ML17109A364
| ML17109A364 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/12/2016 |
| From: | Public Service Enterprise Group |
| To: | D'Antonio J Operations Branch I |
| Shared Package | |
| ML16076A441 | List: |
| References | |
| U01930 | |
| Download: ML17109A364 (317) | |
Text
{{#Wiki_filter:OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump TASK NUMBER: N0020080101 JPM NUMBER: 15-01 NRC RO A1-1 ALTERNATE PATH: l..____.l KIA NUMBER: ~~~~~~~~~---1 2.1.25 IMPORTANCE FACTOR: 3.9 APPLICABILITY: RO SRO EoD RO[ZJ STAD SROD EVALUATION SETTING/METHOD: Classroom
REFERENCES:
S2.0P-AR.ZZ-0003, Overhead Annunciators Window C, Rev. 19 S2.0P-SO.RC-0004, Identifying and Measuring Leakage, Rev. 16 (Both Rev checked 8-9-16) TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-9-16 Instructor Validated By: R Evans I N Mulford Date: 9-22-16 I 9-29-16 SME or Instructor ~ Approved By: Oper~ng ~a~r Approved By: Ope~rtment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 1 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: ~~~~~~~~~~~~~~ SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump TASK NUMBER: N0020080101 SIMULATOR SETUP N/A INITIAL CONDITIONS: Unit 2 is operating at 100% power, steady state, BOL. At 0015, OHA C-2 CNTMT SUMP PMP START unexpectedly annunciates, along with OHA A-41. The Aux typewriter shows 21 containment sump pump has started. 2 minutes later, OHA C-2 clears, OHA A-41 annunciates, and the Aux typewriter shows 21 containment sump pump has stopped. The plant remains stable, no indications of a RCS leak are apparent, and no operations have been performed which would cause containment sump level to rise. INITIATING CUE: You are the RO. Calculate the leak rate into the Containment Sump by performing Section 5.3 of S2.0P-SO.RC-0004, Identifying and Measuring Leakage. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion:
- 1. Calculate leakage into Containment Sump of 0.85-1.0 gpm.
Page 2 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~- SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U Evaluation)
Provide blank copy of S2.0P-SO.RC-0004, and marked up copy of Attachment 1. SO.RC-4 IF either Containment Sump Pump 5.3.1 AUTO starts, THEN RECORD the following on Attachment 1, Section 2.0:
- Operating Containment Sump Records 21 Cont Sump Pump Number
*
- Time of pump start Records time of pump start as 0015 SO.RC-4 CALCULATE elapsed time in minutes Calculates elapsed time in minutes 5.3.2 between start time and previous between start time and previous Containment Sump Pump stop time Containment Sump Pump stop time and AND RECORD on Attachment 1, records on Attachment 1, Section 2.0 by Section 2.0. using previous stop time of 1855
- yesterday, and with cue of 0015 today determines elapsed time is 320 minutes.
SO.RC-4 ENSURE no draining, sampling, or 5.3.3 liquid additions to Containment Sump Determines from initial conditions that have occurred during selected time no draining, sampling, or liquid additions frame. to Containment Sump have occurred during selected time frame. Page 3 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~ SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U Evaluation)
SO.RC-4 CALCULATE Containment Sump Calculates Containment Sump Leak 5.3.4 Leak Rate using Attachment 3. Rate using Attachment 3 (page 1 of 2),
- and determines the 320 minute line crosses the 0.9 gpm leak rate line.
Note: Due to no increment between 300 and 350 minutes, extrapolation of data may result in leak rate slightly above or below 0.9 gpm. However, the leakrate MUST be determined to be within the bounding numbers for actions required
>0.85 gpm (to initiate Section 5.6) and
>1.0 gpm (to initiate S2.0P-ST.RC-0008)
SO.RC-4 RECORD Containment Sump Pump Records Containment Sump Pump stop 5.3.5 stop time and date on Attachment 1, time as 0017 and todays date on Section 2.0. Attachment 1, Section 2.0. SO.RC-4 lE leakage to Containment Sump Determines leakage to Containment 5.3.6 exceeds 1.0 gpm AND Unit in Modes Sump does not exceed 1.0 gpm 1-4, THEN: A. INITIATE S2.0P-ST.RC-0008(Q), Reactor Coolant Water Inventory Balance. B. REFER to Technical Specification 3.4.7.2. Page 4 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~- SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U Evaluation)
SO.RC-4 IF leakage to Containment Sump Determines leakage to Containment 5.3.7 exceeds 0.85 gpm, THEN INITIATE Sump does exceed 0.85 gpm, and Section 5.6 of this procedure. initiates Section 5.6 of procedure. Terminate JPM when procedure is returned to evaluator. Page 5 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. Lv N"\. ~ 1. Task description and number, JPM description and number are identified. vv M ..-! 2. Knowledge and Abilities (KIA) references are included.
\µ N'\ ~ 3. Performance location specified. (in-plant, control room, or simulator) \y Ni d 4. Initial setup conditions are identified. \Jv N1 A/ 5. Initiating and terminating Cues are properly identified. \Jv Md 6. Task standards identified and verified by SME review.
\J' ML 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
~~d 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. JJ._ Date t/* Z. i. ... 'IP IC,
~~ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: ~ Date: ,,z t."ll SME/lnstructor: {)i[J/il ~ ,1{1,r d\ Date: _°l~{J._q _hb_ SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - - - Page 6 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
INITIAL CONDITIONS: Unit 2 is operating at 100% power, steady state, SOL. At 0015, OHA C-2 CNTMT SUMP PMP START unexpectedly annunciates, along with OHA A-41. The Aux typewriter shows 21 containment sump pump has started. 2 minutes later, OHA C-2 clears, OHA A-41 annunciates, and the Aux typewriter shows 21 containment sump pump has stopped. The plant remains stable, no indications of a RCS leak are apparent, and no operations have been performed which would cause containment sump level to rise. INITIATING CUE: You are the RO. Calculate the leak rate into the Containment Sump by performing Section 5.3 of S2.0P-SO.RC-0004, Identifying and Measuring Leakage. Page 7 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training
s2 .OP-SO.RC-0004(Q) ATTACHMENT 1 (Page 1 of 1) PUMP DATA 1.0 Previous Pump Data Date:l<>d~
- --- -~*--- - ~- ----- - -- ------- - - - --- ------ -*----- -- ---- ----- ------ -- - ---------
Pump Name Stop Time Elapsed Investigation Leak Rate Date Run Time Time (1)
'f d<j:JS RCDT lq c9.7 LO, Z5 5pm a<;ir1 q ,(,.'f':) m I~ N/A Cont Sump 1~5$ L 0.28_qprr. ~es-krclcj 11,31'1 min 7 days
;;. '1'17n-H's RX Sump 051(., '!34k\ifle Cle'() "B4&'( I ,.;e, 30 days 2.0 Daily Pump Data Stop-Start Leak IV Pump Name Start Stop Date Elapsed Rate Initials Time Time Initials Time (2)
Comments: I I (1) Investigation is required if AUTO pump run has not occurred in specified time frame:
- ENSURE OHA-C10 CONT SUMP OVRFLO not in alarm.
J£ C-10 can NOT be cleared !AW S2.0P-AR.ZZ-0003(Q), THEN containment entry is required to inspect sump level and annulus drain path for leakage .
- ENSURE OHA-C18 RX SUMP OVRFLO not in alarm, AND RX Sump requires inspection during next Containment Walkdown !AW S2.0P-PT.CAN-0001(Q).
(2) lE pumps are manually started OR tank/sump is purposely filled, THEN ENTER "Baseline" in Leak Rate column. lE Containment Sump OR Reactor Sump Leakrate exceed 0.85 gpm, THEN PERFORM Section 5.6. (Applicable Modes 1-4) lE RCDT Leak Rate exceeds 10.0 gpm, THEN REFER to Technical Specification 3.4.7.2d Action "b". SM/CRS Review_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date_ _ _ _ __ RETAIN a copy of this attachment with current Control Room Narrative Log. Salem 2 Page 21of42 Rev. 16
s2.oP-SO.RC-0004(Q) ATTACHMENT 3 (Page 1 of 2) CONTAINMENT SUMP LEAK RATE LEAKAGE LESS THAN 1 GPM I I I [!JJ I I I I I I I I I 1 ::5
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Salem 2 Page 24 of 42 Rev. 16
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Conduct of Operations TASK: Calculate Shutdown Margin TASK NUMBER: N1200030301 JPM NUMBER: 15-01 NRCROA1-2 ALTERNATE PATH: '----' KIA NUMBER: 2.1.43
--------~
IMPORTANCE FACTOR: 4.1 APPLICABILITY: RO SRO EOCJ ROITJ STAC] SROCJ EVALUATION SETTING/METHOD: Classroom
REFERENCES:
SC.RE-ST.ZZ-0002(0), Rev. 23 SHUTDOWN MARGIN CALCULATION S2.RE-RA.ZZ-0016(Q), Rev. 8 CURVE BOOK (both checked 8-9-16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 50 minutes Developed By: G Gauding Date: 8-9-16 Instructor Validated By: R Evans I N Mulford Date: 9-22-16 I 9-29-16 SME or lnstructo~l Approved By: Traef-1ent Approved By: Ope~rtment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: SYSTEM: Conduct of Operations TASK: Calculate Shutdown Margin TASK NUMBER: N1200030301 INITIAL CONDITIONS: - Unit 2 Reactor Power is 100%.
- All Control Rod Group Demand Counters are at 227 steps.
- Current boron concentration is 300 ppm.
- Current core burn up is 10,000 EFPH.
- Control Rod 105 was been declared INOPERABLE at 1000 today due to not moving out during a rod exercise test. You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.
- Control Rod 105 has been identified as trippable and is currently at 214 steps.
INITIATING CUE: The current time is 1010. This is a time critical JPM. Time will commence when you are provided with the applicable procedures. When performing calculation, the CRS directs you to use only the tables as directed by SC.RE-ST.ZZ-0002, do not use Figures. Successful Completion Criteria:
- 1. All critical steps completed
- 2. All sequential steps completed in order
- 3. All time-critical steps completed within allotted time
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Perform SOM calculation and determine SOM is -2441 (+/- 5 pcm) and SAT.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 7
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE:- - - - - - - - - - - System: Conduct of Operations Task: Calculate Shutdown Margin
- STEP NO. STEP STANDARD EVAL COMMENTS
(*Denotes a Critical Step) S/U (Required for UNSAT evaluation) Obtains copy of procedure SC.RE- Provide Rev. 23 of surveillance. ST.ZZ-0002(0). Obtains copy of S2.RE-RA.ZZ-0016 Curve Book. Provide Rev. 8 of Curve Book. Evaluator: MARK start time of JPM: 3.0 Reviews and signs off Precautions and Reviews Precautions & Limitations and Limitations Section 3.0 signs off Steps 3.1 - 3.7. 5.1 SELECT the applicable step below (e.g. Determines 5.1.1.C is the correct step 5.1.1.A): for the current conditions, which is to complete Attachment 3. 5.1.1.C IF SOM is to be verified (per T/S Refers to Attachment 3. 4.1.1.1.1.a) with reactor critical (Mode 1 or 2) and one or more control rods are inoperable, THEN COMPLETE Attachment 3. Att. 3 The reactor is in Mode 1 or Mode 2 Determines Unit is in Mode 1. with kett ~ 1.0 2.1 Att. 3 Precautions and Limitations: Section Reviews and signs steps 3.1-3.5. 3.0 3.0 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 7
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: _ _ _ _ _ _ _ _ _ __ System: Conduct of Operations Task: Calculate Shutdown Margin
- STEP NO. STEP STANDARD EVAL COMMENTS
(*Denotes a Critical Step) S/U (Required for UNSAT evaluation) Att.3 Section 4 contains the data points Determines the following data and Section required and the calculations to calculations: 4.1 determine shutdown margin. 4.1.1 100% 4.1.2 300 ppm 4.1.3 0@227 steps 4.1.4 10,000 EFPH 4.1.5 0 4.1.6 1
- Att. 3 4.2.1 -3841 Section 4.2.2 -3335 4.2 4.2.3 728 4.2.4 0 4.2.5 500 4.2.6 0 4.2.7 -5948
- Att.3 4.3.1 -5948 Section 4.3.2 645 4.3 4.3.3 120 4.3.4 2742 4.3.5 -2441 I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 7
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE: _ _ _ _ _ _ _ _ _ __ System: Conduct of Operations Task: Calculate Shutdown Margin
- STEP NO. STEP STANDARD EVAL COMMENTS
(*Denotes a Critical Step) S/U (Required for UNSAT evaluation) 4.4 Att 4 Acceptance Criteria Reviews required SOM in MODE 1 or 2 of -1300 pcm and initials 4.4.1.
- 4.4.1 IS THE SOM (Item 4.3.5) EQUAL TO OR MORE NEGATIVE THAN Determines calculated SOM is SAT and
(-)1300 PCM? initials SAT. Evaluator: MARK stop time of JPM: when procedures are returned to proctor. Total time from START to STOP is 50 minutes or less. Terminating Cue: Once operator has returned procedures to proctor, terminate JPM. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. N'\ ~ 1. Task description and number, JPM description and number are identified. f'M. 7 2. Knowledge and Abilities (KIA) references are included . ~ ./ 3. Performance location specified. (in-plant, control room, or simulator) N"\ f 4. Initial setup conditions are identified. tr\~ 5. Initiating and terminating Cues are properly identified. N"\ -L 6. Task standards identified and verified by SME review. 1'M ~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
~ -../ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. 'Z-l Date 7- Z'-'"'
13
~/ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.
~ Date: )- 2 c -I£
~A(A,lfi_A SME/lnstructor:
SME/lnstructor:(/ °'-"_/1(,_ _ Date: ----=-"}L-/ SME/lnstructor: Date: _ _ _ _ __
------------~
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 7
INITIAL CONDITIONS: - Unit 2 Reactor Power is 100%. - All Control Rod Group Demand Counters are at 227 steps. - Current boron concentration is 300 ppm. - Current core burn up is 10,000 EFPH. - Control Rod 105 was been declared INOPERABLE at 1000 today due to
- -not moving out during a rod exercise test. You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.
- Control Rod 105 has been identified as trippable and is currently at 214 steps. INITIATING CUE: The current time is 1010. This is a time critical JPM. Time will commence when you are provided with the applicable procedures. When performing calculation, the CRS directs you to use only the Tables as directed by SC.RE-ST.ZZ-0002, do not use Figures. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 7
PSEG Salem Unit 2 Page 89 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q} Rev: 8 CURVE BOOK- Salem Unit 2 Cycle 22 Table G Data Points for Curvebo Salem Unit 2 Cycle 22 Total Control Bank Worth versus Core Exposure
~nd CZP Conditions Cycle Burnup Control Bank Worth (pcm)
(EFPH) 68 °F 350 °F ( 547 of) 0.0 2764 3125 3655 100.0 2785 3148 3678 1000.0 2779 3131 3649 2000.0 2780 3121 3626 3000.0 2813 3146 3644 4000.0 2846 3171 3663 5000.0 2878 3196 3682 6000.0 2907 3221 3706 7000.0 2936 3246 3729 8000.0 2964 3272 3763 9000.0 2990 3299 3801
~ 3020 3328
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11000.0 3056 3366 3884 12000.0 3092 3404 3928 12490.9 3110 3423 3949 Page 1 of 1
PSEG Salem Unit 2 Page 88 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 C cle 22 Figure 15 Total Control Bank Worth versus Core Exposure for HZP and CZP Conditions 4200 I I I I I I I I I I ! I I 4100 I I I ! I I I I! ! I I I ml' a I Ii I I ! 4000 I I i 547 °F
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Page 1 of 1
0PSEG Salem Unit 2 Page 91 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cycle 22 Table H Data Points for Curveb~ Salem Unit 2 Cycle 22 Cycle Bumup Shutdown Bank Worth (pcm) (EFPH) 68 °F 350 °F ( 547 °~ 0.0 2655 2785 2984 100.0 2612 2745 2956 1000.0 2744 2874 3073 2000.0 2870 2998 3185 3000.0 2897 3023 3208 4000.0 2923 3047 3232 5000.0 2949 3071 3253 6000.0 2971 3090 3264 7000.0 2993 3108 3274 8000.0 3010 3123 3291 9000.0 3025 3137 3311
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11000.0 3092 3199 3370 12000.0 3137 3240 3406 12490.9 3159 3260 3424 Page 1 of 1
0PSEG Salem Unit 2 Page 90 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cycle 22 Figure 16 Total Shutdown Bank Worth versus Core Exposure for HZP and CZP Conditions 3500 pl I II I I I l I I
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Page 1 of 1
0PSEG Salem Unit2 Page 102 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cycle 22 Table 2*1 (Continued) Salem Unit 2 Cycle 22 Data Points for Curvebook Figure 17A EOL Total Power Defect (pcm) as a Function of Power and Boron Concentration
= =
Burnup 11756.0 EFPH, Range 8924.6 EFPH - EOL Power n Concentration (ppm) Le\1 % 50 100 150 200 250 300 350 400 450 500 550 600 650 700 750 0 0 0 0 0 0 5 179 178 176 175 174 173 172 170 169 168 167 166 165 164 163 162 10 350 347 345 343 340 338 336 333 331 329 327 325 323 321 319 318 15 513 510 506 503 499 496 493 489 486 483 480 477 474 472 469 466 20 671 666 661 657 652 648 644 639 635 631 627 623 620 616 612 609 25 823 817 811 805 800 794 789 784 779 774 769 764 759 755 750 746 30 970 963 956 949 943 936 930 923 917 911 905 900 894 889 883 878 35 1113 1105 1097 1089 1081 1074 1066 1059 1052 1045 1038 1031 1025 1018 1012 1006 40 1253 1244 1235 1226 1217 1208 1199 1191 1183 1175 1167 1159 1151 1144 1137 1130 45 1391 1380 1370 1360 1349 1339 1330 1320 1311 1302 1293 1284 1275 1267 1258 1250 50 1527 1515 1503 1492 1480 1469 1458 1447 1437 1426 1416 1406 1396 1387 1377 1368 55 1662 1649 1635 1622 1609 1597 1584 1572 1560 1549 1537 1526 1515 1504 1494 1484 60 1797 1782 1767 1752 1738 1724 1710 1697 1683 1670 1658 1645 1633 1621 1609 1597 65 1932 1915 1898 1882 1866 1850 1835 1820 1805 1791 1777 1763 1749 1736 1723 1710 70 2067 2049 2030 2012 1995 1977 1960 1944 1927 1912 1896 1881 1866 1851 1836 1822 75 2204 2183 2163 2143 2124 2105 2086 2068 2050 2032 2015 1998 1982 1966 1950 1934 80 2342 2320 2298 2276 2255 2234 2213 2193 2173 2154 2135 2117 2099 2081 2064 2047 83 2426 2402 2379 2356 2334 2312 2290 2269 2248 2228 2208 2188 2169 2151 2132 2114 85 2483 2458 2434 2410 2387 2364 2342 2320 2298 2277 2257 2237 2217 2197 2178 2160 90 2626 2599 2572 2547 2521 2497 2472 2449 2425 2402 2380 2358 2337 2315 2295 2275 95 2771 2742 2714 2686 2659 2632 2605 2580 2554 2530 2505 2482 2458 2436 2413 2391 99 2890 2859 2829 2800 2771 2742 2714 2687 2660 2634 2608 2583 2558 2533 2510 2486
<!!!) 2920 2889 2858 2828 2799 2770
~
2714 2687 2660 2634 2608 2583 2558 2534 2510 Page 7 of 8
0PSEG Salem Unit 2 Page 103 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cycle 22 Table 2-1 (Continued) Salem Unit 2 Cycle 22 Data Points for Curvebook Figure 17A EOL Total Power Defect (pcm) as a Function of Power and Boron Concentration Burnup = 11756.0 EFPH, Range= 8924.6 EFPH
- EOL Power Boron Concentration (ppm)
Le-.el (%) 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 1350 1400 1450 1500 o o o o o o 5 162 161 161 160 159 158 157 157 156 155 154 154 153 152 152 151 10 318 316 314 312 311 309 308 306 305 303 302 300 299 298 296 295 15 466 464 461 459 456 454 451 449 447 445 443 441 439 437 435 433 20 609 605 602 599 595 592 589 586 583 580 578 575 572 570 567 565 25 746 742 737 733 729 725 722 718 714 711 707 704 700 697 694 691 30 878 873 868 863 858 853 849 844 840 835 831 827 823 819 816 812 35 1006 1000 994 988 982 977 971 966 961 956 951 946 941 937 932 928 40 1130 1123 1116 1109 1103 1096 1090 1084 1078 1072 1066 1061 1055 1050 1045 1040 45 1250 1242 1234 1227 1219 1212 1205 1198 1191 1184 1178 1171 1165 1159 1153 1147 50 1368 1359 1350 1342 1333 1325 1317 1309 1301 1293 1286 1279 1272 1265 1258 1252 55 1484 1473 1464 1454 1444 1435 1426 1417 1408 1400 1391 1383 1375 1368 1360 1353 60 1597 1586 1575 1564 1554 1543 1533 1523 1513 1504 1495 1486 1477 1468 1460 1452 65 1710 1698 1685 1673 1662 1650 1639 1628 1617 1606 1596 1586 1576 1566 1557 1548 70 1822 1808 1795 1782 1769 1756 1743 1731 1719 1707 1696 1685 1674 1663 1653 1643 75 1934 1919 1904 1889 1875 1861 1847 1834 1821 1808 1795 1783 1771 1759 1748 1737 80 2047 2030 2013 1997 1982 1966 1951 1937 1922 1908 1894 1881 1868 1855 1842 1830 83 2114 2097 2080 2063 2046 2030 2014 1998 1983 1968 1954 1939 1926 1912 1899 1886 85 2160 2142 2124 2106 2089 2072 2056 2040 2024 2009 1993 1979 1964 1950 1937 1924 90 2275 2255 2235 2216 2198 2179 2161 2144 2127 2110 2093 2077 2062 2047 2032 2017 95 2391 2370 2349 2328 2308 2288 2269 2250 2231 2213 2195 2178 2161 2144 2128 2112 99 2486 2463 2441 2419 2398 2376 2356 2336 2316 2296 2277 2259 2241 2223 2206 2190 100 2510 2487 2464 2442 2420 2399 2378 2357 2337 2318 2298 2279 2261 2243 2226 2209 Page 8 of 8
0PSEG Salem Unit 2 Page 87 of 111 NuclearLLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cycle 22 Table I Salem Unit 2 Cycle 22 Most Reacti~od Worth versus Core Exposure
~nd CZP Conditions Cycle Bumup Worst Stuck Rod Worth (pcm)
(EFPH) 68 °F 350 °F ( 547 °F) 0.0 944 889 '924' 100.0 890 907 950 1000.0 948 861 870 2000.0 998 817 791 3000.0 981 802 765 4000.0 964 788 739 5000.0 947 774 712 6000.0 930 759 686 7000.0 942 767 689 8000.0 956 777 695 9000.0 982 796 707
~11000.0 1022 1061 827 858 CEi) 748 12000.0 1100 889 769 12490.9 1120 904 779 Salem Unit 2 Cycle 22 Most Reactive Stuck Rod Location versus Core Exposure for HZP and CZP Conditions Cycle Bumup Worst Stuck Rod Location (EFPH) 68 °F 350 °F 547 °F 0.0 M-04 K-06 H-08 91.4 M-04 K-06 H-08 1827.9 M-04 M-04 K-06 6093.1 M-04 M-04 K-06 8530.3 M-04 M-04 K-06 12490.9 M-04 M-04 H-06 Page 1 of 1
0PSEG Salem Unit 2 Page 86of111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cycle 22 Figure 14 Most Reactive Stuck Rod Worth versus Core Exposure for HZP and CZP Conditions 1200 I m
! I 1150 I
I I I I I I I I I i I I I I I I i m1 I
. I I I I I I I I I 68 °F ILL.I-I I I I I rTTTI 1-I I I I /i 1100 ! ! I ! ! I I I i i I I I I I !-
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,..... I I ~*, l ! I I I I
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I I I I I ! I I I i I I I I i I i ! i I i ; ! I I I I 650 I I I I I I I I I I I I I I I I I ! I I I ! I I 600 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 Cycle Burn up (EFPH) Page 1 of 1
0PSEG Salem Unit 2 Page 14 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2.RE-RA.ZZ-0016(Q) Rev: 8 CURVE BOOK- Salem Unit 2 Cycle 22
~
Sal~e22 Summary of Control Rod Worths HZP. No Xe Control and Shutdown Burnup (EFPH) Control Banks (pcm) Shutdown Banks (pcm) Banks(pcm) BOL 0.0 3654. 1 2984.0 6638. 1 MRDS 1827.9 3622.0 3181.2 6803.2 MOL 6093. 1 3703.9 3265.3 6969.2 LFPC 11756.0 3915.5 3393.8 7309.3
~rth~nalty to Use for Modes 1, 2~
Rod Worth Penalty (pcm) Rod Worth Penalty (pcm) Event A BOL to < MOL (6093.1 EFPH) MOL (6093.1 EFPH) to EOL One Untrippable RCCA 2195 2285 Rod Worth Penalty (pcm) Event B BOL to EOL Two or more Untrippable 2285 RCCAs Rod Worth Penalty Event C (pcm)* BOL to EOL
*In the event of a misaligned RCCA, apply dropped RCCA penalty.
Rod Worth Penalty to Use for Modes 3, 4, 5 Rod Worth Penalty (pcm) Event D BOL to EOL One or more Untrippable RCCA(s) OR 2715 One or more Failed IRPI lndication(s) Highest (ARl-1) Stuck Rod Worths for Cycle 22 Burnup (EFPH) Rod Location Temperature (°F) Rod Worths (pcm) BOL 0.0 H-08 547.0 1097. 1* MRDS 1827.9 K-06 547.0 907.9 MOL 6093.1 K-06 547.0 785.8 LFPC 11756.0 H-06 547.0 880.8
*Highest stuck rod worth for all conditions The EFPH to MWD/MTU conversion factor is 1.64120 MWD/MTU/EFPH Page 1 of 1
0PSEG Salem Unit 2 Page 15 of 111 Nuclear LLC LEVEL 2 - REFERENCE USE S2. RE-RA.ZZ-0016( Q) Rev: 8 CURVE BOOK - Salem Unit 2 Cvcle 22 Table P Salem Unit 2 Cycle 22 Boron Concentration Requirements for IRPI Calibration and RCCA Drop Testing Boron Concentration (ppm) RCCA Configuration and Keff Temcerature 68 °F 200 °F 350 °F 450 °F 500 °F 547 °F ARO, 0.98 2150 2179 2223 2249 2264 2133 Control Bank In, Shutdown Bank Out, 0.95 2197 2212 2228 2227 2223 2051 Control Bank Out, Shutdown Bank In, 0.95 2327 2365 2425 2463 2482 2362 NOTE: All boron concentration values except for 547 °F contain 100 ppm conservatism. NOTE: All boron concentration values were computed at zero power, no xenon conditions. Page 1 of 1
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs TASK NUMBER: N0040420201 JPM NUMBER: 15-01 NRC RO Admin A2 ALTERNATE PATH: I..._ . . I. KIA NUMBER: 2.2.37
~~~~~~~~~---!
IMPORTANCE FACTOR: 3.6 4.6 APPLICABILITY: RO SRO EOLJ RO[RJ STAD SRO[RJ EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-ST.CVC-0010, Rev. 10 (checked 9-28-16)
REFERENCES:
Salem Tech Specs TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 11 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-9-16 Instructor Validated By: S Harris I J Pierce Date: 9-28-16 SME or lnstru Jl, Approved By: Training partmeh{\ Date: 1*/i ,f v Approved By: Operatio~ Date: I6 /11 /1t., ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs TASK NUMBER: N0040420201 SIMULATOR SETUP: IC-249 Reset IC for each JPM and ensure Plant Computer is returned to a neutral screen. RWST levels - CH I 41.4 CH II 41.4 CH 111 41.4 CH IV 41.5 BAST levels - 21 BAST 49.5 22 BAST 49.5 INITIAL CONDITIONS:
- Salem Unit 2 is at 100% power.
- 21 BAT pump developed a leak that went unnoticed until the cross-connected BAST's reached their low level alarm setpoint.
- 21 BAT pump, and the leak, are isolated.
- Chemistry reports current RWST and BAST boron concentrations are:
- 21 BAST - 6610 ppm
- 22 BAST - 6610 ppm
- RWST - 2350 ppm
- Off Normal and Off-Normal Tagged list review has been performed SAT.
INITIATING CUE: You are the Reactor Operator. Perform S2.0P-ST.CVC-0010, Borated Water Sources. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Complete Attachment 2 of S2.0P-ST.CVC-0010 per key and determine the Surveillance is SAT PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~- SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Provide marked up copy of S2.0P-ST.CVC-0010, Borated Water Sources. 3.0 Precautions and Limitations Reads and initials steps. 5.1.1 COMPLETE Attachment 2 per the Completes Attachment 2 with the below data. following:
- RECORD Data .
- RECORD Test Results by initialing SAT or UNSAT column using the stated Acceptance Criteria.
- Att.2 RWST Level Records RWST level with channel for which calibration data was obtained RWST levels are:
CH I: 41.4 CH II: 41.4 CH 111: 41.4 CH IV: 41.5 Initials SAT for RWST Level and inserts date.
- Att. 2 RWSTTemp Checks P-250 computer point T0650A and enters 70°F. Initials SAT for RWST Temp and inserts date.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD SIU evaluation)
- Att. 2 RWSTConc Refers to initial conditions for RWST boron concentration and enters 2350 ppm. Initials SAT for RWST boron concentration and inserts date.
- Att. 2 21 BAST Vol AND/OR 22 BAST Vol Records 21 and 22 BAST level indicated on control console from 2Ll106 and 2Ll102 respectively as 2Ll106-49.5%
2Ll102 - 49.5% Uses Tech Spec 3.1.2.6.a, 3.1.2.6.b, and Figure 3.1-2 and determines 21 BAST Vol AND/OR 22 BAST Vol is SAT. Initials SAT for BAST volume and inserts date.
- Att. 2 21 BAST Temp AND/OR 22 BAST Temp Records 21 and 22 BAST temp indicated on control console from 2Tl107 and 2Tl103 respectively as:
2TI 107 - 98.2 2Tl103 - 97.1 Initials SAT for 21 BAST Temp AND/OR 22 BAST Temp and inserts date. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~- SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Refers to initial conditions for BAST boron
- Att. 2 21 BAST Cone AND/OR 22 BAST Cone concentrations and enters 6610 ppm for 21 BAST and 6610 ppm for 22 BAST.
Uses Tech Spec 3.1.2.6.a, 3.1.2.6.b, and Figure 3.1-2 and determines 21and22 BAST boron concentration is SAT. Initials and inserts date. 5.3.1 This surveillance is considered satisfactory when Attachments 2 and 3 Initials step 5.3.1 (as applicable) are complete with components listed meeting Acceptance Criteria stated in each Attachment. OR 5.3.2 This surveillance is unsatisfactory. N/A's 5.3.2. A. INITIATE Notification(s) to correct the unsatisfactory condition. B. RECORD Notification number(s) and reason for unsatisfactory completion on Attachment 4 in the Comments Section. 5.4.1 COMPLETE Attachment 4, Sections 1.0 Completes Attachment 4, Sections 1.0 and and 2.0, AND FORWARD this procedure 2.0, and returns procedure to JPM Evaluator. to the SM/CRS for review. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
JPM is complete when procedure is returned to evaluator. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 8
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CQtfQITION FQR QPERATION 3.1.2.6 As a minimum, the following borated water source(s) shall be OPERABLE as required by Specifications 3.1.2.1 and 3.1.2.2:
- a. A boric acid storage system with:
- 1. A contained volume of borated water in accordance with figure 3.1-2,
- 2. A Boron concentration in accordance with Figure 3.1-2, and
- 3. A minimum solution temperature of 63°F.
- b. The refueling water storage tank with:
- 1. A contained volume of between 364,500 and 400,000 gallons of water,
- 2. A boron concentration of between 2,300 and 2,500 ppm, and
- 3. A minimum solution temperature of 35°F.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION:
- a. With the boric acid storage system inoperable and being used as one of the above required borated water sources, restore the storage system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and borated to a SHUTDOWN MARGIN equivalent to at least 1% delta k/k at 200°F; restore the boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.
- b. With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:
- a. For the boric acid storage system, when it is the source of borated water in accordance with the Surveillance Frequency Control Program by:
- 1. Verifying the boron concentration in each water source.
- 2. Verifying the water level of each water source, and
- 3. Verifying the boric acid storage system solution temperature.
- b. For the refueling water storage tank by:
- 1. Verifying the boron concentration in accordance with the Surveillance Frequency Control Program,
- 2. Verifying the borated water volume in accordance with the Surveillance Frequency Control Program, and
- 3. Verifying the solution temperature in accordance with the Survelllance Frequency Control Program when the outside air temperature is less than 35°F.
SALEM - UNIT 2 3/4 1-12 Amendment No. 282
BORIC ACID TANK CONTENTS BASED ON RWST CONCENTRATION
~ 100%
zw u a: UJ
- 0. 98°A,
~
~
al
~- 95%
w
- ?
0 92% 0 w a:
~ 90% ~ ~ ..J z<
87%
-0~
.z 85% e,eoo a,100 e,aoo a.soo 1.000 CONCENTRATION IN BAT - ppm BORON SALEM
- UNIT 2 Figure 3. 1-2 j/4 1*12(1) l~nt11':'lf'nt Ho. lJJ
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. \Jv© ~ I 1. Task description and number, JPM description and number are identified.
\JV ~ 2. Knowledge and Abilities (KIA) references are included. \y 7 h~ 3. Performance location specified. (in-plant, control room, or simulator) \.rJ J 4. Initial setup conditions are identified. ~
7A 5. Initiating and terminating Cues are properly identified.
~ ~ 6. Task standards identified and verified by SME review. ~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*). ~ 4 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _1_0_ Date <T(J., ( 13 \f A 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructo~.Jou% .(:'.,, :J * \?,.,_,""- Date: l Q t-fS lib SME/lnstructor;A M'% .h-1 S- ~.:r<n- { Date: -q/Mho SME/lnstructor: Date: - - - - - - PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8
INITIAL CONDITIONS:
- Salem Unit 2 is at 100% power.
- 21 BAT pump developed a leak that went unnoticed until the cross-connected BAST's reached their low level alarm setpoint.
- 21 BAT pump, and the leak, are isolated.
- Chemistry reports current RWST and BAST boron concentrations are:
- 21 BAST - 6610 ppm
- 22 BAST - 6610 ppm
- RWST - 2350 ppm
- Off Normal and Off-Normal Tagged list review has been performed SAT.
