition 'A' applies:

• A solution >9.82% weight requires verifying the concentration and temperature of the boron and pump suction piping temperature on figure 3.1 .7-1 within 8 hrs and once per 12 hrs thereafter.

• Review figure 3.1 .7-1 and determine concentration and temperature plot "Acceptable".

• Restore concentration of boron in solution to <9.82% weight within 72 hrs.

• • • NOTES TO EVALUATOR ***

(1) AT4, a blank copy of OP-PB-108-104 At 1 may be provided (2) AT3 is a "key" to the standards for Step 3 below (3) In Step 3 below, accurate completion of blocks marked with * (TS Number, Condition, Required Action, Completion time) are the critical components of the critical step. Failure to accurately transcribe into those blocks will result in failure of the critical step. Failure to accurately transcribe into other blocks should be critiqued but do NOT constitute failure of the critical step.

• 3 Complete Tech Spec Action Log. P USing OP-PB-1 08-1 04, At 1, complete the following TSA Log data entries:

Unit - "unit experiencing inoperability"

• Unit - Unit 2

• Entry # - sequential number consisting

• Entry # "11 009" of year, unit and sequential TSA #

• Tech Spec Number - "Tech Spec Tech Spec # - "3.1.7" - CRITICAL number for inoperability" (CUE: IF asked to perform Independent Candidate should address the IV process, Verification (IV), STATE "For purpose as this is required by PB process.

of evaluation, IV will NOT be performed")

II *3

• Discovery DatelTime - "date and time

• Discovery date/time - today's PLOR221 C Rev001.doc Page 4 of 6

STEP NO STEP ACT STANDARD (cont) inoperability discovered" date/time of notification

• Equipment 10 - "alpha-numeric

• Equipment 10 - 20T18 designator for inop equipmenf'

• System Number - "system number for

• System # - "11" equipment inop" P

• Reference # - "AR number associated

• Reference # - IR 1127359 with the INOP feature"

'*

• Condition - "applicable Tech Spec

• Condition - "A", Concentration of condition letter and condition boron in solution >9.82% weight.

statement" (Required to be verbatim) - CRITICAL (CUE: IF asked, report that NO related Safety Function Determinations

• SFD Required? NO currently active.)

• Reason - "short reason system is Reason - concentration of boron in inop" solution >9.82% weight.

• Required Action 1 - "Applicable

• Required Action 1 - Verify the required action statement" concentration and tempertur4e of boron in solution and pump suction piping temperatures are within the limits of Figure 3.1.7-1 (Required to be verbatim) - CRITICAL

• Completion Time OatelTime - "Date

• 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> - CRITICAL and time for required action to be completed"

'*

• Required Action 2 - "Applicable

• Required Action 2 - Restore required action statement" concentration of boron in solution

<9.82% weight. (Required to be verbatim) - CRITICAL

• Completion Time DatelTime - "Date

• 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s- CRITICAL and time for required action to be completed" PLOR221 C Rev001.doc Page 5 of 6

STEP NO STEP ACT STANDARD 4 Submit the completed form. P Submit the completed Tech Spec Action Log to the Shift Manager for review.

(Cue: Acknowledge receipt of the completed Tech Spec Action Log. IF candidate makes reference to OP-PB 108-104 Attachment 5, inform them that that Attachment will be completed when and if needed) 5 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the Tech Spec Action Log has been completed and submitted to the Shift Manager, the evaluator will then terminate the exercise.

PLOR221 C Rev001.doc Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Unit 2 is operating at rated power.

2. A Chemistry Tech has just reported that a sample on the Unit 2 Standby Liquid Control Tank shows the concentration of boron in solution at 9.84% weight and a temperature of 72 deg. F.

3. Chemistry has initiated IR# 1127359.

4. All other Tech Spec plant equipment is operable.

5. The Unified Control Room Log Computer is not operating.

6. The next sequential TSA number is "009.".

INITIATING CUE The Control Room Supervisor directs you to determine the impact of this condition and make a manual Tech Spec Action Log entry, if required.

Submit any required forms to the Shift Manager for review.

AR 1127359 Report Aft Fac: Peach Bottom ARType: CR Status: INIT Aft Unit: 02 Owed To: ACAPALL Due Date:

Aft System: 11 Event Date: 1/30/2011 CR Disc Date: 1/30/2011 Level/Class:

How H02 Orig Date: 1/30/2011 Discovered:

WRIPIMS Component SYSTEM Component - 20T18 AR: #:

... ' / ...... .

Action Requesf Details* .... .

Subiect: Unit 2 SBLC Tank Boron Concentration

==

Description:==

Originator: Shift Chemist Supv Contacted: YOUR NAME HERE Condition

Description:

Unit 2 SBLC Tank Boron Concentration is 9.84% weight with a temperature of 72 Degrees Fahrenheit.

Immediate actions taken: Notified SSV.

Recommended Actions:

Operable Basis:

Reportable Basis:

Reviewed by:

Reviewer Comments:

Reviewed by:

Reviewer Comments:

Reviewed by:

Reviewer Comments:

SOC Reviewed by:

SOC Comments:

OP-PB-108-104 ANSWER KEY - DO NOT HAND OUT Revision 1 Page 15 of 23 ATTACHMENT 1 TECHNICAL SPECIFICATION ACTION UNIT -l- (2 OR 3)

PAGE 1 of 1 Entry Made: Equipment ID Reference #

By Catufitfate 2fJll8 19{# 1127359

• n Discovery DatelTime IV _ _ __

lJ'oQO!/s 'Date/Current tTtme Condition Required Action 1 J.t Concentration of Eoron in solution >9.82% ron Concentration is 9.84% I 1lerifiJ tfie concentration amitemperature of Eoron in solution amipump suction piping

'Uleigfit.

temperatures are 'Ulitliin tfie Omits of!FilJure 3.1.7-1 Is a SFD required? YESO Are any other SFDs curre~actiVe? Completion Time DatelTime 8 !JloursJ from (If YES, verify SFD is still valid.) Current'Datefftme Required Action 2 Required Action 3

!/(&store concentration of 'n to .5 9.82% weigfit.

Completion Time DatelTime Completion Time Dati ~ !}[ours {3 'Days)from Current

'Date/Current Jfour I

Exit DatelTime Exit Entries Made:

By _ _ _ __

IV

OP-PB-1 08-1 04 Revision 1 Page 15 of 23 ATTACHMENT 1 TECHNICAL SPECIFICATION ACTION LOG UNIT _ (2 OR 3)

PAGE 1 of 1 Entry # II TS# Entry Made: Equipment ID System # Reference #

8y _ _ __

~========~nb=======91IV Discovery Dateffime ---

Condition Reason Required Action 1 Is a SFD required? YES / NO Are any other SFDs currently active? YES I NO (If YES, verify SFD is still valid.) Completion Time Dateffime I

Required Action 2 Required Action 3 Completion Time Dateffime / Completion Time Dateffime I Exit Justification Exit Dateffime Exit Entries Made:

8y _ _ _ __

IV

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET m each Bottom DII Limerick ~ 011 Common ~

~ JPM D QUALIFICATION MANUAL D O*.IT MODULE LICENSED OPERATOR TRAINING LICENSED OPERATOR REQUALIFICATION 001 M. J. Kelly jav Review And Authorize An Emergency Exposure APPROVALS:

Signature I Title Date Signature / TItle Date Signature I Title Date Signature I TItle Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _--'1_ _-----'1_ __

NAME: ____________________________ ISSUE DATE: _ _ _ _ _ _ _ _ __

Last First M.I.

EMPLOYEE 10#: COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR249C Rev001.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK*JPM DESIGNATOR: 2007550502/ PLOR*249C KIA: G2.3.4 SRO: 3.7 TASK DESCRIPTION: EMERGENCY RADIATION EXPOSURE GUIDELINES AND CONTROLS A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR249C Rev001.doc Page 2 of 6

B. TOOLS AND EQUIPMENT

1. EP-AA-113, Rev. 10 "Personnel Protective Actions"

2. Attachment 2, Authorization for Emergency Exposure Forms completed for Worker One and Worker Two with the exception of the Station Emergency Director authorization.

3. Worker One and Worker Two history descriptions.

C. REFERENCES

1. EP-AA-113, Rev. 10 "Personnel Protective Actions"

2. EP-AA-113-F-02, Rev. B "Authorization of Emergency Exposure" D. TASK STANDARD

1. Satisfactory completion of this task is indicated when the Emergency Director has reviewed the worker histories, Authorization for Emergency Exposure Forms, and made decisions on the Emergency Exposure Requests.

2. Estimated time to complete: 20 minutes. (Not time-critical)

E. DIRECTIONS TO EXAMINEE When given the initiating cue, review the worker histories and Authorization for Emergency Exposure Forms and make the decision as to whether to authorize the Emergency Exposure.

I will describe the initial conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Peach Bottom is experiencing a major plant transient.

2. A General Emergency has been declared.

3. It is necessary for two specially trained individuals to enter an area with extremely high radiation levels (> 520 Rem/hour) to prevent a major release tl1at would cause significant radiation sickness to the general public in the area. The release would also result in long-term somatic and genetic effects for the public. It is estimated that each worker will receive 30 Rem of dose.

4. Only two individuals at Peach Bottom have the required training and experience to be successful in preventing the release.

5. Worker One and Worker Two are available and have volunteered for the assignment.

6. EP-AA-113-F-02, Authorization for Emergency Exposure Form, has been completed for both individuals and require Emergency Director review and authorization.

PLOR249C RevO01.doc Page 3 of 6

7. A description of each worker's history has been attached to the Emergency Authorization Forms.

G. INITIATING CUE As the Emergency Director, review the workers histories and Authorization for Emergency Exposure Forms (EP-AA-113-F-02) for authorization using procedure EP-AA-113 "Personnel Protective Actions". Document your decisions in the space provided on the worker history sheet.

PLOR249C Rev001.doc Page 4 of 6

H. PERFORMANCE CHECKLIST II STEP STEP ACT STANDARD NO NOTES:

The following steps may be done in a different order as long as all steps are completed prior to signing STATION EMERGENCY DIRECTOR (Authorization) on the Authorization for Emergency Exposure Form (EP-AA-113-F-02).

1 Locate the correct section of EP-AA-113, P The operator references section 4.3 of Personnel Protective Actions. EP-AA-113.

2 Evaluate the task to determine if it is P Determine that the task has an worthy of authorizing Emergency acceptable basis to authorize necessary Exposure. emergency exposure. May reference EP-AA-113, Attachment 1, Emergency Worker Exposure Limits and Associated Risks.

3 Evaluate Worker One's Authorization for P Review Worker One's Authorization for Emergency Exposure Form. Emergency Exposure Form and note that it is completed correctly and signed by Worker One and Rad. Protection Management.

4 Evaluate Worker One's History. P Review Worker One's History and determine that it is acceptable for Worker One to receive the Emergency Exposure.

• 5 Authorize Worker One to receive the P Indicate the authorization for Emergency Emergency Exposure. Exposure by signing the Station Emergency Director signature block on the Emergency Exposure Authorization Form.

6 Evaluate Worker Two's Authorization for P Review Worker Two's Authorization for Emergency Exposure Form. Emergency Exposure Form and note that it is completed correctly and signed by Worker Two and Rad. Protection Management.

• 7 Evaluate Worker Two's History. P Review Worker Two's History and recognize that he has received an Emergency Exposure in the past.

PLOR249C .RevO01.doc Page 5 of 6

STEP STEP ACT STANDARD NO

• 8 Do NOT authorize Worker Two to receive P Determine that since Worker Two has the Emergency Exposure. previously received an Emergency Exposure, he is not permitted to receive another Emergency Exposure. This is based on the CAUTION in EP-AA-113 just after Step 4.3.3 which states that "All Emergency Exposures in excess of 25 Rem TEDE shall be voluntary and shall be limited to once in a lifetime."

The Examinee must NOT sign Worker Two's Emergency Exposure Form (EP AA-113-F-02).

9 Inform the evaluator of the results of his P The Examinee informs the evaluator that reviews. Worker One may be authorized to perform the task, but that Worker Two is NOT eligible for the Emergency Exposure.

10 As an evaluator, ensure that you have P Positive Control Established.

positive control of all exam material provided to the examinees (Task Conditions/Prerequisites, Worker II Histories, and procedure copies.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE:

When the Emergency Exposure Authorization Review is complete, the Examinee will inform the Evaluator and the exercise will be terminated.

PLOR249C Rev001.doc Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Peach Bottom is experiencing a major plant transient.

2. A General Emergency has been declared.

3. It is necessary for two specially trained individuals to enter an area with extremely high radiation levels (>520 Rem/hour) to prevent a major release that would cause significant radiation sickness to the general public in the area. The release would also result in long-term somatic and genetic effects for the public. It is estimated that each worker will receive 30 Rem of dose.

4. Only two individuals at Peach Bottom have the required training and experience to be successful in preventing the release.

5. Worker One and Worker Two are available and have volunteered for the assignment.

6. EP-AA-113-F-02, Authorization for Emergency Exposure Form, has been completed for both individuals and require Emergency Director review and authorization.

7. A description of each worker's history has been attached to the Emergency Authorization Forms.

INITIATING CUE As the Emergency Director, review the workers histories and Authorization for Emergency Exposure Forms (EP-AA-113-F-02) for authorization using procedure EP-AA-113 "Personnel Protective Actions". Document your decisions in the space provided on the worker history sheet.

WORKER ONE HISTORY

• Worker One is a 33 year old male.

• He is in generally good health.

• Current Annual Exposure is 1765 mRem.

• Lifetime Occupational Exposure is 29,632 mRem.

• Worker One has never exceeded Station Administrative Limits.

Worker One (Circle one, IF Denied, then document basis)

Approved Denied Basis for Denial, If applicable:

WORKER TWO HISTORY

• Worker Two is a 48 year old male.

• He is in very good health.

• Current Annual Exposure is 112 mRem.

• Lifetime Occupational Exposure is 28,564 mRem.

• On June 5, 1997, Worker Two received 25,388 mRem while saving a coworker's life.

Worker Two (Circle one, IF Denied, then document basis)

Approved Denied Basis for Denial, If applicable:

Exelon~

EP-AA-113-F-02 Revision B Page 1 of 2 Nuclear AUTHORIZATION FOR EMERGENCY EXPOSURE Name: _ _ _W~o;.:..:rk=e:.:..r...::::O~n=e_ _ _ _ _ _ Date I Time: To/Day/2011 10:00 Employee 10 Number: _ _....!.1=23~4;:..::5::.::6:...-..___ Current Annual Exposure: 1765 mRem Reason For Request:

To complete a task for which he is uniquely quamied that will prevent a major radiological release that would cause radiation sickness and long-term somatic and genetic effects to the General Public.

REQUESTING AUTHORIZATION TO EXCEED:

o 5 RemTEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) o 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)

Wor!(erOne Today/ 10 mins. ago

• Emergency Worker Signature Date/Time

• Emergency Worker Exposure Lim its and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.

{Bad. P. %anagement Today I 5 mins.ago _ _

Rad. Protection Management (Review) Date /Time

1. Station Emergency Director (Authorization) Date/Time

1. The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.

Document Retention SRRS ID - 58.100

Exelon~

EP-AA-113-F-02 Revision B Page 2 of 2 Nuclear AUTHORIZATION FOR EMERGENCY EXPOSURE Name: _ _--,;W~o!..!.:rk~e!....rT.!...:w:.!.:o::l:.--_ _ _ _ _ _ Date I Time: Tol DaY! 2011 10:05 Employee ID Number: _ _-=2:::!.34..!.:!5~6~7_ _ _ _ Current Annual Exposure: 112 mRem Reason For Request:

To complete a task for which he is uniguely gualified that will prevent a major radiological release that would cause radiation sickness and long-term somatic and genetic effects to the General Public.

REQUESTING AUTHORIZATION TO EXCEED:

o 5 RemTEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) o 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE)

!:8l 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)

Wort(erTwo Today I 10 mins. ago

• Emergency Worker Signature Date I Time

• Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.

!R.aa. P. Management Today I 5 mins. ago _ _

Rad. Protection Management (Review) Date I Time

1. Station Emergency Director (Authorization) Date/Time

1. The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.

Document Retention SRRS ID - 58.100

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET each Bottom ~ Limerick I Common QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR REQUALIFICATION 002 jay EAL CLASSIFICATION WITH STATE AND LOCAL NOTIFICATIONS (FU1, wind from 265 degrees, airborne release not in progress)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _---' _ _---' _ __

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date II PLOR232C Rev002.doc Page 1 of 7

EXELON NUCLEAR PEACH BOnOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator TASK-JPM DESIGNATOR: 20075405021 PLOR-232C KIA: 2.4.41 SRO: 4.6 TASK DESCRIPTION: Emergency Director A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical ..IPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR232C RevO02.doc Page 2 of 7

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. EP-AA-112-100, Rev. 10, "Control Room Operations"

2. EP-AA-111, Rev. 16, "Emergency Classification and Protective Action Recommendations"

3. EP-MA-114-100, Rev. 14, "Mid-Atlantic State/Local Notifications"

4. EP-MA-114-100-F-01, Rev I, "State/Local Notification Form"

5. EP-AA-112-100-F-01, Rev. L, "Shift Emergency Director Checklist"

6. EP-AA-1007, Table PBAPS 3-1, Rev. 19, "Emergency Action Level (EAL) Matrix"

7. EP-AA-114-F-01, Rev. D, "Release in Progress Determination Guidance" D. TASK STANDARD

1. Performance Location: Simulator

2. Satisfactory task completion is indicated when EP-MA-114-100-F-01, "State/Local Event Notification Form" has been completed accurately.

(NOTE: The criteria for accurate Event Notification form completion was derived from EP-AA-125-1002, Rev. 006, "ERO Performance - Performance Indicators Guidance".)

3. Estimated time to complete: TIME CRITICAL

• Event Classification: 15 minutes

• State/Local Notification Form: 13 minutes E. DIRECTIONS TO EXAMINEE When given the initiating cue, make the Emergency Classification and complete the State/Local Notifications (if required). I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 was at 100% power when a steam leak was reported in the Outboard MSIV room.

2. A Main Steam Line (MSL) HI-HI temperature Signal generated a Group I isolation signal.

3. Six of the eight MSIVs closed.

PLOR232C Rev002.doc Page 3 of 7

4. The "C" MSL inboard and outboard MSIVs failed to close.

5. A full reactor scram occurred; all rods are in.

6. T-103 was entered due to Secondary Containment high temperature. Points 1 and 16 have exceeded their Action Levels. No other T -103 Alarm levels have been reached.

7. RPV level and pressure are normal, being maintained with HPCI, RCIC, and SRVs.

8. The PRO placed both the inboard and outboard "C" MSL control switches to close but the valves did not respond.

9. When the PRO depressed the inboard and outboard "C" MSL Test pushbuttons both valves fully closed.

10. Drywell pressure rose to 0.9 pSig and suddenly lowered to 0.0 pSig.

11. Torus temperature is 104°F and rising slowly.

G. INITIATING CUE As Emergency Director, make the EAL Classification and complete EP-MA-114-1 00-F-01 ,

State/Local Notification Form.

PLOR232C RevOO2.doc Page40f 7

H. PERFORMANCE CHECKLIST II STEP STEP ACT STANDARD NO

• • • NOTE ****

Record the time using the clock above the Full Core Display. Time =

1 Obtain a copy of EP-AA-112-1 00-F-01 P Copies of EP-AA-112-100-F-01 and and EP-AA-1007. EP-AA-1007 are obtained.

2 Determine that the isolation of the Main P MSL is successfully isolated with the Test Steam Line (MSL) with the Test pushbutton.

pushbutton constitutes successful isolation of the MSL.

3 Determine that the successful isolation of P Successful isolation of the MSL does the MSL does NOT satisfy the criterion of NOT satisfy the criterion of the Fission the Fission Product Battier Matrix Product Battier Matrix thresholds 2.d.1 ,

thresholds 2.d.1, 2.dA, 3.d.1 or 3.d.3. 2.d.4, 3.d.1 or 3.d.3.

4 Determine that the Fission Product P Fission Product Barrier Matrix threshold Barrier Matrix threshold for RCS leakage for RCS leakage >50 gpm is NOT

>50 gpm is NOT applicable since the leak applicable since the leak has been has been isolated. isolated.

• 5 Determine that the Fission Product P EAL FU1 is the correct classification due Barrier Matrix threshold 3.b.1 is met due to a rapid unexplained drop in Drywell to Primary Containment pressure pressure following initial pressure rise.

unexpectedly lowering to 0 psig.

6 Announce the event classification to the S UNUSUAL EVENT is announced.

facility staff.

• • • NOTE ****

Record the time using the clock above the Full Core Display. Time =

Determine if the elapsed time since the initiating cue exceeds 15 minutes.

• • • NOTE ***

Inform the examinee that the Public Address Announcement and the ERO Notification required by EP-AA-112-1 OO-F-01, Shift Emergency Director Checklist, are NOT required for this JPM.

• • • NOTE ***

The following steps are associated with completion of EP-MA-114-1 OO-F-01, "StatelLocal Event Notification Form."

• 7 Check the call status. P "This is a drill" line is checked in Block #1.

• 8 Check the affected station. P "Peach Bottom" is checked in Block #2.

• 9 Check the event classification. P "UNUSUAL EVENT" classification is II checked in Block #3a.

PLOR232C Rev002.doc Page 5 of 7

STEP STEP ACT STANDARD NO

• 10 Check the affected unit. P Unit "Two" is checked in Block #3b.

• 11 Enter the time and date of the P Declaration time (in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock declaration. nomenclature) and today's date are entered in Block #3c. The declaration time should match the time the examiner entered in the note before JPM step 1.

• 12 Check the applicable change in P "Initial Declaration" is checked in Block classification status. #3d.

• 13 Enter the EAL number declared ANDIOR P EAL# "FU 1" is annotated in Block #4a provide a brief non-technical description AND a simplified explanation for the of event. event classification is provided in Block

1. 4b. Acronyms, abbreviations or other terms that would not be recognized by state and local response agencies are avoided. The Offsite EAL Reference Manual may be referred to, if necessary.

• 14 Check the non-routine radiological P "Airborne" non-routine radiological release status. release is NOT in progress is checked in Block #5A. EP-AA-114-F-01, "Release in Progress Determination Guidance" may be referenced.

• 15 Enter the wind direction "degrees from." P "265" is entered as the wind direction degrees from in Block #6a.

(Cue: Wind direction is from 265 degrees.)

• 16 Enter the wind speed. P Wind speed is entered as "5" miles per hour in Block #6b.

(Cue: Wind speed is 5 mph.)

• 17 Check the utility Protective Action P 7a, NOT APPLICABLE is checked.

Recommendation.

• 18 Check the appropriate conclusion. P "This is a drill" line is checked in Block #8.

19 Approve the event notification form. P The event notification form is signed in the form's header area by the Emergency Director.

• • • NOTE ***

WHEN the examinee completes the Event Notification form, THEN record the time using the clock above the Full Core Display. Time =

Determine if the elapsed time since the declaration exceeds 13 minutes.

PLOR232C RevO02.doc Page 6 of 7

STEP STEP ACT STANDARD NO 20 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When EP-MA-114-1 00-F-01 , "State/Local Event Notification Form" has been completed, the evaluator will terminate the exercise.

PLOR232C RevOO2.doc Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1. Unit 2 was at 100% power when a steam leak was reported in the Outboard MSIV room.

2. A Main Steam Line (MSL) HI-HI temperature signal generated a Group I isolation signal.

3. Six of the eight MSIVs closed.

4. The "c" MSL inboard and outboard MSIVs failed to close.

5. A full reactor scram occurred; all rods are in.

6. T-103 was entered due to Secondary Containment high temperature. Points 1 and 16 have exceeded their Action Levels. No other T-103 Alarm levels have been reached.

7. RPV level and pressure are normal, being maintained with HPCI, RCtC, and SRVs.

8. The PRO placed both the inboard and outboard "c" MSL control switches to close but the valves did not respond.

9. When the PRO depressed the inboard and outboard "c" MSL Test pushbuttons both valves fully closed.

10. Drywell pressure rose to 0.9 psig and suddenly lowered to 0.0 psig.

11. Torus temperature is 104°F and rising slowly.

INITIATING CUE As Emergency Director, make the EAL Classification and complete EP-MA-114-1 00-F-01, State/Local Notification Form.

EP-MA-114-100-F-01 Revision I Nuclear Page 1 of 3 STATE/LOCAL EVENT NOTIFICATION FORM (OR ELECTRONIC FACSIMILE)

UTILITY MESSAGE NO. _ __

EILfEFlGliNG¥ :DIREtroFlAPeROVA~:=,_-"-'--;.....;....;.._____""'"-:~=j,jr=tl'_J~~*.*'. -,".=%J,,,->_::_""",,--"""""-;""';"";"';;;';';"

PERFORM INITIAL ROLL CALL PRIOR TO TRANSMITTING - Refer to Page 3 of Form

1. CALL STATUS is: 2.Thisis _ _ _ _ _ _ _ _ _ __

[X1This isaDRILL. for [ ] LIMERICK / {)<l pEACH aonoM I [ ] TMI

[ ] This is an ACTUAL EVENT. My phone number is The cur

[Communicator will provide his/her NAME. PHONE NU TIME (in 24-hour clock) when notification is read.]

3.a EMERGENCY CLASSIFICATION

[Xl.lINUSVAlEvENI

[ ] ALERT

[ ] SITE AREA EMERGENCY c. DECLARED AT:

[ ] GENERAL EMERGENCY TIME:':J;b

[ ] RECOVERY -IN CLASSIFICATION STATUS

[ ] TERMINATION

4. a. EMERGENCY ACTION LEVEL (EAL) NO. is: -'"""~......~

b. A BRIEF NON-TECHNICAL DESCRIPTIO E EVENT is as follows:

(Anything similar to the below wor cceptable. Wording does NOT have to be exact.)

~ .*" **"' ... ) '.' . . . . . . . . . . . :..,.,,'.,...

Thereat~::ind.i.Q~tio~~o .9~~;or PQSII,~I~:fPsS of Pritlla.r:y;eOntaiiltnent:rnte~tity.; .Current

• ',*x**;* '."

  • 'x'** ..' ';'.';' ".'

plantconditIQnIB'OOr,JO rEtsten publIc safety..

