Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML102600138
Person / Time
Site:	Hope Creek
Issue date:	08/06/2010
From:	; Public Service Enterprise Group
To:	Todd Fish; Operations Branch I
	Hansell S
Shared Package
ML100560172	List: ML102290400; ML102600032; ML102600038; ML102600044; ML102600053; ML102600085; ML102600125; ML102600129; ML102600138; ML103410313;
References
	TAC U01788
	Download: ML102600138 (424)
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JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance TASK NUMBER: 4010010201 JPM NUMBER: 305H-J PM .ZZ040 REV #: 00

- - NRC ADMIN JPM RO A1***

SAP BET: NOH05JPZZ40E ALTERNATE PATH: [KJ APPLICABILITY:

EOD RO [ ] ] STA [:=J SRO [ ] ]

DEVELOPED BY: Archie E. Faulkner DATE: 6/30/10 Instructor REVIEWED BY: fJ-,~ Operations Represell1tative DATE: ~!Jd/~~/()

APPROVED BY: gu~ ~ DATE: 7/1//D Training Department

TQ-AA-106*0303 STATION: Hope Creek JPM NUMBER: ZZ040 REV: 00 SYSTEM: Conduct of Operations TASK NUIVIBER: 4010010201 TASK: Petiorm Core Thermal Limits Surveillance ALTERNATE PATH: [KJ KIA NUMBER: 2.1.18 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EoD ROW STAD SROW EVALUATION SETTING/METHOD: ClassroomfPetiorm

REFERENCES:

HC.OP-DL.ZZ-0026 Rev. 121 HC.RE-ST.ZZ-0001 Rev. 19 TOOLS, EQUIPMENT AND PROCEDURES: Prepared copies of HC.RE-ST.ZZ-0001 Blank copies of HC.OP-DL.ZZ-0026 Att 1b page 4, HC.RE-ST.zZ-0001 Att 2, ALTERNATE P1 Report.

ESTIMATED COMPLETION TIME: 12 *Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - N/A Minutes JPM PERFORMED BY:

GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ-AA-106*0303 NAME:

DATE:

SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance TASK NUMBER: 4010010201 INITIAL CONDITIONS:

1. The plant is operating at 99.8 percent core thermal power following a startup.

2. HC.OP-DL.ZZ-0026(Q) Surveillance Log Attachment 1a is being performed for Midnight Shift.

3. The normal P1 Report is not available.

INITIATING CUE:

PERFORM DL-26 Attachment 1a Surveillance Log Items 20, 21, and 22 with materials provided below:

DL-26 Attachment 1a - Surveillance Log page 22.

ALTERNATE P1 REPORT.

HC.RE-ST.ZZ-0001 CORE THERMAL LIMITS SURVEILLANCE procedure without EXHIBITS, completed up to and including Step 5.3.

HC.RE-ST.ZZ-0001 CORE THERMAL LIMITS SURVEILLANCE Attachment 2.

WHEN FINISHED, RETURN ALL PAPERWORK TO THE PROCTOR.

Page 3 of 14

TQ*AA~1 06~0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Perform Core Thermal limits Surveillance

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO. STANDARD evaluation)

CUE PROVIDE the operator the initiating cue AND a prepared copy of:

DL-26 Attachment 1a Surveillance Log page 22.

ALTERNATE P1 REPORT.

HC.RE-ST.ZZ-0001 CORE THERMAL LIMITS SURVEILLANCE procedure Operator repeats back initiating cue.

without EXHIBITS, completed up to and including Step 5.3.

HC.RE-ST.ZZ-0001 CORE THERMAL LIMITS SURVEILLANCE Attachment 2.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Page 4 of 14

TQ-AA-106-0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 00 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD IF using the Alternate P1 5.5 Report, THEN OBTAIN AND RECORD the below required data from the Alternate P1 Report.

Date and Time of the Operator fills in date and time from Monitor case ALTERNATE P1 Calculation time.

("Calculated" date and time) 23 - AUG - 2010 23:31

MFLCPR (First

MFLCPR value listed Operator fills in MFLCPR value from under "Most Limiting Alternate P1 Sheet on Attachment 2 Locations") Form.

0.945

MFLPD (First MFLPD Operator fills in MFLPD value from

value listed under "Most Alternate P1 Sheet on Attachment 2 Limiting Locations") Form.

1.002

MAPRAT (First

MAPRAT value listed Operator fills in MAPRAT value from under "Most Limiting Alternate P1 Sheet on Attachment 2 Locations") Form.

1.001 Page 5 of 14

TQ-AA-106-0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE: __~______________

SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance

(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step)

EVAL {Required for UNSAT NO. # eval**...*;........\

STANDARD S/U DETERMINE whether the 5.6 Operator determines Acceptance Acceptance Criteria have been met. Criteria is not met.

Operator marks UNSATISFACTORY

Check Box.

Failure to meet the Acceptance NOTE Criteria for a core thermal limit requires entry into the TIS Action Statement for that core thermal limit if Core Thermal Power is 2: 24% RTP.

Operator reads NOTE.

With respect to TIS required actions, violation of an administrative Hmit is treated identically to a violation of a TIS Limit.

IF any of the core thermal 5.7 limits fails to meet its Acceptance Criteria, THEN Operator notifies CRS of immediately NOTIFY the UNSATISFACTORY surveillance.

SM/CRS.

CUE ACKNOWLEDGE report from operator that Thermal Limits N/A MFLPD and MAPRAT are above Maximum Acceptable Limits.

Page 6 of 14

TQ~AA-1 06-0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 00 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

DETERMINE whether the 5.8 core is in a Limiting Control Operator determines Limiting Control Rod Pattern.

Rod Pattern criteria is not met.

r---------~

The definition of a Limiting Control NOTE Rod Pattern includes any administrative limits on core Operator reads NOTE.

thermal limits. With respect to TIS required actions, a core therrnal limit exactly at the administrative limit (Le. Limiting Control Rod Examiner Note: The definition of a I Pattern) is treated identically to a Limiting Control Rod Pattern is only met if all 3 limits aie exactly 1.000.

I I core thermal limit on a TIS limit.

Operator marks NOT LIMITING Check Box.

IF the core is in a Limiting Control 5.9 Rod Pattern, THEN immediately NOTIFY the Operator determines Limiting Control SM/CRS. Rod Pattern criteria is not met.

L- ~---- --- ~

Page 7 of 14

TQ-RA-106-0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Conduct of Operations TASK: Perform Core Thermal limits Surveillance

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) {Required for UNSAT NO.

STANDARD RECORD any comments 5.10 conceming the procedure performance on Attachment 1. Not required for RO's.

SIGN AND DATE as the 5.11 Operator signs and fills in date/time in Performer. "Performed By" line on Attachment 2.

Page 8 of 14

TQ-AA-106-0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 00 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD evaluatio ITEM MFLCPR Operator fills in MFLCPR value. I

20 0.945.

I ITEM MFLPD Operator fills in MFLPD value. I

21 1.002.

Examiner Note: It is not critical to Operator circles Out Of Spec reading.

circle Out Of Spec reading.

iTEM MAPRAT Operator fiBs in MAPRAT value. I

22 1.001.

Examiner Note: It is not critical to Operator circles Out Of Spec reading.

circle Out Of Spec reading.

ACKNOWLEDGE report from operator that Thermal Limits I N/A MFLPD and MAPRAT are above Maximum Acceptable Limits.

Page 9 of 14

TQ-AA-106-0303 JPM: ZZ040 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Perform Core Thermal Limits Surveillance

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME REPEAT BACK any message from N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 10 of 14

JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: ZZ040 TASK: Perform Core Thermal Limits Surveillance TASK NUMBER: 4010010201 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT 1...-1._ _ _ _- - '

Page 11 of 14

TQ-AA*106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ040 Rev# Date Description I Validation Required?

00 4/21/10 New Admin JPM. Validated with 2 ROs. Ayerage validation time ! Y was 12 minutes.

J

HC.RE-ST.ZZ-0001 (Q)

ALTERNATE P1 REPORT Page 1 of 2 PAGE 1 HOPE CREEK CYCLE 16 CORE PARAMETERS 1 CALCULATED POWER MWT 3832.3 PERIODIC LOG PRINTED POWER MWE 1268.5 AUTOMATIC CASE IO FMLD10804 93156 FLOW MLB/HR 87.257 CALC RESULTS RESTART FMLD10804 90201 FPAPDR 0.799 LPRM SHAPE - FULL SUBC BTU/LB 24.05 Keff 1.0062 PR PSIa 1018.96 XE WORTH 'I; -2.26 LOAD CORE MWD!sT 20831.2 XE!RATED 1.001 CORE CYCLE MWD/sT 3557.5 AVE VF 0.473 CORE MCPR 1.450 FLLLP 0.997 CORRECTION FACTORS: MFLCPR= 1. 001 MFLPD'~ 0.999 ft OPTION: ARTS 2 LOOPS ON M.~NUA::" FLOW MCPR t-10ST LIMITING LOCATIONS (NON-SY MFLCPR LOC MFLPD LOC MAP&~T LOC LOC

~~:~ ~i=;~

23 4 23 17 5 41-24 1 919 33 5 0.940 23-20 0.986 27 16- 6- 997 23 4 0.929 25*-22 0.981 15 8- .996 43 5 0.928 39--26 0.972 43 0.993 41 4 0.917 43-26 0.970 25 0.993 11 5 0.915 25--18 0.968 25 0.988 23 5 0.912 35-36 0.964 39 0.987 13 5 0.905 27-16 0.963 23-24 0.986 27 4 0.904 15-28 0.958 27-20 4 0.985 27 5 SEQ. A.,..2 C=MFLCPR D=MFLPD T *=MULTIPLE COR~ AVE ~~IAL NOTC3 R~L PW LOC 0.161 25 CO 0.290 24 59 02 0.538 23 L 04 0.685 22 55 06 0.783 21 51 08 0.856 20 L 10 0.904 19 47 12 0.929 18 43 14 0.952 17 L 16 0.937 16 39 16 18 0.966 15 35 20 1.094 14 22 1.129 13 16 16 16 24 1. 184 12 26 1. 235 11 28 1.260 10 16 16 30 1. 286 09 C

32 1. 333 08 34 1. 369 07 16 16 36 1. 420 06 38 1. 468 05 <

40 1. 457 04 16 42 1. 342 03 44 1. 043 02 L L L L L L L 46 0.379 01 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 CORE AVERAGE RADIAL POWER DISTRIBUTION RING # 1 234 5 6 7 8 REL PW 1.168 1.209 1.132 1.248 1.186 1.196 1. 015 0.554 Hope Creek Page 1 of ~~

ATTACHMENT 2 CORE THERMAL LIMITS SURVEILLANCE FORM Page 1 of 1 1.0 COLLECTION OF CORE THERMAL LIMITS DatelTime of Monitor Case*:

Date

Limiting MFLCPR

Limiting MFLPD

Limiting MAP RAT 2.0 ACCEPTANCE CRITERIA Action Statements D SATISFACTORY TIS 3.2.3 TIS 3.2.4

-+ TIS 3.2.1

~ UNSATISFACTORY .,

3.0 LIMITING CONTROL R Action Statements o LIMITING FLCPR [1] = 1.000 TIS 3.1.4.3, 3.2.3 ND iting MFLPD . [2] = 1.000 TIS 3.1.4.3, 3.2.4 AND Limiting MAPRAT [3] = 1.000 TIS 3.1.4.3, 3.2.1 Otherwise Date~Time NIA NIA Date~Trme Hope Creek

HC.OP-[ ,:-0026{Q)

ATTACHMENT 1a Page 4 of 17 Surveillance Log - Control Room Operational Condition ~

ITEM I SURVEILLANCE OPER ACCEPTABLE liMITS INSTRUMENT (PANEL) COMMENTS

.MIN NORM 10 I S::-U-::::P=P=R=ES:;:-:S::-:-10=N:-:-:=CH:-:-A-:-:M-=B""E=Rc--+-'1-:-'.2=-.3::'-t1~ 5()

AVERAGE WATER TEMP 60

11. DRYWELL PRESSURE 1,2,3 -25 0-1 12 SUPPRESSION CHAMBER 1,2,3 -.25 0-1 +1.5 I GS-PR4960B3 RX BLDG PRESSURE RE I 1,2,3," I - I <0 GS-PDR9426A QR B (NOTE 19.)

STORAGE TANK 1,2 4640 4800 - 4880 CRIDS PT A7052 (NOTE 14.,15.,)

LUME 4880 15 RPV FLANGE LEAK IN ALARM 1,2,3 NO 16 SLCTANKTROUBLE IN 1,2 NO ALARM 17 SDV VENT AND DRAIN 1,2 YES 18 CONT VENTING OR PURGING NOTE I YES IS THRU RBVS OR FRVS 18.

19 SLCWT% 1,2 13.6 (NOTE 14.)

SLC TK VOL 1,2 (NOTE 14.)

20 MFLCPR MFLPD 22 MAPRAT NOTES: 2. IF VALUE IS OOS OR INST~" EN , S INOP, r~ . RF.ASED SURVEILLANCE REQUIREMENTS MAY BE NECESSARY.

13. INCREASED SURVEILLAN'~' " NTS \, Y BE NECESSARY (WHEN OPERATING WITH A LIMITING CONTROL ROO PATTERN; WITHIN 12HRS AFTER THERMAL POWER INCREAS~G'TER THA,~, '

024% OF RTP). .

14. ITEMS 14 AND 19...*.*. ' EPENDENT5!"*'FIGU . E 3.1.5-1 INTIS. IF CONCENTRATION OR VOLUME IS OUTSIDE OF THE NORM BAND, THEN DETERMINE SAT OR UNSAT WITHIN ACCEPT,,*, OPE TING 'ION OF FIGURE 3.1.5-1. .

15. TANK VOLUME ~lJLD. INTAI,," D BETWEEN 4800 - 4880 TO ALLOW FOR THE WIDEST POSSIBLE CONCENTRATION RANGE PER TIS FIGURE 3.1.5-1. [80001560]

16. REFER TO ATTAC 1..... /"." W~O L'fERNATE SUPPRESSION POOL TEMPE,RATURE DETERMINATION. IF 95°F EXCEEDED, IMPLEMENT ATTACHMENT 3F.

17. ENSURE READINGS'~DOCU' ED BY COMPLETING ATT 1 OF HC.RE-$r.ZZ-0001(Q).

18. WHENEVER THE CONT)\1~MEi ' VENTED OR PUR,GED. CONTAINMENT SHALL BE DETERMINED TO BE ALIGNED FOR VENTING OR PURGING THROUGH EITHER THE RBVS OR FRVS WITHIN 4 \W~RS PRIOR TO START OF AND AT LEAST ONCE PER 12 HOURS DURING VENTING OR PURGING OF THE DRYWELL. FOLLOWING TYPE A ILRT THE MARK 1 CONTAINMENTMAY BE VENTED THROUGH THE HARDENED TORUS VENT. NlA WHEN NO VENTING OR PURGING IS IN PROGRESS.

19. WHEN HANDLING RECENTLY IRRADIATED FUEL IN THE SECONDARY CONTAINMENT AND DURING OPERATIONS WITH A POTENTIAL FOR DRAINING THE REACTOR VESSEL

20. RECORD HIGHEST OPERABLE INDICATION FROM EACH CHANNEL (ALPHA - SB-TR-3881A1, RM-11 (9AX833) II BRAVO - S8-TR-3881 81, RM-11 (9AX834>>.

HODe Creek Pace 22 of 101 Rev. 121

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is operating at 99.8 percent core thermal power following a startup.

2. HC.OP~DL.zZ~0026(Q) Surveillance Log Attachment 1a is being performed for Midnight Shift. .

3. The normal P1 Report is not available.

INITIATING CUE:

PERFORM DL-26 Attachment 1a - Surveillance Log Items 20, 21, and 22 with materials provided below:

DL-26 Attachment 1a - Surveillance Log page 22.

ALTERNATE P1 REPORT.

HC.RE-ST.ZZ-0001 CORE THERMAL LIMITS SURVEILLANCE procedure without EXH IBITS, completed up to and including Step 5.3.

HC.RE-ST.ZZ-0001 CORE THERMAL LIMITS SURVEILLANCE Attachment 2.

WHEN FINISHED 1 RETURN ALL PAPERWORK TO THE PROCTOR.

HC.RE-ST.ZZ-0001 (Q)

ALTERNATE P1 REPORT Page 1 of 2 PAGE 1 HOPE CREEK CYCLE 16 SEQUENCE NO 20 CORE PARAl\1ETERS 3DM/P11 23-AUG-2010 23:31 CALCULATED POliIJER MWT 3832.3 PERIODIC LOG 23-AUG-2010 23:59 PRINTED POWER MWE 1268.5 AUTOMATIC CASE ID FMLD1080428 FLOW MLB/HR 87.257 CALC RESOLTS RESTART FMLD1080428 FPAPDR 0.799 LPRlYl SHAPE SUBC BTU/L8 24.05 Keff 1.0062 PR PSIa 1018.96 XE WORTH % -2.26 LOAD CORE MWD/sT 20831.2 XE/RATED 1.001.

CYCLE MWD/sT 3557.5 ~VE VF 0.473 MCPR 1.450 FLLLP 0.997 CORRECTION FACTORS: MFLCPR= 1.001 MFLPD= 0.999 ft OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPR MOST LIMITING LOCATIONS (NON-SYMMET MFLCPR LOC MFLPD LOC MAPRAT LOC 0.945 19-20 1.002 23 4 1.001 17 5 0.941 41-24 0.994 41 4 0.957 9 33 5 0.940 23-20 0.986 27 4 0.953 .997 23 4 0.929 25-22 0.981 15 4 0.953 0.996 43 5 0.928 39-26 0.972 43 4 O. """""""""'"""C",'" O. 9 93 41- 2 4 - 4 0.917 43-26 0.970 25 4 O. 4 0.993 11 5 0.9:5 25-18 0.968 25 4 4 0.988 23 5 0.912 35-36 0.964 39 4 4 0.987 13 5 0.905 27-16 0.963 23 4 4 0.986 27 4 0.904 15-28 0.958 27 4 0.985 27 5 SEQ. A-2 C=MFLCPR *=MUI,TIPLE CORE AVE AXIAL NOTCH REL PW LOC 0.161 ~5 00 0.290 24 59 02 0.538 23 L 04 0.685 22 55 06 0.783 21 51 08 0.856 20 L 10 0.904 19 47 16 12 0.929 18 43 14 0.952 17 16 0.937 16 16 18 0.966 15 20 1. 094 14 22 1.129 13 16 16 24 1.184 12 26 1.235 11 28 1. 260 10 16 16 16 30 1. 286 09 C

32 1. 333 08 34 1.369 07 16 16 36 l. 420 06 38 l. 468 05 <

40 1. 457 04 07 16 42 1. 342 03 03 44 1. 043 02 L L L L L L L 46 0.379 01 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 CORE AVERAGE RADIAL POWER DISTRIBUTION RING # 1 2 3 4 5 6 7 8 REL PW 1.168 1.209 1.132 1.248 1.186 1.196 1. 015 0.554 Hope Creek Page 1 of 1

HC.RE-ST .ZZ-0001 (Q)

AL TERNATE P1 REPORT Page 2 of 2 PAGE 2 HOPE CREEK CYCLE 16 INSTRUMENT READINGS/STll.TOS SEQUENCE NO 20 CALIBRATED LPRM READIKGS 23-AUG-2010 23:31 CALCULATED 23-AUG-2010 23:59 PRINTED 570 21.4 28.2 24.2 26.6 CASE 10 FMLDI080428093156 C 27.3 37.7 31. 9 36.1 LPRM SHAPE - FULL CORE B 31.3 47.0 39.0 45.3 A 25.8 48.1 35.3 49.2 490 22.7 36.1 41.3 38.3 41.4 32.5 C 29.4 48.7 49.3 50.8 49.8 43.3 FAILED SENSO B 33.0 60.5 56.7 60.7 57.2 0.0 LPRM ( 4 A 26.6 67.1 59.0 66.5 62.2 56.7 841B LPRM (

410 34.1 43.0 40.2 34.9 43.6 42.2 26.7 OTHER C 45.9 51.5 53.7 47.4 56.3 50.0 36.9 B 0.0 0.0 64.9 57.2 65.5 58.0 46.0 A 61. 8 60.4 73.2 62.2 73.2 61. 9 49.0 330 30.4 38.5 34.2 37.5 35.0 37.7 C 43.0 51.9 47.5 51.1 47.2 50.9 LOCA1'ION B 54.5 63.1 59.2 62.6 57.6 61. 0 MFljPD LOCA'l'ION A 60.5 72 .3? 62.7 67.8 62.4 68.3 .PCRAT LOCATION

. MULTIPLE LIMIT 25D 35.1 43.1C 38.7 33.4 40.2 C 47.3 51.8 52.8 46.7 54.4 B 59.6 60.0 64.8 58.7 65.4 A 68.0 65.3* 74.9 65.4 74.8 170 32.4 40.7 ~2.8 39.1 C 43.2 51.7 51.5 B 53.0 60.7 59.4 A 54.5 b2.0 65.6 090 31.3 C 42.2 B 52.1 A 55.6 08 40 48 56 CALC SUB FLOW 87.5% DP t<lEAS PSI 11.683 OPER SUB FLOW -1. 0% DP CALC PSI 17.139 FLOW BASIS NEAS FEEDWTR FLOW MLB/HR 14.23 APRM CALIBRATION A B C D E F 99.8 99.5 100.3 99.5 99.6 99.7

1. 001 1.004 0.996 1. 004 1.003 1. 001 APRN - %C'l'P 0.0 -0.3 0.5 -0.3 -0.2 -0.1 TIP RUNS RECOMMENDED STRINGS: NONE Hope Creek Page 2 of2

ATTACHMENT 2 CORE THERMAL LIMITS SURVEILLANCE FORM Page 1 of 1 1.0 COLLECTION OF CORE THERMAL LIMITS Date/Time of Monitor Case*:

Date Time

Limiting MFLCPR

Limiting MFLPD

Limiting MAPRAT 2.0 ACCEPTANCE CRITERIA Action Statements o SATISFACTORY Limiting MFLCPR TIS 3.2.3 AND Limiting MFLiaS" TIS 3.2.4 AND f:;~;?

7 A TIS 3.2.1 o UNSATISFACTORY 7 3.0 LIMITING CONTROL ROD Action Statements o LlMITII\lG g MFLCPR [1] = 1.000 TIS 3.1.4.3, 3.2.3 AND MFLPD [2] = 1.000 TIS 3.1.4.3, 3.2.4 AND Limiting MAPRAT [3] = 1.000 TIS 3.1.4.3, 3.2.1 Otherwise Date-Time Reviewed By Date-Time Hope Creek Page 22 of 101

HC,OP-[ ;-0026(Q) "

ATTACHMENT 1a Page 4 of 17 Surveillance Log - Control Room Operational Condition ITEM SURVEILLANCE OPER I ACCEPTABLE LIMITS INSTRUMENT (PANEL) COMMENTS MIN NORM MAX 10 I SUPPRESSION CHAMBER 60 Error! Reference source not found.,

AVERAGE WATER TEMP 60 95

11. DRYWELL PRESSURE 0-1 1,2':3t 12 SUPPRESSION CHAMBER 1,2,3 -.25 0-1 +1.5 I GS-PR4960B3 13 RX BLDG PRESSURE 1,2,3: <0 GS-PDR9426A OR B (NOTE 19.)

14 SLC STORAGE TANK 1,2 I 4640 4800 - I 4880 I CRIDS PT A7052 (NOTE 14., is.,)

VOLUME 4880 15 RPV FLANGE LEAK IN ALARM 1,2,3 NO D3-M 16 SLC TANK TROUBLE IN 1,2 NO C1-E1 ALARM 17 SDV VENT AND DRAIN 1,2 YES VALVES OPEN 18 CONT VENTING OR PURGING NOTE YES IS THR.U RBVS OR FRVS 18.

19 SLCWT% 1,2 13.6 (NOTE 14.)

SLCTKVOL 1,2 (NOTE 14.)

20 MFLCPR (NOTE 13., 17.)

I .---+~

21 MFLPD (NOTE 13., 17.)

22 MAPRAT (NOTE 13., 17.)

NOTES: 1~: :~6~~~~ ~~~~~~~J~~~~M~I~~~~I~~~:EE~ES;E~~~~~~E~Eg;'~~~~~~~YA8Ci~~~~~~~~ROL ROD PATIERN; WITHIN 12HRS AFTER THERMAL POWER INCREASE GREA~R THANlPR EQQ:~TO 24% OF RTP). .

14. ITEMS 14 AND 19 ARE DEP'EI'JPEN'f:ON FIGURE 3.1.5-1 IN T1S. IF CONCENTRATION OR VOLUME IS OUTSIDE OF THE NORM BAND, THEN DETERMINE SAT OR UNSAT WITHIN ACCEPTABLI~:"Olf,sRA7r1w'~ REGION OF FIGURE 3.1.5-1.

15. TANK VOLUME SI-j~m:.[jB~(MA1N~e.INED BETWEEN 4800 4880 TO ALLOW FOR THE WIDEST POSSIBLE CONCENTRAnON RANGE PER TIS FIGURE 3.1.5-1. [800015601

16. REFER TO ATIA<1Ii1MENT 3Wti~ORtAJ;:TERNATE SUPPRESSION POOL TEMPERATURE DETERMINATION. IF 95°F EXCEEDED, IMPLEMENT ATIACHMENT 3F.

17. ENSURE READINt:p ARE DOCI\1,,rvtENTED BY COMPLETING ATI 1 OF HC.RE-ST.zz-0001(Q).

18. WHENEVER THE OONTAINMEIlI'r IS VENTED OR PURGED. CONTAINMENT SHALL BE DETERMINED TO BE ALIGNED FOR VENTING OR PURGING THROUGH EITHER THE RBVS OR FRVS WltbtlN4Ho,URS PRIOR TO START OF AND AT LEAST ONCE PER 12 HOURS DURING VENTING OR PURGING OF THE DRYWELL FOLLOWING TYPE A ILRT THE MARK 1 CONTAINMENT'MAY BE VENTED THROUGH THE HARDENED TORUS VENT. N/A WHEN NO VENTING OR PURGING IS IN PROGRESS.

19. WHEN HANDLING RECENTLY IRRADIATED FUEL IN THE SECONDARY CONTAINMENT AND DURING OPERATIONS WITH A POTENTIAL FOR DRAINING THE REACTOR VESSEL

20. RECORD HIGHEST OPERABLE INDICATION FROM EACH CHANNEL (ALPHA - SB-TR-3881A1, RM-11 (9AX833) II BRAVO - SB-TR-3881B1, RM-11 (9AX834)).

Hone Creek Pace 22 of 101 Rev. 121

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment TASK NUMBER: 2990090301 JPM NUMBER: 305H-\.IPM.ZZ030 REV #: 02

~**NRC ADMIN JPM RO A2*~*

SAP BET: NOH05JPZZ30E ALTERNATE PATH: D APPLICABILITY:

EOD RO [KJ S1"A D SRO [KJ DEVELOPED BY: A Faulkner DATE: 6/30/10 Instructor REVIEWED BY:

~ Op rations Represcmtative DATE: &6 u 0 O/6 APPROVED BY: qucn~ DATE: ]j)/Iv Training Department

TQ*AA*106*0303 STATION: Hope Creek JPM NUMBER: Z2030 REV: 02 SYSTEM: Conduct of Operations TASK NUMBER: 2990090301 TASK: Generate An SAP System Valve/Breaker Alignment ALTERNATE PA"rH: D KIA NUMBER:

2.1.29 IMPORTANCE FACTOR: 4.1 4.0 APPLICABILITY: RO SRO EO D RO [KJ STA D SRO [KJ EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0015 Rev 21 OP-AA-1 09-115-1 001 Rev 0 ,:;/

TOOLS, EQUIPMENT AND PROCEDURES: SAP Computer and accessible SAP printer.

ESTIMA"rED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

- -N/A-- Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes

. ACTUAL "riME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106*0303 NAME:

DATE: ____________________

SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment TASK NUMBER: 2990090301 INITIAL CONDITIONS:

1. The plant is at 100% power steady state.

2. The current time is 3:30 am.

INITIATING CUE:

You are the Tuesday Night Shift Plant Operator.

PRINT a copy of the WCM Off-Normal Report (Off-Normal and NOT Tagged) for the Shift Routine. .

Page 3 of 13

TQ-AA-106-0303 JPM: ZZ030 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment

(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step) .

(Required for UNSAT NO.

STANDARD CUE SETUP ENSURE a printout of an OFF NORMAL report is available on the I N/A day of the exam to compare operator results.

CUE SeTUP Logon to the SAP Training Client Using:

PSEG Applications Online Click on: TRAINING folder Click on: Enterprise Training N/A System - ECC6 icon User: train20 Password: welcome9 Ensure the "WCM: Area Menu" is open (Fast Path ZWCMM)

CUE PROVIDE the operator the initiating cue AND the following:

D A prepared copy of HC.OP-DLZZ-001S with an Operator repeats back initiating cue.

Attachment 1 completed for Dayshift (Attached)

D OP-M-109-115-1001 Page 4 of 13

TQ-AA-106-0303 JPM: ZZ030 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment

(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step)

(Required for UNSAT NO.