INITIATING CUE: You are the Reactor Operator. Perform S2.0P-ST.CVC-0010, Borated Water Sources Data. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 8
PSEG Internal Use Onlv Page _l_ of _l_ PSEG NUCLEAR L.L.C. SALEM/OPERATIONS S2.0P-ST.CVC-0010(Q) - REV. 10 BORATED \VATER SOURCES USE CATEGORY : II
- Biennial Review Performed: Yes No _L_
Change Package(s) and Affected Document Numbers incorporated into this revision: None
- The following OTSC(s) were incorporated into this revision: None REVISION
SUMMARY
+ Added P&L 3.2 for boron administrative limit for the RWST. [70152703] + Added step 5.3.2.A which allows the user to skip writing a notification ifthis surveillance is UNSAT due to purposely changing boron concentration in the BASTs (and they are being tracked in the tech spec tracking log). [70152165] + Revised the acceptance criteria for the RWST in Attachment 3 to match the actual requirements in Tech. Spec. 3.1.2.5. [70092142]
IMPLEMENTATION REQUIREMENTS Effective Date: April 30, 2013 None
s2 .OP-ST .cvc-001 O(Q) BORATED \VATER SOURCES TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE ................................................................ 2 2.0 PREREQUISITES .......................................................... 2 3.0 PRECAUTIONS AND LIMITATIONS ......................................... 2 4.0 EQUIPMENT/MATERIAL REQUIRED ........................................ 2 5.0 PROCEDURE ............................................................. 3 5.1 Borated Water Sources - Modes 1-4 ..................................... 3 5.2 Borated Water Sources - Modes 5-6 ..................................... 3 5.3 Acceptance Criteria .................................................. 3 5.4 Completion and Review .............................................. 4 6.0 RECORDS ................................................................ 5
7.0 REFERENCES
............................................................. 5 ATTACHMENTS Instrument and Test Equipment Data ............................... 6 Borated Water Sources Data Modes 1-4 ............................. 7 Borated Water Sources Data Modes 5-6 ............................. 8 Completion Sign-Off Sheet ...................................... 9 Salem 2 Page 1of10 Rev.10
s2 .OP-ST.cvc-001 O(Q) 1.0 PURPOSE 1.1 Provide instructions necessary to: 1.1.1 Demonstrate operability of Refueling Water Storage Tank (RWST) AND Boric Acid Storage Tanks (BAST) in Modes 1-4 IAW Technical Specification 4.1.2.6.a.1, 4.1.2.6.a.2, 4.1.2.6.a.3, 4.1.2.6.b.1, 4.1.2.6.b.2, 4.5.5.a. l, and 4.5.5.a.2 [C0265] 1.1.2 Demonstrate operability of RWST OR BAST in Modes 5 and 6 IAW Technical Specification 4.1.2.5.a.1, 4.1.2.5.a.2, 4.1.2.5.a.3, 4.1.2.5.b.1, and 4.1.2.5.b.2 [C0265] 1.2 This procedure is required at least once per 7 days in Modes 1-6. 2.0 PREREQUISITES
.a
.r=- 2.1 IDENTIFY sections of this procedure that are NOT to be performed with "NIA" . ~ 2.2 REVIE'W Components "Off Normal and Off-Normal Tagged" List(s) for system and support system(s) associated with evolution to be performed in this procedure. 2.3 ENSURE calibration data for the instruments listed in Attachment 1, as applicable, is obtained. [C0289] .LJ_ 2.4 ENSURE current RWST and BAST boron concentrations are obtained by Chemistry. 3.0 PRECAUTIONS AND LIMITATIONS 3 .1 Steps identified with dollar sign ($) are those items required to meet Technical Specification acceptance criteria. Such steps, if not satisfactorily completed, may have reportability requirements and shall be brought to immediate attention of the SM/CRS. 3.2 In Modes 1-4 RWST boron concentration should be maintained within the administrative limits of 2328 - 2470 ppm. In Modes 5, 6, and Defueled boron concentration should be maintained> 2328 ppm. 4.0 EQUIPMENT/MATERIAL REQUIRED None Salem 2 Page 2of10 Rev.10
s2.oP-S T.cvc-oolO(Q) 5.0 PROCEDURE 8 Borated \Yater Sources - Modes 1-4 5.1.1 COlVIPLETE Attachment 2 per the following:
+ RECORD Data.
+ RECORD Test Results by initialing SAT or UNSAT column using the stated Acceptance Criteria.
5.2 Borated \Vater Sources - Modes 5-6 COMPLETE Attachment 3 per the following:
+ RECORD Data.
+ RECORD Test Results by initialing SAT or UNSAT column using the stated Acceptance Criteria.
5.3 Acceptance Criteria 5.3.1 This surveillance is considered satisfactory when Attachments 2 and 3
$ (as applicable) are complete with components listed meeting Acceptance Criteria stated in each Attachment.
5 .3 .2 This surveillance is unsatisfactory. A. IF the cause of the UN SAT surveillance is due to BAST level being out of specification for expected conditions (e.g. outage preparations) AND this condition is being tracked in the Tech Spec Tracking Log THEN a notification is not required AND GO TO Section 5.4. B. INITIATE Notification(s) to correct the unsatisfactory condition(s). C. RECORD Notification number(s) and reason for unsatisfactory completion on Attachment 4 in the Comments Section. Salem 2 Page 3of10 Rev.10
s2 .oP-S T.cvc-0010(Q) 5.4 Completion and Review 5.4.l COMPLETE Attachment 4, Sections 1.0 and 2.0, AND FOR\VARD this procedure to the SM/CRS for review. 5.4.2 SM/CRS PERFORM the following: A. REVIE\V this procedure with Attachments 1 through 4 for completeness and accuracy. B. COMPLETE Attachment 4, Section 3.0. C. IF ANY Evaluation Result is identified as UNSAT for applicable Mode, THEN ENTER applicable Technical Specification Action Statement(s). D. COMPLETE Attachment 4, Section 4.0. E. FORWARD completed procedure to Operations Staff. END OF PROCEDURE SECTION Salem 2 Page 4of10 Rev.10
s2.oP-S T.cvc-0010(Q) 6.0 RECORDS 6.1 Retain the following IAW RM-AA-101, Records Management Program: Attachment 1 Attachment 2 (as applicable) Attachment 3 (as applicable) Attachment 4
7.0 REFERENCES
7.1 Updated Final Safety Analvsis Report: 7.1.1 Section 9.3.4, Chemical and Volume Control System
7.2 Procedures
7.2.1 SC.CH-TI.ZZ-0180(Q), Sampling Schedule and Chemistry Specifications
7.3 Drawings
7.3.1 205328, Chemical & Volume Control Operation 7.3.2 205334, Safety Injection 7.4 Cross-
References:
7.4.1 Technical Specifications - Unit 2: A. 3/4.1.2.5, Borated Water Sources - Shutdown B. 3/4.1.2.6, Borated Water Sources - Operating C. 3/4.5.5, Refueling Water Storage Tank
7.4.2 Procedures
A. RM-AA-101, Records Management Program B. S2.0P-TM.ZZ-0002(Q), Tank Capacity Data
7.4.3 Others
A. DCP 2EC-3225, Boric Acid Concentration Reduction B. Tech Spec Amendment No. 133
7.5 Commitments
7.5.1 C0265 - NSO LER 311/89-015-00 7.5.2 C0283 - NRC VIOL 311/87-18-01 Salem 2 Page 5of10 Rev.10
s2.oP-S T.cvc-ooIO(Q) ATTACHMENT 1 (Page 1 of 1) INSTRUMENTATION AND TEST EQUIPMENT DATA Instrument/Test Calibration Description Initials Equipment Overdue Date
. [
4 fW f1t ~S'l'"',o,,J 2LT960 -r'(V<"Y)
~
2LT961
\
jj Safety Injection Refueling Water 2LT962 Storage Tanlc Level Transmitter (1)
,Id 2LT963
~ /}
2LT106 21 BAST Level Channel ( ,....0~ 3 f'l;JiH*I,.1 'f('l,,.. tJ 2LT102 22 BAST Level Channel l Jt!J 2TI107 21 BAST Temp Channel j) 2TI103 22 BAST Temp Channel
;:}
2TA3685 (T0650A) RWST Temperature J A (1) Calibration data required for at least one channel. Channel selected is utilized when recording data for this parameter. Salem 2 Page 6of10 Rev.10
s2 .OP-ST.cvc-ooto(Q) ATTACHMENT 2 (Page 1of1) BORATED WATER SOURCES DATA MODES 1-4 Test Results Parameter Data Acceptance Criteria Date SAT UNSAT (la., vt:.i? c;.., j RWSTLevel ch.e.:nn" \
~ 2LT960_
2LT961 2LT962 I.fl.'"! u.1.'-\ 41 . ../ Lll f ft 364,500 to 400,000 gals (240.5 ft ~41.9 ft) v (Note 2) 2LT963 - RWSTTemp 10 op 235°F
/'
T0650A RWSTConc .d.35 0 ppm 22,300 and ~2,500 ppm ~ 21 BAST Vol 'f GI'..)C:" % IAW (2LI106) Tech Spec
@PR 3.1.2.6.a and 3.1.2.6.b i/
'19.s* % Figure 3.1-2 22 BAST Vol (2LI102) (Note 1) 21 BAST Temp '1i.:;i.... op (2TI107)
AND/OR QI.\ op 263°F
~
22BASTTemp (2TI103) 21 BAST Cone fv~I 0 ppm Tech Spec (21 BAST) 3.1.2.6.a and 3.1.2.6.b AND/OR
~&iOppm Figure 3.1-2 /
(Note 1) 22 BAST Cone (22 BAST) (1) If one BAST is the borated water source, then level and concentration requirements must be maintained in acceptable operation region of figure 3.1-2. If two BAS Ts are the borated water source, then combine volumes are used to satisfy Tech Spec 3.1.2.6.a. (2) Refer to S2.0P-TM.ZZ-0002(Q), Tank Capacity Data. Salem2 Page 7of10 Rev. 10
s2 .OP-ST .cvc-0010(Q) ATTACHMENT 3 (Page 1 of 1) BORATED \VATERSOURCES DATA MODES 5-6 1.0 RWST AS BORATED \VATER SOURCE: Test Results Parameter Data Acceptance Criteria Date SAT UNSAT RWST Level 2LT960-2LT961 - ft 2LT962- ~ 37,000 gals c~ 1.9 ft) 2LT963 - RWSTTemp op
~35°P T0650A Boron Cone ppm ~2300 ppm 2.0 BAST AS BORATED WATER SOURCE:
Test Results Date Parameter Data Acceptance Criteria SAT UNSAT 21 BAST Vol % (2LI106) AND/OR ~ 2600 gallons
% (Note 1) 22 BAST Vol (2LI102) 21 BAST Temp op (2TI107)
AND/OR op ~63°F 22 BAST Temp (2TI103) 21 BAST Cone ppm 21 BAST ~6560 ppm AND/OR & ppm ~6990 ppm 22 BAST Cone 22 BAST (1) One or two BASTs may be used as the Borated Water Source, if two BASTs are the Borated Water Source, then combined volumes are used to satisfy Tech Spec. Refer to BAST graph IAW S2.0P-TM.ZZ-0002(Q), Tank Capacity Data graph for% level to gallons conversion. Salem 2 Page 8of10 Rev. 10
s2 .oP-S T .cvc-001o(Q) ATTACHMENT 4 (Page 1of2) COMPLETION SIGN-OFF SHEET
1.0 COMMENTS
(Include test deficiencies and corrective actions.)
2.0 SIGNATURES
Print Initials Signature Date
~I Salem 2 Page 9of10 Rev.10
s2.oP-S T.cvc-0010(Q) ATTACHMENT 4 (Page 2of2) COMPLETION SIGN-OFF SHEET 3.0 EVALUATION OF TEST RESULTS: Test Results Modes Source(s) SAT UNSAT RWST and/or BAST are operable IAW Attachment 2 as required by Tech Spec 3.1.2.1 1-4 or 3.1.2.2. RWST is operable IAW Attachment 3, Section 1.0 OR 5-6 BAST is operable IAW Attachment 3, Section 2.0 4.0 SM/CRS FINAL REVIE\V AND APPROVAL: This procedure with Attachments 1-4 has been reviewed for completeness and accuracy. All deficiencies, including corrective actions, have been clearly recorded in COM:MENTS Section above. Technical Specification compliance, procedure compliance, and Acceptance Criteria have been evaluated. [C0283] Date:- - - - - - SM/CRS Salem 2 Page 10of10 Rev.10
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE (ALARA) TASK: Perform Stay Time Calculation for Emergency Condition. TASK NUMBER: N1200100104 JPM NUMBER: 15-01 NRC RO A3 ALTERNATEPATH: c=J K/ANUMBER:~~~-2_.3_.4~~__, IMPORTANCE FACTOR: - - 3.2 APPLICABILITY: RO SRO EoD Ro[)) STAD sRoD EVALUATION SETTING/METHOD: Classroom
REFERENCES:
Radiological Survey Maps, RP-AA-203 Rev. 6, NC.EP-EP.ZZ-0304 Rev. 16 TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-9-16 Instructor Validated By: R Evans IN Mulford Date: 9-22-16 I 9-29-16 SME or lnst:t~~L 10/t/1 Approved By: T~ent Date: (p Approved By: Date: 10/11/1& 0 rations De artment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE:
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: SYSTEM: ADMINISTRATIVE (ALARA) TASK: Perform Stay Time Calculation for Emergency Condition. TASK NUMBER: N1200100104 INITIAL CONDITIONS:
- 1. Unit 1 experienced Rx trip with a small RCS leak from 100% power.
- 2. The Rx failed to automatically trip on a valid trip demand, and was tripped successfully with the Rx trip handle.
- 3. Salem is currently in an Alert.
- 4. Your TEDE dose for the year is 1925 mrem.
INITIATING CUE: You have been directed to perform a detailed inspection of 22 RHR pump room prior to starting the pump. You will NOT be going into the 22 RHR HX area. Your job is estimated to take 2 hours to complete. Using the correct survey map, and conservatively using the HIGHEST dose rate anywhere in the pump room for your ENTIRE exposure, determine:
- 1. Can you complete the job without exceeding your current dose authorization
- 2. What would be your new TEDE dose for the year after performing the job (or as much as possible) WITHOUT exceeding your current dose authorization?
Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion: Determines:
- 1. YES job can be performed
- 2. Calculates new TEDE dose of 2005 mrem.
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: ADMINISTRATIVE (ALARA) TASK: Determine Radiological Conditions For Personnel Exposure STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Provide the attached survey maps of 21 and 22 RHR rooms, and S1 and S2 55 Selects the Survey Map General area. Also have blank copies of "S2 AUX 045' 22 RHR ROOMS" RP-AA-203, Exposure Control and 1 Map# 21045Z2 Authorization and NC.EP-EP.ZZ-0304, Operational Support Center (OSC) Radiation Protection Response if asked for. START TIME: If asked, provide NC.EP-EP.ZZ-0304, Note: Contains guidance for automatic OSC Radiation Protection Response. increase in allowed dose to 4500 mrem. (Section 5.0 Note.) Determines dose limit is automatically raised to 4500 mrem upon the declaration of an ALERT or higher Emergency. Page 3 of 6
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~ SYSTEM: ADMINISTRATIVE (ALARA) TASK: Determine Radiological Conditions For Personnel Exposure STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation}
2 Determine highest dose rate in room. Per the survey map, squares are dose
- rates in mrem/hr, and circles are smear locations. The highest square is located under the words "22RH37" on the map and indicates 40 mrem/hr.
Note: The square with "250" inside it is in the RHR HX room, and is not in the area which the operator will go. 3 Calculate TEDE dose for year Subtracts year to date TEDE dose from
- Emergency Dose limit of 4,500 mrem, and gets 2575 mrem. Determines 2 hours of work will result in 80 mrem dose, and new TEDE dose is 2005 mrem, which does NOT exceed 4,500 mrem authorized in an Emergency.
Terminate JPM when candidate has returned paperwork. 4 STOP TIME: Page 4 of 6
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. \Jv N-\ d 1. Task description and number, JPM description and number are identified.
~
V" ~ 2. Knowledge and Abilities (K/A) references are included. v~ ,../ 3. Performance location specified. (in-plant, control room, or simulator) v M~ 4. Initial setup conditions are identified. v tt\ ~ 5. Initiating and terminating Cues are properly identified. \J N'\ -/ 6. Task standards identified and verified by SME review. \J N1 £ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*) .
\J N1 ..( 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _Ct>__ Date S'~"Z-i-* tig Iv Nj ~ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SMEllnstructor: ~ Date: 9- 2. -z. - '"" SME/lnstructor: ~.;1/f)wJ Date: q /3-'t/1h SME/lnstructor: Date: - - - - - - Page 5 of 6
INITIAL CONDITIONS:
- 1. Unit 1 experienced Rx trip with a small RCS leak from 100% power.
- 2. The Rx failed to automatically trip on a valid trip demand, and was tripped successfully with the Rx trip handle.
- 3. Salem is currently in an Alert.
- 4. Your TEDE dose for the year is 1925 mrem.
INITIATING CUE: You have been directed to perform a detailed inspection of 22 RHR pump room prior to starting the pump. You will NOT be going into the 22 RHR HX area. Your job is estimated to take 2 hours to complete. Using the correct survey map, and conservatively using the HIGHEST dose rate anywhere in the pump room for your ENTIRE exposure, determine:
- 1. Can you complete the job without exceeding your current dose authorization
- 2. What would be your new TEDE dose for the year after performing the job (or as much as possible) WITHOUT exceeding your current dose authorization?
1. 2. Page 6 of 6
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RucHologica[ po;;tir!g;, !ab<:ls, n:Llrkir"-;;, 0 Dose Rate, rnRemihr U, Smear Location
Radiological Survey 1105500
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i n Dose Rate: mRem/i"'.µ ~-, f./fa.ssiinr1 Path 0, Smear Location !Locatirm: Sl AUX 055' GENER.Al AP-EA jDate:,
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,__,,__.........._ _ _ __, \}Mpin~ r~sults <1000 dpm/16cm2 on floors, walls & equipment @-----7 [~erified Radioiogicat postings, iabe!s, marking, and barriers ~3 0~ Technician Review
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review a completed surveillance to demonstrate Operability of 21 CFCU TASK NUMBER: N1230300302 JPM NUMBER: 15-01 NRC SRO Admin A1-1 ALTERNATE PATH: D KIA NUMBER:
------------<2.1.25 IMPORTANCE FACTOR: 4.2 APPLICABILITY: RO SRO EOCJ ROCJ STAC] SR0[8J EVALUATION SETTING/METHOD: Classroom
REFERENCES:
S2.0P-ST.CBV-0003, Rev. 19 (checked 8-10-16) TOOLS AND EQUIPMENT: VALIDATED JPM COMPLETION TIME: 12 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-10-16 Instructor Validated By: R Boyer I P Williams Date: 9-28-16110-4-16 SME or Instructor~ Approved By: T rammg pa rtHv.t men Approved By: Op~artment Date: . It>P/Jt, ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 1 of 5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training *
. \
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: SYSTEM: Administrative TASK: Review a completed surveillance to demonstrate Operability of 21 CFCU TASK NUMBER: N1230300302 INITIAL CONDITIONS: 21 CFCU was returned from corrective maintenance. S2.0P-ST.CBV-0003, Containment Systems - Containment Cooling was performed for the Operability Retest. INITIATING CUE: You have been directed to review the surveillance for completeness and accuracy IAW Step 5.3.4. If any discrepancies are identified, note them and any actions that you would take on Attachment 8, Section 1.0, Comments. Successful Completion Criteria:
- 1. All critical steps completed
- 2. All sequential steps completed in order
- 3. All time-critical steps completed within allotted time
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion:
- 1. Identify that the Minimum Flow Rate recorded on Attachment 1, Section 3.0, for 87 psid is incorrectly recorded as 1592. Identify the correct Minimum Flow Rate should be 1638.
- 2. Identify that the actual Cooling Water Flow Rate (1625) is below the Minimum Flow Rate required as shown on Attachment 1 and Exhibit 1, and the surveillance is UNSAT vs SAT.
Page 2 of 5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME:, _ _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE:*--~---~-~-- System: ADMINISTRATIVE Task: Review a completed surveillance to demonstrate Operability of 21 CFCU
- STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)
Provide completed S2.0P-ST.CBV-0003 surveillance. Reviews procedure. Identifies that the Minimum Flow Rate recorded on Attachment 1, 21 CFCU Data Sheet,
- Section 3.0, for 87 psid is incorrectly recorded as 1592. {This was due to operator performing ST rounding down as opposed to rounding up IAW P&L 3.4.)
Identifies correct value for Minimum Flow Required as 1638. Cue: IF candidate only determines flow is wrong, THEN ask candidate to determine correct flow.
- Identifies that the actual Cooling Water Flow Rate of 1625 gpm is below the Minimum Flow Rate of 1638 as shown on Exhibit 1 and the ST is UNSAT.
When candidate turns in JPM, ensure they have provided correct flow as per Cue above, then state JPM is complete. Page 3 of 5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 4 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. V /~Task description and number, JPM description and number are identified. \J / £? 2. Knowledge and Abilities (KIA) references are included.
\J ~Performance location specified. (in-plant, control room, or simulator)
IJ
. Initiating and terminating Cues are properly identified. "'"-..Al<-J'-<f)-=~'- 6. Task standards identified and verified by SME review. / ff2 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). ~Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. I l} Date siv:/1 L L~t test the JPM: ~
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: Date: - - - - - - Page 4 of5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
INITIAL CONDITIONS: 21 CFCU was returned from corrective maintenance. S2.0P-ST.CBV-0003, Containment Systems - Containment Cooling was performed for the Operability Retest. INITIATING CUE: You have been directed to review the surveillance for completeness and accuracy IAW Step 5.3.4. If any discrepancies are identified, note them and any actions that you would take on , Section 1.0, Comments. Page5of5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
PSEG Internal Use Only Page _1_ of _1_ PSEG NUCLEAR L.L.C. SALEM/OPERATIONS S2.0P-ST.CBV-0003(Q) REV. 19 CONTAINMENT SYSTEMS - COOLING SYSTEMS USE CATEGORY: I LICENSE RENEWAL RELATED
+ Biennial Review Performed: Yes No NA _L_ + Packages and Affected Document Numbers incorporated into this revision: None + The following OTSCs were incorporated into this revision: None + The following OPEXs were incorporated into this revision: None REVISION
SUMMARY
+ Updated procedure to current Writer's Guide standards. (Rev bars not used) + Page 5, Added additional place keeping lines to support place keeping and Human Performance when using procedure to run multiple CFCU's. [70172703-0020] + Page 4, Updated Section 4.0 to reflect use of M& TE (Heise gauges and Handheld computer) in place of D/P gauge. [70147227-0020] [70094761-0010] [70133586-0010] + Attachments 1-5, Updated Section 2.0 to reflect use of M&TE (Heise gauges and Handheld computer) in place of D/P gauge. [70147227-0020] [70094761-0010] [70133586-0010] + Attachments 6 & 7, Updated Sections 1.0 & 2.0 to reflect use of M& TE (Heise gauges and Handheld computer) in place of D/P gauge. [70147227-0020] [70094761-0010] [70133586-001 O] IMPLEMENTATION REQUIREMENTS Effective Date: June 12, 2015 None
s2.oP-ST.CBV-0003(Q) CONTAINMENT SYSTEMS - COOLING SYSTEMS TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE ........................................................ 2 2.0 PREREQUISITES ................................................... 3 3.0 PRECAUTIONS AND LIMITATIONS .................................... 4 4.0 EQUIPMENT/MATERIAL REQUIRED ................................... 4 5.0 PROCEDURE ...................................................... 5 5.1 CFCU Operability and Service Water Flow Verification ............... 5 5.2 Acceptance Criteria ........................................... 6 5.3 Completion and Review ........................................ 6 6.0 RECORDS ........................................................ 7
7.0 REFERENCES
.................................................... 7 ATTACHMENTS 21 CFCU Data Sheet .......................................... 9 22 CFCU Data Sheet ......................................... 10 23 CFCU Data Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 24 CFCU Data Sheet ......................................... 12 25 CFCU Data Sheet ......................................... 13 21 SW HOR Differential Pressure (~P) Indicator Alignment ........... 14 22 SW HOR Differential Pressure (~P) Indicator Alignment ........... 16 Completion Sign-off Sheet .................................... 18 EXHIBITS Exhibit 1 Minimum CFCU Flow Rates .................................... 19 Salem 2 Page 1of19 Rev. 19
s2 .OP-ST.CBV-0003(Q) 1.0 PURPOSE [C0265] 1.1 Performance of procedure is used to satisfy the following Technical Specifications:
+ 4.6.2.3.b.1, demonstrating operability of each Containment Cooling Fan by starting (unless already operating) each fan from the Control Room in LOW SPEED.
+ 4.6.2.3.b.2, demonstrating operability of each Containment Cooling Fan by verifying that each fan operates for at least 15 minutes in LOW SPEED.
+ 4.6.2.3.b.3, demonstrating operability of each Containment Fan Coil Unit by verifying a cooling water flow rate ~ 1465 gpm. The 1465 gpm value represents 1300 gpm as required by TIS 4.6.2.3.b.3 plus 165 gpm for Instrument Uncertainty.
1.2 Performance of procedure is used to partially satisfy TIS 4.7.4.a, by verifying that flow through valves 21-25SW58, 21-25SW72 and 21-25SW223 servicing 21-25 Containment Fan Coil Units is~ that required for operability consideration thus ensuring correct alignment. 1.3 Performance of procedure is required at least once per 31 days in Modes 1-3, prior to entry into Mode 3 if NOT previously performed in the last 31 days, OR as otherwise specified in post-maintenance operational retest requirements. 1.4 Procedure partially satisfies an NRC commitment for License Renewal Open-Cycle Cooling Water Aging Management Program (AMP) activities. [CM-SC-2009-630] Salem 2 Page 2of19 Rev.19
s2.oP-ST.CBV-0003(Q) 2.0 PREREQUISITES
~ 2.1 REVIEW Components "Off Normal and Off Normal Tagged" List(s) for system AND support system(s) associated with evolution being performed in procedure.
fe 2.2 RECORD applicable SAP Order number(s) AND Reason for Test in applicable Attachment(s), Section 1.0, for CFCU(s) being tested. A 2.3 RECORD Calibration data for instruments listed in applicable Attachment(s), Section 2.0, for CFCU(s) being tested. [C0289]
~ 2.4 ~~2 OR 23 CFCU being tested,
~INITIATE Attachment 6, Section 1.0, Aligning 21 SW HOR Differential Pressure (LlP) Indicator For Service.
t-i/,..jj, 2.5 ~3, 24 OR 25 CFCU being tested, THEN INITIATE Attachment 7, Section 1.0, Aligning 22 SW HOR Differential Pressure (LlP) Indicator For Service. Salem 2 Page 3of19 Rev. 19
s2 .OP-ST.CBV-0003(Q) 3.0 PRECAUTIONS AND LIMITATIONS
.il_ 3.1 Steps identified with a dollar sign($) are items required to meet Technical Specifications acceptance criteria. Identified steps, if NOT satisfactorily completed, may have reportability requirements AND are to be brought to immediate attention of CRS/SM.
A_ 3.2 Testing will be performed during relatively stable SW Header Pressure conditions. A:_ 3.3 Containment Fan Coil Unit OPERABILITY is satisfied when Cooling Water Flow Rate is:::: 1465 gpm {T/S 3.6.2.3) AND is:::: Minimum Flow Rate specified in Exhibit 1 (S-C-SW-MDC-0475, Table A, Minimum CFCU Flow Rates).
+ Flow rates specified in Exhibit 1 are valid when using service water pressure taps SW822 and SW823. The use of alternate pressure tap locations shall be approved by Engineering.
A- 3.4 After recording Differential Pressure (L1P) reading, select corresponding minimum flow value specified in Exhibit 1.
+ lE measured L1P value is between L1P values specified in Exhibit 1, THEN select minimum flow value for next higher L1P value listed (e.g., if measured L1P is 101 psid, use minimum flow required at 105 psid).
,d:_ 3.5 WHEN testing 23 CFCU with both Service Water Headers aligned, THEN two Differential Pressure (L1P) measurements (21 SW HOR AND 22 SW HOR) are required. The higher of the two measurements shall be used to determine 23 CFCU OPERABILITY. k-* Only one Differential Pressure (L1P) measurement (21 SW HOR OR 22 SW HOR) is required during a Service Water Header outage. Acceptable test results can be obtained with one service water header isolated. T-A; 3.6 lE substitution of Measuring and Test Equipment (M&TE) is required, THEN Engineering has specified range, accuracy and documented substitution in the Comments Section of Attachment 8. 4.0 EQUIPMENT/MATERIAL REQUIRED NOTE
.&. one When testing 23 CFCU, Attachments 6 & 7 may be performed sequentially when only indicator is available (Refer to Step 3.5). ):)_ 4.1 Two 0-200 psi HQS-2 Sensor Modules (Four if performing 23 CFCU)
(Accuracy: .+/-. 2% of Full Scale or better) A- 4.2 One Hand Held Heise Pressure Calibrator Gauge, Model PTE-1 Handheld Computer (Two if performing 23 CFCU) Salem 2 Page 4of19 Rev. 19
s2.oP-ST.CBV-0003(Q) 5.0 PROCEDURE 5.1 CFCU Operability and Service Water Flow Verification
~ 5.1.1 PERFORM test on each Containment Fan Coil Unit required to be tested IAW the following instruction:
ENSURE CFCU being tested is in LOW SPEED IAW S2.0P-SO.CBV-0001(Q), Containment Ventilation Operation. _& ~ B. RECORD Start Time in applicable Attachment(s), Section 3.0, for CFCU being tested. WHEN at least 15 minutes has elapsed, THEN RECORD the following in applicable Attachment, Section 3.0, for CFCU being tested: Stop Time Ni..P + Cooling Water Flow Rate (gpm) 1Jit..P + ~sting 21 OR 22 CFCU, WEN RECORD 21 SW HOR L1P.
~~
ftN/Aft + ~sting 23 CFCU,
- WEN RECORD both 21 SW HOR L1P AND 22 SW HOR b.P (Refer to Step 3.5).
tJ/1..µ ~J kJ:J + ~sting 24 OR 25 CFCU,
~. . :. . :. . :.=.:. .;.EN RECORD 22 SW HOR L1P.
A_ ~/*-.J- + RECORD Test Results by initialing the SAT OR UNSAT column
$ T IAW Acceptance Criteria stated in the attachment.
~I"- ~ 0. ~Mode 1-4
~Service Water flow is <1465 gpm, THEN REFER to S2.0P-SO.SW-0005(Q), Service Water System Operation, Service Water System Operability Guidelines. [70090043]
A- ~I A.,_,d- E. ALIGN CFCU as required to support current plant conditions IAW S2.0P-SO.CBV-0001(Q), Containment Ventilation Operation. Salem 2 Page 5of19 Rev. 19
s2.oP-ST.CBV-0003(Q) 5.2 Acceptance Criteria
~*5.2.1 Surveillance is satisfactory when Attachments 1-5, as applicable,
$ are completed with CFCU listed meeting Acceptance Criteria stated in Attachment.
OR jJ;J/A 5.2.2 Surveillance is unsatisfactory: A. INITIATE NOTF to correct unsatisfactory conditions. B. RECORD NOTF number AND reason for unsatisfactory completion on Attachment 8, Section 1.0. 5.3 Completion and Review A. 5.3.1 lE 21 SW HDR Differential Pressure (LlP) Indicator was installed to support testing, THEN COMPLETE Attachment 6, Section 2.0, Removing 21 SW HDR Differential Pressure (LlP) Indicator From Service. Nf,._,;J- 5.3.2 ~2 SW HDR Differential Pressure (LlP) Indicator was installed to support testing, THEN COMPLETE Attachment 7, Section 2.0, Removing 22 SW HDR Differential Pressure (LlP) Indicator From Service. fe 5.3.3 COMPLETE Attachment 8, Sections 1.0 and 2.0, AND FORWARD procedure to CRS/SM for review. 5.3.4 CRS/SM PERFORM the following: A. REVIEW procedure with Attachments 1-8 for completeness AND accuracy. B. COMPLETE Attachment 8, Section 3.0. C. FORWARD completed procedure to Operations Staff. END OF PROCEDURE SECTION Salem 2 Page 6 of 19 Rev. 19
s2.oP-ST.CBV-0003(Q) 6.0 RECORDS 6.1 Retain the following IAW RM-AA-101, Records Management Program:
- Attachments 1-7 (as applicable)
- Attachment 8 6.2 LICENSE RENEWAL -Using designated separator page, separate License Renewal documents from non-License Renewal documents.
7.0 REFERENCES
7.1 Updated Final Safety Analysis Report: 7.1.1 6.2.2.2, Containment Fan Cooling System 7.1.2 9.4.4, Containment Ventilation Systems 7.2 Technical Specifications - Unit 2: 7.2.1 3.6.2.3, Containment Cooling System 7.2.2 3.7.4, Service Water System
7.3 Drawings
7.3.1 205338, Reactor Containment Ventilation 7.3.2 205342, Service Water Nuclear Area
7.4 PSBPs
7.4.1 139970, Technical Manual for Operation and Maintenance of Containment Building Fan - Coil Unit Safeguard Ventilation System
7.5 Others
7.5.1 DCP 2EC-3294, Package 1 7.5.2 DCP 2EC-3590, 96-06 MOD - CFCU Service Water Valve SW65 Position Setting 7.5.3 Setpoint Calculation SC-SW002-01, CFCU Service Water Flow Indication, Rev. 1 7.5.4 PR 961212131, Service Water Flow Requirements to CFCUs 7.5.5 PR 960823139, Testing May Not Be Done IAW Technical Specifications 7.5.6 Unit 2 Technical Specifications Amendment 180 7.5.7 S-C-SW-MEE-1449, Service Water Flow Requirements for CFCUs 7.5.8 70028270, Operability Determination for 22 CFCU 7.5.9 DCP 80089131, Unit 2 CFCU Fixed Flow Modification. 7.5.10 Engineering Calculation S-C-SW-MDC-0475, CFCU Fixed Resistance Flow. Salem 2 Page 7of19 Rev.19
s2.oP-ST.CBV-0003(Q) 7.6 Cross-
References:
7.6.1 Technical Specifications - Unit 2: A. 4.6.2.3.b.1, Containment Systems Surveillance Requirements B. 4.6.2.3.b.2, Containment Systems Surveillance Requirements C. 4.6.2.3.b.3, Containment Systems Surveillance Requirements D. 4.6.2.3.c.2, Containment Systems Surveillance Requirements E. 4.7.4.a, Plant Service Water System Surveillance Requirements
7.6.2 Procedures
A. S2.0P-SO.CBV-0001 (Q), Containment Ventilation Operation
7.7 Commitments
7.7.1 C0265- NSO LER 311/89-015-00 7.7.2 C0283 - NRG VIOL 311/87-18-01 7.7.3 C0289 - INSTRUMENT CALIBRATION REQUIREMENTS 7.7.4 CM-SC-2009-630, Salem UFSAR, Appendix B, Section A.2.1.11, Open-Cycle Cooling Water Program 7.8 License Renewal Documents, (DCRMS Records Management Type - 3E.200) 7.8.1 Records Management SH-PBD-AMP-Xl.M20, Open-Cycle Cooling Water Program Basis Document Salem 2 Page 8of19 Rev. 19
s2.oP-ST.CBV-0003(Q) ATTACHMENT 1 21 CFCU DATA SHEET 1.0 Reason For Test Post-Maintenance Operability Retest? I Yes,4- I No Date: \6J c<::j SAP Order Number(s): 0:.o l 0 d-7 t.fo 2.0 Calibration Data Calibration Instrument/Test Equipment Description ID Number Initials Due Date 2FA5490, 21 CFCU Outlet Water Flow Indicator & monlhr .fro<<lf'l)* ~FA549o g Model HQS-2 Sensor Module 0- )..oti psi ~ (j>q~hr tf. nr' ".J r,,,~-' A Model HQS-2 Sensor Module 0-~" psi ~ r(};ttlh f1~,.,., "*>\ (:,.,'"J'- L 4 Model PTE-1 Hand Held Heise Pressure Calibrator Gauge &()1~ ilH'J h,"' n..,~ G,e~&'-? A 3.0 21 CFCU Performance Data Test Results Component Test Data Acceptance Criteria SAT UNSAT Start Time ;).ooo 21 CFCU Stop Time ,;lO!f.o 21SW58 Cooling Water 21 CFCU operated for at least 15 minutes in LOW SPEED at?>. 1465 gpm. fl-ll,J.S Flow Rate 21SW72 21SW223 21 SW HDRb.P Bl Cooling Water Flow Rate (78' IPA - 21 SW Piping Room) Minimum Flow Rate is ?>. the Minimum Flow Rate obtained in Exhibit 1 A-159d-- for b.P specified. (Exhibit 1) Salem 2 Page 9of19 Rev.19
s2 .OP-ST.CBV-0003(0) ATTACHMENT 6 (Page 1 of 2) 21 SW HOR DIFFERENTIAL PRESSURE (ilP) INDICATOR ALIGNMENT 1.0 Aligning 21 SW HOR Differential Pressure (ilP) Indicator For Service: Installed Instrument ID Description Installation Points Initials Date Range: 0-300 psid
~~' Low Side: 21SW823 A '°10d~
Accuracy: +/-2% of ('JC...,V& 2- Full Scale or better High Side: 21SW822 fi Tod~
~
ENSURE Calibration Data is recorded in the applicable Attachment(s), Section 2.0, for the CFCU(s) being tested.
~ 1.1 ENSURE CLOSED installation points:
4- 1.1.1 21 SW823, 2 SW 21, 22 & 23 CFCU RTN D/P TEST CONN. Jj 1.1.2 21 SW822, 2 SW 21, 22 & 23 CFCU SUP D/P TEST CONN . .A_1.2 INSTALL instrumentation to installation points (78' IPA - 21 SW Piping Room) .