[X] a

] b. AI ORNE radiological release in-progress

] c. LIQUID radiological release in-progress

] d. Radiological release TERMINATED

6. METEOROLOGY is:

a. WIND DIRECTION is FROM. '(07;1".. 265{ '::(degrees)

b. WIND SPEED is: -"-_~-"-'--""""""'~ (miles per hour)

Document Retention SRRS-ID - 5B.1 00

EP-MA-114-100-F-01 Revision I Page 2 of 3 STATE/LOCAL EVENT NOTIFICATION FORM

7. UTILITY PROTECTIVE ACTION RECOMMENDATION: (a or b) - No action should be taken until government officials have been notified: by State:

00 a~ ~1:;:A~I?t:IAeLE (Unusual Event, Alert, Site Area Emergency, Termination or Recovery only)

(Complete the following for Shelter or Evacuation for a General Emergency only for the applicable station):

[ ] b. The PROTECTIVE ACTION RECOMMENDATION (PAR) from the utility is:

] SHELTER 360 DEGREES FROM 0 MILES (SITE BOUNDARY) TO _ __

AND SHELTER THE FOLLOWING SECTORS FROM _ _ MILES TO

[]N []E []8

[ 1 NNE [ ] ESE [ 1 SSW

[ 1 NE [ ] SE [ 1 SW

~~D~:: recommends th~ ~~:~ent officials n~ti~ ::~wbile to :ak:N:'SSium iodide (KI) for those sectors where shelter is recommended and EAS Messages. 6; remainder of the EPZ to monitor WNW NW NNW

!I9Iml",nT officials notify the general public to take potassium iodide

__,..... ~,ion is recommended and advise remainder of the EPZ to o MILES (SITE BOUNDARY) TO _ _

r"I"1~""nrl., that government officials notify the general public to take potassium iodide where shelter is recommended and advise remainder of the EPZ to monitor ATE 360 DEGREES FROM 0 MILES (SITE BOUNDARY) TO _ _ MILES utility recommends that government officials notify the general public to take potassium iodide for those areas where evacuation is recommended and advise remainder of the EPZ to EAS

[ ] This is an ACTUAL EVENT.

PERFORM FINAL ROLL CALL UPON COMPLETION - Rafer to Page 3 of Form

• ASK if there are any questions regarding message or repeat backs needed

• READ "This concludes the notification message"

• FAX completed copies of all form pages to the Control Room, TSC and EOF, as applicable.

• INFORM the Shift Manager (Shift Emergency Director), TSC Director or EOF Director, as applicable, when notification is completed to required contacts.

Document Retention SRRS-ID - 5B.1 00

EP-MA-114-100-F-01 Revision I Page 3 of 3 STATE/LOCAL EVENT NOTIFICATION FORM "15 Minute Notifications" "15 Minute Notifications" PEACH BOTTOM (CAN 833) LIMERICK (CAN 841)

"Notification Line": Dial "833" for conference call. Stay on the line until agencies come on Initial Roll Call "3 Digit Extensions". Make these calls from 3-digit lines.

"Commercial # From PBAPS": Make these calls from a 4-digit line. Dial "g-1-Area Code-Number" "Commercial # From PBABS 3-digit lines": Dial "7-1-9-1-Area Code-Number" Initial Roll Call Final Roll Call (Time Contacted: 24-hour clock) ('/)

Pennsylvania EMA D Ext. 216 or 9-1-800-424-7362/

ty D

-344-5100 9-1-717-651-2001 Maryland EMA D ounty D Ex~r 610-655-4931 Ext. 205 or 9-1-41 0-517 -3600 ~.Oll Call Completed York County D Ext. 219 or 9-1-717-854-5571

~Mln-:teNomlc;'o;s"-

TMI (CAN 44)

Harford County D Ext. 214 Q[ 9-1-410-638-3400 /

9-1-410-638-4900 Commercial # From EOF: Dial "9-1-71 T' and the 4#

Cecil County D TolI*Free "800" # From TMI or EOF: Dial the #'s exactly as they appear below Initial Roll Call Final Roll Call (Time Contacted: 24-hour clock) (..J)

Pennsylvania EMA D Ext. 315 or 9-1-800-424-7362 or 9-651-2001 Cumberland County D Ext. 319 or 9-238-9676, 9-243-4121 or 9-532-8878 Lebanon County D Ext. 321 or 9-272-2025/-7621/ -2054 Lancaster County D Ext. 318 or 9-664-1190/ -1200 P NOTIFICATIONS

• _ ..,...... BOTTOM ON York County D Ext. 317 or 9-854-5571,9-840-2955 or

[ ] Dept. of the Environment 9-1-800-427-8347 Emergency ext. 292 or 235 Dauphin County D 9-1-866-633-4686 Ext. 320 or 9-911 or 9-558-6900

ontactea at

(time: 24-hour clock) Initial Roll Call Completed

] PA State Police, York Barracks Ext. 284 or 9-1-717-428-1011 FOLLOW-UP NOTIFICATIONS * (TMI)

Contacted at: (time: 24-hour clock) [ ] York Haven Power Station 9-266-3654 or 9-818-3962

• NOT required within 15 minutes of Classification Contacted at: (time: 24-hour clock)

Document Retention SRRS-ID - 58.100

Weather Tower #2 EL320 EL 75 EL33 Direction Current 265 265 265 15 MinAvg 265 250 265 60 Min Avg 250 250 265 Speed Current 4 5 4 15 MinAvg 5 5 5 60 MinAvg 5 5 4

EXELON NUCLEAR Nuclear Generation Group OJTfTPE MATERIAL COVERSHEET each Bottom Comm

~ JPM

~==------------==~--------------~

QUALIFICATION MANUAL D OJT MODULE LICENSED OPERATOR TRAINING LOR-307CA LICENSED OPERATOR REQUALIFICATION M. J. Kelly RESPOND TO A ROD DRIFT (ALTERNATE PATH - SECOND ROD DRIFTS)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _---'1_ _ _.1_ __

NAME: ISSUE DATE:

Last First M.I.

Employee ID. NO. COMPLETION DATE: I COMMENTS:

Training Review for Completeness: LMSCODE:

I Signature/Date LMS ENTRY:

I PLOR307CA Rev010.doc Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-..IPM DESIGNATOR: 2002600401 / PLOR-307CA KIA: 201003A2.03 RO: 3.4 SRO: 3.7 TASK DESCRIPTION: RESPOND TO A ROD DRIFT (ALTERNATE PATH - SECOND ROD DRIFTS)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR307CA Rev010.doc Page 2 of 5

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. ON-121, Rev. 9, "Drifting Control Rod"

2. GP-9-2, Rev. 34, "Fast Reactor Power Reduction" D. TASK STANDARD

1. Satisfactory task completion is indicated when the Reactor has been scrammed.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to respond to a drifting Control Rod using appropriate procedure. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Rod 46-07 is drifting in from position 48.

2. Equipment Operator has been directed to inspect HCU 46-07.

3. Reactor Engineering has been notified.

4. PCIOMR Surveillance is NOT required G. II\JITIATING CUE The Control Room Supervisor directs you to respond to the drifting Control Rod situation in accordance with ON-121, "Drifting Control Rod".

PLOR307CA Rev010.doc Page 3 of 5

H. PERFORMANCE CHECKLIST I STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure ON-121. P A copy of procedure ON-121 is obtained.

• 2 Select Rod 46-07. P Rod 46-07 select pushbutton is momentarily DEPRESSED at panel (Cue: Rod 46-07 select pushbutton 20C005A.

backlight is IitJ 3 Monitor the following parameters: P Monitor the following parameters on panels 20C005A and/or 20C008B:

• Reactor Power

• Generator Load

• Generator load on computer pOint

• Reactor Water Level G029 or JR-2157.

• Reactor Pressure

• Reactor water level on lI-85A-C and lI-94A-C.

(Cue: Reactor power and generator load

• Reactor pressure on PI-90A, B.

are lowering slowly. Reactor water level and reactor pressure are steady.)

• 4 Insert Rod 46-07 using the EMERG IN P The Emergency In/Notch Override switch switch and hold the rod at Full-in for 30 is held in the EMER ROD IN position for at seconds. least 30 seconds at panel 20C005A and then released.

(Cue: Full Core Display and Four Rod Display indicate "00" for Rod 46-07.)

5 Reset the" Rod Drift" alarm. P Place the "Drift Alarm" switch 3A-S7 in the "RESET" [COUNTERCLOCKWISE]

(Cue: Annunciator 211 D-4 and Rod position and release the switch at panel 46-07 rod drift light are not lit.) 20C005A.

6 Obtain a copy of procedure GP-9-2. P A copy of procedure GP-9-2 is obtained.

7 Reduce Reactor power to 950 MWe (by P "A" and "B" Recirc Pump Speed Controller reducing Recirc flow). manual control knobs are rotated in the COUNTERCLOCKWISE direction at panel (Cue: Reactor power is 950 GMWe.) 20C004A until Reactor power is 950 MWe.

Note to Evaluator The Alternate Path portion of this JPM starts here.

• 8 Recognize other rod drifts. P "Rod Drift" annunciator 211 D-4 and/or rod 10-19 and 34-55 rod drift lights are (Cue: Rod Drifts lights for Rods 10-19 and recognized.

34-55 are lit and annunciator 211 D-4 is flashing.)

• 9 Scram the Reactor. P 5A-S 1 Reactor Mode Switch is placed in "SHUTDOWN" position or 5A-S3A and (Cue: All rod indicators have green 5A-S3B Scram push buttons are backlight lit on the Full Core Display.) depressed at Panel 20C005A.

PLOR307CA Rev010.doc Page 4 of 5

STEP NO STEP ACT STANDARD 10 Inform Control Room Supervisor of P Second rod drift, Reactor Scram and entry second rod drift, Reactor Scram, and entry condition to T -100 reported to the CRS.

condition to T-100 "Scram".

(Cue: Control Room Supervisor acknow ledges report.)

11 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND

.procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the Reactor has been scrammed, the Control Room Supervisor should be informed.

The evaluator will then terminate the exercise.

PLOR307CA Rev010.doc Page 5 of 5

TASK CONDITIONSIPREREQUISITES

1. Rod 46-07 is drifting in from position 48.

2. Equipment Operator ltas been directed to inspect HCU 46-07.

3. Reactor Engineering has been notified.

4. PCIOMR Surveillance is NOT required INITIATING CUE The Control Room Supervisor directs you to respond to the drifting Control Rod situation in accordance with ON-12l, "Drifting Control Rod."

EXELON NUCLEAR Nuclear Generation Group OJTfTPE MATERIAL COVERSHEET ach Bottom Limerick Common JPM QUALIFICATION MANUAL OJT MODULE Licensed Operator Requalificalion PLOR-303CA Licensed Operator Requalification 010 jav Shutdown the "A" RFP Turbine (Alternate Path - Min Flow Valve Fails Closed)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature Title Date EFFECTIVE DATE: _ _ _,_ _--' _ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 10 NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date PLOR303CA Rev010.doc Page 1 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2590010401/ PLOR-303CA KIA: 259001A4.02 RO: 3.9 SRO: 3.7 TASK DESCRIPTION: SHUTDOWN THE "A' RFP TURBINE (ALTERNATE PATH - MIN FLOW VALVE FAILS CLOSED)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. ...IPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR303CA Rev010.doc Page 2 of 7

B. TOOLS AND EQUIPMENT None REFERENCES

1. SO 6D.2.A-2 Rev. 27, "Reactor Feedwater Pump Shutdown"

2. AO 6D.1-2 Rev. 3, "Reactor Feedwater Pump Shutdown with Failed Minimum Flow Valve" D. TASK STANDARD

1. Satisfactory task completion is indicated when the "A" RFP is secured and its suction valve (MO-2140A) closed.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to shutdown the "A" RFP to the point of having its suction valve (MO-2140A) closed, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. A normal plant shutdown is in progress lAW GP-3, "Normal Plant Shutdown".

2. Three Reactor Feed Pumps running.

3. Reactor power is approximately 78%.

4. Feedwater Master Level Controller is in "AUTO".

5. All RFP M/A Stations are in "AUTO".

6. The Zinc Injection system is shutdown.

7. Heat balance is in Venturi mode for all three RFP strings lAW AO 59C.2-2, 'Transfer Core Thermal Power Calculation LEFMNenturi Mode and Maximum Allowable Power Level Adjustments ll *

8. An Equipment Operator is stationed at the Unit 2 Condensate Demineralizer Panel for Condensate Demineralizer management.

G. INITIATING CUE The Control Room Supervisor directs you to shutdown the "A" RFP using SO 6D.2.A-2, "Reactor Feedwater Pump Shutdown" to the point of having its suction valve (MO-2140A) closed.

PLOR303CA Rev010.doc Page 3 of 7

H. PERFORMANCE CHECKLIST STEP II NO STEP ACT STANDARD 1 Obtain a copy of procedure SO P A copy of procedure SO 6D.2.A-2 is 6D.2.A-2. obtained.

2 Equalize the Bias on the liB" and P Depress the display pushbutton and "C" RFPs without exceeding select "X" on the Band C RFP MIA 0.5 x 106 Ib/hr between the liB" and stations. Turn the control knob until "C" RFPs. the Bias is matched on both RFPs while observing FR-2565 at panel (Cue: When "x" is selected on the 20C005A.

"B" MIA station the value is O.

When "x" is selected on the "C" MIA station the value is 0.)

3 Open AO-2139A, Feed Pump A P AO-2139A control switch is placed in Recirc valve. the 1I0PEN" position at panel 20C006A.

(Cue: Acknowledge control switch operation.)

4 Verify AO-2139A, Feed Pump A P Recognize by reporting failure of AO-Recirc valve is open. 2139A to open at pane120C006A.

(Cue: AO-2139A green light is on, red light is off.)

• • • NOTE***

IT IS EXPECTED THAT THE CANDIDATE WILL RECOGNIZE THAT AO-2139A DID NOT OPEN, AND OBTAIN A COpy OF AO 6D.1-2 "REACTOR FEEDWATER PUMP SHUTDOWN WITH FAILED MINIMUM FLOW VALVE" TO COMPLETE THE EVOLU1"ION. SELECTION OF THE APPROPRIATE PROCEDURE IS THE RESPONSIBILITY OF THE CANDIDATE.

IF NECESSARY, PROVIDE THE FOLLOWING CUE:

"CONTINUE TO SHUTDOWN "rHE "A" RFP USING APPROPRIATE PLANT PROCEDURES TO THE POINT OF HAVING ITS SUCTION VALVE (MO-2140A)

CLOSED" PLOR303CA Rev010.doc Page 4 of7

STEP NO STEP ACT STANDARD

• • • • NOTES ****

(1) The Alternate Path portion of this JPM begins with the next step.

(2) The CUE in the following step must be provided to the candidate independent of plant response.

• S Obtain a copy of procedure P A copy of procedure AO 60.1-2 is AO 60.1-2, "Reactor Feedwater obtained.

Pump Shutdown with Failed Minimum Flow Valve" (Cue: The System Manager and the Shift Manager have determined the Min Flow valve to be FAILED CLOSED.)

• 6 Place "A" RFP M/A Station in P "A" RFP MIA Station Automatic/

MANUAL. Manual select pushbutton is momentarily depressed at panel (Cue: Acknowledge pushbutton 20COOSA.

operation.)

7 Verify the "A" RFP controller is in P "A" RFP controller Automatic/Manual "MANUAL". pushbutton red light is ON at panel 20COOSA.

(Cue: The red light is on and green light is off beside the auto/man pushbutton.)

8 Reduce "A" RFP flow to 2.0 - 2.S x P itA" RFP MIA Station Control knob is 6

10 Ibm/hr by adjusting the control rotated COUNTERCLOCKWISE until knob on the RFP MIA Station. FT 06-0S0A on FR-2S6S indicates 6

2.0 - 2.S x 10 Ibmlhr at panel (Cue: FT-2-06-0S0A on FR-2S6S 20COOSA.

6 indicates 2.3 x 10 Ibm/hr.)

9 Verify Reactor water level P Reactor level is verified to be stable U-2-06-94A, B, and C, is stable on U-2-06-94A, B, C, and total and remaining RFPs can supply feedflow verified to be less than 9.0 x 6

feedwater for existing steam loads. 10 Ibm/hr on FR-2-06-098 at panel 20COOSA.

(Cue: U-2-06-94A, B, and C indicate 23" and stable.

FR-2-06-098 black pen indicates 6

8.S x 10 Ibm/hr.)

10 Place the control switch for P AO-2147A control switch is placed in AO-2147A, Feedpump Check the "CLOSE II position at panel valve, in IICLOSE". 20C006A.

(Cue: Acknowledge control switch II operation.)

PLOR303CA Rev010.doc Page 5 of 7

STEP NO STEP ACT STANDARD 11 Check AO-2147 A, Feedpump P AO-2147 red and green lights are Check valve response. verified ON at panel 20C006A.

(Cue: AO-2147A green light is on, red light is on.)

• 12 8ump closed MO-2149A, P MO-2149A control switch is Feedpump "A" Discharge valve. momentarily placed in the "CLOSE" position at pane120C006A. Valve (Cue: Acknowledge control switch Red Indicating Light/Stop Pushbutton operation.) is depressed to stop valve travel.

Repeat lAW procedure guidance.

13 Monitor Reactor Feed Pumps and P

• Checks discharge flow of "A" RFP RPV level response is dropping

• Checks discharge flow of "8" and (Cue: Discharge flow of "A" RFP is "C" RFPs are rising dropping, discharge flow of "8" and

• Monitors RPV water level, allow "C" RFPs are rising, RPV water RPV water level to stabilize level is stableJ

• 14 When RFP flow lowers to 1 x 10° P When "A" RFP flow lowers to 1 x 10° Ibm/hr, then trip "A" RFP. Ibm/hr, "A" RFPT Turbine Trip pushbutton (PBA 1) is momentarily (Cue: "A" RFPT TRIP" DEPRESSED at panel 20C005A.

annunciator on panel 201 is up.)

15 Verify the "A" RFP tripped. P The "N' RFP green turbine trip lights are verified lit and "A" RFPT speed is (Cue: The "A" RFP green turbine verified to drop to 0 on SPI-2621A at trip lights are lit; SPI-2621 A reads panel 20C005A.

0. Annunciators 201 G-4, 202 G-3, and 210 A-3 are lit.)

16 Verify MO-2149A is fully closed. P MO-2149A green light is verified ON at panel 20C006A.

(Cue: MO-2149A green light is on, red light is off.)

17 Verify "A" RFP Turning Gear P "A" RFP Turning Gear control switch control switch in AUTO. is verified in the AUTO (normal) position at panel 20C005A.

(Cue: Turning gear control switch is in AUTO.)

18 Verify "A" RFPT MSC SELECT P "A" RFPT amber MSC SELECT light light is lit. is verified ON on panel 20C005A.

(Cue: "A" RFPT MSC SELECT light is lit.)

• 19 Close MO-2140A, "Feed Pump 'A' P MO-2140A control switch is Suct" valve. momentarily placed in the close position at panel 20C006A.

(Cue: Acknowledge control switch II operation.)

PLOR303CA Rev010.doc Page 6 of 7

STEP NO STEP ACT STANDARD 20 Verify MO-2140A, "Feed Pump 'AI P MO-2140A green light is verified ON Suct" valve is closed. at pane120C006A.

(Cue: MO-2140A green light is on, red light is off.)

21 Inform Control Room Supervisor of P Task completion reported.

task completion.

(Cue: Control Room Supervisor acknowledges report.)

22 As an evaluator ensure that you P Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the "A" Reactor Feed Pump is secured, and its suction valve (MO-2140A) closed the Control

'-=toom Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR303CA Rev010.doc Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1. A normal plant shutdown is in progress lAW GP-3, "Normal Plant Shutdown".

2. Three Reactor Feed Pumps running.

3. Reactor power is approximately 78%.

4. Feedwater Master Level Controller is in "AUTO".

5. All RFP M/A Stations are in"AUTO" *

6. The Zinc Injection system is shutdown.

7. Heat balance is in Venturi mode for all three RFP strings lAW AO 59C.2-2, "Transfer Core Thermal Power Calculation LEFMNenturi Mode and Maximurn Allowable Power Level Adjustments".

8. An Equipment Operator is stationed at the Unit 2 Condensate Demineralizer Panel for Condensate Demineralizer management.

INITIATING CUE The Control Room Supervisor directs you to shutdown the"A" RFP using SO 6D.2.A-2, "Reactor Feedwater Pump Shutdown" to the point of having its suction valve (MO-2140A) closed.

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET Peach 80 Commo

~ JPM D QUALIFICATION MANUAL D OJT MODULE LICENSED OPERATOR REQUALIFICATION PLOR-023C LICENSED OPERATOR REQUALI FICATION 008 M. J. Kelly jav ADS RESET FOLLOWING SLOWDOWN APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _-----'I_ _~/_ __

NAME: ISSUE DATE:

Last First Mol.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

I LMS ENTRY:

SignaturelDate PLOR023C Rev008.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2180040101/ PLOR-023C KIA: 218000A4.03 RO: 4.2 SRO: 4.2 TASK DESCRIPTION: ADS RESET FOLLOWING BLOWDOWN A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required. '

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR023C RevO08.doc Page 2 of 6

S. TOOLS AND EQUIPMENT None

v. REFERENCES Procedure SO 1G.7.C-2, Rev. 9, "Automatic Depressurization System Reset Following Slowdown" (R)

D. TASK STANDARD

1. Satisfactory task completion is indicated when ADS logic reset, Vacuum breaker position indication reset, and ADS relief valve position indication reset.

2. Estimated time to complete: 7 minutes (A.5) Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset the ADS system using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. An automatic ADS initiation has occurred.

2. RPV water level is now greater than -160" and the capability exists to maintain level above -160".

3. The following annunciators have been reset:

a. "System I ECCS REAC VESSEL LO-LO-LO LEVEL", panel 227 0-2.

b. "System II ECCS REAC VESSEL LO-LO-LO LEVEL", panel 228 C-2.

4. Slowdown of the RPV is complete.

5. Reactor pressure is 10 psig.

6. Drywell pressure is 1.35 psig.

G. 11\lITIATING CUE The Control Room Supervisor directs you to reset the ADS logic in accordance with SO 1G.7.C-2, "Automatic Depressurization System Reset Following Slowdown", Section 4.1.

PLOR023C RevOOB.doc Page 3 of 6

H. PERFORMANCE CHECKLIST I STEP NO STEP ACT STANDARD

• 1 Depress the "A" ADS LOGIC RESET P The "A" ADS LOGIC TIMER RESET TIMER pushbutton, 2E-S2A. pushbutton, 2E-S2A, is momentarily depressed at paneI20C003-01.

(Cue: Acknowledge pushbutton operation.)

• 2 Depress the "B" ADS LOGIC RESET P The liB" ADS LOGIC TIMER RESET TIMER pushbutton, 2E-S2B. pushbutton, 2E-S2B, is momentarily depressed at panel 20C003-01.

(Cue: Acknowledge pushbutton operation. )

3 Reset the following annunciators: P The alarm "RESET' pushbutton is momentarily depressed on panel 20C003.

a. "BLOWDOWN AUX RELAYS ENERGIZED RHR OR CS".

b. "BLOWDOWN RELIEF VALVES HIGH TEMP".

(Cue: Acknowledge pushbutton operation.)

4 Verify "BLOWDOWN AUX RELAYS P "BLOWDOWN AUX RELAYS ENERGIZED RHR OR CS" and ENERGIZED RHR OR CS" and "BLOWDOWN RELIEF VALVES HIGH "BLOWDOWN RELIEF VALVES HIGH TEMP" annunciators are clear. TEMP" annunciators are verified clear on alarm panels 227 E-4 and 227 B-4.

(Cue: Annunciators 227 E-4 and 227 B-4 are not lit.)

5 Verify "BLOWDOWN TIMERS INITIATED" P "BLOWDOWN TIMERS INITIATED" annunciator reset. annunciator is verified clear on alarm panel 227 D-4.

(Cue: Annunciator 227 D-4 is not lit.)

6 Verify "SAFETY RELIEF VALVE OPEN" P "SAFETY RELIEF VALVE OPEN" annunciator reset. annunciator is verified clear on alarm panel 210 D-2.

(Cue: Annunciator 210 D-2 is not lit.)

7 Verify the ADS valves indicate closed. P RV-2-02-71A, B, C, G, & K green lights verified ON at panel 20COO3-01.

(Cue: RV-2-02-71A, B, C, G, & K green lights are on, red lights are off.)

PLOR023C Rev008.doc Page 4016

STEP NO STEP ACT STANDARD 8 Monitor temperature recorder TR-2-02 P TR-2-02-103 monitored at panel 20C003 103 to ensure each valve has reseated. 01 to ensure each ADS valve has reseated, as indicated by each point (Cue: TR-2-02-103 pOints TE-2-2-113A, trending downward from -260-240°F.

B, C, G, & K read -250°F and are decreasing slowly.)

• 9 Depress the "A" ADS LOGIC RESET P The "A" ADS DRYWELL HIGH DRYWELL HIGH PRESS pushbutton, 2E PRESSURE LOGIC RESET pushbutton, S3A. 2A-S3A, is momentarily depressed at paneI20C003-01.

(Cue: Acknowledge pushbutton operation.)

• 10 Depress the "BII ADS LOGIC RESET P The "B" ADS DRYWELL HIGH PRESS DRYWELL HIGH PRESS pushbutton 2E LOGIC RESET pushbutton, 2E-S3B, is S3B. momentarily depressed at panel 20C003 01.

(Cue: Acknowledge pushbutton operation. )

11 Reset the following annunciators: P The alarm "RESETII pushbutton is momentarily depressed on panel 20C003.

a. "DRYWELL HI PRESS SIGNAL SEALED IN".

b. "HIGH DRYWELL PRESSURE BYPASS TIMERS INITIATED".

(Cue: Acknowledge pushbutton operation.)

12 Verify "DRYWELL HI PRESS SIGNAL P "DRYWELL HI PRESS SIGNAL SEALED SEALED IN" and "HIGH DRYWELL INII and "HIGH DRYWELL PRESSURE PRESSURE BYPASS TIMERS BYPASS TIMERS INITIATEDII INITIATED" annunciators are clear. annunciators are veri'fied clear on alarm panels 227 A-4 and 227 A-3.

(Cue: Annunciators 227 A-4 and 227 A-3 are not lit.)

13 Inform the Control Room Supervisor of P Task completion reported.

task completion.

(Cue: Control Room Supervisor acknowledges report.)

PLOR023C RevO08.doc Page 5 of 6

STEP NO STEP ACT STANDARD 14 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the ADS logic has been reset, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR023C RevOOS.doc Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. An automatic ADS initiation has occurred.

2. RPV water level is higher than -160 inches and the capability exists to maintain level above -160 inches.

3. The following annunciators have been reset:

a. "System I ECCS REAC VESSEL lO-lO lO lEVEL", panel 227 0-2.

b. "System II ECCS REAC VESSEL lO-lO lO lEVEL", panel 228 C-2.

4. Blowdown of the RPV is complete.

5. Reactor pressure is 10 psig.

6. Drywell pressure is 1.35 psig.

INITIATING CUE The Control Room Supervisor directs you to reset the ADS logic in accordance with SO 1G.7.C-2, "Automatic Depressurization System Reset Following Blowdown", Section 4.1.