STANDARD CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

HC.OP-DL.ZZ-0015 N/A 3.6.1. PRINT a copy of the WCM Off-Normal A Report Examiner Note: Refer to steps below (Off-Normal and NOT Tagged) for Standards associated with this step.

AND FiLE in the Controi Room f--------/-

Operator obtains procedure OP-AA 109-115-1001.

IF necessary, THEN Operator obtains the corred Examiner Note: The procedure is only procedure. a desktop guide and the operator may be proficient at the task and NOT reference the desktop guide.

OP-AA-109-115-1001 N/A 5.3.6 Printing/Reviewing Off-Normal From the WCM: Area Menu Operator Clicks:

"WCM Reports" menu.

A. Click 'WCM Reports" menu, Operator then clicks then click "Off Normal Report "Off Normal Report (Version 1)".

(Version 1)".

Page 5 of 13

TQ-AA-106-0303 JPM: ZZ030 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT ELEMENT NO. STANDARD # evaluation)

S/U B. Complete "Object Info" section Operator enters the following Object

for report to be obtained. Info:

Planning Plant: NNUC Plant Section: He

Mode: 01

Type: F

Technical Object:

OR H* OR H1*

C. Select desired "Display Filter" either "Off Normal" or "Tagged" I Operator selects "Display Filter" for "Off

I Normal" ONLY.

or both.

D. If printing report: Based on Initiating Cue, Operator determines printing the report IS required.

Examiner Note: It is NOT critical in the following steps HOW the Operator prints the Report. For instance, may select preview mode and then use printer icon. It is also NOT critical to actually retrieve the printout (Not all SAP printers work in the Training Client) Critical portion is to execute steps to generate a printout.

Under "Program" select Under "Program", Operator selects *

"Execute and Print". "Execute and Print",

Page 6 of 13

TQ-AA-106-0303 JPM: ZZ030 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment

(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step)

EVAL (Required for UNSAT NO.

STANDARD # I SfU eval"""tinn CUE IF in the LDC, THEN PROVIDE the Operator with an accessible SAP printer number.

PRINTER PROVIDED: _ __ N/A IF in the LDC and the applicant does not have permission to print the report THEN terminate at this point.

Select output device then Operator Selects an output device then

click "Continue". clicks "Continue".

E. If reviewing report, click Based on Initiating Cue, Operator "Execute". determines this step is not required.

F. Click "Back". Operator clicks "Back" to exit.

HC.OP-DL.ZZ-0015 N/A CUE RETRIEVE printed Off-Normal AND INFORM the operator the Report has N/A been filed.

3.6.1. PRINT a copy of the WCM Off-Normal WHEN printed Off-Normal is filed, A Report THEN Operator enters time (simulated (Off-Normal and NOT Tagged) to be 03:30) AND initials Attachment 1.

AND FILE in the Control Room Page 7 of 13

TQ-AA-106-0303 JPM: ZZ030 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Generate An SAP System Valve/Breaker Alignment

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 13

TQ-AA-106*0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: ZZ03()

TASK: Generate An SAP System Valve/Breaker Alignment TASK NUMBER: 2990090301 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power steady state.

INITIATJNG CUE:

You are the Tuesday Night Shift Plant Operator.

PRINT a copy of the WCM Off~Normal Report (Off~Normal and NOT Tagged) for the Shift Routine.

Page 10 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE ATTACHMENT 1 (Page 1 of 1)

TUESDAY SHIFT ROUTINE LOG Date: TODAY REQUIRED ROUTINES 0600 -1800 1800 - 0600 1 X Shift 3.6.1.B PERFORM lamp test on all possible Sections of i0C800. }7}7 NOTE 3.6.3 MARK all Control Room strip charts (Date & Initial),

VERIFIED status of Paperless Recorders. }7}7 NOTIFIED I&C if Memory Space digital reading:?: 20%.

NOTE - Only recorders that are Operating or Operable need be checked.

REQUIRED ROUTINES I TIME COMPLETED . I INITIALS 1800 - 0600 3.6.1.A PRINT a copy of the WCM Off-Normal Report (Off-Norma! and NOT Tagged)

AND FILE in the Control Room 1800 - 0600 3.6.2 Control Room cleanup 1800 - 0600 3.6.4 Attachment 2 of SH.OP-DL.ZZ-0027(Z), has been and Temporary Log package for the next day has been prepared.

1800 - 0600 3.6.5 PLACE the out-of-service TSC Chilled Water Pump 1A(B)

(pump only) for a i-hour run to purge any air from pi HC.OP-SO.GJ-0002(Q), A(B)K403 1E Panel Room Operation.. [70036044]

1800 0600 I 3.6.6 PLACE the out-of-service Control Area in-service (pump only) for a i-hour r lAW HC.OP-SO.GJ-0001(Q),,.,

By: ~kjlAWU4 Supervisor Review: Zm£~A 0600-1800 1800-0600

TQ-AA-106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ030 Rev # Date Description Validation Required?

1 11/8/08 Converted to new format. Y Changed initiating cue from plant startup conditions to Daily Shift Routine to increase the Operational Validity.

Added Cue to ensure a printout of that day's OFF-NORMAL report is available to compare to the Operator generated report.

Revised wording of LOG ON instructions to match actual LOG ON actions. Editorial cha~ No re-validation required.

2 5/26/10 Revised due to SH.WM-DG.ZZ-0015 was superseded by OP N AA-109-115-1001. Action steps did not change.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Equipment Control TASK: Perform An Accident Monitorrng Instrumentation Channel Check .

TASK NUMBER: 2160010201 JPM NUMBER: 30SH-JPM.ZZ025 REV#: 02

- - NRC ADMIN JPM RO A3***

SAP BET: NOH05JPZZ25E ALTERNATE PATH: m APPLICABILITY:

EoD RO [KJ STAD SRO [KJ DEVELOPED BY:

Q)dltructorA. Faulkner DATE: 6/30/10 REVIEWED BY: DATE: (((3(//2 C/I ()

Operations Represe!ntative APPROVED BY: ~J~

Training Department DATE: 7/J/Jb

TQ*AA*106*0303 STATION: Hope Creek JPM NUMBER: ZZ025 REV: 02 SYSTEM: Equipment Control TASK NUMBER: 2160010201 TASK: Perform An Accident Monitoring Instrumentation Channel Check ALTERNATEPAT~: [}[] ~ANUMBER: ______ 2_.2_.1_2_____

IMPOIRTANCE FACTOR: 3.7 4.1 APPLICABILITY: RO SRO EO D RO [K] STA D SRO [K]

EVALUATIONSETTING/M ETHOD: Simulator/Perform

REFERENCES:

HC.OP-ST.SH-0001 Rev 29 TOOLS, EQUIPMENT AND PROCEDURES: Prepared copy of HC.OP-ST.SH-0001 ESTIMATED COMPLETION TIME: 18 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: __N_/A_ __ Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 22

TQ*AA*106*0303 NAME:

DATE:

SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check TASK NUMBER: 2160010201 INITIAL CONDITIONS:

1. HC.OP-ST.SH-0001(Q), Accident Monitoring Instrumentation Channel Check - Monthly is required.

2. No other testing or maintenance isin progress that will adversely affect the performance of this test.

INITIATING CUE:

PERFORM Steps 5.1 through 5.6.3 of HC.OP-ST.SH-0001 (0).

Another operator will complete the rest of the Surveillance (Steps 5.7 to end).

Page 3 of 22

TQ-AA"106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU CUE PROVIDE the operator the initiating cue AND a prepared copy of HC.OP-ST.SH-0001 with Operator repeats back initiating cue.

Attachment 1 Section 1 .0 PRETEST INFORMATION completed.

CUE I ENTER START TIME:....::.......:c..=.:...::

Operator repeats back the Cue: N/A START TIME:

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing _

precautions and limitations, N/A THEN INFORM operator that all are satisfied.

5.1 LOG test start time in the Control Operator requests that the start time be Room log(s). logged in the Control Room log.

CUE WHEN asked to log the surveillance in the Control Room logs, THEN REPORT the surveillance has Operator initials step 5.1.

been logged in the Control Room logs.

Page4of22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step) COMMENTS STEP

NO.

ELEMENT (#Denotes a Sequential Step) EVAl (Required for UNSAT STANDARD # S/U eval**.,.+i.......\

5.2 ENSURE that all prerequisites have been satisfied lAW Section 2.0.

CUE IF excessive time is taken reviewing prerequisites, N/A THEN INFORM operator that all are satisfied.

2.1 Permission to perform this test has Operator ensures permission to been obtained from the SM/CRS as perform test is authorized on indicated by the completion of Attachment 1 Section 1 Attachment 1, Section 1.0.

All personnel performing any steps in this procedure should complete Operator signs Attachment 1.0, Section Attachment 1, Section 3.0 prior to 3.0.

performing any part of this procedure.

2.3 Plant is in any condition. Operator observes plant is in any condition.

2.4 No other testing OR maintenance is in Based on initial conditions, operator progress that will adversely affect the recognizes no testing or maintenance is performance of this test. in progress that will adversely affect the performance of the test.

Page 5 of 22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3 ENSURE Attachment 1, Section 1.0 of the SM/CRS Data and Signature Operator observes Attachment 1 Sheet has been completed Section 1.0 has been completed and AND Regular Surveillance OR Retest Regular Surveillance is indicated.

is indicated.

5.4 PERFORM a Channel Check of the following Reactor Vessel Pressure Examiner Note: Refer to following instruments, steps for standards associated with this RECORD AND COMPARE the step.

indicated pressure readings on Attachment 2: [TIS 4.3.7.5-1, item 1]

~

5.4.1 REACTOR PRESSURE Indicator PI- Operator records the value of PI-3684A 3684A (Red) (Red) on Attachment 2.

5.4.2 REACTOR PRESSURE Recorder PR-3684A-1 (Red)

Operator records the value of (alternate indication for PI-3684A)

PI-3684A-1 (Red) on Attachment 2.

(Panel 10C650 Section B Subsection B) I 5.4.3 REACTOR PRESSURE Recorder Operator records the value of PR-3684B (Red) PR-3684B (Red pen) on Attachment 2.

Page 6 of 22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # I S/U STANDARD 5.4.4 VERIFY Reactor Pressure

Operator compares the values recorded instrumentation Channel Check for PI-3684A (Red), PI-3684A-1, and complete, PR-3684B (Red pen) and verifies they ENTER SAT or UNSAT are within 75 psig, then enters SAT on AND INITIAL the appropriate space Attachment 2.

on Attachment 2.

Operator initials Attachment 2.

5.5 PERFORM a Channel Check of the following Reactor Vessel Water Level instruments, Examiner Note: Refer to following RECORD AND COMPARE the steps for standards associated with this indicated level readings on step.

Attachment 2:

[TIS 4.3.7.5-1, item 2]

5.5.1 , I REACTOR FUEL ZONE Water Level Operator records the value of LR-R615 Recorder LR-R615 (1 OC650 A Subsection F) on OC650 A Subsection F) Attachment 2.

5.5.2 I REACTOR FUEL ZONE Water Level Operator records the value of LI-R61 0 Indicator LI.. R61 0 (1 OC650 A Subsection G) on (10C650 A Subsection G) Attachment2.

5.5.3 I REACTOR CHANNEL A Water Level Operator records the value of LR Recorder LR-R623A (Red) R623A (Red pen) on Attachment 2.

[32 inches]

Page 7 of 22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

~

SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.5.4 REACTOR CHANNEL B Water Level Operator records the value of LR Recorder LR-R623B (Red) R623B (Red pen) on Attachment 2.

[26 inches]

5.5.5 REACTOR WATER Level Recorder Operator records the value of LR LR-3622A (Blue) 3622A (Blue pen) on Attachment 2. I 5.5.6 REACTOR WATER Level Recorder Operator records the value of LR LR-3622B (Blue) 36228 (Blue pen) on Attachment 2.

Page 8 of 22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

Rev; 02 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - - -

SYSTEM: Equipment Control

,TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.5.7 VERIFY Reactor Water Level Operator compares the values recorded

instrumentation Channel Check for:

complete,

LR-R615 (1 OC650 A Subsection F),

ENTER SAT or UNSAT

L1-R61 0 (10C650 A Subsection G)

AND INITIAL the appropriate space And verifies they are within 10 inches, on Attachment 2. AND,

LR-R623A (Red pen)

LR-R623B (Red pen)

And verifies they are within 10 inches, I AND, I I

LR-3622A (Blue pen) I I

LR-3622B (Blue pen),

Are within 20 inches, then enters SAT on Attachment 2.

Operator initials Attachment 2.

Operator: refers to NOTE 1, determines

the difference between LR-R623A and LR-R623B exceeds half the Max Variance, and notifying System Engineering is required.

2l ~

CUE ACKNOWLEDGE report from operator that variance between N/A

~ ~

LR-R623A and LR-R623B exceeds half the Max Variance. ~

Page 9 of 22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. STANDARD # S/U evalll~tinn\

5.6 PERFORM a Channel Check of the following Suppression Pool Water Level instruments, Examiner Note: Refer to following RECORD AND COMPARE the steps for standards associated with this indicated level readings on step.

Attachment 2:

[TIS 4.3.7.5-1, item 3]

5.6.1 SUPPRESSION POOL Water Level Operator records the value of Recorder LR-4805-1 (RED) LR-4805-1 (10C650B Subsection B) on (10C650B Subsection 8) Attachment 2.

5.6.2 SUPPRESSION POOL Water Level Operatorrecords the value of U-4801 Indicator U-4801 (BLUE) on Attachment 2.

f--------+--- n_n .1 5.6.3 VERIFY Suppression Pool Water Level instrumentation Operator compares the values recorded Channel Check complete, for LR-4805-1 and U-4801 and verifies ENTER SAT or UNSAT they are within 9 inches, then enters AND INITIAL the appropriate space SAT on Attachment 2.

on Attachment 2.

[CD-488E]

Operator initials Attachment 2.

Page 10 of 22

TQ-AA-106-0303 JPM: ZZ025 OPERATOR TRAINING PROGRAM NAME:

DATE: ___________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Perform An Accident Monitoring Instrumentation Channel Check

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U evaluati CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from N/A the operator on the status of the JPM, and then state "'This JPM is complete".

STOP TIME:

Page 11 of22

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 22025 TASK: Perform An Accident Monitoring Instrumentation Channel Check TASK NUMBER: 2160010201 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 12 of 22

TQ~AA~1 06-0303 JOB PERFORMANCE MEASURE ATTACHMENT 1 (Page 1 of 3)

SM/CRS DATA AND SIGNATURE SHEET ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK* MONTHLY 1.0 PRETEST INFORMATION 1.1 Reason for the Test 1.1.1 Regular Surveillance INITIALS 1.1.2 Retest/Other INITIALS t.1.3 lE not performing the complete test, THEN LIST subsection(s)/valves to be performed, as well as marking N/A on the applicable subsection(s)/valves on the Attachment(s) that will not be performed, OR, that do not require an independent verification lAW OP-AA-1 08-1 01-1 002, Component ,Configuration Control SUBSECTION(S)NALVE(S) 1.2 Plant Conditions 1.2.1 Operational Condition 1 1.2.2 Reactor Power Level 1.2.3 GMWe ----~-

1260 1.3 Permission to Perform the Test 1.3.1 Permission granted to perfonn this test.

fhe~ Today/Now OS/CRS/WCC'~--S---- DATE-TIME 1.3.2 Work Order No.

Page 13 of 2:2

~M@~USu@@lolwfQ*AA-106.0303 (Page 2 of 3)

SM/CRS DATA AND SIGNATURE SHEET lfl'iJ ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK - MONTHLY 2.0 POST TEST INFORMATION 2.1 The data acquired during the performance of this test has been reviewed for completenes~ and compliance with Technical Specifications 4.3.7.5, Table 4.3.7.5-1 items 1 thru 12 and 14 and UFSAR 6.2.5.2.5 and the test is considered:

2.1.1 SATISFACTORY (All acceptance criteria is marked SAT)

SM/CRS Date/Time UNSATISFACTORY ancl !E necessary the TIS ACTION statement 2.1.2 has been implemented.

SMiCRS Date/Time 2.1.3 Order No.

2.1.4 Remarks Variance between LR-R623A and LR-R623B exceeds half of the allowable variance. System Engineering notified.

Page 14 of 22

TQ*AA*106*0303 JOB PERFORMANCE MEASURE ATTACHMENT 1 (Page 3 of 3)

SM/CRS DATA AND SIGNATURE SHEET ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK* MONTHLY 3.0 PROCEDURE PERFORMER(S) AND VERIFIER(S) 3.1 I have read and understand the steps of this procedure that I am required to Perform.

(All Departments)

PRINT NAME SIGNATURE INITIALS DATE/TIME Joe Johnson

~~ ---

pep TODAY/NOW Page 15 of 22

~M~~A@@IoI\V7 TQ-AA-106-0303 (Page 1 of 13) ljJ 2J CONTROL ROOM DATA SHEET ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK - MONTHLY REACTOR VESSEL PRESSURE: INSTRUMENTATION MAX VARIANCE STEP INSTRUMENT NUMBER PRESSURE BETWEEN CHs 5.4.1 PI-3684A (RED) 75 PSIG 5.4.2 PR-3684A-1 (Red) (NOTE 1)

)

5.4.3 PR-3684B (RED) 5.4.4 Reactor Vessel Pressure Instrumentation Channel Check SAT/UI\lSAT INITIAL REACTOR VESSEL WATER LEVEL INSTRUMENTATION MAX VARIANCE STEP INSTRUMENT NUMBER LEVEL BETWEEN CHs 5.5.1 LR-R615

-- 10 INCHES (NOTE 1) 5.5.2 LI-R61 0 5.5.3 LR-R623A (RED) 32

-- 10 INCHES (NOTE 1) 5.5.4 LR-R623B (RED) 26 5.5.5 LR-3622A (BLUE)

-- 20 INCHES (NOTE 1) 5.5.6 LR-3622B (BLUE) 5.5.7 Reactor Water Level Instrument Channel Check SAT/UNSAT INITIAL

The asterisk indicates acceptance criterion - in order to satisfy the requirements of the acceptance criteria, the SAT/UNSAT block must be marked SAT NOTE 1 !E maximum channel variance exceeds half the required value NOTIFY System Engineer. [CD-772Fj Page 16 of :~2

~MLrn~@@IoI\V7 TQ*AA-106*0303 (Page 2 of 13)

CONTROL ROOM DATA SHEET l.fl JJ ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK

MONTHLY SUPPRESSION POOL WATER LEVEL INSTRUMENTATION I

MAX VARIANCE STEP INSTRUMENT NUMBER LEVEL I BETWEEN CHs 5.6.1 )

- 9 INCHES 5.6.2 U-4801 (BLUE) 5.6.3 Suppression Pool Level Instrumentation Channel Check SATIU I\lSAT INITIAL SUPPRESSION CHAMBER PRESSURE INSTRUMENTATION MAX VARIANCE STEP INSTRUMENT NUMBER PRESSURE BETWEEN CHs 5.7.1 PR-4960A1 (RED) 10 PSIG 5.7.2 PR*4960B1 (RED) 5.7.3 PR*4960B3 (GREEN) 0.5 PSIG 5.7.4 PI*4960B3 (RED) 5.7.5 Suppression Chamber Pressure Instrumentation Channel Check SAT/UNSAT INITIAL

The asterisk indicates acceptance criterion - in order to satisfy the requirements of the acceptance criteria, the SAT/UNSAT block must be marked SAT Page 17 of 22

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. HC.OP-ST.SH-0001(Q), Accident Monitoring Instrumentation Channel Check - Monthly is required.

2. No other testing or maintenance is in progress that will adversely affect the performance of this test.

INITIATING CUE:

PERFORM Steps 5.1 through 5.6.3 of HC.OP-ST.SH~0001 (Q),

Another operator will complete the rest of the Surveillance (Steps 5.7 to end).

Page 18 of 22

TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to 100% power, COMPLETE Section 1 of HC.OP-ST.SH-0001 to support the surveillance.

ENSURE LR-R623A-B21 indicates 32. Adjust 1/0 Override as necessary.

ENSURE LR-R623B-B21 indicates 26. Adjust I/O Override as necessary.

ENSURE HPCI LR-PR 3684A-1 is in Trend display mode.

ENSURE other Indications are SAT lAW the surveillance. Adjust as necessary.

REMOVE any simulated plant Red Stripes associated with surveillance Instruments.

EVENT ACTION:

COMMAND:

PURPOSE:

EVENT ACTION:

2 COMMAND:

PURPOSE:

Page 19 of 22

TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) 8AR22 R AO REAC LEVEL LR-R623B-B21 NONE 26.5 Page 20 of 22

TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ025 Rev# Date Description Validation Required?

01 11/18/08 Converted JPM ZZ025 to new JPM format. Since Critical JPM Y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial, validation not required.

Removed references to check.ing off/initialing steps in procedure. This is a generic work practice and adds unnecessary clutter to the Standard section. This change is editorial, validation not required.

New revision of ST.SH-0001 added channel check for new Control Room indicator PI-36B4A-1. This requires validation.

03 6/2/10 Revised Step 5.4.2 to add panel location due to procedure Y revision to Rev. 29. Adjusted override values due to new simulator model. Validated with 2 ROs. Avg time was 13 minutes. Added to setup, "ENSURE LR-PR-3684A-1 is in Trend Display mode."

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Rad ioactivity TASK NUMBER: 4000270401 JPM NUMBER: 305H-JPM.ZZ020 REV #: 01

- - I\JRC ADMIN JPM RO A4***

SAP BET: NOH05JPZZ20E ALTERNATE PATH: D APPLICABILITY:

EO D RO [ ] ] STA D SRO [ ] ]

DEVELOPED BY: Archie E. Faulkner DATE: 6/2/10 Instructor REVIEWED BY:

~s Representative DATE: (0 ~(j6';)I tJ APPROVED BY: 0tr~

Training Department DATE: 7/10)0

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 22020 REV:. 01 SYSTEM: Administrative TASK NUMBER: 4000270401 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity ALTERNATE PATH: 0 KIA NUMBER:

- -295038

--- A1.01 1M PORTANCE FACTOR: 3.9 4.2 APPLICABILITY: RO SRO EO RO [ ] ] STA D SRO [ ] ]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0004 Rev.4 i TOOLS, EQUIPMENT AND PROCEDURES: Calculator ESTIMATED COMPLETION '"IME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: __N_/A _ _ lVIinutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF ..IPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 12

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Ad ministrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity TASK NUMBER: 4000270401 INITIAL CONDITIONS:

1. The plant is operating at 100% power.

2. A Fuel Bundle was damaged while being moved in the Spent Fuel Pool.

3. Rising activity is observed on the following RM-11 radiation monitors:

South Plant Vent (SPV) (9RX580)

Refuel Floor Exhaust A, B, and C (9RX627, 628, 629)

4. SPDS is unavailable.

5. GRIDS is unavailable.

6. Abnormal HC.OP-AB.CONT-0004(Q), Radioactive Gaseous Release, and HC.OP AB.GONT-0005(Q), Irradiated Fuel Damage, are being executed concurrently to stop the release of activity.

INITIATING CUE:

Using the RM-11 , determine the Total Noble Gas Release Rate in accordance with Action A.4 of HG.OP-AB.CONT-0004(Q).

PagE~ 3 of 12

TQ-AA-106-0303 JPM: ZZ020 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity (e Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD e ELEMENT S/U . evaluation)

CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

i

~ ~ ~

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

CUE IF candidate attempts to use CRIDS state "CKIUS is unavailable". <IISI Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.CONT-0004.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be A.4.

A.4 DETERMINE the Total Release Rates Operator manipulates the RM-11 of Noble Gas and Iodine as follows: terminal to obtain the values of Noble USE the SPDS Noble Gas Total. Gas release from the 9RX580, 9RX590, OR 9RX680, and 9RX518 detectors and enters the value into the formula; then USE one of the Formulas in Table the operator calculates the Total Noble "A". Gas Release Rate as follows:

Operator determines SPDS is not available.

Page 4 of 12

TQ-AA-106-0303 JPM: ZZ020 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ________~--------

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity

(. Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluation)

Operator used the first formula from Table "A".

Operator uses RM-11 to determine Operator determines value for 9RX580

value for SPV (9RX580). (SPV) is 1.46E+OO !-lCi/sec.

Operator uses RM-11 to determine Operator determines value for 9RX590

value for NPV (9RX590). (NPV) is 1.04E+01 !-lCi/sec.

Operator uses RM-11 to determine Operator determines value for 9RX680

value for FRVS C9RX680). (FRVS) is 4.18E+01 jJCi/sec.

Operator uses RM-11 to determine Operator determines value for 9RX518

value for HTV (9RX518). (HTV) is O.OOE+OO !-lCi/sec.

Operator uses RM-11 to determine Operator determines value for [.ICi/sec

value for Total. Total is 5.366E+01 !-ICi/sec.

EXAMINER NOTE: A tolerance of 0.1 is acceptable. (5.266E+01 to 5.466E+01 !-lei/sec)

Page 5 of 12

TQ-AA-106-0303 JPM: ZZ020 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity

(. Denotes a Critical Element COMMENTS STEP of a Critical Step)

("'Denotes a Critical Step) '" EVAL {Required for UNSAT NO. STANDARD ELEMENT

S/U eval CUE WHEN operator informs you the task is complete, .

OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete",

STOP TIME:

Page 6 of 12

TQ~AA~1 06-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: ZZ020 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity TASK NUMBER: 4000270401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 7 of 12

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: ZZ020 REV#: 01 INITIALIZE the simulator to 100% power, MOL UNPLUG SPDS Monitors.

TURN OFF CRIDS Monitors.

MANUALLY PLACE FRVS in service lAW HC.OP-SO.GU-0001.

PLACE Simulator in FREEZE.

ENSURE a copy of HC.OP-AB.CONT-0004 is available.

COMPLETE "Simulator Ready-for-Training/Examinatlon Checklist".

EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 8 of 12

TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: ZZ020 REV#: 01 RM9627 RFE 'A' - Refuel Floor Exhaust Chan 'A' Vent Duct RM9628 RFE 'B' - Refuel Floor Exhaust Chan 'B' NONE Vent Duct RM9629 RFE 'C' - Refuel Floor Exhaust Chan 'C' NONE 1.49E-3 Vent Duct RM9580 SPV EFF - South Plant Vent Noble Gas NONE 1.46 Effluent RM9680 FRVSV EFF - FRVS Vent Noble Gas NONE 41.8 Effluent RM9590 j\JPV EFF - North Plant Vent Noble Gas NONE 10.4 Effluent AN-C6C5 CRYWOLF ANN C6C5 SPDS SYS . NONE Page 9 of 12

TQ~AA~1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ020 Rev # Date Description Validation

_ _ _ _ _ _ _ _ _ _-1 .... Required?

01 I 6/210 Converted JPM ZZ020 to new JPM format. Broke Critical Task Y i into individual elements. Turned off all CRIDS Monitors. Added I

Cue that CRIDS is unavailable. Validated with 2 ROs. Avg time

.... _--- was 4 minutes. No vVIIIIIII;;:IIl;:'. i i I

i i I

i i Page 10 of 12

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is operating at 100% power.

2. A Fuel Bundle was damaged while being moved in the Spent Fuel Pool.

3. Rising activity is observed on the following RM-11 radiation monitors:

South Plant Vent (SPV) (9RX580)

Refuel Floor Exhaust A, B, and C (9RX627, 628, 629)

4. SPDS is unavailable.

5. CRIDS is unavailable.

6. Abnormal HC.OP-AB.CONT-0004(Q), Radioactive Gaseous Release, and HC.OP-AB.CONT-0005(Q), Irradiated Fuel Damage, are being executed concurrently to stop the release of activity.

INITIATING CUE:

Using the RM-11 , determine the Total Noble Gas Release Rate in accordance with Action A.4 of HC.OP-AB.CONT-0004(Q).

Page 12 of 12

/

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations TASK NUMBER: H304000007 JPM NUMBER: 305H-.JPM.ZZ41 REV #: 00

- - NRC ADMIN JPM SRO A1***

SAP BET: NOH05JPZZ41E ALTERNATE PATH: W APPLICABILITY:

EoD RO D STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 6/30/10 Instructor REVIEWED BY:

~ Operations Representative DATE: ee(3 0(ZO/O APPROVED BY: on~

Training Department DATE: 7////0

TQ"AA*106-0303 STATION: Hope Creek JPM NUMBER: ZZ41 REV: 00 SYSTEM: Conduct of Operations TASK NUMBER: H304000007 TASK: Verify DL-26 log requirements for resuming Core Alterations ALTERNATE PATH: [ } [ ] ~ANUMBER: ______2_.1_.1_8_____

IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EoD ROW STAD SROW EVALUATION SETTING/M ETHOD: Classroom/Perform

REFERENCES:

HC.OP-DL-ZZ-0026(Q) Rev. 121 HC.OP-ST.KE-OOO'1 Rev" 31 TOOLS, EQUIPIVIENT AND PROCEDURES: Blank Core Map Marked up copy of HC.OP-ST.SF-0001, .