.d__ 1.3 Slowly OPEN 21SW823, 2 SW 21, 22 & 23 CFCU RTN D/P TEST CONN.
_,4-* 1.4 Slowly OPEN 21 SW822, 2 SW 21, 22 & 23 CFCU SUP D/P TEST CONN. Salem 2 Page 14of19 Rev. 19
s2.oP-ST.CBV-0003(Q) ATTACHMENT 6 (Page 2 of 2) 21 SW HOR DIFFERENTIAL PRESSURE (aP) INDICATOR ALIGNMENT 2.0 Removing 21 SW HOR Differential Pressure (aP) Indicator From Service: A_ 2.1 CLOSE 21SW822, 2 SW 21, 22 & 23 CFCU SUP D/P TEST CONN. A 2.2 CLOSE 21SW823, 2 SW 21, 22 & 23 CFCU RTN D/P TEST CONN. jJ_ 2.3 REMOVE instrumentation from installation points. _ti_ 2.4 DIRECT second Operator to PERFORM Independent Verification of the following: Component Description Normal Position IV Date 2 SW 21, 22 & 23 CFCU SUP D/P TEST 21SW822 CONN CLOSED o2- 1oJv-<-< 21SW823 2 SW 21, 22 & 23 CFCU RTN D/P TEST CLOSED CONN r::::;;;r 1;)do-; Salem 2 Page 15of19 Rev. 19
s2.oP-ST.CBV-0003(Q) ATTACHMENT 7 (Page 1 of 2) 22 SW HOR DIFFERENTIAL PRESSURE (.6.P) INDICATOR ALIGNMENT 1.0 Aligning 22 SW HOR Differential Pressure (.6.P) Indicator For Service: Installed Instrument ID Description Installation Points Initials Date Range: 0-300 psid Low Side: 22SW823 Accuracy: +/-2% of High Side: 22SW822 Full Scale or better ENSURE Calibration Data is recorded in the applicable Attachment(s), Section 2.0, for the CFCU(s) being tested. 1.1 ENSURE CLOSED installation points: 1.1.1 22SW823, 2 SW 23, 24 & 25 CFCU RTN D/P TEST CONN. 1.1.2 22SW822, 2 SW 23, 24 & 25 CFCU SUP D/P TEST CONN. 1.2 INSTALL instrumentation to installation points (178' IPA- 22 SW Piping Room). 1.3 Slowly OPEN 22SW823, 2 SW 23, 24 & 25 CFCU RTN D/P TEST CONN. 1.4 Slowly OPEN 22SW822, 2 SW 23, 24 & 25 CFCU SUP D/P TEST CONN. Salem 2 Page 16of19 Rev.19
s2.oP-ST.CBV-0003(Q) ATTACHMENT 7 (Page 2 of 2) 22 SW HOR DIFFERENTIAL PRESSURE (.L).P) INDICATOR ALIGNMENT 2.0 Removing 22 SW HOR Differential Pressure (b.P) Indicator From Service: 2.1 CLOSE 22SW822, 2 SW 23, 24 & 25 CFCU SUP D/P TEST CONN. 2.2 CLOSE 22SW823, 2 SW 23, 24 & 25 CFCU RTN D/P TEST CONN. 2.3 REMOVE instrumentation from installation points. 2.4 DIRECT second Operator to PERFORM Independent Verification of the following: Component Description Normal Position IV Date 2 SW 23, 24 & 25 CFCU SUP D/P TEST 22SW822 CLOSED CONN 2 SW 23, 24 & 25 CFCU RTN D/P TEST 22SW823 CLOSED CONN Salem 2 Page 17 of 19 Rev. 19
s2.oP-ST.CBV-0003(Q) ATTACHMENT 8 COMPLETION SIGN-OFF SHEET
1.0 COMMENTS
(Include test deficiencies and corrective actions.)
2.0 SIGNATURES
Print Initials Signature Date b C.,, c,._....._.J '~
)
/:1-- M~ T~d::J
*--1) .Jr, 11s-.1-- ~ -/J,~.J- ""'fi- .t C"~
)
3.0 CRS/SM FINAL REVIEW AND APPROVAL: [C0283] This procedure with Attachments 1-8 is reviewed for completeness and accuracy. All deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment. Technical Specification compliance, procedure compliance, and Acceptance Criteria are evaluated. Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __ SM/CRS Salem 2 Page 18 of 19 Rev. 19
s2 .OP-ST.CBV-0003(Q) EXHIBIT 1 MINIMUM CFCU FLOW RATE MINIMUM FLOW RATES (GPM)
.L1P(1) 21 CFCU 22 CFCU 23 CFCU 24 CFCU 25 CFCU 60 1338 1338 1338 1339 1339 65 1392 1392 1393 1394 1394 70 1445 1445 1446 1447 1447 75 1495 1495 1496 1497 1497 80 1545 1545 1545 1546 1546 85 1592 1592 1593 1594 1594 90 1638 1638 1639 1640 1640 95 1683 1683 1684 1685 1685 100 1727 1727 1728 1729 1729 105 1769 1769 1771 1772 1772 110 1811 1811 1812 1813 1813 115 1852 1852 1853 1854 1854 120 1892 1892 1893 1894 1894 125 1931 1931 1932 1933 1933 130 1969 1969 1970 1971 1971 135 2006 2006 2008 2009 2009 140 2043 2043 2044 2046 2046 145 2079 2079 2081 2082 2082 150 2115 2115 2116 2118 2118 155 2150 2150 2151 2153 2153 160 2184 2184 2186 2187 2187
Reference:
Engineering Calculation S-C-SW-MDC-0475, Table A, Minimum CFCU Flow Rates. (1) When the measured .6.P reading is between the specified .6.P values, use the higher .6.P value (e.g., if measured .6.P is 101 psid, use the minimum flow required at 105 psid). Salem 2 Page 19of19 Rev. 19
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress) TASK NUMBER: N1120760102 JPM NUMBER: 15-01 NRC SRO A1-2 ALTERNATE PATH: D KIA NUMBER: 2.1.42
~-----------1 IMPORTANCE FACTOR: 3.4 APPLICABILITY: RO SRO EoLJ ROCJ STAL] SROITJ EVALUATION SETTING/METHOD: Classroom or Simulator
REFERENCES:
S2.0P-10.ZZ-0010, Rev. 33, S2.0P-SO.CH-0001 Rev 32, S2.0P-SO.SW-0005 Rev 42 S2.0P-SO.DG-0005, Rev. 6 (all rev checked 8-10-16) Salem Tech Specs TOOLS AND EQUIPMENT: VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-10-16 Instructor Validated By: Date: 9-28-16 / 10-4-16 Approved By: Date: 100~ Approved By: Date: 10/1/11., ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 1 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
~~~~~~~~~~~~~~-
DATE: SYSTEM: Administrative TASK: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress) - TASK NUMBER: N1120760102 INITIAL Salem Unit 2 is operating at 99% power, coasting down into a refueling outage CONDITIONS: which will start in 2 weeks. Irradiated fuel movement is in progress in the Spent Fuel Pool IAW S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations, and will continue without interruption for the next 8 hours, at which time it will terminate. The unit has no active Tech Spec LCOs. 21 SW pump is CIT for emergent strainer work. The current time is 0800. INITIATING CUE: You have been directed to review the upcoming work for the shift and determine which activities may proceed as scheduled while continuing the fuel movement in the Spent Fuel Pool uninterrupted. Work scheduled for today Circle whether each activity may or may not be performed 0900- 22 SW pump packing replacement MAY MAY NOT 1000- 2A EOG Monthly surveillance run MAY MAY NOT 1300- 21 Chiller compressor oil change MAY MAY NOT 1400- Delivery of New Fuel into the Fuel MAY MAY NOT Handling Building for upcoming refueling outage. Successful Completion Criteria:
- 1. All critical steps completed
- 2. All sequential steps completed in order
- 3. All time-critical steps completed within allotted time
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion:
- 1. Determines that 22 SW pp work, 2A EOG surveillance, and 21 Chiller work MAY be performed.
- 2. Determines that New Fuel delivery may NOT be performed.
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE: System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress)
- STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)
Provide blank copies of: S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations. S2.0P-SO.DG-0005, Preparation for Removing a Diesel Generator from Service. S2.0P-SO.SW-0005, Service Water System Operation. Provide copies of Tech Specs. Page 3 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME:.~~~~~~~~~~~ JOB PERFORMANCE MEASURE DATE:.~~~~~~~~~~~ System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress)
- STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)
Notes: TSAS 3.8.1.2 applies during Modes 5 and 6 and during movement of irradiated fuel, and only requires two EDGs. Only one FHB exhaust fan is required to be backed by an operable EOG (IOP-10 P&L 3. 7 and page 17) Operable SFP pumps only need one of them backed by operable EOG. {IOP-1 O P&L 3.4 and page 17) TSAS 3. 7.10 allows a chiller to be taken out of service if movement of irradiated fuel is already on-going, and gives 14 days to restore it. Two SW pumps are required to be operable, one of which is EOG backed. (IOP-10 page 18.) The four remaining SW. pumps are powered from B and C ' vital and their EDGs remain operable. TSAS 3.7.4 will be entered for less than two operable SW loops, but is a 72 hour action. Page 4 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~ System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress)
- STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)
Notes: (cont) FHB Truck Bay Door is required to be closed. (IOP-10 paqe 19) Determines that:
- 22 SW pump work MAY be performed.
- 2A EOG surveillance MAY be performed.
- 21 Chiller oil replacement MAY be performed.
New Fuel delivery may NOT be performed. Evaluator ensure tear off sheet has candidates name and status for each of the four work activities, then terminate JPM.
, Page 5 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
Name: OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 4 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below .
./d' '21. Task description and number, JPM description and number are identified. ~Knowledge and Abilities (KIA) references are included .
.L. tf/ ~Performance location specified. (in-plant, control room, or simulator)
/ .d<f:t-4. Initial setup conditions are identified . / ~ 5. Initiating and terminating Cues are properly identified . ./ & ~- Task standards identified and verified by SME review.
I aa Critical steps meet the criteria for critical steps and are identified with an asterisk (*). {fj:2~rify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.~ Date 1/uli(;
~t test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: Date: - - - - - - Page 6 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
INITIAL CONDITIONS: Salem Unit 2 is operating at 99% power, coasting down into a refueling outage which will start in 2 weeks. Irradiated fuel movement is in progress in the Spent Fuel Pool IAW S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations, and will continue without interruption for the next 8 hours, at which time it will terminate. The unit has no active Tech Spec LCOs. 21 SW pump is CIT for emergent strainer work. The current time is 0800. INITIATING CUE: You have been directed to review the upcoming work for the shift and determine which activities may proceed as scheduled while continuing the fuel movement in the Spent Fuel Pool uninterrupted. Work scheduled for today Circle whether each activity may or may not be performed 0900- 22 SW pump packing replacement MAY MAY NOT 1000- 2A EOG Monthly surveillance run MAY MAY NOT 1300- 21 Chiller compressor oil change MAY MAY NOT 1400- Delivery of New Fuel into the Fuel MAY MAY NOT Handling Building for upcoming refueling outage. Page 7 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review a completed surveillance to calculate Shutdown Margin TASK NUMBER: 1200030301 JPM NUMBER: 15-01 NRC SRO A2 ALTERNATE PATH: !.____.I KIA NUMBER:
- - - - -2.2.12 IMPORTANCE FACTOR: 4.1 APPLICABILITY: RO SRO EoD ROD STAD SROCK]
EVALUATION SETTING/METHOD: Classroom
REFERENCES:
SC.RE-ST.ZZ-0002, Rev. 23 Shutdown Margin Calculation S2.RE-RA.ZZ-0016, Rev. 8 Figures Salem Unit 2 Technical Specifications TSAS 3.1.3.1 Movable Control Assemblies TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 20 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 30 minutes Developed By: G Gauding Date: 8-10-16 Instructor Validated: R Boyer I P Williams Date: 9-28-16 / 10-4-16 Approved By: s~:"ft_ Date: 10/y{c. Tra/1'.l:V'1~nment Approved By: Date: 1ojt:)& Operations Repr entative ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 6
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~- DATE: ~~~~~~~~~~~~~~- SYSTEM: Administrative TASK: Review a completed surveillance to calculate Shutdown Margin TASK 1200030301 NUMBER: INITIAL CONDITIONS:
- Unit 2 Reactor Power is 100%.
- All Control Rod Group Demand Counters are at 227 steps.
- Current boron concentration is 300 ppm.
- Current core burnup is 10,000 EFPH.
- Control Rod 105 was declared INOPERABLE at 1000 today due to not moving out during a rod exercise test. A Shutdown Margin Calculation has been performed IAW SC.RE-ST.ZZ-0002, Shutdown Margin Calculation, to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.
- Control Rod 105 has been identified as trippable and is currently at 214 steps.
INITIATING CUE:
- 1. Review the attached SOM calculation procedure SC.RE-ST.ZZ-0002 for completeness and accuracy.
- 2. Note any discrepancies found by the review on Attachment 7.
- 3. Determine if SOM is SAT.
The current time is 1030. This is a time critical JPM. Time will start when procedures are given to you. Time will stop when procedures are returned to proctor. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made Task Standard for Successful Completion:
- 1. Determines SOM is complete, accurate, and SAT.
- 2. Completes review within 30 minutes.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 6
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE: _ _ _ _ _ _ _ _ _ __ System: ADMINISTRATIVE Task: Review a completed surveillance to calculate Shutdown Margin STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
- NO. S/U Evaluation)
Note to Evaluator: The time critical aspect refers to the time required when the Shutdown Margin requirement of TSAS 3.1.3.1.c must be met. 1 Provide the marked up copy of SC.RE- Ensures Sections 3 and 4 are completed. ST.ZZ-0002 and copy of S2.RE-RA.ZZ-0016, Curve Book. Time Start: 2 Review Section 5 to ensure the correct Reviews Section 5 and determines the correct Attachment was performed. Attachment (3) was performed.
- 3 Review the completed Shutdown Reviews SOM and determines it is complete Margin Calculation: and accurate.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 6
OPERATOR TRAINING PROGRAM NAME: ~~~-~------ JOB PERFORMANCE MEASURE DATE: System: ADMINISTRATIVE Task: Review a completed surveillance to calculate Shutdown Margin STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
- NO. S/U Evaluation)
- 4 Acceptance Criteria Determines Acceptance Criteria are met.
Turns in procedures within 30 minutes of start
- Time Stop: time.
Total time to complete JPM MUST be 30 minutes or less. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 6
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. v /I T-1. Task description and number, JPM description and number are identified. v / itJ 2. Knowledge and Abilities (KIA) references are included.
'""- / fie <+/-)3. Performance location specified. (in-plant, control room, or simulator) v I ;1J:>I
- 4. Initial setup conditions are identified.
\/" I J <&.._ 5. Initiating and terminating Cues are properly identified. \!'- / /ii 9-G. Task standards identified and verified by SME review.
\}'-
~Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
~Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.~ Date 10/'1/1-b
;f ----'-""'"-----
#( U
_.:..______;:::;_ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. Date: rh~,£- Date: =/(=.~=:W=* SME/lnstructor: Date: - - - - - - PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 6
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- Unit 2 Reactor Power is 100%.
- All Control Rod Group Demand Counters are at 227 steps.
- Current boron concentration is 300 ppm.
- Current core burnup is 10,000 EFPH.
- Control Rod 105 was declared INOPERABLE at 1000 today due to not moving out during a rod exercise test. A Shutdown Margin Calculation has been performed IAW SC.RE-ST.ZZ-0002, Shutdown Margin Calculation, to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.
- Control Rod 105 has been identified as trippable and is currently at 214 steps.
INITIATING CUE:
- 1. Review the attached SOM calculation procedure SC.RE-ST.ZZ-0002 for completeness and accuracy.
- 2. Note any discrepancies found by the review on Attachment 7.
- 3. Determine if SOM is SAT.
The current time is 1030. This is a time critical JPM. Time will start when procedures are given to you. Time will stop when procedures are returned to proctor. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 6
PSEG Internal Use Only Page 1of1 PSEG NUCLEAR L.L.C. SALEM GENERATING STATION/REACTOR ENGINEERING SC.RE-ST.ZZ-0002(0) - REV. 23 SHUTDOWN MARGIN CALCULATION USE CATEGORY: I
- Biennial Review Performed: Yes No
- - - N/A _X_
- Packages and Affected Document Numbers incorporated into this revision: None
- The following OTSCs were incorporated into this revision: None REVISION
SUMMARY
IAW Order 70163361. Revised step 5.2.1 from "WHEN" to "IF" for proper phrasing of a conditional statement. Added References 7.1.10 and 7.1.11 for OS2.5-0256 and WCAP-14762. Revised Attachment 1, step 2.2 to change "operable" control rods to "trippable" control rods. Added step 4.5.7 to calculate the required increase in boron concentration if a plant shutdown occurs with an inoperable !RPI. Revised Attachment 2 to add step 4.13.2 for guidance to determine the amount of boration required to achieve SOM in the event of an UNSAT SOM. Changed references to "BEACON" from "Reactor Engineer" for Xenon calculation in steps 4.6.2 and 4.6.5. Added step 4.11 and 4.12.7 to calculate a pcm penalty for an inoperable !RPI. Added step 4.13.2 to calculate required boron addition if SOM is UNSAT. Revised Attachment 3 to differentiate between untrippable and dropped/misaligned control rods. Removed fuel burnup from precaution 3.3 as the calculation does take burnup into account. Added precaution 3.5 to highlight the difference between inoperable, untrippable, dropped and misaligned control rods. Added a note to clarify the untrippable RCCA penalties in Table 1-6 include the most reactive stuck rod worth. Added a 120 pcm penalty for rod misalignment relaxation based on WCAP-14762. Added step 4.4.2 to determine the power level at which SOM would be achieved in the event of an UNSAT SOM. Revised Attachment 6 by moving step 4.1 to 4.2.5 to put steps in the proper order to ensure correct procedure use and adherence.
sC .RE-ST.ZZ-0002(0) SHUTDOWN MARGIN CALCULATION TABLE OF CONTENTS Section 1.0 PURPOSE .................................................................................................. 2 2.0 PREREQUISITES ....................................................................................... 3 3.0 PRECAUTIONS AND LIMITATIONS .......................................................... 3 4.0 EQUIPMENT/MATERIAL REQUIRED ........................................................ 3 5.0 PROCEDURE ............................................................................................. 4 5.1 Shutdown Margin Calculation ......................................................... .4 5.2 Acceptance Criteria ......................................................................... 5 5.3 Completion and Review ................................................................... 5 6.0 RECORDS .................................................................................................. 6
7.0 REFERENCES
............................................................................................ 6 ATTACHMENTS Shutdown Margin Verification With No Xenon Credit .................................. 8 Detailed Shutdown Margin Calculation Work Sheet .................................. 12 Shutdown Margin Verification for Modes 1 or 2 ......................................... 20 Rod Insertion Limit Shutdown Margin Calculation Prior to Mode 1 ............ 23 Refueling Boron Concentration for Mode 6 ............................................... 25 Shutdown Margin Verification for Boration Concurrent with Cooldown ...... 27 Completion/Sign-Off Sheet ....................................................................... 30 Salem Common Page 1of30 Rev.23
sC.RE-ST.ZZ-0002(0) 1.0 PURPOSE 1.1 The purpose of this procedure is to provide instructions necessary to perform the following: 1.1.1 To determine the boron concentration required for a desired temperature and rod configuration so that Shutdown Margin (SOM) can be maintained while going to that condition. 1.1.2 To verify that the SOM requirements are met when the Reactor Coolant System (RCS) is borated concurrently with cooldown. 1.1.3 To determine the amount of reactivity by which the reactor is subcritical (kett) and the amount of SOM available while at a specific reactor temperature and rod position. 1.1.4 To verify that the SOM requirements are met in Modes 1 or 2. 1.1.5 To verify that the SOM requirements are met at rod insertion limits prior to entering Mode 1 after a refueling outage. 1.1.6 To determine the RCS and Refueling Canal boron concentration which will ensure adequate SOM is maintained during refueling operations. 1.2 According to Technical Specifications (TIS) this requirement is applicable as follows:
+ At least once per 24 hours.
- Modes 3 & 4 TIS 4.1.1.1.1.e
- Mode5 TIS4.1.1.2.b
+ Within 1 hour after detection of an inoperable control rod and at least once per 12 hours thereafter while rod is inoperable.
- Mode 1 & 2 TIS 3.1.3.1 Action a and action c.3
- Modes 1 - 4 TIS 4.1.1.1.1.a
- Mode5 TIS4.1.1.2.a
+ Prior to initial operation above 5% rated thermal power after each fuel loading with control banks at the maximum insertion limit in the COLR.
- Modes 2 - 4 TIS 4.1.1.1.1.d
+ Within 1 hour of detection of NO OPERABLE source range channels and at least once per 12 hours thereafter (Modes 3, 4, and 5).
- Mode 3 - 5 TIS 3.3.1.1, Table 3.3-1 Action 5 Salem Common Page 2 of 30 Rev.23
sC .RE-ST.ZZ-0002(Q)
+ When boration is required for the following T/S LCO's:
- Modes 1 - 3 T/S 3.1.2.2, Reactivity Control, Flow Paths
- Modes 1 - 3 T/S 3.1.2.4, Reactivity Control, Charging Pumps
- Modes 1 - 4 T/S 3.1.2.6, Reactivity Control, Borated Water Sources
+ Prior to and during refueling operations
- Mode 6 TIS 3.9.1
+ Whenever a SDM calculation is needed to ensure the reactor has adequate SDM.
2.0 PREREQUISITES None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 The Reactor Engineering Manager may substitute reactivity worths on the work sheet at his/her discretion. This allows the use of the latest determined reactivity worths that might not be incorporated into the Figures. Reactivity substitutions of any type should be noted on Attachment 7 and should be initialed by the Reactor Engineering Manager and the Shift Manager/Control Room Supervisor (SM/CRS) prior to use in the SDM calculation. 3.2 SDM shall be 2': 1300 pcm in Modes 1-4 (TIS 3.1.1.1). 3.3 SDM shall be 2': 1000 pcm in Mode 5 (T/S 3.1.1.2). 3.4 Maintaining SDM does NOT ensure that the reactor remains subcritical. Take note of keff to ensure against ACCIDENTAL CRITICALITY. Ensure that the required keff is maintained for the desired mode. 3.5 Since reactivity data will change with fuel exposure, use the most recent burn-up when reading reactivity data. 3.6 Reactivity effects of samarium have not been included in this procedure. After a shutdown, samarium concentration always increases tending to further poison the core. Any SDM calculated by this procedure would actually be more conservative since no credit is taken for samarium. 3.7 This procedure may be performed to verify SDM for current conditions or for the desired future conditions. 4.0 EQUIPMENT/MATERIAL REQUIRED
- J.d.A 4.1 Excel Spreadsheets (i.e. S 1(2)RE-STZZ-0002(Q).xls) (Optional)
Salem Common Page 3 of 30 Rev.23
sC .RE-ST.ZZ-0002(0) 5.0 PROCEDURE A s.1 Shutdown Margin Calculation 5.1.1 SELECT the applicable step below (e.g., 5.1.1.A): JlMlA A. !E. SDM is to be verified with no xenon credit (for Modes 3, 4, or 5), including IRPI Calibrations and/or Rod Drop Time Testing, THEN COMPLETE Attachment 1. A ,J/t,. B. !E. calculating the amount of reactivity by which the reactor is sub-critical (keff) and the amount of shutdown margin available in Modes 2, 3, 4 or 5 at any time in core life from a known critical condition THEN COMPLETE Attachment 2 (Detailed SDM Calculation).
!E. SDM is to be verified (per TIS 4.1.1.1.1.a) with reactor critical (Modes 1 or 2) and one or more control rods are inoperable THEN COMPLETE Attachment 3.
!E. SDM is to be verified (per T/S 4.1.1.1.1.d) prior to initial operation above 5% rated thermal power following a refueling outage with control banks at the maximum insertion limit THEN COMPLETE Attachment 4 .
.kJ rJI a. E. !E. determining a Mode 6 boron concentration in the Reactor Coolant System, the fuel storage pool, the refueling canal, and the refueling cavity which ensures the most restrictive reactivity condition is met per T/S 3.9.1, THEN COMPLETE Attachment 5.
!E. the reactor is in Mode 3 with the shutdown banks and control banks fully inserted and SDM is to be verified for RCS boration concurrent with cooldown (Modes 3, 4 or 5) THEN COMPLETE Attachment 6.
Salem Common Page 4 of 30 Rev.23
sC .RE-ST.ZZ-0002(Q) ~ 5.2 Acceptance Criteria
,,d_ 5.2.1 lE the acceptance criteria in the applicable attachment is met,
$ THEN this surveillance is satisfactory.
m IF\he acceptance criteria in the applicable attachment is NOT met, this surveillance is unsatisfactory. PERFORM the following: A. NOTIFY the SM/CRS. B. NOTIFY Nuclear Fuels. C. NOTIFY the Reactor Engineering Manager. A 5.3 Completion and Review
.d:: 5.3.1 COMPLETE Attachment 7, Sections 1.0 and 2.0.
& 5.3.2 DIRECT a Qualified Individual to PERFORM a review of this procedure.
5.3.3 Reviewer PERFORM a review of this procedure. COMPLETE Attachment 7, Section 3.0 and FORWARD this procedure to the Control Room Supervisor (CRS) for review. 5.3.4 SM/CRS PERFORM the following: A. REVIEW this procedure with all applicable attachments for completeness and accuracy. B. COMPLETE Attachment 7, Sections 2.0 and 4.0. C. FORWARD the completed procedure to Operations Staff. The most recently completed procedure should be maintained in the appropriate control room file. Ops Staff should FORWARD the previously completed procedure for records retention. END OF PROCEDURE SECTION Salem Common Page 5 of 30 Rev.23
sC .RE-ST.ZZ-0002(0) 6.0 RECORDS RETAIN the following IAW RM-AA-101, Records Management Program: Attachment 1 (as applicable) Attachment 2 (as applicable) Attachment 3 (as applicable) Attachment 4 (as applicable) Attachment 5 (as applicable) Attachment 6 (as applicable) Attachment 7
7.0 REFERENCES
7.1 Salem Common: 7.1.1 INPO SER 15-92, Loss of Shutdown Reactivity Margin 7 .1.2 DEF DES-91-00778 7.1.3 NOR, The Nuclear Design and Startup Report of the Current Cycle for Salem 1 OR Salem 2 Nuclear Power Plant 7.1.4 LCR S00-04, Request for Change to Technical Specifications Position Indicating System-Shutdown, Salem Generating Station, Unit Nos. 1 and 2, Facility Operating License DPR-70 and DPR-75, Docket Nos. 50-272 and 50-311 7.1.5 LCR S02-12, Request for Change to Technical Specifications for Fuel Storage Pool Boron Concentration Fuel Assembly Storage in the Spent Fuel Pool, Salem Generating Station, Unit Nos. 1 and 2, Facility Operating License DPR-70 and DPR-75, Docket Nos. 50-272 and 50-311 7.1.6 DS1 .8-0074, Relaxation of Keff During IRPI Calibration and Rod Drop Time Measurement 7.1.7 NFS 05-014, Considerations to Remove Administrative Shutdown Keff Requirement 7.1.8 NUTS 80086443, Relaxation of Keff During Lower Mode Control Rod Testing 7.1.9 Westinghouse Technical Bulletin TB-13-5, Calculation of Shutdown Margin for N-2 Configurations 7.1.10 082.5-0256, Inputs for Salem Technical Evaluation of Misaligned Rod ACE 7.1.11 WCAP-14762, Conditional Extension of the Rod Misalignment Technical Specification for Salem Units 1 and 2 7.2 Salem 1: 7.2.1 Safety Evaluation SECL-92-140, Salem Unit 1, Cycle 11 Operation with Increased Auxiliary Feedwater Flow 7.2.2 NFS 93-666, Salem Unit 1 cycle 12 Reload Safety Evaluation for Operation in Modes 5 through 1 and NRC Notification 7.2.3 DCP 1EC-3254, Boric Acid Concentration Reduction Program 7.2.4 Technical Specification Amendment No. 205 7.2.5 Technical Specification Amendment No. 232 7.2.6 Technical Specification Amendment No. 262 Salem Common Page 6 of 30 Rev. 23
sC .RE-ST.ZZ-0002(Q) 7.3 Salem 2: 7.3.1 NFU 92-155, Salem Unit 2 Administrative Shutdown Margin Requirements 7.3.2 NFU 92-181, Salem Unit 2 Cycle 7 Reload Safety Evaluation for Operation in all Modes and NRG Notification 7.3.3 DCP 2EC-3225, Boric Acid Concentration Reduction Program 7.3.4 NRG Docket No. 50-311, Amendment No. 197 7.3.5 Technical Specification Amendment No. 187 7.3.6 Technical Specification Amendment No. 213 7.3. 7 Technical Specification Amendment No. 244 7.4 Technical Specifications: 7.4.1 3/4.1.1.1, Boration Control, Shutdown Margin Tavg > 200°F 7.4.2 3/4.1.1.2, Boration Control, Shutdown Margin Tavg :::; 200°F 7.4.3 3/4.1.2.2, Reactivity Control, Flow Paths - Operating 7.4.4 3/4.1.2.4, Reactivity Control, Charging Pumps - Operating 7.4.5 3/4.1.2.6, Reactivity Control, Borated Water Sources - Operating 7.4.6 3/4.1.3.1, Reactivity Control, Movable Control Assemblies Group Height 7.4. 7 3/4.1.3.5, Reactivity Control, Control Rod Insertion Limits 7.4.8 3/4.3.1.1, Instrumentation, Reactor Trip System Instrumentation 7.4.9 S1 3/4.4.9.1, S2 3/4.4.10.1 Pressure/Temperature Limits, Reactor Coolant System 7.4.10 3/4.9.1, Refueling Operations, Boron Concentration 7.5 Cross-
References:
7.5.1 RM-AA-101, Records Management Program 7.5.2 S1 (2).0P-SO.CVC-0006(0), Boron Concentration Control 7.5.3 S1 (2).0P-SO.CVC-0008(0), Rapid Boration 7.5.4 S1 (2).0P-SO.RCS-0001 (0), Rod Control System Operation 7.5.5 SC.RE-ST.ZZ-0003(0), Core Reactivity Balance Calculation 7.5.6 S1 (2).RE-RA.ZZ-0016(0), Curvebook 7.5.7 S1(2).RE-RA.ZZ-0012(Q), Figures Salem Common Page 7 of 30 Rev.23
sC .RE-ST.ZZ-0002(Q) ATTACHMENT 3 SHUTDOWN MARGIN VERIFICATION FOR MODES 1 OR 2 Page 1 of 3 SALEM UNIT ()__ 1.0 PURPOSE 1.1 The purpose of this attachment is to determine the SDM with a critical reactor. 1.2 This attachment satisfies the surveillance requirements of TIS 4.1.1.1.1.a and 4.1.1.1.2. 1.3 This attachment SHALL be performed within 1 hour after detection of an inoperable control rod and at least once per 12 hours thereafter while the rod(s) is (are) inoperable. 1.4 This attachment is used to ensure adequate shutdown margin IAW SC.RE-ST.ZZ-0003(0), Core Reactivity Balance Calculation. 2.0 PREREQUISITES A 2.1 The reactor is in Mode 1 or Mode 2 with keff~ 1.0. 3.0 PRECAUTIONS AND LIMITATIONS A 3.1 All figures are located in S1 (2).RE-RA.ZZ-0016(0) Curvebook. -81 3.2 All data from the tables and figures should be taken as the absolute value. Any mathematical signs(+/-) should be propagated throughout the rest of the calculation. 3.3 This calculation does NOT consider the effects of RCS boron concentration, RCS average temperature, xenon concentration, or samarium concentration. Tave will decrease from the critical condition to the hot zero power shutdown condition. However, the reactivity effect of this will be accounted for in the power defect. The other factors will stay constant from the critical condition to the hot zero power shutdown condition. 3.4 The term "abs" found in some formulas refers to the absolute value of the item in question. 3.5 Inoperable RCCAs are further classified as untrippable, dropped or misaligned. 4.0 PROCEDURE 4.1 CRITICAL CONDITIONS 4.1.1 POWER LEVEL 100 %RTP 4.1.2 BORON CONCENTRATION 3DO ppm 4.1.3 CONTROL BANK POSITION Bank_Q__ at :J..J/ Steps 4.1.4 BURNUP 1opoo EFPH 4.1.5 #OF UNTRIPPABLE RCCA(s) 0 RCCA(s) 4.1.6 #OF DROPPED OR MISALIGNED RCCA(s) RCCA(s) Salem Common Page 20 of 30 Rev.23
SC. RE-ST.ZZ-0002( Q) ATTACHMENT 3 SHUTDOWN MARGIN VERIFICATION FOR MODES 1 OR 2 Page 2 of 3 SALEM UNIT d._ 4.2 CALCULATION OF ROD WORTH 4.2.1 TOTAL CONTROL BANK WORTH (Figure 15/Table G) (-} 302-f I pcm 4.2.2 TOTAL SHUTDOWN BANK WORTH (Figure 16/Table H) (-} 3335 pcm 4.2.3 MOST REACTIVE STUCK ROD WORTH 7.A.6 pcm (Figure 14/Table I) NOTE The reactivity worth for a single or multiple untrippable RCCAs and dropped or misaligned RCCAs comes from Table 1-6 S1 (2).RE-RA.ZZ-0016, Curve Book. For multiple untrippable RCCAs, the penalty in 4.2.4 should have a maximum value of the sum of the total shutdown and control bank worths in steps 4.2.1 and 4.2.2. 4.2.4 PENALTY FOR UNTRIPPABLE RCCA(s) 0 pcm 0 x = Item 4.1.5 Table 1-6 4.2.5 PENAL TY FOR DROPPED OR MISALIGNED RCCA(s) 500 pcm x 500 = Item 4.1.6 Table 1-6 4.2.6 INTEGRAL ROD WORTH INSERTED AT POSITION IN ITEM 4.1.3 (If ARO, use zero) 0 pcm (HFP: Figure 2C/Table 1-7 or HZP: Figure 2A!Table 1-8) NOTE The penalties for untrippable RCCAs include the most reactive stuck rod worth. The most reactive stuck rod worth from step 4.2.3 is not needed when calculating the trippable rod worth with at least one untrippable RCCA. 4.2.7 CHOOSE the appropriate calculation below. MARK the calculation not used "N/A." TRIPPABLE ROD WORTH - 5q 4 B pcm (Item 4.2.1) + (Item 4.2.2) + (Item 4.2.3) + (Item 4.2.5) + (Item 4.2.6) = OR TRIPPABLE ROD WORTH WITH UNTRIPPABLE RCCA(s) tJ/A pcm (Item 4.2.1) + (Item 4.2.2) + (Item 4.2.4) + (Item 4.2.5) + (Item 4.2.6) = Salem Common Page 21of30 Rev. 23
sC.RE-ST.ZZ-0002(0) ATTACHMENT 3 SHUTDOWN MARGIN VERIFICATION FOR MODES 1 OR 2 Page 3 of 3 SALEM UNIT :J._ 4.3 CALCULATION OF SOM (Note: See Precaution 3.4) 4.3.1 TRIPPABLE ROD WORTH (Item 4.2.7) - S'i4B pcm 4.3.2 TEN PERCENT ROD WORTH PENALTY (+) (.,,Lf 5 pcm ( 3£1..fl + 3335 728 )x0.10= abs(ltem 4.2.1) abs(ltem 4.2.2) (Item 4.2.3) 4.3.3 ROD MISALIGNMENT RELAXATION PENALTY (+) 120 pcm 4.3.4 POWER DEFECT (Figure 17A/Table 2-1) J,14J._ pcm 4.3.5 SOM ,... J-1-/-4 I pcm (Item 4.3.1) + (Item 4.3.2) + (Item 4.3.3) + (Item 4.3.4)= 4.4 ACCEPTANCE CRITERIA NOTE REQUIRED SOM (perT/S 3.1.1.1) MODE 1 OR2: (-)1]_ % flk/k = (-)1300 PCM fa 4.4.1 IS THE SOM (Item 4.3.5) EQUAL TO OR MORE NEGATIVE THAN(-) 1300
$ PCM?