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET Peach Bottom u.-...=:!II Limerick II Common D QUALIFICATION MANUAL D O..IT MODULE licensed Operator Training PLOR-353CA icensed Operator Requalification 000 John A Verbillis jav Startup HPCI in the CST To CST Mode (Alternate Path - Turbine Exhaust Diaphragm High Pressure)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _ _.j_ _~/_ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 10 NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date II PLOR353CA RevOOO.doc Page 1 of 9

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2060480401/ PLOR-353CA KIA: 206000A3.07 RO: 3.9 SRO: 3.8 TASK DESCRIPTION: Startup HPCI in the CST to CST Mode (Alternate Path - Turbine Exhaust Diaphragm High Pressure)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR353CA ReVOOO.doc Page 2 of 9

B. TOOLS AI\ID EQUIPMENT None C. REFERENCES

1. SO 23.1.B-2, Rev. 22, "HPCI System Manual Operation"

2. SO 23.2.A-2, Rev. 15, "HPCI System Shutdown"

3. RRC 23.1-2, Rev. 5, "HPCI System Operation During a Plant Evenf'

4. ARC 221 (20C204B) E-3, Rev. 2, "HPCI Turb Exh Diaphram Hi Press" D. TASK STANDARD

1. Satisfactory task completion is indicated when the HPCI Turbine has been started and then manually tripped due to receipt of Turbine Exhaust Diaphragm rupture alarm.

2. Estimated time to complete: 16 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to steps to startup HPCI in the CST to CST mode using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

r. TASK CONDITIONS/PREREQUISITES

1. Reactor is shutdown following an electrical transient.

2. The HPCI System is set up for operation in accordance with SO 23.1.A-2, "HPCI System Setup for Automatic or Manual Operation u *

3. "B" loop of RHR is in the Torus Cooling mode in accordance with SO 10.1.D-2, "RHR System Torus Cooling".

4. SBGT is in service in accordance with SO 9A.1.B, "Standby Gas Treatment System Manual Startupll G. INITIATING CUE The Control Room Supervisor directs you to start up HPCI in the CST to CST Mode in accordance with RRC 23.1-2, "HPCI System Operation During a Plant Evenf' and lower reactor pressure to 500 psig.

PLOR353CA RevOOO.doc Page 3 of 9

H. PERFORMANCE CHECKLIST

~STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure RRC 23.1 - 2. P A copy of procedure RRC 23.1 -2 is obtained.

• 2 Open MO-2-23-024, IICond. Tank Return". P MO-2-23-024 control switch is momentarily placed in the OPEN position at panel (Cue: Acknowledge control switch 20COO4B.

operation.)

3 Verify MO-2-23-024, "Cond. Tank Return ll P MO-2-23-024 red light is verified ON at valve opened. panel 20COO4B.

(Cue: MO-24 red light is ON, green light is OFF.)

4 Verify closed MO-2-23-019, "To Feed P MO-2-23-19 veri'fied CLOSED at panel Line" 20COO4B.

(Cue: MO-19 red light is OFF, green light is ON.)

5 Start the Gland Seal Condenser Vacuum P Gland Seal Condenser Vacuum Pump Pump 20KOO2. control switch is placed in the liSTARTII position at pane120COO4B.

(Cue: Acknowledge control switch operation.)

6 Verify the Gland Seal Condenser Vacuum P 20K002 red light is verified 01\1 at panel Pump 20K002 is running. 20COO4B.

(Cue: 20K002 red light is ON and green light is OFF.)

• 7 Throttle open MO-2-23-021, IIFull Flow P MO-2-23-021 control switch is momentarily Test" until the red "OPEN" indicating light placed in the OPEN position.

has been lit for 3 to 4 seconds. Approximately 3 to 4 seconds after the red light lit, the red stop travel pushbutton is (Cue: MO-21 green light is ON, red light depressed at the 20C004B panel.

has been ON for 3 to 4 seconds.)

• 8 Simultaneously START the Auxiliary Oil P Auxiliary oil pump control switch is placed Pump, 20P026 and OPEN MO-2-23-014 in the START position while "Supply" valve. simultaneously placing MO-2-23-014 IISupplyll control switch momentarily in the (Cue: Acknowledge control switch "OPEN" position at panel 20COO4B.

operation.)

II PLOR353CA RevOOO.doc Page 4 of 9

STEP NO STEP ACT STANDARD 9 Verify the Auxiliary Oil pump started. P Auxiliary Oil Pump red light is verified ON at panel 20C004B.

(Cue: Auxiliary Oil pump red light is ON, green light is OFF and annunciator 222 D 5 is alarming.)

10 Verify MO-2-23-014, "Supply" valve P MO-2-23-14 red light verified ON and HPCI opened. speed, discharge pressure, and flow are verified at panel 20C004B. HPCI Aux Oil (Cue: MO-14 red light is ON, green light is Pump is verified to have turned itself OFF OFF, HPCI discharge pressure, flow, as the Attached Oil Pump ramps up.

speed and exhaust pressure rise, Aux. oil pump red light is OFF and green light is ON.)

11 Verify pump 'Flowrate of 5000 gpm on P FIC-2-23-10B setpoint is adjusted to obtain FI-2-23-10B. 5000 gpm on FI-2-23-10B at panel 20C004B.

(Cue: FI-2-23-10B indicates 5000 gpm.)

12 Throttle MO-2-23-021 to obtain desired P MO-2-23-021 control switch is closed to pressure. raise pressure, opened to lower pressure and red stop travel pushbutton is (Cue: Acknowledge control switch depressed to obtain a pressure of 200 psig operation. PI-2-23-109 reads about BOO below reactor pressure on PI-2-23-109 psig, FI-2-23-10B reads 5000 gpm.) while maintaining turbine speed greater than 2200 rpm at SPI-4505 at panel 20C004B.

• • • • NOTE: ****

The Alternate Path portion of this JPM begins with the next step.

• 13 Recognize HPCI Exhaust Diaphragm P Recognize annunciator 221 E-3 is flashing rupture condition. and consult Alarm Response Card 221 E-3 recognize condition requiring HPCI turbine (Cue: Annunciator 221 E-3 is alarming.) trip as Adequate Core Cooling is NOT in jeopardy.

PLOR353CA RevOOO.doc Page 5 of 9

• • • • NOTE****

The following steps are scripted from SO 23.2.A-2, "HPCI System Shutdown." IF the Rapid Response procedure RRC 23.1-2 is used, THEN the steps indicated with "RRP NlA" are NOT applicable.

14 Verify HPCI initiation pushbutton (23A P HPCI Manual Initiation (23A-S105) collar is S105) collar is in "DISARM". verified in the "DISARM"

[counterclockwise] position on 20C0048 or (Cue: HPCI initiation collar is in "DISARM" "HPCIIN TEST/ARMED" annunciator 221 and annunciator 221 8-2 is not lit.) 8-2 is clear.

15 Verify the Aux oil pump (20P026) control P Aux oil pump (20P026) control switch is switch is in "START". verified in "START" at panel 20C0048.

(Cue: Aux oil pump control switch (20P026) is in "START".)

16 Verify annunciators IIHPCI AUX OIL P Annunciators IIHPCI AUX OIL PUMP PUMP MOTOR OVERCURRENT" (221 MOTOR OVERCURRENT' (221 A-2) and RRP A-2) and "HPCI DC MOTOR POWER "HPCI DC MOTOR POWER LOSS" (221 LOSS" (221 A-1) are clear. A-1) are verified clear.

N/A (Cue: Annunciators 221 A-1 and 221 A-2 are not lit.)

17 Verify Gland Seal Condenser Vacuum P Gland Seal Condenser Vacuum Pump Pump (20K002) is in "STARTII. (20K002) control switch is verified in "START" at pane120C0048.

(Cue: Vacuum pump switch is in "Start".

red light is on and green light is off.)

• 18 Depress and hold the HPCI System P Remote trip pushbutton is DEPRESSED "Remote Trip" pushbutton. AND HELD in until MO-2-23-014 indicates fully closed at panel 20C0048.

(Cue: Turbine speed drops and 221 8-1 is alarming "HPCI TUR8 TRIP".)

19 Verify HPCI Aux oil pump starts as turbine P HPCI Aux oil pump (20P026) red light is slows down (1200-1500 RPM). verified ON at panel 20C0048 and/or "HPCI AUX OIL PUMP RUNNING" (Cue: HPCI Aux oil pump red light is lit annunciator 222 D-5 is verified lit.

and green light is off. Annunciator 222 D 5 is flashing.)

PLOR353CA RevOOO.doc Page60f 9

• 20 Close MO-2-23-014, IISupply" valve OR P SO 23.2.A-2 and RRC 23.1-2 standard Wait for the Turbine shaft to stop rotating as indicated by SPI-4505 on 20C004B (or MO-2-23-014 control switch is momentarily Local Indication) and place the Aux oil placed in the CLOSE position within 5 pump control switch to the PTL position. minutes of receiving annunciator 221 B-3 at pane120C004B.

(Cue: Acknowledge control switch operation. ) (The operator may follow the ARC guidance which directs the operator to trip the HPCI turbine. The operator may elect to place the Aux Oil Pump control switch to PTL after the turbine shaft stops rolling and before releasing the trip pushbutton) 21 Verify MO-2-23-014, "Supply" valve P MO-2-23-014 green light verified ON at closed. panel 20C004B.

(Cue: MO-14 green light is on red light is off. HPCI speed, discharge pressure, and exhaust pressure have dropped to 0.)

22 Verify closed the MO-2-23-019, "To Feed P MO-2-23-019 green light verified ON and Line" valve. red light verified OFF on panel 20C004B.

(Cue: MO-2-23-019 green light ON, red light OFF.)

23 When MO-2-23-14 is fully closed, release P Remote trip pushbutton is RELEASED at the HPCI system "Remote Trip" panel 20COO4B.

pushbutton.

(Cue: Acknowledge pushbutton is released.)

24 CLOSE MO-2-23-021 "Full Flow Test" P MO-2-23-021 Control Switch is momentarily place in CLOSE.

RRP (Cue: Acknowledge Control Switch Operator.)

NJA 25 Verify MO-2-23-021 "Full Flow Test" is P MO-2-23-021 Green light verified on at CLOSED. Panel 20COO4B.

RRP (Cue: MO-21 Red light is OFF, Green NJA light is ON.)

26 Close MO-2-23-024 "Cond Tank Return" P MO-2-23-024 Control Switch is momentarily placed in CLOSE.

RRP (Cue: Acknowledge control Switch Operation.)

N/A PLOR353CA RevOOO.doc Page 7 of 9

27 Verify MO-2-23-024 IICond Tank Return P MO-2-23-024 green light verified ON at valve is closed. II Panel 20C0043.

RRP (Cue: MO-24 Red light is OFF, Green N/A light is ON.)

28 Verify 228 C-5, "HPCI RELAYS NOT P 228 C-5 is veri'fied clear RESET" is reset RRP N/A (Cue: 228 C-5 is clear) 29 Verify OPEN AO-2-23-042, "Drain Isol to P AO-2-23-042 Verified Open Mn Cndr" RRP NlA (Cue: AO-042 Red light is ON, Green light is OFF.)

30 Verify OPEN AO-2-23-043, "Drain Isol to P AO-2-23-043 Verified Open Mn Cndr" RRP N/A (Cue: AO-043 Red light is ON, Green light is OFF.)

31 Direct Equipment Operator to Verify HPCI P Equipment Operator dispatched Turbine Shaft is Stopped RRP N/A (Cue: Acknowledge direction, inform Candidate JPM is concluded) 32 Inform Control Room Supervisor of P Exhaust Diaphragm rupture indications Exhaust Diaphragm rupture indications and HPCI Turbine trip reported.

and HPCI Turbine trip.

NOTE: This step may be performed at any (Cue: Control Room Supervisor point post-Alarm condition. IF Evaluator acknowledges report.) Terminates JPM before CRS is informed, then this step is NtA.

33 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

PLOR353CA RevOOO.doc Page 8 of 9

Under "ACT" P - must perform S - must simulate

.. TERMINATING CUE When the HPCI Turbine has been tripped due to Exhaust Diaphragm rupture indications, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR353CA RevOOO.doc Page 9 of 9

TASK CONDITIONS/PREREQUISITES

1. Reactor is shutdown following an electrical transient.

2. The HPCI System is set up for operation in accordance with SO 23.1.A-2, IIHPCI System Setup for Automatic or Manual Operation II *

3. IIBII loop of RHR is in the Torus Cooling mode in accordance with SO 10.1.0-2, "RHR System Torus Cooling".

4. SBGT is in service in accordance with SO 9A.1.B, "Standby Gas Treatment System Manual Startup" INITIATING CUE The Control Room Supervisor directs you to start up HPCI in the CST to CST Mode in accordance with RRC 23.1-2, "HPCI System Operation During a Plant Event" and lower reactor pressure to 500 psig.

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET Limeri

...1PM QUALIFICATIOI\I MANUAL OJT MODULE Licensed Operator Training Licensed Operator Requalification Training 07 J. R. Felice HPSW Injection Into tile Torus APPROVALS:

Signature f Title Date Signature f Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _ _1_ _----'1_ __

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR081 C RevO07.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2004800501/ PLOR-081C KIA: 219000A4.13 RO: 3.9 SRO: 3.8 TASK DESCRIPTION: HPSW Injection Into the Torus A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" ..IPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" ..IPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR081C Rev007.doc Page 2 of 6

B. TOOLS AND EQUIPMENT

1. Keys for MO-2-1 0-174 and MO-2-10-176 C. REFERENCES

1. T-231-2, Rev. 6, "HPSW Injection Into the Torus" D. TASK STANDARD

1. Satisfactory task completion is indicated when the 2B HPSW Pump is injecting water into the Torus.

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to inject water into the Torus using the 2B HPSW pump using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Use of this procedure has been directed by the TRIP procedures.

2. High Pressure Service Water Pumps are available.

3. A LPCI initiation signal is NOT present.

4. 4 KV Buses are receiving power from off-site power.

G. INITIATING CUE The Control Room Supervisor directs you to perform T-231-2, "HPSW Injection into the Torus" in order to inject water into the Torus with the 2B HPSW pump.

PLOR081 C Rev007.doc Page 3 of 6

H. PERFORMANCE CHECKLIST I STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure T-231-2, P A copy of procedure T-231-2, "HPSW "HPSW Injection into the Torus". Injection into the Torus" is obtained. Steps 4.1 and 4.2 are referenced.

2 Verify closed MO-2-10-154B, "Outboard P MO-1548 green light verified ON, red light Disch". verified OFF on paneI20C003-02.

(Cue: MO-1548 green light ON, red light OFF.)

3 Verify RHR pump 28P035 shutdown. P "8" RHR pump green light verified ON at panel 20C003-02.

(Cue: "B" RHR pump green light ON, red light OFF.)

4 Verify RHR pump 2DP035 shutdown. P "0" RHR pump green light verified ON at panel 20C003-02.

(Cue: "0" RHR pump green light ON, red Ught OFF.)

5 Verify 28P042 HPSW pump shutdown. P "8" HPSW pump green light verified ON at paneI20C003-02.

(Cue: "8" HPSW pump green light ON, red light OFF.)

6 Verify 20P042 HPSW pump shutdown. P "0" HPSW pump green light verified ON at panel 20C003-02.

(Cue: "0" HPSW pump green light ON, red light OFF.)

7 Verify closed MO-2-10-0898, "8 HPSW Hx P MO-0898 green light verified ON, red light Out". verified OFF at paneI20C003-02.

(Cue: MO-0898 green light ON, red light OFF.)

8 Verify closed MO-2-10-0890 "0 HPSW Hx P MO-089D green light verified ON, red light Ouf'. verified OFF at panel 20C003-02.

(Cue: MO-089D green light ON red light OFF.)

PLOR081 C Rev007.doc Page 4 of 6

STEP NO STEP ACT STANDARD 9 Verify closed MO-2-32-2344 (10-186), P MO-2344 (10-186) green light verified ON, "HPSW Loop Cross Tie". red light verified OFF at panel 20COO-03.

(Cue: MO-2344 (10-186) green light ON, red light OFF.)

• 10 Open MO-2-10-174, "HPSW/RHR Em P Key is obtained from the SSV keybox, Inner Cross Tie". inserted into MO-174 keylock switch and placed in the OPEN position at panel 20C003-03.

(Cue: Acknowledge key lock switch operation.)

11 Verify MO-2-10-174, "HPSW/RHR Em P MO-174 red light verified on at panel Inner Cross Tie" valve is opened. 20C003-03.

(Cue: MO-174 red light is ON, green light is OFF.)

• 12 Open MO-2-10-176, "HPSW/RHR Em P Key is obtained from the SSV keybox, Outer Cross Tie". inserted into MO-176 keylock switch and placed in the OPEN position at panel 20C003-03.

(Cue: Acknowledge keylock switch operation.)

13 Verify 1VI0-2-10-176, "HPSW/RHR Em P MO-176 red light verified on at panel Outer Cross Tie" valve is opened. 20C003-03.

(Cue: MO-176 red light is ON, green light is OFF.)

• 14 Open MO-2-10-0398, "Torus Hdr" P MO-2-10-0398 control switch is momentarily placed in the OPEN position (Cue: Acknowledge switch operation.) at paneI20C003-02.

15 Verify MO-2-10-0398, "Torus Hdr." is P MO-2-10-0398 red light verified ON at opened. panel 20C003-02.

(Cue: MO-398 red light is on, green light is off.)

• 16 Start the "8" HPSW pump. P "8" HPSW pump control switch is momentarily placed in the START pOSition (Cue: "8" HPSW pump red light is on, at paneI20C003-02.

green light is off and annunciator 225 8-5 is alarming.)

PLOR081C Rev007.doc Page 5 of 6

STEP NO STEP ACT STANDARD 17 Verify proper start of the "8" HPSW pump. P Pump amps and discharge pressure are verified stable after starting current (Cue: 10A*A28 indicates 62 amps and PI* decays.

23308 indicates 430 psig.)

18 Acknowledge the "RHR DISCH HDRS HI P The annunciator "ACKNOWLEDGE" PRESS & SHUTDOWN SUCTION HDRS pushbutton is depressed on panel HI PRESS" annunciator. 20C003*04.

(Cue: Annunciator 225 8-5 is lit sOlid.)

• 19 Throttle open MO-2-10-0348, "Full Flow P MO-2-10-0348 control switch is Tesf' valve to maintain HPSW flow less momentarily placed in the OPEN position than 5300 gpm on FI-2-10-1398. until 5000-5300 gpm is obtained on FI-2 10-1398 THEN the red, stop travel (Cue: FI-1398 reads 5200 gpm.) pushbutton is depressed at panel 20C003-02.

20 Inform the Control Room Supervisor of P Task completion reported.

task completion.

(Cue: Control Room Supervisor acknowledges report.)

21 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT' P - must perform S - must simulate I. TERMINATING CUE When the 28 HPSW Pump is injecting into the Torus, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR081C Rev007.doc Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Use of this procedure has been directed by the TRIP procedures.

2. High Pressure Service Water Pumps are available.

3. A LPCI initiation signal is NOT present.

4. 4 KV Buses are receiving power from off-site power.

INITIATING CUE The Control Room Supervisor directs you to perform T-231-2, "HPSW Injection into the Torus" in order to inject water into the Torus with the 2B HPSW pump.

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET JPM D QUALIFICATION MANUAL D OJT MODULE PLOR-344CA LICENSED OPERATOR REQUALIFICATION 001 jav Restoration of 4KV Buses From 2SUE (Alternate Path - 2SU-A Bkr Closes)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _------!I_ _---'I_ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 10 NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR344CA ReVO01.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2008470501 -PLOR344CA KIA: 262001 A4.01 RO: 3.4 SRO: 3.7 TASK DESCRIPTION: Restore Power to E13 Bus From Offsite A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" ...IPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. ..JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this ...IPM, though listed in the task standard, is not to be given to the examinee.

6. This JPM is designed to be given in the Control Room Simulator.

PLOR344CA RevO01.doc Page 2 of 6

B. TOOLS AND EQUIPMENT

1. T-350-3 'Area 50 Fire Guide' C. REFERENCES

1. T-350-3 'Area 50 Fire Guide' Rev 007.

D. TASK STANDARD

1. Satisfactory task completion is indicated when the E12 bus and the E13 bus are being powered from the 2SU Off-Site power source with the 2SU-A Bkr open.

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to restore power to the E12 and E13 Buses from 2SU using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. 2SU is the only offsite power source available.

2. A loss of power to the 2SU Transformer Tap Changer has occurred.

3. 4KV Buses have tripped on undervoltage.

4. E22, E32, E42, E23, E33, E43 Buses are now being powered from their respective Diesel Generator.

5. The E1 Emergency Diesel Generator has failed to start.

6. T -350-3 Attachment 1 "Defeat of 4KV Bus 2SU Feeder Breakers Degraded Voltage Trip Relays" has been completed.

G. INITIATING CUE The Control Room Supervisor directs you to restore power to the E12 and the E13 Buses from 2SU in accordance with T-350-3 'Area 50 Fire Guide' steps 2.8 AND 2.9.

PLOR344CA RevO01.doc Page 3 of 6

H. PERFORMANCE CHECKLIST II STEP STEP T STANDARD NO 1 Obtain a copy of T-350-3 'Area Fire P Correct procedure obtained.

Guide'

• 2 OPEN breaker 252-0308 "2SU-A Bkr" at P Control Switch for the 2SU-A Breaker is Panel 00C024 taken to the 'Trip' position and then permitted to spring return to normal.

CUE: 2SU-A Breaker green indicating light is lit (red indicating light is out).

• • • Notes ***

A. After step 2 is complete the simulator operator will simUlate the action of the fire by re closing the 2SU-A breaker (over-riding the Sync Switch for the 2SU-A Breaker to the 'ON TRIP 0906' position and momentarily overriding the 2SU-A Breaker Control Switch to the 'Close' position). Simulator Operator MUST immediately return Breaker 2SU-A Control Switch to

'normal' operation. This action can easily be initiated by using an Event Trigger.

B. The above action by the simulator operator is the start of the Alternate Path.

C. Step 3 below (Step 2.9 of T-350-3) does NOT have to be performed in the order listed.

• 3 OPEN breaker 252-0308 "2SU-A Bkr" at P Control Switch for the 2SU-A Breaker is Panel OOC024 taken to the 'Trip' position and then permitted to spring return to normal.

CUE: 2SU-A Breaker green indicating light is lit (red indicating light is out).

• 4 OPEN breaker 252-0311 "2SU-B Bkr" at P Control Switch for the 2SU-B Breaker is Panel OOC024 taken to the 'Trip' position and then permitted to spring return to normal.

CUE: 2SU-B Breaker green indicating light is lit (red indicating light is out).

PLOR344CA RevO01.doc Page 4 of 6

STEP STEP ACT STANDARD NO

• 5 PLACE the "E212 BKR SYNC" switch to P Sync Switch for the E212 Breaker is "ON" positioned to the 'ON' position using the Sync Key.

CUE: The component that you identified is in the position that you described.

• 6 TURN the "E212 BKR" Control Switch to P Control Switch for E212 Breaker is the 'CLOSE' position AND VERIFY the momentarily taken to the 'CLOSE' E212 Breaker closed. position and allowed to spring return to normal. Examinee verifies E212 Breaker CUE: The E212 Breaker red indicating red indicating light is lit, green indicating light is lit, the green indicating light is out. light is out.

7 PLACE the "E212 BKR SYNC" switch to P Sync Switch for the E212 Breaker is "OFP' positioned to the 'OFP position.

CUE: The component that you identified is in the position that you described.

8 VERIFY the E124 Breaker is closed P Verify E124 Breaker is closed.

CUE: The E124 Breaker red indicating light is lit, the green indicating light is out.

• 9 PLACE the "E213 BKR SYNC" switch to P Sync Switch for the E213 Breaker is "ON" positioned to the 'ON' position using the Sync Key.

CUE: The component that you identified is in the position that you described.

• 10 TURN the "E213 BKR" Control Switch to P Control Switch for E213 Breaker is the 'CLOSE' position AND VERIFY the momentarily taken to the 'CLOSE' E213 Breaker closed. position and allowed to spring return to normal.

CUE: The E213 Breaker red indicating light is lit, the green indicating light is out.

il PLOR344CA Rev001.doc Page 5 of 6

STEP STEP ACT STANDARD NO 11 PLACE the "E213 BKR SYNC" switch to P Sync Switch for the E213 Breaker is "OFF" positioned to the 'OFF' position.

CUE: The component that you identified is in the position that you described.

12 VERIFY the E134 Breaker is closed P Verify E134 Breaker is closed.

CUE: The E134 Breaker red indicating light is lit, the green indicating light is out.

13 Notify the Control Room Supervisor that P Notify the Control Room Supervisor that power has been restored to the E12 and power has been restored to the E12 and the E13 Buses from 2SU in accordance the E13 Buses 'from 2SU in accordance with T-350-3 'Area 50 Fire Guide' steps with T -350-3 'Area 50 Fire Guide' steps 2.8 and 2.9 2.8 and 2.9 CUE: If the examinee identified that the 2SU-A Breaker re-closed, then the evaluator should acknowledge the report and terminate the JPM.

• • • Note ***

When the E12 bus and the E13 bus are being powered from the 2SU Off-Site power source (with the 2SU-A Bkr open), then the evaluator may terminate the JPM.

14 As an evaluator ensure you have positive P Positive control established control of all exam material provided to the examinee (Task Conditions/

PrereQuisites) AND procedures.

Under "ACT' P - must perform S - must simulate D - must discuss I. TERMINATING CUE When the E12 bus and the E13 bus are being powered from the 2SU Off-Site power source (with the 2SU-A Bkr open) the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR344CA RevO01.doc Page 6 of 6

TASK CONDITIONSIPREREQUISITES

1. 2SU is the only offsite power source available.

2. A loss of power to the 2SU Transformer Tap Changer has occurred.

3. 4KV Buses have tripped on under voltage.

4. E22, E32, E42, E23, E33, E43 Buses are now being powered from their respective Diesel Generator.

5. The E1 Emergency Diesel Generator has failed to start.

6. T -350-3 Attachment 1 "Defeat of 4KV Bus 2SU Feeder Breakers Degraded Voltage Trip Relays" has been completed.

INITIATING CUE:

The Control Room Supervisor directs you to restore power to the E12 and the E13 Buses from 2SU in accordance with T -350-3

'Area 50 Fire Guide' steps 2.8 AND 2.9.

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET mil Peach Bottom ~ ~ Limerick II DII Common II

~ ..IPM D QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR~270C LICENSED OPERATOR REQUALIFICATION 001 J. A. Verbillis jaY ECW System Makeup to Tower Using a HPSW Pump APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _---11_ _---11_ __

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR270C Rev001.doc Page 1 of 9

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGI\lATOR: 2770040101 / PLOR-270C KIA: 400000 A4.01 URO: 3.1 SRO: 3.0 TASK DESCRIPTION: ECW System Makeup to Tower using a HPSW Pump A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical ..IPMs, completion within the estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR270C Rev001.doc Page20f 9

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. SO 48.7.A Rev 5 "Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump"

2. SO 32.1.A-2 Rev 15 "High Pressure Service Water System Startup And Normal Operations"

3. SO 32.2.A-2 Rev 8 "High Pressure Service Water System Shutdown" D. TASK STANDARD

1. Satisfactory task completion is indicated when:

Emergency Cooling Tower level is at or about 18 Ft 3 In, and Emergency Service Water is returned to a standby lineup.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to makeup to the Emergency Cooling Tower with the High Pressure Service Water system using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Emergency Cooling Water tower level is 17 ft.