Marked up copy of HC.OP-DL-ZZ-0026(Q) Attachment 2 ESTIMATED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

--- N/A

- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIIVIE CRITICAL COIVIPLETION TIME: N/A Minutes REASON,IF JPM UNSATISFACTORY:

EVALUATORJS SIGNATURE: DATE:

Page 2 of 12

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations TASK NUMBER: H304000007 INITIAL CONDITIONS:

1. Operational Condition 5, with the reactor core fully loaded.

2. The One-Rod-Out Interlock is operable.

3. Control Rod Drive Mechanism (CRDI\I,) 34**39 has been removed.

4. All other rods are at 00.

5. CRDM 26-43 is scheduled to be replaced once CRDM 34-39 is restored.

6. The following Control Rods are hydraulically disarmed for this work:

18-51 22-51 26-51 30-51 34**51 18-47 22-47 26-47 30-47 34-47 38-47 42-47 18-43 22-43 26-43 30-43 34*-43 38-43 42-43 18-39 22-39 26-39 30-39 34**39 38-39 42-39 18-35 22-35 26-35 30-35 34**35 38-35 42-35 30-31 34**31 38-31 42-31

As the CRS, you direct HC.OP-DL.ZZ-002*6 logs for Attachment 2 ITEMS 13, 14, and 15 to be taken for the midnight shift.

INITIATING CUE:

Validate the completed HC.OP-DL.ZZ-0026 Attachment 2 ITEMs 13, 14, and 15 for the midnight shift.

Page 3 of 12

TQ-AA-106-0303 JPM: ZZ41 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

CUE Provide operator marked-up copy of HC.OP-DL-ZZ-0026 Attachment

2. N/A Operator determines beginning step Operator determines correct beginning of the procedure. step to be 3.2.

3.2 If in OP CON 4 or 5 then complete Operator reviews Attachment 2.

Attachment 2 as follows daily.

Examiner Note: Initialing steps is not critical. I N/A Page 4 of 12

TQ-AA-106-0303 JPM: ZZ41 OPERATOR TRAINING PROGRAM NAME: _________________

Rev: 00 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations

(*Denotes a Critical Step) COMMENTS STEP (#Denotes a Sequential Step)

ELEMENT EVAL (Required for UNSAT NO. STANDARD # SIU evaluation)

ITEM 4 FUEL ASSEMBLIES 13 SURROUNDING EACH REMOVED CONTROL ROD OR MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL OR ALL OTHER CONTROL RODS IN A 5X5 ARRAY HAVE BEEN INSERTED AND DISARMED.

CUE Provide copy of blank Control Rod Il N/A ~

map_

Operator uses list of hydraulically disarmed Control Rods to determine that Control Rod 34-39 DOES NOT meet this requirement.

Operator identifies ITEM 13 is * -

incorrectly marked YES.

Page 5 of 12

TQ-AA-106-0303 JPM: ZZ41 OPERATOR TRAINING PROGRAM NAME: ___________________

Rev: 00 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations

(*Oenotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL* (Required for UNSAT NO. #

STANDARD S/U evaluatio Operator marks ITEM 13 in the MID

column NO or UNSAT, Operator adds an entry in the COMMENTS section to indicate Rod 34-39 does not meet the 5 X 5 requirement because 26-31 is not dis armed.

CUE If necessary, cue the operator to continue with the remaining items. N/A ITEM VERIFY HC.OP-ST.SF-0001 (Q) 14 IS CURRENT.

CUE Provide operator with marked up copy of HC.OP-ST.SF-0001. N/A Page 6 of 12

TQ-AA-106-0303 JPM:* ZZ41 OPERATOR TRAINING PROGRAM NAME:

DATE: ___________________

Rev: 00 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations

(*Denotes a Critical Step) .., COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD StU evaluati Operator obtains last completion date of the last performance from Attachment 1 of HC.OP-ST.SF-0001.

Operator determines difference of 19 months is correct Operator identifies that ITEM 14 should .*

EXAMINER NOTE:

be marked YES or 19 Mo.

It is critical that the SRO identify 4.0.2 can be applied. Tech Spec 4.0.2 grace period of 25%

can be applied, and should be noted in the COMMENTS.

CUE If necessary, cue the operator to continue with the remaining items.

ITEM ALL OTHER CONTROL RODS ARE Operator determines from the 15 INSERTED Conditions that all other rods are inserted.

Page 7 of 12

TQ-AA-106-0303 JPM: ZZ41 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Conduct of Operations TASK: Verify DL-26 log requirements for resuming Core Alterations

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. # eval**...+i ....... \

STANDARD StU Operator observes the ITEM is correctly logged.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons,

. THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 12

JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ41 Rev # Date Description Validation Required?

00 6/1/10 Significantly modified Hope Creek 2003 NRC Remediation Y

, Exam Admin A1-2. Changed related rods to a different part of

. the core. Updateto new ,JPM format. Updated all related procedure revisions. Corrected KA Importance Factor values.

Validated with 2 SROs. Feedback provided to change 19 Mo.

with NO for Item 14.

HC.OP-DL;'. J026(Q}

ATTACHMENT 2 Page 20f5 Refuel/Core Alterations Date Todav's Date ITEM SURVEilLANCE OPER COND I ACCEPTABLE LIMITS MIN NORM MAX INSTRUMENT (PANEL) DAY COMMENTS IE CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER TIS 3.9.10.1 OR 3.9.10.2, THEN ITEMS - N/A

10. I REACTOR MODE SWiTCH POSITION I 4,5 I I LOCKED IN SID OR i (10C651) I ~ I I (NOTE 1)

REFUEL

11. I FUEL LOADING OPERATIONS 4,5 YES N1A SUSPENDED

12. I SRM'S FULLY INSERTED AND 4,5 YES OPERABLE lAW TIS 3.9.2 LE CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER T, I 4 FUEL ASSEMBLIES ~..-JRod 34-39 does not meet 5X5 13.

SURROUNDING EACH REMOVED CONTROL ROD OR 4,5

-=-IYES MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL OR ALL OTHER CONTROL RODS INA5X5 ARRAY HAVE BEEN iNSERTED AND I

DISARMED.

14. I VERIFY HC.OP-ST.SF-0001(Q) 4,5 NfA NfA Surveilance date 1/20/09 is within 25%

IS CURRENT. race period ofTS 4.0.2

15. I ALL OTHER CONTROL RODS 4,5 ARE INSERTED YES

16. I VERIFY REACTOR MODE NfA NfA NfA (NOTES)

SWITCH REFUEL POSITION ONE-ROO-OUT INTERLOCK OPERABLE AND CURRENT lAW HC.OP-8T.KE-0001(Q)

_. ,,,..-'Or.,

IS BEING MAlNTAINED "lOCKED".

~_.-

NOTES: 1.

5. ONTROl ROD OR CONTROL ROD MECHANISM REMOVAL UNDER TIS 4.9.10.1.

6. ENCY EVERY 7 DAYS, lAW TIS 3.9.1.

Hope Creek Page 56 of 101 Rev. 121

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: ZZ41 TASK: Verify DL"26 log requirements for resuminu Core Alterations TASK NUMBER: H304000007 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 12

TQ-AA..106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Operational Condition 5, with the reactor core fully loaded.

2. The One-Rod-Out Interlock is operable.

3. Control Rod Drive Mechanism (CRDM) 34-39 has been removed.

4. All other rods are at 00.

5. CRDM 26-43 is scheduled to be replaced once CRDM 34.,39 is restored.

6. The following Control Rods are hydraulically disarmed for this work:

18-51 22-51 26-51 30-51 34*51 18-47 22-47 26-47 30-47 34,*47 38-47 42-47 18-43 22-43 26-43 30-43 134-43 38-43 42-43 18-39 22-39 ,26-39 30-39 34,*39 38-39 42-39 18-35 22-35 26-35 30-35 34,*35 38-35 42-35 30-31 34,*31 38-31 142-31

As the CRS, you direct HC.OP-OL.ZZ-0026 logs for Attachment 2 ITEMS 13, 14, and 15 to be taken for the midnight shift.

INITIATING CUE:

Validate the completed HC.OP-DL.ZZ-0026 Attachment 2 ITEMs 13, 14, and 15 for the midnight shift.

Page 10 of 12

HC.OP-DL.; )026(Q)

ATTACHMENT 2 Page 1 of 5 Refuel/Core Alterations Date Today's Date OPER ITEM SURVEILlANCE COND INSTRUMENT (PANEL) DAY COMMENTS

1. REACTOR MODE SWITCH 5 (10C651)

POSITION

2. I DATE THE REACTOR MODE 5 WITHIN .N/A SWITCH REFUEL POSITION LAST ONE-ROO-OUT INTERLOCK WAS VERIFIED OPERABLE I 7 DAYS lAW HC.OP-ST.KE-0001(Q}

3. J ALL SRM'S FULLY INSERTED 4,5 YES

4. I RX WATER LEVEL >22' 2" 5 YES

5. I ALL CONTROL RODS 4,5 (NOTE 2)

INSERTED AND ALL CONTROL ROD DRIVE MECHANISMS INSTALLED

6. I ADEQUATE SHUTDOWN MARGIN 1 4

,51 YES IF CORE ALTERATIONS ARE IN PROGRESS THEN COMPLETE ITEMS 7

7. I OPERA.BLE SRM IN SAME AND A ..,

-" t; YES (NOTE 7)

ADJACENT QUADRANT AS CORE ALTERATIONS

8. I DIRECT COMMUNICATION BETWEEN CONTROL ROOM I 5 (10C651)

AND REFUEL FLOOR EXISTS.

9. I DATE THE NEEDED REFUEL 5 N/A POSITION INTERLOCKS WERE DEMONSTRATED OPERABLE lAW HC.OP-ST.KE-0001 (Q).

NOTES: 1. ENSURE KEY IS RE IS BEING MAINTAINED "LOCKED".

2. EXCEPT CONTR! 00 DRIVE MECHANISMS REMOVED PER TIS 3.9.10.1 OR 3.9.10.2 (SHORTING LINKS MAY HAVE TO BE PULLED FOR OTHER CONTROL ROD

7. THIS IS 8T 3 SRMS ARE OPERABLE DUE TO THE QUADRANT REDEFINrTION ANALYSIS. IF LESS THAN 3 SRMS ARE OPERABLE, REFER TO HC.RE- ER GUIDANCE.

Hope Creek Page 55 of 101 Rev. 121

HC.OP-DL: )026(Q)

ATTACHMENT 2 Page 2 of5 Refuel/Core Alterations Date Today's Date ITEM SURVEILLANCE OPER COND I ACCEPTABLE LIMITS MIN NORM MAX INSTRUMENT (PANEL) DAY COMMENTS lECONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER TIS 3.9.10.1 OR 3.9.10.2, THEN C 11,12, AND 13, OTHERWISE, MARK ITEMS-N/A

10. I REACTOR MODE SWITCH POSITION I 4,5 I IIN LOCKED SID OR I (10C651) (NOTE 1)

REFUEL

11. I FUEL LOADING OPERATIONS 4,5 YES NIA SUSPENDED

12. I SRM'S FULLY INSERTED AND 4, 5 YES OPERABLE lAW TIS 3.9.2 lE. CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER TIS 3.

13. I 4 FUEL ASSEMBLIES I 4, 5 YES YES SURROUNDING EACH REMOVED CONTROL ROD OR MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL Q8 ALL OTHER CONTROL RODS IN A5X5ARRAY HAVE BEEN INSERTED AND DISARMED.

14. I VERIFY HC.OP-ST.SF-0001(Q) 4,5 NIA N/A NIA IS CURRENT. NO

15. I ALL OTHER CONTROL RODS 4,5 ARE INSERTED YE"'S

16. VERIFY REACTOR MODE NfA N/A N/A (NOTES)

SWITCH REFUEL POSITION ONE-ROD-OUT INTERLOCK OPERABLE AND CURRENT lAW HC.OP-ST.KE-0001(Q)

NOTES: 1. HILESW!TCH IS BEING MAINTAINED L.V'JN::U

5. TART OF CONTROL ROD OR CONTROL ROD MECHANISM REMOVAL UNDER TIS 4.9.10.1,

6. ,:\[ION FREQUENCY EVERY 7 DAYS, lAW TIS 3.9.1.

'-\:,;lj>

~

Hope Creek Page 56 of 101 Rev. 121

HC.OP-DL.: J026(Q)

ATTACHMENT 2 . Page 3 of5 Refuel/Core Alterations Date Todayrs Date

.---=~=::

OPER ACCEPTABLE LIMITS ITEM SURVEILLANCE COND MIN NORM MAX INSTRUMENT (PANEL) DAY COMMENTS IF CONTROL RODS OR CONTROL ROD MECHANISMS HAVE BEEN REMOVED UNDER TIS 3.9.10.2, THEN COMPLETE ITFM'I:~Ilf7<lm

17. I THE 4 FUEL ASSEMBLIES 5~

YES NIA (NOTE 3)

SURROUNDING EACH REMOVED CONTROL ROD OR MECHANISM HAVE BEEN REMOVED FROM THE CORE CELL.

18. I ALL OTHER CONTROL RODS 4,5 YES ARE INSERTED IF THE REFUELING PLATFORM FUEL GRAPPLE IS IN SERVICE THEN COMPLETE ITEMS 19 TH IFTHE REFUELING PLATFORM FUEL GRAPPLE IS NOT IN SERVICE OR IF ITEMS HAVE AL TED ONCE ON THIS DAILY LOG THEN MARK ITEMS 19 THRU 26 AS NlA

19. I VISUALLY INSPECT THE FUEL 5 SAT GRAPPLE HOIST CABLE BY OBSERVING THE CABLE IS PROPERLY WOUND ON THE HOIST DRUM, NOT KINKED OR I CREASED AND INDIVIDUAL WIRE THREADS ARE NOT BROKEN

20. I VISUALLY INSPECT THE FUEL 5 (LOCAL)

GRAPPLE PNEUMATIC HOSES BY OBSERVING THE HOSES ARE NOT RIPPED, TORN OR KINKED

21. I VISUALLY INSPECT THE FUEL I 5 (LOCAL)

GRAPPLE LIGHT ELEC. CABLE BY OBSERVING THE CABLE IS NOT BROKEN OR STRIPPED

22. I VERIFY THE NORMAL (LOCAL)

GRAPPLE UP LIMIT SWITCH OPERABLE BY OBSERVING THAT THE EUEL G HOIST AUTOMAT STOPS", 8 FEET WATERLEVE GRAPPLE Up*

ILLUMINATES NOTES: 3. THE ONE-ROI1J~'F'INTERLOCKMAY BE BYPASSED FOR THE AFFECTED CONTROL CELLS AFTER THE FUEL IS REMOVED FROM THE CELLS (TIS 3.9.10.2.A)

4. ITEMS 19THRU 26 ARE ONLY REQUIRED TO BE COMPLETED ONE TIME DAILY WHEN THE REFUELING PLATFORM FUEL GRAPPLE IS IN USE.

Hope Creek Page 57 of 101 Rev. 121

HC.OP-DL.~ 1026(Q)

ATTACHMENT 2 Page 4 of5 Today's Date Refuel/Core Alterations Date _ __

ITEM I SURVEILLANCE OPER I COND I ACCEPTABLE LIMITS MIN NORM MAX INSTRUMENT (PANEL) I DAY Jz;,\{E"" '1¢~MID COMMENTS

23. I VISUALLY INSPECT THE FUEL 5 I SAT I (LOCAL)

GRAPPLE HOOKS BY OBSERVING:

A WHEN THE FUEL GRAPPLE

'ENGAGE' PB IS DEPRESSED, THE FUEL GRAPPLE HOOKS MOVE TO THE ENGAGFD POSITION, THE 'ENGAGE' LIGHT IS ON, AND NO AIR BUBBLES ESCAPE FROM THE AIR HOSES OR HOOK OPERATING CYLINDER, AND B. WHEN THE FUEL GRAPPLE

'RELEASE' PB IS DEPRESSED, THE FUEL GRAPPLE HOOKS MOVE TO THE RELEASED POSITION, THE 'ENGAGE' LIGHT IS OFF, AND NO AIR BUBBLES ESCAPE FROM THE AIR HOSES OR HOOK OPERATING CYLINDER.

~:i&il "'"

24. I VERIFY THE SLACK CABLE LIMIT SWITCH IS OPERABLE BY I 5 I SAT .!::1il'4.

. "~~.'.. :i'!i',;,:"""

¥';4}ii:i~;~) (LOCAL)

OBSERVING THAT WHEN THE GRAPPLE IS LOWERED ONTO A FUEL BUNDLE OR DUMMY FUEL BUNDLE, DOWNWARD MOTION AUTOMATICALLY STOPS AND THE "SLACK CABLE" LIGHT ILLUMINATES.

25. I VERIFY THE HOIST LOADED (LOCAL)

SWITCH IS OPERABLE BY OBSERVING:

A. WHEN A FUEL BUNDLE DUMMY FUEL BUNDLE IS THE "HOIST LOADED" ILLUMINATES, AND B. WHENTHEB DOWN THE "HOIST LIGHT EXTINGUISH Hope Creek Page 58 of 101 Rev. 121

HC.OP-DL: J026(Q)

ATTACHMENT 2 Page 5 of 5 Refuel/Core Alterations Date Todayfs Date ITEM SURVEILLANCE OPER COND I ACCEPTABLE.LlMITS MIN NORM MAX INSTRUMENT (PANEL) DAY COMMENTS

26. I VERIFY THE FUEL GRAPPLE 5 SAT (LOCAL)

BRAKE IS OPERABLE BY OBSERVING NO DOWNWARD MOTION OF THE FUEL GRAPPLE WHEN A FUEL BUNDLE OR DUMMY FUEL BUNDLE IS SUSPENDED ON THE FUEL GRAPPLE.

Hope Creek Page 59 of 101 Rev. 121

59 I r 55 I

51 47 43 39 35 31 27 23 19 15 11 07 10 14 18 22 26 30 34 38 42 46 50 54 58

f f JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 JPM NUMBER: 305H..JPM.ZZ031 REV#: 02

- - NRC ADMIN ..IPM SRO A2***

SAP BET: NOH05JPZZ31 E ALTERNATE PATH: 00 APPLICABILITY:

EOD RO D STA SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 6/1/10

~MPstructor REVIEWED BY: DATE: &2 boL 2.0 ( c)

Operations Representative APPROVED BY:

0Jtf~

Training Department DATE: 7///[0

TQ-M-106-0303 STATION: Hope Creek JPM NUMBER: ZZ031 REV: 02 SYSTEM: Conduct of Operations TASK NUMBER: 2991110302 TASK: Initiate and Review System Lineup Sheets ALTERNATE PATH: [ ] ] KIA NUMBER: _ . _ -2.1.29 IMPORTANCE FACTOR: 4.1 4.0 APPLICABILITY: RO SRO EoD ROD slAD SRO[]J EVALUATION SETTING/METHOD: Classroom/Perform

~~~~~~it'f~

REFERENCES:

HC.OP-IO.ZZ-0003 Rev 91'1;'$ .

M-42-1 Sheet 2 Tech Spec 3.3.2 TOOLS, EQUIPMENT AND PROCEDURES:*

Simulated Off-Normal Report, Prepared HC.OP-IO.ZZ-0003 Attachment 4 ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 15

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Conduct of Operations TASK:. Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 INITIAL CONDITIONS:

1. A start-up is in progress lAW HC.OP-IO.ZZ-0003.

2. Preparations are being made to enter Operational Condition 1 lAW Attachment 4 of the lOP.

3. The Current Mode has been changedto Mode 1 lAW step 1.2.1 of Attachment 4.

4. A Components in OFF-Normal Position Report has been generated lAW step 1.2.3 of HC.OP-IO.ZZ-0003 Attachment 4.

INITIATING CUE:

COMPLETE step 1.2.4 of HC.OP-IO.ZZ-0003 Attachment 4.

You will be allowed access to SAP and DCRMS to research component data.

The provided Off Normal Report does NOT reflect the current status of the actual plant.

Do NOT perform ANY changes to actual plant data.

Page 3 of 15

TQ-A.A-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu eval CUE PROVIDE the operator the initiating cue AND:

o Prepared HC.OP-IO.ZZ-0003 Attachment 4 (Attached) Operator repeats back initiating cue.

o Prepared Components Off-Normal Position Report (Attached)

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

HC.OP-IO.ZZ-0003 Attachment 4 I N/A 1.2.3 GENERATE a Components In Off Normal Position Report N/A USING WCM Reports/Off Normal Report function.

Page 4 of 15

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME: ___________________

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.2.4 POSITION all components as Operator reviews Components In required. Off-Normal Position Report.

Operator recognizes the following

isolation valves are closed and should be open:

H1AB -1ABV9979-B

H1AB -1ABV9980-B Operator determines these valves are

required for isolation instrumentation in I OPCON 1.

I Examiner Note: I M-42-1 Sheet 2 - Transmitters are Main Steam Low Pressure to NSSSS TIS Table 3.3.2-1 Trip Function 3c Page 5 of 15

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE AFTER the operator determines the V9979-B and V99S0-B are required to be open, THEN:

INFORM the operator investigation has determined the valves were inadvertently closed Operator repeats initiating cue and during I&C work on the opposite accepts updated Off-Normal.

channels and have been re-opened.

PROVIDE the operator the updated Off-Normal with the I V9979-B and V99S0-B removed. I I I I 1.2.4 POSITION all components as Operator reviews Components In required. Off-Normal Position Report.

Operator recognizes NO components require re-positioning.

Operator initials IO.ZZ-0003

Attachment 4 step 1.2.4.

Page 6 of 15

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

{"'Denotes a Critical Step} 'I< COMMENTS STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 7 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 22031 TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 8 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ031 Rev # Description Validation I

Required?

1 11/9/08 Converted ZZ031 to new JPM format. Y Changed critical Off-Normal components to MSL Low Pressure transmitters, which are NOT required in OPCON 2, but ARE required in OPCON 1.

Updated Off-Normal distractor items to more current dates.

Added CUE that valves were re-positioned and a corrected Off-Normal to provide to the operator and allow completion of

the task.

2 6/1/10 Updated all reference procedure revisions. Updated Off-normal printout Change Dates to be consistent with exam dates. No Y I operator actions have changed. Validated with 2 SROs. Avg validation time was 8 minutes. Added EXHIBIT 1 and EXHIBIT 2 to the IineLl~ sheets.

TQ*AA*106*0303 JOB PERFOFlMANCE MEASURE INITIAL CONDITIONS:

1. A startwup is in progress lAW HC.OP-IO.ZZ-0003.

2. Preparations are being made to enter Operational Condition 1 lAW Attachment 4 of the lOP.

3. The Current Mode has been changed to Mode 1 lAW step 1.2.1 of Attachment 4.

4. A Components in OFF-Normal Position Report has been generated lAW step 1.2.3 of HC.OP-IO.ZZ-0003 Attachment 4.

INITIATING CUE:

COMPLETE step 1.2.4 of HC.OPwIO.ZZ-0003 Attachment 4.

You will be allowed access to SAP and DCRMS to research component data.

The provided Off Normal Report does NOT reflect the current status of the actual plant.

Do NOT perform ANY changes to actual plant data.

Page 10 of 15

ATTACHMENT 4 STARTUP FROM COLD SHUTDOWN TO RATED POWER FINAL CHECKS (ENTERING OPERATIONAL CONDITION 1)

(Page 1 of 2)

NOTE The following checks may be performed in any order.

1. FINAL CHECKS 1.1 System requirements AND surveillances required for entering Operational Condition 1 are completed. This review must include the disposition of all outstanding Equipment Non~Conformances to determine impact on system operability. Any shutdown LCO's which will not be exited prior to changing modes have been assessed lAW Tech Spec 3.0A.b and OP~HC~1 08-115~1 001.

1.1.1 Operations 'BoD Today 1.1.2 I&C 'BirrSmith Today 1.1.3 Reactor Engineering Susan Ylntnony Today 1.1.4 Chemistry ends Anaerson Today 1.1.5 System Engineering 'Betty Xiaman Today Date 1.2 PRIOR to taking the RPS MODE SWITCH to RUN, PERFORM the following:

1.2.1. CHANGE WCM "Current Operating Mode" from 2 to 1 USING the Mode Dependent Tagging/Current Mode/Change function. T:M'B 1.2.2. ENSURE all current notifications are screened for operability prior to mode change. [70021851]

Joe ]onnson Today/Now SM/CRS DATE~TIME NOTE The Components in off - l\lormal Position Report will indicate all components NOT in the required position for POWER OPERATION.

1.2.3. GENERATE a Components In Off~Normal Position Report USING WCM Reports/Off Normal Report function. T:M'B Continued on next page

ATTACHMENT 4 STARTUP FROM COLD SHUTDOWN TO RATED POWER FINAL CHECKS (ENTERING OPERATIONAL CONDITION 1)

(Page 2 of 2) 1.2.4. POSITION all components as required.

1.2.5. UPDATE WCM using the Mode/Dependent Tagging/Normal Positions/Change Function.

1.2.6. The above items have been completed with all equipment required for going into POWER OPERATION available.

SM/CRS DATE-TIME 1.3 Pre-Startup Walk down COMPLETED. IF NOT required, INDICATE "NA". IF completed, ATTACH completed NC.CC-AP.ZZ-0011 (Q), Form-1, Pre-Startup Missile Hazard Inspection Report, to this procedure.

SM/CRS DATE-TIME Reviewed By:

SM/CRS

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet TASK NUMBER: 4010590202/2990640305 JPM NUMBER: 305H-JPM.ZZ029 REV #: 02

- - NRC ADMIN JPM SRO A3***

SAP BET: NOH05JPZZ29E ALTERNATE PATH: D APPLICABILITY:

EO RO D STA [KJ SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 8/2/10 Instructor REVIEWED BY: 0kffl DATE: n.t&o Operations Representative APPROVED BY: qv~ DATE: t/~/LD Training Department

TQ~AA*1 06*0303 STATION: Hope Creek JPM NUMBER: ZZ029 REV: 02 SYSTEM: Equipment Control TASK NUMBER: 4010590202/2990640305 TASK: Complete An Action Statement Log Sheet ALTERNATE PATH: D KiA NUMBER:

2.2.23 IMPORTANCE FACTOR: 3.1 4.6 APPLICABILITY: RO SRO EO D RO D STA [ ] ] SRO [ ] ]

EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

OP-HC-1 08-115-1001 Rev 10 Tech Spec 3.6.4.2 Amendment 133 HC.OP-ST.GS-0003 Rev 8 TOOLS, EQUIPMENT AND PROCEDURES: HC Technical Specifications

Prepared OP-HC-1 08-115-1 001 Attachment 3-1, Blank OP-HC-1 08-115-1001 Form 1 ESTIMATED COMPLETION TIME: 15 Minutes N/A TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 25

TQ-AA-106-0303 NAME: ____________________

DATE:

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet TASK NUMBER: 4010590202/2990640305 INn"tAL CONDITIONS:

1. The plant was at 100% power performing the monthly HC.OP-ST.GS-0003 Reactor Building/Suppression Chamber Vacuum Breaker Operability Test - Monthly.

2. The GS-PSV-5032 failed to stroke open when tested.

3. Local observation confirms the valve is failing to stroke due to a problem with the test actuator and the valve fully closed. .

4. All other valves passed the surveillance.

5. The failure occurred one hour ago at . (ENTER Current Time minus one hour)

6. SAP is currently unavailable, and no NOTF has been written.

7. SAP LCO Tracking is NOT available.

INITIATING CUE:

You are the CRS.

Complete a manual Action Statement log entry for the failure of GS-PSV-5032.

Determination of retests is NOT required at this time.

Page 30f25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU CUE PROVIDE the operator the initiating cue AND:

o A blank OP-HC-108-115-1001 Attachment 3-1 o Copy of OP-HC-1 08-115-1 001 Operator repeats back initiating cue.

o A blank OP-HC-108-115-1001 Form 1 o Copy of HC.OP-ST.GS~0003 o Technical Specifications CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator determines beginning Operator determines correct beginning step of the procedure. step to be 5.3.1 .

5.3.1 Any time it is determined that a TECH SPECS/LAOT SSC is or will be INOPERABLE either due to a Condition Adverse to Quality identified via the NOTF process Operator determines a TIS LCO must be (Section 5.1), a planned activity entered.

(Section 5.2), or following a Plant Transient, the appropriate TIS LCOILAOT Action Statement is entered.

Page 4 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) 5.3.2 DETERMINE if the TIS LCOILAOT Action Statement is ACTIVE or TRACKING based on the following criteria:

ACTIVE: An Active TIS LCOILAOT Action Statement is entered for those conditions where the SSC is INOPERABLE and the SSC design function is specifically required to be OPERABLE in the current Operational Condition by Technical Specifications/LAOTs. An example of an Active TIS LCO/LAOT Action Statement is a failure of an Emergency Diesel Generator to Operator determines failure requires satisfy its surveillance requirements in ACTIVE LeO due to INOPERABLE sse Operational Condition 1. and the the sse design function is TRACKING: A Tracking T/S specifically required to be OPERABLE in LCO/LAOT Action Statement is the current Operational Condition by entered whenever either of the Technical Specification 3.6.4.2.

following conditions exists:

The SSC is INOPERABLE, but is not required by Technical Specifications/LAOTs to be OPERABLE in the current Operational Condition. An example" of this type of Tracking TIS LCO/LAOT Action Statement is a failure of an Emergency Diesel Generator to satisfy surveillance requirements in Operational Condition

5. This includes refuel outage LCOs Page 5 of 25 not required for the current operational condition.

TQ-AA-106-0303 JPM: 22029 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.2 OR The SSC is INOPERABLE, but there cont is 100% redundant equipment that satisfies the Operability requirements of Technical Specifications/LOATs for the current Operational Condition. An Operator determines failure requires example of this type of Tracking TIS ACTIVE LCO due to absence of 100%

LCO/LAOT Action Statement is the redundant equipment lAW TIS 3.6.4.2.

inoperability of one 1E 125 VDC battery charger in Operational Condition 1, provided the other battery charger is OPERABLE (100%

redundant). [CD-026F]

5.3.3 IF the cause of the SSC being INOPERABLE is a planned Operations, Maintenance, Radiation Operator determines the cause was NOT Protection, or Chemistry Evolution planned and this step does NOT apply.

that satisfies the following criteria:

[CD-524G CD-538G CD-421Y]

5.3.4 For activities that cause a TECH SPECS/LAOT SSC to be Operator determines the cause does INOPERABLE that do not meet the NOT meet the criteria of Section 5.3.3 criteria of Section 5.3.3, DOCUMENT and the following steps apply.

the condition as follows:

Page 60f25

TQ-I-'iA 106-0303 M

JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD NOTE TS LCO/LAOT Action Statement Tracking may be accomplished using either the computerized SAP LCO N/A Tracking System or Attachment 3-1 and Fonn 1.

5.3.4.1 For SAP LCO tracking, REFER TO Based on Initial Conditions (Electronic guidance provided in LCO Tracking NOT available), operator OP-AA-108-115-1001, SAP LCO Entry. recognizes this step does NOT apply.

NOTE Preparation of Fonn 1 is not limited to the SM/CRS. Fonn 1 may be prepared by appropriate personnel in advance to support planned activities, or, after the fact during plant .

N/A transients. During nonnal operations, the SM/CRS remains responsible for the accuracy of the information provided and authorizing entry into TIS LCO/LAOT Action Statements.

Page 7 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluation) 5.3.4.2 For LCO tracking using Attachment 3- Based on Initial Conditions (Electronic 1 and Form 1, PEFORM the LCO Tracking NOT available) and following: Initiating Cue, operator recognizes the following steps apply.

5.3.4.2. ASSIGN the next consecutive LCO A Index Number obtained from the Action Statement Log Index (Attachment 3-1) and LOG the TIS LCO/LAOT ACTION Statement on the Index.

f-~~~~~

CUE PROVIDE the operator with the E Index Number... SIM-001.

N/A U

Operator assigns next consecutive log number SIM-001 from Attachment 3-1.

Operator logs the TSAS on the Index.

5.3.4.2. COMPLETE Sections 1 and 2 of B Form 1 by performing the following:

- RECORD the LCO Index Number Operator records SIM-001 in LCO INDEX (from Attachment 3-1 ) NUMBER.

- RECORD the LCO Status (Active Operator records ACTIVE in LCO

I Tracking) STATUS.

Page 8 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: ______-----------

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluation) 5.3.4.2. RECORD the applicable

B Technical Specification/LAOT LCO number. When an (cont) INOPERABLE TECH Operator records 3.6.4.2 in TECH SPEC SPECS/LAOT SSC affects NUMBER.

multiple LCO Action Statements, RECORD the LCO number with the most limiting Action Time.

- RECORD the DatelTime Entered. Operator records current date and

failure time from Initial Conditions in DATEITIME ENTERED.

- RECORD the Operational Operator records 1 ~2 and 3 in the Condition Applicability for the APPLICABILITY.

LCO.

RECORD the DatelTime Action

Required. When recording the date and time that Action is Operator records a Daterrime of failure required for an LCO Action time plus.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in DATEITIME Statement that has multiple ACTION REQUIRED.

actions, use the most limiting Action time. For Tracking Action Statements, record 'N/A'.

- RECORD Other Applicable TIS.

List only active LCOs. Applicable Operator recognizes no other TIS apply tracking LCOs should be listed and leaves blank.

separately in the Summary Description ofthe Log Sheet.

Page 9 of 25

TQ-AA-106-0303 JPM: ZZ029 ' OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.4.2. - RECORD the Equipment B description. Operator records GS-PSV-5032, or similar in EQUIPMENT.

(cont)

Briefly STATE the reason for the SSC condition in the Summary Description section and include a brief summary 9f actions required, Operator enters verbiage from TIS including submittal of any special 3.6.4.2 Action a. or similar.

reports to the NRC. NOTIFY the Shift Operations Superintendent of any reporting requirements.

--- L-----"

INITIATE Responsible ,

Department Notifications for required compensatory actions and DOCUMENT Name of Operator determines no compensatory Department and Person Notified actions or notifications are required_

with the Notification Dateffime, as well as Name of Person Making Notification_ (Include NOTIF # if applicable)

Page 10 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.4.2. The individual being notified will B come to the Control Room and sign the NOTIF# box next to their (cant) name to indicate that they have received the information and they Due to absence of compensatory actions, fully understand the action they operator determines this step does not have been directed to take. In the apply.

TSAS Description Addendum section they will list the procedure they will use to take the action to comply with the license.

- For recurring samples, analysis, hook-up of sample equipment, etc., the departmental individual performing this action will report to the Control Room and Due to absence of compensatory actions, document in the description operator determines this step does not addendum of the TSAS each time apply.

an action is taken. This will be audited at a frequency determined by Licensed Operations Supervision.

Page 11 of25

TQ-J.\A-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

("'Denotes a Critical Step) '" COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD SJU evaluation) 5.3.4.2. - When actions are no longer B required or an instrument is to be restored to the pre-LCO condition (cont) (example: OGPTRMS correction Due to absence of compensatory actions, factor) the action taken will be operator determines this step does not documented and signed for by the apply.

departmental individual performing the action in the description addendum section of the TSA8.

- ENSURE all applicable Non-Conforming Component/Material (NCCM) Evaluations, Notifications/Orders, Work Clearance Documents (WeD) etc., are entered on the Order and Operator leaves ORDER AND WeD weD Addendum. INCLUDE any ADDENDUM blank, since none is surveillances required to restore available and determination of retests is the equipment to operability as part of the Addendum. NOT required lAW Initiating Cue.

Surveillance tests should be reviewed to determine if the appropriate prerequisites would exist for the equipment scheduled restoration.

RECORD Redundant Equipment Operator enters Y in REDUNDANT Operable (YIN). EQUIPMENT OPERABLE.

Page 12 of 25.

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

DATE: ___________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step)

ELEMENT EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.4.2. IF the INOPERABLE SSC will impact C Secondary Containment Integrity per TIS 3.6.5.1 - during Fuel Handling and CORE ALTERATIONS when Secondary Containment Integrity and FRVS actuation is not required, Based on Initial Conditions (OPCON 1),

THEN COMPLETE Attachment 5, and absence of effect on Secondary "Contingency Plan for Sealing Containment, operator recognizes this Secondary Containment Penetrations During Fuel Handling and CORE step does not apply.

ALTERATIONS" for EACH inoperable penetration. Attachment 5, Section 1 L and 2 may be completed in advance as part of refueling outage preparations.

Page 13 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO. STANDARD NOTE For a planned entry into an action statement, SRO/STA concurrence is required, but the signature on the Action Statement Log Sheet is not required prior to entering the action statement.

For an unplanned entry into an action statement, SRO/STA concurrence should be obtained as soon as practical after entering the action statement.

If the person who completed Sections N/A 1 and 2 of Form 1 (Step 5.3.4.2.B) was not an actively licensed and proficient SRO, or a qualified and proficient STA, then the following step requires concurrence review from ah actively licensed and proficient SRO, and/or a qualified and proficient STA.

The actively licensed and proficient SRO, and/or the qualified and proficient STA completing the concurrence review shall not be the same person who authorizes entry into the TECH SPECS/LAOT Action Statement in 5.3.4.B.5 Page 14 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step)

EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati 5.3.4.2. OBTAIN CONCURRENCE REVIEW D from an actively licensed and proficient SRO and/or a qualified and proficient STA of plant conditions, TIS, existing active and tracking action statements, and, the TIS Action Statement Log, to ensure the equipment can be, or, is properly removed from service (for unplanned entry into a TIS LCO/LAOT Action Operator obtains CONCURRENCE Statement) and, that redundant REVIEW.

equipment is operabie. For planned entry into a TIS LCO/LAOT Action Statement, this review should be performed within a reasonable time prior to removal of the equipment from service to ensure plant conditions are reflective of conditions when the SSC will be removed form service. [CD.079A]

CUE ROLE PLAYas STA and sign for NlA CONCURRENCE.

Page 15 of 25

TQ-AA-106-0303 JPM: ZZ029 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Equipment Control TASK: Complete An Action Statement Log Sheet

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U 5.3.4.2. OBTAIN SM/CRS AUTHORIZATION E for entry into the TECH SPECS/LAOT Action Statement. The SM/CRS should review plant conditions, TIS, existing active and tracking action statements, and the TIS Action Operator obtains SM/CRS Statement Log to ensure the AUTHORIZATION.

equipment can be, or is properly removed from service (for unplanned entry into a TS LCO/LAOT Action Statement) and that redundant equipment is operable. [CD-079A]

CUE ROLE PLAYas SM and sign for Examiner Note: Once the Action AUTHORIZATION. Statement entry is Authorized, the JPM is complete.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message N/A from the operator on the status of the JPM, and then state This JPM is complete".

STOP TIME:

Page 16 of 25

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

~------------------

DATE:

JPM Number: ZZ029 TASK: Complete An Action Statement Log Sheet TASK NUMBER: 4010590202/2990640305 QUESTION:

RESPONSE

~~---"'"' ---------------------------

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 17 of 25

OP-HC-1()6-115~1001 Revision 3 ATTACHMENT 3-1 TECHNICAL SPECIFICATION ACTION STATEMENT LOG INDEX (Page 1 of 1)

,-Lco TECH ACTIVEJ

SUMMARY

PLANNED ENTRY EXPIRATION DATE/TIMEJ EXIT YIN

~NDEX SPEC TRACKING DESCRIPTION DATE! CONDITION DATE!

NUMBER NUMBER -------

TIME TIME SI~.001 INITIAL

' GS-PSV-5032 Failed INITIAL CONDITION DATEITIME 3.6.4.2 ACTIVE to stroke N CONDITION

+72 hours DATEITIME B0J~'

r-D

);@lillJl~

-~~~~~~

==i

.~ ~. ~ ~ ~~~-~~~~

C

~-~~~~

, ~~~-~~~-

~ ~ ~~ L~~~ ~. ~ ~ ~~~_~~~ ~ ---------

Page 18 of 25

OP-HC-1 08-115-1 001 1

TECHNICAL SPECIFICATION ACTION STATEMENT LOG (Page 1 of 4) 1.0 ACTION STATEMENT LOG SHEET LCO INDEX NUMBER: SIM-001 LeO STATUS (ACTIVE/TRACKING): ACTIVE

INIT CONDITION TECH SPEC NUMBER: 3.6.4.2 DATE/TIME ENTERED:

DArE/TIME APPLICABILITY: 1,2,3 DATEITIME ACTION REQUIRED: INIT CONDITION DATE/TIME + 72hr OTHER APPLICABLE T/S:

EQUIPMENT:

SUMMARY

DESCRIPTION (Include Summary of Actions Required)

GS-PSV-5032 failed to stroke open when tested:

3.6.4.2 Each reactor building - suppression chamber vacuum breaker assembly shall be OPERABLE APPLICABILITY: OPERATIONAL CONDITIONS 1,2 and 3.

ACTION:

a. With one reactor building - suppression chamber vacuum breaker assembly, with one or two valves inoperable for opening, restore the vacuum breaker assembly to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within thefollowin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

RESPONSIBLE DEPARTMENT NOTIFICATION(S)

SPECIAL REPORT REQUIRED YES NO 0 REPORT INITIATION DUE DATE N/A NOTIFICATIONS FOR COMPENSATORY ACTIONS OR SURVEILLANCES

NAME of DEPARTMENT NOTIFICATION NAME of PERSON NOTIF#

and PERSON NOTIFIED (DATE/TIME) MAKING NOTIFICATION (If applicable)

ENTRY I EXIT

" lE entry into an Action Statement or failure to meet an Action Statement tim on requires the submittal of a special report to the NRC, THEN:

ENSURE the responsible department is notified of thH reporting requirements, AND, NOTIFY the SOS or other Operations Management within one hour, AND, ENSURE the licensing Department is notified of the reporting requirements, AND, INITIATE a Notification lAW LS-AA-120, Notification Process.

REDLINDANT EQUIPMENT OPERABLE (YIN) : Y i

APPROVAL TO REMOVE FROM SERVICE, VERIFICATION OF REDUNDANT EQUIPMENT CONCURRENCE AUTHORIZATION Examiner STA Name Examiner SM Name SRO/ST A (print name) SM/CRS (print name)

&~ S7,4 S~t#Ite 'Z'ale/7ime &~ sm S'9H4t#1te SRO/STA (signature) DATE/TIME SM/CRS (signature) DATEITIME Page 19 of 25

OP-HC-108-115-1001 1

TECHNICAL SPECIFICATION ACTION STATEMENT LOG (Page 2 of 4) 2.0 ORDER AND WCD ADDENDUM I DR! NOTF I I DESCRIPTION SYSTEM TASKI RESP. STATUS

ORDER TYPE DEPT!

WCD i GROUP NUMBER i

~ 0 t:::\

S):~uovoTI~O[gJ L1C2rm1m (Continue on Page 3)

RETURN TO SERVICE (SM/CRS INITIAL OR N/A ALL BOXES)

TAGS RELEASED, SYSTEM/EQUIPMENT FILLED & VENTED, RESTORED FOR OPERATION :

SURVEILLANCE RETESTS & SPECIAL TEST/ACTIONS COMPLETE RESPONSIBLE DEPARTMENTS .. INFORMED DCP TURNOVER CHECKLIST COMPLETED .

ACTION STATEMENT LOG INDEX UPDATED :

VERIFICATION OF OPERABILITY REQUIREMENTS AND SYSTEM RESTORATION CONCURRENCE AUTHORIZATION I

SRO/STA (print name) SM/CRS (print name)

SRO/STA (signature) DATEITIME SM/CRS (signature) DATEITIME Page 20 of 25

OP-HC-108-115-1001 TECHNICAL SPECIFICATION ACTION STATEMENT lOG (Page 3 of 4) 2.0 ORDER AND WCD ADDENDUM (Continued)

INDEX NUMBER Page Number _ of _

DRI NOTF I DESCRIPTION SYSTEM TASK! I RESP. STATUS!

I ORDER TYPE i DEPTI WCD i GROUP NUMBER

--;::J 0 t;;:\ i S)~~~OO~~O[~ J lCZOf~

i I

i i

i Page 21 of 25

OP-HC-108-115-1001 1

TECHNICAL SPECIFICATION ACTION STATEMENT LOG SHEET (Page 4 of 4)

3.0 DESCRIPTION

ADDENDUM INDEX NUMBER _~_ _ Page Number_ of __

~Jfl}

A... .JlJL~ ~

Page 22 of 25

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant was at 100% power performing the monthly HC.OP-ST.GS-0003 Reactor Building/Suppression Chamber Vacuum Breaker Operability Test - Monthly.

2. The GS-PSV-5032 failed to stroke open when tested.

3. Local observation confirms the valve is failing to stroke due to a problem with the test actuator and the valve fully closed.

4. All other valves passed the surveillance.

5. The failure occurred one hour ago at . (ENTER Current Time minus one hour)

6. SAP is currently unavailable, and no NOTF has been written.

7. SAP LCO Tracking is NOT available.

INITIATING CUE:

Complete a manual Action Statement log entry for the failure of GS-PSV-5032.

Determination of retests is NOT required at this time.

Page 23 of 25

TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ029 Rev# i Date Description 01 12/6/08 Converted JPM 22029 to new JPM format Since Critical..JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial, validation not required.

Removed references to checking off/initialing steps in procedure. This is a generic work practice and adds unnecessary clutter to thl3 Standard section. This change is editorial, validation not required.

Incorporation of significant governing procedure change requires validation.

02 6/1/10 Updates all reference procedure revisions. Validated with 2 Y SROs. Avg validation time was 9 minutes.

i

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping TASK NUMBER: 2990740302 JPM NUMBER: 305H-JPM.ZZ032 REV #: 02

- - NRC ADMIN JPM SRO A4***

SAP BET: NOH05JPZZ32E ALTERNATE PATH: 0 APPLICABILITY:

EOD RO D STA D SRO 00 DEVELOPED BY: Archie E. Faulkner DATE: 6/30/10 REVIEWED BY: a, ~ructor Operations Representative DATE: r.e(dZ//1IJ APPROVED BY: cwr9v---

Training Department DATE: 7/t/tD

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: ZZ032 REV: 02 SYSTEM: Radiation Control TASK NUMBER: 2990740302 TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping ALTERNATE PATH: 00 KIA NUMBER: _ _ _2_.3_.1_1_ __

IMPORTANCE FACTOR: 3.8 4.3 APPLICABILITY: RO SRO EOD ROO STAD SROCK]

EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

HC.OP-GP.ZZ-0004 Rev 7 TOOLS, EQUIPMENT AND PROCEDURES:

Prepared copy of HC.OP-GP.ZZ-0004 (Attached); Tech Specs ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPIVI PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 24

TQ-AA-106*0303 NAME: _____________________

DATE:

SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping TASK NUIVIBER: 2990740302 INITIAL CONDITIONS:

1. The plant is Operational Condition 2 with a startup in progress following a Refuel Outage.

2. Pressure has been raised to 905 psig, and preparations are being made to transition to Operational Condition 1.

3. Leakage into the Core Spray Loop A Injection Header resulted in loop pressurization above normal ECCS Jockey Pump discharge pressure observed at 1BEPISH*N654A (Panel 1OC617) AND 1BEPI*R600A (Panel 1OC650).

4. HC.OP-GP.ZZ-0004 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERMINATION was pertormed to determine the leakage rate.

INITIATING CUE:

PERFORM the CRS review of the completed HC.OP-GP.ZZ-0004 AND COMPLETE ATTACHMENT 1 Section 2 POST TEST INFORMATION.

Page 3 of 24

TQ-AA-106-0303 JPM: ZZ032 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: ______~----------

SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U eva CUE PROVIDE the operator the initiating cue AND the attached prepared copy Operator repeats back initiating cue.

of HC.OP-GP.ZZ-0004.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I NVA START TIME:

ATT.1 POST TEST INFORMATION NfA 2.1 The data acquired during the performance of this test has been reviewed for completeness and Operator reviews completed com pliance with Technical HC.OP-GP.ZZ-0004.

Specification 3.4.3.2, Reactor Coolant System Operational Leakage and the test is considered:

Page 4 of 24

TQ-AA-106-0303 JPM: ZZ032 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.11 CALCULATE the leak rate through 1BE-VOO? (HV-F005A) Operator recognizes a math error was by dividing the volume recorded in made when calculating Leak Rate in Step 5.1.9 by the step 5.1.11.

elapsed time recorded in Step 5.1.10. Actual leak rate is 6.3 gpm, NOT 0.63 RECORD leak rate in gpm on gpm (6.25 gpm rounded up).

Attachment 2.

Operator ensures 5.1.11 ACTUAL block

is corrected to 6.25 OR 6.3 gpm.

Examiner Note: Operator may correct data or call Performer to correct data.

CUE IF directed as Performer to correct data entered, THEN ROLE PLAYas Performer and N/A CORRECT ACTUAL block as directed

88 by Operator.

Page 5 of 24

TQ-AA-106-0303 JPM: ZZ032 OPERATOR TRAINING PROGRAM NAME: -----------------

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD stu evaluation) 5.1.11 CALCULATE the leak rate through 1BE-V007 (HV-FOO5A) by dividing the volume recorded in Operator recognizes 5.1.11 ACTUAL Step 5.1.9 by the Leak Rate exceeds REQUIRED Leak elapsed time recorded in Step 5.1.10. Rate of ~ 5 GPM.

RECORD leak rate in gpm on Attachment 2.

Operator ensures 5.1.11 SAT/UNSAT

block is corrected to UNSAT.

Examiner Note: Operator may correct data or call Performer to correct data.

CUE IF directed as Performer to correct data entered, THEN ROLE PLAYas Performer and N/A CORRECT SAT/UNSAT block as directed by Operator. ~

Page 6 of 24

TQ-AA-106-0303 JPM: ZZ032 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD stu evaluation)

TIS Reactor coolant system leakage shall

be limited to:

3.4.3.2 Operator determines TIS 3.4.3.2 Action

d. 0.5 gpm leakage per nominal inch c applies:

of valve size up to a maximum of 5 gpm from any reactor coolant With any reactor coolant system system pressure isolation valve pressure isolation valve leakage greater .

specified in Table 3.4:3.2-1, at than the above limit, isolate the high rated pressure. pressure portion of the affected system APPLICABILITY: OPCON 1,2,3 from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed ACTION:

manual or deactivated automatic or

c. With any reactor coolant system check* valves, or be in at least HOT pressure isolation valve leakage SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months greater than the above limit, isolate and in COLD SHUTDOWN within the the high pressure portion of the affected system from the low following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by Examiner Note: Determining the use of at least one closed manual SPECIFIC compensatory action is or deactivated automatic or check*

valves, or be in at least HOT beyond the scope of the JPM. It is only SHUTDOWN within the next 12 necessary for the Operator to hours and in COLD SHUTDOWN IDENTIFY the applicable Tech Spec within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Action.

Page 7 of 24

TQ-AA-106-0303 JPM: ZZ032 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U eva I

~w~w~J------------~----~

CUE AFTER the Operator determines the applicable Tech Spec Action statement, N/A THEN INFORM the Operator compensatory actions have been implemented.

ATT.1 POST TEST INFORMATION N/A 2.1.2 UNSATISFACTORY AND Operator signs UNSATISFACTORY JF necessary the T.S. ACTION block 2.1.2 of Attachment 1.

statement has been implemented.

CUE IF the Operator goes beyond the Leak Rate Determination Tech Specs, N/A THEN CUE the Operator to stay with the Leak Rate Determination.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 24

TQ*AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: ZZ032 TASK: Perform Leak Rate Measurement Data Sheet for Water Or Steam Filled Piping TASK NUMBER: 2990740302 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

---~-~.--- ....**------------------------------------------------------

RESPONSE

RESULT: SAT UNSAT Page 9 of 24

, TQ*AA*106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ032 Rev # Date Description Validation i Required? i 1 11/9/08 Converted ZZ032 to new JPM format. Since Critical JPM Y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

Changed JPM to have CRS review completed GP.ZZ-0004 instead of completing the final step. This has greater Operational Validity for the SRO position.

Added Examiner Cue: "IF the Operator goes beyond the Leak Rate Determination Tech Specs, CUE the Operator to stay with the Leak Rate Determination." per Chief Examiner request.

2 6/1/10 Updated Reference procedure revision numbers. Updated "Cal N Due" Date to reflect exam date. Validated with 2 SROs. Avg validation time was 7 minutes. Validation comment; revise Initiation Cue to be more specific on what needs to be performed. Revised cue to read: "PERFORM the CRS review of the completed HC.OP-GP.ZZ-0004 AND COMPLETE ATTACHMENT 1 Section 2 POST TEST INFORMATION."

i I i

TQ*AA*106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is Operational Condition 2 with a startup in progress following a Refuel Outage.

2. Pressure has been raised to 905 psig, and preparations are being made to transition to Operational Condition 1.

3. Leakage into the Core Spray Loop A Injection Header resulted in loop pressurization above normal EGGS Jockey Pump discharge pressure observed at 1BEPISH-N654A (Panel 1OC617)

AND 1BEPI-R600A (Panel 10C650).

4. HC.OP-GP.ZZ-0004 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAKAGE DETERM INATION was perfonned to determine the leakage ~

INITIATING CUE:

PERFORM the CRS review of the completed HC.OP-GP.ZZ-0004 AND COMPLETE ATIACHIVIENT 1 Section 2 POST TEST INFORMATION.

Page 10 of 24

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505

- - NRC ADIVIIN JPIVI SRO A5***

JPM NUMBER: 305H-JPM.ECG004 REV #: 02 SAP BET: NOH05JPCL04E ALTERNATE PATH: D APPLICABILITY:

EoD RO STA [KJ SRO DEVELOPED BY: Archie E. Faulkner DATE: 6/30/10 Instructor REVIEWED BY: /flt/I!

Operations Representative DATE: lrJ L~/zoIQ APPROVED BY: 0U~

Training Department DATE: 7/1((6

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: ECG004 SYSTEM: Administrative Duties/Reporting Requirements TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition ALTERNATE PATH: I I KJA NUMBER:

2.4.38 IMPORTANCE FACTOR: 2.4 4.4 APPLICABILITY: RO SRO EO D RO D STA [ ] ] SRO [ ] ]

EVALUATION SETTING/METHOD: Simulator/Perform or In PlanUSimulate

REFERENCES:

Hope Creek Event Classification Guide, TOC Rev 90 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15/13 Minutes JPM PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: 1 Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 15

TQ-AA-106-0303 NAME: ______________________

DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition TASK NUMBER: 2000500302/2000020505 INITIAL CONDITIONS:

1. The plant is in OPERATIONAL CONDITION 4 and has been shutdown for 10 days.

2. 'B' RHR was in Shutdown Cooling at 10,000 gpm with an RCS temperature of 120 degF.

3. The torus access hatches have been removed for work on the Suppression Chamber to Drywell Vacuum Breakers.

Then, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1 g.

1. Control Room Annunciator C6-C4"SEISMIC MaN PNL C673" is in.

2. On Panel 10C673:

The SMA-3 Event Indictor is White.

The Strong Motion Accelerograph Tape Machines have advanced but are not currently running.

The AMBER alarm light on the Seismic Switch Power Supply Drawer is lit.

3. Numerous amber lights and 8 red lights are lit on the response spectrum analyzer.

4. A LOCA occurs. RPV level dropped to, then stabilizes between -150" and

-155", being maintained using all available ECCS.

5. Estimated restoration time for remaining ECCS is at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

6. FRVS Vent RMS failed. Alternate sampling methods are not yet in place.

7. The Rad Pro Shift Technician reports dose rates measured at the Security Center entrance are 150 mRem/hr.

8. The current 33 ft. elevation wind direction is from 291 0 at 4 mph.

INITIATING CUE:

Based on this information, classify thi~ event and make the initial notifications.

This is a Time Critical Task, and has two Time Critical elements.

Time zero for this event is now.

Page 3 of 15

TQNAA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event AndlOr Plant Condition TASK:

STEP ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

I I EVAL COMMENTS (Required for UNSAT NO.

STANDARD # S/U CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains Hope Creek Event Operator obtains the correct Classification Guide.

procedure.

ECG Classification: .To use this ECG Section volume, follow this sequence: Operator assesses the initial conditions, and determines that Sections 6.0 LlV.C 1. ASSESS the event and/or plant (Radiological Releases), Sections 8.0 conditions and DETERMINE (System Malfunctions) and 9.0 which ECG section(s) is most (Hazards - Internal/External) are appropriate. appropriate ECG sections.

2. REFER to Section EALIRAL Operator reviews the EALs and Flowchart diagram( s), and identify determines that the Initiating Conditions the Initiating Conditions that are for EALs 6.1.3, 8.1.2, 8.1.3.a, and 9.5.2 related to the evenUcondition that are related to the event that has occurred Operator refers to the has occurred or is ongoing.

Conditions for EAL are related to the event that has occurred.

Page 4 of 15

TQ-AA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step) EVAL ELEMENT (Required for UNSAT NO. #

STANDARD SIU evaluation)

Table In the table, review the Emergency Operator reviews the EALs of all 3.0 Action Levels of all columns and columns, and determines the Barrier identify which need further review. Table is not applicable in OC 4.

ECG 3. REVIEW the associated EALs as Section compared to the event and LIV.C SELECT the highest appropriate I

(cont.) emergency or reportable action level. If identification of an EAL is questionable, refer to paragraph IV.Aabove.

Operator reviews the EALs in section If there is any doubt with regard to 6.1, and determines that EAL #6.1.3.b assessment of a particular EAL, is the highest emergency action level the ECG Technical Basis met or exceeded (Site Area Document should be reviewed. Emergency).

Words contained in an EAL that are bold face are either threshold values associated with that action level or are words that are defined in the basis for that specific EAL.

Page 5 of 15

TQ-AA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

II Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition EVAL COMMENTS (Required for UNSAT STANDARD # S/U ECG 4. If an EAL has been entered, then Section equal level EALs or lower level i.lV.C EALs and RALs are not required (cont.) to be reported as long as the Examiner Note: Filling out the NRC applicable information is Data Sheet is beyond the scope of this JPM.

communicated to the NRC using Attachment 5, NRC Data Sheet.

ECG 5. The STA is responsible to Section perrormanindependent LlV.C verification of the EAL (cont.) classification. The STA verification does not alleviate the requirement of the SM to make a timely classification. Should the N/A SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO.

CUE IF the Operator requests the STAfIA to independently verify the EAL Classification, THEN INFORM the Operator the N/A 5TAliA is not available.

Page 6 of 15

TQ-AA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

6. IDENTIFY and IMPLEMENT the Section referenced Attachment under LlV.C Action Required. Operator identifies and implements ECG Attachment 3.

(cont.)

ECG I. EMERGENCY COORDINATOR Operator declares a Site Area

Att.3 {Ee} LOG SHEET Emergency, places the EAL # s 6.1.3.b, A. DECLARE A SITE AREA time and date in the appropriate spots EMERGENCY AT HOPE in attachment 3, and initials the step as CREEK the EG.

EAL #(s) , , Examiners Note: ENTER the declaration time that the operator DECLARED AT hrs on entered on AU. 3. The difference time date between the START TIME and the "DECLARED AT" TIME is the first critical time (15 min.) Initialing the step is not critical.

ECG B. NOTIFICATIONS Operator calls the communicator using Att.3 the plant page.

1. CALL the communicators to the Control Room Examiner Note: this JPM is being performed in a classroom, THEN this step will not be performed.

Page 7 of 15

TQ-AA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME:

~----------

JOB PERFORMANCE MEASURE DATE: ________~________

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step) EVAL ELEMENT (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE After 2 minutes, report as the Examiner Note: IF this JPM is being communicators and give your performed in a classroom, THEN this name as CM1 and CM2. step will not be performed.

ECG 2. ACTIVATE "ERO Emergency Operator activates the ERO per posted Att.3 Callout" per posted instructions instructions titled Training Use titled: "Emergency Callout Emergency Callout Activation.

Activation" (EP96-003) Examiner Note: ENSURE the operator is using the Simulator Training Activation instructions.

Examiner Note: IF this JPM is being performed in a classroom, THEN this step will not be performed.

Page 8 of 15

TQ-AA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu evaluation)

ECG 3. COMPLETE the INITIAL Operator Completes the ICMF.

Att.3 CONTACT MESSAGE FORM (ICMF) (last page of this Examiners Note: See the attached attachment).

ICMF for an example of what the form should look like when filled out properly.

Note that the exact words do not have to be in the "DESCRIPTION OF EVENT', but the description must convey the sense of the Initiating Condition. For EAL 6.1.3.b the recommended wording from "HOPE CREEK EMERGENCY CLASSIFICATION DISCRIPTION TABLE" is "Radioactive Gas Release Exceeds 10% of the Protective Action Guide Limit". The operator may place the Examiners name as the Communicator or tell the Examiner to place his/her name as the Communicator.

4. PROVIDE the ICMF to the

Primary Communicator (CM1) Operator provides the ICMF to CM1 and DIRECT the Communicator and directs implementation of Att.6.

to implement ECG Attachment 6.

Page 9 of 15

TQ-AA-106-0303 ECG004 OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a sequ.ential Step)

I TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event And/Or Plant Condition EVAL COMMENTS (Required for UNSAT STANDARD # stu evaluation CUE LOG the time the ICMF is provided to CM1.

Examiners Note: The difference LOG TIME: _ _ _ __ between the "DECLARED AT' TIME Role-playas CM1 and repeat back and this LOG TIME is the second the direction as given. critical time (13 min.)

ECG 5. DIRECT the Secondary Operator directs CM2 to implement Att 4 Communicator (CM2) to Att.8 for a SITE AREA EMERGENCY.

implement ECG Attachment 8 for a SITE AREA Examiner Note: IF this JPM is being EMERGENCY. performed in a classroom, THEN this step will not be performed.

CUE ROLE-PLAYas CM2 and REPEAT N/A BACK the direction as given.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 10 of 15

TQ*AA*106*0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUIVIENTATION NAME:

DATE:

JPM Number: ECG004 TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition TASK NUMBER: 2000500302/2000020505 QUESTION:

RESPONSE

RESULT: SAT UNSAT !

QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 11 of 15

TQ-AA-106*0303 JOB PERFORMANCE MEASURE ATT3 Pg. 2of2 INITIAL CONTACT MESSAGE FORM I. THIS IS (Not Required) , COMMUNICATOR IN THE rgJ CONTROL ROOM

~--~-----

(NAME) (Check not required) TSC EOF AT THE HOPE CREEK NUCLEAR GENERATING STATION.

II. [g] THIS IS NOTIFICATION OF A SITE AREA EMERGENCY \VHICH WAS DECLARED AT Time -24 Hour ON , Today's Date

~--~~~==~~==~-- --~~==-----

(Time - 24 HOUR CLOCK)

EAL # 6.1.3.a. DESCRIPTION OF EVENT:

Radioactive Gas Release Exceeds 10% of the Protective Action Limit

.. . . . ------------------------------------------------.. -.. . .--.. -----l~F*,

In NO RADIOLOGICAL RELEASE IS IN PRO .

rgJ THERE IS A RADIOLO'-'iL"cU.J IV.

291 WIND SPEED: 4 S)

v. IZl NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME Initials EC Initials royal to Transmit IeM NOTE:

Radiological Release is defined as: Plant Effluent> Federal Limit of 1.20E+04 !Jei/sec Noble Gas or 1.70E+Ol ~lCi/sec 1-131.

Page 120f 15

TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ECG004 Rev # Date Description Validation I Required?

02 6/1/10 Updated Reference procedure revision number. No change in Y operator actions. This change is editorial.

Converted JPM ECG004 to new ,JPM format. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted. This change is editorial.

Removed references to checking off/initialing steps in procedure. This is a generic work practice and adds unnecessary clutter to the Standard section. This change is editorial.

Updated Initial Conditions due to changes in the ECG to make the resulting classification specific to 6.1.3.b for a Site Area Emergency. Validated with 2 SROs. Average validation time is 13 minutes. One SRO commented that there should be a release rate given. Based on the information in the I.C sheet, there is sufficient information available to determine that a release rate above Tech Spec limits is in progress.

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1, The plant is in OPERATIONAL CONDITION 4 and has been shutdown for 10 days, 2, 'B' RHR was in Shutdown Cooling at 10,000 gpm with an RCS temperature of 120 degF.

3. The torus access hatches have been removed for work on the Suppression Chamber to Drywell Vacuum Breakers.

Then, Hope Creek experiences an earthquake which indicates a magnitude of > 0.1 g.

1. Control Room Annunciator C6~C4"SEISMIC MON PNL C673" is in.

2. On Pane110C673:

The SMA~3 Event Indictor is White .

The Strong Motion Accelerograph Tape Macrlines have advanced but are not currently running.

The AMBER alarm light on the Seismic Switch Power Supply Drawer is lit.

3. Numerous amber lights and 8 red lights are lit on the response spectrum analyzer.

4. A LOCA occurs. RPV level dropped to, then stabilizes between -150" and

-155", being maintained using all available ECCS.

5. Estimated restoration time for remaining ECCS is at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

6. FRVS Vent RMS failed. Alternate sampling methods are not yet in place.

7. The Rad Pro Shift Technician reports dose rates measured at the Security Center entrance are 150 mRem/hr.

8. The current 33 ft. elevation wind direction is from 291 0 at 4 mph.

INITIATING CUE:

Based on this information, classify this event and make the initial notifications.

This is a Time Critical Task, and has two Time Critical elements.

Time zero for this event is now.

Page 13 of 15

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump TASK NUMBER: 2590020101

,..IPM NUMBER: 30SH-JPM.AE009 REV#: 01 SAP BET: NOH05JPAE09E ALTERNATE PATH: D APPLICABILITY:

EO RO []J STA SRO DEVELOPED BY: Archie E. Faulkner DATE: 8/2/10 I"f'i/'

REVIEWED BY:

~.Operatlo s Representative APPROVED BY: DATE: 0/'1//6 Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUIVIBER: AE009 REV: 01 SYSTEM: Feedwater TASK NUMBER: 2590020101 TASK: Start a Secondary Condensate Pump ALTERNATE PATH: 0 KIA NUMBER: _ _ 25_6_00_0,_A_4_.0_1_ _

IMPORTANCE FACTOR: 3.3 3.3 APPLICABILITY: RO SRO EO D RO [ ] ] STA D SRO [ ] ]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP~SO.AE~0001 Rev 63 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 11 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 17

TQ*AA*106*0303 NAME:

DATE:

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump TASK NUMBER: 2590020101 INITIAL CONDITIONS:

1. A plant startup is in progress lAW HC.OP-IO.ZZ-0003.

2. Reactor pressure is 500 psig.

3. "A" and "8" Primary Condensate Pumps are in service.

4. "A" Secondary Condensate Pump is in service.

5. "B" RFPT is in service.

6. The Start-Up Level Control Valve is in AUTO.

7. The Turbine Building Operator has been briefed and is standing by an location.

INITIATING CUE:

Start the second Secondary Condensate Pump BP102 lAW HC.OP-SO.AE-0001(Q).

Page 3 of 17

TQ-AA-106-0303 JPM: *AE009 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME '-'-'--'-='-'

Operator repeats back the Initiating C~: I N~

START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-SO.AE-0001.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, N/A THEN INFORM operator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.11.

~Wv~

1.11 WHEN required by HC.OP-IO.ZZ 0003(Q), Startup from Cold Shutdown to Rated Power START the first Secondary Condensate Pump A(8,C)P137, as follows:

Page 4 of17

TQ-AA-106-0303 JPM: AE009 OPERATOR TRAINING PROGRAM NAME:

Rev: JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation 5.1.11. ENSURE at least two Primary Operator observes the A and B Primary A Condensate Pumps are running. Condensate Pumps are running.

5.1.11. ENSURE HV-1651A(B,C), SEC Operator observes the HV-1651 B, SEC B CNDS PUMP A(B,C) DISCH VLV, for CNDS PUMP B DISCH VL V CLOSE the DumD to be run is closed. light is illuminated and OPEN light is extinguished.

5.1.11. ENSURE valve FV-1650A(B,C), MIN C FLOW VALVE FLOW CONTROL Operator contacts Turbine Building (FIC-1650A(B,C)), is in AUTO with a Equipment Operator (TBEO) to check setpoint of 4800 gpm. (Local Panel FIC-1650B is in AUTO with a setpoint A(B,C)C102). of 4800 gpm on local panel1B-C-102.

INFORM operator that FIC-1650B is CUE in AUTO with a setpoint of 4800 N/A gpm on local panel 1B-C-1 02.

NOTE DO NOT place Secondary Condensate Pump Auxiliary Lube Oil Operator reads NOTE Pump in-service until just prior to starting the associated Secondary Condensate Pump.

Page 5 of 17

TQ-AA-106-0303 JPM: AE009 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO. #

STANDARD eva I 5.1.11. START lube oil system for Secondary D Condensate Pump A(B,C) as follows:

Operator contacts the TBEO to 5.1.11. OBSERVE L1-1671A(B,C), Secondary OBSERVE L1-1671 B, Secondary D.1 Condensate Pump Lube Oil Reservoir Condensate Pump Lube Oil Reservoir Level, indicates a normal level Level, indicates a normal level between between LOW and HIGH marks LOW and HIGH marks locally on the (local).

pump skid.

INFORM operator that LI-1671B, CUE Secondary Condensate Pump Lube Oil Reservoir Level, indicates a N/A normal level between LOW and HIGH marks.

5.1.11. PRESS SEC CNDS PUMP A(B,C) Operator presses the SEC CNDS

Y N Flagging D.2 AUX LUBE OIL PMP START PUMP B AUX LUBE OIL PMP START Y N STAR pushbutton. Y N Peer Check pushbutton.

Operator observes the START light is illuminated and STOP light is extinguished.

Page 6 of 17

TQ-AA-106-0303 JPM: AE009 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U 5.1.11. OBSERVE PI-1669A(B,C), AUX Operator contacts the TBEO to 0.3 LUBE Condensate Pump A(B,C) OBSERVE PI-1669B, AUX LUBE Pressure, indicates approximately 7 Condensate Pump B Oil Pressure, to 9 psig (local). . indicates approximately 7 to 9 psig locally on the pump skid.

INFORM operator that PI-1669B, CUE AUX LUBE Condensate Pump BOil Pressure, indicates approximately N/A 7 to 9 psig.

5.1.11. OBSERVE CNDS PUMP A(B,C) Operator observes the START E START ENABLEis illuminated. ENABLE is illuminated.

CAUTION When starting a SCP, the time between starting the pump and opening the discharge valve should be minimized. Operation with the min Operator reads CAUTION flow valve open diverts flow and may lower feed pressure to the RPV, challenging RPV level. RPV level and start-up level control valve operation should be monitored closely.

Page 7 of 17

TQ-AA-106-0303 JPM: AEOQ9 OPERATOR TRAINING PROGRAM NAME:

~-----------

Rev: 01 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step) "/( COMMENTS STEP NO.

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation) 5.1.11. START SEC CNDS Pump A(B,C) Operator presses the SEC CNDS

Y N Flagging F AND PERFORM the following: PUMP B START pushbutton. Y N STAR Y N Peer Check c---

Operator observes the START light is illuminated and STOP light is extinguished.

5.1.11. OBSERVE FV-1650A(B,C), SEC Operator observes FV-1650B, F.1 CNDS PUMP A(B,C) MIN FLOWVLV CNDS PUMP B MIN FLOW VLV OPEN, is illuminated. OPEN, is illuminated.

5.1.11. OBSERVE AI-6317A(B,C), SEC Operator observes the AI-6317B, SEC F.2 CNDS PUMP A(B,C) MOT AMPS, CNDS PUMP B MOT AMPS, indicates indicates < 279 amps << 481 amps for < 279 amps.

CP137).

5.1.11. PRESS SEC CNDS Pump A(B,C) Operator presses the SEC CNDS G AUX LUBE OIL PMP STOP PUMP B AUX LUBE OIL PMP STOP pushbutton. pushbutton.

Operator observes the STOP light is illuminated and START light is extinguished.

Page 8 of 17

TQ-AA-1 06~0303 JPM: AE009 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

{*Denotes a Critical Step} COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # SfU evaluation) 5.1.11. PRESS SEC CNDS Pump A(B,C) Operator presses the SEC eNDS

Y N Flagging H AUX LUBE OIL PMP AUTO Pump B AUX LUBE OIL PMP AUTO Y N STAR pushbutton. pushbutton. Y N Peer Check

-~

Operator observes the AUTO light is illuminated and MAN light is extinguished.

NOTE AD-HV-1710 PRI eNDS FLOW PATH MIN FLOW RECIRC valve will not Operator reads NOTE.

have an auto open signal present once two Secondary Condensate Pumps are in service.

CAUTION Flow through Condensate Demineralizer should be Operator reads CAUTION.

maintained between 3000 - 6000 gpm during normal operation.