YES: then surveillance is SAT: NO: then surveillance is UNSAT: NOTE If the required power defect in step 4.4.2.A is negative, then it is not possible to meet SOM by lowering reactor power and step 4.4.2.B will be 0%. 4.4.2 IF the SOM is UNSAT, THEN PERFORM the following: A. CALCULATE the power defect required to achieve required SOM.
;.1/A - tJ/1>. - 120 pcm -1300 pcm= _Nit-.
_ _ _ pcm abs( Item 4.3.1) Item 4.3.2 Item 4.3.3 B. DETERMINE Reactor Power Level based on power defect in 4.4.2.A and boron concentration in 4.1.2. (Figure 17A/Table 2-1) _N~/A.__ %RTP C. NOTIFY SM/CRS to initiate rapid boration, IAW S1 (2).0P-SO. CVC-0008(Q), Rapid Boration, and reduce reactor power UNTIL the required SOM is attained. Completed by: A&i-Jl.:.,.0 bP-.ubl~ Date: "ToDA.(t Time: 10-z...o Reviewed by: -t4~. SPiZl>.:(.Sl~i-> Date: -toa "\I Time: 10'2...9 Salem Common Page 22 of 30 Rev. 23
sC.RE-ST.ZZ-0002(0) ATTACHMENT 7 COMPLETION/SIGN-OFF SHEET Page 1 of 1
1.0 COMMENTS
(Procedure deficiencies shall be documented with corrective actions in this section.)
2.0 SIGNATURES
3.0 REVIEWER SIGNATURES: Name (Print) Initials
'6 Sfn,,ff k~ .-c:...
4.0 FINAL REVIEW AND APPROVAL: This procedure has been reviewed for completion and accuracy. All deficiencies with their associated corrective actions have been clearly recorded in the COMMENTS section above. Approved B y : - - - - - - - - - - - - - - Date: _ _ _ _ _ _ __ SM/CRS Salem Common Page 30 of 30 Rev.23
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Determine required actions upon Radioactive Effluent Monitor failure TASK NUMBER: N1200010301 JPM NUMBER: 15-01 NRC SRO Admin A3 ALTERNATE PATH: D KIA NUMBER: _________ 2.3.11 __, IMPORTANCE FACTOR: 4.3 APPLICABILITY: RO SRO EOCJ ROCJ STAL] SROITJ EVALUATION SETTING/METHOD: Classroom Salem ODCM, Salem Tech Specs, S1 .OP-SO.WL-0001, Rev. 27, S1 .OP-SO.WG-
REFERENCES:
0011, Rev. 31, S1 .OP-SO.CBV-0002, Rev. 21 (All checked 8-10-16) TOOLS AND EQUIPMENT: VALIDATED JPM COMPLETION TIME: 25 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-10-16 Instructor Validated By: Date: 9-28-16110-4-16 Approved By: Approved By: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
~~~~~~~~~~~~-
DATE: SYSTEM: Administrative TASK: Determine required actions upon Radioactive Effluent Monitor failure TASK NUMBER: N1200010301 INITIAL CONDITIONS: Unit 1 is operating at 100% power. Radiation Monitor 1R12A, Containment Noble Gas, failed its Source Check when preparing to perform a normal Containment Pressure Relief IAW S1 .OP-SO.CBV-0002, Containment Pressure-Vacuum Relief System Operation. 11 CVCS Monitor Tank is ready for release. 14 Gas Decay Tank (GOT) is ready for release. INITIATING CUE: Prior to initiating the Containment Pressure Relief, Rad Monitor 1R41 D, Plant Vent Release Rate, indication fails high, and is confirmed as an instrument failure. For the following radiological releases, determine:
- 1) Can the release be performed with the failed monitors described above, and,
- 2) If the release can be performed, what compensatory actions are required.
Assume each release will be performed individually. RELEASES
- Containment Pressure Relief
- 11 CVCS Monitor Tank release
- 14 GOT release Successful Completion Criteria:
- 1. All critical steps completed
- 2. All sequential steps completed in order
- 3. All time-critical steps completed within allotted time
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion:
- 1. Determines ALL the releases may be performed.
- 2. Determines additional compensatory measures apply for the Waste Gas Release and the Containment Pressure Relief per key, and no additional compensatory actions are required for Liquid Release.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE:, _ _ _ _ _ _ _ _ __ System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure STEP STEP STANDARD EVAL COMMENTS NO.
- Denotes a Critical Step S/U (Required for UNSAT evaluation)
Provide blank copies of: S1 .OP-SO.WG-0011 S1 .OP-SO.CBV-0002 S1 .OP-SO.WL-0001 Salem ODCM Waste Gas Release Determines ODCM 3.3.3.9 applies to S1 .OP-SO.WG-0011 Gaseous Effluent which directs actions per Table 3.3-13. Determines Table 3.3-13, Instrument #1, Waste Gas Holdup System is applicable, which requires (1) 1R41A~ D. Action 31 applies. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE:. _ _ _ _ _ _ _ _ _ __ System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure
- STEP STEP STANDARD EVAL COMMENTS NO.
- Denotes a Critical Step I S/U (Required for UNSAT evaluation)
Action 31 states that with less than the minimum required Operable channels, the contents of the tank may be released provided that prior to the initiating the release:
- a. At least two independent samples of the tanks contents are analyzed,
- and
- b. At least two technically qualified members of the facility Staff independently verify the release rate calculations and discharge valving lineup; otherwise suspend release of radioactive effluents via this pathway.
- Additionally, S1 .OP-SO.WG-0011, Discharge of 14 Gas Decay Tank to Plant Vent, Attachment 2, Section 3.0, Dose Estimates and Approval, Step 3.4.C (on page 18) states ... " Grab samples are being obtained at least once per 8 hours I AND analyzed for gaseous principal gamma emitters within 24 hours PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE: System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure
- STEP STEP STANDARD EVAL COMMENTS NO.
- Denotes a Critical Step S/U (Required for UNSAT evaluation)
- Determines that there is no restriction on performing Liquid Releases.
Containment Pressure Relief Determines that Precaution and Limitation S1 .OP-SO.CBV-0002 2.3 of S1 .OP-SO.CBV-0001 directs operator to notify Chemistry to comply with the contingency actions associated with the ODCM prior to performing a Containment Pressure Relief. Determines Table 3.3-13, Instrument #3, applies to the Containment Pressure Relief. With both channels (1R41A_& DOR 1R12A) inoperable, Action 37 applies. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 8
OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ __ JOB PERFORMANCE MEASURE DATE: System: ADMINISTRATIVE I Task: Determine required actions upon Radioactive Effluent Monitor failure
- STEP STEP I STANDARD EVAL COMMENTS NO.
- Denotes a Critical Step SIU (Required for UNSAT evaluation)
Action 37 states that with less than the minimum required Operable channels, Containment Pressure I Reliefs may be performed provided that prior to initiating the release:
- a. At least two independent samples of the tanks contents are analyzed, and
- b. At least two technically qualified members of the facility Staff independently verify the release rate calculations, otherwise suspend release of radioactive effluents via this pathway.
Waste Liquid Release Determines no compensatory actions are S1 .OP-SO.WL-0001 required to initiate the Liquid Release. Terminate JPM when all paperwork is handed in. Note to Evaluator: JPM modeled after Pilgrim Jan 2011 NRC Exam SRO Admin JPM RC. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.
\fa / ~ 1J'1. Task description and number, JPM description and number are identified.
\t- / ~@z. Knowledge and Abilities (KIA) references are included. \;v / r-<{j;;j. Performance location specified. (in-plant, control room, or simulator)
\,f' I ~ ~- Initial setup conditions are identified.
~ /- ,-. ~. Initiating and terminating Cues are properly identified.
/r PG. Task standards identified and verified by SME review.
;--/\Pr_ Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
~ '8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _ _ Date----..,..--
/1.,.,- A.\\ {'¢..v~C.:J.A~ ~lucA ~(2.-<\/lio
/ 7 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
rJ l~~he JPM cannot be performed as written with proper responses, then revise the JPM. Nw'P1:1f When JPM is revalidated, SME or Instructor sign and date JPM cover page. Date: Cf /it{ l1o Date: f 6/p{c SME/lnstructor: Date: - - - - - -
------------~
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8
INITIAL CONDITIONS: Unit 1 is operating at 100% power. Radiation Monitor 1R12A, Containment Noble Gas, failed its Source Check when preparing to perform a normal Containment Pressure Relief IAW S1 .OP-SO.CBV-0002, Containment Pressure-Vacuum Relief System Operation. 11 CVCS Monitor Tank is ready for release. 14 Gas Decay Tank (GOT) is ready for release. INITIATING CUE: Prior to initiating the Containment Pressure Relief, Rad Monitor 1R41 D, Plant Vent Release Rate, indication fails high, and is confirmed as an instrument failure. For the following radiological releases, determine:
- 3) Can the release be performed with the failed monitors described above, and,
- 4) If the release can be performed, what compensatory actions are required.
Assume each release will be performed individually. RELEASES
- Containment Pressure Relief
- 11 CVCS Monitor Tank release
- 14 GOT release PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1) TASK NUMBER: 1240020502 JPM NUMBER: 15-01 NRC SRO Admin A4-1 (ESG-1) ALTERNATE PATH: I I KIA NUMBER: ~~~~~~~~~-i 2.4.41 IMPORTANCE FACTOR: 4.6 APPLICABILITY: RO SRO EOD ROD STAD SRO[g] EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)
REFERENCES:
EP-SA-111-F2 Rev. 2 (ALERT) TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 9-19-15 Instructor Validated By: C Davis I P Williams Date: 9-21-16/10-4-16 SME or Ins ruct~ Approved By: Traini epa/D.ent Date: 10/cfu Approved By: Date: 1o}j1i, obepartment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1of8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1) TASK NUMBER: 1240020502 INITIAL CONDITIONS:
- 1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.
INITIATING CUE: You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator. This is a Time Critical JPM. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Declare an ALERT under EAL RB3.P within 15 minutes of start time, and provide ICMF to the Primary Communicator within the next 15 minutes.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD for UNSAT S/U evaluation)
Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as and Blank Copies of EP-SA-111-F1 necessary - 5 minute limit prior to starting) through F4 (UE, ALERT, SAE, GE)
*START TIME:
*Start time begins when candidate '
Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started. duties Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG Classifies the event Determines the classification of the event and refers to ECG Attachment 2 (Alert) Att 2 CALL communicators to the Control Pages communicators and initials as SM A.1 Room Cue: I am the Primary Communicator PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD for UNSAT S/U evaluation)
Att 2 IF a Security Event is in progress, THEN Determines Security Event is not in A.2 IMPLEMENT the prompt actions of progress. NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to the classification. If time allows, DIRECT Classification Att 2 Cue: No independent verification will be A.3 Independent Verification to be performed. performed. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD for UNSAT S/U evaluation)
Att 2 After Classification Independent Declares an ALERT under RB3.P within A.4 Verification is obtained: 15 minutes of Start Time:
*
- DECLARE the ALERT (enter time and date on ICMF)
Completes and Approves the ICMF as
*
- COMPLETE I APPROVE the ICMF follows:
EAL#(s): RB3.P Description of Event: Potential Loss of the Reactor Coolant System Boundary Note: Description of Event is found in EAL Description Table Fills out Section Ill: Checks IS NOT for a Radiological Release in progress. Fills out Section IV: Retrieves wind speed (10)and direction (160) data from SPDS Initials for ai;mroval to transmit Att 2 l I I A.5 If time allows OBTAIN accuracy peer check of the completed ICMF Cue: No peer check will be performed. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD S/U for UNSAT evaluation)
Att 2 A.6 Continue with NOTIFICATION AND ACTIVATION as follows:
- If not previously performed, ACTIVATE I DIRECT ACTIVATION of ERO Cue: Activation of ERO Emergency Callout is not required for this JPM.
Emergency Callout (EP 96-003)
- DIRECT the Primary Communicator to Provides ICMF to Primary Communicator implement ECG Attachment 6 within 15 minutes of event declaration Terminate JPM when ICMF is given to the Evaluator.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 8
TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.
\.JJ / ~<a-r.Task description and number, JPM description and number are identified.
/ tJ,.._~. Knowledge and Abilities (KIA) references are included.
~
\_tJ / a-
8. Verify the procedure referenced by this JPM matches the most current revision of ,;{\ that procedure: Procedure Rev. _1_ Date <il *'lf* / 6 IA.,. ~Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
~......-~* If the JPM cannot be performed as written with proper responses, then revise the JPM. '6 . . . ~ When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnsfJuctor~Af'~ Date:~ SME/lnstructor: . /~J Date:~ SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __ PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8 INITIAL CONDITIONS:
- 1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.
You may continue to reference the procedures or to look at the control board but "the clock will be -running;-lf there are multiple ECG calls, classify the most severe. INITIATING CUE: You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator. This is a Time Critical JPM. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 8 EP-SA-111-F2 ATT2 Pg. 1of5 ATTACHMENT 2 ALERT A. CLASSIFICATION
- 1. CALL communicators to the Control Room.
SM 2.~ IF a Security Event is in progress, THEN IMPLEMENT the prompt actions of NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to classification. SM
- 3. If time allows, DIRECT Classification Independent Verification to be performed SM
- 4. After Classification Independent Verification is obtained:
- DECLARE the ALERT (enter time and date on ICMF)
- COMPLETE I APPROVE the ICMF EC
- 5. If time allows OBTAIN accuracy peer check of the completed ICMF EC
- 6. Continue with NOTIFICATION AND ACTIVATION as follows:
EC
- If not previously performed, ACTIVATE I DIRECT ACTIVATION of ERO Emergency Callout
{EP 96-003) EC
- DIRECT the Primary Communicator to implement ECG Attachment 6 EC
- DIRECT the Secondary Communicator to implement ECG Attachment 8 for an ALERT EC
- If not previously performed, VERIFY I DIRECT VERIFICATION of ERO Emergency Callout activation EC
- UPDATE Crew/Facility with Emergency Classification Level and potential escalation criteria EC
- IMPLEMENT NC.EP-EP.ZZ-0102, EC Response EC SGS Rev. 02
EP-SA-111-F2 ATT2 Pg. 2 of 5 INITIAL CONTACT MESSAGE FORM I. THIS IS _ _ _ _ _ _ _ _ , COMMUNICATOR IN THE D CONTROL ROOM (NAME) D TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT(s) No. _ _ II. THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED AT ON - -(Time - -- 24-HR-CLOCK) ---- - - - - -(DATE) EAL# - - - - - - - DESCRIPTION OF EVENT Any release II I. D THERE IS A RELEASE IN PROGRESS DUE TO THE EVENT } above normal. - attributable to the 0 THERE IS NO RELEASE IN PROGRESS DUE TO THE EVENT event. See Basis - for examples. IV. 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED: (From MET Computer /SPDS) (DEGREES) (MPH) V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME EC Initials (Approval to Transmit ICMF) SGS Rev.02 EP-SA-111-F2 ATT2 Pg. 3 of 5 BASIS - ALERT ICMF Classification
- Non-Delegable Actions: Actions taken in the process of emergency classification maybe delegated as needed with the exception of the 4 non-delegable actions listed below (1)
- --*---- -- - --- ---o
- Classify emergencies in accordance with the Salem and Hope Creek-Event Classification Guides - Includes final determination of the classification and approval of the ICMF o Make decisions to notify and recommend protective actions to offsite agencies o Provide overall direction, control and coordination of PSEG Nuclear's Emergency Response o Authorize the expenditure of company funds and commit corporate resources as necessary to implement emergency procedures and/or
______ -*-------- to._rniJigate the accident_ -**----* **-*-----*--------*-------
- Communicators: Call communicators to the Control Room as soon as possible to provide time for them to respond from the field
- Independent Verification:
o When the Shift Manager (SM) is the Emergency Coordinator, the Shift Technical Advisor (STA) is responsible to perform an independent verification of the EAL classification. The STA verification does not alleviate the requirement of the SM to make a timely classification. Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO, the Independent Assessor. o Independent verification, while recommended, is not required and should be performed at the SM/ECs discretion as time allows and based on plant conditions. (2 )
- STA or designee performs Independent Verification for SM
- SM or designee performs Independent Verification for EDO
- EDO or designee performs Independent Verification for ERM o During the verification phase begin filling in the ICMF, completing the EAL declaration time once the EC and Independent Verifier have conferred and agree on a classification.
SGS Rev. 02 EP-SA-111-F2 ATT2 Pg. 4 of 5
- Accuracy Peer Check: Have the STA, TSS, SSM or other knowledgeable individual perform an accuracy peer check of the ICMF. The peer check should include:
o verification that the correct form has been used for the classification o review of all applicable fields that have been completed by the SM during completion of the ICMF (date, time, EAL, Description etc.) to ensure data is correcUaccurate o EC approval initials have been completed.
- Classification Timeliness: Classification must occur after verification and before the 15 minute EAL clock expires. Assessment of an Emergency Condition should be completed in a timely manner, which is considered to be within 15 minutes of when events are known or should have been known. If an EAL specifies a duration time (e.g., loss of annunciators for 15 minutes or longer), the assessment time runs concurrently with the EAL duration time
~ and is the same length. ~3!
- Rad Release Determination (Salem): Any of the following conditions constitutes a release in progress due to the event:
o Increase in Plant Vent Release Rate (NOT caused by operational transients or ventilation changes) which is caused by the EVENT. o A Steam Generator rupture which is faulted to the atmosphere (SRV, Atmospheric Vent or Line Break) o Evidence of an UNMONITORED release to atmosphere, examples include:
- Primary to Secondary leak and the steam driven feed pump is in service
- Bypass release from the Aux Building through the Electrical Pen
- Leakage from the Containment directly to atmosphere after a LOCA
- Elevated background radiation levels downwind from the station as monitored/reported by Radiation Protection Technician at fence line SGS Rev. 02
EP-SA-111-F2 ATT2 Pg. 5 of 5 Notification
- Callout Activation (Alert, SAE, GE):
o Emergency Response Organization (ERO) Emergency Callout Activation is required for an Alert or higher classification. o Activation maybe delegated to the communicators if available, but
-- must be performed as soon as possible after classification. The SM-shall perform the callout if communicators are not available.
o Activate the ERO Emergency Callout system using the posted instructions titled "Emergency Callout Activation". o ERO callout system activation will be confirmed by a return call from the Everbridge system to the Communicators phone. If callout fails, then utilize backup procedures to alert the ERO (EP Aid-0032)
References:
- - - - ( - 1 ) EmergencyJ21an,-Section.3.Q__.,.._Qrganization, ParagraphA.Q_...,._Emergency-Direction.and Control ------~ (2) ECG Introduction and Usage Section 8.4.8 (3) ECG Introduction and Usage Section 8.2.1 (4) EP 96-003 - Enhance callout system by correcting deficiencies and capturing time inefficiencies SGS Rev. 02
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2) TASK NUMBER: 1240020502 JPM NUMBER: 15-01 NRC SRO Admin A4-1 (ESG-2) ALTERNATE PATH: KIA NUMBER: _________ 2.4.41 __, IMPORTANCE FACTOR: 4.6 APPLICABILITY:
- -RO- - SRO EOLJ ROLJ STAD SRO[))
EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)
REFERENCES:
EP-SA-111-F2 Rev. 2 (ALERT) TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 9-19-15 Instructor Validated By: Date: 9-21-16110-4-16 Approved By: Approved By: ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1of8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2) TASK NUMBER: 1240020502 INITIAL CONDITIONS:
- 1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.
INITIATING CUE: You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator. This is a Time Critical JPM. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Declare an ALERT under EAL RB3.L within 15 minutes of start time, and provide ICMF to the Primary Communicator within the next 15 minutes.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD for UNSAT S/U evaluation)
Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as and Blank Copies of EP-SA-111-F 1 necessary - 5 minute limit prior to starting) through F4 (UE, ALERT, SAE, GE)
*START TIME:
*Start time begins when candidate I Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started.
duties Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG Classifies the event Determines the classification of the' event and refers to ECG Attachment 2 (Alert) Att 2 CALL communicators to the Control Pages communicators and initials as SM A.1 Room Cue: I am the Primary Communicator PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD for UNSAT S/U evaluation)
Att 2 IF a Security Event is in progress, THEN Determines Security Event is not in A.2 IMPLEMENT the prompt actions of progress. NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to the classification. If time allows, DIRECT Classification Att 2 Cue: No independent verification will be A.3 Independent Verification to be performed. performed. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8
OPERATOR TRAINING PROGRAM NAME: ------ JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD for UNSAT S/U evaluation)
Att 2 After Classification Independent Declares an ALERT under RB3.L within A.4 Verification is obtained: 15 minutes of Start Time:
*
- DECLARE the ALERT (enter time and date on ICMF)
Completes and Approves the ICMF as
*
- COMPLETE I APPROVE the ICMF follows:
EAL#(s): RB3.L Description of Event: Loss of the Reactor Coolant System Boundary Note: Description of Event is found in EAL Description Table Fills out Section Ill: Checks IS for a Radiological Release in progress. Fills out Section IV: Retrieves wind speed (10)and direction (160) data from SPDS Initials for a1;rnroval to transmit Att 2 A.5 If time allows OBTAIN accuracy peer check of the completed ICMF Cue: No peer check will be performed. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2) COMMENTS STEP STEP (Required (*Denotes a Critical Step) EVAL
- NO. STANDARD forUNSAT S/U evaluation)
Att 2 A.6 Continue with NOTIFICATION AND ACTIVATION as follows:
*If not previously performed, ACTIVATE I DIRECT ACTIVATION of ERO Cue: Activation of ERO Emergency Callout is not required for this JPM.
Emergency Callout (EP 96-003)
- DIRECT the Primary Communicator to Provides ICMF to Primary Communicator implement ECG Attachment 6 within 15 minutes of event declaration Terminate JPM when ICMF is given to the Evaluator.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 8
TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.
~~Task description and number, JPM description and number are identified. ~Q.*Knowledge and Abilities (KIA) references are included.
0 U°3:'Performance location specified. (in-plant, control room, or simulator)
~Initial setup conditions are identified.
Vi Qs.-lnitiating and terminating Cues are properly identified. 0, ~Task standards identified and verified by SME review.
~~ Critical steps meet the criteria for critical steps and are identified with an asterisk (*). ~ f!/)s. Verify the procedure referenced by this JPM matches the m?st current revision of
- that procedure: Procedure Rev.~ Date Vj, ?A'lh
~B-Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
V\.. 9:o. If the JPM cannot be performed as written with proper responses, then revise the JPM.
~0 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.
SME/lnstructor: ~ SME/lnstructor~~ SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __ PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8
INITIAL CONDITIONS:
- 1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.
You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe. INITIATING CUE: You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator. This is a Time Critical JPM. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 8
OPERATOR TRAINING PROGRAM: JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 JPM NUMBER: 15-01 NRC Sim a ALTERNATE PATH: I x I KIA NUMBER: 001 A4.03
~~~~~~~~~--<
IMPORTANCE FACTOR: 4.0 3.7 APPLICABILITY: RO SRO EoO RO[)) STAD SRO[)) EVALUATION SETTING/METHOD: Simulator
REFERENCES:
S2.0P-ST.RCS-0001, Rev. 22 (checked 8-3-16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-3-16 Instructor Validated By: M Lutek I W Russell Date: 8-22-16 SME or Instructor rfY Approved By: Train in
,v'\ .,, rlL'-1 partment Date: 10/i/(.,
Approved By: Opebment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE:
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 SIMULATOR IC: IC-251 in 15-01 NRC JPMs MALFUNCTIONS REQUIRED: RT-1 will trip 21 SGFP MALF: BF0105A, 21 STM GEN FEED PUMP TRIP, Final Value: 3 OVERRIDES REQUIRED: None SPECIAL INSTRUCTIONS: None Note to Evaluator: OP-AP-300-1001 required a peer check for all non-emergency manual rod motion. Do NOT correct operator if a mistake is made when performing a peer check. For all required peer checks simply state "Peer check SAT".
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~~~ DATE: ~~~~~~~~~~~~~~~~ SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 INITIAL CONDITIONS: Unit 2 is operating at steady state, 100% power. Power has been at 100% for 30 days. INITIATING CUE:
- You are directed to perform S2.0P-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.
- A Maintenance Technician is stationed at the Rod Control System Power Cabinets .
- Communications are established via plant page between the Control Room and Jeff Stevens, NEO, at the Rod Control System Power Cabinets.
- The CRS has directed that steps 5.1.2 through 5.1.9 are to be performed in order.
- The CRS directs that 15 steps of rod insertion are to be performed for each bank to ensure that each rod moves at least 1O steps.
- Initial Control Rod Positions are:
SDA SOB SOC SOD F-04 229 G-03 229 E-03 229 C-05 229 D-10 228 C-09 227 C-11 223 E-13 223 K-12 227 J-13 227 L-13 224 N-11 224 M-06 227 N-07 229 N-05 224 L-03 227 B-04 230 J-02 223 D-14 224 C-06 223 P-12 229 G-13 227 M-02 230 N-09 230 Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion: Operator trips the Rx when Shutdown Bank B is inserted in the core and a SGFP trips.
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~- SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U Evaluation)
Provide marked up copy of S2.0P-ST.RCS- Reviews Prerequisites. 0001, Rev. 22, with Prerequisite Sections 2.1-2.8 filled out. Provide copy of 0 P-AP-300-1001, PW R Control Reviews OP-AP-300-1001, PWR Control Rod Movement Requirements. Rod Movement Requirements. Reviews and signs Precautions and Limitations. Cue: IF ASKED, state that no special contingency actions have been briefed other than what is in the P&L's. 5.1.1 IF this surveillance is to be performed .... Determines step is N/A based on steady state 100% operation. 5.1.2 PERFORM Attachment 2, Rod Control System Performs Attachment 2 Rod Control Voltage Checks as follows: System Voltage Checks by: A. PLACE Rod Bank Selector Switch to A. Places Rod Bank Selector Switch "MANUAL". to manual. B. Direct Maintenance to COMPLETE B. Directs Direct Maintenance to Attachment 2, Rod Control System complete Attachment 2, Rod Voltage Checks. Control System Voltage Checks. Cue: Maintenance reports Attachment 2 Rod Control System Voltage Checks are complete SAT.
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~- SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD SIU Evaluation)
Note _The Shutdown Rod Insertion Limit (TS Initials both notes. 3.1.3.4) is not applicable during the performance of this test for rods actually undergoing testing. _Steps 5.1.3 through 5.1.10 may be performed in any order.
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~- SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U Evaluation) 5.1.3 PERFORM Shutdown Bank A testing as follows:
A. IF the Rx is critical, THEN ENSURE Tavg Checks Tave/Tref recorder on 2RP4 and is within +/-1°F ofTref* notes Tavg is within 1°F of Tref.. B. PLACE Bank Selector Switch in the Rotates Bank Selector Switch fully counter
* "SBA" position. clockwise to the SBA position.
C. ENSURE GRP. SELECT "C" lights are Contacts NEO and directs him to verify illuminated on Rod Control System GRP. SELECT "C" lights are illuminated Power Cabinets 21AC and 22AC. on Rod Control System Power Cabinets 21AC and 22AC. Cue: GRP SELECT "C" lights are illuminated at Rod Control System Power Cabinets 21AC and 22AC. D. Maneuver Shutdown Bank A at least 10 IAW OP-AA-300-1001, prior to rod
- steps in any one direction. movement, operator states initial Shutdown Bank A position, target control rod position, and direction of rod movement, then inserts SBA at least 1O steps to stated target position.
E. ENSURE each rod in Shutdown Bank A Verifies rod movement by viewing rod indicated rod movement of at least 10 position on P-250 computer. steps. F. RECORD Shutdown Bank A "Test Initials SAT for Groups 1 and 2 for SBA on Results" by initialing in Attachment 1. Att 1. G. RESTORE Shutdown Bank A to pre-test Operator states initial Shutdown Bank A
- condition. position, target control rod position, and direction of rod movement, then withdraws SBA to stated target ARO position.
Continuous rod withdrawal is acceptable.
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~ SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD SIU Evaluation) 5.1.4 PERFORM Shutdown Bank B testing as follows:
A. IF the Rx is critical, THEN ENSURE T avg Checks Tave/Tref recorder on 2RP4 and is within +/-1°F of Tref* notes Tavg is within 1°F of Tref. B. PLACE Bank Selector Switch in the Rotates Bank Selector Switch clockwise to
* "SBB" position. the SBB position.
C. ENSURE GRP. SELECT "C" lights are Contacts NEO and directs him to verify illuminated on Rod Control System GRP. SELECT "C" lights are illuminated Power Cabinets 21 BD and 22BD. on Rod Control System Power Cabinets 21 BD and 22BD. Cue: GRP SELECT "C" lights are illuminated at Rod Control System Power Cabinets 21 BD and 22BD. D. MANUEVER Shutdown Bank B at least Operator states initial Shutdown Bank B
- 10 steps in any one direction. position, target control rod position, and direction of rod movement, then inserts SBB at least 10 steps to stated target position.
E. ENSURE each rod in Shutdown Bank B SIMULATOR OPERATOR: INSERT RT-1 indicated rod movement of at least 10 when the operator is checking rod position steps. after insertion. This will trip 21 SGFP. Responds to 21 SGFP trip by tripping the
- Rx IAW P&L 3.13.
Movement of the Rod Bank Selector Switch to MAN or AUTO under these conditions is incorrect. When the operator has either tripped the Rx or initiated rod insertion in MAN or AUTO, state JPM is complete.
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 4 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.
\J / d-lJ?11. Task description and number, JPM description and number are identified.
{JI I ~£M2. Knowledge and Abilities (KIA) references are included. V ./ d"" lffe13. Performance location specified. (in-plant, control room, or simulator) tJ I (r-{'1._ Initial setup conditions are identified. V / Cr i.t1. Initiating and terminating Cues are properly identified. (.!" I 'C--U'1. Task standards identified and verified by SME review. \r I §~ Critical steps meet the criteria for critical steps and are identified with an asterisk(*). (, I y[l/'d, Verify the procedure referenced by this JPM matches the{'lOSt current revision of t}t that procedure: Procedure Rev. _2J._ Date ~ / 1 :e, /_J_ $""
~ 9. Pilot test the JPM:
t ltl\ a. verify Cues both verbal and visual are free of conflict, and L¥' \ b. ensure performance time is accurate. 0 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: IV\ L "t -t...-lt.-
---~---------
Date: ~11.. ,_/1;o SME/lnstructor:~JVJ~'~Lr~---+--~£~u.=.r~s~,elf'-"'-+--- Date: f' /z:i-/r 0
--,---.II-"-'~-
SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Unit 2 is operating at steady state, 100% power. Power has been at 100% for 30 days. INITIATING CUE:
- You are directed to perform S2.0P-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.
- A Maintenance Technician is stationed at the Rod Control System Power Cabinets .
- Communications are established via plant page between the Control Room and Jeff Stevens, NEO, at the Rod Control System Power Cabinets.
- The CRS has directed that steps 5.1.2 through 5.1.9 are to be performed in order .
- The CRS directs that 15 steps of rod insertion are to be performed for each bank to ensure that each rod moves at least 10 steps.
- Initial Control Rod Positions are:
SDA SOB SOC SOD F-04 229 G-03 229 E-03 229 C-05 229 D-10 228 C-09 227 C-11 223 E-13 223 K-12 227 J-13 227 L-13 224 N-11 224 M-06 227 N-07 229 N-05 224 L-03 227 B-04 230 J-02 223 D-14 224 C-06 223 P-12 229 G-13 227 M-02 230 N-09 230
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE: STATION: SALEM SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sump blockage TASK NUMBER: N1150900501 JPM NUMBER: 15-01 NRC Sim b ALTERNATE PATH: I x I KIA NUMBER: ~~~~~~~~___, 2.4.4 IMPORTANCE FACTOR: 4.5 4.7 APPLICABILITY: RO SRO EoD RO[KJ STAD SRO[KJ EVALUATION SETTING/METHOD: Simulator I Perform 2-EOP-LOCA-1, REV. 30, 2-EOP-LOCA-3, Rev. 30, 2-EOP-APPX-7, Rev. 0, OP-
REFERENCES:
AA-101-111-1003, Rev. 6 (All rev checked 5/9/16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 5-9-16 Instructor Validated By: D Cox I M Lutek Date: 8-22-16 SME or Instructor Approved By: Tra~~~-"1 Date: lo /o/v Approved By: Oper~ent Date: /o /1of r., ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE: STATION: SALEM SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sump blockage TASK NUMBER: N1150900501 JPM NUMBER: 15-01 NRC Sim b ALTERNATE PATH: I x I KIA NUMBER:
------ 2.4.4
-----4 IMPORTANCE FACTOR: 4.5 4.7 APPLICABILITY: RO SRO EOCJ ROL8] STACJ SROL8]
EVALUATION SETTING/METHOD: Simulator I Perform 2-EOP-LOCA-1, REV. 30, 2-EOP-LOCA-3, Rev. 30, 2-EOP-APPX-7, Rev. 0, OP-
REFERENCES:
AA-101-111-1003, Rev. 6 (All rev checked 5/9/16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 5-9-16 Instructor Validated By: D Cox I M Lutek Date: 8-22-16 SME or Instructor Approved By: Date: Training Department Approved By: Date: Operations Department ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE: NAME: ~~~~~~~~~~~~~~ DATE: ~~~~~~~~~~~~~~ SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sump blockage TASK NUMBER: N1150900501 SIMULATOR SETUP: RT-1 MALFS: VL0120 21SJ44 fails to position (0-100%) Severity 1.0 VL0121 22SJ44 fails to position (0-100%) Severity 2.0 I/O's: AA04 B LO 21SJ44 SIS SUMP VALVE OPEN: ON AAOS B LO 21SJ44 SIS SUMP VALVE OPEN: ON AAOS CLO 22SJ44 SIS SUMP VALVE CLOSED: OFF AA04 CLO 21SJ44 SIS SUMP VALVE CLOSED: OFF ET-1 KAA01TPN 21 RHR pump STOP PB, tied to delete VL0120 ET-3 KAA01TPN 21 RHR pump STOP PB, tied to delete VL0121 Mark up LOCA-3 up to step 21. INITIAL CONDITIONS:
- A LBLOCA has occurred on RCS loop 23.
- The crew has responded by performing TRIP-1 and LOCA-1.
- The crew is performing LOCA-3 with all AC buses energized from off-site power, and is waiting at step 21 for RWST lo-lo level alarm.
- All ECCS pumps are operating except 22 CS pump which was stopped at step 8.
INITIATING CUE: You are the Reactor Operator. Continue performing LOCA-3. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Secure all ECCS pumps.
- 2. Reestablish recirculation flow with ONE RHR pump and ONE charging OR SI pump.
PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block -*- - STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for
- NO. STANDARD S/U UNSAT evaluation)
Simulator Operator: Insert RT-1 to cause cavitation of both RHR pumps. Determines ECCS pumps are exhibiting signs of cavitation and recognizes entry into APPX-7 is warranted from Continuous Action Summary. Evaluator: IF the intention to stop the cavitating RHR pumps is voiced, THEN IMMEDIATELY CUE: The CRS directs you to implement APPX-7. (This is to prevent activation of Event Trigger when 21 RHR pump is stopped. CUE IF REQUIRED: The CRS directs you to implement APPX-7. Note: Operator may go to EOP-LOCA-5, but first step of LOCA-5 will direct performance of APPX-7. Use above cue if required in LOCA-5. Evaluator: Provide paper copy of 2-EOP-APPX-7. PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~ SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block --- - STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for
- NO. STANDARD S/U UNSAT evaluation)
APPX-7 CAUTION
- Any pump receiving suction from an RHR pump should be stopped before stopping the RHR pump.
- If any Charging Pump, SI Pump, or Containment Spray Pump loses suction or shows indication of cavitation, the pump should be stopped.
1 (CAS) MONITOR RHR Pump suction conditions: Determines BOTH RHR pumps exhibit signs
- a. CHECK NO indications of of cavitation, as well as ALL ECCS pumps cavitation. being supplied from RHR pumps.
- Pump Amps - stable and normal for discharge pressure and flow.
- Flow - stable and normal for discharge pressure.
- Discharge Pressure - stable and normal for flow
- Oscillations - none indicated PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for
- NO. STANDARD S/U UNSAT evaluation) 1.a a. PERFORM the following:
RNO 1. ENSURE 21 RH29 AND 22RH29 Places 21 RH29 and 22RH29 in AUTO. in AUTO.