2. All 4 KV busses are receiving power from the off-site startup sources.

3. Power available to the HPSW System per SO 54 and SO 56E.

4. The HPSW System is lined up for normal operation in accordance with COL 32.1.A-2 "High Pressure Service Water System" and SO 32.1.A-2 "High Pressure Service Water System Startup And Normal Operations"

5. Emergency Cooling Water (ECW) System is lined for normal standby operation in accordance with COL 48.1.A, "Emergency Cooling Water System {Units 2 and 3)".

6. High Pressure Service Water Radiation Monitoring System is lined up for normal operation in accordance with SO 63H.1.A-2, High Pressure Service Water Radiation Monitoring System Startup and Normal Operations.

PLOR270C RevO01.doc Page 3 of 9

7. Outside air temperature is 50°F.

8. One HPSW System has been declared INOPERABLE and appropriate TSA entries have been made per SO 48.7.A Precaution 3.1.

G. INITIATING CUE:

The Control Room Supervisor directs you to makeup to the Emergency Cooling Tower to a level of 18 ft 3 in, then restore to a normal lineup, using the "A" HPSW Pump I Heat Exchanger lAW SO 48.7.A "Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump" PLOR270C RevO01.doc Page 4 of 9

H. PERFORMANCE CHECKLIST II STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure SO 48.7.A. P Procedure obtained.

2 Obtain a copy of SO 32.1 .A-2 for starting P A copy of SO 32.1 .A-2 is obtained the HPSW pump 3 Direct Equipment Operator to verify "An P EO directed to verify Oil Level HPSW Pump motor oil level at STAND STILL level (Cue: Report as EO that "A" HPSW Pump motor oil level at STAND STILL level) 4 Direct Equipment Operator to verify Area P EO directed to verify Fan alignment Ventilation Fans are aligned as follows:

• HPSW + ESW Pump Room Supply Fan 2BV060 should be in "AUTO" AND 2AV060 should be in "AUTO STBY" on Pane120C139.

• HPSW + ESW Pump Room Exhaust Fans 2AV083 AND 2BV083 should be in "AUTO" on Pane120C139.

(Cue: Report as EO that fans aligned as above) 5 Notify Chemistry that the "A" RHR Heat P Chemistry notified Exchanger will be placed in service and appropriate samples are required (Cue: As Chemistry, acknowledge the report) 6 Monitor "A" HPSW motor bearing P PMS used for bearing temperature temperatures on PMS monitoring

• 7 Open MO 2 10 089A HPSW Hx Out p Correct valve opened (Cue: Red Light On, Green Light Off)

• 8 Start the "A" HPSW Pump. P "A" HPSW pump control switch (Cue: Acknowledge control switch manipulated.

operation.)

PLOR270C ReVO01.doc Page 5 of 9

STEP NO STEP ACT STANDARD 9 Verify "A" HPSW Pump operating as P HPSW pump parameters verified to be in expected. expected range.

(Cue: Red Light On, Pump amps initially peg high then settle at about 110 amps, discharge pressure is 270 psig.)

10 Throttle MO 2 10 089A to establish 3300 P System Flow verified in band provided in to 5300 gpm flow on FI 2 10 132A on SO.

Panel 20C003.

(Cue: System Flow is 4500 gpm) 11 Verify DPI 2 10 130A indicates greater P DP and Annunciator status are verified than 20 psid across the inservice RHR heat exchanger AND annunciator 20C203C C-4, "RHR Heat Exchanger Tube to Shell Low Press" is clear.

(Cue: DP is 95 psid, Annunciator C-4 is clear) 12 Direct Equipment Operator to perform SO P EO directed to perform routine inspection.

32.8.A 2, "High Pressure Service Water Candidate should NOT wait for EO report System Routine Inspection". of completion.

(Cue: EO acknowledges.)

• 13 Open MO 2 32 2803, IIUnit 2 HPSW Disch P At Panel 00C123 (MCR Emergency to Clg Tower" Cooling Tower Panel), candidate opens (Cue: Red light ON, Green light OFF) MO 2803, "Unit 2 HPSW Disch to Clg Towerll 14 Verify TSA log entries are completed for P Candidate acknowledges requirement for one HPSW subsystem inoperable. TSA log entry (Cue: TSA log entry will be made by Supervisor)

• 15 Close MO 2 32 2486, "Unit 2 HPSW Disch P At Panel 00C123 (MCR Emergency to Pond" Cooling Tower Panel), candidate closes (Cue: Red light OFF, Green light ON) MO 2486, "Unit 2 HPSW Disch to Pond ll PLOR270C Rev001.doc Page 6 of 9

STEP NO STEP ACT STANDARD

• • • NO"rE***

In the following step, ECT level as indicated on LI-0503 WILL NOT CHANGE, so this information must be CUED to the Candidate.

16 Monitor ECT reservoir level. P Observe level indicator L1-0503, "Clg Twr" on Panel 00C123.

(Cue: ECT reservoir level is slowly rising.)

(Cue: Inform candidate that ECT level is now 18 feet, 3 inches.)

17 Obtain a copy of SO 32.2.A for shutting P A copy of SO 32.2.A is obtained down the HPSW pump

• 18 Shutdown the running HPSW pump. P Running HPSW Pump control switch taken to OFF.

(Cue: Acknowledge switch operation.)

19 Verify "A" HPSW Pump shutdown as P HPSW pump parameters verified to be as expected. expected for shutdown pump.

(Cue: Red light OFF, Green light ON, Pump amps 0, discharge pressure is 0 psig.)

20 Close MO-2-10-089A "HPSW Hx Out" P Correct valve closed (Cue: Red light OFF, Green light ON) 21 Direct Equipment Operator to verify CHK P Check Valve verified closed 2-32-502A "HPSW 2A P042 Discharge Check Valve" is closed (Cue: As Equipment Operator, report that CHK-2-32-502A is CLOSED)

PLOR270C Rev001.doc Page 7 of 9

STEP NO STEP ACT STANDARD 22 Direct Equipment Operator to verify Area P EO directed to verify Fan alignment Ventilation Fans are aligned as follows:

• HPSW + ESW Pump Room Supply Fan 2BV060 should be in "AUTO" AND 2AV060 should be in "AUTO STBY" on Pane120C139.

• HPSW + ESW Pump Room Exhaust Fans 2AV083 AND 2BV083 should be in "AUTO" on Panel 20C 139.

(Cue: Report as EO that fans aligned as above) 23 Open MO 2 32 2486, "Unit 2 HPSW Disch P At Panel 00C123 (MCR Emergency to Pond" Cooling Tower Panel), candidate opens (Cue: Red light ON, Green light OFF) MO 2486, "Unit 2 HPSW Disch to Pond" 24 EXIT TSA one HPSW subsystem P Candidate acknowledges requirement for inoperable. TSA status change (Cue: TSA status entry will be made by Supervisor) 25 Close MO 2 32 2803, "Unit 2 HPSW Disch P At Panel OOC123 (MCR Emergency to Clg Tower" Cooling Tower Panel), candidate closes (Cue: Red light OFF, Green light ON) MO 2803, "Unit 2 HPSW Disch to Clg Tower" 26 Inform Control Room Supervisor of task P Task completion reported.

completion.

(Cue: Control Room Supervisor acknowledges report.)

27 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AI\ID procedures.

Under "ACT" P - must perform S - must simulate PLOR270C Rev001.doc Page 8 of 9

I. TERMINATING CUE When the lineup for making up to the Emergency Cooling Tower is secured, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR270C Rev001.doc Page 9 of 9

TASK CONDITIONS/PREREQUISITES

1. Emergency Cooling Water tower level is 17 ft.

2. All 4 KV busses are receiving power from off-site startup sources.

3. Power available to the HPSW System per SO 54 and SO 56E.

4. The HPSW System is lined up for normal operation in accordance with COL 32.1.A-2 "High Pressure Service Water System" and SO 32.1.A-2 "High Pressure Service Water System Startup And Normal Operations"

5. Emergency Cooling Water (ECW) System is lined for normal standby operation in accordance with COL 48.1.A, "Emergency Cooling Water System (Units 2 and 3}".

6. High Pressure Service Water Radiation Monitoring System is lined up for normal operation in accordance with SO 63H.1.A-2, High Pressure Service Water Radiation Monitoring System Startup and Normal Operations.

7. Outside air temperature is 50°F.

8. One HPSW System has been declared INOPERABLE and appropriate TSA entries have been made per SO 48.7.A Precaution 3.1.

INITIATING CUE The Control Room Supervisor directs you to makeup to the Emergency Cooling Tower to a level of 18 ft 3 in, then restore to a normal lineup, using the "A" HPSW Pump / Heat Exchanger lAW SO 48.7.A "Emergency Cooling Water System Makeup To Tower Using A High Pressure Service Water Pump"

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET Peach Botto Limerick Common

~ JPM D QUALIFICATION MANUAL D OJT MODULE Licensed Operator Requalification PLOR-044C Licensed Operator Requalification 018 M. J. Kelly jav Manually Start SBGT System APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _-.JI_ _-.JI_ __

NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR044C Rev018.doc Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-..JPM DESIGNATOR: 2610050101 / PLOR-044C KIA: 261000A4.03 URO: 3.0 SRO: 3.0 TASK DESCRIPTION: Manually Startup the SBGT System A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical ..IPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critica.l JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR044C Rev018.doc Page 2 of 5

B. TOOLS AND EQUIPMENT l\Jone

v. REFERENCES

1. Procedure SO 9A.1.B Rev. 9, "Standby Gas Treatment System Manual Startup"

2. Procedure ST-0-09A-500-2, Rev. 4 "Standby Gas Treatment Filter Train Operation Log" D. TASK STANDARD

1. Performance Location: Simulator

2. Satisfactory task completion is indicated when Standby Gas Treatment System in operation with:

a. "A" or "B" SBGT fan running.

b. "A" Filter train in service.

3. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to manually start the Standby Gas Treatment System using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Standby Gas Treatment System is lined up for automatic operation in accordance with SO 9A.1 .A, "Standby Gas Treatment System Lineup for Automatic Operation".

2. Standby Gas Treatment System is required for HPCI System operation.

3. The "B" SBGT filter train run time is greater than the "A" SBGT filter train run time.

4. Data required by ST 09A-500-2 "Standby Gas Treatment Filter Train Operation Log" is being completed by another Reactor Operator.

G. INITIATING CUE The Control Room Supervisor directs you to start the Standby Gas Treatment System in preparation for HPCI System operation using SO 9A.1.B "Standby Gas Treatment System Manual Startup".

PLOR044C Rev018.doc Page 3 of 5

H. PERFORMANCE CHECKLIST II STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure P A copy of procedure SO 9A.1.B is SO 9A.1.B. obtained.

2 Notify Health Physics prior to starting P Health Physics has been notified that SBGT for Unit 2 HPCI operations. SBGT is going to be started.

(Cue: Health Physics acknowledges noti'fication. )

• 3 Open AO-00475-1, SBGT IIAII Filter P AO-00475-1 control switch is placed in Inlet damper. the "OPEN" position at panel 20C012.

(Cue: Acknowledge control switch operation.)

4 Verify AO-00475-1 SBGT "All Filter P AO-00475-1 red light is verified ON at Inlet damper is open. pane120C012.

(Cue: AO-0475-1 red light is on, green light is off.)

5 Acknowledge the "STAND-BY GAS P The annunciator "ACKNOWLEDGE" TREATMENT FILTERS NOT IN pushbutton is depressed at panel AUTO" annunciator. 20C012.

(Cue: Annunciator 216 A-5 is not lit.)

• 6 Open AO-00475-2 SBGT "A" Filter P AO-00475-2 control switch is placed in Outlet damper. the "OPEN" position at panel 20C012.

(Cue: Acknowledge control switch operation.)

7 Verify AO-00475-2 SBGT "A" Filter P AO-00475-2 red light is verified ON at Outlet damper is open. pane120C012.

(Cue: AO-00475-2 red light is on, green light is off.)

8 Verify AO-20469-1 DIW Rx Bldg Equip P AO-20469-1 green light is verified ON at Exh damper is closed. panel 20C012.

(Cue: AO-20469-1 green light is on, red light is off.)

II PLOR044C Rev018.doc Page 4 of 5

STEP NO STEP ACT STANDARD 9 Verify AO*20469*2 DIW Rx 81dg Equip P AO-20469-2 green light is verified ON at Exh damper is closed. panel 20C012.

(Cue: AO-20469*2 green light is on, red light is off.)

• • • NOTE TO EVALUATOR ***

The candidate has the choice of either "A" or "B" SBGT Fan since system operation is in support of HPCI operation. See NOTE at Step 4.4 of SO 9A.1.B.

• 10 Start nA" or "8" S8GT Fan. P "A" or "8" S8GT Fan control switch is placed in the "RUN" position at panel (Cue: Acknowledge control switch 20C012.

operation.)

11 Verify the proper start of the "An or "8" P "A" or "8" S8GT Fan red light is S8GT Fan.

(Cue: nA" or "8" S8GT Fan red light is on, green light is off.)

• • • NOTE TO EVALUATOR ***

SBGT system flows and system differential pressures do not need to be verified in a specific range for HPCI System operation per step 4.4.1. Procedure steps 4.4.1, 4.4.2, and 4.4.3 can be skipped.

12 Inform Control Room Supervisor of P Task completion reported.

task completion.

(Cue: Control Room Supervisor acknowledges report.)

13 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND I procedures.

Under "ACT' p. must perform S

• must simulate I. TERMINATING CUE When S8GT system is running to support HPCI operation, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR044C Rev018.doc Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. Standby Gas Treatment System is lined up for automatic operation in accordance with SO 9A.1.A, "Standby Gas Treatment System Lineup for Automatic Operation".

2. Standby Gas Treatment System is required for HPCI System operation.

3. The "B" SBGT filter train run time is greater than the"A" SBGT filter train run time.

4. Data required by ST-0-09A-500-2 "Standby Gas Treatment Filter Train Operation Log" is being completed by another Reactor Operator.

INITIATING CUE The Control Room Supervisor directs you to start the Standby Gas Treatment System in preparation for HPCI System operation using SO 9A.1.B "Standby Gas Treatment System Manual Startup".

Exelon Nuclear Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET Common JPM QUALIFICATION MANUAL

===-------------~==-------------

D OJT MODULE Licensed Operator Training PLOR-346PA Licensed Operator Requalification 000 J. A. Verbillis jav Manual Operation Of Scoop Tube Positioner (Alternate Path - Hand Crank Fails To Engage)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Date EFFECTIVE DATE: _ _ _.1 _ _ _- ' _ _ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE I.D. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date II PLOR346PA RevOOO.doc Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2020100401/ PLOR-346PA KIA: 202001 A4.08 URO: 3.2 SRO: 3.1 TASK DESCRIPTION: Manual Operation of Scoop Tube Positioner (Alternate Path - Hand Crank Fails to Engage)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this ..IPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR346PA RevOOO.doc Page 2 ot6

B. TOOLS AND EQUIPMENT

1. None C. REFERENCES

1. AO 2D.2-2, Rev. 7, "Recirculation MG Set Scoop Tube Manual Operation" D. TASK STANDARD

1. Satisfactory task completion is indicated when the 2A Recirculation MG Set speed has been reduced to 1400 RPM using manual control of the MG Set Scoop Tube Positioner.

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to take manual control of the 2A Recirculation MG Set Scoop Tube Positioner using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Prerequisites for AO 2D.2-2, "Recirculation MG Set Scoop Tube Manual Operation" are complete.

2. 2A Recirculation pump M/A Station is NOT operable.

3. 2A Recirculation pump speed is 1420 RPM.

4. Recirculation flow reduction is required.

5. 2A Recirculation pump Scoop Tube Positioner has been locked up.

G. INITIATING CUE The Control Room Supervisor directs you, the extra RO, to take manual control of the 2A Recirculation MG Set Scoop Tube Positioner and reduce its speed to 1400 RPM using AO 2D.2-2, "Recirculation MG Set Scoop Tube Manual Operation".

PLOR346PA RevOOO.doc Page 3 of 6

H. PERFORMANCE CHECKLIST

• STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure AO 20.2-2. P A copy of procedure AO 20.2-2 is obtained.

2 Establish constant communications with S Communications (Radio) with Control Control Room. Room Operator established.

(Cue: Evaluator responds as Control Room Operator.)

• • • • NOTE ****

Reinforce to Examinee the importance of simulating ALL manipulations during the conduct of this JPM.

• • • • NOTE ****

The Alternate Path portion of this JPM begins with the next step.

3 For the 2A Recirc MG set, depress the S 2A Recirc MG set MANUAL plunger MANUAL plunger next to the manual hand depressed.

crank.

(Cue: Inform candidate that plunger spring returns to normal position.)

4 Rotate hand crank in the COUNTER- S Hand crank turned in the COUNTER CLOCKWISE direction in an attempt to CLOCKWISE direction.

reduce the speed of the 2A Recirculation MG Set.

(Cue: When candidate indicates rotation of hand crank, inform the candidate that NO resistance is felt.)

(Cue: IF the candidate asks the Control Room Operator for Recirc Speed change, report NO CHANGE in 2A Recirc Pump Speed.)

• 5 RECOGNIZE the failure of the handwheel P Candidate should recognize failure of to engage hand crank mechanism to latch based on lack of resistance and lack of speed change.

PLOR346PA RevOOO.doc Page 4 of 6

STEP NO STEP ACT STANDARD

• • • Note to Evaluator***

The following step may have been accomplished with initial rotation of handwheel. It is acceptable to NOT rotate handwheel an additional rotation provided a full turn was made after plunger was initially depressed.

6 Rotate hand crank one full turn. S Hand crank turned one full turn (Cue: Hand crank is turned one full turn.)

• 7 Depress the MANUAL plunger next to the S 2A Recirc MG set MANUAL plunger manual hand crank. depressed.

(Cue: Inform candidate that plunger spring returns to normal position.)

• 8 Rotate hand crank in the COUNTER S Hand crank turned in the COUNTER CLOCKWISE direction in an attempt to CLOCKWISE direction. Speed reduction reduce the speed of the 2A Recirculation recognized.

MG Set to 1400 RPM.

IF the candidate indicates rotation in the (Cue: When candidate indicates rotation CLOCKWISE direction, report that speed of hand crank, inform the candidate that is RISING and reactor power is RISING, resistance is felt.) and grade this step as UNSAT.

(Cue: IF the candidate asks the Control Room Operator for Recirc Speed change, report CHANGE in 2A Recirc Pump Speed of 5 RPM for each simulated revolution. IF candidate asks for plant response, report that reactor power is lowering.)

• 9 Reduce the speed of the 2A Recirculation S Hand crack positioned 4 rotations in the MG Set to 1400 RPM by making a total of COUNTER-CLOCKWISE direction.

4 rotations in the COUNTER-CLOCKWISE direction.

(Cue: Report CHANGE in 2A Recirc Pump Speed of 5 RPM for each simulated revolution. IF candidate asks for plant response, report that reactor power is lowering.)

PLOR346PA RevOOO.doc Page 5 of 6

STEP NO STEP ACT STANDARD 10 Verify the 2A Recirculation MG Set speed S 2A Recirculation MG Set speed reduction is 1400 RPM. is verified by communicating (radio) with the Control Room Operator.

(Cue: Control Room Operator reports that 2A Recirculation MG Set speed is 1400 RPM. Inform candidate that no further speed adjustment is required.)

11 Inform Control Room of task completion. S Task completion reported using radio, telephone, or plant page system.

I (Cue: Acknowledge report.)

12 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND i procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the speed of the 2A Recirc MG set has been reduced to 1400 RPM, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR346PA RevOOO.doc Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Prerequisites for AO 20.2-2, "Recirculation MG Set Scoop Tube Manual Operation" are complete.

2. 2A Recirculation pump M/A Station is NOT operable.

3. 2A Recirculation pump speed is 1420 RPM.

4. Recirculation flow reduction is required.

5. 2A Recirculation pump Scoop Tube Positioner has been locked up.

INITIATING CUE The Control Room Supervisor directs you, the extra RO, to take manual control of the 2A Recirculation MG Set Scoop Tube Positioner and reduce its speed to 1400 RPM using AO 20.2-2, "Recirculation MG Set Scoop Tube Manual Operation".

EXELON NUCLEAR Nuclear Generation Group OJTrrPE MATERIAL COVERSHEET each Bottom 011 Limerick I D Common

~ JPM D QUALIFICATION MANUAL D OJT MODULE Licensed Operator Training PLOR-334PA Licensed Operator Requalification 02 M. J. Kelly Swapping EHC System Pressure Regulators - Unit 3 (Alternate Path - Backup Pressure Regulator Instabilities)

APPROVALS:

Signature / Title Date Signature / Title Date Signature I Title Date Signature Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _--'1_ _---'1_ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE 1.0. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

LMS ENTRY:

Signature/Date PLOR334PA Rev002.doc Page 1 of 7

EXELON NUCLEAR PEACH BOnOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK~JPM DESIGNATOR: 2480260401/ PLOR~334PA KIA: 241000A2.01 RO: 3.5 SRO: 3.7 TASK DESCRIPTION: Swap EHC Pressure Regulators A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps {P}

shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non~time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR334PA RevO02.doc Page 2 of 7

B. TOOLS AND EQUIPMENT

1. AO 10.1-3 "Swapping EHC Pressure Regulators" with steps 4.1.1, 4.1.2, and 4.1.3 already signed off and documenting that the 3A EHC pressure regulator is in control.

C. REFERENCES

1. AO 10.1-3, Rev.3, Swapping EHC Pressure Regulators D. TASK STANDARD

1. Satisfactory task completion is indicated when it is identified that the backup Unit 3 EHC pressure regulator is not providing stable RPV pressure control and the original pressure regulator is placed back in-service.

2. Estimated time to complete: 25 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to swap Unit 3 EHC System pressure regulators using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 3 power level has been reduced from 100% to 99% due to observed 1 to 2 psig swings in RPV pressure.

2. The EHC System is in service in accordance with SO 1D.1.A-3, "EHC Oil System Startup and Normal Operations."

3. The 'A' pressure regulator in is service. The "A IN CONTROL" lamp is lit on both the 30C008A panel in the Main Control Room and the 30C030 panel in the Cable Spreading Room

4. Permission to swap EHC pressure regulators has been granted by both the Unit 3 Reactor Operator and the Control Room Supervisor.

5. Steps 4.1.1 through 4.1.3 of AO 10.1-3 "Swapping EHC Pressure Regulators" are complete.

G. INITIATING CUE The Control Room Supervisor directs you to swap from the 3A to the 38 EHC pressure regulator using procedure AO 10.1-3 "Swapping EHC Pressure Regulators".

PLOR334PA RevO02.doc Page 3 of 7

H. PERFORMANCE CHECKLIST

• ""'TEP STEP ACT STANDARD 1\10

• • NOTE **

Reinforce to Candidate the importance of simulating ALL manipulations during the conduct of this JPM.

1 Obtain a copy of procedure AO 1D.1-3. P A copy of procedure AO 1D.1-3 is obtained.

(Cue: provide AO 1D.1-3 "Swapping EHC Pressure Regulators" with steps 4.1 .1 ,

4.1.2, and 4.1.3 already signed off and documenting that the 3A EHC pressure regulator is in control.)

2 Record initial Pressure Setpoint Bias P On EHC panel 30C030 record Pressure potentiometer reading. Setpoint Bias potentiometer reading in step 4.1.4 of AO 1D.1-3. Place initials on (Cue: Pressure setpoint bias same step.

potentiometer indicates 4.53.)

• • NOTE **

Candidate should utilize Section 4.3 of AO 1 D.1-3.

3 Slowly turn the Pressure Setpoint Bias S On panel 30C030 in the Cable Spreading potentiometer CLOCKWISE. Room, unlock and SLOWLY turn the pressure setpoint bias potentiometer in the CLOCKWISE direction. SLOWLY (Cue: Acknowledge potentiometer means 1/8 of a turn (0.12 to 0.13 operation. After 4 to 5 operations of the indicated) every 30 seconds.

potentiometer in the CLOCKWISE direction, state that both the "A and BIN CONTROL" lamps are illuminated.)

4 Record the Pressure Setpoint Bias P Record the Pressure Setpoint Bias potentiometer reading when both the "A potentiometer reading on AO 1D.1-3, step and B IN CONTROL" lamps are 4.3.2.

illuminated.

(Cue: Report that the potentiometer is indicating 5.12.)

PLOR334PA Rev002.doc Page 4 of 7

STEP STEP ACT STANDARD NO

• 5 Continue Slowly turning the Pressure S On the 30C030 in the Cable Spreading Setpoint Bias potentiometer CLOCKWISE Room, SLOWLY turn the Pressure until only the "B IN CONTROL" lamp is Setpoint Bias potentiometer in the illuminated. CLOCKWISE direction until it is observed that the "B IN CONTROL" lamp is lit and (Cue: The "B IN CONTROL" lamp is lit. the "A IN CONTROL" lamp is not lit.

The "A IN CONTROL" lamp is NOT lit.

Report that the potentiometer is indicating SLOWLY means 1/8 of a turn (0.12 to 5.30.) 0.13 indicated) every 30 seconds.

• 6 Slowly turn the Pressure Setpoint Bias S On the 30C030 in the Cable Spreading potentiometer CLOCKWISE 0.75 turns Room, SLOWLY turn the Pressure past the position at which the "B IN Setpoint Bias potentiometer in the CONTROL" lamp lit. CLOCKWISE direction to obtain a pOSition 3A of a turn from where the "B IN (Cue: Acknowledge potentiometer CONTROL" lamp lit.

motion in the CLOCKWISE direction.

Report that the potentiometer is indicating SLOWLY means 1/8 of a turn (0.12 to 5.87. REPORT that the Main Control 0.13 indicated) every 30 seconds.

Room is observing a rise in reactor pressure instabilities of 3 to 4 psig RPV pressure swings.)

• • NOTES TO EVALUATOR**

A. The Alternate Path portion of this JPM begins with the next step.

B. The Candidate determines that the 3A Pressure Regulator should be placed back in service based on precaution Step 3.1 of AO 10.1 ~3.

C. The Candidate can place the 3A Pressure Regulator back in service by utilizing Section 4.2 of AO 10.1-3 OR by immediately reversing steps previously performed based on precaution Step 3.1 of AO 1 0.1-3.

O. IF the candidate interacts with the evaluator as supervision asking for direction as to how to proceed, the evaluator should cue the candidate to "Comply with the procedural guidance." The intent is to ensure the candidate identifies and carriers out the direction provided in precaution 3.1 to return the system to previous alignment without inappropriate cueing.

PLOR334PA Rev002.doc Page 5 of 7

STEP STEP ACT STANDARD NO

• 7 Slowly turn the Pressure Setpoint Bias S On the 30C030 in the Cable Spreading potentiometer COUNTER-CLOCKWISE. Room, SLOWLY turn the Pressure Setpoint Bias potentiometer in the (Cue: Acknowledge potentiometer COUNTER-CLOCKWISE direction.

operation. After 4 to 5 operations of the SLOWLY means 1/8 of a turn (0.12 to potentiometer in the COUNTER- 0.13 indicated) every 30 seconds.

CLOCKWISE direction, state that both the "A and B IN CONTROL" lamps are ilium inated J

• • NOTE TO EVALUATOR**

The following step is only applicable if utilizing Section 4.2 of AO 1 0.1-3.