~~~~~~--~~

Page 9 of 17

TQ-AA-106-0303 JPM: AE009 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step) ., COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.11. IF TWO Secondary Condensate

Y N Flagging Operator determines this step is Y N STAR I Pumps are now in service THEN applicable and presses the AO-HV PRESS AO-HV-1710 PRI CNOS Y N Peer Check 1710 PRI CNDS FLOW PATH FLOW. PATH MIN FLOW RECIRC FLOW RECIRC CLOSE PB.

CLOSE PB.

Operator observes the AO-HV-171 0 PRJ CNDS FLOW PATH MIN FLOW RECIRC OPEN and CLOSE lights are illuminated.

Operator observes the AO-HV-171 0 PRJ CNDS FLOW PATH MIN FLOW RECJRC OPEN light extinguishes.

CUE When asked about the Start-Up Level Control Valve, provide T erminatiing Cue. N/A Page 10 of 17

TQ-AA-106-0303 JPM: AE009 OPERATOR TRAINING PROGRAM NAME: _ _ __

Rev: 01 JOB PERFORMANCE MEASURE DATE: _ _ _ _ _ _ _ _ _..........

SYSTEM: Feedwater TASK: Start a Secondary Condensate Pump

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) {Required for UNSAT NO. #

STANDARD evaluati CUE WHEN operator infonns you the task is complete, the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete",

STOP TIME:

Page 11 of 17

TQ-AA*106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: AE009 TASK: Start a Secondary Condensate Pump TASK NUMBER: 2590020101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 12 of 17

TQ-AA*106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A plant startup is in progress lAW HC.OP-IO.ZZ-0003.

2. Reactor pressure is 500 psig.

3. "A" and uB" Primary Condensate Pumps are in service.

4. "A" Secondary Condensate Pump is in service.

5. "B" RFPT is in service.

6. The Start-Up Level Control Valve is in AUTO.

7. The Turbine Building Operator has been briefed and is standing by on locat:on.

INITIATING CUE:

Start the second Secondary Condensate Pump BP1 02 lAW HC.OP-SO.AE-0001 (0).

Page 13 of 17

TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to a startup I.C., 500 psig reactor pressure.

ENSURE A and B Primary Condensate Pumps are in service.

ENSURE A Secondary Condensate Pump is in service.

ENSURE a copy of HC.OP-SO.AE-0001 is available.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Page 14 of 17

TQ-AA-106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 15 of 17

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AE009 Rev# Date Description Validation I

I Required?

01 5/26/10 Converted JPM AE009 to new JPM format. Since Critical JPM Y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

Added additional information to turnover cue sheet. Revised FV 1650A(B,C) flow setpoint from 5500 gpm to 4800 gpm.

Vandation required. Validation comments: Added to cue sheet "7. The Turbine Building Operator has been briefed and is standing by on location." Validated avg time 11 minutes.

I I

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor/Turbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure TASK NUMBER: 4000570401 JPM NUMBER: 305H-JPM.CH002 REV#: 07 SAP BET: NOH05JPCH02E ALTERNATE PATH: [ ] ]

APPLICABILITY:

EO D RO 00 STA D SRO DEVELOPED BY: Archie E. Faulkner DATE: 5/21/10 Instructor REVIEWED BY: DATE: C

-"""'----=---

Operations Representative APPROVED BY: _~~~"",,--=-- _ _' DATE: :JjJ~

Training Department

TQ-AA-106*0303 STATION: Hope Creek JPM NUMBER: CH002 REV: 07 SYSTEM: Reactorrrurbine Pressure Regulating System TASK NUMBER: 4000570401 TASK: Respond to a Low Turbine Hydraulic Pressure ALTERNATE PATH: CD KIA NUMBER: _ _ 24_1_0_00_A_2_.0_6_ _

IMPORTANCE FACTOR: 3.1 3.2 APPLICABILITY: RO SRO EOD ROW STAD SROW EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP~SO.CH-0001 Rev. 42 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - N/A--

Minutes JPM PERFORMED BY: GRADE: o SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ*AA*106-0303 NAME:

DATE:

SYSTEM: Reactorrrurbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure TASK NUMBER: 4000570401 INITIAL CONDITIONS:

1. The plant is at 100% power, steady state.

2. The BP116 EHC pump is in MAN and running, the AP116 is in Standby.

3. The BP116 EHC is scheduled for maintenance.

INITIATING CUE:

You are the Plant Operator.

Swap In service EHC pumps to AP116 in service, and BP116 in Standby.

Leave BP116 in Standby (AUTO) for a confidence run on AP116 prior to CIT the BP116.

Page 3 of 14

TQ-AA-106-0303 CH002 OPERATOR PROGRAM NAME:

Rev: 07 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reacto(/Turbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD stu evaluati CUE PROVIOE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTERSTARTTIME~c..=.!....>

OPERATOR REPEATS BACK CUE: N/A START TIME:

Operator obtains and locates Operator obtains the correct procedure.

procedure HC.OP-SO.CH-0001.

Operator reviews precautions and Operator reviews precautions and limitations. limitations, and initials each precaution and limitation in the space provided in the procedure.

CUE If excessive time is taken to review N/A precautions and limitations, inform ooerator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step of procedure to be 5.12.

5.12.1 ENSURE all prerequisites of Section Operator reviews Prerequisites and 2.12 are satisfied. initials each Prerequisite in the space provided in the procedure.

Examiner Note: It is NOT critical to the procedure steps.

Page 4 of 14

TQ-r\A-106-0303 JPM: CH002 OPERATOR TRAINING PROGRAM NAME:

Rev: 07 ./OB PERFORMANCE MEASURE DATE:

SYSTEM: ReactorlTurbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure

(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step)

EVAL (Required for UNSAT NO. #

STANDARD S/U CUE If excessive time is taken reviewing I N/A prerequisites, inform operator that all are satisfied.

5.12.2 1 STATION an equipment operator at The operator contacts the equipment the EHC Skid to monitor pump operator.

rmance CUE Inform the operator that an NfA equipment operator is standing by to monitor pump performance.

5.12.3 PERFORM the following to alternate the EHC 10C651C):

5.1 PRESS HYDR FLUID PUMP Operator presses the HYDR FLUID I

A B(A)P116 MAN push-button PUMP AP116 MAN pushbutton.

AND OBSERVE AUTO lamp #

extinguish AND MAN lamp backlight illuminates.

Operator observes AUTO lamp extinguishes AND MAN lamp backlight

-h-illuminates.

5.12.3. PRESS HYDR FLUID PUMP . Operator presses the HYDR FLUID I

B B(A)P116 START push-button. PUMP AP116 START push-button I #

Page 5 of 14

TQ-i-lA-106-0303 JPM: CH002 OPERATOR TRAINING PROGRAM NAME:

Rev: 07 JOB PERFORMANCE MEASURE DATE:

SYSTEM: ReactorlTurbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure

(*Denotes a Critical Step) COMMENTS STEP

(#Denotes a Sequential Step)

ELEMENT EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator observes the START pushbutton illuminates and the STOP pushbutton extinguishes.

5.12.3. OBSERVE that B(A)P116, HYDR Operator observes the AP116, HYDR C FLUID PUMP, starts AND develops FLUID PUMP, starts AND develops flow, as indicated by AI-6427B(A), flow, as indicated by AI-6427B(A),

MOTOR AMPS, for both pumps MOTOR AMPS, for both pumps indicating approximately the same indicating approximately the same current. current.

f-----~~~~

5.12.3. VERIFY HYDR FLUID PUMP Operator verifies that BP116 MAN D A(B)P116 is in manual AND the push-button lamp backlight is AUTO lamp is extinguished AND illuminated.