- 2. STOP ANY Charging Pump or SI Stops 21 and 22 Charging pumps and 21 and Pump taking suction from 22 SI pumps.
affected RHR Pump(s)
- 3. IF indications of cavitation Determines pump cavitation is continuing, continue, THEN CLOSE 21 CS36 verifies 21 CS36 and 22CS36 are shut.
AND 22CS36, RHR TO CS VALVE.
- 4. IF indications of cavitation continue AND radiological conditions permit, THEN PERFORM the following: CUE: Radiation Protection has determined
- a. SEND an operator to release both RHR pump rooms to be unavailable for tags and restore CA to access due to high radiation levels.
RH18(s).
- b. CLOSE affected RH18(s).
- 5. IF indications of cavitation Determines RHR pump cavitation is continue, THEN REMOVE continuing, and removes lockout from 21 SJ49 LOCKOUT(s) AND CLOSE and 22SJ49 RHR TO COLD LEG and shuts affected SJ49(s), RHR TO COLD 21 SJ49 and 22SJ49.
LEG.
- 6. IF indications of cavitation Determines indications of cavitation continue, continue, THEN STOP affected and stops 21 and 22 RHR pump.
RHR Pump(s). Simulator Operator: Ensure ET-1 and ET-3 are TRUE when 21 and 22 RHR pump STOP PBs are depressed. This removes the SJ44 failures. PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment
- -- Sumo block STEP COMMENTS STEP
(*Denotes a Critical Step) EVAL (Required for
- NO. STANDARD S/U UNSAT evaluation) 2 CHECK ALL AVAILABLE CFCUs Determines all CFCUs are running in Low running in Low Speed. Speed.
- 3. SECURE Containment Spray flow path:
- a. STOP ALL Containment Spray Stops 21 CS pump.
Pumps.
- b. CHECK 21CS36 AND 22CS36 Determines 21 CS36 and 22CS36 are shut.
CLOSED.
- 4. (CAS) CHECK RWST level >1.2 feet. Determines RWST level is >1.2 feet.
- 5. ATTEMPT to establish RHR Pump suction:
- a. CHECK 21SJ44 AND 22SJ44 Determines 21 SJ44 AND 22SJ44 are open.
OPEN.
- b. CHECK AT LEAST ONE RHR Determines NEITHER RHR Pumps is running Pump running, with suction with suction aligned to Containment Sump.
aligned to Containment Sump. 5.b b. PERFORM the following: RNO 5.b 1. REMOVE LOCKOUT(s) AND Determines 21 SJ49 and 22SJ49 previously RNO CLOSE affected SJ49(s) RHR shut. DISCH TO COLD LEG. 5.b 2. ENSURE 21RH29 AND 22RH29 Determines 21 RH29 and 22RH29 are in RNO in AUTO AUTO.
- 5.b 3. START ONE RHR Pump. Starts 21 OR 22 RHR pump.
RNO PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block --- STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for
- NO. STANDARD S/U UNSAT evaluation) 5.b 4. IF indications of cavitation occur, Determines cavitation is NOT occurring.
RNO THEN STOP the running RHR pump, AND START the other RHR pump. 5.b 5. IF NO RHR Pumps can be run Determines RHR pump can be run without RNO without cavitation, THEN STOP cavitation. any running RHR Pumps AND GO TO Step 8.
- 5. c) CHECK 21RH29 AND 22RH29 Determines 21 RH29 and 22RH29 are in in AUTO. AUTO.
d) REMOVE LOCKOUT(s) AND Determines BOTH SJ49's are shut. CLOSE affected SJ49(s) RHR DISCH TO COLD LEG. e) CHECK ONLY ONE RHR Pump Determines only one RHR pumps is running. running with suction from Containment Sump.
- 6. ATTEMPT to establish Charging Pump or SI Pump flow in recirculation mode:
- a. CHECK Charging Pump and SI Determines running RHR pump SJ45 is open.
Pump suction aligned to running RHR pump.
- b. CHECK ONLY ONE Charging Determine NO Charging or SI pumps are Pump OR SI Pump running. running.
I PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~ SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block -- - - STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for
- NO. STANDARD S/U UNSAT evaluation)
- 6.b START OR STOP, Charging and SI Starts ONLY ONE Charging or SI pump.
RNO Pumps, as required, to obtain ONLY ONE pump running in recirculation Note: Per the NOTE at top of page 3, the alignment. intent of Step 6 is to start only a single pump (Charging or SI), and it is preferable to start a Charging pump. SAT performance of Step 6 does not require starting a Charging pump, just one of the 4 available charging or SI pumps. 6 c. CHECK Charging Pump or SI Determines Charging or SI pump is running in Pump running in recirculation recirculation alignment. alignment.
- d. GO TO Step 9 Terminate JPM when operator goes to Step 9.
PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
JOB PERFORMANCE MEASURE TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. ____ 1. Task description and number, JPM description and number are identified. ____ 2. Knowledge and Abilities (KIA) references are included. ____ 3. Performance location specified. (in-plant, control room, or simulator) ____ 4. Initial setup conditions are identified. - - - - 5. Initiating and terminating Cues are properly identified. ____ 6. Task standards identified and verified by SME review. ____ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*). ____ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date _ _ _ _ __ - - - - 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. - - - - 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: Date: - - - - - - SME/lnstructor: Date: - - - - - - SME/lnstructor: Date: - - - - - - - PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- A LBLOCA has occurred on RCS loop 23.
- The crew has responded by performing TRIP-1 and LOCA-1.
- The crew is performing LOCA-3 with all AC buses energized from off-site power, and is waiting at step 21 for RWST lo-lo level alarm.
- All ECCS pumps are operating except 22 CS pump which was stopped at step 8.
INITIATING CUE: You are the Reactor Operator. Continue performing LOCA-3. PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 TASK NUMBER: 1150070501 JPM NUMBER: 15-01 NRC Sim c ALTERNATE PATH: I x I KIA NUMBER: E09 EA1.1
~~~~~~~~~~--1 IMPORTANCE FACTOR: 3.5 3.5 APPLICABILITY: RO SRO EoD ROITJ STAD SRO[))
EVALUATION SETTING/METHOD: Simulator I Perform
REFERENCES:
2-EOP-TRIP-6 Rev. 30 (Rev checked 8-3-16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-3-16 Instructor Validated By: W Russell I D Cox SME or lnstructo~* rl.. Date: 8-22-16 10/(v Approved By: Train~nt Date: Approved By: O~ment Date: Jb//1/1(, ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 1of6
OPERATOR TRAINING PROGRAM JOB PERFOR11ANCE MEASURE NAME: DATE: SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 TASK NUMBER: 1150070501 SIMULATOR SETUP:
- 1. Trip RCP's
- 2. Perform EOP's to TRIP-6, Step 12- SI ACCUM ISOLATION
- 3. Override 24SJ54, Acc. Isolation Valve, close PB in the OFF position.
- 4. Place SPDS on Press/Temp Display
- 5. Put RCS Tcolds on trend on console.
- 6. Provide marked up copy of TRIP-6 INITIAL CONDITIONS:
A reactor trip occurred when a 500KV grid perturbation occurred, which also caused all RCPs to trip. The operating crew has progressed through the EOP's and is now in 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS. The RCPs will NOT be restarted. INITIATING CUE: Begin performing 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS at step 12. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Shut 21, 22, and 23 SJ54's.
- 2. Vent 24 Accumulator to atmospheric pressure.
PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 2 of 6
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~- JOB PERFORMANCE MEASURE 0 ATE: SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Reviews conditions and the marked up EOP-TRIP-6 Natural Circ Cooldown With RVLIS 12 IS RCS PRESSURE <1000 PSIG Verifies RCS pressure <1000 psig. 12.1 REMOVE LOCKOUT FROM 21-24SJ54 At 2RP4 Panel, selects VALVE OPERABLE on (ACCUMULATOR OUTLET VALVES) 21-24SJ54 ACCUMULATOR OUTLET VALVES LOCKOUT switches.
- 12.1 CLOSE 21-24SJ54 Depresses CLOSE PB on 21-24SJ54, noting that 21, 22, and 23SJ54 begin to stroke closed.
I 12.1 ARE 21-24SJ54 CLOSED Determines 24SJ54 is OPEN. i VENT ANY AFFECTED ACCUMULATORS: I 12.2
- MAINTAIN RCS PRESSURE Verifies RCS Pressure >24 Accumulator GREATER THAN ACCUMULATOR Pressure NITROGEN PRESSURE
*
- OPEN 2NT35 (N2 HOR VALVE) Opens 2NT35 (N2 HOR VALVE)
*
- OPEN AFFECTED SJ93 (N2 Opens 24SJ93 (N2 SUPPLY VALVE) and SUPPLY VAL VE) observes 24 Accumulator pressure lowering PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 3 of 6
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 12.3 WHEN ACCUMULATOR VENTING IS Cue: 24 Accumulator has been completely COMPLETE THEN CLOSE: vented and 24 Accumulator pressure is now reading ZERO.
*
- 2NT35 Closes 2NT35 N2 HOR VALVE
*
- 21 THRU 24 SJ93 Closes 24SJ93 N2 SUPPLY VAL VE Cue: JPM is complete PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 4 of 6
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, rev~lidate JPM using steps 8 and 11 below. (/ V lir----++-1.LJ.. Initial setup conditions are identified. (; __,,..._~..........--; 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*) .
. Verify the procedure referenced by this JPM mate es the most current revision of that procedure: Procedure Rev.~ Date I?' z:i. lo
. Pilot test the JPM:
- a. verify cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
_ _ _ _ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. _ _ _ _ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: /l? ~ SME/lnstructor: ~, LP/-- SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __ PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 5 of 6
INITIAL CONDITIONS: A reactor trip occurred when a 500KV grid perturbation occurred, which also caused all RCPs to trip. The operating crew has progressed through the EOP's and is now in 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS. The RCPs will NOT be restarted. INITIATING CUE: Begin performing 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS at step 12. PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 6 of 6
OPERATOR TRAINING PROGRAM JOB PERFORMANC.E MEASURE STATION: SALEM 1 & 2 SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents) TASK NUMBER: N 1150290501 JPM NUMBER: 15-01 NRC Sim d ALTERNATE PATH: I x I KIA NUMBER: EPE E05 EA1 .1
~---------\
IMPORTANCE FACTOR: 4.1 4.0 APPLICABILITY: RO SRO EOCJ ROCK] STAC] SROCK] EVALUATION SETTING/METHOD: Simulator - Perform
REFERENCES:
2-EOP-FRHS-1, Loss of Secondary Heat Sink, Rev.......a-C:(3 / .A 10/11)11,,, TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 6 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-2-16 Instructor Validated By: S Harris I J Pierce Date: 9-28-16 SME or Instructor rfl Approved By: h - - y VI., fk-- Traini~Department Approved By: Ope~ment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: SYSTEM: Emerqencv Operatinq Procedures TASK: TCAF a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents) TASK NUMBER: N1150290501 SIMULATOR SETUP: RX HEAD VENT KEYS ARE LOCATED IN SIM BOOTH IC-254 developed by: MSL rupture (10%)downstream of MSIVs. Fail all MSIVs open. All AFW pumps failed. Fail 2PR2 shut. Performed TRIP-1 through Step 20. SG WR levels <32%. INITIAL CONDITIONS:
- Unit 2 initiated a Rx trip from 100% power in response to a Main Steam line break at the mixing bottle.
- An automatic Safety Injection initiated.
- The Main Turbine failed to trip automatically, and was manually tripped from the control console.
- MSLI failed, and all MSIV's remain open.
- All AFW flow has been lost. - -- - - ------ ------------~--- -- -- ---------
- EOP-TRIP-1 was performed and a transition to FRHS-1, Loss of Secondary Heat Sink was made at Step 20.1 INITIATING CUE:
You are the Reactor Operator. Perform FRHS-1 starting at Step 1. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Stop ALL RCPs.
- 2. Open 2PR1.
- 3. Open Rx Head Vent Valves 2RC40-2RC43.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink {Initiate Bleed and Feed with SI pumps and Rx Head Vents) STEP COMMENTS STEP {* Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 1 IS TOTAL AFW FLOW LESS THAN Determines it was not operator action which 22E04 LB/HR DUE TO OPERATOR caused total AFW flow to be less than 22E04 ACTIONS lb/hr.
2 IF AT LEAST ONE INTACT OR Recognizes ALL SGs are faulted. RUPTURED SG IS AVAILABLE, THEN DO NOT FEED A FAULTED SG 3 IS RCS PRESSURE GREATER THAN Checks RCS pressure on control console ANY INTACT OR RUPTURED SG and determines it is greater than all SG PRESSURE pressures checked on control console. 3.1 ARE RCS T-HOTS GREATER THAN Checks RCS Thot indication on control 350°F console and determines that RCS Thats are greater than 350°F. 4 !E WR LEVELS IN AT LEAST TWO SG's Determines at least 2 SG WR levels < 32% ARE LESS THAN 32% (37% ADVERSE), and goes to Step 21. THEN IMMEDIATELY GO TO STEP 21 TO INITIATE RCS BLEED AND FEED PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents) STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 21 CAUTION TO ESTABLISH RCS HEAT REMOVAL Reads Step.
BY RCS BLEED AND FEED, STEPS 24 THRU 29 MUST BE PERFORMED QUICKLY AND WITHOUT INTERRUPTION
- 23 STOP ALL RCPS Depresses STOP PB for 21-24 RCPs and verifies green stop light illuminates and red start light extinguishes.
22 INITIATE SI Uses Safeguards key and initiates SI on at least one train of Safeguards initiation. 23 ARE SI VALVES IN SAFEGUARDS Checks 2RP4 and/or console indication to POSITION determine that all valves listed in Table Bare in Safeguards position. Table B valves are: 2SJ4 OPEN BIT INLET 2SJ5 OPEN BIT INLET 2SJ12 OPEN BIT OUTLET 2SJ13 OPEN BIT OUTLET 2CV68 CLOSED CHARGING DISCHARGE 2CV69 CLOSED CHARGING DISCHARGE (continued next paqe) PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: - - - - - - - - - SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents) STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Table B Valves (can't}: 21-24SJ54 OPEN ACCUMULATOR OUTLET 2SJ1 OPEN RWST TO CHARGING 2SJ2 OPEN RWST TO CHARGING 2CV40 CLOSED DISCHARGE STOP 2CV41 CLOSED DISCHARGE STOP 23.1 IS 21 OR 22 CHARGING PUMP Checks control console and determines 21 RUNNING and 22 charging pump are running. IS BIT FLOW ESTABLISHED Checks console and determines BIT flow is established. 23.2 IS ANY SI PUMP RUNNING Checks control console and determines 21 and 22 SI pumps are running. ARE VALVES IN TABLE COPEN FOR Checks control console indication for valves AT LEAST ONE RUNNING SI PUMP listed in Table C and determines the valves are open for at least one running SI pump. Table C valves are: 21/22 SI PUMPS 2SJ30 (FROM RWST) 21/22SJ33 (SI PUMP SUCTION) 2SJ135 (COLD LEG DISCHARGE) 21/22SJ134 (COLD LEG DISCHARGE) PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 8
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents) STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
ARE ALL CHARGING AND SI PUMPS Determines all charging and SI pumps are RUNNING AND ALIGNED TO DELIVER running and aligned to deliver flow. FLOW 24 OPEN BOTH PZR PORV STOP VALVES Checks control console and determines BOTH 2PR6 and 2PR7 PORV STOP VALVES are open. Places 2PR1 in manual and depresses 2PR1
- OPEN -BOTH
- PZR PORVS PZR PORV open PB and verifies green closed light extinguishes and red open light illuminates.
Places 2PR2 in manual and depresses 2PR2 PZR PORV open PB. and reports that 2PR2 will not open. 24.1 ARE BOTH PZR PORV STOP VALVES Checks control console and determines BOTH OPEN 2PR6 and 2PR7 PORV STOP VALVES are open. ARE BOTH PZR PORVS OPEN Determines 2PR2 PZR PORV is not open. Inserts key into each 2RC40 THRU 2RC43
- 24.2 OPEN 2RC40 THRU 2RC43 (REACTOR HEAD VENTS) (REACTOR HEAD VENTS) switch on 2RP3, turns to open, and verifies each valve opens.
Terminate JPM when operator has opened 2RC40 thru 2RC43 Reactor Head Vents. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 8
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. v I IY ~ 1. Task description and number, JPM description and number are identified.
./ ~ ~ 2. Knowledge and Abilities (KIA) references are included.
I' l,t ~ 3. Performance location specified. (in-plant, control room, or simulator) tr I ,!')- ~ 4. Initial setup conditions are identified. I "),,, ~ 5. Initiating and terminating Cues are properly identified.
/
./ 7 \ 6. Task standards identified and verified by SME review.
v I 1" '1 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
}.,, \ 8. Verify the procedure referenced by this JPM matches the most current revision of
"\ that procedure: Procedure Rev. )0 Date 'T/2-1/1"
,V ~ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor:
~. ~l~di-r~ Date: 7ft '1)£ SME/lnstructor: 5
- Ukrn' ~ 'Jvjk Date: ci L{e */1t:?
SM E/I nstru ct or: Date: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8
INITIAL CONDITIONS:
- Unit 2 initiated a Rx trip from 100% power in response to a Main Steam line break at the mixing bottle.
- An automatic Safety Injection initiated.
- The Main Turbine failed to trip automatically, and was manually tripped from the control console.
- MSLI failed, and all MSIV's remain open.
- All AFW flow has been lost.
- EOP-TRIP-1 was performed and a transition to FRHS-1, Loss of Secondary Heat Sink was made at Step 20.1 INITIATING CUE:
You are the Reactor Operator. Perform FRHS-1 starting at Step 1. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 8
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: Salem Generating Station SYSTEM: Emergency Operating Procedures TASK: TCAF Total Loss of All Service Water TASK NUMBER: N1140380401 JPM NUMBER: 15-01 NRC Sim e ALTERNATE PATH: ITJ KIA NUMBER: IMPORTANCE FACTOR:
- - - -076 A2.01
-- - -3.7
--i
- -3.5- - SRO APPLICABILITY: RO EOD ROCK] STAD SROCK]
EVALUATION SETTING/METHOD: Simulator I Perform S2.0P-AB.SW-0001, Loss of SW Header Pressure, Rev. 16 S2.0P-AB.SW-0005, Loss of All Service Water Rev. 4 S2.0P-AR.ZZ-0002, Overhead Annunciator Window B Rev. 36
REFERENCES:
(All rev checked 8-3-16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 3-23-16 Instructor Validated By: W Russell I D Cox Date: 8-22-16 SME or Instructor Approved By: Date: Approved By: Date: ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
. , __.~ OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~
DATE: ~~~~~~~~~~~~~~ SYSTEM: Abnormal Operating Procedures TASK: TCAF a Total Loss of All Service Water TASK: N1140380401 Simulator Setup: IC-255 100% power. 21 charging pump in service 2 SW bay removed from service IAW S2.0P-AB.SW-003, Service Water Bay Leak. All 4 bay pumps in service. S2.0P-AB.SW-003 out and marked up. MALFS: Tied to RT-1 24 SW pump trip 25 SW pump trip 26 SW pump trip INITIAL CONDITIONS: Unit 2 is operating at 100% power. 21 charging pump is in service. 23 charging pump is aligned for Normal operation IAW Section 4.1 of S2.0P-SO.CVC-0002, Charging Pump Operation.
- 2 SW Bay has been removed from service to isolate a leak in the bay IAW S2.0P-AB.SW-0003, Service Water Bay Leak.
All #4 Service Water Bay pumps are in service. INITIATING CUE: You are the Reactor Operator. Respond to all indications and alarms. Successful Completion Criteria
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made Task Standard for Successful Completion:
- 1. Trip the Rx
- 2. Stop all RCPs prior to or within 3 minutes of any RCP bearing temperature reaching 175°F or any other RCP trip criteria being met in S2.0P-AB.RCP-001.
- 3. Place 23 Charging pump in service.
- 4. Reduce operating CCW pumps to one.
PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR TR,....* ~ING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: SYSTEM: Abnormal Operating Procedures TASK: TCAF a Loss of all Service Water
.*: STEP'< .... :.STEP STANDARD .EVAL . COMMENTS
.. .:-~.' :.*.
*<*No~ ..*,:.
l, ; .. . ..** S/U Simulator Operator: Insert RT-1 after operator assumes watch. This trips all 4 Bay SW pumps. Recognizes that all SW pumps have tripped. Enters S2.0P-AB.SW-0005, Loss of All Service Water directly, or responds IAW ARP for low service water header pressures. ARP steps are after AB.SW-5 steps here in JPM. AB.SW-1 steps are after ARP steps here in JPM.
- AB.SW-5 TRIP the reactor, AND CONFIRM the Trips the Rx using either trip handle, and 3.1 Reactor Trip. confirms the Rx trip.
- AB.SW-5 STOP all RCPs. Depresses stop PBs for all RCPs.
3.2 GO TO 2-EOP-TRIP-1, Reactor Trip or Cue: You are to continue with S2.0P-AB.SW-Safety Injection, AND CONTINUE with this 0005 while other operators perform TRIP-1. procedure. Evaluator: Silence OHA's as not associated with loss of SW. AB.SW-5 CLOSE the following valves to isolate
3.4 letdown
*
- 2CV3, 45 GPM ORIFACE Shuts the open orifice isolation valve and PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR TR1-*u1-JING PROGRAM JOB PERFORMANCE MEASURE
.ST.EP '.> .* .STEP STANDARD EVAL COMMENTS
.:.* <No. .:. :> } **s1u . :: *.;' <
- 2CV4, 75 GPM ORIFICE ensures the remaining orifice isolation valves
- 2CV5, 75 GPM ORIFICE are shut.
AB.SW-5 INITIATE Attachment 1, Continuous Action Initiates Attachment 1, Continuous Action 3.5 Summary. Summary. AB.SW-5 3.6 lE a Centrifugal Charging Pump is in Determines a centrifugal charging pump is in service AND the 23 Charging Pump is service and 23 charging pump is immediately IMMEDIATELY available to be placed in available to be placed in service. service, THEN PERFORM the following: A. VERIFY ALL 21-24 RCP Seal Inlet Temperatures <225°F as indicated on 2CC1 or the Plant Computer B. ENSURE 23 Charging Pump is aligned for Normal Operation IAW S2.0P-SO.CVC-0002(Q) Charging Pump Operation. C. PLACE 23 Charging Pump in MANUAL.
- D. PLACE Charging Master Flow Controller in MANUAL.
- E. SET 23 Charging Pump Speed Demand to 10-12%.
- F. START 23 Charging Pump AND immediately INCREASE Speed Demand to approximately 20% to couple pump.
G. ADJUST 23 Charging Pump Speed Demand to obtain desired flow. H. ENSURE Seal Injection Flow 6-12 gpm to each Reactor Coolant Pump not to exceed 40 gpm total Seal PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR Tk.,....NING PROGRAM JOB PERFORMANCE MEASURE STEP.. STEP STANDARD EVAL COMMENTS
- '°<No; ..* S/U .*.
Injection Flow.
- I. STOP 21 and 22 Centrifugal Charging Pumps.
J. DISPATCH an Operator to monitor operation of 23 Charging Pump due to the potential for rising Component Cooling Water System temperature. AB.SW-5 lE a Centrifugal Charging Pump is in Determines a Centrifugal Charging Pump is not 3.7 service AND the 23 Charging Pump is NOT in service IMMEDIATELY available to be placed in service, THEN STOP 21 and 22 Centrifugal Charging Pumps. AB.SW-5 PLACE 2CC131, RCP THERMAL Places 2CC131, RCP THERMAL BARRIER, in 3.8 BARRIER, in MANUAL. MANUAL. AB.SW-5 PLACE Component Cooling Pumps in Places all Component Cooling Pumps in
- 3.9 MANUAL AND REDUCE the number of MANUAL AND stops all but one Component operating Component Cooling Water Cooling Water Pumps.
Pumps to one. Terminate JPM. ARP 3.1 VERIFY header low pressure using Determines header pressure is low. OHA's 2PA5373 on 2CC1. B-13, 14 3.2 IF low pressure conditions exists due to Determines loss of SW system pressure does known system configuration, THEN GO TO not conditions exists due to known system S2.0P-S0.8W-0001 (Q) Service water configuration. Pump operation, to adjust system pressure. 3.3 lE a valid low pressure condition exists, Determines valid low pressure condition exists, THEN GO TO 82.0P-AB.8W-0001(Q), and goes to 82.0P-AB.8W-0001, Loss of PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR Th...*~ING PROGRAM JOB PERFORMANCE MEASURE
,, ', .STEP, "' STEP STANDARD EVAL* . .COMMENTS
* 'No.>..
'5/U .***
Loss of Service Water Header Pressure. Service Water Header Pressure. AB.SW-1 INITIATE Attachment 1, Continuous Action Initiates Attachment 1, Continuous Action 3.1 Summary. Summary. AB.SW-1 Is there indication of a leak in a Service Determines there is no unisolated leak (SW 3.2 Water Bay per the following? Bay 2 has been isolated)
- Visual indication
- OHA B-29, 21-23 SW PMP SMP AREA LVL HI
- OHA B-30, 24-26 SW PMP SMP AREA LVL HI AB.SW-1 START Service Water pumps to maintain Determines no SW pumps are available to be 3.4 header pressure between 95 and 105 psig. started.
AB.SW-1 Is there a leak or valve malfunction on the Determines the cause of low SW header 3.5 turbine header as indicated by any of the pressure is from loss of all SW pumps. following? AB.SW-1 Are both nuclear Service Water headers in Determines neither nuclear SW header is in 3.6 service? service. AB.SW-1 IF the Unit is in a Service Water Header Determines the Unit is not in a Service Water 3.7 Outage ... Header Outage. AB.SW-1 IF the Unit is NOT in a Service Water Determines the Unit is not in a Service Water 3.8 Header Outage, THEN GO TO S2.0P- Header Outage, and goes to S2.0P-AB,SW-AB.SW-0005 (Q), Loss of All Service Water 0005. TERMINATING CUE: After reduction of CCW pumps to one, terminate JPM. PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 5 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. \). ,l/Jl?1 ~ 1. Task description and number, JPM description and number are identified. If' ;Wf! , 2. Knowledge and Abilities (KIA) references are included.
'-P- ,/~/ 3. Performance location specified. (in-plant, control room, or simulator)
V/ 4. Initial setup conditions are identified.
\f / 5. Initiating and terminating Cues are properly identified. \r./
- 6. Task standards identified and verified by SME review.
~8. Verify the procedure referenced by this JPM matches the most current revision of p that procedure: Procedure Rev. ':! Date [/12/iro uJ1\ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: SME/lnstructor: SME/lnstructor: Date: - - - - - -
------------~
PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Unit 2 is operating at 100% power. 21 charging pump is in service. 23 charging pump is aligned for Normal operation IAW Section 4.1 of S2.0P-SO.CVC-0002, Charging Pump Operation.
- 2 SW Bay has been removed from service to isolate a leak in the bay IAW S2.0P-AB.SW-0003, Service Water Bay Leak.
All #4 Service Water Bay pumps are in service. INITIATING CUE: You are the Reactor Operator. Respond to all indications and alarms. PSEG Confidential- Possession Requires Specific Approval from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer and PRT TASK: Adjust PRT level and pressure TASK NUMBER: N0100110101 JPM NUMBER: 15-01 NRC Sim f ALTERNATE PATH: I I K/A NUMBER: ~~~~~~~~~~--< 007 A4.04 IMPORTANCE FACTOR: 2.6 2.6 APPLICABILITY: RO SRO EoO RO[D STAD SRO[D EVALUATION SETTING/METHOD: Simulator I Perform
REFERENCES:
S2.0P-SO.PZR-0003, Rev. 15 (checked 8-5-16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: M Lutek I W Russell SME or Instructor i, Date: 8-22-16 Tra~tn1* 4 10 Approved By: Date: / /'-' Approved By: O~artment Date: /tJ/, ,;;(,
- ACTUAL JPM COMPLETION TIME:
ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 1 of7
OPERA TOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: SYSTEM: Pressurizer and PRT TASK: Adjust PRT level and pressure TASK NUMBER: N0450040101 SIMULATOR SETUP: 15-01 NRC IC-256 PRT level 56.2% (or low enough for the PRT Hi-Lo Lvl alarm to be locked in) with PRT pressure 9.8 psig. Paper copies of procedure needed. INITIAL CONDITIONS: Unit 2 is at 100% power. 2PR1 is leaking and 2PR6 is shut with power applied. Operators have been attempting to determine the leak rate through 2PR1. Console alarm PRT Level Hi-Lo is in alarm (lo) with PRT level at 56.2%. INITIATING CUE: You are directed to raise PRT level to 60% IAW S2.0P-SO.PZR-0003, Pressurizer Relief Tank Operation, Section 5.1. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion:
- 1. Raise PRT level to > 60% while maintaining PRT pressure ~10 psig.
PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 2 of7
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: PZR and PRT TASK: Adjust PRT level and pressure STEP STEP EVAL COMMENTS
- NO. (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT Evaluation)
Provide marked up paper copy of S2.0P- Reviews Precautions and Limitations. SO.PZR-0003. 5.1.1 IF PRT level is low, THEN PERFORM the Note: The step for reducing PRT pressure following: may be performed prior to raising level, since pressure is close to the maximum allowed. (See Step 5.1.1.D) IF PRT pressure reduction is performed first, THEN Cue if PRT pressure is lowered past 7 psig ... " CRS states that the pressure reduction is sufficient to allow filling of the PRT now."
- 5.1.1.A IF required, THEN START 21 or 22 Primary Depresses start pushbutton for 22 Primary Water Pump. Water Pump. (aligned for manual start)
OR Places 21 Primary Water Pump in manual and depresses start pushbutton for 21 Primary Water Pump. IF operator does not start a Primary Water Pump and will gravity feed to makeup to the PRT, THEN Cue: The CRS directs you to use a Primary Water pump to makeup to the PRT. PSEG Restricted-Possession Requires Specific Pem1ission from Nuclear Training Page 3 of7
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~ SYSTEM: PZR and PRT TASK: Adjust PRT level and pressure STEP STEP EVAL COMMENTS
- NO. (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT Evaluation)
- 5.1.1.B OPEN 2WR80, CONT PRI WATER STOP. Depresses open pushbutton for 2WR80 CONT PRI WATER STOP and verifies open light lit.
- 5.1.1.C OPEN 2WR82, PRT WATER SUPPLY. Depresses open pushbutton for 2WR82, PRT WATER SUPPLY and verifies open light lit.
- 5.1.1.D lE PRT pressure approaches 10 psig, THEN Depresses open pushbutton for 2PR15, OPEN 2PR15, VENT, as necessary, to maintain VENT Qrior to PRT Qressure rising PRT pressure at >3 psig and ~10 psig. above 10.0 QSig, and depresses close pushbutton prior to PRT pressure lowering below 3.1 psig.
Note: IF PRT Hi Pressure alarm is received, it prevents the 2PR15 from opening, and pressure cannot be reduced. When operator has demonstrated that they can raise level without exceeding 10 psig, then Cue: PRT level is now 60% PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 4 of7
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~ SYSTEM: PZR and PRT TASK: Adjust PRT level and pressure STEP STEP EVAL COMMENTS
- NO. (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT Evaluation) 5.1.1.E When PRT level increases to between 59% and When PRT level rises to 60%:
- 86%:
Closes 2WR80, CONT PRI WATER
- 1. CLOSE 2WR80, CONT PRI WATER STOP.
STOP.
- 2. CLOSE 2WR82, PRT WATER SUPPLY Closes 2WR82, PRT WATER SUPPLY.
- 3. ENSURE 2PR15, VENT is closed. Ensures 2PR15, VENT is closed.
Depresses stop pushbutton for running
- 4. IF Primary Water Pump is in service Primary Water Pump. IF 21 Primary JAW Step 5.1.1.A, AND is NOT required to be in service for any other reason, Water pump was used to fill PRT, THEN places 21 or 22 Primary Water pump in THEN STOP running Primary Water auto.
Pump. 5.1.1.F DIRECT a second Operator to perform an Independent Verification of component position in Attachment 1, Section 1.0 TERMINATING CUE: After operator reads Step 5.1.1.F, state JPM is complete. PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 5 of7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. \,\ I (r l//h1. Task description and number, JPM description and number are identified.
\f. / a- W, 2. Knowledge and Abilities {KIA) references are included.
IA / a-- l#IJ 3. Performance location specified. (in-plant, control room, or simulator)
\,.- / d-' \.6?J 4. Initial setup conditions are identified. ~ / a-- lJ/115. Initiating and terminating Cues are properly identified.
~ / &"""' lift\. 6. Task standards identified and verified by SME review.
\/ r vi\ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
}" ~ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.~ Date S/7-"L/111
}- LI/I\ 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor:
~L'-'tl!ll-- J SME/lnstructor:_hl,_.._,__,
+/-
~~~---=__.__ ___.R_:;;;;L__s-=--~__,*
Date: Date: SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __ PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 6 of 7
OPERATOR TRAINING PROGRAM JOB PERFORJ.'1ANCE MEASURE INITIAL CONDITIONS: Unit 2 is at 100% power. 2PR1 is leaking and 2PR6 is shut with power applied. Operators have been attempting to determine the leak rate through 2PR1. Console alarm PRT Level Hi-Lo is in alarm (lo) with PRT level at 56.2%. INITIATING CUE: You are directed to raise PRT level to 60% IAW S2.0P-SO.PZR-0003, Pressurizer Relief Tank Operation, Section 5.1. PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 7 of 7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE 3TATION: Salem Generating Station SYSTEM: Emergency Operating Procedures TASK: Perform Actions for a Loss of All AC Power (Energize a 4KV Vital Bus from a Station Power Transformer) TASK NUMBER: 1150140501 JPM NUMBER: 15-01 NRC Sim g ALTERNATE PATH: I I KIA NUMBER: EPE 055 EA 1.07
~~~~~~~~--;
IMPORTANCE FACTOR: 4.3 4.5 APPLICABILITY: RO SRO EOD RO[ZJ STAD SRO[ZJ EVALUATION SETTING/METHOD: Simulator I Perform
REFERENCES:
S2.0P-SO.DG-0001, Rev. 39, S2.0P-S0.4KV-0001, Rev. 32 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 4-18-16 Instructor Validated By: Hancock I Russell Date: 8-16-16 SME or Instructor Approved By: rraZm*nt Date: 10/y{v Approved By: Date: /6j1/1~ Operbsentative ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 1 of 7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: SYSTEM: Emergency Operating Procedures TASK: Perform Actions for a Loss of All AC Power (Energize a 4KV Vital Bus from a Station Power Transformer) TASK 1150140501 NUMBER: Simulator Setup: IC-256 (with 24ASO racked down and control power off) INITIAL CONDITIONS:
- 1. Unit 2 is recovering from a loss of all AC Power.
- 2. The crew is performing step 16 of 2-EOP-LOPA-1.
- 3. 23 AFW pump is supplying all required AFW flow.
- 4. 2A EOG was started first and is providing power to 2A Vital Bus
- 5. 2B EOG was just started and is powering 2B 4KV vital bus.
- 6. 2C 4KV Vital Bus remains deenergized and unavailable.
- 7. 24 Station Power Transformer (SPT) has just been energized.
- 8. With 24 SPT now available, the CRS has directed that S2.0P-SO.DG-0001 Section 5.8 and S2.0P-S0.4KV-0001 Section 5.3.6 be utilized to swap 2A Vital Bus from 2A EOG to 24 SPT.
INITIATING CUE: You are the Control Board Operator. Complete Section 5.8 of S2.0P-SO.DG-0001, and then utilize Section 5.3.6 of S2.0P-S0.4KV-0001 to restore power to 2A Vital Bus from 24 SPT. Prerequisites and Precautions and Limitations have been reviewed and signed. Successful Completion Criteria
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made Task Standard for Successful Completion:
- Energize 2A 4KV vital bus using 24 SPT PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 2 of 7
I OPERATOR TRn1t\llNG PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: SYSTEM: Emergency Operating Procedures TASK: Perform Actions for a Loss of All AC Power (Energize a 4KV Vital Bus from a Station Power Transformer) I STEP STEP STA~DARD EVAL COMMENTS No. (* denotes critical task) I S/U Provide marked up copies of S2.0P-SO.DG-0001 and S2.0P-S0.4KV-0001. I SO.DG-1 IF 2A EOG is paralleled on 2A 4KV Vital 1 Determines 2A Diesel Generator is not 5.8.1 Bus .... paralleled on 2A 4KV Vital Bus. 5.8.2 IF 2A Vital Bus is isolated and energized from 2A EOG, THEN: Places redundant equipment in service as
- PLACE redundant equipment in needed: I service as necessary to support deenergizing 2A Vital Bus
- 22 CCW pump Note: 1 SW pump with the TGA isolated is
- STOP all 2A Vital Bus loads using sufficient for maintaining SW header pressure I
Attachment 1 I Stops the following equipment (if running):
- 21 CCW pump1
- 21 SW pump I I
- 21 CFCU !