8 Record the Pressure Setpoint Bias P Record the Pressure Setpoint Bias potentiometer reading when both the "A potentiometer readings on AO 10.1-3, and B IN CONTROL" lamps are step 4.2.2.

illuminated.

(Cue: Report that the potentiometer is indicating 5.28.)

• 9 Continue slowly turning the Pressure S On the 30C030 in the Cable Spreading Setpoint Bias potentiometer COUNTER- Room, SLOWLY turn the Pressure CLOCKWISE until only the "A IN Setpoint Bias potentiometer in the CONTROL" lamp is illuminated. COUNTER-CLOCKWISE direction until it is observed that the "A IN CONTROL" (Cue: The "A IN CONTROL" lamp is lit. lamp is lit and the "B IN CONTROL" lamp The "A IN CONTROL" lamp is NOT lit. is not lit.

Report that the Pressure Setpoint Bias potentiometer indicates 5.10.) SLOWLY means 1/8 of a turn (0.12 to 0.13 indicated) every 30 seconds.

• 10 Slowly turn the Pressure Setpoint Bias S On the 30C030 in the Cable Spreading potentiometer COUNTER-CLOCKWISE Room, SLOWLY turn the Pressure 0.75 turns past the position at which the Setpoint Bias potentiometer in the "A IN CONTROL" lamp lit. COUNTER-CLOCKWISE direction to obtain a position 3;4 of a turn from where (Cue: Acknowledge potentiometer the "A IN CONTROL" lamp lit.

motion in the COUNTER-CLOCKWISE direction. Report that the Pressure SLOWLY means 1/8 of a turn (0.12 to Setpoint Bias potentiometer indicates 0.13 indicated) every 30 seconds.

4.53. Report that RPV pressure has returned to the original 1 to 2 psig swings.}

PLOR334PA RevO02.doc Page 6 of 7

STEP STEP ACT STANDARD NO

• • NOTE TO EVALUATOR**

The following step is only applicable if utilizing Section 4.2 of AO 1 0.1-3.

11 Record final reading for the Pressure P Record the Pressure Setpoint Bias Setpoint Bias potentiometer. potentiometer reading on AO 1D.1-3, step 4.2.8.

(Cue: Potentiometer is reading 4.53.)

• • NOTE TO EVALUATOR**

At this time report that steps 4.4 and 4.5 of AO 10.1-3 are being performed by the Main Control Room.

12 Inform Control Room of task completion. S Task completion reported using telephone or plant page system.

13 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT' P - must perform S - must simulate I. TERMINATING CUE When the original 3A EHC Pressure Regulator has been placed back in service, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR334PA Rev002.doc Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1. Unit 3 power level has been reduced from 100% to 990/0 due to observed 1 to 2 psig swings in RPV pressure.

2. The EHC System is in service in accordance with SO 1 D.1.A-3, "EHC Oil System Startup and Normal Operations. "

3. The 'A' pressure regulator in is service. The "A IN CONTROL" lamp is lit on both the 30C008A panel in the Main Control Room and the 30C030 panel in the Cable Spreading Room

4. Permission to swap EHC pressure regulators has been granted by both the Unit 3 Reactor Operator and the Control Room Supervisor.

5. Steps 4.1.1 through 4.1.3 of AO 1D.1-3 "Swapping EHC Pressure Regulators" are complete.

INITIATING CUE The Control Room Supervisor directs you to swap from the 3A to the 38 EHC pressure regulator using procedure AO 1 D.1-3 "Swapping EHC Pressure Regulators".

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET mil Peach Bottom 1\ 011 Limerick I 011 Common I D QUALIFICATION MANUAL D OJT MODULE icensed Operator Training PLOR-096P

'censed Operator Requalification Training 016 J. R. Felice rja Loss of RBCCW (Plant Actions for the Instrument Nitrogen System)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _ _----JI_ _----JI_ __

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE I.D. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMSCODE:

I LMS ENTRY:

Signature/Date PLOR096P Rev016.doc Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2002000401 / PLOR-096P KIA: 295018AA 1.01 RO: 3.3 SRO: 3.4 TASK DESCRIPTION: LOSS OF RBCCW (PLANT ACTIONS FOR THE INSTRUMENT NITROGEN SYSTEM)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3. JPM Performance

a. "Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4. Satisfactory performance of this JPM is accomplished if:

a. The task standard is met.

b. JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR096P ReV016.doc Page 2 of 5

B. TOOLS AND EQUIPMENT None C. REFERENCES Procedure ON-113, Rev. 18, "Loss of RBCCW" D. TASK STANDARD

1. Satisfactory task completion is indicated when

a. The Instrument Air System is supplying the Instrument Nitrogen System.

b. The Instrument Nitrogen Compressors have been shutdown.

2. Estimated time to complete: 17 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to lineup the Unit 2 Instrument Air System to supply the Instrument Nitrogen System and trip the Instrument Nitrogen Compressors, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

- TASK CONDITIONS/PREREQUISITES

1. RBCCW has been lost on Unit 2.

2. ON-113, "Loss of RBCCW" is in progress.

G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform steps 2.10 and 2.11 of ON-113, "Loss of RBCCW" on Unit 2.

PLOR096P Rev016.doc Page 3 of 5

H. PERFORMANCE CHECKLIST II STEP STEP ACT STANDARD NO 1 Obtain a copy of procedure ON-113. P A copy of procedure ON-113 is obtained.

• 2 Open AO-4230A "A" Instrument Air S SV-4230A control switch is placed in the Backup to "A" Instrument N2 Header valve. OPEN position at the local control station, 2AC839 on Reactor Building 135' (Cue: Acknowledge control switch Elevation, SDV area.

operation.)

3 Verify AO-4230A "A" Instrument Air P AO-4230A red light is veri'fied ON at the Backup to "A" Instrument N2 Header valve local control station, 2AC839 on Reactor is open. Building 135' Elevation, SDV area.

(Cue: AO-4230A red light is on, and green light is off.)

• 4 Open AO-4230B liB" Instrument Air S SV-4230B control switch is placed in the Backup to "B" Instrument 1\J 2 Header valve. OPEN position at the local control station, 2BC839 on Reactor Building 135' (Cue: Acknowledge control switch Elevation. (TIP Room Roof) operation.)

5 Verify AO-4230B "B" Instrument Air P AO-4230B red light is verified ON at the Backup to liB" Instrument N2 Header valve local control station, 2BC839 on Reactor is open. Building 135' Elevation. (TIP Room Roof)

(Cue: AO-4230B red light is on, and green light is off.)

• 6 Shutdown the "A" Instrument Nitrogen S "A" Instrument Nitrogen Compressor Compressor. control switch (HS-2-16-4225) is placed in the OFF position at the local control (Cue: Acknowledge control switch station, 2AC268 on Reactor Building 195' operation.) Elevation.

7 Verify the "A" Instrument Nitrogen P "A" Instrument Nitrogen Compressor OFF Compressor is shutdown. (green) light is ON at the local control station, 2AC268 on Reactor Building 195' Cue: The "A" Instrument Nitrogen Elevation.

Compressor control switch is in OFF and I green light is on.)

• 8 Shutdown the "B" Instrument Nitrogen S "B" Instrument Nitrogen Compressor Compressor. control switch (HS-2-16-4121) is placed in the OFF position at the local control (Cue: Acknowledge control switch station, 2BC268 on Reactor Building 195' operation.) Elevation.

9 Verify the liB" Instrument Nitrogen P "B" Instrument Nitrogen Compressor OFF Compressor is shutdown. (green) light is ON at the local control station, 2BC268 on Reactor Building 195' (Cue: The "B" Instrument Nitrogen Elevation.

Compressor control switch is in OFF and II green light is on.)

PLOR096P Rev016.doc Page 4 of 5

STEP STEP ACT STANDARD NO 10 Inform Control Room Supervisor of task S Task completion reported using telephone, completion. hand held radio, or GAI-TRONICS page system.

(Cue: Control Room Supervisor acknowledges report.)

11 As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND

,procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the Instrument Air backup valves to Instrument Nitrogen, AO-4230A and AO-4230B, are open and the Instrument Nitrogen Compressors have been shutdown, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR096P Rev016.doc Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. RBCCW has been lost on Unit 2.

2. ON-113, "Loss of RBCCW" is in progress.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform steps 2.10 and 2.11 of ON-113, "Loss of RBCCW" on Unit 2.

SIMULATOR OPERATOR INSTRUCTIONS FOR 2011 NRC SCENARIO #1 GENERAL REQUIREMENTS

• Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

• All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

• All markable procedures, boards, etc. will be erased.

• All paper used by the crew will be retained for the examination team as requested.

• The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

• This is a new scenario developed for the 2011 NRC ILT Exam.

INITIAL SETUP Initial Conditions

• IC-S1, 100% power, created from IC-14

• Ensure recorder power is on; roll recorders as required

• Ensure annunciator horns are active Blocking Tags

• None Activate APP "2011_NRC_SCN1", or insert the following:

Event Triggers None Malfunctions IMF MTA03C (E1 00) (Turbine stop valve #3 fails closed)

IMF HPC02 (E2 0 0) (HPCI spurious automatic start)

IMF HPC07 (E3 0 0) 5 20:00 0 (HPel steam supply line break)

Overrides lOR ZYP01A2A1S02 (none 0 0) NORMAL ('e' RFP discharge startup bypass MO-S090) lOR ZYP13A1S07 (none 0 0) OPEN (HPel steam line isolation valve MO-23-15) lOR ZYP13A1S05 (none 0 0) OPEN (HPCI steam line isolation valve MO-23-16) 2011 NRC Scenario #1 - T-103 HPCI Steam Leak, Rev O.doc

Remote Functions NOTE: the following Remote Function is activated manually (see Simulator Operator Directions for Event #2); it is NOT included in the APP file.

MRF T210_3 MIN (closes CRD pump suction strainer isolation to simulate clogged strainer)

Trip Overrides MRF HP004TO Override (HPCI isolation override - includes K27, K28, K36, K57 relays)

MRF MGA01 TO Override (Main Generator 86 lockout relay)

Batch Files None Turnover Procedures

• SO 55.6.A-O, 480V Auxiliary Load Center Cross-Tie 2011 NRC Scenario #1 - T-I03 HPCI Steam Leak, Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 1 Support the crew as necessary to perform SO 55.6.A-O "480V Auxiliary Load Center Cross-Tie" .

EVENT 2 After the 480V load centers are cross-tied, or when directed by the Lead Examiner, MRF T210_3 MIN to simulate a clogged CRD pump suction strainer.

NOTE: The local horn and beacon are auto resetting. If an operator is sent to verify the horn and beacon it will not be alarming if the pump has already tripped.

If directed to investigate the 'A' CRD pump I breaker, report the pump I breaker appear normal.

When directed to bypass and isolate the suction filter, wait approximately 2 minutes, then MRF T210_3 MAX and report that the suction filter is bypassed and isolated.

If directed to make the '8' CRD pump ready for start, then wait 4 minutes and report that it is ready for start.

When directed to open the '8' CRD pump discharge valve, MRF CRH02 OPEN.

EVENT 3 After the CRD system is returned to service, or when directed by the Lead Examiner, initiate pending events on ET 1 (IMF MTA03) to cause turbine stop valve

1. 3 to fail closed.

EVENT 4 After reactor power has been lowered to 95% or when directed by the Lead Examiner, initiate pending events on ET 2 (IMF HPC02) to cause a spurious start of HPCI.

If an Equipment Operator is dispatched to investigate the HPCI start, wait approximately 5 minutes and report HPCI is operating normally.

EVENT 5 After the Tech Spec determination has been made, or when directed by the Lead Examiner, initiate pending events on ET 3 (IMF HPC07 5 20:00 0) to cause a HPCI steam supply line break.

Modify the leak severity as necessary to control the scenario pace and ensure a second Reactor 8uilding area exceeds the Action Level for temperature. This will vary based on the crew's action to depressurize the reactor.

EVENT 6 Following the GP-4 shutdown and Main Turbine Trip, the Main Generator will not lockout.

EVENT 7 When the URO attempts to establish RPV level control using MO-8090, the valve will not open.

2011 NRC Scenario #1 - T-I 03 HPCJ Steam Leak, Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 8 When the second area temperature exceeds the action level, the CRS will direct an emergency blowdown. The CRS may have directed a rapid depressurization with bypass valves prior the second parameter exceeding the action level.

TERMINATION The scenario may be terminated when 5 SRVS are open, the RPV is depressurized, and RPV level is under control.

2011 NRC Scenario #1 - T-103 HPCI Steam Leak, Rev O.doc

SHIFT TURNOVER PLANT CONDITIONS:

• Unit 2 is at 100% power.

INOPERABLE EQUIPMENT/LCOs:

• None SCHEDULED EVOLUTIONS:

• Cross-tie 480V auxiliary load center 1PS4 with 3PS4 (with 1PS4 supplying) to allow for scheduled preventive maintenance on the 1PS4 breaker.

o An Operational Risk review has been performed in accordance with WC-A-1 04 "Integrated Risk Management".

o The Director of Operations has approved the 480V cross-tie.

o Operations Management has determined no loads are required to be shed.

o The work on the load center breaker is expected to take 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCES DUE THIS SHIFT:

• None ACTIVE CLEARANCES:

• None GENERAL INFORMATION:

• None 2011 NRC Scenario # 1 - T -103 HPCI Steam Leak, Rev O.doc

CRITICAL TASK LIST

1. Following a positive reactivity addition, restore Reactor power below 100%.

2. When a Primary System is discharging into Secondary Containment through an unisolable leak, scram the Reactor prior to performing an Emergency Blowdown.

3. Perform T-112 "Emergency Blowdown" when the same parameter (temperature) exceeds a T -103 "Secondary Containment Control" Action Level in more than one area and the system breach has not been isolated.

OR Perform a rapid depressurization using RC/P-12 when the blowdown limit in T-103 is approached.

2011 NRC Scenario # 1 - T -103 HPCI Steam Leak, Rev O.doc

Operator Actions ES-O-2 Op Test No.: 1 Scenario No.: 1 Event No.: 1 Page: 10f12 Event

Description:

Cross-tie 480v auxiliary load center 1PS4 with 3PS4.

Cause: Required to allow for scheduled preventive maintenance on the 1PS4 breaker Effects: N/A Position Applicant's Actions or Behavior CRS Direct the PRO to Cross-tie 480v auxiliary load center 1PS4 with 3PS4 lAW SO 55.6.A-O, 480V Auxiliary Load Center Cross-Tie.

PRO Cross-tie load centers by performing the following:

• Hold closed the control switch for the 1-3 PS4 Tie Breaker on Panel 20C009.

• Open the 1PS4 BUS BKR on Panel 20C009.

• Verify the 1-3 PS4 Tie Breaker by observing the indicating lights and ammeter indications.

• Release the 1-3 PS4 Tie Breaker control switch.

2011 NRC Scenario #1 - T-103 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page: 20f12 Event

Description:

'A' CRD pump trip Cause: Clogged suction filter causes a low suction pressure trip of the 'A' CRD pump Effects: 1. Alarms:

• 211 F1 A' CRD Water Pump Trip"

• 211 F3 "'A' CRD Pump Suction LO Press"

2. 'A' CRD pump trip Position Applicant's Actions or Behavior URO Recognize and report the 'A' CRD pump trip.

Recognize and report entry into ON-107 "Loss of CRD Regulating Function".

Enter and execute ON-107 "Loss of CRD Regulating Function".

Enter and execute Alarm Response Card 211 F3 "'A' CRD Pump Suction LO Press".

Enter and execute Alarm Response Card 211 F1 "'A' CRD Water Pump Trip".

• Place the pump control switch for the 'A' CRD pump in the STOP position.

CRS Enter and execute ON-107 "Loss of CRD Regulating Function".

Determine that Unit 2 can operate for up to 20 minutes when the following conditions exist:

• Reactor Pressure> 900psig And

• Charging header pressure is < 940 psig And

• Two or more CRD accumulator trouble indicators are lit on withdrawn control rods.

Verify compliance with Tech Spec 3.1.5.B.

Determine that Unit 2 can operate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after receiving a valid CRD High Temperature alarm.

Direct bypassing the CRD pump suction filter and placing the 'B' CRD pump in service.

NOTE: step 2.4 of ON-107 directs placing the alternate CRD pump ('B' in this case) in service since the in-service pump did not trip "for reasons other than a CRD system related issue".

20]] NRC Scenario #1 - T-103 HPCI Steam Leak, Rev O.doc

Operator Actions OpTestNo.: 1 Scenario No.: 1 Event No.: 2 Page: 30f12 Event

Description:

'A' CRD pump trip (continued)

Position Applicant's Actions or Behavior URO Perform ON-107 actions:

• Direct an Equipment Operator to bypass and isolate the pump suction filter using step 2.3.1 -2.3.3 of ON-1 07.

• Start the 'B' CRD pump using SO 3.1.B-2 "Control Rod Drive Hydraulic System Startup with the System Filled and Vented".

o Direct an Equipment Operator to check the 'B' CRD pump per step 4.1 and standby for a start.

o Place the CRD flow controller in manual and close the flow control valve.

o Open MO-2-3-20 "Drive Water Pressure".

o Close MO-2-2A-8029 A and B "Seal Purge".

o Start the 'B' CRD pump.

o Direct an Equipment Operator to slowly open HV-2-3-36B.

o When CRD flow has stabilized and the CRD hydr:aulic accumulators have charged, then establish system flow.

• Adjust the flow controller for 55-65 gpm.

• Place the flow control valve in AUTO.

• Throttle MO-2-3-20 "Drive Water Pressure" to obtain 260 to 280 psid.

Restore recirc pump seal purge lAW SO 2A.1.C-2 "Operation of the Recirculation Pump Seal Purge System".

• Direct the Equipment Operator to perform steps 4.1.1 through 4.1.6 (for the 2A pump) and steps 4.2.1 through 4.2.6 (for the 2B pump).

• Open MO-8029A "Seal Purge Supply" for 2A Recirc pump.

• Open MO-8029B "Seal Purge Supply" for 2B Recirc pump.

• Direct Equipment Operator to adjust/verify seal purge flowrate in accordance with SO 2A.1.C-2.

CRS Direct monitoring recirc pump seal temperatures lAW ON-107.

PRO Monitor recirc pump seal temperatures and CRD temperatures, as directed.

2011 NRC Scenario # I - T-l 03 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page: 4of12 Event

Description:

Turbine stop valve fails closed I Reactor power reduction Cause: An internal fault in the control pac for #3 stop valve causes the stop valve to go closed Effects: Reactor pressure will rise due to the valve closure.

Reactor power will rise in response to the rise in RPV pressure.

Position Applicant's Actions or Behavior URO/PRO Recognize and report the rise in RPV pressure.

Recognize and report entry into OT-102 "Reactor High Pressure".

Enter and execute OT-102 "Reactor High Pressure".

URO/PRO Recognize and report the rise in reactor power.

Recognize and report entry into OT-104 "Positive Reactivity Insertion".

Enter and execute OT-104 "Positive Reactivity Insertion".

Exit OT-104 (per step 3.2).

CRS Enter and execute OT-102 "Reactor High Pressure".

Enter and execute OT-104 "Positive Reactivity Insertion".

Exit OT-104 (per step 3.2).

Recognize OT-102 requirement to reduce reactor thermal power within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to comply with Tech Spec 3.2.

Enter and execute GP-5 "Power Operation" per OT-102, step 3.5.

CRS Direct the URO to lower reactor power to ::;;95% (3338 MWth).

Verify operation is within the acceptable region of AO 1E. 4-2 "Planned Removal of the Fifth or Fourth Stage Feedwater Heaters for Service During End of Cycle Coastdown and Return to Normal Shutdown Condition" .

URO Lower reactor power using Recirc until reactor power ::;;95% (3338 MWth),

as directed.

20 II NRC Scenario # I - T -103 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 4 Page: 50f12 Event

Description:

Inadvertent HPCI initiation Cause: Initiation relay contacts short closed Effects: 1. Alarms:

• 222 0-5 "HPCI Auxiliary Oil Pump Running"

• 228 C-5 "HPCI Relays Not Reset"

2. HPCI injection to the RPV; reactor water level and reactor power increase Position Applicant's Actions or Behavior PRO Recognize and report HPCI initiation.

Verify, using at least two independent indications, misoperation of HPCI and/or adequate core cooling is assured.

URO Control feed pump speed I discharge pressure as necessary to maintain RPV water level below +35 inches.

CRS Enter and execute OT-104 "Positive Reactivity Insertion".

• Verify, using at least two independent indications, misoperation of HPCI and/or adequate core cooling is assured.

• Direct HPCI tripped in accordance with RRC 23.1-2 "HPCI System Operation during a Plant Event".

Enter and execute OT-110 "Reactor High Level".

• Direct maintaining RPV water level below +35 inches.

Review Tech Spec 3.3.5.1 and determine Condition B applies:

• Declare HPCI inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• Place the channel in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Review Tech Spec 3.5.1 and determine Condition C applies:

• Verify RCIC operability immediately.

• Restore HPCI to operable status within 14 days.

PRO Perform RRC 23.1-2 "HPCI System Operation During a Plant Event",

Section E, "HPCI Shutdown With Initiation Signal Present (short-term shutdown):

• Place Aux Oil Pump control switch in START.

• Place Vacuum Pump control switch in START.

• Depress and hold Remote Trip pushbutton.

• When turbine speed reaches - 0 RPM, place Aux Oil Pump control switch in P-T-L and release the Remote Trip pushbutton.

2011 NRC Scenario # I - T-l 03 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 1 Event No.: 5 Page: 60f12 Event

Description:

HPCI steam leak into Secondary Containment Cause: Unisolable HPCI steam line break in the HPCI room Effects: Secondary containment temperature and radiation levels will increase. First alarm to actuate is 210 J-3 "High Area Temp". This will cause an entry into T-103 "Secondary Containment Control".

Time Position Applicant's Actions or Behavior URO/PRO Recognize and report alarms 218 B-5 "Vent Exh Stack Rad Monitor HilTrouble A" and 218 C-5 "Vent Exh Stack Rad Monitor HilTrouble B" and enter the corresponding Alarm Response Cards.

Monitor RI-2979 to verify a valid signal.

Enter ON-104 "Vent Stack High Radiation".

CRS Enter ON-104 "Vent Stack High Radiation" and direct search for source of high vent exhaust radiation.

URO/PRO Recognize and report alarms 218 B-4 "Vent Exh Stack Rad Monitor Hi-Hi A" and 218 C-4 "Vent Exh Stack Rad Monitor Hi-Hi Bn.

Announce T-104 "Radiation Release" entry.

CRS Enter/direct actions lAW T-104 "Radioactivity Release Control".

• Initiate dose assessment.

• Determine radiation release occurring in the Reactor Building.

• Direct a GP-15 evacuation of the Reactor Building.

PRO/URO Recognize and report the "High Area Temp" (210 J-3).

Recognize and report the Fire Panel alarm (007C-6 Lower).

PRO Report the temperature rise on HPCI room temperature (Point #3).

Report the temperature alarm as an entry into T-103 "Secondary Containment Control".

2011 NRC Scenario #) - T-103 HPCI Steam Leak, Rev O.doc

Operator Actions Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page: 7of12 Event

Description:

HPCI steam leak into Secondary Containment (continued)

Position Applicant's Actions or Behavior CRS Enter and direct T-103 "Secondary Containment Control".

• Monitor and control secondary containment temperatures.

• Perform a local evacuation lAW GP-15.

• Direct operators to isolate all systems discharging into the area except systems required to suppress a fire or are required by the TRIP procedures.

• Determine a primary system is discharging into the Reactor Building.

PRO Monitor secondary containment temperatures on TR-2-13-139.

Inform the CRS of the inability to isolate HPCI.

Perform a GP-15 local evacuation as directed.

CT CRS Direct a GP-4 "Manual Reactor Scram" before HPCI room temperature (Point #3) exceeds the action level of 150 degrees F.

Enter and direct T-101 "RPV Control".

CT URO Perform GP-4 "Manual Reactor Scram" as directed:

• Place the mode switch to SHUTDOWN.

• Verify control rods are inserting.

• Verify APRMs are downscale.

• When RPV level begins to recover, then "Emergency Stop" all 3 RFPTs.

• Depress "SLOW RAISE" or "FAST RAISE" on the RFPT to remain in service.

• Close all RFP discharge valves and open 'C' RFP discharge bypass valve. (See Event 7)

• Establish and maintain RPV level control with feedwater.

• Verify all control rods are inserted.

• Verify RPV pressure, trend, and status of EHC.

• Notify health physics of changing plant conditions.

2011 NRC Scenario #1 - T-I03 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 1 Event No.: 5 Page: 8of12 Event

Description:

HPCI steam leak into Secondary Containment (continued)

Position Applicant's Actions or Behavior PRO Perform GP-4 "Manual Reactor Scram" as directed:

• Transfer 13 KV house loads.

• Trip main turbine when directed by the CRS.

• Verify main generator lockout. (See Event 6)

• Verify Group II and III isolations and SGTS initiation.

• Verify scram discharge volume vents and drains are closed.

• Verify hydrogen water chemistry is isolated.

• Verify both recirc pumps speed have runback to 30%.

• Monitor instrument air header pressure and drywell pressure.

• When the CRS is ready, report scram actions.

CRS Direct the URO to control RPV level between +5" to +35" with feedwater.

Direct the PRO to bypass and restore instrument nitrogen to the drywell.

URO Control RPV level between +5" to +35" with feedwater.

PRO Bypass and restore drywell instrument nitrogen lAW RRC 94.2-2 or GP-8E.

• Place AO-2969A control switch to "CLOSE".

• Place AO-2969B control switch to "CLOSE".

• Place Drywellinstrument Nitrogen Bypass Switch 16A-S100 in the "BYPASS" position.

• Place Drywell Instrument Nitrogen Bypass Switch 16A-S99 in the "BYPASS" position.

CRS Direct RPV depressurization lAW T-101 "RPV Control" URO/PRO Perform RPV depressurization using the Bypass Valves, as directed.

2011 NRC Scenario #1 - T-l03 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 1 Event No.: 6 Page: 90f12 Event

Description:

Generator lockout fails to occur following Main Turbine trip Cause: Failure in the generator lockout circuit Effects: Main Generator output breakers fail to open Main Generator exciter field breaker fails to open Position Applicant's Actions or Behavior PRO Recognize the failure of the Main Generator lockout while performing PRO scram actions.

Open the Main Generator output breakers (215 BKR and 225 BKR).

Open the exciter field breaker (ALT EXC FLO BKR 41-0601).

Report to the CRS that the Main Generator lockout failed and that you manually opened the Main Generator output breakers and the field breaker.

2011 NRC Scenario #1 - T-103 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 7 Page: 10 of 12 Event

Description:

'C' reactor feedpump discharge bypass valve fails to open Cause: Failure of the motor operator for MO-8090 ('C' feed pump discharge bypass) to engage and open the valve Effects: RPV level must be controlled using the RFP discharge valve and not the RFP bypass, complicating post-scram and post blowdown Reactor level control.

Position Applicanfs Actions or Behavior URO Recognize the failure of MO-8090 to open during URO scram actions.