MAN lamp backlight is illuminated.

~~~-

~ -----------

5.12.3. PRESS HYDR FLUID PUMP Operator presses the BP116 STOP

E A(B)P116 STOP push-button. push-button.

Operator observes the START lamp extinguish AND STOP lamp backlight illuminates.

Examiner Note: The operator may notice the reduction of system pressure at any time while performing the following.

----------- --'---~~~

Page 6 of 14

TQ-~A-1 06-0303 JPM: CH002 OPERATOR TRAINING PROGRAM NAME:

Rev: 07 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor/Turbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. . STANDARD # SlU evaluat 5.12.3. OBSERVE that A(B)P116, HYDR Operator observes that BP116, HYDR F FLUID PUMP, stops AND that FLUID PUMP, stops AND thatAP116, B(A)P116, HYDR FLUID PUMP, HYDR FLUID PUMP, does NOT maintains system pressure. (1550 maintain system pressure. (1550 1700 psig using CRIDS Point A3290 1700 psig using CRIDS point A3290 OR equivalent) OR equivalent).

5.12.3. the B(A)P116. HYDR FLUID Based on previous step, operator

G PUMP, fails to maintain system determines this step applies, pressure, IMMEDIATELY IMMEDIATELY starts BP116, HYDR #

START A(B)P116, HYDR FLUID FLUID PUMP by pressing HYDR PUMP. FLUID PUMP BP116 START pushbutton.

Examiner Note: Starting the BP116, HYDR FLUID PUMP will prevent low pressure and turbine trip/reactor scram. If the turbine trips, then consider this step UNSAT.

Operator observes that the pump starts AND develops flow, as indicated by AI 6427AlB, MOTOR AMPS, for both pumps indicating approximately the same current.

CUE If asked, direct the operator to start the BP116, "B" HYDR FLUID PUMP.

After the Operator starts the BP116 N/A OR the turbine trips, GIVE the termin~ting Cue.

Page 7 of 14

TQ-AA-1 06~0303 JPM: CH002 OPERATOR TRAINING PROGRAM NAME:

Rev: 07 JOB PERFORMANCE MEASURE DATE: _ _ ._____________

SYSTEM: ReactorJTurbine Pressure Regulating System TASK: Respond to a Low Turbine Hydraulic Pressure

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO. STANDARD # evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

~-----

DATE:

JPM Number: CH002 TASK: Respond to a Low Turbine Hydraulic Pressure TASK NUMBER: 4000570401 QUESTION:

RESPONSE

RESULT: SAT UNSAT I QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power, steady state.

2. The BP116 EHC pump is in MAN and running, the AP116 is in Standby.

3. The BP116 EHC is scheduled for maintenance.

INITIATING CUE:

You are the Plant Operator.

Swap In service EHC pumps to AP116 in service, and BP116 l

in Standby.

Leave BP116 in Standby (AUTO) for a confidence run on A p116 prior to CIT the BP116.

Page 10 of 14

TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

ENSURE the BP116 COMPLETE "Simulator Ready-for-Tralnlng/Examination Checklist",

EVENT ACTION: zdtuehtb II '8' EHC pump STOP pushbutton COMMAND:

PURPOSE:

EVENT ACTION: zdtuehsb II 'B' EHC pump START pushbutton 2 COMMAND: dmftc16 PURPOSE:

Page 11 of 14

TQ*AA*106~0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

! TC16 EHC Pump Discharge Filter clogging Page 12 of 14

TQ*AA*106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: CH002 I

I Rev# Date Description Validation I Required?

05 8/26/08 Update to new JPM format and revise performance y I

completion times.

I Update reference procedure revisions.

I 06 9/9109 I Update reference procedure revisions. No varidation N i I required.

I 07 4/20/10 i Update reference procedure revisions. Updated estimated Completion time based on pre-briefed 2009 LOR I performance. No validation required.

I I I

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: High Pressure Coolant Injection TASK: Place HPClln Full Flow Recirc TASK NUMBER: 2060180201 JPM NUMBER: 30SH-JPM.BJ006 REV#: 08 SAP BET: NOH05JPBJ06E ALTERNATE PATH: D APPLICABILITY:

EoD RO [ ] ] STA D SRO [ ] ]

DEVELOPED BY: Archie E. Faulkner DATE: 7/1/10 Instructor REVIEWED BY:

~~

Operations Representative DATE: '7/,l/d APPROVED BY:

~

Training Department DATE: ~/) /D

TQ-AA*106*0303 STATION: Hope Creek JPM NUMBER: BJ006 REV: 08 SYSTEM: High Pressure Coolant Injection TASK NUMBER: 2060180201 TASK: Place HPClln Full Flow Recirc ALTERNATE PATH: D KIA NUMBER: _ _ 20_6_0_00_A_4_.0_6_ _

IMPORTANCE FACTOR: 4.3 4.3 APPLICABILITY: RO SRO EO D RO [ ] ] STA D SRO [ ] ]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.ZZ-0001 Rev 21 TOOLS J EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - NJA Minutes JPM PERFORMED BY: GRADE: D SAT [J UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ*AA*106*0303 NAME:

DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPClln Full Flow Recire TASK NUMBER: 2060180201 INITIAL CONDITIONS:

1. The Reactor has scrammed due to a spurious Group 1 isolation.

2. All control rods are full in.

3. RCIC was manually initiated and is injecting to the RPV.

4. Reactor water level is approximately -15 inches and slowly rising.

5. Reactor pressure is being controlled with Lo-Lo Set.

6. RHR loop B is in suppression pool cooling.

7. Another operator is taking the HC.OP-OL.ZZ-0026, Attachment 3.m, Suppression Chamber Average Water Temp 5 Minute Log.

INITIATING CUE:

Place HPCI into the Full Flow Test Mode.

Page 3 of 14

TQ-MA-106-0303 JPM: BJ006 OPERATOR TRAINING PROGRAM NAME:

Rev: 08 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: High Pressure Coolant Injection TASK: Place HPClln Full Flow Recire

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

xxx CUE ENTER START TIME AFTER 90 ~ 28 Operator repeats back the Initiating Cue: N/A

~

START TIME:

9028 ~ ~

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.ZZ-0001 Attachment 6.

Operator d~termines beginning step Operator determines correct beginning of the procedure. step to be 1.0.

I

<XX) <XXX>: :

1.0 IF HPCI is NOT in the Injection mode

~ ~

of operation PERFORM the following: N/A

~

1.0.A ENSURE OP216 VAC TK VACUUM Operator presses the OP216 START STARYN PUMP is RUNNING. pb.

Operator observes the red RUNNING light illuminates.

Page 4 of 14

TQ-RA-106-0303 JPM: BJ006 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 08 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: High Pressure Coolant Injection TASK: Place HPClln Full Flow Recirc

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step)

ELEMENT EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.B ENSURE HV-F059 is OPEN. Operator presses the HV-F059 OPEN "" STARYN pb.

Operator observes the red OPEN light illuminates and green CLSO light extinguishes.

r~ --~

1.0.C ENSURE HPCI AND RCIC Suctions are Operator observes the HPCI HV-F004 lined up to the CST. OPEN light is illuminated and green CLSO light is extinguished.

Operator observes the RCIC HV-F010 OPEN light is illuminated and green CLSO light is extinguished.

1.0.0 PRESS HV-F008 INCR PB for:::; 20 Operator presses HV-F008 INCR pb for "" STARYN seconds. ~ approximately 20 seconds. #

t-~ -- -~~

Operator observes the HV-F008 OPEN I light illuminates.

I I I Page 5 of 14

TQ-A-A-106-0303 JPM: BJ006 OPERATOR TRAINING PROGRAM NAME:

Rev: JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coola'nt Injection TASK' Place HPClln Full Flow Recire

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD SJU evaluation) 1.0.E ADJUST FIC-R600 HPCI FLOW setpoint Operator presses the LOWER

STARYN to 1000 gpm. SETPOINT pb on the FIC-R600 #

controller until the pointer is on 1000 gpm.

1.0.F SIMULTANEOUSLYPERFORM the following: N/A I

1 1.0.F. START AUXILIARY OIL PUMP Operator presses the AUXILIARY OIL

1 PUMP OP213 START pb. #

Operator observes the red RUNNING light illuminates.

1.0.F. PRESS FD-HV-F001 OPEN Pushbutton Operator presses the HV-F001 OPEN

2 pb. #

Operator observes the red OPEN light illuminates and green CLSD light I elciinguishes.

I I I I Page 6 of 14

TQ-AA-106-0303 JPM: BJ006 OPERATOR TRAINING PROGRAM NAME:

Rev: 08 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK' Place HPClln Full Flow Recirc

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.G IMMEDIATELY OPEN AP-HV-F011. Operator presses the AP-HV-F011

OPEN pb. #

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

1.0.H WHEN Discharge Pressure turns Operator observes HPCI Pump STARYN ADJUST FIC-R600 setpoint to 3000 gpm. Discharge Pressure on PI-R601-E41 (red) ribbon indicator rises and lowers.

Operator (JI the RAISE

SETPOINT or LOWER SETPOINT pbs as necessary to obtain a flow setpoint of 3000 gpm.

L-Page 7 of 14

TQ-AA-106-0303 JPM: BJ006 OPERATOR TRAINING PROGRAM NAME:

Rev: 08 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaI 1.0.1 THROTTLE HV-F008 AND ADJUST Fle Operator presses the HV-F008 INCR or STARYN R600 setpoint as necessary, up to and DECR pbs and/or RAISE SETPOINT or including full flow rate, to control HPCI LOWER SETPOINT pbs as necessary pump parameters/reactor pressure. to adjust pump parameters.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 14

TQ*AA*106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: BJ006 TASK: Place HPClln Full Flow Recirc TASK NUMBER: 2060180201 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

~----------------

RESULT: SAT , - - I_ _- '

UNSAT Page 9 of 14

TQ*AA*106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Reactor has scrammed due to a spurious Group 1 isolation.

2. All control rods are full in.

3. RCIC was manually initiated and is injecting to the RPV.

4. Reactor water level is approximately -15 inches and slow[y rising.

5. Reactor pressure is being controlled with Lo-Lo Set.

6. RHR loop B is in suppression pool cooling.

7. Another operator is taking the HC.OP-DL.zZ-0026, Attachment 3.m, Suppression Chamber Average Water Temp 5 Minute Log.

INITIATING CUE:

Place HPCI into the Full Flow Test Mode.

Page 10 of 14

TQ*AA*106*0303 JOB PERFORMAI\lCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to 100% power, MOL.

Place "B" RHR in Suppression Pool Cooling, Lower Suppression Pool level to approximately 75.0" Reduce Recirc to minimum.

- - - Place Mode Switch to SID.

_ _ _ Stabilize RPV level at approximately -20 Inches with RFPs. Do NOT allow water Ivl to drop to Ivl 2.

--~

Arm and depress channels A and D NSSSS, then disarm. (Simulates spurious Group 1 isolation)

_ _ _ Manuady initiate RCIC, runback flow controller setpoint to maintain RPV level at approximately -15 inches, Freeze simulator.

ENSURE Mode Switch key is removed.

--~

COMPLETE "Simulator Ready-for-Training/Examination Checklist",

Page 11 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 12 of 14

TQ-AA*106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: BJ006

! Rev# I Date Description Validation

, Required?

08 7/1/10 JPM BJ006 updated to new JPM format. Y Converted JPM BJ006 to new JPM format. Since Critical JPM actions are now uniquely identified by the format. all statements identifying critical portion of action were redundant and deleted.

Added Initial Condition, "Reactor pressure is being controlled with La-La Set." Reduce SP level to 75 inches to provide more

time before suction swap. Validated with 2 licensed operators.

I I I Validation time 12 minutes.

I I I i I ,

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAIlsolation Conditions TASK NUMBER: 3780050501 "IPM NUMBER: 30SH-JPM.KL003 REV #: 01 SAP BET: NOH05JPKL03E ALTERNATE PATH: m APPLICABILITY:

EO LJ RO [ ] ] STA SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 7/213/10 Instructor REVIEWED BY: DATE:~~_ _

Operations Representative APPROVED BY: 01J02v Training Department

TQ*AA-106*0303 STATION: Hope Creek JPM NUMBER: KL003 REV: 01 SYSTEM: Primary Containment Instrument Gas TASK NUMBER: 3780050501 TASK: Operate The PCIG System During Post LOCA/lsolation Conditions ALTERNATE PATH: [K] KiA NUMBER: 223001 A4.11 IMPORTANCE FACTOR: 3.1 3.0 APPLICABILITY: RO SRO EO D RO []J STA D SRO []J EVALUATION SETTING/M ETHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.COMP-0002 Rev. 6 HC.OP-SO.KL-0001 Rev. 25 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: __N_/A _ _ Minutes JPIIII PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIIVIE: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 18

TQ*AA-106*0303 NAME:

DATE:

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAIlsolation Conditions TASK NUMBER: 3780050501 INITIAL CONDITIONS:

1. The plant is operating at 100 percent power.

2. An inadvertent Channel "An isolation signal has occurred.

INITIATING CUE:

Restore Primary Containment Instrument Gas lAW HC.OP-AB.COMP-0002 PRIMAHY CONTAII\IMENT INSTRUMENT GAS Subsequent Action D.

Page 3 of 18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE . DATE: ___________________

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAIlsolation Conditions

("'Denotes a Critical Step) ... COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu evalu CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains procedure Operator obtains the correct HC.OP-AB. CONT-0002.

procedure.

Operator reviews Retainment Override Conditions and Actions.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be Subsequent Operator Action D.

Page 4 of 18

TQ-.HA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

~

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAllsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) .

NOTE Both PCIG Compressors are placed 5 in STOP to prevent a SAFETY LOCKOUT due to low suction Operator reads NOTE.

pressure until the suction line up is restored.

0.1 PRESS A and B PCIG Compress9rs Operator presses A PCIG Compressor

Y N STAR STOP PB. STOP PB.

Operator observes the STOP light is illuminated and START light is extinguished.

Operator presses B PCIG Compressor

YN STAR STOP PB.

Operator observes the STOP light is illuminated and START light is extinguished.

'----~~ ---~"--- ~~

Page 5 of 18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

DATE: ________________

Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Primary Containment Instrument Gas TASK:

-- -- Operate The PCIG System During Post LOCA/lsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 0.2 ENSURE Isolations per Attachment 5 Operator turns to Attachment 5 of for A Channel. HC.OP-AB-COMP-0002.

-~ .... --

NOTE Valves isolate on 1.68 psig 1 ORYWELL PRESSURE, 1 X 10-3 uCi/cc REACTOR BUILDING EXHAUST RADIATION, Core Spray Operator reads NOTE.

Manual Initiation Pushbutton and

-129" Low Reactor Level unless otherwise noted.

Attach KL-HV5152A INSTRUMENT GAS Operator observEls the KL-HV5152A 5 SUPPLY HDR A INBD ISLN INSTRUMENT GAS SUPPLY HDR A INBD ISLN CLOSE light is illuminated and OPEN light is extinguished.

Attach KL-HV5148 INSTRUMENT GAS Operator observes the KL-HV5148 5 CPRSR SUCT INBD ISLN INSTRUMENT GAS CPRSR SUCT INBD ISLN CLOSE light is illuminated and OPEN light is extinguished.

f------

Attach KL-HVS172A CONT ATMOSPHERE Operator observes the KL-HV5172A 5 A INSTR GAS EMER SUP CONT ATMOSPHERE A INSTR GAS EMER SUP CLOSE light is illuminated and OPEN light is extinguished.

Page 6 of18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAllsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U eva I NOTE Opening of the Reactor Building Post 6 Accident Compressor Suction Valves in Step 0.3 or 0.5 may cause a rise Primary Containment Oxygen Operator reads NOTE.

concentrations. Monitor Orywell and Suppression Chamber Oxygen Concentration for compliance. [TS 3.6.6.2]

1-- ------------+-----------------100 0.3 PLACE B PCIG Compressor in service as follows:

O.3.A CLOSE HV-5162. Operator presses the HV-5162 CLOSE

Y N STAR PB.

Operator observes the HV-5162 CLOSE light is illuminated and OPEN light is extinguished.

Page 7 of 18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAI\solation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio 0.3.B OPEN HV-5160B using Key Lock Operator opens HV-5160B using Key

Y N STAR Switch. Lock Switch.

Operator observes the HV-5160B OPEN light is illuminated and CLOSE light is extinguished.

D.3.C ENSURE B PCIG Compressor Operator contacts Reactor Building SAFETY LOCKOUT is RESET. Equipment Operator and ensures B PCIG Compressor SAFETY LOCKOUT is RESET.

CUE IF contacted as Reactor Building Equipment Operator, THEN after approximately 1 minute, TRIGGER NfA ET-4 and REPORT that the Safety Circuit lockout is reset.

0.3.0 PRESS B PCIG Compressor AUTO Operator presses the B PCIG Y N STAR LEAD PB. Compressor AUTO LEAD PB.

Operator observes the B PCIG Compressor AUTO LEAD light is illuminated.

Page 8 of 18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAllsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluatio D.4 ENSURE the following valves are OPEN:

HV-5156A Operator obseNes the HV-5156A OPEN light is illuminated and CLOSE light is extinguished.

HV-5156B Operator obseNes the HV-5156B OPEN light is illuminated and CLOSE light is extinguished.

Operator recognizes trip of B PC1G by:

A1-A5 INST GAS PANEL NB C213 Operator reports trip of B PCIG to the CRS.

CUE "Take any required action" NtA Page 9 of 18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAIlsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD stu eval CUE IF contacted as Reactor Building Equipment Operator, THEN after approximately 1 minute, REPORT N/A that the B PCIG Compressor Safety Circuit Lockout is tripped and will not reset.

0.5 If B PCIG Compressor is not available, PLACE A PCIG Operator recognizes these steps are Compressor in service as follows: applicable.

D.5.A CLOSE HV-5147. Operator presses the HV-5147 CLOSE

Y N STAR PB.

Operator observes the HV-5147 CLOSE light is illuminated and OPEN light is extinguished.

0.5.8 OPEN HV-5160A using Key Lock Operator opens HV-5160A using Key

Y N STAR Switch. Lock Switch.

Operator observes the HV-5160A OPEN light is illuminated and CLOSE light is extinguished.

Page 10 of 18

TQ-AA-106-0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAllsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluatior D.5.C ENSURE A PCIG Compressor Operator ensures A PCIG Compressor SAFETY LOCKOUT is RESET. SAFETY LOCKOUT is RESET.

Operator contacts Reactor Building Equipment Operator and ensures A PC!G Compressor SAFETY LOCKOUT is RESET.

CUE IF contacted as Reactor Building Equipment Operator, THEN after approximately 1 minute, TRIGGER ET-6 and REPORT that the Safety N/A Circuit Lockout is reset.

0.5.0 PRESS A PCIG Compressor AUTO Operator presses the A PCIG

Y N STAR LEAD PB. Compressor AUTO LEAD PB.

Operator observes the A PCIG Compressor AUTO LEAD light is illuminated.

Page 11 of 18

TQ-AA-106*0303 JPM: KL003 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _______________

SYSTEM: Primary Containment Instrument Gas TASK: Operate The PCIG System During Post LOCAIlsolation Conditions

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluatio CUE WHEN operator informs you the task is complete, the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete",

STOP TIME:

Page 12 of 18

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

jPM Number: KL003 TASK: Operate The PC1G System During Post LOCAJlsolation Conditions TASK NUMBER: 3780050501 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 13 of 18

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is operating at 100 percent power.

2. An inadvertent Channel "A" isolation signal has occurred.

INITIATING CUE:

Restore Primary Containment Instrument Gas lAW HC.OP-AB.COMP-0002 PRIMARY CONTAINMENT INSTRUMENT GAS Subsequent Action D.

Page 14 of 18

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I INITIALIZE the simulatorto a 100 petcent power IC.

LOWER PCIG Gas pressure to -85 psig using IA03 Loss of drYvVell instrument gas.

INSERT PC03A in the tripped condition and allow valves to travel to required positions.

i ACKNOWLEDGE alarms and place simulator in FREEZE.

Description

. ENSURE a copy of HC.Op*AB.COMP-0002 is available.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

i EVENT ACTION: ZDIA60BO >= 1.0/1 HV5160 3 COMMAND:

PURPOSE: Simulates opening of HV-5160B EVENT ACTION: ZD >= 1.0 II B PCIG COMMAND:

PURPOSE:

Page 15 of 18

i t, TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

PC03A Drywell pressure transmitter N094A failure NONE 3 3 AN*A1A5 CRYWOLF ANN A1A5 -INST GAS ET-5 PANEL NB C213 i

I IA091nstrument gas compressor B reset lAOS Instrument gas compressor A reset i AN01 B A1-A5 Inst Gas Panel BC213 ET-4 NORM AN01A A1-A5 Inst Gas ET-6 00:00:27 ET-3 00:00:30 ET-3 Page 16 of 18

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: KL003 I

Rev # I Date Description Validation Required?

00 5/26/10 New JPM. Validation required. Validated with 2 RO's. Avg Y

. validation time 12 minutes.

01 7/28/10 Fixed trigger numbers ET-4 and ET-6 in text to agree with snap. N

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction TASK NUMBER: 4000780401 JPM NUMBER: 305H-,JPM.EG008 REV #: 05 SAP BET: NOH05JPEG08E ALTERNATE PATH: 0 APPLICABILITY:

EOD RO [K] STA D SRO [K]

DEVELOPED BY: Archie E. Faulkner DATE: 5/~:6/1 0 Instructor REVIEWED BY:

Operations Representative APPROVED BY: 3tL OQJ-=::::

Training Department DATE:~L

TQ-AA*106-0303 STATION: Hope Creek JPM NUMBER: EG008 REV: 05 SYSTEM: Safety Auxiliaries Cooling Water TASK NUMBER: 4000780401 TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction ALTERNATE PATH: ~ ~ANUMBER: ___2_9_5_01_8_AA_1_.0_2___

IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO EO D RO [ ] ] . STA D SRO [ ] ]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.COOL-0002, Rev 6 HC.OP-SO.KJ-0001, Rev 54 TOOLS, EQUIPMENT AND PROCEDURES: Annotated copy of HC.OP-SO.KJ-0001.

ESTIMATED COMPLETION TIME: 3 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

--- 9 - - Minutes PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

i Page 2 of 16

TQ*AA*106*0303 NAME: _____________________

DATE:

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Coaling Water Malfunction TASK NUMBER: 4000780401 INITIAL CONDITIONS:

1. The plant is at 100% power with TACS being supplied by the lA' SACS loop.

2. The '0' EOG is INOPERABLE and has been placed in service for a loaded maintenance run following work on the governor.

3. The '0' EOG has been 10qded to 1000 't<JN and approximately 500 KVAR lAW HC.OP-SO.KJ-0001. Load is being held here while governor stabllity at low loads is being evaluated.

4. The 'B' SACS pump just tripped and HC.OP-AB.COOL-0002 is being implemented.

INITIATING CUE:

Implement Condition A of HC.OP-AB.COOL-0002.

You are only responsible for actions contained in HC.OP-AB,COOL-0002, The Simulator is in freeze and you will be given five minutes to walk down the panels and obtain your procedure. Inform your examiner when you are ready to begin, This is a time critical "IPM.

Page 3 of 16

TQ-.MA-106-0303 JPM: EG008 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) I CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

Examiner Note: Keep the Simulator ~ ~88 :881 ~

in freeze and allow the Operator to walk down the panels and obtain HC.OP-AB.COOL-0002.

~ ~ ~

Operator obtains procedure Operator obtains the correct procedure.

HC.OP-AB.COOL-0002.

CUE When EITHER five minutes has elapsed, OR the Operator has ~

indicated he/she is ready to begin, PLACE the Simulator in RUN and

~

INFORM the Operator the JPM has commenced. ~

~ ~ ~

CUE ENTER START TIME AFTER SIMULATOR IS REMOVED FROM ~ ~ ~

FREEZE: ~ ~

START TIME: ~

Page 4 of 16

TQ-AA-106-0303 JPM: EG008 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD A1 START the unaffected pump as follows:

A1.a VERIFY INOP and OVLDJPWR FAIL Operator observes the SAFETY are not illuminated. AUXILIARIES COOLING LOOP B PUMPS PUMP 0 INOP and OVLD/PWR FAIL lights are not illuminated.

A1.b PLACE the pump in manual. Operator presses the SAFETY

AUXILIARIES COOLING LOOP B PUMPS PUMP 0 MAN pushbutton. #

Operator observes the MAN light illuminates and the AUTO light extinguishes.

Page 5 of 16

TQ-i'iA~1 06-0303 JPM: EG008 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

.(*Denotes a Critical Step) COMMENTS STEP ELEMENT (#Denotes a Sequential Step)

'" EVAL (Required for UNSAT NO. STANDARD # StU evaluation)

A1.c START the pump. Operator presses the SAFETY

AUXILIARIES COOLING LOOP B PUMPS PUMP 0 DP210 START #

TIME:

pushbutton.

Operator observes the PUMP 0 DP210 START light illuminates and the STOP light extinguishes Operator observes the PUMP D DP210 AI-63560 (amps) goes off-scale high.

After approximately 3 seconds, the '0' SACS pump trips and the operator observes the following:

PUMP 0 AI-63560 amps drop to zero

OHAA1 SACS LOOP B TROUBLE reflashes

The PUMP 0 DP210 START light extinguishes

The PUMP 0 STOP light begins flashing I I I I I Page 6 of 16

TQ-AA-106-0303 JPM: EG008 OPERATOR TRAINING PROGRAM Rev: OS JOB PERFORMANCE MEASURE SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

(*Denotes a Critical Step) COMMENTS STEP

NO.. ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT STANDARD # Stu A.2 IF flow cannot be restored to the Operator determines flow cannot be affected loop, restored to the '8' SACS loop.

THEN PERFORM the following:

CUE If the Operator questions who is responsible for the '0' EDG, N/A DIRECT the Operator to perform steps in A.2 of HC.OP-AB.COOl-0002.

A.2 UNLOAD AND SECURE all EOG's aligned to the affected loop as follows:

A.2.a PRESS GEN VR LOWER Operator presses the EMERGENCY pushbutton until Generator KVAR . GENERATORS 0 01 ESEL loading is < 200 KVAR. GENERATOR 10G400 GEN VR LOWER pushbutton until* GEN 0 VARI-639SD indicates < 200 KVAR.

A.2.b PRESS DIESEL ENG GOV DECR Operator presses the EMERGENCY pushbutton until Generator load < GENERATORS 0 DIESEL 200 KW. GENERATOR 10G400 DIESEL ENG GOV DECR pushbutton until GEN 0 WI-6394D indicates < 200 KW.

Page 7 of 16

TQ-MA-106-0303 JPM: EG008 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Examiner Note: The D EDG output breaker may trip on reverse power.

A2.c TRIP associated EOG GEN BRKR. Operator presses the EMERGENCY GENERATORS D DIESEL GENERATOR 10G400 GEN BRKR TRIP pushbutton.

Operator observes the 40407 TRIP light illuminates and the CLOSE light extinguishes.

perator presses A2.d STOP the EDG. GENERATORS 0 DIESEL

GENERATOR 1DG400 DIESEL ENG STOP Pllshbutton. TIME: _ __

Operator observes the DG400 STOP light illuminates and the START light extinguishes BEFORE the EDG catastrophically fails and trips (::::9 minutes with NO operator action).

Page 8 of 16

TQ-....A-106-0303 EG008 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 DATE: ___________________

JOB PERFORMANCE MEASURE SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Examiner Note: Time Critical portion is satisfied if Operator secures EDG before it catastrophically fails and trips.

ENSURE Control Room Chilled Operator observes the 'A' Control Water is aligned to the unaffected Room Ventilation and Chilled Water 100p.(GJ) train is in service.

ENSURE TSC Chilled Water is Operator observes the 'A' TSC aligned to the unaffected 100p.(GJ) Ventilation and Chilled Water train is in service.

DECLARE the loop inoperable, Operator informs CRS the 'B' SACS AND IMPLEMENT Condition K. loop should be declared inoperable and Condition K should be implemented.

Examiner Note: It is not necessary for the Operator to perform any Condition K actions.

Page 9 of 16

TQ-~-1 06*0303 EG008 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE: __~--------------

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U eva I CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 10 of16

TQ-AA-106*0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: EG008 TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction TASK NUMBER: 4000780401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 11 of 16

TQ~AA*1 06*0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power with TACS being supplied by the 'A' SACS loop.

2. The '0' EOG is INOPERABLE and has been placed in service for a loaded maintenance run following work on the governor.

3. The '0' EOG has been loaded to 1000 KJN and approximately 500 KVAR lAW HC.OP-SO.KJ-0001. Load is being held here while governor stability at low loads is being evaluated.

4, The '8' SACS pump just tripped and HC.OP-AB.COOL-0002 is being implemented.

INITIATING CUE:

Implement Condition A of HC.OP-AB.COOL-0002.

You are only responsible for actions contained in HC.OP-AB.COOL-0002.

The Simulator is in freeze and you will be given five minutes to walk down the panels and obtain your procedure. Inform your examiner when you are ready to begin.

This is a time critical JPM, Page 12 of 16

TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

. INITIALIZE the simulator to 100% power, MOL.

ENSURE TACS is aligned to the 'A' SACS loop_

ENSURE the 'A' Control Room Ventilation train is in service.

ENSURE the 'N TSC Ventilatlon train is in service.

i ENSURE the EG-HV-2314B is closed ('B' SACS to Fuel Pool Cooling Hx).

START the '0' EDG and LOAD to 1000 KW and 500 KVAR lAW SO.KJ-0001.

! ACKNOWLEDGE Control Room and Local alarms.

INSERT the trip of the 'B' SACS pump as follows:

1. ENSURE the 'B' SACS pump is in service and '0' SACS pump is in standby.

2. INSERT Malfunction CW10B

3. Allow the pump to trip AND OHA A1-A5 to alarm, then FREEZE the simulator.

INITIAL HC.OP-SO.KJ-0001 for the '0' EOG.

UPDATE the LAST START and BAR information for '0' EOG on 10C651 E to the current date.

PLACE Robust Op Barriers on the '0' EOG BRKR and ENG controls FLAG the '0' EOG GOV AND GEN VR pushbuttons COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT ACTION: cw:z52pd >= 1.0 II '0' SACS pump start COMMAND:

PURPOSE: Trips '0' SACS pump shortly after start.

Page 13 of 16

TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

CW10D Trip of 'D' SACS pump 3 sec ET-1 Page 14 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: EG008 Rev# i Date Description Validation Required?

03 9/4108 Revised to new JPM format. JPM Initial Cue and Start N Time did not change, therefore previously validated time did not change. No re-validation required.

Updated reference procedure revision number.

I Revised power level for EPU.

Operator actions did not change.

04 12/7/09 Updated reference procedure revision number. Revised N power level for EPU. Operator actions did not change.

Added f'TIME " to step A.2.d COMMENTS field to mark time of stopping EDG. Replaced N/A with "gf!

minutes to "Time Period For Time Critical Steps". This time was already specified In the body of the JPM and IS an editorial change.

05 I 5/26/10 Updated reference procedure revision numbers. Split out N action steps from observation elements. Deleted Tap changers in manual. No longer needed for EDG operation in test. Operator actions did not change. Validated with 2 RO's. Average validation time did not chan e.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction TASK NUMBER: 4000070401 JPM NUMBER: 305H-JPM.SB004 REV #: 13 SAP BET: NOH05JPSB04E ALTERNATE PATH:

0 APPLICABILITY:

EO RO []J STA SRO []J DEVELOPED BY: Archie E. Faulkner DATE: 4/20/10 Instructor REVIEWED BY:

Operations Representative APPROVED BY:

orv~

Training Department DATE: ~/-,---/tJ_

TQ-AA-106-0303 STATION: Hope Creek JPlVI NUMBER: S8004 REV: 13 SYSTEM: Control Rod and Drive MechC)nism TASK NUMBER: 4000070401 TASK: Respond To A Control Rod System Malfunction ALTERNATE PATH: [KJ KIA NUMBER: 295015 AA1.02 IMPORTANCE FACTOR: 4.0 4.2 APPLICABILITY: RO SRO EoD ROW STAD SROW EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-ST.SF-0003 Rev 12 HC.OP-AB.IC-0001 Rev 10 HC.OP-AB.ZZ-0001 Rev 21 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 14 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 22

TQ-AA-106*0303 NAME:

DATE: ______________.______

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction TASK NUMBER: 4000070401 INITIAL CONDITIONS:

1. Reactor is at 100% power.

2. No other testing or maIntenance is in progress.

3. A thermal scan of all 185 HCUs has been performed.

INITIATING CUE:

You are the Reactor Operator.

Perform HC.OP-ST.SF-0003, RPS MANUAL SCRAM TEST - WEEKLY.

Page 3 of 22

TQ-AA-106-0303 JPM: S8004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE:

~------

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluati CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the. correct Operator obtains procedure procedure. HC.OP-ST.SF-0003.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE If excessive time is taken reviewing precautions and limitations, inform N/A operator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.1.

5.1.1 LOG test start time in the Control Operator requests that the start Room log(s). time be logged in the Control Room logs.

CUE INFORM the Operator the test $tart time has been fogged in the NiA Control Room logs.

Page 4 of 22

TQ-,",A-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME: ----

Rev: 13 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluatio 5.1.2 ENSURE all prerequisites have been Operator reviews Prerequisites, satisfied lAW Section 2.1. completes Section 3.0 of Attachment 1, and initials each Prerequisite in the space provided in the procedure.

CUE If excessive time is taken reviewing prerequisites, inform operator that NJA all are satisfied.

5.1.3 ENSURE Attachment 1, Section 1.0 Operator ensures that Attachment 1, SM/CRS Data and Signature Section 1.0 of the SM/CRS Data and Sheet has been completed and Signature Sheet has been completed Regular Surveillance or Retest is and Regular Surveillance is indicated indicated.

5.1.4 ENSURE all RPS TRIPS are reset. Operator observes RPS indications on the 10C651 panel and overhead annunciator panels, and determines that RPS is reset.

5.1.5 ARM RPS TRIP SYS Ai MAN INIT Operator rotates the RPS TRIP SYS Ai

PB. MAN INIT push button clockwise. #

5.1.6 VERIFY Annunciator MANUAL SCRAM SW ARMED alarms. Operator observes OHA C3-A 1

[TIS 4.3.1.1] MANUAL SCRAM SW ARMED alarms.

Page 5 of 22

TQ-AA-106-0303 JPM:. SB004 OPERATOR TRAINING PROGRAM NAME: ___________________

Rev: 13 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

NOTE following step will cause a TRIP Operator reads NOTE.

of RPS TRIP SYS A 1.

1.7 PRESS RPS TRIP SYS A1 MAN INIT Operator presses the RPS TRIP

PB. A1 MAN INIT push button.

5.1.8 VERIFY the following occurs:

N/A 5.1.8. Annunciator MANUAL SCRAM alarms Operator observes OHA C5-A3 MANUAL SCRAM annunciator alarms.

A 5.1.8. RPS TRIP SYSTEM A TRIP LOGIC A 1 NORMAL/RESET Operator verifies the RPS TRIP B SYSTEM A TRIP LOGIC A 1 light extinguishes. [TIS 4.3.1.1]

NORMAL/RESET light extinguishes.

5.1.8. PILOT SCRAM VALVE SOLENOID TRIP ACTUATOR Operator verifies the PILOT SCRAM C

LOGICS Groups 1, 2, 3 and 4 VALVE SOLENOID TRIP ACTUATOR SOLENOIDS LOGIC A LOGICS Groups 1, 2, 3 and 4 NORMAL lights extinguish. [TIS SOLENOIDS LOGIC A NORMAL lights 1.1] extinguish.

Page 6 of 22

TQ-AA-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME: -----------------

Rev: 13 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step) EVAL ELEMENT (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.8. Annunciator REACTOR SCRAM TRIP Operator observes OHA C3-A2 LOGIC A 1 alarms. REACTOR SCRAM TRIP LOGIC A1 0

annunciator alarms.

5.1.9 UN-ARM RPS TRIP SYS A1 MAN Operator rotates the RPS TRIP SYS A1 INIT PB. MAN INIT push button counterclockwise.

5.1.10 RESET RPS Channel A1. Operator momentarily rotates the RPS

TRIP SYS A1 RESET key switch clockwise, then allows it to return to the counterclockwise position.

xx:

5.1.11 VERIFY the following occurs: <5<%<

N/A 5.1.11. MANUAL SCRAM annunciator is Operator observes OHA C5-A3 clear. MANUAL SCRAM annunciator A

extinguishes.

Page 7 of 22

TQ~~-1 06-0303 JPM: S8004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD SJU evaluation) 5.1.11. MANUAL SCRAM SW ARMED Operator observes OHA C3-A 1 annunciator is clear. [TIS 4.3.1.1] MANUAL SCRAM SW ARMED B

annunciator extinguishes.

5.1.11. RPS TRIP SYSTEM A TRIP LOGIC Operator verifies the RPS TRIP Ai NORMAL/RESET SYSTEM A TRIP LOGIC Ai C

light is illuminated. [TIS 4.3.1.1] NORMAL/RESET light illuminates.

5.1.11. PILOT SCRAM VALVE SOLENOID Operator observes the PILOT SCRAM TRIP ACTUATOR VALVE SOLENOID TRIP ACTUATOR D

LOGICS Groups 1, 2, 3 and 4 LOGICS Groups 1, 2, 3 and 4 SOLENOIDS LOGIC A SOLENOIDS LOGIC A NORMAL lights NORMAL lights are illuminated. [TIS illuminate.

4.3.1.1]

Examiner Note: RPS is considered ~ ~ ~

reset. N/A ~ ~ ~

~ ~ ~

5.1.11. REACTOR SCRAM TRIP LOGIC Ai Operator observes that OHA C3-A2 is clear. REACTOR SCRAM TRIP LOGIC Ai E

clears.

Page 8 of 22

TQ-AA-106-0303 JPM: S8004 OPERATOR TRAINING PROGRAM NAME: -------------------

Rev: 13 JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu evaluation) I 5.1.12 ENSURE all RPS Trips are RESET. Operator observes RPS indications on the 10C651 panel and overhead annunciator panels, and determines that RPS is reset.

5.1.13 ARM RPS TRIP SYS A2 MAN INIT Operator rotates the RPS TRIP SYS A2

PB. MAN INIT push button clockwise.

5.1.14 VERIFY Annunciator MANUAL SCRAM SW ARMED alarms. [TIS Operator observes OHA C3-A 1 4.3.1.1] MANUAL SCRAM SW ARMED alarms.

NOTE The following step will cause a TRI P ~~

of RPS TRIP SYS A2. N/A 28 5.1.15 PRESS RPS TRIP SYS A2 MAN

INIT PB. Operator presses the RPS TRIP SYS A2 MAN INIT push button. #

5.1.16 VERIFY the following occurs:

N/A I I I Page 9 of 22

TQ-AA-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) i 5.1.16. Annunciator MANUAL SCRAM A alarms. Operator observes OHA C5-A3 MANUAL SCRAM annunciator alarms.

5.1.16. RPS TRIP SYSTEM A TRIP LOGIC Operator verifies the RPS TRIP B A2 NORMAURESET SYSTEM A TRIP LOGIC A2 light extinguishes. [TIS 4.3.1.1] NORMAURESET light extinguishes.

5.1.16. PILOT SCRAM VALVE SOLENOID C TRIP ACTUATOR Operator verifies the PILOT SCRAM VALVE SOLENOID TRIP ACTUATOR LOGICS Groups 1, 2, 3 and 4 LOGICS Groups 1, 2, 3 and 4 SOLENOIDS LOGIC A SOLENOIDS LOGIC A NORMAL lights NORMAL lights extinguish. [TIS extinguish.

4.3.1.1]

5.1.16. Annunciator REACTOR SCRAM TRIP Operator observes OHA C3-A3 D LOGIC A2 alarms. REACTOR SCRAM TRIP LOGIC A2 annunciator alarms.

5.1.17 UN-ARM RPS TRIP SYS A2 MAN Operator rotates the RPS TRIP SYS A2 INIT PB. MAN INIT push button counterclockwise.

Page 10 of 22

TQ-nA-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 13 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U eval 5.1.18 RESET RPS Channel A2. Operator momentarily rotates the RPS

TRIP SYS A2 RESET key switch clockwise, then allows it to return to the counterclockwise position.

5.1.19 VERIFY the following occurs:

NIA 5.1.19. MANUAL SCRAM annunciator is Operator observes OHA C5-A3 A clear. SCRAM extinguishes.

5.1.19. MANUAL SCRAM SW ARMED Operator observes OHA C3-A 1 B annunciator is clear. [TIS 4.3.1.1] MANUAL SCRAM SW ARMED annunciator extinguishes.

5.1.19. RPS TRIP SYSTEM A TRIP LOGIC Operator verifies the RPS TRIP C A2 NORMAL/RESET SYSTEM A TRIP LOGIC A2 light is illuminated. [fIS 4.3.1.1] NORMAL/RESET light illuminates.

Page 11 of22

TQ-AA-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu evaluation) i 5.1.19. PILOT SCRAM VALVE SOLENOID D TRIP ACTUATOR Operator observes the PILOT SCRAM LOGICS Groups 1, 2, 3 and 4 VALVE SOLENOID TRIP ACTUATOR LOGICS Groups 1, 2, 3 and 4 SOLENOIDS LOGIC A SOLENOIDS LOGIC A NORMAL lights NORMAL lights are illuminated. [flS illuminate.

4.3.1.1]

Examiner Note: RPS is considered N/A reset.

5.1.19. REACTOR SCRAM TRIP LOGIC A2 Operator observes that OHA C3-A3 E is clear. REACTOR SCRAM TRIP LOGIC A2 clears.

5.1.20 ENSURE all RPS Trips are RESET. Operator observes RPS indications on the 10C651 panel and overhead annunciator panels, and determines

. that RPS is reset.

5.1.21 ARM RPS TRIP SYS 81 MAN INIT Operator rotates the RPS TRIP SYS 81

PB. MAN INIT push button clockwise.

I I I Page 12 of 22

TQ-MA-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.22 VERIFY Annunciator MANUAL SCRAM SW ARMED alarms. [f/S Operator observes OHA C3-A 1 4.3.1.1] MANUAL SCRAM SW ARMED alarms ..

NOTE The following step will cause a TRIP of RPS TRIP SYS B1. N/A 5.1.23 PRESS RPS TRIP SYS B1 MAN Operator presses the RPS TRIP SYS INIT PB. 81 Page 13 of 22

TQ~hA-1 06-0303 SB004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step)

COMMENTS ELEMENT (#Denotes a Sequential Step) (Required for UNSAT STANDARD evaluatio IMMEDIATE OPERATOR ACTIONS Multiple Control Rods are Drifting Simultaneously. . Operator recognizes multiple rods drifting.

LOCK the Mode Switch in SHUTDOWN.

Operator rotates the Mode Switch

Counterclockwise to SHUTDOWN.

Examiner Note: Operator may select drifting rods on Rod Select Matrix to verify drifting prior to placing Mode I N/A Switch to SHUTDOWN.

Examiner Note: Placing Mode Switch in SHUTDOWN may be performed I N/A during Hard card execution.

Operator removes the Mode Switch key.

1.0 ANNOUNCE "Crew Standby for Operator announces "Crew - Standby Scram Report". Scram Report".

Page 14 of 22

TQ-AA-106-0303 JPM: SB004 OPERATOR TRAINING PROGRAM NAME: - - - - - - - - - - - - - - - - - - -

Rev: 13 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT ELEMENT NO. STANDARD # stU evaluation) 2.0 LOCK the Mode Switch in Shutdown. IE not previously performed, THEN Operator rotates the Mode Switch Counterclockwise to SHUTDOWN and removes the key.

3.0 ANNOUNCE the following: Operator observes red FULL OUT lights extinguish and green FULL IN

Rod Motion status lights illuminate on the Full Core Display.

Operator announces the presence of rod motion.

APRM Downscale status Operator observes Operator observes the amber MONITOR STATUS DNSC lights for all APRMs are Illuminated.

Operator announces the APRMs are downscale.

Page 15 of 22

TQ-AA-106-0303 JPM: S8004 OPERATOR TRAINING PROGRAM NAME:

Rev: 13 JOB PERFORMANCE MEASURE DATE:

~~--------

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To A Control Rod System Malfunction

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U

Reactor Shutdown status Operator observes all rods are fully inserted and/or reactor is shutdown on one or more of the following:

Rod Worth Minimizer

CRIDS

Full Core display

Four Rod Display

Plant Process Computer

SPDS Operator announces the reactor is shutdown.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons,

-=-.:...:.='-'- RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 16 of 22

TQ-AA..106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: S8004 TASK: Respond To A Control Rod System Malfunction TASK NUMBER: 4000070401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 17 of 22

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1, Reactor is at 100% power.

2, No other testing or maintenance is in progress, 3, A thermal scan of all 185 HCUs has been performed.

INITIATING CUE:

You are the Reactor Operator.

Perform HC,OP-ST,SF-0003, RPS MANUAL SCRAM TEST - WEEKLY.

Page 18 of 22

TQ~AA*1 06~0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to 100% power.

PERFORM any other set-up items that can be snapped.

ENSURE Copy of HC.OP*ST.SF-0003 with Attachment 1 Section 1.0 completed is available.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT ACTION: rp:k14b <= 0.0 II rp:k14d <= 0.0 II RPS B1 or B2 tripped COMMAND:

PURPOSE: Initiates multiple rod scrams.

I EVENT ACTIOI\!:

2 COMMAND:

PURPOSE:

Page 19 of 22

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

CD012627 Control Rod 26-27 Drift In ET-1 CD011827 Control Rod 18-27 Drift In ET-1 Page 20 of 22

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: SB004 Rev # Date Description Validation Required?

10 7/20/07 Revision 10 of HC, OP-ST,SF-0003 added verbiage "and initial N Attachment 2" to various steps. Since these steps already had Attachment 2 initials, and the Standard already referenced the need to initial Attachment 2 for these steps, no new actions were generated and the change is editorial, validation is not required.

Corrected typographical error in SB004 Rev 9 which identified the Scram Hard Card as "HC.OP-AB,IC-0001 Attachment 1" instead of HC,OP-AB,ZZ-0001 Attachment 1", This change is editorial, validation not required, Converted SB004 to new JPM format. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted, This change is editorial, validation not required, Removed references to initialing procedure steps, This is a generic work practice and adds unnecessary clutter to the Standard section, This change is editorial, validation not required, References to initialing of Attachment 2 remain, since they are relevant to the documented completion of the surveillance, Added Note text to Element section, This is for examiner reference only and has no associated student actions, This change is editorial, validation not required.

11 8/25/08 Revision 11 to OP-ST.SF-003 required the following changes: Y All steps with "Initial Attachment 2" removed, Revision 9 to AB-IC-0001 Immediate Operator Action required the following changes:

Rod malfunctions for scramming rods changed to drifting rods, 12 10/6J09 Updated Reference procedure revision number, Revised Initial N Conditions from 97% to 100% power, Corrected typos on Malfunction Summary description for Control Rod numbers. No chE!r~t() operator actions, No validation required, 13 4/20/10 Updated Reference procedure revision number. Split out N operator actions and observation elements. No change to

, operator actions, No validation required .

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

TASK NUMBER: 5880040101 JPM NUMBER: 305H-JPM.ED001 REV #: 10 SAP BET: NOH05JPED01 E ALTERNATE PATH: D APPLICABILITY:

EO RO.~ ~ STA D.. SRO I){l

~

DEVELOPED BY: Archie E. Faulkner DATE: 7/28/10 Instructor REVIEWED BY: ~

Operations Representative DATE: ¥/r/;~

APPROVED BY: qv~ DATE: rltl/i)

Training Department

STATION: Hope Creek

. JPM NUMBER: ED001 REV: 10 SYSTEM: Reactor Auxiliary Cooling System TASK NUMBER: 5880040101 TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

ALTERNATE PATH: 0 KIA NUMBER: 295018 AA 1.01 IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO EO D RO []J STA D SRO []J EVALUATION. SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0001 Rev 01 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ-AAu106*0303 NAME:

DATE:

SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

TASK NUMBER: 5880040101 INITIAL CONDITIONS:

1. The plant is at 100% Reactor power.

2. All Turbine Building chilled water eire pumps have tripped due to a Freon leak into the system.

3. All Turbine Building chillers have tripped and efforts to restart them have failed.

4. HC.OP-AB.CONT-0001 Orywell Pressure is being implemented.

INITIATING CUE:

Align RACS to supply drywell cooling lAW Condition B of HC.OP-AB.CONT-0001.

Page 3 of 14

TQ-Io\A-106-0303 ED001 OPERATOR TRAINING PROGRAM NAME:

~

Rev: 10 JOB PERFORMANCE MEASURE DATE:

~

SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U eva I CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TI ME '-=---'-==-.::

OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.CONT-0001.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be Condition B.

Condition B Turbine Bldg. Chill Water N/A System is lost to the Drywell.

CAUT If the cause of the loss of Turbine 1 Building Chilled Water is Gas/Air intrusion, there is a potential to displace air into the RACS system, Operator reads CAUTION degrading its operation.

Page 4 of 14

TQ-AA-106-0303 JPM: ED001 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U eval B.1 ALIGN RACS to the Chill Water System for Drywell Cooling as follows: N/A B.1.a ENSURE RACS to the out of service Off-Gas Train is ISOLATED as follows: N/A

the Common Off-Gas is Operator recognizes this step does service, NOT apply, leaves the HV-2577 open.

THEN CLOSE HV-2577

the UNIT 1 Off-Gas train is Operator presses the OFF GAS CLR

Y N STAR in service, CNDS COOLING OOE306 COMMON

-=-.:....:.=-:...:. CLOSE HV-7712A1. HV-7712A1 CLOSE pushbutton.

Operator observes the CLOSE illuminates and OPEN light extinguishes.

Page 5 of 14

TQ-AA-106-0303 ED001 OPERATOR TRAINING PROGRAM NAME: ___________________

Rev: 10 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

(*Denotes a Critical Step} COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

B.1.b CLOSE HV-9532-1 Operator presses the CHW ISLN RTN

YN STAR AND HV-9532-2. VLV HV-9532-1 CLOSE pushbutton.

Operator presses the CHW ISLN SUP

YN STAR VLV HV-9532-2 CLOSE pushbutton.

i Operator observes the green CLOSE indicators illuminate and the red OPEN indicators extinguish.

B.1.c PRESS LOOP A SPLY/RTN OPEN Operator presses the CONTAINMENT

YN STAR RACS PB. CLG SPLY SELECT LOOP A SPLY/RTN CHW/RACS SEL OPEN RACS pushbutton.

B.1.d PRESS LOOP B SPLY/RTN OPEN Operator presses the CONTAINMENT

Y N STAR RACS PB. CLG SPLY SELECT LOOP B SPLY/RTN CHW/RACS SEL OPEN RACS pushbutton.

Page 6 of 14

TQ-AA-106-0303 JPM: ED001 OPERATOR TRAINING PROGRAM NAME: -------~~~~--

Rev: 10 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD stu evaluation)

B.1.e OBSERVE the following indications:

N/A

HV-9530A1/A3 CLOSED The green HV-9530A1/A3 CLOSED indicator illuminates and red OPEN extinguishes.

HV-9530B1/B3 CLOSED The green HV-9530B1/83 CLOSED indicator illuminates and red OPEN indicator extinguishes.

HV-9530A2/A4 OPEN The red HV-9530A2/A4 OPEN indicator illuminates and green CLOSED indicator extinguishes.

HV-9530B2/B4 OPEN The red HV-9530B2IB4 OPEN indicator illuminates and green CLOSED indicator extinguishes.

Page 7 of 14

TQ-AA-106-0303 JPM: E0001 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE OATE: ___________________

SYSTEM: Reactor Auxiliary Cooling System TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluati B.1.f OPEN HV-9532-1 Operator presses the CHW ISLN RTN

YN STAR AND HV-9532-2. VLV HV-9532-1 OPEN pushbutton.

Operator presses the CHW ISLN SUP

YN STAR*

VL V HV-9532-2 OPEN pushbutton.

Operator observes the red OPEN indicators illuminate and the green CLOSED indicators extinguish.

CUE WHEN operator infonns you the task is complete, OR the JPM has been terminated for

.. reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: ED001 TASK: Manually Switch between Chill Water and The Reactor Auxiliary Cooling System (RACS)

TASK NUMBER: 5880040101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

... ~.~~..... --------------------------

RESULT: SAT UNSAT Page 9 of 14

TQ*AA*106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% Reactor power.

2. All Turbine Building chilled water eire pumps have tripped due to a Freon leak into the system.

3. All Turbine Building chillers have tripped and efforts to restart them have failed.

4. HC.OP-AB.CONT-0001 Drywell Pressure is being implemented.

INITIATING CUE:

Align RACS to supply drywell cooling lAW Condition B of HC.Op*AB.CONT*OOO1.

Page 10 of 14

TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to 100% power, MOL.

PLACE CP161 in MANUAL.

INSERT trips of AP161, BP161, and CP161 and allow TB Chillers to trip.

MAXIMIZE Drywell Cooling.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT ACTION: mstunl >= 135 II Main Steam Tunnel temp. 135 degF COMMAND:

PURPOSE: Starts BVH216 Steam Tunnel Unit Cooler to prevent MSIV isolation.

EVENT ACTION:

2 COMMAND:

PURPOSE:

Page 11 of 14

TQ-AA-106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIOI\JAL)

CW18B TB Chilled Water Cire Pump BP161 Trip CW18C TB Chilled Water Cire Pump CP161 Trip 1A113 E 01 BK111 Safety Ckt Pushbutton 1 A134 E 01 CK111 Safety Ckt Pushbutton 1A181 E1 OJ DK111 Safety Ckt Pushbutton

. 1A97 A1 LO AP161 OVLD/PWR FAIL 1A115 A1 LO BP161 OVLD/PWR FAIL Page 12 of 14

JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ED001 IRev# Date Description Validation

! Required?

7 7/20/07 Revision 1 of HC.OP-AB.CONT-0001 incorporated OTC DB and N changed Condition C to Condition B with NO change in action steps. ED001 updated to reflect this re-numbering of steps. No change in actions, validation not required.

Converted E0001 to new JPM format. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial, validation not required.

Removed references to checking off steps in abnormal. This is a generic work practice and adds unnecessary clutter to the Standard section. This change is editorial, validation not required.

Added Caution text to Element section. This is for examiner reference only and has no associated student actions. This change is editorial, validation not required.

8 9/17/08 Broke down steps B.1.b and B.1.f into individual elements. N i Marked action steps as critical. Editorial change only. No i changes to operator actions. No validation is required.

9 10/6/09 Corrects typo at I/O Override Summary 1A 181 E1 01 OK111 N Safety Ckt Pushbutton. No operator actions changed. Validation is not required.

10 I 7/28/10

Adds HPI check items. Add CW18C to snap. Corrects typo error. No operator actions changed. Validation is not required.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System TASK NUM BER: 4880060101 JPM NUMBER: 305H-JPM.GK002 REV#: 00 SAP BET: NOH05JPGK02E ALTERNATE PATH: [KJ APPLICABILITY:

EO RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 8/2/10 Instructor REVIEWED BY: ~-

Operations Representative DATE:~L APPROVED BY:

1ni~t DATE: ~/4/lo

06-0303 STATION: Hope Creek JPM NUMBER: GK002 REV: 00 SYSTEM: Control Area Ventilation System TASK NUMBER: 4880060101 TASK: Isolate the Control Room HVAC System ALTERNATE PATH: W KiA NUMBER: _ _ 29_0_00_~3_A_4_.0_1__

IMPORTANCE FACTOR: 3.2 3.2 APPLICABILITY: RO SRO EoD ROm STAD SROm EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.HVAC-0002 Rev 7 HC.OP-SO.GK-0001 Rev 14 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 18 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

-- N/A

- - Minutes JPM PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 23

TQ*AA~1 06-0303 NAME:

DATE:

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System TASK NUMBER: 4880060101 INITIAL CONDITIONS:

1. The plant is at 100% power.

2. "An Control Room Ventilation train is in service.

3. The Aux Building Operator has been briefed and is standing by on location.

INITIATING CUE:

You are the Plant Operator.

Swap Control Room Ventilation to "8" Train lAW HC.OP-SO.GK-0001.

Page 3 of 23

TQ-AA-106-0303 GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE; ___________________

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evalu CUE . PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I NM START TIME:

Operator obtains procedure Operator obtains the correct HC.OP-SO.GK-0001.

procedure.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.4.

5.4.1 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.4 are satisfied. have been satisfied.

CUE IF excessive time is taken reviewing prerequisites, N/A THEN INFORM operator that all are satisfied.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

Page 4 of 23

TQ-M-106-0303 GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: JOB PERFORMANCE MEASURE DATE: - - - - - - - -

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a.Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. # eval .-4-:--\

STANDARD S/U l CUE IF excessive time is taken reviewing precautions and limitations, N/A THEN INFORM operator that all are satisfied.

NOTE operations are performed from 1OC651 E unless otherwise noted.

Procedure describes transfer from A Control Chilled Water Loop in service to the B Loop in service, values parentheses used to transfer back to A in service.

SACS Pump Room Unit Coolers 1 AVH214 AND 1BVH214 are Operator reads NOTE.

interlocked to operate in AUTO only IF Chilled Water Pump AP400 is in service. SACS Pump Room Unit Coolers 1CVH214 and 1DVH214 are interlocked to operate in AUTO only IF Chilled Water Pump BP400 is service.

5.4.2 PRESS CH W elRC PUMP B(A)P400 Operator presses the MAN PB.

MAN PB. MAN comes on.

Page 5 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

~------------------

Rev: 00 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD SJU evaluation Operator observes the MAN light illuminates.

5.4.3 STOP the running Chiller by performing the following: N/A 5.4.3. PRESS CH W CPRSR A{B)K400 Operator presses the CH W CPRSR

A MOT STOP PB. VERIFY STOP AK400 MOT STOP PB.

comes on.

Operator observes the STOP light illuminates.

Operator acknowledges OHA D1-A4 "BOP SAFETY SYS OUT OF SVCE" 5.4.3. OBSERVE the following:

N/A B

5.4.3. CH W CPRSR MOT A (B) ON/AUTO Operator observes the CH W CPRSR B.1 goes off. MOT A MAN light illuminates.

Page 6 of 23

TQ-AA.-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME: __~~_____________

Rev: 00 JOB PERFORMANCE MEASURE DATE: ______________

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluation) 5.4.3. CH W CPRSR A (8) OFF comes ON. Operator observes the CH W CPRSR A B.2 OFF light illuminates.

5.4.3. CH W CPRSR A (6) PROGRAM Operator observes the CH W CPRSR A 8.3 TIMER ON comes on. PROGRAM TIMER ON light illuminates.

5.4.3. CH W CPRSR A (8) SAFETY CKT Operator observes .the CH W CPRSR A B.4 COMPLETE goes off. SAFETY CKT COMPLETE light extinguishes.

5.4.3. After approximately 99 seconds 8.5 PROGRAM TIMER ON goes off AND Operator observes the CH W CPRSR A the Chiller is ready for re-start. PROGRAM TIMER ON light extinguishes.

~-----

5.4.4 PRESS CH W CIRC PUMP A (8) Operator presses the CH W CIRC

P400 MAN PB. A (B) P400 MAN PUMP AP400 MAN PB.

comes on.

Operator observes the CH W CIRC I PUMP AP400 M~N light illuminates.

I I I --

Page 7 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE: ~-----------------

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # I stu evaluati 5.4.5 PRESS CW W CIRC PUMP A (8) Operator presses the CW W CIRC

P400 STOP PB. STOP comes on PUMP AP400 STOP PB.

AND the following actions occur:

Operator observes the CW W CIRC PUMP AP400 STOP light illuminates.

5.4.5. Cont Rm Sply Fan 1A (8) VH403 Operator observes the Cont Rm Sply A stops. Fan 1AVH403 stops.

5.4.5. Cont Eq Rm Sply Fan 1A (B)VH407 Operator observes the Cont Eq Rm B stops. Sply Fan 1AVH407 stops.

Operator acknowledges OHA E6B1 "CONTROL AREA HVAC FAN MALF" 5.4.6 ACKNOWLEDGE fan trips by selecting STOP on the following:

5.4.6. PRESS CONT RM SPLY FAN Operator presses the CONT RM SPLY

A A(B)VH403 STOP PB. VERIFY STOP FAN AVH403 STOP PB.

comes on.

IJ Page 8 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

{*Denotes a Critical Step}

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator observes the CaNT RM

. SPLY FAN AVH403 STOP light illuminates.

5.4.6. PRESS CONT EQ RM SPLY FAN A Operator presses the CONT EO RM

B (B) VH407 STOP PB. VERIFY STOP SPLY FAN AVH407 STOP PB.

comes on.

Operator observes the CONT EO RM SPLY FAN AVH407 STOP light illuminates.

5.4.7 PRESS CONTROL RM RTN AIR FAN Operator presses the CONTROL RM

A (B) VH415 MAN PB THEN STOP RTN AIR FAN AVH415 MAN PB.

PB to secure fan.

Operator observes the CONTROL RM RTN AIR FAN AVH415 MAN light illuminates.

I Operator presses the CONTROL RM RTN AIR FAN AVH415 STOP PS.

I ~xaminer Note: The AVH415 fan may have tripped on low flow.

Page 9 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # SJU evaluation)

Operator observes the CONTROL RM RTN AI R FAN A VH415 STOP light illuminates.

I 5.4.8 PRESS CONTROL RM RTN AIR FAN

A (8) VH415 AUTO PB. VERIFY Operator presses the CONTROL RM AUTO comes on AND INITIAL RTN AIR FAN AVH415 AUTO PB.,

Attachment 1.

Operator observes the CONTROL RM RTN AIR FAN AVH415 AUTO light illuminates.

NOTE Control Area Chilled Water Pumps 1AP400 and 1BP400 are interlocked to operate in AUTO mode with SACS Pumps CP210 and DP210 Operator reads NOTE.

respectively_

Page 10 of 23

TQ-AA-106*0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME: - - - - - - -

Rev: 00 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # I S/U STANDARD evaluation) 5.4.9 PLACE the B(A) Control Area Chilled Water Loop in service as follows:

5.4.9. PRESS CH W CIRC PUMP B (A) Operator presses the CH W CIRC ""

A P400 START PB B(A)P400. VERIFY PUMP BP400 START PB.

START comes on.

Operator observes the CH W CIRC PUMP BP400 START light illuminates.

5.4.9. PRESS CONT RM SPLY FAN B (A) ""

B VH403 START PB. VERIFY B (A)

Operator presses the CONT RM SPLY #

VH403 START comes on AND FAN BVH403 START PB.

OBSERVE CONTROL RM RTN AIR FAN 1B (A) VH415 Auto Start.

Operator observes the CONT RM SPLY FAN BVH403 START light illuminates.

Operator observes the CONTROL RM RTN AIR FAN 1BVH415 START light illuminates.

Page 11 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # I SfU eva I 5.4.9. PRESS CONT EO RM SPLY FAN B Operator presses the CONT EQ RM

C (A) VH407 START PB. VERIFY SPLY FAN BVH407 START PB.

START comes on.

Operator observes the CONT EO RM SPLY FAN BVH407 START light illuminates.

5.4.9. To start Chiller 1B(A)K400 from D CONT RM, PERFORM the following: N/A 5.4.9. IF CH W CPRSR B (A) REMOTE is 0.1 on, PRESS REMOTE PB. VERIFY Operator observes the CH W CPRSR B REMOTE goes off. REMOTE light is extinguished.

5.4.9. PRESS CH W CPRSR B (A) Operator presses the CH W CPRSR B 0.2 ON/AUTO PB. VERIFY ON/AUTO ON/AUTO PB.

comes on. _Examiner Note: The CH W CPRSR B ON/AUTO PB liaht is already on.

Operator observes the CH W CPRSR B ON/AUTO light is illuminated.

Page 12 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME: -------------------

Rev: 00 JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) 5.4.9. WHEN CH W CPRSR B (A) SAFETY 0.3 CKT COMPLETE is on, PRESS CH Operator observes the CH W CPRSR B W CPRSR MOT B (A) K400 START SAFETY CKT COMPLETE.