- 21 Aux Building Exhaust Fan
- 21 SWGR Room Supply Fan
- 21 SWGR Room Exhaust Fan
- 21 BAT pump i
- 21 FHB Exhaust Fan
- 21 AFW pump
- 21 SI I 21 CS pumps I
I PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 3 of 7 I
OPERATOR Th. ***"ING PROGRAM JOB PERFORMANCE MEASURE STEP STEP EVAL STANDARD COMMENTS No. (* denotes critical task) S/U 5.8.3 OPEN 2A DIESEL GENERATOR BREAKER Opens 2A DIESEL GENERATOR BREAKER by performing one of the following: by performing one ofjthe following:
- OPEN 2AD1AX60, 2A DIESEL
- Directs opening of 2AD1AX6D, 2A GENERATOR BREAKER (64' Swgr DIESEL GENERATOR BREAKER (64' Rm), or Swgr Rm), or,
- PRESS 2A BREAKER OPEN
- Presses 2A BREAKER OPEN pushbutton (2CC3), or pushbutton (2CC3), or
- PLACE 2A-DF-GCP-3, GENERATOR
- Directs placing 2A-DF-GCP-3, CIRCUIT (BCS), to TRIP (2A DIG GENERATOR CIRCUIT (BCS), to I
Control Panel). TRIP (2A D/Gi Control Panel). 5.8.4 ALLOW Diesel to run unloaded for~ 3 Cue: 2A EOG will bJ shutdown by local minutes prior to stopping the EOG. operator. I 5.8.5 If diesel unloading ... Determines step is N/A S0.4KV-1 IF 2A 4KV Vital Bus is to be energized from 5.3.6 24 SPT,THEN: I I 5.3.6.A Direct NEO to RACK UP 2AD1AX24ASD, Contacts NEO and directs them to rack up 24 STATION POWER TRANSFORMER 2AD1AX24ASD, 24 STATION POWER INFEED BREAKER (64' Swgr Rm). TRANSFORMER INF:EED BREAKER. I Simulator Operator:! MODIFY REMOTE cn?1n to ON, then report 2AD1AX24ASD, 24
-. -~~,..,..,~ACR INFEED
OPERATOR T"-... NING PROGRAM JOB PERFORMANCE MEASURE 5.3.6.C PERFORM the following:
- 1. PRESS AND HOLD control console Presses and Holds control console 24ASD 24ASD CLOSE pushbutton. CLOSE pushbutton, then releases pushbutton
- 2. RELEASE pushbutton when 24ASD when 24ASD indicates closed.
indicates CLOSED.
- 3. ENSURE the following: Checks Console bezel 24ASD MIMIC BUS
- a. Console bezel 24ASD MIMIC BUS INTLK INTLK CLOSE SELECTION is extinguished.
CLOSE SELECTION is extinguished.
- b. 2A 4KV Vital Bus voltage is 4.275 -
4.336KV (normal) OR 4.330 - 4.417KV (single source of off-site Determines 2A Vital Bus voltage is 4.275 - power). 4.385KV (single source of off-site power.
- c. OHA J-17, 2A 4KV VTL BUS Determines OHA J-17 2A 4KV VTL BUS UNDRVOLT, is clear. UNDRVOLT is clear.
Terminate JPM. PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 5 of 7 I I
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. V. / ;:J- 1. Task description and number, JPM description and number are identified.
' ./ ().., 2. Knowledge and Abilities (KIA) references are included .
. A v L2- 3. Performance location specified. (in-plant, control room, or simulator) v ~ 4. Initial setup conditions are identified.
v ~ 5. Initiating and terminating Cues are properly identified. v / ~ 6. Task standards identified and verified by SME review.
*v - 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
c::r that procedure: Procedure Rev. 2 V ---0..=:- 8. Verify the procedure referenced tC)5 JPM matche: the most current revision of
, Date <3/JtJlllo fJ 9. Pilot test the JPM: .] z_
~ a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
--~::._ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.
_ ___,__ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.
~nstructo?fi;,~~ Date: $> JH /1,
~lnstructor..=~t/ Date: .SJ I &/J 6 I '
SMqLnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: -~-~-- PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 6 of 7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- 1. Unit 2 is recovering from a loss of all AC Power.
- 2. The crew is performing step 16 of 2-EOP-LOPA-1.
- 3. 23 AFW pump is supplying all required AFW flow.
- 4. 2A EOG was started first and is providing power to 2A Vital Bus
- 5. 2B EOG was just started and is powering 2B 4KV vital bus.
- 6. 2C 4KV Vital Bus remains deenergized and unavailable.
- 7. 24 Station Power Transformer (SPT) has just been energized.
- 8. With 24 SPT now available, the CRS has directed that S2.0P-SO.OG-0001 Section 5.8 and S2.0P-S0.4KV-0001 Section 5.3.6 be utilized to swap 2A Vital Bus from 2A EOG to 24 SPT.
INITIATING CUE: You arethe Control-Soard Operator.--complete Section 5.8 of S2.0P-SO.OG-0001, and then utilize Section 5.3.6 of S2.0P-S0.4KV-0001 to restore power to 2A Vital Bus from 24 SPT. Prerequisites and Precautions and Limitations have been reviewed and signed. PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 7 of 7
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air TASK NUMBER: N1140070401 JPM NUMBER: 15-01 NRC Sim h ALTERNATE PATH: I x I KIA NUMBER: APE 065 AA2.06
~~~~~~~~~-i IMPORTANCE FACTOR: 3.6 4.2 APPLICABILITY: RO SRO EoD ROITJ STAD SROITJ EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-AB.CA-0001, Rev. 21 Loss of Control Air (both rev checked 8-5-16)
REFERENCES:
S2.0P-AR.ZZ-0011, Rev. 60, pages 118-128 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: M Lutek I W Russell Date: 8-22-16 SME or Instructor ~ Approved By: Trai~.;.:v Date: Approved By: Date: Operbrtment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 13
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~ DATE: ~~~~~~~~~~~~~~ SYSTEM: Loss of Control air TASK: TCAF Loss of Control Air TASK NUMBER: N1140070401 SIMULATOR SETUP: Check 2WG41 is open 15-01 NRC IC-258 RT-1 MALF: CA0221 #2 STATION AIR CMPRSSR TRIP REM: CA13D LOCKOUT #1 STATION AIR CMPRSR, Delay 1:30 1/0 : AQ01 OVLO COMP 1 TROUBLE ALARM, Fin Val: ON, Delay 1:30 Other setup: REM: CA15D LOCKOUT #3 STATION AIR CMPRSR CA11D #1 EMERGENCY AIR COMPRSR IN AUTO Fin Val: MANUAL CA 12M #1 EMRGENCY AIR CMPRSR SWITCH Fin Val: Stop 1/0 : AQ01 OVLO COMP 3 TROUBLE ALARM, Fin Val: ON INITIAL CONDITIONS:
- Unit 2 is operating at 100% power.
- A WG release is in progress from 21 GOT.
* #3 SAC is CIT for scheduled maintenance.
- Unit 1 is operating at 100% power.
INITIATING CUE: You are the Unit 2 Reactor Operator. Respond to all indications and alarms. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Isolate Letdown
- 2. Terminate Gaseous Release
- 3. Trip the Rx prior to auto trip on lo lo SG NR level.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2of13
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Note: The #1 and #3 Compressor Trouble alarms on 2CC1 do NOT have audible or flash capabilities (S2.0P-AR.ZZ-0011 page 120). Simulator Operator: Insert RT-1 after operator assumes watch. Determines #2 Station Air Compressor (SAC) has tripped, and the Unit 2 Emergency Control Air Compressor (ECAC) has automatically started. Note: All 3 SAC supply breakers open is an auto start signal for both ECAC's. The Unit 2 ECAC will auto start, (Unit 1 will not). By design, the ECAC will not load until its control air header pressure lowers to 85 psig. 2A control air header is supplied from #2 ECAC, 28 control air header is supplied from #1 ECAC. Note: The next-to-load SAC (follow) will not immediately start. It requires Station Air header pressure to drop to 5 psig below the follow setpoint (105 psig) for- 5 seconds. Refers to the S2.0P-AR.ZZ-0011, Control Console 2CC1, ARP for COM PR 2 TROUBLE. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3of13
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE 0 ATE: SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
ARP 3.1 IF SAC 2 trips, THEN: A. COORDINATE (as necessary) Coordinates with Unit 1 to start at least one with Unit 1 SAC IAW SC.OP-SO.SA-0001 (Z), Station Air B. ENSURE operating OR START at System Operation. least one SAC IAW SC.OP-SO.SA-0001(Z), Station Air Cue when contacted as Unit 1: Unit 1 will System Operation. ensure #1 SAC is placed in service. ARP 3.2 IF AT ANY TIME Station Air pressure GOES TO S2.0P-AB.CA-0001(Q), Loss of cannot be maintained _:::100 psig, THEN Control Air, when Station Air pressure lowers GO TO S2.0P-AB.CA-0001 (Q), Loss of to 100 psig if AB not entered previously. Control Air. Simulator Operator: Ensure #1 SAC locks out 1:30 after insertion of RT-1, then announce twice on plant page: "#1 Station Air Compressor Trip." Recognizes that no SAC's are running, and enters S2.0P-AB.CA-0001 if not entered previously. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4of13
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Note: Approximate event times are listed below from insertion of RT-1. 1 min - 1 SAC auto starts. 1 min 30 sec - 1 SAC trips. 3 min 50 sec- 2 ECAC begins loading. 4 min 10 sec - 28 Control Air header pressure reaches 80 PSIG, and SA low pressure alarm. 4 min 25 sec - CA low pressure alarm. 6.5 min 24BF19 Feed Reg Valves begin I closing. 7 min 10 sec- G-15 OHA ADFCS TRBL. AB.CA INITIATE Attachment 1, Continuous Initiates Attachment 1, Continuous Action 3.1 Action Summary. Summary. Cue IF Required: If CAS Step 8.0 action is being taken to refer to Attachment 2 for valve fail positions and for further action to be taken, then: Cue: The CRS will refer to Attachment 2 3.2 EITHER of the following conditions exist? Determines all SAC's are stopped or
- ALL Station Air Compressors determines Station Air Header pressure is stopped <100 psig. I
- EITHER Station Air Header <100 psig PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5of13
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 3.3 IF a loss of 1 F Group Bus has occurred, Determines a loss of 1F Group Bus has not AND 1 H Group Bus is available, THEN occurred. !
SEND an Operator to restore power to #1 SAC Auxiliary Oil pump by transferring 11 Turbine West 230V Control Center IAW Attachment 14, Section 1.0. 3.4 lE a loss of 2F Group Bus has occurred, Determines a loss of 2F Group Bus has not AND 2H Group Bus is available, occurred. THEN SEND an Operator to restore power to #2 SAC Auxiliary Oil pump by I transferring 21 Turbine West 230V Control Center IAW Attachment 14, Section 2.0. 3.5 IF a loss of 1H Group Bus has occurred, Determines a loss of 1H Group Bus has not AND 1 F Group Bus is available, occurred. THEN SEND an Operator to restore power to #3 SAC Auxiliary Oil pump by transferring 11 Turbine East 230V I Control Center IAW Attachment 14, I Section 3.0. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 13
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 3.6 START or have Unit One Control Room Determines no SAC's are available.
START Next to Load Station Air Compressor. Cue if required: If Unit 1 is contacted, report i that #3 Station Air Compressor is tagged out and #1 Station Air Compressor has tripped, and that an operator has been dispatched to I the Station Air Compressors. ' 3.7 Either Station Air Header indicating less Determines both Station Air Headers are than100 psig? indicating less than100 psig. 3.8 Attempt to START, or have Unit One Determines no SAC's can be started. Control Room START, remaining Station Air Compressor. 3.9 NOTIFY the CRS/SM to evaluate use of Cue: CRS will evaluate use of temporary air temporary air compressors. compressors. 3.10/3.11 2A Control Air Header less than or equal Determines 2A control air header pressure is: to 88 psig? less than or equal to 88 psig and determines
#2 ECAC is in service OR
>88 psig.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7of13
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~- SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 3.12/3.13 28 Control Air Header less than or equal Determines 28 control air header pressure is:
to 88 psig? less than or equal to 88 psig and contacts Unit 1 to place #1 ECAC in service OR
>88 psig.
Cue: When Unit 1 is contacted to start #1 ECAC, state:"# 1 ECAC has tripped." 3.14 SEND operators to: Dispatches operators to:
- LOCATE AND ISOLATE ANY air
- LOCATE AND ISOLATE any air system leaks. system leaks.
- INVESTIGATE cause of ANY air
- INVESTIGATE cause of air compressor trip/trouble. compressor trip/trouble.
3.15 IF Station Air is lost, AND EITHER of the Determines Station Air is lost, and neither of following are in service: the following are in service:
- Spent Fuel Pool Transfer Pool
- Spent Fuel Pool Transfer Pool Weir Weir Gate Seals Gate Seals
- SG Nozzle Dams
- SG Nozzle Dams THEN:
A. EVACUATE personnel from areas subject to leakage/flooding. B. INITIATE monitoring of Fuel Pool or Reactor Vessel levels for the need to makeup due to leakage. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8of13
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~- SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 3.16 !E cooling water to the Station or Determines cooling water to the Station or Emergency Air Compressors is lost, Emergency Air Compressors is not lost.
THEN INITIATE the applicable portion of Attachment 6. 3.17 BOTH 2A and 2B Control Air Headers Determines both 2A and 2B Control Air less than 80 psig? Headers are not <80 psig. I I 3.18 ANY Excess Flow Check Valve closed as I indicated by at least one of the following? (Attachment 5, Excess Flow Check Valve Determines NO Excess Flow Check Valve 1, Table) [INPO IER L2 15-16] closed.
- Groups of valves repositioning with normal air pressure indicated in Control Room
- Local observation of low pressure downstream of an Excess Flow Check Valve 3.19 2B Control Air Header less than 80 psig? Determines 2B Control Air Header is <80 psig.
3.57 CONTINUE
- 3.58 CLOSE the following valves: Closes the following valves:
A. 2CV3, LTDWN ORIFICE ISOL VALVE A. 2CV3, LTDWN ORIFICE ISOL VALVE ' B. 2CV4, LTDWN ORIFICE ISOL VALVE B. 2CV4, LTDWN ORIFICE ISOL VALVE I
'"' 2CV5, LTDWN ORIFICE ISOL VALVE
'-'* C. 2CV5, LTDWN ORIFICE ISOL VALVE !
D. 2CV2 LETDOWN LINE ISOL VALVE D. 2CV2 LETDOWN LINE ISOL VALVE E. 2CV277 LTOWN LINE ISOL VALVE E. 2CV277 LTDWN LINE ISOL VALVE F. 2CV7 LTDWN HX INLET VALVE F. 2CV7 LTDWN HX INLET VALVE PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9of13
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~ SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 3.57 VERIFY ANY Liquid or Gaseous release Determines 2WG41, GAS DECAY TK TO
- is stopped by ensuring the following PLANT VENT is open, and shuts 2WG41, valves CLOSED: GAS DECAY TK TO PLANT VENT.
- 2WL51, TO CIRC WTR DISCHARGE Verifies 2WL51 is shut.
- 2WG41, GAS DECAY TK TO PLANT VENT CAS IF AT ANY TIME Station Air is lost, 6.0 THEN:
- INITIATE monitoring of 21- Identifies all BF19 valves closing.
24BF19 SG FW CONT VALVE,
- operation. Trips the Reactor.
- lE ANY Bf 19 SG FW CONT VALVE closes AND Applicable SG water level CANNOT be maintained, THEN:
A. TRIP the Reactor B. CONTINUE with this procedure C. GO TO 2-EOP-TRIP-1, Reactor Trip Or Safety Injection. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 10of13
OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
TRIP-1 Performs Immediate Actions of EOP-TRIP-1: Confirms the Rx trip Trips the Main turbine Checks at least 1 4KV vital bus energized Determines SI is not initiated or required. Cue after Immediate Actions have been performed: The CRS and another operator will continue performing the EOPs. You are to continue in current procedure. Terminate JPM once Rx has been tripped, letdown isolated, and the WG release terminated. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 11 of 13
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. / (l--PJt] Task description and number, JPM description and number are identified. / ) - ~.Knowledge and Abilities (KIA) references are included. I ~. Performance location specified. (in-plant, control room, or simulator) ,/ Q~* Initial setup conditions are identified. I . Initiating and terminating Cues are properly identified. / M. Task standards identified and verified by SME review. 0 lJ\. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
}=lll. 8. Verify the procedure referenced z r s JPM mate es th most current revision of that procedure: Procedure Rev. Date "'l- '(r:~. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: M.,~ ~;:;:;:. Date: &/2 1-} I l12 SME/lnstructor:____.~,__"~~~--~-~-u-~_Jd-._i(_ __ Date: S2 /z.1- / l l:>
--,1--~--
SME/lnstructor: Date: - - - - - -
------------~
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 12 of 13
INITIAL CONDITIONS:
- Unit 2 is operating at 100% power.
- A WG release is in progress from 21 GOT.
* #3 SAC is CIT for scheduled maintenance.
- Unit 1 is operating at 100% power.
INITIATING CUE: You are the Unit 2 Reactor Operator. Respond to all indications and alarms. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 13of13
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer/Pressure Relief TASK: Transfer Pressurizer 22 Backup Heaters to Emergency Power Supply TASK NUMBER: 115 043 05 01 JPM NUMBER: 15-01 NRC Annual IP-i ALTERNATE PATH: D KIA NUMBER: 010 A4.02
~~~~~~~~~___,
IMPORTANCE FACTOR: 3.6 3.4 APPLICABILITY: RO SRO EOD ROITJ STAD SROITJ EVALUATION SETTING/METHOD: In Plant, Simulate
REFERENCES:
S2.0P-SO.PZR-0010 Rev. 10 (Rev. checked 8-5-16) TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 20 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: S Bickhart I J Hancock Date: 9-30-16 SME or lnstruc~~(l 10~<>~0-Tr~rtment Approved By: Date: Jo/10/I~ Approved By: Ope~ent Date: ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 1of6
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Pressurizer/Pressure Relief TASK: Transfer Pressurizer 22 Backup Heaters to Emergency Power Supply TASK 115 043 05 01 NUMBER: INITIAL CONDITIONS: Due to a loss of power to the group buses it is necessary to energize the PZR Backup Heaters from their emergency power supply. INITIATING CUE: The CRS directs you to perform S2.0P-SO.PZR-001 O(Q), Section 5.3, Transferring Pzr Htr 22 BU Group To The Emergency Power Supply. All prerequisites and Precautions and Limitations have been reviewed and completed. 2A EOG is carrying 2A Vital Bus and is loaded to 2400 KW. You have a JAM key. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion:
- 1. Simulate opening all but three PZR heater disconnects.
- 2. Simulate aligning emergency power to PZR heater bus from 2A vital bus.
Page 2of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~ SYSTEM: Pressurizer/Pressure Relief DATE:~~~~~~~~~~ TASK: Transfer 22 Backup Heaters to Emergency Power Supply STEP COMMENTS
- STEP (*Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation}
Operator obtains procedure S2.0P- Provide marked up copy of S2.0P-SO.PZR-0010, Pressurizer Backup Heaters SO.PZR-0010, Pressurizer Backup Power Supply Transfer. Heaters Power Supply Transfer 5.3.1 ENSURE 2AX1AX14X, 2EP Locates breaker 2AX1AX14X 2EP PRESSURIZER HEATER BUS FEED PRESSURIZER HEATER BUS FEED (EMERGENCY) is OPEN (84' Swgr Rm). (EMERGENCY) on 2A 460V Vital Bus, Elev. 84' Swgr Rm and determines current breaker position. Cue: 2AX1AX14X Breaker indicates OPEN. 5.3.2 Request NCO to PERFORM the following: Locates nearest means of A. PLACE 22 Backup Group in communications and requests NCO to MANUAL. place 22 B/U Htrs in MANUAL and B. PRESS the 22 BACKUP OFF press the 22 BACKUP OFF pushbutton pushbutton. Cue: NCO reports 22 B/U Htrs are in MANUAL and 22 BACKUP OFF pushbutton has been depressed.
- 5.3.3 ENSURE 2EX1EP2EPX, 2EP 480V Locates 2EX1 EP2EPX, 2EP 480V PRESSURIZER HEATER BUS MAIN PRESSURIZER HEATER BUS MAIN BREAKER is OPEN (78' Electrical BREAKER on El. 78 Electrical Pen.
Penetration). Cue:2EX1EP2EPX,2EP480V PRESSURIZER HEATER BUS MAIN BREAKER is OPEN. Page 3of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:~~~~~~~~~~ SYSTEM: Pressurizer/Pressure Relief DATE:~~~~~~~~~~ TASK: Transfer 22 Backup Heaters to Emergency Power Supply STEP COMMENTS
- STEP (*Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD SIU Evaluation)
- 5.3.4 REMOVE interlock key from breaker Describes turning key and removing 2EX1 EP2EPX. interlock key from breaker 2EX1 EP2EPX.
Note: Tab must be pushed in to rotate key to allow its removal.
- 5.3.5 PLACE any eleven of the following Operator locates individual heater disconnects in OFF (only three disconnects disconnects, places all but three are to remain ON) AND MARK the disconnects in OFF and notes remaining disconnects as N/A: disconnects left ON as NIA in procedure.
- 5.3.6 PLACE, 2AX1AX14X-1, 2EP PZR HTR Operator locates 2AX1AX14X-1, 2EP BUS EMERGENCY FEED DISCONNECT PZR HTR BUS EMERGENCY FEED SWITCH, in the ON position (Elev 78' DISCONNECT SWITCH, and places it Electrical Penetration). in the ON position (Elev 78' Electrical Penetration).
- 5.3.7 INSERT interlock key, AND UNLOCK Locates Corry Key Interlock on breaker 2AX1AX14X. 2AX1AX14X breaker, inserts and turns key.
5.3.8 NOTIFY NCO that PZR Htr 22 B/U Group Candidate makes report to the Control has been transferred to the emergency Room. power supply (2A 460V Vital Bus). Repeat back notification and state: JPM is complete. Page 4of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM
- W usage, revalidate JPM using steps 8 and 11 below.
- 1. Task description and number, JPM description and number are identified.
- 2. Knowledge and Abilities (KIA) references are included.
~3. Performance location specified. (in-plant, control room, or simulator)
~4. Initial setup conditions are identified.
~5. Initiating and terminating Cues are properly identified.
? 16. Task standards identified and verified by SME review.
~7. Critical steps meet the criteria for critical steps and are identified with an asterisk(').
~ 8. Verify the procedure referenced by this JPM mat9h~s the most current revision of
< that procedure: Procedure Rev. Y Date HL"11)
.); ) 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor:~ll"',.,.._,.- Date: '/Jo(1&, SME/lnstruct~ i5fdt~~ Date: 'If3v ,J, 6 SME/lnstructor: Date: - - - - - -
------------~
OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Due to a loss of power to the group buses it is necessary to energize the PZR Backup Heaters from their emergency power supply. INITIATING CUE: The CRS directs you to perform S2.0P-SO.PZR-0010(Q), Section 5.3, Transferring Pzr Htr 22 BU Group To The Emergency Power Supply. All prerequisites and Precautions and Limitations have been reviewed and completed. 2A EOG is carrying 2A Vital Bus and is loaded to 2400 KW. You have a JAM key. Page 6of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE: STATION: SALEM SYSTEM: Auxiliary Feedwater TASK: Perform Auxiliary Feedwater Back Leakage Test TASK NUMBER: N0610160204 JPM NUMBER: 15-01 NRC IP-j ALTERNATE PATH: I I KJA NUMBER: 061 K1.02
~~~~~~~~--;
IMPORTANCE FACTOR: 3.4 3.7 APPLICABILITY: RO SRO EoO RO[ZJ STAD SRO[ZJ EVALUATION SETTING/METHOD: lnplant- Simulate
REFERENCES:
S1 .OP-PT.AF-0002, Rev. 7, Auxiliary Feedwater Backleakage (checked 8-5-16) TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: S Bickhart I J Hancock Date: 9-30-16 SME or Instructor Approved By: ~ MvHIW\ Training~partment Approved By: Date: /o flJpt., Opebrtment ACTUAL JPM COMPLETION TIME: ACTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: Page 1 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE: NAME: ~~~~~~~~~~~~~~ DATE: ~~~~~~~~~~~~~~ SYSTEM: Auxiliary Feedwater System TASK: Perform Auxiliary Feedwater Back Leakage Test TASK NUMBER: N0610160204 INITIAL CONDITIONS: Unit 1 is operating at 100% power. 11 AFW pump was secured 30 minutes ago after its normally scheduled quarterly surveillance run. INITIATING CUE: You are directed to perform S1 .OP-PT.AF-0002, Auxiliary Feedwater Backleage. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Task Standard for Successful Completion:
- 1. Determine 13 AFW line venting is required
- 2. Vent 13 AFW line Page 2 of 8
- PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~- JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~- SYSTEM: AFW TASK Perform Auxiliarv Feedwater Back Leakaae Tes STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
Provide operator with blank copy of S1 .OP- Reviews and initial all Prerequisites PT.AF-0002, Rev. 7, and a calculator. and Precautions and Limitations. 5.1.1 RECORD following on Attachment 1, Section 1.0: After locating 1TA165551, provide
- AFW Line Temperatures (1TA165551) the following AFW line
- Highest line temperature temperatures:
11- 104
- Average line temperature 12- 106
- Temperature difference 13- 161 14- 108 On Attachment 1, records AFW temperatures, calculates total of 479, divides that by 4 and determines
- highest line temp is 161 and average line temp is 119.75.
Determines Temp Diff 161- 119.75 = 41.25. 5.1.2 IF temperature in each line is <120°F, AND temperature difference between highest Determines highest temp is >120°F and average line temp is _:::10°F, THEN RECORD Test Results in Attachment 1, Section 5.0. Page 3 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training.
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~- SYSTEM: AFW TASK Perform Auxiliarv Feedwater Back Leakaae Tes STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation) 5.1.3 IF temperature in any line is :::120°F AND <160°F, THEN: Determines highest temp is >160°F A. RECORD Auxiliary Feedwater System piping temperatures every hour in Control Room Narrative Log.
B. RECORD Test Results in Attachment 1, Section 5.0. 5.1.4 IF temperature difference between highest and average line temp is >10°F, THEN Determines temperature difference RECORD Test Results in Attachment 1, between highest and average line
- Section 5.0. temp is >10°F, and records Test Results in Attachment 1, Section 5.0.,
as UNSAT for all three categories. 5.1.6 I IF temperature in any line is :'.:160°F THEN: A. RECORD findings in Control Room Narrative Log. B. VENT Auxiliary Feedwater pumps/piping IAW Section 5.2. Page 4 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~ JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~- SYSTEM: AFW TASK: Perform Auxiliarv Feedwater Back Leakaae T STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT
- NO. STANDARD S/U evaluation)
- 5.2.1 IF 11 Auxiliary Feedwater Pump and piping is affected, THEN:
A. SLOWLY THROTTLE OPEN 11 AF83, AF Locates and opens 11 AF83, AF PUMP VENT, until a solid stream of water is PUMP VENT, until a solid stream of observed. water is observed. Cue: A solid stream of water is observed. Closes 11 AF83 B. CLOSE 11 AF83. Locates and opens11AF114, AF C. SLOWLY THROTTLE OPEN 11 AF114, PUMP DISCH VENT, until a solid AF PUMP DISCH VENT, until a solid stream stream of water is observed. of water is observed. Cue: A solid stream of water is observed. D. CLOSE 11AF114. Closes 11 AF114. Terminate JPM Page 5 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
This Page Intentionally Blank This Page Intentionally Blank PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 6 of 8
JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. [.. ~1. Task description and number, JPM description and number are identified. U>> 2 . Knowledge and Abilities (KIA) references are included. V ,;;}- <) 13. Performance location specified. (in-plant, control room, or simulator) V ;J S / 4. Initial setup conditions are identified. u
---+--..,.....__,_./?. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
- 18. Verify the procedure referenced by this JPM matchfs the most current revision of
_ ( that procedure: Procedure Rev.+- Date l/fltfl.
#-L-- 9. Pilot test the JPM:
- a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstructor: ~4>V'- Date: q/~/;..b SME/lnstructo~~clt1Mll. t- Date: 9/~ ~JIG. SME/lnstructor: Date: - - - - - -
------------~
Page 7 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Unit 1 is operating at 100% power. 11 AFW pump was secured 30 minutes ago after its normally scheduled quarterly surveillance run. INITIATING CUE: You are directed to perform S1 .OP-PT.AF-0002, Auxiliary Feedwater Backleage. Page 8 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM Emergency Diesel Generator Start and synchronize an Emergency Diesel Generator ASK NUMBER: 113 001 05 01 PM NUMBER: 15-01 NRC IP-k LTERNATE PATH: D KIA NUMBER: IMPORTANCE FACTOR: 064 A2.09
~~~~~~~~~~-t 3.1 3.3
-- RO
-- SRO PPLICABILITY:
EOC) R0[8J STAD SR0[8J EVALUATION SETTING/METHOD: In Plant I Simulate
REFERENCES:
2A Diesel Generator Operation, S2.0P-SO.DG-0001(Q)Rev. 39 (checked 8-5-16) OOLS AND EQUIPMENT: None ALIDATED JPM COMPLETION TIME: 20 min IME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor alidated By: S Bickhart I J Hancock Date: 9-30-16 pproved By: Date: roJ /<- 0 pproved By: CTUAL JPM COMPLETION TIME: CTUAL TIME CRITICAL COMPLETION TIME: PERFORMED BY: GRADE: [JsAT OuNSAT REASON, IF UNSATISFACTORY: EVALUATOR'S SIGNATURE: DATE: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: EOG TASK: Start and synchronize an Emergency Diesel Generator TASK 113 0010501 NUMBER: INITIAL Unit 2 is operating at 100% power, with no equipment OOS. Engineering has CONDITIONS: requested a loaded run of 2A EOG. INITIATING CUE: The Unit 2 CRS has directed you to locally start and load 2A DIG IAW S2.0P-SO.DG-0001 (Q), Section 5.2. & 5.4 Prerequisites, Precautions and Limitations, and Section 5.1, Diesel Generator Startup Checks have been performed. Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Task Standard for Successful Completion: Perform S2.0P-SO.DG-0001 Sections 5.2 and 5.4 in correct order and to completion. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2of12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME:~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE:~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation)
Provide marked up copy of S2.0P-SO.DG-0001 2A Diesel Generator Operation 5.2.1 NOTIFY NCO that 2A Diesel Generator is Locates nearest page. to be locally started. Cue: NCO acknowledQes. 5.2.2 CHECK voltage permissive indicator light Points out voltage permissive indicator 2DAE4-LT2, EOG VOLTAGE, on light 2DAE4-LT2, EOG VOLTAGE, on Generator Control Panel is OFF Generator Control Panel. Cue: Light is off 5.2.3 CHECK speed permissive indicator light Points out speed permissive indicator 2DAE4-L T3, EOG SPEED, on Generator light 2DAE4-LT3, EOG SPEED, on Control Panel is OFF. Generator Control Panel. Cue: LiQht is off
- 5.2.4 IF 2A 4KV Vital Bus is currently energized, (Diesel Generator is to be parallel loaded),
THEN: Points out 2A-DF-GCP-1, 2A DIESEL A. PLACE 2A-DF-GCP-1, 2A DIESEL GEN LOADING SW., and simulates GEN LOADING SW in MANUAL rotating to DROOP position. (DROOP). B. ENSURE B-9, GENERATOR LOADING Cue: Annunciator B-9, Generator IN DROOP MODE, is in alarm. loading in Droop Mode annunciates. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME:~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE:~~~~~~~~~~~~- COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation)
- 5.2.5 PLACE 2A-DF-SS, 2A DG STOP/START Points out2A-DF-SS, 2A DG SWITCH in START. STOP/START SWITCH, and simulates placing in START.
Cue: 2A Diesel is acceleratinQ.
- 5.2.6 lE Diesel Generator Speed is NOT 900 rpm, THEN SET speed to 900 rpm using Cue when Speed indicator is the SPEED CONTROL SWITCH (GS). checked: Speed is 880 rpm.
Points out SPEED CONTROL SWITCH (GS) and simulates turning in RAISE direction. Cue: 2A Diesel Speed is 900 rpm. 5.2.7 lE 2AD1AX6D*, 2A Diesel Generator 125VDC breaker is closed, THEN:
- CHECK voltage permissive Points out voltage permissive indicator indicator light 2DAE4-LT2, EOG light 2DAE4-LT2, EOG VOLTAGE.
VOLTAGE, on Generator Control Cue: Voltage permissive indicator light Panel is ON. 2DAE4-LT2, EOG VOLTAGE Light is on
- CHECK speed permissive indicator Points out speed permissive indicator light 2DAE4-LT3, EOG SPEED, on light 2DAE4-LT3, EOG SPEED Generator Control Panel is ON. Cue: Speed permissive indicator light 2DAE4-LT3, EOG SPEED light is on PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4of12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: ~~~~~~~~~~~~- TASK: Locally start and load an Emergency Diesel Generator DATE: ~~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation) 5.2.8 !E Field Ground Relay 64/G white indicating light is OFF, AND C-6, GENERATOR FIELD GROUND, is clear, Points out Field Ground Relay 64/G THEN: white indicating light.
A. RESET 64/G relay B. ENSURE 64/G white indicating Cue: Field Ground Relay 64/G white light is illuminated. indicating light is illuminated. 5.2.9 ENSURE 2A Diesel Generator K1 C Field Points out 2A Diesel Generator K1 C Flashing Relay Supervisory Light is OFF. Field Flashing Relay Supervisory Light Cue: 2A Diesel Generator K1C Field Flashing Relay Supervisory Light is off. 5.2.10 RECORD the following Diesel Generator Points out gages and switches to Start Readings: determine readings. Cue when proper gauge is pointed out: 2VM189 Gen. Volts - 4160 Volts on all 3 phases 2FM186 Gen. Frequency - 60 Hz 2PL6429 LO Hdr. Press - 80 psig 2PL6449 JW Hdr. Press - 45 psig 2PL7209 Air Manifold Press - O psig 2TA16524 Gen. Stator Temp - 187° PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5of12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: ~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE: ~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation) 5.2.11 !E 2A Diesel Generator is to be operated Cue: Diesel will be parallel loaded.
unloaded for an extended period of time(>30 minutes), THEN INITIATE Section 5.7, Diesel Generator Running Checks. 5.2.12 !E Diesel Generator is to be parallel Initiates Section 5.4, Diesel Generator loaded, THEN INITIATE Section 5.4, Parallel Loading. Diesel Generator Parallel Loading. 5.4.1 !E Section 5.1 Diesel Generator Startup Verifies Section 5.1 is complete. Checks, was NOT performed, THEN at 2A DG 4KV cabinet cubicle breaker 2AD1AX6D, PLACE selector switch 2A DG SYNC ENABLE in ENABLE. 5.4.2 NOTIFY NCO that 2A EOG is to be Cue: NCO acknowledges 2A DG is to synchronized and loaded locally. be synchronized and loaded locally. 5.4.3 ENSURE 2A-DF-GCP-1, 2A DIESEL GEN Verifies 2A-DF-GCP-1, 2A DIESEL LOADING SW, in MANUAL (DROOP) GEN LOADING SW, is in MANUAL (DROOP) PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME:~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE:~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation)
- 5.4.4 ADJUST 2A EOG output voltage, as indicated on VOLTMETER-GEN (2VM189) When operator points out 2VM189 to 50 - 100 Volts higher than that of 2A and 2VM190, then Cue: 2VM189 reads 4KV Vital Bus voltage, as indicated by 4150, and 2VM190 reads 4150.