Throttle open RFP discharge valve MO-2149A, B or C.

Maintain RPV level by controlling RFP discharge valve position and RFP speed (pump discharge pressure).

NOTE: when RFP's are no longer available (e.g., following emergency depressurization), the RPF discharge valve must be throttled to control Condensate flow to the RPV.

2011 NRC Scenario #1 - '1'-103 HPCI Steam Leak, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 1 Event No.: 8 Page: 11 of 12 Event

Description:

Emergency blowdown due to exceeding Reactor Building temperature limits in more than one area Cause: Steam leak in the Reactor Building continues to degrade Secondary Containment parameters Effects: RPV depressurization via Bypass Valves and ADS SRVs Position Applicant's Actions or Behavior CT CRS When a second Reactor Building area temperature approaches the Action Level, direct the URO to perform a rapid depressurization using T-101, RC/P-12.

CT URO Rapidly depressurize the reactor by opening all Main Turbine bypass valves.

CT CRS When the same parameter exceeds an action level in more than one area (HPCI Room and Torus Room) and the primary system breach has not been isolated, enter and execute T-112 "Emergency Blowdown":

• Verify torus level is above 7 feet.

• Verify RPV pressure is 50 psig or more above torus pressure.

• Direct 5 ADS SRVs opened.

CT PRO When directed, open 5 ADS SRVs by placing their control switches in OPEN.

TERMINATION CRITERIA:

The scenario may be terminated when 5 SRVS are open, the RPV is depressurized, and RPV level is under control.

2011 NRC Scenario #1 - T-I03 HPCI Steam Leak, Rev O.doc

Operator Actions ES-O-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page: 12 of 12 Event

Description:

EAL classification Position Applicant's Actions or Behavior CRS Determine EAL classification using EP-AA-1007.

• Based on the scenario conditions and expected outcome, the CRS will classify the event as FS 1 Based on a Loss of the Primary Containment Barrier and a Potential loss of the Reactor Coolant System Barrier.

• Based on the scenario conditions and expected outcome, the CRS should determine that there is a Release in Progress.

2011 NRC Scenario #1 - 1'-103 HPCI Steam Leak. Rev O.doc

SIMULATOR OPERATOR INSTRUCTIONS FOR 2011 NRC SCENARIO #2 GENERAL REQUIREMENTS

• Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

• All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

• All markable procedures, boards, etc. will be erased.

• All paper used by the crew will be retained for the examination team as requested.

• The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

• This is a modified scenario that was originally developed for the 2009 NRC ILT Exam.

INITIAL SETUP Initial Conditions

• IC-82, 100% power

• Ensure recorder power is on; roll recorders as required

• Ensure annunciator horns are active Blocking Tags

• None Activate APP "2011_NRC_SCN2", or insert the following:

Event Triggers None Malfunctions IMF PCI01V (none 0 0) (RWCU INBO isolation valve (MO-15) failure)

IMF PCI01W (none 0 0) (RWCU OTBO isolation valve (MO-18) failure)

IMF PCI01X (none 0 0) (RWCU OTBO isolation valve (MO-68) failure)

IMF TBW04B (none 0 0) (TBCCW pump 'B' auto start failure)

IMF TBW01A (E1 00) (TBCCW pump lA' Trip)

IMF RRS08A (E3 0 0) (Recirc M-G drive motor 'A' breaker trip)

IMF SWC01 (E4 3:00 0) (loss of Stator Water Cooling with a three-minute time delay) 2011 NRC Scenario #2 - T-I17 Electric ATWS, Rev O.doc

Overrides lOR ZYP02A5S14 (none 0 0) NORMAL (Drywell N2 valve 2969A isolation bypass) lOR ZYP02A5S12 (none 00) NORMAL (Drywell N2 valve 29698 isolation bypass) lOR ZYP04A4S22 (E2 010) START ('A' ESW pump spurious start; 10 second deactivation) lOR AN0209RA5 (E4 0 0) ALARM_ON (Stator cooiantlH2 seal oil trouble alarm 220 A-5) lOR AN0208RG5 (E41:30 0) ALARM_ON (Stator coolant standby pump run alarm 206 G-5)

Remote Functions None Trip Overrides Insert the following to provide an electrical ATWS:

MRF ARI01TO OVERRIDE MRF ARI02TO OVERRIDE MRF RPS01TO OVERRIDE MRF RPS02TO OVERRIDE MRF RPS03TO OVERRIDE MRF RPS04TO OVERRIDE MRF RPS05TO OVERRIDE MRF RPS06TO OVERRIDE Batch Files None Turnover Procedures

• RT-0-010-402-2 "Master Trip Solenoid Valves Operability Test" 2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 1 Support the crew as necessary for the Master Trip Solenoid Valves Routine Test.

EVENT 2 Following completion of the Master Trip Solenoid Valves RT, or when directed by the Lead Examiner, initiate pending events on ET1 (IMF TBW01A) to trip the 'A' TBCCWpump.

If directed to investigate the trip of the 'A' TBCCW pump, wait approximately ~

minutes and report there is the smell of burnt insulation at the 'A' TBCCW pump.

If directed to investigate the breaker for the 'A' TBCCW pump, wait approximately 1.

minutes and report the breaker is closed.

If requested to perform step 4.1 of SO 34.6.A-2 "Placing Standby TBCCW System Pump In Service" to vent the 'B' TBCCW pump, then wait approximately 2 minutes and report the step is complete and the pump is vented.

If directed to verify the operation of the 'B' TBCCW pump, then after the 'B' TBCCW pump is started, wait approximately 10 minutes and report the 'B' TBCCW pump is operating properly.

EVENT 3 When the 'B' TBCCW pump is in-service, or when directed by the Lead Examiner, initiate pending events on ET2 (lOR ZYP04A4S22 START) to cause a spurious start of the 'A' ESW pump.

lE directed to investigate the start of the 'A' ESW pump, wait 3 minutes and report that you are at the E-22 bus and there is a burnt electrical smell in the vicinity of the

'A' ESW pump breaker.

EVENT 4 When the Tech Spec determination is complete for the ESW pump, or when directed by the Lead Examiner, initiating pending events on ET3 (IMF RRS08A) to trip the "A' Recirc M-G Drive Motor Breaker.

Support the crew as necessary for GP-9 "Fast Power Reduction". Role-playas the Power System Director when called.

EVENT 5 When Single loop operation is established and the Tech Spec determination is complete or when directed by the Lead Examiner, initiate ET4 to initiate the following sequence of events (times are in minutes):

• T = 0 - Stator cooiantlH2 seal oil trouble 220 A-5 (lOR AN0209RA5)

• T = 1.5 - Stator coolant standby pump run 206 G-5 (lOR AN0208RG5)

• T =3.0 - Loss of stator cooling (IMF SWC01) 20 II NRC Scenario #2 - T -117 Electric ATWS, Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 5 When directed to investigate the Stator Coolant trouble alarm, wait 2 minutes then (continued) report "INLET FLOW lOW and INLET PRESSURE lOW are alarming on Panel 20C084; investigating the cause."

If directed to report the status of the standby stator cooling pump, report both pumps are running.

If directed to report Stator Cooling head tank level, report level is normal.

Pre-inserted malfunctions (Trip Overrides) will result in an electrical ATWS.

NOTE: Do not permit the operators to utilize the individual scram test switches on the RPS panels when performing T*213 "Scram Solenoid Deenergization."

When the applicant opens the panel, inform him/her that the individual scram switches are all in the down position.

When directed, provide support for T-220 as an Equipment Operator then wait approximately 4 minutes and MRF T220_2 CLOSE and report to the control room that HV-2-3-56 is closed.

When directed to perform T-221 on Unit 2, wait 5 minutes then MRF T221_1 DEFEAT.

After RPV level has been lowered to control power lAW T-240 and the APRM downscale lights are lit, then on the lead Examiner's cue insert control rods using T-214 "Venting the Scram Air Header" (MRF T214 VENT).

Report that you have commenced venting the scram air header lAW T-214.

EVENT 6 Pre-inserted malfunctions (PCI01V, W, X) will prevent RWCU from automatically isolating when SBlC is initiated.

EVENT 7 Pre-inserted failures (overrides) will prevent restoring normal drywell instrument nitrogen. This will prevent all non-ADS SRVs from being used for pressure control and/or depressurization. The crew should align Backup Instrument Nitrogen (bottles) to the ADS SRVs and/or request aligning CAD in accordance with T -261.

If directed to perform T-261 , wait 20 minutes then enter MRF T261_1 OPEN.

TERMINATION The scenario may be terminated when all control rods have been inserted and reactor level is being controlled above the top of active fuel.

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

SHIFT TURNOVER PLANT CONDITIONS:

• Unit 2 is at 100% power.

INOPERABLE EQUIPMENT/LCOs:

• None SCHEDULED EVOLUTIONS:

• RT-0-010-402-2 "Master Trip Solenoid Valves Operability Test" SURVEILLANCES DUE THIS SHIFT:

• RT 010-402-2 "Master Trip Solenoid Valves Operability Test" ACTIVE CLEARANCES:

• None GENERAL INFORMATION:

• Maintain current power.

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

CRITICAL TASK LIST

1. Before torus temperature exceeds the limits of the Heat Capacity Temperature Limit (HCTl) curve, lower reactor power by performing T-240 "Terminating and Preventing Injection" to lower RPV level until:

a. Reactor power is below 4%, OR

b. RPV level reaches -172 inches, OR

c. All SRVs remain closed and drywell pressure is below 2 psig.

2. Initiate a reactor shutdown by performing one or more of the following:

a. T-214 "Isolating and Venting the Scram Air Header"

b. T -220 "Driving Control Rods During a Failure to Scram"

c. Injecting Standby Liquid Control before torus temperature exceeds 110 degrees F (requires manual isolation of RWCU).

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 1 Page: 1of12 Event

Description:

Main turbine master trip solenoid valves routine test Cause: N/A Effects: None Position Applicant's Actions or Behavior CRS Direct PRO to perform RT-0-010-402-2 "Master Trip Solenoid Valves Operability Test".

PRO Perform RT-0-01 0-402-2 "Master Trip Solenoid Valves Operability Test":

• Review RT

• Place the Master Trip Test Selector switch to TRIP A

• Verify "Test An lamp if OFF

• Release and place Master Trip Test Selector switch to RESET

• Verify "Test An lamp if ON

• Place the Master Trip Test Selector switch to TRIP B

• Verify 'Test B" lamp if OFF

• Release and place Master Trip Test Selector switch to RESET

• Verify "Test B" lamp if ON

• Complete RT paperwork CRS Review RT for completeness/satisfactory results.

URO Monitor plant parameters/assist as directed.

2011 NRC Scenario #2 - T-117 Electric A TWS, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 2 Page: 2 of 12 Event

Description:

TBCCW pump failure / trip with failure of the standby pump to auto-start Cause: Failure of the 42 relay in the 'A' TBCCW pump motor circuit Failure of PS-2131 to actuate on low TBCCW System pressure Effects: 1. Alarm: 217 C-5 'TURB BLDG COOLING WATER SUPPLY LO PRESS"

2. Loss of cooling to TBCCW loads Position Applicant's Actions or Behavior URO Recognize annunciator 217 C-5 'TURB BLDG COOLING WATER SUPPLY LO PRESS" and report trip of 2A TBCCW pump. Respond lAW Alarm Response Card.

Place 2A TBCCW pump control switch to "OFF".

Recognize failure of 2B TBCCW pump to auto start after 20 seconds.

CRS Enter ON-118 "Loss of TBCCW".

Direct starting the 2B TBCCW pump.

Direct follow-up use of SO 34.6.A-2 "Placing Standby TBCCW System Pump In Service".

Direct troubleshooting.

URO Place 2B TBCCW pump control switch to "RUN".

Verify placing standby TBCCW pump in service lAW SO 34.6.A-2 "Placing Standby TBCCW System Pump In Service".

PRO Monitor plant parameters/assist as necessary.

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 3 Page: 30f12 Event

Description:

ESW pump spurious start Cause: Failure in the ESW pump breaker causes a spurious start Effects: Inoperable ESW pump requiring Tech Spec evaluation Position Applicanfs Actions or Behavior PRO Recognize and report the 'A' ESW pump start Recognize and report that no automatic start signals exist and that the pump is operating normally.

CRS Direct an Equipment Operator to investigate the spurious pump start.

Direct the PRO to shutdown the 'A' ESW pump Recognize that a Tech Spec LCO is not met.

Refer to Tech Spec 3.7.2 and determine Condition A applies:

• The 'A' ESW pump must be restored to operable status within 7 days.

PRO Shutdown the 'A' ESW pump using SO 33.2.A "Emergency Service Water System Shutdown.

• Stop the 'A' ESW pump by placing its control switch in STOP.

201 I NRC Scenario #2 - T-l 17 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 4 Page: 40f12 Event

Description:

Recirc pump trip ('A' M-G set drive motor breaker)

Cause: Instantaneous overcurrent trip Effects: 1. Alarms:

• 214 8-4 "A Recirc Pump Low Diff Press"

• 214 C-2 "A Recirc Gen Lockout Trip"

• 214 C-3 "A Recirc Drive Motor Trip"

• 214 D-4 itA Recirc Gen Aux Lockout Trip"

2. Trip of the 'A' recirc pump, causing reduction in core flow and reactor power Position Applicant's Actions or Behavior URO Recognize and report trip of the 'A' reactor recirc pump and entry into OT-112 "Unexpected/Unexplained Change in Core Flow".

Enter the corresponding Alarm Response Cards for alarms 214 C-2 "A Recirc Gen Lockout Trip", 214 C-3 "A Recirc Drive Motor Trip" and 214 D-4 itA Recirc Gen Aux Lockout Trip" (as time permits).

CRS Enter and execute OT-112 "Unexpected/Unexplained Change in Core Flow".

Verify insertion of ALL GP-9-2 Table 1 control rods.

Determine current operating point on Power-Flow Operation Map.

Direct monitoring for THI.

Direct closing 'A' recirc pump discharge valve MO-053A, then re-opening valve after 5 minutes.

Direct performing SO 2A.2.A-2 "Recirculation System Shutdown".

URO Insert ALL GP-9-2 Table 1 control rods.

Monitor for THI.

Close 'A' recirc pump discharge valve MO-053A; re-open after 5 minutes.

Perform SO 2A.2.A-2 "Recirculation System Shutdown" (as time permits).

CRS Perform AO 2A.1-2 "Recirculation System Single Loop Operation".

Refer to Tech Spec 3.4.1 and determine requirements for operating in single loop.

NOTE: since OT-112 and Tech Spec 3.4.1 allow up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for transitioning to single loop, these actions may be assessed as follow-up questions after the scenario is complete.

20 II NRC Scenario #2 - T -117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 2 Event No.: 5 Page: 50f12 Event

Description:

Loss of Stator Water Cooling I reactor scram I ATWS (electric)

Cause: Clogged SWC filter I scram condition with power above 4% due to RPS failure Effects: 1. Alarms:

• 220 A-5 "2 Gen Stator Coolant or H2 Seal Oil Trouble"

• 206 G-5 "Stator Coolant Standby Pump Run"

• 206 L-1 "Generator Protection Circuit Energized"

2. The crew will attempt to initiate a manual scram, and then take actions to terminate the A TWS, as well as control RPV level/power.

3. The turbine will trip in 3.5 minutes since stator amps will be greater than 7760.

Position Applicant's Actions or Behavior PRO Recognize and report 220 A-5 "2 Gen Stator Coolant or H2 Seal Oil Trouble" and enter the corresponding Alarm Response Card.

Dispatch an Equipment Operator to investigate the alarm.

URO Recognize and report 206 G-5 "Stator Coolant Standby Pump Run" and 206 L-1 "Generator Protection Circuit Energized" and enter the corresponding Alarm Response Cards.

CRS Enter/direct actions lAW OT-113 "Loss of Stator Cooling":

• Lead crew in verifying a valid loss of Stator Cooling condition exists (per OT-113, 206 L-1 in conjunction with 206 G-5 is a valid loss of Stator Cooling).

• Direct a reactor scram per GP-4 "Manual Reactor Scram".

URO Perform GP-4 "Manual Reactor Scram":

• Reduce recirc flow controllers to minimum (20% demand)

• Place the mode switch to "SHUTDOWN".

• Report control rods are NOT inserting.

• Report APRMs are NOT downscale.

• Depress both manual scram pushbuttons.

• Report T-101 entry due to an ATWS with reactor power> 4%.

2011 NRC Scenario #2 - T -117 Electric A TWS, Rev O.doc

Operator Actions ES-O-2 OpTestNo.: 1 Scenario No.: 2 Event No.: 5 Page: 6of12 Event

Description:

Reactor scram I ATWS (continued)

Position Applicant's Actions or Behavior PRO Perform GP-4 "Manual Reactor Scram" / scram actions:

• Transfer 13 KV house loads using RRC 53.1-2.

• Verify Group II & III isolations and SGTS initiation.

• Verify scram discharge volume vents and drains are closed (only the outboard vents and drains will close due to the RPS failure).

• Isolate Hydrogen Water Chemistry.

• Verify recirc pumps are at (or below) 30% speed.

• Monitor instrument air header pressure and drywell pressure.

• Report to the CRS instrument air header pressure is greater than drywell pressure.

• WHEN the turbine trips (due to the loss of Stator Cooling), verify generator lockout.

CRS Enter/direct actions for T-101 "RPV Control":

• Verify lIRO/PRO scram actions.

• Direct RPV pressure stabilized below 1050 psig using EHC (using SRVs and/or HPCI after the turbine trips).

• Direct drywell instrument nitrogen restored.

• Direct actions for the ATWS (see next page).

PRO When the isolation occurs (+1 inch RPV level), attempt to restore drywell instrument nitrogen lAW GP-8.E "Primary Containment Isolation Bypass".

• Place AO-2969A control switch to "CLOSE".

• Place AO-2969B control switch to "CLOSE".

• Place Dryweilinstrument Nitrogen Bypass Switch 16A-S100 in the "BYPASS" position.

• Place Dryweilinstrument Nitrogen Bypass Switch 16A-S99 in the "BYPASS" position.

Recognize and report that while attempting to restore drywell instrument nitrogen, the valves did not reopen (see Event #7).

CRS Enter T-103 "Secondary Containment Control" as necessary for Torus Compartment High Radiation (per ARC 003 B-1 "2 Unit Reac Bldg Hi Radiation), due to SRV lift following turbine trip.

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

Operator Actions OpTestNo.: 1 Scenario No.: 2 Event No.: 5 Page: 7of12 Event

Description:

Reactor scram I ATWS (continued)

Position Applicant's Actions or Behavior CRS Direct T-101 RC/Q actions:

• Initiate ARI.

• Trip'S' recirc pump.

• T-213 "Deenergize Scram Solenoids".

CT

• T-214 "Vent Scram Air Header" (this direction ;s critical because it is the only success path to insert control rods during the ATWS).

CT

• T-220 "Driving Control Rods During Failure To Scram".

• Enter T-117 "Level/Power Control".

CT

• Initiation of SSLC.

URO Perform T-101 RC/Q actions when directed:

• Initiate ARI; report to the CRS that ARI was NOT successful.

• Trip'S' recirc pump.

• Direct an Equipment Operator to perform T -213. Attempt URO portion of T -213; report to the CRS that T -213 was NOT successful.

NOTE to Examiner: do NOT allow T-213 to be performed.

CT

• Direct an Equipment Operator to perform T-214.

CT

• Perform T-220.

• Initiate SBLC in accordance with RRC 11.1-2 "Standby Liquid System Initiation During A Plant Event" (see Event #6).

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 2 Event No.: 5 Page: 8of12 Event

Description:

Reactor scram I ATWS (continued)

Position Applicant's Actions or Behavior CRS Direct T-117 actions:

• Inhibit ADS.

• T-221 "Main Steam Isolation Valve Bypass".

CT

• Lowering RPV level to below -60 inches by terminating and preventing RPV injection using T-240, Attachment 1, Figure 1.

URO/PRO Perform T -117 actions when directed:

• Inhibit ADS.

• Direct an Equipment Operator to perform T-221 to bypass the low level MSIV isolation (-160 inches).

CT Perform T-240 when directed.

• Terminate and prevent injection using T-240, Attachment 1, Figure 1:

o If HPCI is NOT running, place the Aux Oil Pump in "Pull-to-Lock".

o If HPCI is running, place the Aux Oil Pump in "Start", depress and hold the "Remote Trip" pushbutton; when turbine speed reaches -0 rpm, place the Aux Oil Pump in "Pull-to-Lock" and release the "Remote Trip" pushbutton.

o Press "Emergency Stop" for all reactor feed pumps.

o Press "Slow Raise" or "Fast Raise" for 2 reactor feed pumps.

o Close reactor feed pump discharge valves MO-2149A, B, C.

o Verify closed MO-S090 "C RFP Discharge Bypass".

• Restore RPV injection to control level below -60 inches and within the RPV level band, and using the source, directed by the CRS.

URO/PRO Recognize and report entry into T-102 "Primary Containment Control" due to high Torus temperature of 95 degrees F and/or Torus level high 14.9 feet (depending on whether or not SRVs are lifting).

CRS Enter and execute T-102:

• Ensure Torus cooling has been maximized.

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 2 Event No.: 5 Page: 90f12 Event

Description:

Reactor scram / ATWS (continued)

Position Applicant's Actions or Behavior CRS Direct T -117 actions:

NOTE: Torus temperature is NOT expected to reach 110 degrees F during this scenario.

CT

• IF Torus temperature reaches 110 degrees F, direct the crew to perform T-240 using Attachment 1, Figure 1, if no SRVs are open; OR Attachment 1, Figure 2, if any SRV is open.

CT

• If not already done, direct initiation of SBLC at or before Torus temperature reaches 110 degrees F (see Event #6).

CT URO/PRO Perform T-240 again, if directed.

• Terminate and prevent injection using T-240, Attachment 1, Figure 2 (the specific performance steps are listed on page 8).

• Restore RPV injection when any of the following are reached:

o RPV level reaches -172 inches, or o Reactor power drops below 4%, or o All SRVs remain closed.

Control level as directed by the CRS to prevent level from lowering below

-226 inches (2/3 core coverage).

CT URO Recognize "Scram Valve Pilot Air Header Press Lo" (211 D-2) alarm and/or control rods inserting due to T-214 and inform the CRS.

Verify all control rods are inserted and inform the CRS.

CRS Determine the ATWS is terminated, exit T -117 "Level/Power Control" and enter T-101 RC/L:

• Direct crew to restore level to +5 to +35 inches.

• Direct restoration actions.

URO/PRO Restore RPV level to +5 to +35 inches as directed by CRS.

2011 NRC Scenario #2 - T -117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 6 Page: 10 of 12 Event

Description:

RWCU fails to automatically isolate on Group II isolation signal Cause: Isolation logic failure Effects: When SBLC is initiated, RWCU will not automatically isolate, resulting in dilution and removal of boron solution. Operator action will be required in order to isolate RWCU.

Position Applicant's Actions or Behavior URO Initiate SBLC, when directed, per RRC 11.1-2:

• Close Recirc sample valves AO-039 and AO-040.

• Start 'A' or 'B' SBLC pump.

• Recognize RWCU did not isolate.

CT

• Manually close RWCU valves MO-1S, MO-18, and MO-68.

• Verify SBLC is injecting based on SBLC pump discharge pressure greater than reactor pressure and lowering tank level.

20 II NRC Scenario #2 - T -117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 2 Event No.: 7 Page: 11 of 12 Event

Description:

Unable to restore drywell instrument nitrogen /Ioss of non-ADS SRVs Cause: Failure of isolation bypass logic Effects: Non-ADS SRVs are not available for reactor pressure control and/or depressurization Position Applicant's Actions or Behavior CRS Direct alternate methods of supplying nitrogen to the SRVs:

• Backup Instrument Nitrogen to ADS using SO 16A.7.A-2 o Place SV-8130A and SV-8130B control switches on panel 20C003-03 to RESET and then in AUTO/OPEN.

o Verify open SV-8130A & B.

o Verify PI-8142 "Backup N2" on the 20C003-03 panel is ~ 85 psig.

• T-261 "Placing the Backup Instrument Nitrogen Supply From the CAD Tank in Service".

PRO Restore drywell instrument nitrogen as directed.

• If directed to use Backup Instrument Nitrogen to ADS using SO 16A.7.A-2:

o Place SV-8130A and SV-8130B control switches on panel 20C003-03 to RESET and then in AUTO/OPEN.

o Verify open SV-8130A & B.

o Verify PI-8142 "Backup N2" on the 20C003-03 panel is ~ 85 psig.

• If directed to perform T-261 "Placing the Backup Instrument Nitrogen Supply From the CAD Tank in Service":

o Verify closed AO-2969B on panel 20C003-03.

o Dispatch an Equipment Operator to the CAD Building perform step 4.2 (manual valving).

TERMINATION CRITERIA:

The scenario may be terminated when all control rods have been inserted and reactor water level is being controlled above the top of active fuel.

2011 NRC Scenario #2 - T-117 Electric ATWS, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 2 Event No.: 8 Page: 12 of 12 Event

Description:

EAL classification Position Applicant's Actions or Behavior CRS Determine EAL classification using EP-AA-1007.

• Based on the scenario conditions and expected outcome, the CRS will classify the event as MS3 "Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Scram Once a Reactor Protection System Setpoint has been Exceeded and Manual Scram Was NOT Successful".

2011 NRC Scenario #2 T-117 Electric ATWS, Rev O.doc

SIMULATOR OPERATOR INSTRUCTIONS FOR 2011 NRC SCENARIO #3 GENERAL REQUIREMENTS

• Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

• All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

• All markable procedures, boards, etc. will be erased.

• All paper used by the crew will be retained for the examination team as requested.

• The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

• This is a new scenario containing elements from the 2005 and 2007 NRC ILT Exams.

INITIAL SETUP Initial Conditions

• IC-83, -5% power (created from IC-8)

• Ensure recorder power is on; roll recorders as required

• Ensure annunciator horns are active Blocking Tags

• None Activate APP "2011_NRC_SCN3" or insert the following:

Event Triggers TRG E5 DW_PRESSURE_GT_26 TRG E6 DWCW_HEADER_RETURN_VALVE_GREEN_LlGHT_ON TRG E6 = DMF ARM01_23 Malfunctions IMF PRM01_08 (E1 00) 100 ('A' main stack radiation monitor fails upscale)

IMF RFC04A (E2 0 0) 100 (Recirc M-G flow controller 'A' oscillations)

IMF MSS08H (E3 0 0) 50 (Reactor pressure relief valve 'H' failure)

IMF ADS02C (E4 0 0) 100 5:00 0 (Rupture in 'H' SRV downcomer wI 5-minute ramp)

IMF DWC04 (E5 0 0) 100 (DWCW leakage inside the drywell)

IMF ARM01_23 (E5 0 0) 0.1 (Heater & RFPT South 165 Elev. ARM failure - causes ARM 3.1 to alarm at 9 mRem/hr, indicating a DWCW leak into the Turbine Building) 2011 NRC Scenario #3 - T-102 RCS Leak, Rev O.doc

Overrides Prevent CLOSE indication on drywell vent valve AO-2506 with the following overrides:

lOR ZLOPC03A02506_1 (none 0 0) OFF lOR ZLOPC03A02506_2 (none 0 0) ON lOR ZLOPC03A02506GRP_1 (none 0 0) OFF lOR ZLOPC03A02506GRP_2 (none 0 0) ON Prevent drywell spray with the following overrides:

lOR ZYP12A1S23 (none 0 0) CLOSE (Drywell header valve MO-26A fails to open) lOR ZYP12A1S43 (none 0 0) CLOSE (Torus header valve MO-39A fails to open) lOR ZYP12A3S21 (none 0 0) CLOSE (Drywell spray valve MO-31 B fails to open) lOR ZYP12A3S41 (none 0 0) CLOSE (Torus spray valve MO-38B fails to open)

Trip Overrides None Batch Files None Turnover Procedures

• GP-2 "Normal Plant Start-Up" complete up through step 6.2.31

• Rod Sequence Sheet is complete up through RWM Sequence Step 14 (Array 8); next control rod is 26-43 in Sequence Step 15 (Array 8)

• Control rod withdrawal per SO 62.1.A-2 "Withdrawingllnserting a Control Rod"

• Reactor level control through AO-8091 using SO 5.7.E-2 "Long Path Recirc for Startup Level Control" at step 4.1.19.8

• SO 7B.4.A-2 "Containment Atmosphere De-Inerting And Purging Via SBGT System" at step 4.19

• Turbine chest warming in progress using SO 1B.1.A-2 "Main Turbine Startup and Normal Operations" at step 4.10

• OP-AB-300-1003 Attachment 1 "Reactivity Maneuver Approval Form" at step 1 of 4 covering startup from all rods in to generator synchronization 2011 NRC Scenario #3 - T -102 RCS Leak, Rev O.doc

SIMULATOR OPERA TOR DIRECTIONS EVENT 1 Support crew as necessary during HPCI steam supply valve (MO-2-23-014) cycling (GP-2, Rev 126 Step 6.2.32).

EVENT 2 Support crew as necessary while Recirc pump speeds are raised to the 30% speed limiter (GP-2, Rev 126 Step 6.2.33).

EVENT 3 When Reactor Recirc speeds have been raised to the 30% speed limiter, or when directed by the Lead Examiner, initiate pending events on ET1 (IMF PRM01_08 100) to cause the 'A' main stack radiation monitor failure at 100% severity.

Pre-inserted overrides will result in drywell vent valve AO-2506 indicating OPEN (cannot actually fail just this valve open).

EVENT 4 When the Tech Spec determinations are complete, or at the direction of the Lead Examiner, notify the control room that there is excessive seal leakage on the 'B' RBCCW pump. Report that the 'B' RBCCW pump should be removed from service immediately.

Support the crew in starting the 'A' RBCCW pump (SO 35.6.A-2 step 4.1):

• Report the suction block valve is open.

• Report that the discharge block valve is open.

• Report proper oil level in the pump.

• Wait approximately five minutes after being directed to vent the pump to report that the pump is vented.

EVENT 5 After the 'A' RBCCW pump is placed in service, or when directed by the Lead Examiner, initiate pending events ET2 (IMF RFC04A 100) to cause Recirc M-G flow controller lA' oscillations.

EVENT 6 When the 'A' M-G set is "locked up" and the operators have reviewed the actions to take with a locked up M-G Set, or when directed by the Lead Examiner, initiate pending events on ET3 (IMF MSS08H 50) to cause SRV 'H' to fail open.

If directed to remove fuses for the 'H' SRV in accordance with OT-114, then MRF ADS02H REMOVE.

EVENT 7 After Torus cooling has been placed in-service, or when directed by the Lead Examiner, initiate pending events on ET4 (IMF ADS02C 100) to cause a rupture in

'H' SRV downcomer (5-minute ramp rate).

Modify the leak severity I ramp rate as necessary to control the scenario pace and ensure the crew has sufficient time to respond to scenario conditions and attempt to spray containment prior to exceeding the PSP curve.

2011 NRC Scenario #3 - T-102 Res Leak, Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 7 Pre-inserted overrides will prevent spraying the containment.

(continued)

When requested, support activities to place OW cooling in-service lAW T-223.

EVENT 8 IF directed to check DWCW return header pressure, report that DWCW return header pressure is 20 psig.

When Drywell pressure exceeds 26 psig, and DWCW has NOT been isolated, then verify initiation of pending events on ET5:

• IMF DWC04 100

• IMF ARM01_23 0.1 If/when DWCW is isolated, then delete the following malfunctions:

• DMF DWC04

• DMF ARM01_23 If DWCW was not isolated per GP-8B prior to 26 psig in the Drywell and surveys are directed, report as Ops HP that the Turbine Building 165 ft. Elev. general area radiation levels are 10 mR/hr and rising slowly.

EVENT 9 The crew will perform an emergency blowdown due to exceeding the PSP Curve.

TERMINATION The scenario may be terminated when 5 SRVS are open, the RPV is depressurized, RPV level is under control and Drywell Chilled Water is isolated.

20 J J NRC Scenario #3 - T -102 RCS Leak, Rev O.doc

SHIFT TURNOVER PLANT CONDITIONS:

• Unit 2 is starting up at -5% reactor power, 450 psig

• The drywell is de-inerted due to required inspections INOPERABLE EQUIPMENT/LCOs:

• None SCHEDULED EVOLUTIONS:

• Continue the reactor startup in accordance with GP-2, which is complete through step 6.2.31.

SURVEILLANCES DUE THIS SHIFT:

• None ACTIVE CLEARANCES:

• None GENERAL INFORMATION:

The crew is expected to resume startup actions lAW GP-2 step 6.2.32 to cycle the HPCI Steam supply valve (MO-2-23-14). Then raise Recirc pump speeds lAW step 6.2.33 and continue with subsequent actions in GP-2.

Rod Sequence Sheet is complete up through RWM Sequence Step 14 (Array 8); next control rod is 26-43 in Sequence Step 15 (Array 8)

Currently in Step 1 of ReMA PB2C19-1.0 Reactor level control through AO-8091 using SO 5.7.E-2 (at step 4.1.19.8)

Containment purge in progress using SO 7B.4.A-2 (at step 4.19)

Turbine chest warming in progress using SO 1B.1.A-2 (at step 4.10)

The turbine bypass jack is at approximately 5%

2011 NRC Scenario #3 T-102 RCS Leak. Rev O.doc

CRITICAL TASK LIST

1. Perform an emergency blowdown in accordance with T-112 "Emergency Blowdown" when the PSP Curve of T-102 is violated.

OR Perform a rapid depressurization using RC/P-12 when the PSP Curve limit in T-102 is approached.

2. Perform isolations per GP-S.B "PCIS Isolation - Group II and III" when Drywell pressure exceeds Drywell Chilled Water System pressure.

2011 NRC Scenario #3 - T-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 1 Page: 1 of 13 Event

Description:

Cycle the HPCI Steam Supply valve (MO-2-23-14)

Cause: N/A Effects: N/A Position Applicanfs Actions or Behavior CRS Direct the PRO to perform step 6.2.32 of GP-2 "Normal Plant Start-up" and cycle HPCI MO-2-23-014.

PRO Verify HO-4513 "HPCI Stop" is closed.

Open MO-2-23-014 "HPCI Supply".

Verify open MO-2-23-014 "HPCI Supply".

Close MO-2-23-014 "HPCI Supply".

Verify closed MO-2-23-014 "HPCI Supply".

Close MO-2-23-025 "HPCI Min Flow".

Verify closed MO-2-23-025 "HPCI Min Flow".

2011 NRC Scenario #3 T-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 3 Event No.: 2 Page: 2of13 Event

Description:

Raise Recirc pump speed to the 30% speed limiter N/A Cause:

Reactor power change Effects:

Time Position Applicant's Actions or Behavior eRS Direct the URO to perform sep 6.2.33 of GP-2 "Normal Plant Start-up" and raise Recirc pump speed to the 30% speed limiter.

URO Use the Recirc controllers and raise Recirc pump speed to 30%.

Monitor changes to:

• The Recirc system

• Reactor power

• Reactor pressure

• Reactor water level 2011 NRC Scenario #3 T-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 3 Page: 3 of 13 Event

Description:

Main stack radiation monitor fails upscale I Drywell 18-inch vent AO-2S06 fails to close Cause: Module failure I valve control failure Effects: Radiation monitor failure will cause the inboard drywell vent and purge valves greater than 2 inches to isolate.

Failure of AO-2S06 to close will require the crew to close outboard vent valve AO-2S07.

Position Applicant's Actions or Behavior PRO Recognize and report alarm 003 D-1 "Main Stack Radiation High-High" and enter the corresponding Alarm Response Card.

• Verify automatic actions - all inboard Torus and Drywell vent and purge valves 2-inches and larger isolate (may use GP-8.B or GP-8.C)

• Recognize and report Drywell 18-inch vent valve AO-2S06 failed to isolate; attempt to manually close AO-2S06.

• Close outboard vent valve AO-2S07 (if directed).

• Secure the Drywell Purge Supply Fans.

• Determine radiation monitor RI-0-17-0S0A failed upscale.

• Perform AO 63E.1-2 to bypass the failed main stack rad monitor.

CRS Enter and execute the Alarm Response Card for 003 D-1.

• (May enter T-104 "Radioactive Release" but should exit without taking any actions).

• Direct manual isolation of Drywell 18-inch vent valve AO-2S06; when manual isolation fails, direct closure of outboard vent valve AO-2S07.

• For the failed radiation monitor, direct performance of AO 63E. 1-2 to bypass the failed Main Stack radiation monitor.

NOTE: AO 63E.1-2 is not required to be completed prior to the next event.

• Review Tech Spec 3.3.6.1 for the radiation monitor failure:

o Determine Condition A applies - channel must be placed in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2c).

• Review Tech Spec 3.6.1.3 for the vent valve failure (AO-2S06):

o Determine Condition A applies - isolate flow path within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• Review ODCM 3.8.CAA for the radiation monitor failure (RI-SOA):

o Determine no actions are required once AO 63E.1-2 is complete (since 1 channel remains operable), per OP-PB-108-11S-1001.

2011 NRC Scenario #3 - T-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 4 Page: 40f13 Event

Description:

RBCCW pump swap due to excessive seal leakage on the 'B' RBCCW pump Cause: Excessive seal leakage Effects: 'B' RBCCW pump removed from service and 'A' RBCCW pump placed in-service Position Applicant's Actions or Behavior URO Recognize and inform the CRS of the report from the Equipment Operator that there is excessive seal leakage from the 'B' RBCCW pump.

CRS Direct the PRO to swap RBCCW pumps using SO 35.6.A-2 "Placing Standby Reactor Building Closed Cooling Water Pump In Service" PRO Direct the Equipment Operator to verify the 'A' RBCCW pump is ready for a start.

Start the 'A' RBCCW pump.

Verify that pressure on PI-2350 has risen slightly.

Trip the 'B' RBCCW pump.

20 J J NRC Scenario #3 - 1'-\ 02 RCS Leak, Rev O.doc

Operator Actions Op Test No.: 1 Scenario No.: 3 Event No.: 5 Page: 50f13 Event

Description:

'A' Recirc M-G Flow Controller oscillations Cause: Failure in the 'A' flow controller Effects: 1. Jet pump flow oscillation

2. Total flow oscillations

3. RPV level oscillations

4. 'A' Recirc parameter changes

5. Reactor power oscillations Position Applicant's Actions or Behavior URO Recognize and report the 'A' Recirc pump (controller) oscillations Recognize and report the oscillations as an entry into OT-112 "Unexpected/Unexplained Change in Core Flow".

URO may lockup the 'A' Recirc M-G set without direction at this time.

Enter and execute OT-112 "Unexpected/Unexplained Change in Core Flow".

CRS Direct the URO to Lock-up the 'A' Recirc pump by placing the Scoop Tube switch to "LOCK" at panel 20C004A.

Refer to SO 20.7.8-2 "Recirculation MG Set Scoop Tube Lockup and Reset" Verify the Jet pump flow mismatch is within 10.25 Mlbm/hr.

URO "Lock up" the 'A' Recirc MG Set if not already completed.

2011 NRC Scenario #3 - 1'-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 3 Event No.: 6 Page: 60f13 Event

Description:

SRV 'H' inadvertently opens Cause: Mechanical failure of relief valve pilot Effects: 1. Alarms:

• 2100-2, "Safety Relief Valve Open"

• 227 B-4, "Blowdown Relief Valves Hi Temp"

2. Heat input to the primary containment.

Position Applicant's Actions or Behavior URO/PRO Recognize, report, and take actions lAW ARC 2100-2, "Safety Relief Valve Open", and ARC 227 B-4, "Blowdown Relief Valves Hi Temp".

CRS Enter/direct actions lAW OT-114:

• Lead crew in confirming an SRV is open.

• Direct both loops of RHR placed in torus cooling.

• Direct attempts to close the 'H' SRV.

URO/PRO Confirm the 'H' SRV is open lAW OT-114.

PRO Cycle the 'H' SRV control switch when directed.

Place both loops (only 'B' will work) of RHR in torus cooling lAW RRC 10.1-2, "RHR System Torus Cooling During a Plant Event", as directed:

• Open MO-039B (MO-39A will fail to open)

• Open MO-089B (D)

• Start RHR pump B (D)

• Open MO-034B

• Verify flow is 11,500-12,200 gpm for one RHR pump in service

• Start HPSW pump in each loop to be used for torus cooling

• Start additional RHR and HPSW pumps as directed

• Verify flow is 2: 20,000 gpm for two RHR pumps in service

• Direct an Equipment Operator to close stay full injection valve(s) for the RHR loop(s) in service CRS Declare the 'H' SRV inoperable; verify compliance with Tech Spec 3.4.3:

• Determine sufficient SRVs (>11) are operable; PTSA applies for 'H' SRV inoperability.

2011 NRC Scenario #3 - T-I02 RCS Leak, Rev O.doc

Operator Actions OpTestNo.: 1 Scenario No.: 3 Event No.: 7 Page: 7 of 13 Event

Description:

Rupture in the 'H' SRV downcomer Cause: Failure of the piping down stream of the SRV Effects: "Drywell Hi-Lo Press" alarms (210 F-2, 225 A-4)

High Drywell Pressure Scram Signal, Isolations, Diesel and HPCI auto starts.

Rising drywell pressure resulting in manual scram at 1.2 psig or auto scram at 2 psig with isolations, HPCI and diesel starts.

Loss of the suppression capability of the Torus Time Position Applicant's Actions or Behavior URO/PRO Recognize Drywell High Pressure alarms.

Recognize drywell pressure is rising and announce entry into OT-101 "High Drywell Pressure".

Trend the drywell pressure rise.

CRS Enter/direct actions in accordance with OT-101 "High Drywell Pressure":

Verify drywell inerting is not in progress.

Direct placing additional drywell cooling in service.

Direct actions to monitor components e.g., RRP seals.

NOTE: the following action is not applicable if the crew determines that the leak is from the SRV tailpipe.

As time permits, direct crew to isolate and restore systems lAW OT-101 to stop the source of the leak, including:

• RWCU, HPCI and RCIC (i.e. close HPCI MO-15 steam supply valve, close RCIC MO-15 steam supply valve ... ).

If not done earlier, direct manual isolation of Drywell 18-inch vent valve AO-2506; when manual isolation fails, direct closure of outboard vent valve AO-2507.

PRO Perform OT-101 actions as directed:

Monitor drywell pressure and plant parameters.

If directed, verify drywell inerting is not in progress.

If directed, place additional drywell cooling in service.

Monitor components for abnormal indications as directed by the CRS.

As time permits, isolate plant systems, including RWCU, HPCI, and RCIC, as directed by the CRS lAW OT-101 (Le. close HPCI MO-15 steam supply valve, close RCIC MO-15 steam supply valve ... ).

2011 NRC Scenario #3 - T -102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 7 Page: 80f13 Event

Description:

Rupture in the 'H' SRV downcomer (continued)

Position Applicant's Actions or Behavior CRS Direct GP-4 "Manual Reactor Scram" when drywell pressure cannot be restored and maintained below 1.2 psig.

URO Perform GP-4 "Manual Reactor Scram" actions:

• Place the mode switch to "Shutdown".

• Verify control rods inserting.

• Manually control the Reactor Feed Water System to control reactor level.

• Verify APRMs are downscale and report to the CRS.

• Verify all control rods inserted and report to the CRS PRO Perform scram actions.

• Verify all isolations, as applicable.

• Restore Instrument Nitrogen to the drywell when directed by the CRS.

CRS Enter and execute T-100 "Scram":

• Direct level restored and maintained +5 to +35 inches.

• Direct restoration of drywell instrument nitrogen lAW GP-8.E "Primary Containment Isolation Bypass".

2011 NRC Scenario #3 T-I02 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 7 Page: 90f13 Event

Description:

Drywell spray valve failures - prevents drywell spray Cause: Failure of drywell spray valves to open on both loops of RHR system Effects: 2 psig isolations, HPCI auto start, Core Spray and RHR pumps auto-start (due to low reactor pressure), and emergency diesels start.

Drywell pressure continues to rise above 2 psig and requires the crew to perform an Emergency 81owdown when torus pressure cannot be maintained below the PSP curve.

Position Applicant's Actions or Behavior URO/PRO Recognize and respond to 2 psig drywell pressure and announce entry into T-101 and T-102:

Recognize and verify Group II/III isolations.

Recognize and verify Diesel Generator starts and has cooling water.

Recognize and report the HPCI auto start.

Recognize and report Core Spray and RHR pumps auto start.

Trend and report containment parameters.

CRS Recognize and respond to 2 psig drywell pressure and announce entry into T-101 and T-102:

Re-enter T-101 "RPV Control" and enter T-102 "Primary Containment Control".

Verify adequate level and direct either a HPCI shutdown or isolation, and Core Spray and RHR pumps shutdown.

PRO Perform an isolation or shutdown of HPCI as directed by the CRS.

• For isolation, depress the HPCI isolation pushbutton and verify that HPCI shuts down and the HPCI Steam Line Isolation Valves close.

• For a HPCI shutdown, trip HPCI, verify that the HPCI aux oil pump starts as required, and place the HPCI Aux Oil Pump in PUIl-to-Lock when HPCI stops rotating.

Shutdown Core Spray and RHR pumps as directed by the CRS.

CRS Direct T-102 actions:

Direct Torus sprays lAW T-204 using A(8) Loop RHR Verify GP-88 isolations.

Trend containment parameters, specifically drywell pressure and bulk average temperature.

2011 NRC Scenario #3 - T-102 RCS Leak, Rev O.doc

Operator Actions ES-O-2 OpTestNo.: 1 Scenario No.: 3 Event No.: 7 Page: 10 of 13 Event

Description:

Drywell spray valve failures - prevents drywell spray (continued)

Position Applicant's Actions or Behavior PRO Perform Torus Sprays lAW T-204 "Initiation of Containment Sprays using RHR":

Recognize and report that Containment Sprays cannot be placed in service on either loop of RHR.

URO/PRO Recognize and report containment parameters:

Bulk drywell temperature at 145 degrees F and entry into T-102.

CRS Re-enter T-102 on bulk average temperature of 145 degrees F.

Continue T-101 actions:

Direct RPV level controlled +5 to +35 inches.

Direct closing turbine bypass valves to slow cooldown/depressurization.

(May) direct closing MSIVs to slow down RPV cooldown rate.

(May) remove steam users from service to slow down the cooldown rate.

URO Maintain RPV level using Feedwater.

URO/PRO Trend and report containment parameters.

CRS Direct URO/PRO to perform T -223 "Drywell Cooler Fan Bypass" to bypass and restore drywell ventilation.

URO/PRO Perform T -223:

Direct EO to place drywell fans in slow.

Verify T-223 requirements.

2011 NRC Scenario #3 - T-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 3 Event No.: 8 Page: 11 of 13 Event

Description:

Drywell Chilled Water (DWCW) piping break I manually isolate DWCW Cause: Failure of drywell spray valves to open on both loops of RHR system Effects: Drywell to Turbine Building leak, resulting in rising radiation levels in the Turbine Building (if DWCW is not manually isolated).

Position Applicant's Actions or Behavior CT CRS Direct isolating Drywell Chilled Water per GP-8.B "PCIS Isolation Groups II and III" when drywell pressure exceeds Drywell Chilled Water System pressure.

CT URO/PRO Isolate Drywell Chilled Water per GP-8.B when drywell pressure exceeds Drywell Chilled Water System pressure, as directed:

• Trip the 'B' recirc pump.

• Close MO-2-200A and MO-2-200B.

• Close MO-2-201A and MO-2-201 B.

• Trip the drywell chillers.

• Place the DWCW pump control switches in "Pull-to-Lock".

• Trip the drywell cooler fans.

NOTE: the following steps are N/A if DWCW is isolated using GP-8B before drywell pressure exceeds 26 psig.

URO/PRO Recognize and report alarm 003 B-2 "2 Unit Turb Bldg Hi Rad" and enter the corresponding Alarm Response Card.

Monitor and report Turbine Building ARM readings.

CRS If alarm 003 B-2 alarm is received, direct GP-15 "Local Evacuation" of 165 ft. Elev. of the Unit 2 Turbine Building.

2011 NRC Scenario #3 - T-I02 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 8 Page: 12 of 13 Event

Description:

Emergency Blowdown due to exceeding the PSP curve Cause: Failure of drywell spray valves to open on both loops of RHR system Effects: N/A Position Applicant's Actions or Behavior CT CRS If the MSIVs are open, when the combination of Torus pressure and Torus level approach the limits of the PSP curve, direct the URO to perform a rapid depressurization using T-101, RC/P-12.

CT URO Rapidly depressurize the reactor by opening all Main Turbine bypass valves.

CT CRS When the combination of Torus pressure and Torus level cannot be maintained on the Safe Side of the PSP curve, enter and execute T -112 "Emergency Blowdown":

• Verify torus level is above 7 feet.

• Verify RPV pressure is 50 psig or more above torus pressure.

• Direct 5 ADS SRVs opened.

CT PRO When directed, open 5 ADS SRVs by placing their control switches in OPEN.

URO Control reactor level as directed following the blowdown.

(Note that level will swell high during the actual blowdown.)

TERMINATION CRITERIA:

The scenario may be terminated when 5 SRVS are open, the RPV is depressurized, RPV level is under control and Drywell Chilled Water is isolated.

2011 NRC Scenario #3 - T-102 RCS Leak, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 3 Event No.: 9 Page: 13 of 13 Event

Description:

EAL classification Time Position Applicant's Actions or Behavior CRS Determine EAL classification using EP-AA-1 007.

• Based on the scenario conditions and expected outcome, the CRS will classify the event as FA1 "Loss of the Reactor Coolant System Barrier".

20 II NRC Scenario #3 - '1'-102 RCS Leak, Rev O.doc

SIMULATOR OPERATOR INSTRUCTIONS FOR 2011 NRC SCENARIO #5 GENERAL REQUIREMENTS

• Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

• All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

• All markable procedures, boards, etc. will be erased.

• All paper used by the crew will be retained for the examination team as requested.

• The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

• This is a bank scenario that was last used on the 2009 NRC ILT exam. It has been modified (altered) Slightly and is being submitted as a spare scenario for the 2011 NRC ILT exam.

INITIAL SETUP Initial Conditions

• IC-85, 88% power, full power rod pattern

• Place the backup EHC pump in RUN (for ST-0-001-200-2)

• Ensure recorder power is on; roll recorders as required

• Ensure annunciator horns are active Blocking Tags

• None Activate APP "2011_NRC_SCNS" or insert the following:

Event Triggers TRG E5 ARI_A_ARMED TRG E4 = BAT BUS_2_0VERClIRRENT_LOCKOUT

=

TRG E5 MRF ARI01TO NORMAL Malfunctions IMF SWS01 B (E1 00) ('8' Service Water pump trip)

IMF MCS05A (E3 0 0) CA' Condensate pump trip)

IMF RRS20 (E4 5:00 0) 4 20:00 0 (Recirc loop rupture at 4% severity, 5 minute delay and 20 minute ramp)

IMF HPC03 (E6 0 0) (HPCI turbine trips) 2011 NRC Scenario #5 - T-ill Low Level, Rev O.doc

Overrides lOR ZLORP15DS26B (none 0 0) ON (5A-DS26B light at RPS Pane120C017 to ON) lOR ZYP06A521S16 FALSE (SFCS recirc runback inhibit) lOR ZYP12A1S19 (none 0 0) OFF (Override Switch 10A-17A, prevents containment sprays) lOR ZYP12A3S19 (none 0 0) OFF (Override Switch 10A-17B, prevents containment sprays) lOR AN0205LD4 (E2 0 0) ALARM_ON (RPS INSTRUMENT GROSS FAILURE - 210 D-4) lOR AN0205LF1 (E2 0 0) ALARM_ON (DW HI PRESSURE - 210 F-1)

Trip Overrides MRF ARI01 TO OVERRIDE (prevents ARI auto-initiation on 'N channel)

MRF RPS03TO OVERRIDE (prevents RPS B1 trip)

MRF RPS04TO OVERRIDE (prevents RPS B2 trip)

MRF RPS06TO OVERRIDE (prevents RPS B3 trip)

Batch Files (Verify the following Batch File exists - DO NOT ENTER AT THIS TIME)

BAT BUS_2_0VERCURRENT_LOCKOUT IMF MAP06D IMF MAP06E IMF MAP06F lOR AN0209LA2 ALARM_ON lOR AN0209LC4 ALARM_OFF lOR ZYP14A3S04 TRIP lOR ZYP14A3S08 TRIP lOR ZYP14A3S37 TRIP Turnover Procedures

• GP-5 completed through step 5.3.1

• ST-0-001-200-2 completed through step 6.2.1.34; next step is 6.3.1

• Provide crew with Key #18 for the turbine stop valve functional test 2011 NRC Scenario #5 T-III Low Level. Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 1 Support crew for main turbine stop valve functional test.

During the performance of ST-0-001-200-2 "Turbine Stop Valve Closure And EOC RPT Functional" provide the crew with the following information (role playas Extra RO at Panels 20C015 and 20C017, allowing the CRS to apply Tech Specs:

• Step 6.3.7.2 - auxiliary scram relay 5A-K10A did de-energize.

• Step 6.3.7.3 - auxiliary scram relay 5A-K10B did not de-energize.

• Step 6.3.7.4 - indicating light 5A-DS26B is lit.

• Step 6.3.8.1 - auxiliary scram relay 5A-K1 OA did energize.

• Step 6.3.8.2 - auxiliary scram relay 5A-K10B remained energized.

• Step 6.3.8.3 - indicating light 5A-DS26B is lit.

EVENT 2 After the Tech Spec evaluation is complete, or when directed by the Lead Examiner, initiate ET1 (IMF SWS01 B) to trip the 'B' Service Water pump.

When requested to check the 'B' Service Water pump breaker, report that it tripped on instantaneous overcurrent.

Support the crew while placing the 'C' Service Water pump in service lAW SO 30.1.A-2, section 4.2.