VOLTMETER-BUS (2VM190), using the VOLTAGE CONTROL SWITCH (VCS). Points out VOLTAGE CONTROL SWITCH (VCS) and simulates going to RAISE. Cue: 2VM189 reads 4210, and 2VM190 reads 4150. 5.4.5 ENSURE generator terminal voltage is Points out VOLTMETER SWITCH - present on all 3 phases by rotating GEN (VS-G), simulates rotating through VOLTMETER SWITCH - GEN (VS-G) each position, while observing 2VM189 through each position AND OBSERVING voltmeter 2VM189. Cue: Voltage is present on all three phases. 5.4.6 ENSURE 2A 4KV Vital Bus voltage is Points out VOLTMETER SWITCH - present on all 3 phases by rotating BUS (VS-B), simulates rotating through VOLTMETER SWITCH - BUS (VS-B) each position, while observing 2VM190 through each position AND OBSERVING voltmeter 2VM190. Cue: Voltage is present on all three phases. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7of12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME:~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE:~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation) 5.4.7 PLACE the following switches in "1-2": Points out VOLTMETER SWITCH -
GEN (VS-G) and VOLTMETER
- VOLTMETER SWITCH - GEN SWITCH - BUS (VS-B)
(VS-G)
- VOLTMETER SWITCH - BUS (VS-B) Cue: Switches are in 1-2.
5.4.8 ENSURE 20AE4-LT2, EOG Voltage Points out 20AE4-LT2, EOG Voltage indication light is ON. indication light. Cue: 2DAE4-LT2, EDG Voltage indication liqht is on. 5.4.9 ENSURE 20AE4-LT3, EDG Speed Points out 20AE4-LT3, EDG Speed indication light is ON. indication light. Cue: 20AE4-L T2, EOG Voltage indication liaht is on. 5.4.10 SYNCHRONIZE 2A Diesel Generator to 2A 4KV Vital Bus as follows:
- 5.4.10 PLACE 2A-DF-SYNCH, 2A DG SYNC A. SWITCH (SS) to ON. Points out 2A-DF-SYNCH, 2A OG SYNC SWITCH (SS), and simulates placing in ON position.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8of12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME:~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE: ~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation)
- 5.4.10 ADJUST Diesel speed using the SPEED When operator points out B. CONTROL SWITCH (GS) such that synchroscope, then Cue: Scope is Synchroscope pointer rotates slowly in the going in the slow direction.
FAST (clockwise) direction. Points out SPEED CONTROL SWITCH (GS)and simulates going to RAISE. Cue Synchroscope pointer rotating slowly in the FAST direction. 5.4.10 ENSURE the following four SYNC CHECK Points out four SYNC CHECK RELAY C. RELAY 25 UPPER AND LOWER 25 UPPER AND LOWER VOLTAGE VOLTAGE LIMIT LEDS are ON. LIMIT LEDS.
"Upper Voltage Limit" "L OK" "B OK" "Lower Voltage Limit" "L OK" "B OK" Cue as each LED is located: Light is on.
5.4.10 !Ethe SYNC CHK RELAY 25 ilF OK LED Points out SYNC CHK RELAY 25 ilF D. is OFF, THEN ADJUST 2A Diesel OK LED. Generator speed using the SPEED CONTROL SWITCH (GS) until the ilF OK Cue Light is on. LED is ON. 5.4.10 ENSURE DG SYNC PERMISSIVE green E. indicating light is ON each time the Cue DG SYNC PERMISSIVE green synchroscope indicator is near 12 o'clock indicating light is ON each time the position(+/- approximately 3 minutes), synchroscope indicator is near 12 AND is OFF in any other position of the o'clock position(+/- approximately 3 synchroscope. minutes), AND is OFF in any other position of the synchroscope. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9of12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: ~~~~~~~~~~~~ TASK: Locally start and load an Emergency Diesel Generator DATE: ~~~~~~~~~~~~ COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT (*Denotes a Critical Step) S/U
- NO. Evaluation)
- 5.4.10 COORDINATE the following when the F synchroscope is at "12 o'clock" (+zero, -2 minutes):
- 1. CLOSE 2A-DF-GCP-3 Points out 2A-DF-GCP-3 GENERATOR GENERATOR CIRCUIT CIRCUIT BREAKER SWITCH (BCS)
BREAKER SWITCH (BCS) and simulates taking to the CLOSE position when the synch scope is at 12
- 2. RAISE 2A Diesel Generator load to o'clock.
~ 500KW using SPEED CONTROL SWITCH (GS) to Cue 2A Diesel Generator Breaker has prevent tripping the Diesel closed.
Generator Breaker on reverse power. Points out SPEED CONTROL SWITCH (GS) simulates going to RAISE while observing KW meter. Cue Load is 500 KW. 5.4.10 PLACE 2A-DF-SYNCH, 2A DG SYNCH Points out 2A-DF-SYNCH, 2A DG G SWITCH (SS) to OFF. SYNCH SWITCH (SS), and simulates placing it in OFF position. Cue: JPM is complete. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 10 of 12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below. l1 ~1. Task description and number, JPM description and number are identified.
&. ~2. Knowledge and Abilities (KIA) references are included.
,_, ~3. Perfonnance location specified. (in-plant, control room, or simulator)
~4. Initial setup conditions are identified.
;)_.)._,L 5. Initiating and terminating Cues are properly identified.
~
~ ;r
) I 6. Task standards identified and verified by SME review.
J JI 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).
'l ) 8. Verify the procedure referenced by this JPM matches the most current revision of
~ that procedure: Procedure Rev.~ Date ~ho/;&,
~9. Pilot test the JPM:
/ a. verify Cues both verbal and visual are free of conflict, and
- b. ensure performance time is accurate.
____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. ____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. SME/lnstruc~U:;_ c."-.. Date: 7 /Jo Ufa SME/lnstruc . Pt :t-- Date: q~//6 SME/lnstructor: Date: - - - - - - PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 11 of 12
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Unit 2 is operating at 100% power, with no equipment OOS. Engineering has requested a loaded run of 2A EOG. INITIATING CUE: The Unit 2 CRS has directed you to locally start and load 2A DIG IAW S2.0P-SO.DG-0001(Q), Section 5.2. & 5.4 Prerequisites, Precautions and Limitations, and Section 5.1, Diesel Generator Startup Checks have been performed. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 12of12
Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 15-01 NRC Examiners: Operators: Initial Conditions: 100% power, MOL. PZR Pressure Channel Ill is selected for Control. Turnover: Maintain current power. Event Malf. No. Event Event Type* No. Description I 1 PR0017A Controlling PZR level channel fails low (TS) ALL 2 RC0002 c RCS leak (TS) ALL M 3 RC0002 Small Break LOCA ALL 4 RP0342 c High Head ECCS isolation valves fail to open RP0343 CRS/RO 5 CB09 A DI c SEC fails to reset KCB09ASE CRS I PO RP318E1 6 RP318E2 c All AFW pumps fail to start AF0353A CRS/PO AF0353B 7 RC0002 c SBLOCA escalation after entering SI Termination procedure CRS/RO
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
TQ-AA-106-0204 Page 1of27 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 15-01 NRC ESG-1 SCENARIO NUMBER: 15-01 NRC ESG-1 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 00 PROGRAM: .____ __.I LO. REQUAL I. x I INITIAL LICENSE I I STA
.____ __.I OTHER Revision Summary New issue for 15-01 ILOT NRC exam PREPARED BY: G Gauding 7-18-16 Lead Regulatory Exam Author Date APPROVED BY:
APPROVED BY: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 2 of 27
TQ-AA-106-0204 Page 3 of 27 A. Given the order or indications of a charging system malfunction, perform actions as the nuclear control operator to RESPOND to the loss or malfunction of the charging system in accordance with S2.0P-AB.CVC-0001. B. Given indication of a loss or malfunction of the Charging system DIRECT corrective action for a Charging System malfunction in accordance with S2.0P-AB.CVC-0001. C. Given the indications of a reactor coolant system (RCS) malfunction or leak, perform actions as the nuclear control operator to RESPOND to the malfunctioning accordance with S2.0P-AB.RC-0001. D. Given the indications of a reactor coolant system (RCS) malfunction or leak, DIRECT the response to the malfunction in accordance with S2.0P-AB.RC-0001. E. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1. F. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1. G. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures. H. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures. I. Given a safety injection has occurred and inadequate ECCS flow exists, ALIGN equipment to obtain required ECCS flow in accordance with station procedures. J. Given the order or indications of a loss of coolant accident (LOCA), complete actions as the nuclear control operator to PERFORM the immediate response to the LOCA in accordance with the approved station procedures. K. Given indication of a loss of coolant accident (LOCA), DIRECT the immediate response to the LOCA in accordance with the approved station procedures. L. Given conditions that allow SI termination, perform actions as the nuclear control operator to TERMINATE safety injection in accordance with the approved station procedures.
- M.~ Given conditions that allow SI termination, DIRECT the response to the safety injection termination in accordance with the approved station procedures.
A. Controlling PZR Level Channel fails low B. 20 gpm RCS leak C. 150 gpm SBLOCA D. SBLOCA escalation during SI termination PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 4 of 27 A. The crew will take the watch with the unit at 100% power, MOL. PZR Pressure Channel Ill is selected for Control. B. After the crew assumes the watch, the controlling PZR level channel will fail low. CVCS Letdown will isolate, and the Master Flow Controller will raise charging flow. The crew will enter S2.0P-AB.CVC-0001, Loss of Charging. The crew will take manual control of charging flow and return PZR level to program. The crew will remove the failed channel from service. The crew will restore normal letdown. The CRS will identify Tech Specs. C. After the PZR level channel failure has been addressed, a 20 gpm RCS leak will occur. The crew will diagnose the leak. The crew will swap to a centrifugal charging pump and a 45 gpm orifice, and estimate the leak rate. The CRS will identify Tech Specs. D. After the crew has stabilized PZR level and the CRS has identified Tech Specs, the RCS leak will rise to 150 gpm. The crew will diagnose deteriorating primary conditions. When it is determined that PZR level will be unable to be maintained >11 %, the crew will take the CAS action to trip the reactor and initiate Safety Injection. E. The crew will perform plant stabilization and diagnostics in EOP-TRIP-1, Reactor Trip or Safety Injection. The crew will identify no AFW flow. 2A SEC will not reset, and will require deenergization to start 21 AFW pump. The crew will establish at least 22E4 lbm/hr AFW flow. (CT#1) F. The crew will determine there is no High Head ECCS flow, and open the BIT Isolation Valves to establish High Head ECCS Injection (CT#2). G. The crew will transition to EOP-LOCA-1, Loss of Reactor Coolant when directed in TRIP-1. H. The crew will reset Safeguards in LOCA-1, and determine SI termination criteria are met to transition to EOP-TRIP-3, SI Termination. I. The crew will stop all but one Charging pump and align CVCS for normal charging. When evaluating the leak, the SBLOCA will get significantly larger. The crew will diagnose degrading conditions and take the CAS action to start ECCS pumps as necessary, and go to EOP-LOCA-2. J. The scenario will terminate when the transition to LOCA-2 has been made. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 5 of 27 IC-231 1 VC1 and VC4 CIT 2 RCPs (SELF CHECK) _ 3 RTBs (SELF CHECK) _ 4 MS167s (SELF CHECK) _ 5 500 KV SWYD (SELF CHECK) _ 6 SGFP Trip (SELF CHECK) _ 7 23 CV PP (SELF CHECK) 8 PZR Pressure Channel Ill selected for Control. g Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist." Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Pa e 6 of 27 ET# Description "---~-~------*--- EVENT ACTION: COMMAND: PURPOSE: SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time 01 PR0017A PZR LEVEL CH I (LT459 FAILS H/L NIA NIA N/A RT-1 0 RC0002 RCS LEAK INTO CONTAINMENT (equiv to 0-02 4 inches NIA NIA NiA RT-3 20 03 RP0342 2SJ12 FAILS TO AUTO OPEN ON SEC NIA N/A N!A N/A 04 RP0343 2SJ13 FAILS TO AUTO OPEN ON SEC NIA N/A N/A N/A 05 RP318E1 Aux Feed Pump 21 Fails to Start on SEC NIA N/A N/A N/A 06 RP318E2 Aux Feed Pum 22 Fails to Start on SEC N!A N/A N/A N/A AF0353A 21 AFP FAILURE TO AUTO START ON ANY 07 ALL SIGNALS NIA N!A NIA NIA AF0353B 22 AFP FAILURE TO AUTO START ON ANY 08 ALL SIGNALS NIA N/A NIA NIA SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time I 01 DG01D DEENERGIZE "A" SEC CABINET NIA N!A NIA RT-9 YES 02 SP01A1 Prevailin Wind S eed N/A N!A N!A NIA 10 03 SP01A2 Prevailin Wind Direction NIA NIA NIA NIA 160 04 MS05A 21MS45 21 STM GEN STM SUP-23 AFP N/A NIA N/A NIA 0 05 MS06A 23MS45 23 STM GEN STM SUP-23 AFP N/A NIA N!A NIA 0 SELF- Description Delay Initial Ramp Trigger Condition/ CHECK Time Value Time Severity CB09 A DI KCB09ASE 2A SFGD EMER OPR-EMERG 01 LOADING RESET NIA N/A NIA N/A OFF PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 7 of 27 1. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 8 of 27 A. State shift job assignments. B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet). C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time. CRS please inform me when your crew is ready to assume the shift". D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 9 of 27
- 1. Controlling PZR Level Channel Fails LOW RO reports unexpected OHA E-36, PZR HTR OFF LVL LO.
RO diagnoses controlling PZR level channel failure. RO may request permission to place the Master Flow Controller in manual prior to direction in AB.CVC to do so. CRS enters S2.0P-AB.CVC-0001, Loss of Charaina. CRS directs initiation of Attachment 1 CAS. RO reports charging pumps are running, and no indication of cavitation. RO reoorts PZR level channel I has failed low. If not previously performed, RO takes manual control of charging and maintains PZR level within band assianed bv CRS. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 10 of 27 RO selects operable channel for Control, Alarm, and Recorders. RO restores PZR heaters to pre-event condition. RO announces OHA E-20 PZR HTR ON LVL HI as expected when it annunciates due to no letdown with charaina flow established. PO restores letdown by: Ensuring open 2CV7 Placing 2CV18 in manual and closing, then opening until close PB extinguishes. Opening 2CV2 and 2CV277, then placing both in auto. Ensuring charging flow is 90 gpm. Opening a 75 gpm orifice isolation valve while adjusting 2CV18 to control letdown pressure -300 psig. Placino 2CV18 in auto. RO returns Master Flow Controller to auto when PZR level returns to oroaram. CRS contacts IC for assistance in removing channel from service. CRS enter LCO 3.3.1.1 action 6. Proceed to next event after Tech Spec call at direction from Lead evaluator. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 11of27 .o; *~!~.~:& 'H:c,~;:'.;:" -, 0 eorilaifi~en ..:;\F'****.;;.*.**\*,z,>i P1'7lrV~
. . . )1Ja.4va u~ ...
RO reports that charging flow is rising (if MFC has been returned to auto) and PZR level is lowerina slowlv. Crew reports reading on 2R11A containment radiation monitor is risin~. RO reports unexpected OHA C-2 CNTMT SUMP PMP START when it occurs. CRS enters S2.0P-AB.RC-0001, Reactor Coolant Svstem Leak. CRS directs initiation of Attachment 1 CAS. RO reports RCS temperature > 350°F in Mode 1. RO reoorts PZR level is lowerin~. Note: PZR level is above program, and charging flow will be lower than normal to reduce PZR level. If charging flow is raised here to stabilize level, then step to place a centrifugal charging pump in PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 12 of 27 service may not be performed. CRS enters S2.0P-AB.RAD-0001, Abnormal Radiation after OHA A-6 unexpected annunciation. RO swaps to a centrifugal charging pump IAW Step 3.14, and raises charging flow to stabilize PZR level. PO reduces letdown flow to minimum by opening 2CV3, maintaining letdown pressure
-300 psig with 2CV18 in manual, then closing the open 75 gpm orifice and returning 2CV18 to auto.
RO stabilizes PZR level and estimates leak rate. CRS initiates S2.0P-ST.RC-0008, Reactor Coolant Svstem Water lnventorv Balance. CRS contacts Rad Pro for recommendation on CFCU ooeration. Role Play: If contacted state Rad Pro recommends placing 2 CFCU's in Low Speed and 2 CFCU's in High Speed. PO places 2 CFCU's in Low Speed and 2 CFCU's in Hiah Soeed. CRS initiates actions to locate and isolate the leak IAW Attachment 2. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 13 of 27 CRS enters TSAS 3.4.7.2.b action b for RCS leakage, and 3.6.1.4 for containment pressure if it has reached 0.3 osia. Proceed to next event on direction from Lead Evaluator.
- 3. SBLOCA t?Simutator~o" eratof:*tMo01Fv:.' * *,
t~~~Q~~~itf~,~1i~fi~oO!\ . RO reports PZR level trending down and adiusts charaina flow to maintain PZR level. RO reports PZR level will not be able to be maintained >17%. CRS directs Rx trio and Safetv lniection RO trips the reactor and confirms the reactor trio. RO initiates Safetv lniection. RO continues Immediate Actions of TRIP-1 Trips the Main Turbine Reports at least one 4KV vital bus energized. Reoorts SI initiated. CRS and RO verify performance of immediate actions. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 14 of 27
~:~:r~f~ft"~~;~4
- 4. AFW fails to initiate PO reports SEC loading is not complete for 2A and 28 vital buses, 21 and 22 AFW pumps have failed to start. Reports 23 AFW pump started but is not orovidina anv AFW flow.
RO blocks 2A and 28 SECs. PO resets 2A and 28 SECs. PO reports 2A SEC will not reset. CRS dispatches operator to deenergize 2A SEC. 1 7 tor::'.2tminufes ., . E~A~rY:~tt-~ 1 f!tohdeer1 1 ~*L2~~,g~!~!~f~{:!;~j@ PO reports AFW pump status, and starts 21 AFW oumo when 2A SEC is deeneraized. PO reoorts not all valve arouos in Table B are PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 15 of 27 PO reports 2SJ 12 and 2SJ 13 BIT isolation valves have not ooened. RO opens 2SJ12 and 2SJ13 and reports BIT flow is established. RO reoorts 21 and 22CA330s are shut. RO reports containment pressure has remained <15 osia. CRS directs imolementation of the ECG. PO reoorts all 4KV vital buses eneraized. RO reoorts CAV in AP mode. RO reports 2 switchgear supply and one exhaust fan are runnina. RO reoorts 2 or more CCW pum RO reports RCS not aligned for Cold Leg Recirc. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 16 of 27 si PO reports total AFW flow is 22E4 lbm/hr or 9% level in at least one SG NR level, then maintains 19-33% level. RO reports all RCPs running, and RCS temperature is stable at or trending to 547°F. RO reports both RTBs are open. RO reports both PZR PORVs are shut with their Block Valves open. RO reports all RCPs in service and PZR spray operating as expected for current plant conditions. RO reports RCS pressure >1350 psig and maintains seal iniection flow to all RCPs. PO reports no indication of faulted SGs. PO/RO report no indications of a steam enerator tube rupture. RO reports radiation monitor channel status in Table F. PO reports 2 or more channels risina or in PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 17 of 27 CRS transitions to EOP-LOCA-1, Loss of Reactor Coolant. Note: CFST monitoring will commence after the transition out of TRI P-1. STA will report to the control room 1O minutes after being paged. PO reoorts no faulted SGs. PO reports total AFW flow is 22E4 lbm/hr or 9% level in at least one SG NR level, then maintains 19-33% level. RO resets SI, Phase A, and Phase B isolations. RO ooens 21 and 22CA330s. PO resets 2C SEC, and reports 230V control centers reset. RO resets SGBD Sample Isolation Bypass and ooens 21-24SS94s. CRS directs chemistry to sample SGs for activitv and boron. RO reports PORVs are shut with Block valves ooen. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 18 of 27 RO reports subcoolina > 0°F. PO reports AFW flow >22E4 lbm/hr or SG NR level >9%. ressure is stable or risin RO reports PZR level >11%. CRS transitions to EOP-TRIP-3, SI Termination. RO resets SI, Phase A, and Phase B isolations if not previouslv reset. RO opens 21 and 22CA330s if not previously erformed. rav valves are not failed open. PO resets 2C SEC and reports 230V control centers reset if not previouslv performed. RO stops all but one charain RO reports charging pump suction is aligned to the RWST. RO opens 2CV139 and 2CV140 if shut. RO shuts BIT isolation valves 2SJ4, 2SJ5, PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 19 of 27 2SJ12, 2SJ13. RO shuts 2CV55 Charaina Flow Control valve. RO opens 2CV68 and 2CV69 Charging Discharae valves . . r\S.nnula(Q:t:oB~t~lC>t~Mgp1F,~!0;ti%::
..,.A,.L. c""R'""c***0***o* **0**2*."f*. *****iiNL'1*'i5**0°"'t **2**.. o'*o**o**""" '"M 0 0
- ~~tr~l~9'1a~i~~~~~~ie9:~,fi:;t;8$~f,r.*
RO adjusts 2CV55 to maintain PZR level
>25%.
RO reports PZR level is not stable or risin PO reoorts no faulted SGs. RO opens BIT isolation valves 2SJ4,5, 12, 13, and shuts normal charging line isolation valves 2CV68 and 69. CRS goes to EOP-LOCA-2, Post LOCA Cooldown and Deoressurization. Terminate scenario on direction from Lead Evaluator after the transition to LOCA-2 is made. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 20 of 27 A. Alarm Response Procedures (Various) B. Technical Specifications C. Emergency Plan (ECG) D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-IO.ZZ-0004, Power Operation F. S2.0P-AQB.CVC-0001, Loss of Charging G. S2.0P-AB.RC-0001, Reactor Coolant System Leak H. 2-EOP-TRIP-1, Reactor Trip or Safety Injection I. 2-EOP-TRIP-3, Safety Injection Termination J. 2-EOP-LOCA-1, Loss of Reactor Coolant K. 2-EOP-LOCA-2, Post LOCA Cooldown and Depressurization PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 21of27
,, '.,':.'.-t ,.. . ..,,, ~,:~;/;\:;~~~;;1;.;.;;f;J;;,:--, /'*' "
. ; ,>\{*>.f\,.~*';:"~*;;*l: AITAGHMENT'1*~x V* '".*
*rrtt*~l!~*riWPT~~~T~~~~~~~:rriit. .
MODE: 1 POWER: 100% RCS BORON: 857 MWe 1220 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED): NA REACTIVITY PARAMETERS MOST LIMITING LCO AND DATE/TIME OF EXPIRATION: EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS: ABNORMAL PLANT CONFIGURATIONS: PZR Pressure Channel Ill is selected for Control CONTROL ROOM: Unit 1 and Hope Creek at 100% power. No penalty minutes in the last 24 hrs. PRIMARY: SECONDARY: RADWASTE: No discharges in progress CIRCULATING WATER/SERVICE WATER: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 22 of 27
- 1. Verify simulator is in "TRAIN" Load
- 2. Simulator is in RUN
- 3. Overhead Annunciator Horns ON
- 4. All required computer terminals in operation
- 5. Simulator clocks synchronized
- 6. All tagged equipment properly secured and documented
- 7. TSAS Status Board up-to-date
- 8. Shift manning sheet available
- 9. Procedures in progress open and signed-off to proper step
- 10. All OHA lamps operating (OHA Test) and burned out lamps replaced
- 11. Required chart recorders advanced and ON (proper paper installed)
- 12. All printers have adequate paper AND functional ribbon
- 13. Required procedures clean
- 14. Multiple color procedure pens available
- 15. Required keys available
- 16. Simulator cleared of unauthorized material/personnel
- 17. All charts advanced to clean traces and chart recorders are on.
- 18. Rod step counters correct (channel check) and reset as necessary
- 19. Exam security set for simulator
- 20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out
- 21. Shift logs available if required
- 22. Recording Media available (if applicable)
- 23. Ensure ECG classification is correct
- 24. Reference verification performed with required documents available
- 25. Verify phones disconnected from plant after drill.
- 26. Verify EGC paperwork is marked "Training Use Only" and is current revision.
- 27. Ensure sufficient copies of ECG paperwork are available.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 23 of 27 In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant. The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant. I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...
- degradation of any barrier to fission product release
- degraded emergency core cooling system (ECCS) or emergency power capacity
- a violation of a safety limit
- a violation of the facility license condition
- incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)
- a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...
- effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.
- recognize a failure or an incorrect automatic actuation of an ESF system or component.
- take one or more actions that would prevent a challenge to plant safety.
- prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 24 of 27 SCENARIO IDENTIFIER: 15-01 ILOT NRC ESG-1 REVIEWER: C Recchione Initials Qualitative Attributes CR 1. The scenario has clearly stated objectives in the scenario. CR 2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events. CR 3. The scenario consists mostly of related events. CR 4. Each event description consists of:
- the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position)
- the event termination point CR 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
CR 6. The events are valid with regard to physics and thermodynamics. CR 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. CR 8. The simulator modeling is not altered. CR 9. All crew competencies can be evaluated. CR 10. The scenario has been validated. CR 11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario. CR 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 25 of 27 Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section D.5.d) GG 3 Malfunctions after EOP entry: 1-2 GG 2 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 2 EOPs entered/requiring substantive actions: 1-2 GG 0 EOP contingencies requiring substantive actions: 0-2 GG 2 EOP based Critical tasks: 2-3 COMMENTS: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 26 of 27 15-01 NRC ESG-1 CT#1 (CT-4) Establish the minimum required feed flow prior to a transition to FRHS-1 being required. Basis: Failure to establish the required minimum feed flow rate under the postulated plant conditions, results in "adverse consequence(s) or significant degradation in the mitigative capability of the plant." Failure to perform the critical task represents a "demonstrated inability of the crew to: Take an action or combination of actions that would prevent a challenge to plant safety Recognize a failure I incorrect auto actuation of an ESF system or component." CT#2 (CT-6) Establish flow from at least one high-head ECCS pump before transition out of TRIP-1. Basis: Failure to manually start at least one Charging pump under the postulated conditions constitutes misoperation or incorrect crew performance in which the crew does not prevent "degraded emergency core cooling system (ECCS) ... capacity." In this case, at least one Charging/SI pump (high-head SI pump for LP plants) can be manually started from the control room. Therefore, failure to manually start a Charging/SI pump (high-head SI pump for LP plants) also represents a failure by the crew to "demonstrate the following abilities: Effectively direct or manipulate engineered safety feature (ESF) controls that would prevent a significant reduction of safety margin beyond that irreparably introduced by the scenario Recognize a failure or an incorrect automatic actuation of an ESF system or component" Additionally, under the postulated plant conditions, failure to manually start a Charging/SI pump (high-head SI pump for LP plants) (when it is possible to do so) is a "violation of the facility license condition." Note to Evaluators: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Task procedure WCAP-17711-NP PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 27 of 27 EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out y LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TP/'111\1 N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s) N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.
Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-2 Op-Test No.: 15-01 NRC Examiners: Operators: Initial Conditions: 89.4% power, MOL. Xenon is building in at 25 pcm/hour. 2C EDG Jacket Water heater is C/T after failing yesterday. Turnover: Power is reduced in preparation for performing Main Turbine Valve testing later in shift. Maintain current power. Event Malf. No. Event Event Type* No. Description 1 AN0266 c 2C EDG Pre-lube pump failure (TS) CRS 2 CN0117C c 23 Condensate pump trip CRS I PO R 3 CRS/RO Down power N PO 4 SG0078A c SGTL (TS) ALL M 5 SG0078A SGTR ALL 6 RC0003C c 23 RCP trip during cooldown RC0003A ALL 7 VL0123 c PZR PORV fails to shut during RCS depressurization CRS/RO
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
TQ-AA-106-0204 Page 1 of 31 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 15-01 NRC ESG-2 SCENARIO NUMBER: 15-01 NRC ESG-2 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 00 PROGRAM: .____ __.I LO. REQUAL X I INITIAL LICENSE
..__ __.! STA
~-~'OTHER Revision Summary New issue for 15-01 ILOT NRC exam PREPARED BY: G Gauding 8-3-16 Lead Regulatory Exam Author Date APPROVED BY: tJlvFl f "b'i?f<_,
raining Manager ate APPROVED BY:
~ aclHty Repre ~./.[/u,'
atlve 10Ll1 LL~ v I date PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 2 of 31
TQ-AA-106-0204 Page 3 of 31 A. Given a loss of a heater drain pump or condensate pump, take corrective action IAW S2.0P-AB.CN-0001. B. Given the order or indications of a feedwater or condensate system malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with S2.0P-AB.CN-0001. C. Given indication of a feedwater or condensate system malfunction, DIRECT the response to the malfunction in accordance with S2.0P-AB.CN-0001. D. Given a steam generator tube leak, take corrective action, IAW S2.0P-AB.SG-0001. E. Given the order or indications of a steam generator tube leak (SGTL), perform actions as the nuclear control operator to RESPOND to the tube leak in accordance with S1/S2.0P-AB.SG-0001. F. Given the order or indications of a steam generator tube leak (SGTL), DIRECT the response to the tube leak, in accordance with S2.0P-AB.SG-0001. G. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1. H. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1. I. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures. J. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures. K. Given the order or indications of a steam generator tube rupture (SGTR), perform actions as the nuclear control operator to RESPOND to the tube rupture in accordance with the approved station procedures. L. Given indication of a steam generator tube rupture (SGTR), DIRECT the response to the SGTR in accordance with the approved station procedures. A. 2C EOG Pre-lube pump failure (TS) B. 23 Condensate pump trip C. Power Reduction D. 21 SGTL I 21 SGTR E. Loss of Spray during RCS depressurization F. Stuck open PZR PORV during RCS depressurization PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 4 of 31 A. The crew will take the watch with the unit at 89.4% power, SOL. Power was reduced last shift in preparation for performing Main Turbine Valve testing later this shift. 2C EOG Jacket Water heater failed last shift. Condensate Polisher is in service. B. After the crew assumes the watch, the 2C EOG Pre-lube pump will fail. The CRS will identify 2C EOG is now inoperable, and enter the appropriate LCO. The CRS will initiate actions to ensure S2.0P-ST.500-0001, Electrical Power Systems AC Sources Alignment is performed within one hour. C. After the EOG failure has been addressed, 23 Condensate pump will trip. The crew will enter 82.0P-AB.CN-0001, Main Feedwater I Condensate System Abnormality, and perform actions to bypass the polisher and feedwater heaters strings as required to maintain SGFP suction pressure. D. The crew will perform a power reduction to,::: 85% power and ensure SGFP suction pressure remains above 320 psig. E. During the power reduction, a SGTL will occur on 21 SG. The crew will enter S2.0P-AB.SG-0001, Steam Generator Tube Leak. The crew will perform actions to minimize the spread of secondary contamination and minimize the potential for steam release from the affected SG. The crew will isolate the steam supply to 23 AFW pump from 21 SG, and the CRS will identify 23 AFW is inoperable and enter the appropriate LCO. F. After the AFW pump LCO is identified, the SG tube will rupture. The crew will identify the SGTR, and initiate a Rx trip and Safety Injection based on the uncontrolled rise in 21 SG NR or WR level. G. The crew will perform plant stabilization and diagnostics in EOP-TRIP-1, Reactor Trip or Safety Injection. 21 AFW pump will trip shortly after starting. The crew will isolate AFW flow to and steam flow from 21 SG. (CT-1 ). H. The crew will transition to EOP-SGTR-1, Steam Generator Tube Rupture to address the tube rupture. The crew will perform a cooldown to target temperature and demonstrate the ability to maintain RCS temperature< Target temperature (CT-2). The crew will initiate a RCS depressurization. During the depressurization the RCP providing driving head for Spray flow will trip. The crew will open a PZR PORV to continue the depressurization. If 2PR1 is the selected PORV, it will not open, and 2PR2 will be used. I. The PZR PORV opened to depressurize the RCS will fail to shut when demanded after the depressurization is complete. The crew will attempt to terminate the depressurization by closing the PORV Block valve, which will not shut. J. The scenario will be terminated after the CRS transitions to EOP-SGTR-3, SGTR with LOCA-Subcooled Recovery, to address the loss of RCS pressure with the stuck open PORV. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 5 of 31 IC-232 Initial j Description 1 VC1and VC4 CIT 2 RCPs (SELF CHECK) _ 3 RTBs (SELF CHECK) _ 4 MS167s (SELF CHECK) _ 5 500 KV SWYD (SELF CHECK) _ 6 SGFP Trip (SELF CHECK) _ 7 23 CV PP (SELF CHECK) 8 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist." Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Pa e 6 of 31 Description EVENT ACTION: MONP254 <10. //CONTROL BANK C GROUP POSITION 1 COMMAND: PURPOSE: <update as needed> ~-~-~~+--~~~~~~~1~~~~~~~~~~~~~~~~~~---~-~~~~~~~~~--- EVENT ACTION: KB202LCI //2PR7 RELIEF VALVE-22 STOP VALVE 3 COMMAND: PURPOSE: <update as needed> SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time SER POINT AN0266 SER 266 FAILS - :J20 2C DIESEL 01 NiA NIA N/A RT-1 FAILS/OVRD GENERATOR URGENT TROUBLE TOON 02 CN0117C 23 CONDENSATE PUMP TRIP NIA N/A N/A RT-3 03 SG0078A 21 STEAM GENERATOR TUBE RUPTURE NIA N/A NIA RT-5 5 AAS POINT 04 AN3735 AAS 735 FAILS - :21 TGA SUMP LEVEL HIGH 00:03:00 N/A NIA RT-11 FAILS/OVRD TOON AAS POINT 05 AN3736 AAS 736 FAILS - :22 TGA SUMP LEVEL HIGH 00:03:10 N/A N/A RT-11 FAILS/OVRD TOON AAS POINT 06 AN3737 AAS 737 FAILS - :23 TGA SUMP LEVEL HIGH 00:03:20 N!A NIA RT-11 FAILS/OVRD TOON AAS POINT 07 AN3738 AAS 738 FAILS - :24 TGA SUMP LEVEL HIGH 00:03:30 NIA N/A RT-11 FAILS/OVRD TOON AAS POINT 08 AN3739 AAS 739 FAILS - :25 TGA SUMP LEVEL HIGH 00:03:50 N/A NIA RT-11 FAILS/OVRD TOON 09 AF0181A 21 AUX FEEDWATER PUMP TRIP 00:04:00 NIA NiA ET-1 10 VL0297 2PR1 Fails to Position 0-100% N/A N/A NIA N/A 0 11 VL0298 2PR2 Fails to Position 0-100% NIA NfA NIA RT-13 100 12 RC0003C 23 RC PUMP ELECTRICAL TRIP NIA NIA N/A RT-7 13 RC0003A 21 RC PUMP ELECTRICAL TRIP NIA NIA NIA RT-9 14 VL0123 2PR7 Fails to Position 0-100% N/A NIA N/A ET-3 90 SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time 01 SP01A1 Prevailin Wind Speed N/A N/A NIA NIA 10 02 SP01A2 Prevailin Wind Direction NIA N/A NIA N/A 160 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 7 of 31 SELF- Description Delay Initial Ramp Trigger Condition/ CHECK Time Value Time Severity C201 A LO QC201AY3 2C DIESEL GEN-TROUBLE 01 N/A N/A NIA ON ALARM
- 1. None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 8 of 31 A. State shift job assignments. B. Hold a shift briefing, detailing instruction to the shift (provide crew members a copy of the shift turnover sheet). C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time. CRS please inform me when your crew is ready to assume the shift". D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 9 of 31
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- 1. 2C EOG Pre-Lube pump failure PO announces unexpected OHA J-20, 2C DG URGENT TRBL.
The crew refers to the ARP and dispatches an operator to investiaate. Role play: 2 minutes after being dispatched call control room and report 2C EDG Alarm Window A-7 PRE-LUBE PUMP FAILURE is in alarm. You have checked the Pre-lube pump and it is NOT running. The Pre-lube pump breaker remains shut. CRS refers to S2.0P-SO.DG-0003, 2C Diesel Generator Operation and recognizes 2C EOG is now inoperable with the Jacket Water Heater and Pre-lube pump inoperable, and enters LCO 3.8.1.1.b, action b. CRS determines that S2.0P-ST.500-0001, Electrical Power Systems AC Sources Alianment must be performed within one hour PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 10 of 31 to demonstrate the operability of the independent AC Sources (action b.1 Proceed to next event on direction from Lead Evaluator.
- 2. 23 Condensate pump trip
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- pqmp;;tr1 ptv CRS enters S2.0P-AB.CN-0001, Main Feedwater I Condensate Svstem Abnormal it..
PO reports no SGFP tripped. PO re PO bypasses condensate polisher by opening 21 thru 23 CN108 if SGFP suction pressure is
<320 Psia.
Role Play: If dispatched, after 3 minutes report as NEO that you can't see anything wrong with 23 condensate pump. If dispatched to 4KV breaker, report after 2 minutes that there is an overcurrent relay flag dropped. PO reports SGFP suction pressure. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA* 1 u6*0204 Paae 11 of31 Note: Crew. should discuss power increase expected when the CN47 is opened. (Note in AB.CN-1 ). CRS directs 2CN47 opened if suction ressure remains < 320 osi~. PO isolates letdown by closing 21-24GB4 and 21-24GB185 if 2CN47 is ooen. CRS directs power reduction to 85% at _:::5%/min with 2 Condensate pumps and 3 Heater Drain pumps in service IAW Attachment 2. CRS enters 82.0P-AB.LOAD-0001, Rapid Load Reduction, to perform the load reduction. CRS directs initiation of AB.LOAD CAS. RO calculates boron addition and rate for ower reduction. RO initiates boration. PO initiates turbine load reduction to 85% at rate directed bv CRS. RO announces auto rod motion when it occurs. Proceed to next event on direction PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 12 of 31 from Lead Evaluator.
- 3. 21 SG Tube Leak RO reports unexpected OHA A-6 and identifies 2R53A 21 Main Steamline N2 monitor from CRT indication in alarm.
RO reports 2R53A level >1Q_QO gpd. CRS enters S2.0P-AB.SG-0001, Steam Generator Tube Leak, and S2.0P-AB.RAD-0001, Abnormal Radiation. RO reports OHA A-6 reflash is 2R15 Condenser Air Eiector monitor in alarm. CRS directs initiation of AB.SG CAS. RO reports when 2R19A is in warning and alarm. PO reports when SGBD isolation occurs on hiqh radiation. CRS dispatches operator to isolate TGA and Condensate Polisher area sum PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 13 of 3 RO reports PZR level being maintained stable bv risina charaina flow. Note: Initial charging flow with stable PZR level is -89 gpm. 23 charging pump will deliver -99 gpm at full flow and seal injection of -26 gpm. IF RO reports PZR level is lowering (due to lag in Master Flow control response,) then RO will swap to a centrifugal charging pump at Step 3.6. RO reports PZR level can be maintained stable or risin~. Note: SGBD will isolate -2.5 minutes after 2R53D alarms. This will cause RCS temp and PZR level to rise. PO reoorts when load reduction is comolete. RO reports unit 2 is in MODE 1. RO reoorts 21 SG is affected SG. PO sets 21 MS 10 to 1045 osia, and ensures PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 14 of 31 21 GB4, 21MS18, and 21 MS? are shut. CRS dispatches an operator to shut 21 MS45 steam suoolv to 23 AFW oum~. Note: Do NOT report the 21 MS45 is shut until AFTER 23 AFW pump has been tripped at step 4. 7 of SGTR-1. CRS enters LCO 3.7.1.2 for less than 3 operable AFW pumps, and LCO 3.4.7.2.c for
>150 gpd primary to secondary leakage thouah 21 SG.
CRS determines (Action Level 3) the unit must be less than 50% in less than one hour, the unit olaced in Hot Standbv within 6 hours. CRS dispatches an operator to realign SGBD and Samolina. Proceed to next event on direction from Lead Evaluator after Tech Specs have been addressed.
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<on.<;1ir:ecf1oci frarrreL.esrC! .Eva]O'ator, RO reports indications of worsening tube leak/rupture, with lowering PZR level and ressure. CRS directs RO to trio the Rx, confirm the Rx PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 15 of 31 trip, and initiate a Safety Injection, then enter TRIP-1. RO trips the Rx, confirms the Rx trip, and initiates Safetv lniection.
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1 RO backs up the Main Turbine trip, reports 4KV vital buses energized, and reports SI manuallv initiated. CRS and RO verifv TRIP-1 immediate actions. PO receives CRS concurrence and isolates AFW to 21 SG by closing 21AF11 and 21AF21. PO receives CRS concurrence and reduces total AFW flow to no less than 22E04 lbm/hr until at least one SG NR level is> 9%, then PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 16 of 31 PO reports when 21 AFW pump trips, and adjusts flow from 22 and 23 AFW pumps as reauired based on current SG NR levels. Note: 21 AFW pp supplies 23/24 SGs 22 AFW pp supplies 21/22 SGs 23 AFW pump supplies all SGs PO reports all available equipment started on SEC loadina. PO reoorts which AFW s are runnin PO reports correct safeguards valve alignment. RO reports 21 and 22CA330s are shut. RO reports containment pressure remains less than 15 osia. PO reoorts no indication of hi steam flow. PO reoorts all 4KV vital buses eneraized. RO reports ventilation svstems lineuos correct PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 17 of 31 RO reports at least 2 CCW pumps are runnina. RO reports proper ECCS flow indicated for current olant conditions. PO reports AFW status, and maintains at least 22E4 lbm/hr flow until at least one SG NR level is >9%, then maintains SG NR levels 19-33%. RO reports RCP status, and RCS temoerature stable at or trendina to 547°. RO reports both RTBs are open. RO reports PZR PORVs are shut with Block valves ooen. RO reports PZR spray status for current plant conditions. ressure is >1350 osi RO maintains seal iniection flow to RCPs. PO reoorts no SGs are faulted. PO reoorts NR or WR level is risina in 21 SG. CRS transitions to EOP-SGTR-1, Steam Generator Tube Ruoture. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 18 of 31 Note: STA will report to Control Room 1O minutes after being paged to report, and initiate monitoring of CFSTs. RO maintains seal iniection flow to all RCPs. PO reports 21 SG is ruptured, and ensures 21MS10 is set at 1045 osia. PO reports 21 MS10 operating as expected for current pressure. PO shuts 21MS167, and verifies 21MS7, 21 MS18, and 21 GB4 are shut. Note: These steps complete CT#1 PO reoorts 21 SG is ruptured. PO reports 23 AFW pump is not the only source of AFW. PO ensures 23 AFW pump speed at minimum and trios 23 AFW CRS dispatches operator to shut 21 MS45 if PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 19 of 31 CRS dispatches operator to shut 2SS321 samole valve. PO reports 21 SG is isolated from all intact SGs. PO controls AFW flow if required to maintain 21 SG NR level >9%. PO reoorts 21 SG oressure is >375 osi CRS determines target temperature from Table D. (503°F for ruptured SG pressure
~1000 osia.
PO reports intact SGs are available for cooldown. PO reports steam dumps are available, and places in MS Pressure Control-Manual at 25% to oerform cooldown. PO bypasses Tavg when Tavg Low-Low is reached. Crew monitors hottest CET temperature while continuina in orocedure. Note: When hottest CET is <503°F, crew will stop cooldown with steps PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 20 of 31 on next page. RO reports power is available to both PZR PORV Stop valves, both PZR PORVs are shut, and both PZR PORV Stop valves are ooen. RO resets SI and Phase A isolation, and reoorts Phase B isolation reset. RO ooens 21 and 22CA330. PO resets each SEC and reports 230V control centers are reset. RO reports RHR suction is aligned to the RWST and no RHR oumo discharae flow. RO stoos both RHR S. PO reports 21 SG is ruptured and 21MS167 is shut. RO shuts charging pump mini flows when RCS oressure is < 1500 osi~. RO reports when hottest CET is less than RCS cooldown taraet tern~.
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TQ-AA-106-0204 Page 21 of 31 PO reoorts 21 SG oressure is stable or risin RO re RO reoorts normal PZR SRrav is available. RO fullv ooens both PZR Sorav Valves. RO reports PZR Spray is reducing RCS ressure. Crew continues deoressurization. ' llt~f~j11~;:~~~~ 1 RO reports 23 RCP tri~. Note: The crew is in a "do loop" when reducing RCS pressure using spray, and will return to Step 19.2 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 22 of 31 RO shuts both PZR Sorav valves. RO reoorts both PZR PORVs are available. Crew reviews deoressurization criteria. CRS directs RO to open onlv one PORV. IF 2PR1 is selected as the PORV to deoressurize, RO reoorts 2PR1 will not ooen. RO ooens 2PR2. '.;:J * ,-, '.;,:~, "~;:* t ..: :* ri.4**--:*7~---:-~---------,-,--~-,c~ 1;;;:"0.Tf"-"-T-----~":-----~-------.,; .: ,
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~~1~fr~ti~~nl~~~~%~}***:.;!*~*~;~!~r RO reoorts when condition in Table E is met.
RO reoorts 2PR2 will not shut. CRS directs closure of 2PR7 PZR PORV Block Valve. ?~?J!iJii~~iif PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 23 of 31 RO reports that after initiating closed on 2PR7, the open limit extinguished but the closed limit has not illuminated. CRS transitions to EOP-SGTR-3, SGTR with LOCA - Subcooled Recoverv. Terminate the scenario when the transition to SGTR-3 is announced. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 24 of 31 A. Alarm Response Procedures (Various) B. Technical Specifications C. Emergency Plan (ECG) D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-IO.ZZ-0004, Power Operation F. S2.0P-SO.DG-0003, 2C Diesel Generator Operation G. S2.0P-ST.500-0001, Electrical Power Systems AC Sources Alignment H. S2.0P-AB.SG-0001, Steam Generator Tube Leak I. S2.0P-AB.LOAD-0001, Rapid Load Reduction J. 2-EOP-TRIP-1, Reactor Trip or Safety Injection K. 2-EOP-SGTR-1, Steam Generator Tube Rupture PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 P,age 25 of 31 MODE: 1 POWER: 89.4% RCS BORON: 1114 MWe 1080 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED): NA REACTIVITY PARAMETERS Control Bank D is at 193 steps. Xenon is building in at 25 pcm I hr following downpower last shift MOST LIMITING LCO AND DATE/TIME OF EXPIRATION: EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS: S2.0P-PT.TRB-0003, Main Turbine Valve testing is being briefed by a dedicated test team to be performed in one hour. ABNORMAL PLANT CONFIGURATIONS: 2C EOG Jacket Water heater is failed and CIT. CONTROL ROOM: Unit 1 and Hope Creek at 100% power. No penalty minutes in the last 24 hrs. PRIMARY: SECONDARY: Condensate Polisher is in service RADWASTE: No discharges in progress CIRCULATING WATER/SERVICE WATER: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 26 of 31
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StMULATOR .* :\~~~~ ~o'~*rRi1~/~a*b~~*6KLIST
- 1. Verify simulator is in "TRAIN" Load
- 2. Simulator is in RUN
- 3. Overhead Annunciator Horns ON
- 4. All required computer terminals in operation
- 5. Simulator clocks synchronized
- 6. All tagged equipment properly secured and documented
- 7. TSAS Status Board up-to-date
- 8. Shift manning sheet available
- 9. Procedures in progress open and signed-off to proper step
- 10. All OHA lamps operating (OHA Test) and burned out lamps replaced
- 11. Required chart recorders advanced and ON (proper paper installed)
- 12. All printers have adequate paper AND functional ribbon
- 13. Required procedures clean
- 14. Multiple color procedure pens available
- 15. Required keys available
- 16. Simulator cleared of unauthorized material/personnel
- 17. All charts advanced to clean traces and chart recorders are on.
- 18. Rod step counters correct (channel check) and reset as necessary
- 19. Exam security set for simulator
- 20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out
- 21. Shift logs available if required
- 22. Recording Media available (if applicable)
- 23. Ensure ECG classification is correct
- 24. Reference verification performed with required documents available
- 25. Verify phones disconnected from plant after drill.
- 26. Verify EGC paperwork is marked "Training Use Only" and is current revision.
- 27. Ensure sufficient copies of ECG paperwork are available.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 27 of 31
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3: CRITICAL TASK M'ETHd6~~bd~I~ }'* : In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant. The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant. I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...
- degradation of any barrier to fission product release
- degraded emergency core cooling system (ECCS) or emergency power capacity
- a violation of a safety limit
- a violation of the facility license condition
- incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)
- a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...
- effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.
- recognize a failure or an incorrect automatic actuation of an ESF system or component.
- take one or more actions that would prevent a challenge to plant safety.
- prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 28 of 31 SCENARIO IDENTIFIER: 15-01 ILOT NRC ESG-2 REVIEWER: C Recchione Initials Qualitative Attributes CR 1. The scenario has clearly stated objectives in the scenario. CR 2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events. CR 3. The scenario consists mostly of related events. CR 4. Each event description consists of:
- the point in the scenario when it is to be initiated
- the malfunction( s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position)
- the event termination point CR 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
CR 6. The events are valid with regard to physics and thermodynamics. CR 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. CR 8. The simulator modeling is not altered. CR 9. All crew competencies can be evaluated. CR 10. The scenario has been validated. CR 11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario. CR 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 29 of 31 Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section D.5.d) GG 2 Malfunctions after EOP entry: 1-2 GG 3 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 1 EOPs entered/requiring substantive actions: 1-2 GG 0 EOP contingencies requiring substantive actions: 0-2 GG 2 EOP based Critical tasks: 2-3 COMMENTS: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 30 of 31 15-01 ILOT NRC ESG-2 CT#1 (CT-18) Isolate feed flow into and steam flow from 21 SG prior to a transition to SGTR-3 being required. Basis: Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. The fact that the crew allows the differential pressure to dissipate and, as a result, are then forced to transition to a contingency ERG constitutes an incorrect performance that "necessitates the crew taking compensating action that would complicate the event mitigation strategy.... " CT #2: (CT-19) Establish and maintain an RCS temperature so that transition from SGTR does not occur because temperature is too high to maintain minimum subcooling, or so low it causes transition to FRTS or FRSM. Basis: Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to a contingency ERG. This failure constitutes an incorrect performance that "necessitates the crew taking compensating action that would complicate the event mitigation strategy.... " Note to Evaluator: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Tasks procedure WCAP-17711-NP PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 31 of 31 EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water y Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TD.1\.111.1 N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area y Any Diesel Generator N RHR Suction Line valves from Hot Leg y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST Y Cooldown the RCS and depressurize the system y Isolate the affected Steam Generator that has the tube rupture(s) N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.
Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-3 Op-Test No.: 15-01 NRC Examiners: Operators: 8 Initial Conditions: 1x10- Amps during startup at BOL. 25 CFCU CIT. 23 Charging pump CIT. Turnover: Raise power to 2%. Event Malf. No. Event Event No. Type* Description I 1 PR0016A Controlling PZR Pressure Instrument fails high (TS) CRS/RO 2 RD0267 c Dropped control rod (TS) CRS/RO M Steam Rupture in containment on 21 SG during rod 3 MS0090Ar21 ALL insertion RP0277A RP0277B 4 MS0092E c ALL MSIVs fail to shut MS0092F ALL MS0092G MS0092H 5 AF0181A c 21 AFW pump trip CRS/PO 6 RP318L 1 c Containment Spray pumps fail to start RP318L2 ALL Appendix D, Page 38 of 39
TQ-AA-106-0204 Page 1of29 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 15-01 NRC ESG-3 SCENARIO NUMBER: 15-01 NRC ESG-3 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 00 PROGRAM: ~-~' LO. REQUAL X ! INITIAL LICENSE
~~*!STA I I OTHER Revision Summary New issue for 15-01 ILOT NRC exam PREPARED BY: G Gauding 8-11-16 Lead Regulatory Exam Author Date APPROVED BY: rlV\ (o/~J<.,
'Date APPROVED BY:
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aciiifyResentative afiti:/' 1 ate PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 2 of 29
TQ-AA-106-0204 Page 3 of 29 A. Given the order or indications of a pressurizer control system malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with S1/S2.0P-S2.0P-AB.PZR-0001. B. Given indication of a pressurizer control system malfunction, DIRECT the response to the malfunction in accordance with S2.0P-AB.PZR-0001. C. Given indication of a dropped control rod perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with S2.0P-AB.ROD-0002. D. Given indication of a dropped control rod DIRECT the response to the malfunction in accordance with S2.0P-AB.ROD-0002. E. Given the order or indications of a loss of secondary coolant, perform actions as the nuclear control operator to RESPOND to the coolant loss in accordance with EOP-LOSC-1. F. Given indication of a loss of secondary coolant, DIRECT the response to the loss of secondary coolant, in accordance with EOP-LOSC-1. G. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1. H. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1. I. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures. J. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures. K. Given the order or indications of a multiple steam generator depressurization, perform actions as the nuclear control operator to RESPOND to the generator depressurization in accordance with EOP-LOSC-2. L. Given indication of a multiple steam generator depressurization, DIRECT the response to the generator depressurization in accordance with EOP-LOSC-2. A. Controlling PZR Pressure Instrument fails high B. Dropped control rod C. Steam Leak/Rupture in containment PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 4 of 29 A. The crew will take the watch with the unit stable at 1x1 o-s Amps during a plant startup, BOL. 21 SGFP is in service and 22 SGFP is O/S. Steam dumps are in MS Pressure Control -Auto
@ 1,000 psig. 25 CFCU is CIT for maintenance. 23 charging pump is CIT for emergent maintenance. The crew will be instructed to raise power to 2%.
B. After assuming the watch and before the power ascension is started, the controlling PZR Pressure instrument will fail high, deenergizing PZR heaters and causing both PZR Spray valves to open fully. The crew will respond IAW S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction to establish manual control of PZR pressure control and restore pressure to normal, swap to an operable channel, and remove the failed channel from service. The CRS will identify applicable LCO's. C. After the Pressurizer Pressure control system failure has been addressed, a control rod will drop fully into the core. The crew will respond IAW S2.0P-AB.ROD-0002, Dropped Rod. The crew will identify the Rx is subcritical, and initiate control rod insertion to fully insert all Control and Shutdown rods. The CRS will identify applicable LCO's. D. During the rod insertion, a steam leak in containment will occur on 21 SG. The crew will diagnose changing containment conditions, and determine a Rx trip is required and MSLI will be required in an attempt to isolate the steam leak. E. The crew will trip the Rx. The steamline will rupture. MSLI (auto and manual) will fail to shut any MSIV. The crew will initiate Safety Injection when it is identified that the source of the steam leak is not isolated. F. The crew will perform plant stabilization actions in EOP-TRIP-1, Reactor Trip or Safety Injection. With all SGs faulted, the crew will maintain AFW flow to each SG. 21 AFW pump will trip during TRIP-1 performance. Containment Spray pumps will not automatically start when demanded on hi-hi containment pressure, and the crew will manually start at least one CS pump (CT-1 ). The crew will transition to EOP-LOSC-1, Loss of Secondary Coolant. G. The crew will transition to EOP-LOSC-2, Multiple Steam Generator Depressurization with all SG's faulted. H. The crew will identify the RCS cooldown rate of >100°F I hr, and control AFW flow to minimize RCS cooldown (CT-2). The crew will reset Safeguards. When evaluating SI Flow Reduction Criteria, local operators will successfully shut a MSIV. The crew will recognize rising pressure in that SG, and transition to LOSC-1. I. The scenario will be terminated upon transition to LOSC-1. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 5 of 29 IC-233 1 VC1and VC4 CIT 2 RCPs (SELF CHECK) _ 3 RTBs (SELF CHECK) _ 4 MS167s (SELF CHECK) _ 5 500 KV SWYD (SELF CHECK) _ 6 SGFP Trip (SELF CHECK) _ 7 23 CV PP (SELF CHECK) __ 8 21 Charging pump in service 9 25 CFCU CIT _ 10 23 Charging pump CIT _ 11 IOP-3 open and complete up to Section 4.3, Power Operation. 12 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist." PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 6 of 29 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group Description EVENT ACTION: MONP254 <10 II CONT ROD BANK C < 10 ( RX TRIP ) 1 COMMAND: PURPOSE: <update as needed> SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time 01 PR0016A PZR PRESS CH I PT455 FAILS H/L NiA N/A NIA RT-1 2500 02 RD0267 ANY RODS INADVERTENTLY DROPS NIA NIA NIA RT-3 3 MS0090Ar 21 Main Steam Line Leak Inside Cont 03 NIA NIA NIA RT-5 2 AFTER orifice 04 RP0279A AUTO MSUS FAILS TO ACT, TRNA NIA NIA NIA N/A 05 RP0279B AUTO MSLIS FAILS TO ACT, TRN B N/A NIA NIA NIA 06 MS0092E 21MS167 FAILS OPEN NiA NIA NIA N/A 07 MS0092F 22MS167 FAILS OPEN N!A NIA N/A NIA 08 MS0092G 23MS167 FAILS OPEN N/A NIA N/A NIA 09 MS0092H 24MS167 FAILS OPEN NIA NIA NIA NIA 10 RP0274A AUTO SI FAILS TO ACT, TRNA NIA N/A N/A NIA 11 RP0274B AUTO SI FAILS TO ACT, TRN B Nii\ NIA N/A N/A 12 AF0181A 21 AUX FEEDWATER PUMP TRIP 00:05:00 N/A NIA ET-1 13 RP318L 1 21 CS Pump Fails to Start on SEC NIA NIA NIA NIA 14 RP318L2 22 CS Pum Fails to Start on SEC NIA N/A NIA NIA SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time 01 CV52D 23 CHG PUMP BKR CONTROL POWER N/A NIA NIA NIA OFF 02 PR34D PORV STOP VALVE 2PR6 TAGGED N/A NIA NIA RT-7 TAGGED 03 SP01A1 Prevailin Winds eed NIA NIA N!A NIA 10 04 SP01A2 Prevailin Wind Direction NIA NIA NIA NIA 160 05 CT195-1D 25 CFCU BKR #1 Hi h S eed 125VDC NIA NIA NIA N/A OFF 06 CT195-2D 25 CFCU BKR #2 Hi h Speed 125VDC N/A NIA NIA NIA OFF PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 7 of 29 07 I CT195-3D 2S CFCU BKR #3 Low Speed 125VDC N/A NiA N/A I NIA I OFF I SELF- Description Delay Initial Ramp Trigger Condition/ CHECK Time Value Time Severity 01 Cl11 CLO QCl11HR2 TURNING GEAR-ENGAGED N/A NIA NIA N/A ON 02 Cl11 E LO QCl11PR2 TURNING GEAR-STARTED N/A N/A N/A N/A ON 03 Cl11 FLO QCl11TG2 TURNING GEAR-STOPPED N!A NIA NIA N/A OFF 04 Cl11 D LO QCl11LG2 TURNING GEAR-DISENGAGED N/A NIA NIA N/A OFF
- 1. None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 8 of 29 A. State shift job assignments. B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet). C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time. CRS please inform me when your crew is ready to assume the shift". D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 9 of 29
- 1. Controlling PZR pressure instrument fails HIGH
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RO announces unexpected OHA alarms D-8 RC Press HI, and E-42 2PR1 % Tri~. RO determines actual pressure is not high and reports spray valves open, and recommends lacina Master Pressure Controller in manual. CRS directs RO to place Master Pressure Controller in manual. RO takes manual control of Master Pressure controller, and lowers demand (increase ressure) to close soravs. CRS enters S2.0P-AB.PZR-001, Pressurizer Pressure Malfunction. CRS directs initiation of AB.PZR CAS. CRS aives band for control of PZR oressure. RO identifies PZR Press Channel I failed hiah. RO selects Channel Ill for control. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 10 of 29 i1antlstUaent,*R£i&'<~"rfije.
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RO matches master pressure controller demand to current pressure and returns Master Pressure Controller to AUTO. RO shuts 2PR6. Note: The requirement to shut 2PR6 and deenergize it is within one hour of the PZR Pressure Channel I instrument failure IAW Tech Specs. CRS directs WCC to remove power from 2PR6. CRS directs PO to initiate removing failed channel from service and contact l&C for support IAW S2.0P-SO.RPS-003. PO checks that tripping associated bistables will not result in an ESF or RPS actuation. Note: Crew may wait for l&C response before performing any actions in S2.0P-SO.RPS-0003. PO verifies that Channel Ill is selected for Master Pressure Control. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 11of29 PO selects PZR Pressure recorder to channel other than I. CRS enters TSAS 3.3.1.1 Action 6, 3.3.2.1.b Action 19*, 3.4.5.b, and 3.2.5. Proceed to next event on direction from Lead Evaluator.
- 2. Dropped control rod RO reports unexpected OHA E-48 ROD BOTTOM, and reports Shutdown Bank rod 1SA3 rod bottom liaht is illuminated.
CRS enters S2.0P-AB.ROD-0002, Dropped Rod. RO reports control rods are in manual. PO reports Main Turbine is S/D. RO reports the reactor is subcritical as a result of the dropped rod. CRS directs RO to insert all control and shutdown bank rods. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 12 of 29 RO initiates insertion of control rods in manual.
- 3. 21 SG steam leak I rupture in containment PO announces OHA C-38, CFCU LK DET HI as unexpected, and shortly after, OHA C-30, CFCU LK DET HI-HI as well.
PO refers to ARP for OHA C-38 and C-30. PO reports indications of a steam leak inside containment including: Containment pressure rising Tavg slowly lowering Rising steam flows on all loops Steam dumo demand lowerin CRS enters S2.0P-AB.STM-0001, Excessive Steam Flow. CRS directs monitorina of AB.STM CAS. CRS notifies Emergency Services of the steam leak. PO reports that the Main Turbine is not PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 13 of 29 latched. PO reports no indication of MS1 O or steam dumo valves malfunction. RO reports no indication of a SG Safety Valve artiallv ooen or leakina. RO reports Rx power and RCS temperature are NOT stable. CRS directs the RO to trio the Rx. Note: A MSLI will be required to attempt to isolate the steam leak in containment. The CRS can use the CAS of AB.STM for direction, or will use Step 11 in TRIP-1 when containment pressure exceeds 15 psig. Auto and Manual MSLI are failed and will not actuate. RO trips the Rx and confirms the Rx tri~. Simulator Operator: Ensure ET-1 is true upon the Rx trip. This trips 21 AFW pump after a 5 minute delay. IF usina AB.STM CAS, then RO will attemot a PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 14 of 29 IF using AB.STM CAS, RO reports the steam leak is NOT isolated. RO continues Immediate Actions of TRIP-1: Reports the Main Turbine is tripped. Reports all 4KV vital buses are energized. Reports a demand for Safety Injection is present and Safety Injection has NOT actuated (or reports Safety injection was manually initiated as described in revious ste~ .. RO initiates Safety Injection (if not previously erformed. Note: With all SGs faulted, AFW flow should not be isolated to any SG. PO reoorts SEC loadina is not comolete. PO reoorts all available eauioment started. PO reports 21 and 22 AFW pumps are running, and if not previously performed, receives permission to throttle total AFW flow to no less than 22E4 lbm/hr. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 15 of 29 PO reports valve groups in Table B are in Safeauards oosition. RO reoorts 21 and 22CA330 are shut. PO reports when 21 AFW pump trips, and adiusts AFW flow if reauired. RO reports containment pressure has not remained less than 15 psi~. RO initiates Phase B and Sprav actuation. RO reports neither Containment Spray pump has started. RO blocks 2A and 2C SECs. PO resets 2A and 2C SEC's. RO starts 21 and 22 CS oumos. RO reoorts MSLI has failed to close anv MSIV. RO stops all RCPs. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-1 UG-0204 Page 16 of 29 RO reports MSLI has failed to close any MSIV. CRS dispatches operators to place valves from Table D (locally close MSIVs) in safeguards position if not previously erformed. PO reoorts all 4KV vital buses are eneraized. RO reports control room ventilation is in Accident Pressurized mode. RO reports 2 switchgear supply and 1 exhaust fan are runnina. RO reoorts 2 CCW RO reports ECCS flow as expected for current RCS oressure. PO maintains total AFW flow greater than 22E4 lbm/hr until at least one SG NR level is
>15% (adverse), then maintains SG NR level 19-33%.
RO reoorts no RCPs are runnin RO reoorts RCS Tcolds are dro PO reoorts no dumoina steam. RO reoorts MSLI failed to isolate anv MSIV. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 17 of 29 RO reoorts both PZR PORVs are closed. RO reoorts 2PR6 is shut, and 2PR7 is ooen. CRS dispatches operator to restore power to 2PR6 if deeneraized. RO reoorts no RCPs are runnin RO maintains seal iniection flow to all RCPs. PO reports all SG pressures are dropping in an uncontrolled manner with MSLI failure. CRS transitions to EOP-LOSC-1, Loss of Secondarv Coolant. Note: CFSTs are in effect when transition out of TRIP-1 occurs. STA will report to control room 10 minutes after being summoned via page to monitor CFSTs. RO reports MSLI failed to shut any MSIV, all MS? and MS18 valves are shut, and action has been directed to locallv shut MSIVs. PO reports all SG pressures are dropping in an uncontrolled manner. CRS transitions to EOP-LOSC-2, Multiple Steam Generator Deoressurization. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Paae 18 of 29 PO reports all valves in table A are shut except for all MSIVs. CRS dispatches operators, if not previously performed, to locally shut valves in Table A one looo at a time. CRS determines 23 AFW pump in service, and either stops 23 AFW pump or leaves it in service. Note: 23 AFW pump may be left in service if it is determined it is necessary to maintain minimum AFW flow to keep SG tubes wet. IF required, CRS dispatches operator to shut 21 and 23MS45 steam supplies to 23 AFW pump. RO reoorts RCS cooldown rate is >100°F I hr. PO reduces AFW flow to each SG to no less than 1.0E4 lbm I hr. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-1 UG-0204 Page 19 of 29 CRS transitions to FRHS-1, verifies operator action was cause of RED path, and returns to rocedure in effect. RO reoorts RCS Thats are dro RO reports RCS pressure, and reports a cooldown is in oroaress or RCPs are secured. RO reoorts both PZR PORVs are closed. RO reoorts 2PR6 is shut, and 2PR7 is ooen. RO resets SI, Phase A, and Phase B. RO ooens 21 and 22CA330. PO reoorts all SECs are reset. PO reoorts all 230V Control Centers reset. RO resets SGBD Sample Isolation Bypass, and ooens 21-24SS94s. CRS directs Chemistry to sample SGs for activitv and boron. PO reoorts no indication of anv SGTR. RO reports RHR pumps running with suction from RWST, and no discharae flow. RO reports RCS pressure is stable or rising, and stoos both RHR oumos .. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 20. of 29 s are runnin RO reoorts containment oressure. If/when containment pressure is <13 psig, then RO:
- Resets Spray actuation
- Stops both CS pumps
- Shuts 21 and 22CS2 CS pump discharae valves RO reports RWST lo level alarm has not actuated.
RO reports RCS Thots status. IF <375, PO removes lockouts for 21-24SJ54's, and RO shuts 21-24SJ54's. RO reoorts subcoolina is >0°F. RO reoorts RCS pressure and trend. RO reports RCS pressure is stable or rising and:
- Realigns charging pump through normal charging line and adjusts 2CV55 to maintain PZR level >33%.
- Reoorts PZR level trend.
iilifl~!i~~~ PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 21of29
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PO reoorts indication of 23MS 167 beina shut. CRS determines pressure rise in 23 SG reauires transition to LOSC-1. CRS transitions to LOSC-1. Terminate the scenario when the transition to LOSC-1 is announced. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 22 of 29 A. Alarm Response Procedures (Various) B. Technical Specifications C. Emergency Plan (ECG) D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load F. S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction G. S2.0P-AB.ROD-0002, Dropped Rod H. S2.0P-AB.STM-0001, Excessive Steam Flow I. 2-EOP-TRIP-1, Reactor Trip or Safety Injection J. 2-EOP-LOSC-1 Loss of Secondary Coolant K. 2-EOP-LOSC-2 Multiple Steam Generator Depressurization PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 23 of 29 MODE: 1 POWER: 1x10-8 A RCS BORON: 1711 MWe 0 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED): NA REACTIVITY PARAMETERS Control Bank D at 130 steps withdrawn. Core burnup 500 EFPH. MOST LIMITING LCO AND DATE/TIME OF EXPIRATION: 3.6.2.3 for 25 CFCU action a expires in 165 hours. EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS: S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load complete up to Section 4.3, Power Operation. ABNORMAL PLANT CONFIGURATIONS: CONTROL ROOM: Unit 1 and Hope Creek at 100% power. PRIMARY: 21 Charging pump in service 23 Charging pump CIT for emergent repair, expected return in 2 hours 25 CFCU CIT for breaker replacement SECONDARY: 21 SGFP in service 22 SGFP O/S with steam supply valves shut RADWASTE: No discharges in progress CIRCULATING WATER/SERVICE WATER: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 24 of 29
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- 1. Verify simulator is in "TRAIN" Load
- 2. Simulator is in RUN
- 3. Overhead Annunciator Horns ON
- 4. All required computer terminals in operation
- 5. Simulator clocks synchronized
- 6. All tagged equipment properly secured and documented
- 7. TSAS Status Board up-to-date
- 8. Shift manning sheet available
- 9. Procedures in progress open and signed-off to proper step
- 10. All OHA lamps operating (OHA Test) and burned out lamps replaced
- 11. Required chart recorders advanced and ON (proper paper installed) 12.* All printers have adequate paper AND functional ribbon
- 13. Required procedures clean
- 14. Multiple color procedure pens available
- 15. Required keys available
- 16. Simulator cleared of unauthorized material/personnel
- 17. All charts advanced to clean traces and chart recorders are on.
- 18. Rod step counters correct (channel check) and reset as necessary
- 19. Exam security set for simulator
- 20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out
- 21. Shift logs available if required
- 22. Recording Media available (if applicable)
- 23. Ensure ECG classification is correct
- 24. Reference verification performed with required documents available
- 25. Verify phones disconnected from plant after drill.
- 26. Verify EGC paperwork is marked "Training Use Only" and is current revision.
- 27. Ensure sufficient copies of ECG paperwork are available.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 25 of 29
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In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant. The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant. I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...
- degradation of any barrier to fission product release
- degraded emergency core cooling system (ECCS) or emergency power capacity
- a violation of a safety limit
- a violation of the facility license condition
- incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)
- a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...
- effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.
- recognize a failure or an incorrect automatic actuation of an ESF system or component.
- take one or more actions that would prevent a challenge to plant safety.
- prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.
PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 26 of 29 SCENARIO IDENTIFIER: 15-01 NRC ESG-3 REVIEWER: C Recchione Initials Qualitative Attributes CR 1. The scenario has clearly stated objectives in the scenario. CR 2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events. CR 3. The scenario consists mostly of related events. CR 4. Each event description consists of:
- the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position)
- the event termination point CR 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
CR 6. The events are valid with regard to physics and thermodynamics. CR 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. CR 8. The simulator modeling is not altered. CR 9. All crew competencies can be evaluated. CR 10. The scenario has been validated. CR 11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario. CR 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 27 of 29 Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section 0.5.d) GG 2 Malfunctions after EOP entry: 1-2 GG 3 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 2 EOPs entered/requiring substantive actions: 1-2 GG 0 EOP contingencies requiring substantive actions: 0-2 GG 2 EOP based Critical tasks: 2-3 COMMENTS: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 28 of 29 15-01 NRC ESG-3 CT#1 (CT-3) Manually actuate at least one Containment Spray pump before an extreme challenge develops to the containment CSF. Basis: Failure to manually actuate the minimum required complement of containment cooling equipment under the postulated conditions demonstrates the inability of the crew to "recognize a failure or an incorrect automatic actuation of an ESF system or component." CT#2 (CT-33) Control the AFW rate to not less than 1 E4 lbm/hr to minimize the cooldown rate. Basis: Failure to control the AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the critical task increases the challenges to the subcriticality and the containment CSFs beyond those irreparably introduced by the postulated plant conditions. Thus, failure to perform the critical task constitutes a demonstrated inability by the crew to "take one or more actions that would prevent a challenge to plant safety." It also fails to prevent "a significant reduction of safety margin beyond that irreparably introduced by the scenario." Note to Evaluator: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Tasks procedure WCAP-17711-NP PSEG Restricted - Possession Requires Specific Permission from Nuclear Training
TQ-AA-106-0204 Page 29 of 29 EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss of CCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT. SYSTEM. OR TRAIN Y/N COMPONENT, SYSTEM, OR TR1'.lf\1 N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s) N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.}}