Support the crew while restoring the Fuel Pool Service Water booster pumps lAW SO 19.1.A-2, section 4.2.

EVENT 3 When Fuel Pool Service Water is restored, or when directed by the Lead Examiner, initiate ET2 for the drywell pressure instrument failure, and verify the following:

• lOR AN0205LF1 ALARM_ON, DW HI PRESSURE (210 F-1)

• lOR AN0205LD4 ALARM_ON, RPS INSTRUMENT GROSS FAILURE (210 D-4)

When requested to check the 2AC065D and 2BC065D instrument racks, report Drywell Pressure Instrument PIS-2-5-12A is upscale high with the gross failure light lit. If directed to reset the gross failure, report that it will NOT reset.

EVENT 4 After the crew has inserted a half scram on RPS channel A 1 and before inserting a PCIS channel trip, or when directed by the Lead Examiner, initiate a trip of the 'A' condensate pump using ET3 (IMF MCS05A).

• Recirc pumps will fail to automatically runback due to a pre-inserted override (lOR ZYP06A521S16 FALSE).

When requested to check the 'A' condensate pump breaker, report that it tripped on instantaneous overcurrent.

Support the crew as necessary during the power reduction.

2011 NRC Scenario #5 - T-III Low Level, Rev O.doc

SIMULATOR OPERATOR DIRECTIONS EVENT 5 When actions for the condensate pump trip are complete, or when directed by the lead Examiner, initiate ET4 (BAT BUS_2_0VERCURRENT_LOCKOUT) to cause an overcurrent lockout on #2 aux bus.

Verify a Recirc loop rupture initiates 5 minutes later at 4% severity on a 20 minute ramp (IMF RRS20 4 20:00).

If asked, report DWCW return header pressure is 28 psig.

EVENT 6 RPS fails to scram automatically or manually (manual ARI works) - pre-inserted.

The 'A' ARI channel will fail to automatically initiate. When the URO arms the 'A' ARI channel, verify ET5 (MRF ARI01TO NORMAL) initiates to restore the 'A' ARI channel to normal.

When directed to close HV-2-3-56 (per T-246), MRF T220_2 CLOSE and report HV-2-3-56 is closed.

EVENT 7 After HPCI automatically starts (or is manually started), and as soon as DW Sprays are initiated, initiate ET6 (IMF HPC03) (HPCI turbine trips)

When directed to investigate the HPCI turbine trip, wait 5 minutes and then report unable to determine the cause of the trip.

EVENT 8 Pre-inserted instrument failures will prevent the crew from spraying the torus or the drywell.

After the crew attempts to spray the containment (either torus or drywell), delete the override on the OPPOSITE RHR lOOP:

• To delete the override on the 'B' RHR loop, DOR ZYP12A3S19

• To delete the override on the 'A' RHR loop, DOR ZYP12A1S19 NOTE: adjust the severity of RRS20 as necessary to control the pace of RPV level trend toward -172 inches.

TERMINATION The scenario may be terminated after the RPV has been depressurized and level has been recovered and is controlled.

2011 NRC Scenario #5 - T-III Low Level, Rev O.doc

SHIFT TURNOVER PLANT CONDITIONS:

• Unit 2 is steady at 90% power.

• A load drop was been performed in preparation for 8T-0-001-200-2.

• GP-5 "Power Operations" is in progress, complete through step 5.3.1 INOPERABLE EQUIPMENT/LCOs:

• None SCHEDULED EVOLUTIONS:

• Perform 8T-0-001-200-2.

• Raise power to 100% once Reactor Engineers provide ReMA guidance.

SURVEILLANCES DUE THIS SHIFT:

• Perform ST-0-001-200-2 "Turbine Stop Valve Closure and EOC-RPT Functional".

o The ST has been started and is complete through step 6.2.1.34.

o Continue the Turbine Stop Valve functional test beginning at step 6.3.1.

o An extra RO is available to perform steps 6.3.7.2 through 4, and 6.3.8.1 through 3.

(Provide KEY #18 to the crew during turnover.)

ACTIVE CLEARANCES:

• None GENERAL INFORMATION:

• Power was lowered to 90% in accordance with GP-5 "Power Operations" under the Reactor Engineers guidance to perform ST-0-001-200-2. The Reactor Engineer will provide a ReMA for returning to full power following the completion of ST-0-001-200-2.

2011 NRC Scenario #5 - T-lll Low Level, Rev O.doc

CRITICAL TASK LIST

1. Recognize failure of the Reactor Protection System to scram the reactor and initiate Alternate Rod Insertion (ARI) to insert control rods in accordance with T-101 "RPV Control" and RRC 3B.1-2 "Alternate Rod Insertion During A Plant Event".

2. Spray the drywell in accordance with T-204 "Initiation of Containment Sprays Using RHR" when conditions permit, but before drywell temperature exceeds 281 degrees F.

3. Perform an emergency blowdown in accordance with T-112 "Emergency Blowdown" when RPV water level cannot be restored and maintained above -172 inches.

2011 NRC Scenario #5 - T-lll Low Level, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 5 Event No.: 1 Page: 1 of 16 Event

Description:

Perform the turbine stop valve functional test Cause: N/A Effects: N/A Position Applicant's Actions or Behavior CRS Direct the PRO to perform ST-0-001-200-2 "Turbine Stop Valve Closure and EOC-RPT Functional", beginning at step 6.3.1.

PRO Perform ST-0-001-200-2 "Turbine Stop Valve Closure and EOC-RPT Functional":

• ReviewST

• Inform the Unit Reactor Operator that the test is going to be conducted and what indications can be expected (this may be covered during turnover and/or a CRS briefing).

• At Panel 20C015 and 20C017:

1. Verify all RPS 'A' and 'B' scram solenoid group 1-4 lights are lit.

2. Verify A1 and B1 TURB STOP VALVE NORMAL lights are lit.

• At Panel 20C008B, place the CV/SV test selector switch to "sv TEST".

• Verify the lights on all four TSV test buttons are ON.

• At Panel 20C015, place the EOC-RPT test switch in "TEST" (.Y§i!]g KEY #18).

• Verify alarm 214 D-3 SYSTEM I EOC-RPT LOGIC PWR FAILITEST.

• At Panel 20C008B, depress and hold TSV-1 test pushbutton.

1. Verify TSV-1 position indicator moves smoothly at low speed to less than 10% open and then fast closes.

2. After 2 to 3 seconds at full close, release the test pushbutton.

3. Verify TSV-1 valve position indicator moves smoothly from closed to full open.

• When the RPS relay failure is reported, STOP the functional test.

1. Place the CV/SV test selector switch to "OFF".

2. Verify the lights on all four TSV test buttons are off.

3. Place backup EHC pump to "STOP", then back to "AUTO".

URO Monitor plant parameters/assist as directed.

20 II NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions ES-O-2 Op Test No.: 1 Scenario No.: 5 Event No.: 1 Page: 2 of 16 Event

Description:

RPS failure during turbine stop valve functional test Cause: Turbine stop valve position switch input to RPS logic fails Effects: RPS instrumentation failure; application of Tech Specs Position Applicant's Actions or Behavior NOTE: the "Extra RO" at Panels 20C015 and 20C017 (role-played by the Simulator Operator in the booth) will provide the crew with the following information from ST-0-001-200-2, allowing the CRS to apply Tech Specs:

• Step 6.3.7.2 - auxiliary scram relay 5A-K10A did de-energize.

• Step 6.3.7.3 - auxiliary scram relay 5A-K10B did not de-energize.

• Step 6.3.7.4 - indicating light 5A-DS26B is lit.

• Step 6.3.8.1 - auxiliary scram relay 5A-K10A did energize.

• Step 6.3.8.2 - auxiliary scram relay 5A-K10B remained energized.

• Step 6.3.8.3 - indicating light 5A-DS26B is lit.

PRO Stop the functional test when the RPS failure is reported.

Perform system restoration lAW ST-0-001-200-2, step 6.7 (see previous page).

CRS Direct stopping the functional test and system restoration when the RPS failure is reported.

Review Tech Spec 3.3.1.1 and determine Condition A applies (RPS Function 8 on Table 3.3.1.1-1):

• Place associated channel (or trip system) in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, OR

• Reduce thermal power to <29.5% RTP within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Review Tech Spec 3.3.4.2 and determine Condition A applies:

• Restore EOC-RPT instrumentation, or place channel in trip, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, OR

• Apply COLR limits of Tech Spec LCOs 3.2.1, 3.2.2, and 3.2.3 for inoperable EOC-RPT, OR

• Reduce thermal power to <29.5% RTP within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2011 NRC Scenario #5 - T-ll1 Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 2 Page: 30f16 Event

Description:

'B' Service Water pump trips on overcurrent Cause: Motor winding failure Effects: 1. Alarms:

• 216 H-1 B' Service Water Pump Trip"

• 216 H-2 "'B' Service Water Pump OVLD"

• 216 F-1 "Service Water Header Lo Press"

• 216 F-5 "Fuel Pool Service Water To HX Lo Press"

2. Loss of 'B' Service Water pump, requiring manual start of 'C' Service Water pump.

Time Position Applicant's Actions or Behavior URO/PRO Recognize and report the following alarms and enter corresponding Alarm Response Cards:

• 216 H-1 "'B' Service Water Pump Trip"

• 216 H-2 "'B' Service Water Pump OVLD"

• 216 F-1 "Service Water Header Lo Press"

• 216 F-5 "Fuel Pool Service Water To HX Lo Press" Recognize and report trip of the 2B Service Water pump.

Recognize and report trip of the 2A and 2B Fuel Pool Service Water (FPSW) booster pumps.

Green flag the 2B Service Water pump control switch.

Green flag the 2A and 2B FPSW booster pump control switches.

Dispatch an Equipment Operator to investigate the Service Water pump and breaker.

CRS Enter and direct actions of Alarm Response Cards 216 H-1, 216 H-2, 216 F-1 and 216 F-5.

Direct placing the 2C Service Water pump in service lAW SO 30.1.A-2 "Unit 2 Service Water System Normal Operations".

PRO Place the 2C Service Water pump in service lAW SO 30.1.A-2 as follows:

• Direct an Equipment Operator to prepare the 2C Service Water pump for start lAW SO 30.1.A-2, steps 4.2.3 and 4.2.4.

• Start the 2C Service Water pump by placing the pump contro! switch in "Run".

• Verify Service Water pump discharge pressure is 65-95 psig (both in the Control Room and locally).

20 II NRC Scenario #5 - T-lil Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 2 Page: 4of16 Event

Description:

'B' Service Water pump trips on overcurrent (continued)

Position Applicant's Actions or Behavior CRS Direct placing the 2A and 28 Fuel Pool Service Water booster pumps in service lAW SO 19.1.A-2 "Fuel Pool Cooling System Startup and Normal Operations" .

PRO Place the 2A and 2B Fuel Pool Service Water booster pumps in service lAW SO 19.1.A-2 as follows:

• Direct an Equipment Operator to prepare the 2A and 2B Fuel Pool Service Water booster pumps for start lAW SO 19.1.A-2, steps 4.2.4 and 4.2.5.

• Start the 2A Fuel Pool Service Water booster pump by placing the pump control switch in "Run".

• Start the 2B Fuel Pool Service Water booster pump by placing the pump control switch in "Run".

• Direct an Equipment Operator to adjust differential pressure for the 2A and 2B Fuel Pool Service Water booster pumps lAW SO 19.1.A-2, step 4.2.8.

CRS Request troubleshooting/technical assistance through the Shift Manager.

2011 NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 3 Page: 50f16 Event

Description:

Drywell pressure instrument fails upscale without the expected half scram Cause: PIS-2-5-12A fails upscale (gross failure)

Effects: Alarms:

• 210 F-1 "Drywell Hi Pressure Trip"

• 2100-4 "RPS/PCIS Trip Units in Calibration of Gross Failure" Drywell pressure instrument fails high (gross failure); RPS half scram fails to occur.

Position Applicant's Actions or Behavior URO Recognize and report the following alarms and enter the corresponding Alarm Response Cards:

• 210 F-1 "Drywell Hi Pressure Trip"

• 2100-4 "RPS/PCIS Trip Units in Calibration of Gross Failure" Determine actual drywell pressure is below the scram setpoint.

Recognize and report the drywell pressure instrument failure did NOT cause the expected RPS half scram.

CRS Enter and execute the Alarm Response Cards for 210 F-1 and 210 D-4.

Direct an Equipment Operator to check the instrument racks in the Reactor Building to aid in determining the cause of the trip.

CRS Direct troubleshooting in accordance with the Alarm Response Card for 210 D-4 "RPS/PCIS Trip Units in Calibration of Gross Failure".

Declare drywell pressure instrument PIS-2-5-12A inoperable.

Review Tech Spec 3.3.1.1 and determine Condition A applies (RPS Function 6 on Table 3.3.1.1-1):

• Place associated channel (or trip system) in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, OR

• Be in Mode 3 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Review Tech Spec 3.3.6.1 and determine Condition A applies (PCIS Function 2.b on Table 3.3.6.1-1):

• Place associated channel (or trip system) in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, OR

• Be in Mode 3 in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Mode 4 in the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Review Tech Spec 3.3.6.2 and determine Condition A applies (SCIS Function 2 on Table 3.3.6.2-1):

• Place associated channel (or trip system) in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, OR

• Take the compensatory actions for Condition C.

Recognize that RPS/PCIS trips must be installed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

20 II NRC Scenario #5 - T-I 11 Low Level, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 5 Event No.: 3 Page: 60f16 Event

Description:

Orywell pressure instrument fails upscale without the expected half scram (continued)

Position Applicant's Actions or Behavior NOTE: due to the RPS failure, the Lead Examiner will act as the Shift Manager and direct the crew to perform GP-25 to install the RPS/PCIS trips.

CRS Initiate GP-25 Appendices 1 and 5 to install redundant RPS/PCIS trips.

PRO Install trip on A 1 RPS channel as directed by the CRS using GP-25 Appendix 1:

• Complete Appendix 1.

• Inform URO that a half scram on RPS channel A1 will be inserted.

• At Pane120C015, insert key and place the A1 Test Keylock Switch to the TEST position.

NOTE: the next event will be initiated before the crew can perform Appendix 5 of GP-25 (PCIS).

2011 NRC Scenario #5 - T-lll Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 4 Page: 7 of 16 Event

Description:

'A' Condensate pump trip with automatic Recirc runback failure / power reduction Cause: 'A' Condensate pump trips on overcurrent / relay failure in the Recirc runback logic Effects: 1. Alarms:

• 203 E-1 "A Condensate Pump Overload"

• 203 E-2 "A Condensate Pump BKR Trip"

2. Recirc automatic runback fails to occur, resulting in lowering RPV level and requiring manual recirc flow reduction to control RPV level.

Time Position Applicant's Actions or Behavior URO Recognize and report trip of the 'A' Condensate pump.

Recognize and report the 45% Recirc pump run back failed to occur.

Recognize and announce entry into the OT-1 00 "Reactor Low Level":

• Recognize the RPV water level drop is caused by a lack of makeup capability, requiring power to be lowered with Recirculation.

• Reduce power by lowering the 'A' and 'B' Recirc pump speed controllers to a speed demand of 45% (NOTE: this must be done in a controlled manner that does not result in level swell and a high level trip of the Reactor Feed pumps).

Monitor for Thermal Hydraulic Instabilities (THI).

CRS Enter / direct actions of ARC 203 E-2 "A Condensate Pump BKR Trip":

• Direct the URO to lower power by lowering Recirc flow manually to 45% speed.

(May) refer to GP-5 "Power Operations" to determine power must be limited to <80% total feedwater flow with 2 Condensate and 3 Reactor Feedwater pumps.

Enter and direct actions lAW OT-112 "Unexpected/Unexplained Change in Core Flow".

Enter OT-1 00 "Reactor Low Level" (as necessary) - no additional actions are required.

PRO Investigate the cause of the 'A' Condensate pump trip using the applicable alarm response cards.

Direct an Equipment Operator to investigate the breaker and pump.

Green flag the 'A' Condensate pump control switch.

2011 NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions ES-D-2 OpTestNo.: 1 Scenario No.: 5 Event No.: 5/6 Page: 80f16 Event

Description:

Loss of #2 auxiliary bus (loss of Condensate and Feedwater) I RPS failure requires manual ARI initiation to scram the reactor Cause: Failure in the bus work results in an overcurrent condition and a bus lockout I RPS 'B' automatic and manual channel failure Effects: 1. Alarms:

• 219 A-2 "2 Aux Bus Overcurrent Relays"

• 219 B-2 "2 Aus Bus Lo Voltage"

2. #2 Auxiliary Bus breakers trip, de-energizing the bus and its loads

3. The immediate impact of loss of #2 Auxiliary Bus is the resultant loss of the remaining Condensate pumps, causing RPV water level to drop rapidly.

4. Full Reactor scram does not occur; manual ARI initiation is required.

5. Reactor level drop is greater because more time is spent under power conditions with no high-pressure injection.

Position Applicant's Actions or Behavior PRO Recognize and report the loss of #2 Auxiliary Bus.

URO Recognize and report Reactor water level is dropping rapidly.

Attempt to manually scram the Reactor by placing the Mode Selector Switch in "Shutdown".

Attempt to scram 'B' RPS by depressing the manual scram pushbutton.

Recognize and report an RPS scram has failed to occur.

Report entry into T-101 "RPV Control" for the ATWS condition.

CT CRS Recognize a failure to scram condition exists; enter and execute T-101 "RPV Control".

For RC/Q:

• Direct initiation of Alternate Rod Insertion (ARI).

2011 NRC Scenario #5 - 1'-111 Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 5/6 Page: 9 of 16 Event

Description:

Loss of #2 auxiliary bus I RPS failure (continued)

Position Applicant's Actions or Behavior CT URO Initiate ARI lAW RRC 38.1-2 "Alternate Rod Insertion During a Plant Event":

• Rotate the "A" and "8" ARI pushbutton collars to "Armed".

• Depress the "A" and "8" ARI push buttons.

• Verify the following ARI solenoid valves open:

o SV-2-03-141A o SV-2-03-142A o SV-2-03-1418 o SV-2-03-1428

• Verify and report the scram air header is depressurizing.

• Monitor and report when control rods begin to insert.

• Verify APRMs are downscale and report to the CRS.

• Report the status of RPV level control, RPV pressure control, Control Rods.

CRS Execute T-101 "RPV Control".

For RC/L:

• Direct restoring RPV level to +5 to +35 inches with HPCI and RCIC.

For RC/P:

• Direct instrument nitrogen bypassed and restored lAW GP-8E.

• Direct RPV pressure stabilized below 1050 psig.

PRO Perform applicable scram actions:

• Transfer 13 KV house loads (#1 bus only).

• Trip main turbine at approximately 50 MWe.

• Verify main generator lockout.

• Verify Group II & III isolations and SGTS initiation.

• Verify SDV vent and drain valves are closed.

• Verify HWC isolated.

• Verify recirc pumps are tripped.

• Report PRO scram actions to the CRS

• Monitor instrument air header pressure and drywell pressure; report instrument air header pressure is greater than drywell pressure.

201 J NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions OpTestNo.: 1 Scenario No.: 5 Event No.: 5/6 Page: 10 of 16 Event

Description:

Loss of #2 auxiliary bus I RPS failure (continued)

Position Applicant's Actions or Behavior PRO Bypass and restore drywell instrument nitrogen lAW GP-8E, as directed.

• Place both instrument nitrogen valve control switches to "Close".

• Place both keylock switches in "Bypass".

• Place both instrument nitrogen valve control switches to "Open" NOTE: this activity may be coordinated between the URO and the PRO.

URO/PRO Announce an additional entry condition for T -101 based on Reactor level below -48 inches.

Operate HPCI and RCIC to restore RPV level to +5 to +35 inches 2011 NRC Scenario #5 - T-Ill Low Level, Rev O.doc

Operator Actions ES-D-2 OpTest No.: 1 Scenario No.: 5 Event No.: 5 Page: 11 of 16 Event

Description:

Reactor coolant leak inside the drywell Cause: A leak develops on a weld joint on the suction piping of the "8" reactor recirculation pump after it tripped; the leak size propagates over time.

Effects: 1. Initial alarms:

• 210 F-2 "Drywell Hi-Lo Press"

• 225 A-4 "Drywell Hi-Lo Press"

2. Drywell pressure and temperature will rise at an increasing rate, eventually leading to a high drywell pressure alarm, ECCS automatic start signals, and PCIS isolation signals. Conditions will escalate requiring the use of containment sprays.

Time Position Applicant's Actions or Behavior URO/PRO Recognize and report alarms 210 F-2 "Drywell Hi-Lo Press" and 225 A-4 "Drywell Hi-Lo Press" and enter corresponding Alarm Response Cards.

CRS Enter and execute follow-up actions of OT-101 "High Drywell Pressure":

• When drywell pressure reaches 2 psig, then enter T-101 "RPV Control" and T -102 "Primary Containment Control" and execute concurrently with OT-101.

• Direct additional drywell cooling placed in service.

URO/PRO Maximize drywell cooling by placing all drywell cooler fans to RUN.

CRS Enter and execute T-102 "Primary Containment Control" when drywell pressure reaches 2 psig.

For PC/P:

• Direct torus sprays initiated lAW T-204 "Initiation of Containment Sprays Using RHR".

For DWIT:

• Direct drywell cooling maximized by performing T-223 "DW Cooler Fan 8ypass".

For PC/G:

• Direct CAD placed in service as time permits.

Re-enter T-102 when Torus level reaches 14.9 feet, and when Drywell temperature reaches 145 degrees F.

2011 NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 5 Page: 12 of 16 Event

Description:

Reactor coolant leak inside the drywell (continued)

Position Applicant's Actions or Behavior CRS When drywell pressure and temperature plot within the safe region of the Drywell Spray Initiation Limit Curve:

• Direct drywell cooling fans shut down.

CT

• Direct drywell sprays initiated lAW T-204 "Initiation of Containment Sprays Using RHR".

URO/PRO Monitor T-102 parameters (torus temperature, torus level, drywell pressure, torus pressure, drywell temperature) and provide trends to the CRS as appropriate.

URO Maximize drywell cooling by performing T-223 "OW Cooler Fan Bypass".

Shutdown drywell cooling fans when directed.

PRO Spray the torus in accordance with T-204 "Initiation of Containment Sprays Using RHR" (see Event #7).

CT Spray the drywell in accordance with T-204 "Initiation of Containment Sprays Using RHR".

URO/PRO Place CAD in service when directed.

Monitor RPV level, and report to the CRS RPV level is continuing to lower.

2011 NRC Scenario #5 T-Il1 Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 7 Page: 13 of 16 Event

Description:

Pressure instrument failure prevents using containment spray on 1 RHR loop Cause: Orywell pressure input to spray logic permissive not functioning Effects: Prevents containment spray using 8 (A) loop of RHR, resulting in Orywell temperature rising toward 281 degrees F (the A (8) loop of RHR is available).

Position Applicant's Actions or Behavior NOTE: the spray logic failure will effect whichever loop of RHR (8 or A) is first selected to spray the containment. The simulator operator will delete the associated override (failure) on the opposite RHR loop to allow spraying the containment with that loop. The steps listed below apply to the 8 loop of RHR but are the same as those for the A loop of RHR, with the exception of the letter designations.

PRO Spray the torus in accordance with T-204 "Initiation of Containment Sprays using RHR":

• Verify System 1 and 2 Orywell Pressure Permits Containment Spray annunciators (224 0-3, 225 8-3) are lit.

• Place keylock switch 10A-S188 in "MANUAL OVERRIDE".

• Momentarily place switch 10A-S178 in "MANUAL".

• Open or verify open MO-2-10-398 Torus Header".

• Open or verify open MO-2-10-898(D) HPSW Hx Outlet".

• Verify load on EOG supplying selected pumps is below 1400 KW.

• Start 8(0) RHR pump.

• Start 8(0) HPSW pump.

• Close or verify closed MO-2-10-348 "Full Flow Test".

• Throttle open MO-2-1 0-388 "Torus Spray" to obtain 1,000 gpm on FI 2-10-1368.

CT Recognize and report inability to spray the torus (drywell) with the 8 (A) loop of RHR.

CT CRS Direct the operator to attempt to spray the torus with the opposite loop of RHR.

CT PRO As directed, spray the torus using the opposite loop of RHR in accordance with T-204 "Initiation of Containment Sprays using RHR".

2011 NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 8 Page: 14 of 16 Event

Description:

HPCI turbine trip I emergency blowdown Cause: Instrument failure Effects: HPCI will trip after Drywell Sprays are in**service, required emergency blowdown Position Applicant's Actions or Behavior URO Recognize and report alarm 221 B-1 "HPCI Turb Trip" and enter the corresponding Alarm Response Card (as time permits).

Dispatch an Equipment Operator to determine the cause of the trip.

When report is received from the field, report to the CRS that there is no apparent cause for the HPCI trip.

CRS Direct SBlC initiation to augment RPV level control.

Direct T-246 "Maximize CRD Flow to the Reactor Vessel URO/PRO Initiate SBlC for RPV level control, as directed.

Perform T-246 "Maximize CRD Flow to the Reactor Vessel.

CRS After it is determined RPV level cannot be maintained above -172 inches, exit the RC/l leg of T-101 and enter/execute T-111 "level Restoration" :

• Direct ADS inhibited.

• Direct Core Spray and lPCI pumps started.

CT When RPV level drops to -172 inches, enter and execute T-112 "Emergency Blowdown":

• Verify torus level is above 7 feet.

• Verify reactor pressure is 50 psig above torus pressure.

• Direct 5 ADS SRVs opened.

URO/PRO Inhibit ADS when directed.

Verify start of all available Core Spray and lPCI pumps.

CT When directed, open 5 ADS SRVs by placing their control switches in OPEN.

20 II NRC Scenario #5 - T-III Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 8 Page: 15 of 16 Event

Description:

HPCI turbine trip I emergency blowdown (continued)

Cause: Instrument failure Effects: HPCI will trip after Drywell Sprays are in-service, required emergency blowdown Position Applicant's Actions or Behavior CT CRS After T-112 is executed, direct RPV injection maximized with all systems, subsystems, and alternate subsystems.

After it is determined RPV level can be maintained above -172 inches, exit T -111 and enter T-101, RPV Control at step RC/L -1.

Direct RPV level restored to +5 to +35 inches with Core Spray/RHR.

CT URO/PRO Maximize injection with all systems, subsystems, and alternate subsystems.

Restore and maintain RPV level +5 to +35 inches, as directed.

TERMINATION CRITERIA:

The scenario may be terminated when the RPV has been depressurized and reactor level has been recovered and controlled.

201 1 NRC Scenario #5 - '1'-111 Low Level, Rev O.doc

Operator Actions ES-D-2 Op Test No.: 1 Scenario No.: 5 Event No.: 9 Page: 16 of 16 Event

Description:

EAL classification Position Applicant's Actions or Behavior CRS Determine EAL classification using EP-AA-1 007.

• Based on the scenario conditions and expected outcome, the CRS will classify the event as FS1 "Loss of the Reactor Coolant System Barrier" and Potential Loss of Fuel Clad Barrier".

2011 NRC Scenario #5 - T-111 Low Level, Rev O.doc