PB. VERIFY B (A) K400 START comes on.

Operator presses the CH W CPRSR

MOT BK400 START PB.

%<9 5.4.9. PERFORM the following:

0.4 N/A m ~ ~ ~

5.4.9. VERIFY CH W CPRSR B (A) TIMER Operator observes the CH W CPRSR B O.4.a ON is on. PROGRAM TIMER ON light is illuminated.

5.4.9. After approximately 51 seconds, D.4.b VERI FY Compressor starts by observing CPRSR B(A) AI 6362B(A)

MOTOR AMPS indicates After approximately 51 seconds, approximately 48 to 50 amps AND Operator observes the CPRSR B AI B(A)K400 START is illuminated OR 6362B MOTOR AMPS indicates CH W CPRSR B (A) LOAD approximately 48 to 50 amps.

I\.-,.......'-/~I r- :_ r'"\h.1

"-CI.J T I.JLC I~ VI\!.

I I Page 13 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD stU evaluation)

Operator observes the BK400 START light illuminates.

5A.9. VERIFY CH W CPRSR B (A) TIMER Operator observes the CH W CPRSR B DA.c ON goes off. PROGRAM TIMER ON extinguishes. !

5.4.9. VERIFY CH W CPRSR B (A) MOTOR Operator observes the CH W CPRSR B DA.d RESTART DELAY comes on, AND MOTOR RESTART DELAY light THEN extinguishes (approx. 10 sec). illuminates and then extinguishes.

Page 14 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD CUE REPORT as Yard Operator that there is a large fire north of the HC Million Gallon Fuel Oil Storage Tank and smoke is headed towards N/A the power block.

CUE Light smoke is coming out of the Control Room ventilation supply ductwork into the Main Control Room.

[SRO] Take any required actions. NfA

[RO] Implement AB-HVAC-0002 and take any required actions.

Page 15 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD Operator reviews HC.OP-AB.HVAC 0002 CONTROL ROOM ENVIRONMENT.

EXAMINER NOTE: The same actions are contained within SO-GK-0001. The operator may not go to AB.HVAC-0002.

Cond Smoke OR Toxic Gases are L ENTERING the Control Room from an Operator determines Retainment Outside source. Override Condition I. applies.

I.a PRESS the ISOLATE PB for the liS Operator presses the ISOLATE PB for

Control Room Ventilation Train. the B Control Room Ventilation Train.

Operator observes the HD9598B ISOLATE PB for the B Control Room Ventilation Train illuminates.

Operator observes BV400 START PB illuminates.

Page 16 of 23

TQ-AA-106-0303 JPM: GK002 OPERATOR TRAINING PROGRAM NAME:

Rev: 00 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Area Ventilation System TASK: Isolate the Control Room HVAC System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evalu I.b PRESS the RECIRC PB for the lIS Operator presses the RECI.RC MODE

CREF Unit. PB for the B CREF Operator observes the RECIRC PB for the B CREF Unit illuminates.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 17 of 23

TQ*AA*106*0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

~

DATE:

JPM Number: GK002 TASK: Isolate the Control Room HVAC System TASK NUMBER: 4880060101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAr UNSAT Page 18 of 23

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power.

2. "A" Control Room Ventilation train is in service.

3. The Aux Building Operator has been briefed and is standing by on location.

INITIATING CUE:

You are the Plant Operator.

Swap Control Room Ventilation to "8" Train lAW HC.OP-SO.GK-0001.

Page 19 of 23

TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to 100% power, MOL.

ENSURE Band D SACS Pumps in service supplying TACS and in AUTO.

SWAP TSC HVAC to place B train in service.

ENSURE C SACS Pump in service and in AUTO.

ENSURE A SACS Pump stopped and in AUTO .

ENSURE a copy of HC.OP-SO.GK-0001 is available.

ENSURE a copy of HC.OP-AB.HVAC-0001 is available.

COMPLETE "Simulator Ready-for-Trainlng/Examination Checklist".

EVENT ACTION:

COIVIMAND:

PURPOSE:

Page 20 of 23

TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 21 of 23

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: GK002 Rev # Date Description Validation Reguirad?

00 5/26/10 New Alternate Path JPM. Validated with 2 RO's. Added to cue Y sheet: "3. The Aux Building Operator has been briefed and is standing by on location." Average validation time 18 minutes.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Redundant Reactivity Control TASK: Defeat ARI Interlocks TASK NUMBER: 2000720504 JPM NUMBER: 305H-JPM.SA001 REV #: 10 SAP BET: NOH05JPSA01 E ALTERNATE PATH: D APPLICABILITY:

EO [ ] ] RO [ X I STA SRO [ ] ]

DEVELOPED BY: Archie E. Faulkner DATE: 4/20/10 Instructor REVIEWED BY:

~~ Operations Representative DATE: ~.:.c:c2'..6I,-,-()_

APPROVED BY:

~~Training Department DATE: 7!//i{)

STATION: Hope Creek JPM NUMBER: SA001 REV: 10 SYSTEM: Redundant Reactivity Control TASK NUMBER: 2000720504 TASK: Defeat ARI Interlocks ALTERNATE PATH: 0 KIA NUMBER: 295037 EA1.03 IMPORTANCE FACTOR: 4.1 4.1 APPLICABILITY: RO SRO EO [KJ RO [KJ STA D SRO [KJ EVALUATION SETTING/METHOD: In Plant/Simulate

REFERENCES:

HC.OP-EO.zZ-0320 Rev 4 TOOLS, EQUIPMENT AND PROCEDURES:

EOP-320 Implementation Kit specified in Section 4.0 of HC.OP-EO.ZZ-0320 ESTIMATED COMPLETION TIME: 9 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: __N_/A _ _ Minute~;

JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ*AA~1 06-0303 NAME:

DATE:

SYSTEM: Redundant Reactivity Control TASK: Defeat ARI Interlocks

. TASK NUMBER: 2000720504 INITIAL CONDITIONS:

1. The plant has experienced a failure to scram.

2. All Scram Valves have opened but the Scram Discharge volume is full.

3. RPV level is being maintained at -50 inches.

4, HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

5. Draining the SDV and attempting a manual scram is required.

6. HC.OP-EO,ZZ-0302. has NOT been implemented.

INITIATING CUE:

Defeat the ARI interlocks lAW HC.OP-EO.ZZ-0320.

Page 3 of 14

TQ-~-1 06-0303 JPM: SA001 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Redundant Reactivity Control TASK: Defeat ARI Interlocks

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.zZ-0320..

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. N/A Page 4 of 14

TQ-AA-106-0303 SA001 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE: _ _ _ _ _ _ _ __

SYSTEM: Redundant Reactivity Control TASK: Defeat ARllnterlocks

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) (Required for UNSAT NO.

STANDARD 4.0 EQUIPMENT REQUIRED Examiner Note: After operator has demonstrated ability to obtain required equipment, ensure that the equipment is retumed to its appropriate storage location.

4.1 EOP-320 Implementation kit (OS office EOP drawer) Operator obtains the following required Contents: 1 set of fuse pullers equipment:

1 flashlight EOP-320 Implementation kit from SM 1 plastic bag for ARI fuses Office Clerk Area EOP drawer.

4 banana plug jumpers OR OR 4.2 Key #9 for EOP Locker in OSC (obtain from OS office or break red key holder glass in OSC).

Key #9 from SM office or key from AND break glass key holder in OSC for OSC EOP locker.

EOP-320 Implementation kit (EOP Locker in OSC) AND Contents: 1 of fuse pullers EOP-320 Implementation kit from EOP 1 flashlight locker in OSC.

1 plastic bag for ARI fuses 4 banana plug jumpers Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.1.

Page 5 of 14

TQ-AA-106-0303 JPM: SAOOi OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Redundant Reactivity Control TASK: Defeat ARllnterlocks

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation 5.1 Oefeatina ARI Interlocks N/A NOTE Execution of the following steps will defeat all automatic and manual RRCS ARI functions and cause all RRCS ARI valves to close and remain N/A closed. ARI valve position indication will be retained.

5.1.1 ENSURE that Prerequisites have Operator ensures that all prerequisites been satisfied lAW Section 2.1. have been satisfied.

CUE If excessive time is taken reviewing prerequisites, inform operator that all are satisfied. N/A Page 6 of 14

TQ-I"iA-106-0303 SA001 OPERATOR TRAINING PROGRAM NAME: -----'---

Rev: 10 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Redundant Reactivity Control TASK: Defeat ARJ Interlocks

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD StU evaluati REMOVE the following fuses in Local Panel 1OC601 (Aux Bldg elev. 163',

RRCS Panel, front center section, iower door) (see Attachment 3):

F268 C22A-F6A Operator removes fuse F268

C22A-F6A in 10C601.

Operator removes fuse F267 *.

F267 C22A-F5A C22A-F5A in 10C601.

CUE "The fuses you indicated are removed." N/A Page 7 of 14

TQ-AA-106-0303 JPM: SA001 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Redundant Reactivity Control TASK: Defeat ARI Interlocks

(*Denotes a Critical Step)

COMMENTS STEP (#Denotes a Sequential Step)

ELEMENT EVAL (Required for UNSAT NO. #

STANDARD S/U 5.1.3 ENSURE the following RRCS ARI Operator observes the GREEN Valves are CLOSED. CLOSED indicator is illuminated and (Local indication on 1OC60i, Green the RED OPEN indicator is extinguished for the following valves:

when CLOSED):

C11-F160A

C11-F160A

C11-F162A

C11-F162A

C11-F162C

C11-F162C

C11-F163A

C11-F163A CUE "The green CLOSED indicator is illuminated and the red OPEN indicator is extinguished for the N/A valve(s) you indicated."

Page 8 of 14

TQ-AA-106-0303 JPM: SA001 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Redundant Reactivity Control TASK: Defeat ARllnterlocks STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD I EVAL S/U COMMENTS (Required for UNSAT evaluati 5.1.4 REMOVE the following fuses in Local Panel10C602 (Aux Bldg elev. 163',

RRCS Panel, front center section, lower door) (see Attachment3):

F267 C22A-F5B Operator removes fuse F267

C22A-F5B in 10C602.

F268 C22A-F6B Operator removes fuse F268

C22A-F6B in 10C602.

CUE "The fuses you indicated are removed." N/A Page 9 of 14

TQ-hA-106-0303 JPM: SAOOi OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Redundant Reactivity Control TASK: Defeat ARllnterlocks

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu evaluation) 5.1'.5 ENSURE the following RRCS ARI Operator observes the green CLOSED valves are CLOSED indicator is illuminated and the red (Local indication on 10C602, Green OPEN indicator is extinguished for the valves:

when CLOSED):

C11-F160B

C11-F160B

C11-F162B

C11-F1628

C11-F162D

C11-F162D

C11-F163B

C11-F163B CUE "The green CLOSED indicator is illuminated and the red OPEN indicator is extinguished for the N/A valve(s) you indicated:'

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status ofthe JPM, and then state "This JPM is complete",

STOP TIME:

Page 10 of14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: SA001 TASK: Defeat ARI Interlocks TASK NUMBER: 2000720504 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 11 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced a failure to scram.

2. All Scram Valves have opened but the Scram Discharge volume is full.

3. RPV level is being maintained at -SO inches.

4. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

S. Draining the SDV and attempting a manual scram is required.

6. HC.OP-EO.ZZ-0302 has NOT been implemented.

INITIATING CUE:

Defeat the ARI interlocks lAW HC.OP-EO.zZ-0320.

Page 12 of 14

TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: SA001 Rev# I Date Description Validation Required?

09 7/31/07 Revision 3 of HC.OP~EO.ZZ~0320 added the text "Green when N CLOSED" to steps 5.1.3 and 5.1.5 with NO change in action steps. JPM SA001 updated to reflect this. JPM already contained examiner cues for these steps. No change in actions, i validation not required.

Converted ",IPM SAOOi to new JPM format. This change is editorial, validation not required.

Added Note text to Element section. This is for examiner reference only and has no associated student actions. This change is editorial, validation not required.

10 4/20/10 Updated reference procedure revision number. Revised N estimated completion time to 9 minutes based on 2008 LOR performance times. No changes to operator actions. No

~----.

validation required.

I I

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504 JPM NUMBER: 305H-JPM. BE002 REV #: 10 SAP BET: NOH05JPBE02E ALTERNATE PATH: D APPLICABILITY:

EO D RO [KJ STA [KJ .SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 4/20/10 .

Instructor REVIEWED BY:

Operations Representative APPROVED BY: 9n~

Training Department DATE: ~o______

TQ*AA*106*0303 STATION: Hope Creek JPM NUMBER: BE002 REV: 10 SYSTEM: Core Spray TASK NUMBER: 2000530504 TASK: . Perform Torus Makeup Via Core Spray System ALTERNATE PATH: c==J ~ANUMBER: ___2_9_50_3_0_E_A_1._06_ __

IMPORTANCE FACTOR: 3.4 3.4 APPLICABILITY: RO SRO EO D RO [KJ STA [ ] ]

EVALUATION SETTING/METHOD: Reactor Building/Simulate

REFERENCES:

HC.OP-EO.zZ-0315 (0) Rev. 5 tfI!ii'f.

TOOLS, EQUIPMENT AND PROCEDURES:. None ESTIMATED COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

- -N/A

--- Minutes JPM PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 13

TQ*AA-106*0303 NAME:

DATE:

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504 INITIAL CONDITIONS:

1. A leak on the '0' RHR Pump suction line has lowered suppression pool level to 73 inches.

2. The leak has been isolated ard suppression pool level is stable.

INITIATING CUE:

Make-up to the Suppression Chamber from Core Spray Loop B lAW HC.OP-EO.ZZ-0315 Page 3 of 13

TQ-.f\A-106-0303 JPM: BE002 OPERATOR TRAINING PROGRAM NAME:

Rev; 10 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD SJU evaluatio CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains/locates procedure Operator obtains the correct procedure.

HC.OP-EO.ZZ-031 Operator reviews precautions and Operator reviews precautions and limitations. limitations.

1-----+---

CUE Examiner Cue: If excessive time is N/A taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 1.

~-~-------

Page 4 of 13

TQ-rir\-106-0303 BE002 OPERATOR TRAINING PROGRAM Rev: 10 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD stu evalu 4.0 EQUIPMENT REQUIRED Operator obtains the following required equipment:

1 Key #9 for EOP Locker in OSC (obtain from OS office or break 1. Key #9 for EOP locker in OSC red key holder glass in OSC (obtain from OS office or break red key holder glass in OSC)

AND EOP-315 implementation kit from EOP-315 Implementation Kit EOP locker in OSC (EOP Locker in OSC) Examiner Note: After operator has Contents: 1 Wire Cutter demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location.

5.1.1 ENSURE that all prerequisites have. Operator ensures that all prerequisites been satisfied lAW Section 2.1. have been satisfied.

CUE If excessive time is taken reviewing N/A prerequisites, inform operator that all are satisfied.

Page 5 of 13

TQ-J.V\-106-0303 JPM: BE002 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE: ______________----

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD Stu evaluation)

CAUT The SM/CRS shall be aware of, and Operator reads CAUTION.

take into consideration, the environmental and radiological conditions that exist in areas requiring entry prior to dispatching personnel into the field.

Adequate core cooling takes precedence over suppression pool make-up. See HC.OP-AB.ZZ-0155, Attachment 3 for direction on aligning Core Spray B to make-up to the RPV from the CST. Use of Core Spray with suction from the CST injecting to the RPV meets the intent of this procedure.

UNLOCK AND OPEN 1-AP-V068 Operator locates 1-AP-V068, Cond Stor IICond Stor & Xfr to Core Spray Pump and Xfr to Core Spray Pump B & D 5.1.2 Suction Fill & Flush Isln Valve on the 77 Band D Suction Fill & Flush Isln Vlvll.

(local, Room 4203 reactor building, ft. elevation of the Reactor building.

elevation 77')

Operator simulates UNLOCKING

1-AP-V068. #

- - .-----~---- .

Page 6 of 13

TQ-AA-106-0303 JPM: BE002 OPERATOR TRAINING PROGRAM NAME:

Rev: 10 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - - -

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT {#Denotes a Sequential Step} EVAL {Required for UNSAT NO. #

STANDARD S/U evaluation}

Operator simulates OPENING 1-AP-

V068, by turning the hand-wheel in the counterclockwise direction until the hand-wheel reaches a hard stop.

<XXX: 000 OO<X ~

CUE The valve you indicated is N/A

~

unlocked and open. ~

~

5.1.3 ENSURE the following (PANEL C650) Operator contacts Control Room and are OPEN: directs Control Room Operator to verify OPEN HV-F001 Band HV-F001 D.

A. HV-F001 B CS Pmp B Suct Isln MOV B. HV-F001D CS Pmp 0 Suet Isln MOV Examiner Note: Operator may verify ~

these valves OPEN before leaving the Control Room Area.

CUE Respond as the MCR, HV-F001 B N/A ~ :88 and HV-F001 D are open.

~

~ ~

Page 7 of 13

~---.---

TQ-~A-1 06-0303 JPM: BE002 OPERATOR TRAINING PROGRAM NAME: ___________________

Rev: 10 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD SJU evaluation) 5.1.4 UNLOCK AND THROTTLE OPEN Operator locates BE-V058 CS Pmps B one OR both of the followina valves to & D Suct X-Tie Isln Vlv (Reactor obtain the desired fill rate building, elevation 54' B CS Pump monitoring CST and Torus levels Room)

(local, reactor building, elevation 54'): and/or BE-V059 CS Pmps B & D Suct X-Tie Isln Vlv (Reactor building, elevation 54' D CS Pump Room)

Examiner Note: It is critical to unlock I N/A and open at least one of the following two valves.

BE-V058 CS Pmps B & D Suet X-Tie Operator simulates UNLOCKING

1-BE-V058.

Operator throttles open BE-V058 by

turning the hand-wheel counterclockwise until flow is heard.

CUE (As appropriate) The valve you indicated is throttled open. Flow N/A can be heard past the valve(s).

Page 8 of 13

TQ-MA-106-0303 JPM: BE002 OPERATOR TRAINING PROGRAM NAME: -------------------

Rev: 10 JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Core Spray TASK: Perform Torus Makeup Via Core Spray System

(*Denotes a Critical Step) COMMENTS STEP

(#Denotes a Sequential Step)

EVAL (Required for UNSAT ELEMENT NO. STANDARD # S/U evaluation)

BE-V059 CS Pmps B & D Suct X-Tie Operator simulates UNLOCKING

Isln Vlv 1-BE-V059.

Operator throttles open BE-V059 by

turning the hand-wheel counterclockwise until flow is heard.

(As appropriate) The valve you ~

CUE indicated is throttled open. Flow N/A WS R% <5<S<

can be heard past the valve(s).

RSlSI R\X ~

Operator informs Control Room that Suppression Chamber makeup is in progress.

~

CUE If operator informs Control Room, I N/A provide Terminating Cue.

CUE WHEN operator informs you the task is complete, ~

OR the JPM has been terminated for

~

other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". ~

STOP TIME: ~

Page 9 of 13*

TQ*AA*106*0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: BE002 TASK: Perform Torus Makeup Via Core Spray System TASK NUMBER: 2000530504 QUESTION:

- -......* - - - - - - ---~--------------------- ----

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT . , - - I_ _---1 UNSAT Page 10 of 13

TQ*AA*106*0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A leak on the '0' RHR Pump suction line has lowered suppression pool level to 73 inches.

2. The leak has been isolated and suppression pool level is stable.

INITIATING CUE:

Make-up to the Suppression Chamber from Core Spray Loop B lAW HC.OP-EO.ZZ-0315 Page 11 of 13

TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: BE002 Rev # Date Description Validation Required?

08 9/3/2008 Revised to new JPM format. Revalidated JPM time. Y Updated reference procedure revision number. Operator actions did not change.

Added missinQ 5.1.4.B element for BE-V059.

9 9/9/09 Added Caution at step 5.1.1. Updated reference procedure N revision number. Operator actions did not change. Re-validation not required.

10 4/20/10 Revised estimated completion time based on 2009 LOR N performance. Split-out operator action and observation elements. Operator actions did not change. Validation not required.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Emergency Diesel Generators TASK: Manual Emergency Start A DG from the Local Panel TASK NUMBER: 2640180104 JPM NUMBER: 305H-JPM.KJ003 REV #: . 14 SAP BET: NOH05JPKJ03E ALTERNATE PATH: D APPLICABILITY:

EO 00 RO 00 STA SRO 00 DEVELOPED BY: Archie E. Faulkner DATE: 101'1/09 Instructor REVIEWED BY:

~~ Representative APPROVED BY: DATE: 711110 I

Training Department

TQ-AA-'106-0303 STATION: Hope Creek

..IPM NUMBER: KJ003 REV: 14 SYSTEM: Emergency Diesel Generators TASK NUMBER: 2640180104 TASK: Manual Emergency Start A DG from the Local Panel ALTERNATE PATH: D KiA NUMBER: 295003 A1.02 IMPORTANCE FACTOR: 4.2 4.3 i APPLICABILITY: RO SRO EOW ROW STA SROW EVALUATION SETTING/METHOD: Plant/Simulate

REFERENCES:

HC.OP~SO.KJ-0001 Rev. 54 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-SO.KJ-0001 ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: _ _ N/_A_ Minutes JPM PERFORMED BY:

GRADE: 0 SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 11

TQ-AA~106-0303 NAIVIE: _ _ _ _ _ _ _ _ _ __

DATE: ______________________

SYSTEM: Emergency Diesel Generators TASK: Manual Emergency Start A DG from the Local Panel TASK NUMBER: 2640180104 INITIAL CONDITIONS:

1. A Loss of Offsite Power has occurred.

2. The Reactor is shutdown. All rods are full in.

3. HC.OP-AB'.ZZ-0135 is being implemented.

4. 1AG400 Diesel Generator has failed to start, but all other EDGs have started and loaded onto their respective buses.

INITIATING CUE:

Start 1AG400 Diesel Generator from local panel 1AC421 (102' EI.).

Page 3 of 11

TQ-AA-106-0303 JPM: KJ003 OPERATOR TRAINING PROGRAM NAME:

Rev: 14 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Diesel Generators TASK: Manual Emergency Start A DG from the Local Panel

(. Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluati CUE I PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME =--=-.:.-==-..::

Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains procedure Operator obtains the correct HC.OP-SO.KJ-0001.

procedure.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, N/A THEN INFORM operator that all are satisfied.

Operator determines beginning step Operator determines correctbeginning of the procedure. step to be 5.5.1.

Page 4 of 11

TQ-~-1 06-0303 JPM: KJ003 OPERATOR TRAINING PROGRAM NAME:

Rev: 14 JOB PERFORMANCE MEASURE DATE: _______________

SYSTEM: Emergency Diesel Generators TASK: Manual Emergency Start A DG from the Local Panel

(. Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluatio NOTE All Operations are performed at Local Operator reads NOTE.

Engine Control PaneI1A(B,C,D)C 421 EI. 102'.

5.5.1 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.5 are satisfied. have been satisfied.

CUE IF excessive time is taken reviewing prerequisites, THEN INFORM operator that all are satisfied.

5.5.2 OBTAIN key #51 KIRK- Diesel Emg Takeover/Local Cant., from Operator obtains key #51 from Work Work Control Center for the Control Center.

REM/LOC/MAINT CONTROL SELECT Switch at PaneI1A(B,C,D)

C421 EI. 102'.

Examiner Note: Once the trainee demonstrates where to obtain the required key, key use '.vill be simulated.

,j I Page 5 of 11

TQ-AA-106-0303 JPM: KJ003 OPERATOR TRAINING PROGRAM NAME:

Rev: 14 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Emergency Diesel Generators TASK: Manual Emergency Start A DG from the Local Panel

(. Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

NO. of a Critical Step) EVAL (Required for UNSAT STANDARD ELEMENT

S/U NOTE I Manual operations performed from Local Engine Control Panel 1A(8,C,O)C-421 EI. 102' are not Operator reviews NOTE.

taken-over by an auto-initiation signal.

5.5.3 PLACE REM/LOC/MAINT CONTROL .Operator simulates inserting the key

SELECT Switch in LOCAL. and placing A EDG REM/LOC/MAINT CONTROL SELECT Switch in LOCAL.

CUE The control you have indicated is N/A in the position stated.

5.5.4 PLACE LOCAL ENGINE CONTROL Operator places LOCAL ENGINE Switch in START. CONTROL Switch in START.

CUE The control you have indicated is in the position stated. The Diesel engine is running. N/A 5.5.5 OBSERVE that DIESEL RUNNING Operator identifies the DIESEL NOT LOADED comes ON. RUNNING NOT LOADED indicating light.

Page 6 of 11

TQ-I-V\-106-0303 JPM: KJ003 OPERATOR TRAINING PROGRAM NAME: - - - - -

Rev: 14 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generators TASK: Manual Emergency Start A DG from the Local Panel

(. Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) (Required for UNSAT NO. STANDARD ELEMENT CUE The indication you have identified is lit. N/A 5.5.6 INFORM Control Room that 1AG400 8G400, 1 CG400, 1DG400) Diesel Operator notifies the Main control Generator is running. Room that the A EDG is running.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT 6ACK any message from I N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 7 of 11

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: KJ003 TASK: Manual Emergency Start A DG from the Local Panel TASK NUMBER: 2640180104 QUESTION:

-~----------- --------------------------------------------------

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 8 of 11

TQ-AA-106*0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A Loss of Offsite Power has occurred.

2. The Reactor is shutdown. All rods are full in.

3. HC.OP-AB.zZ-0135 is being implemented.

4. 1AG400 Diesel Generator has failed to start, but all other EDGs have started and load ed onto their respective buses.

INITIATING CUE:

Start 1AG400 Diesel Generator from local panel1AC421 (102' EI.).

Page 11 of 11

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: KJ003 I Rev# Date Description Validation i i Reguired?

~

I 13 10/1/09 Converted JPM KJ003 to new JPM format. Validated with 2 operators from A Shift. Avg completion time is 20 minutes. *...

14 4/20/10 Revised estimated completion time to 12 minutes based on N average 2009 LOR performance times. Deleted Simulator setup instructions which are not used for an In-Plant JPM. Revised reference procedure revision number. No operator actions

GhCIII~tiU. No validation required, ...

Page 9 of 11

SIMULATOR SCENARIO TITLE: NRC SCENARIO 1 SCENARIO NUMBER:

EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 50-60 minutes REVISION NUMBER: 01 PROGRAM: '-------'

L.O. REQUAL INITIAL LICENSE

'---_---'10TH ER REVISION

SUMMARY

1. Added spurious trips of all 3 RFTS when reactor is scrammed to begin inventory loss from a lower level per Chief Examiner request.

2. Change HPCI from being tagged to HPCI fails to initiate. Added Malfunction HP04.

PREPARED BY: Archie E. Faulkner 8/2/10 Instructor DATE APPROVED BY:

aMi L T Group Lead or Designee ?f fitE='-O--

APPROVED BY:

th40 DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Critical tasks within this examination scenario guide are identified with an " *.")

A. Raise Reactor Power with Control Rods B. Swapping In-Service SJAE's C. APRM D Failure Upscale D. Main Steam Line Pressure Transmitter N076D failure E. SJAE B Malfunction F. Loss of Main Condenser Vacuum with Reactor Feed Pump trips G. LOP wI EDG B failure H. EDG A Fails to Auto Start I. HPCI F001 failure to open.

J. RCIC Overspeed The scenario starts with the plant at approximately 90% power. The crew will withdraw Control Rods to 95% power. The crew will commence swapping SJAE's. During the rod withdrawal, D APRM will fail upscale. The crew will bypass the APRM and reset RPS. The CRS will enter the appropriate Tech Specs. After the reactivity manipulation, Main Steam Line Pressure transmitter N076D will fail high resulting in a Tech Spec entry. At the end of the SJAE swap, the oncoming SJAE will malfunction, combined with a loss of Main Condenser vacuum requiring the unit to be shutdown. When the reactor is scrammed, all Reactor Feed Pumps will spuriously trip. A LOP will occur after the Main Generator trips off-line. EDG A will fail to auto start, requiring manual action to initiate containment cooling. EDG B will fail completely. HPCI FOOi will not respond automatically or manually. RCIC Turbine will trip on overspeed requiring manual operator action to restore high pressure injection. The scenario will be terminated when reactor level is controlled above 61 inches and Suppression Pool Cooling is in service.

ESG-NRC-S1 Page 2 of 27 Rev.: 01

W/R Reactor Pressure

Main Condenser pressure COMPLETE the Simulator Ready for Training/Examination Checklist.

PRE-BRIEF the crew for the power change and SJAE swap.

ESG-NRC-S1 Page 3 of 27 Rev.: 01

MC01 leak to 10% and inserts RCIC trip on Overspeed.

&& ZLEG65T II Both Main Gen Output Breakers open EVENT ACTION:

COMMAND:

PURPOSE:

ESG-NRC-S1 Page 4 of 27 Rev.: 01

MS09D Steam line header pressure transmitter N076D fails MC01 Low pressure turbine exhaust bellows leak i FW26A Feedwater ump turbine AS10S trip FW268 Feedwater pump turbine AS1 OS tri i FW26C Feedwater pump turbine AS10S trip ET-5 filter BF201 clo ging PP04 OD-3 Crossflow

, AN28 CROSSFLOW ALARMITRBL ET-6 NORM AN17 A4-F3 Off Gas Recomb Pnl OOC327 ET-8

!---1.~-------

NORM

... - - - ... - - - - - - - j - . - - - - - f - - - - - f - - = ' - - . : : : . - + - - . - f - - ' - ' - ' ' ' - ' - - ' ' - ' - ' -

. EP36 EOP-323, Bypass BC-HV-F015A isolation

interlocks 11 :00 ET-10 BYPASS EP37 EOP-323, Bypass BC-HV-F01S8 isolation interlocks 11 :00 ET-10 BYPASS CD02 Pump B discharge valve V008 position (0 i

, 100%) ET-11 CRD FCV A ET-12 ESG-NRC-S1 Page 5 of 27 Rev.: 01

V. SCENARIOGUIDESEQUENCE ANDEXPECTEDRESP()NS~

.E)(p~ct~cf PI~~tlStud~ntRespons~

CRS directs the RO to raise Reactor power with Control Rods in accordance with RE guidance.

RO withdraws Control Rods in HPI USED:

accordance with HC.OP-SO.SF STAR 0 0001 and CRS directions. PEER CHECK 0

=:> Selected rod PB comes ON OP BARFUERS 0 (bright white).

=:> CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod position (1 OC650C).

=:> The associated Full Core Display (white) numbered rod identification light comes ON (10C650C).

NOTE: Operator may single

At the ROD SELECT MODULE, notch withdraw the rods, as press the WITHDRAW PB necessary, in which case the and observe the following:

CONTINUOUS WITHDRAW =:> The INSERT (white) light PB is NOT used. comes ON momentarily.

The WITHDRAW (white) light comes ON.

=:> CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod movement.

The WITHDRAW (white) light goes OUT.

=:> The SETTLE (white) light comes ON for::::; 6 seconds, then goes out.

ESG-NRC-S1 Page 6 of 27 Rev.: 01

.SCENARIO GUIDESEQUENCEANDEXPECTED

, " " ',' - .. - " - - -" -, - /-:, '" - - . - -

RESPONS.

E

. Expect~cI el~htlStud~ntkeiponse ,

CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod has settled to the desired position.

RO indicates the completion of the movement on the Pull Listing.

'D'APRMUpscaU~

RO monitors Reactor power, After the2hd contfbl' rod is pressure, and level and ensure

~ithdt~VJn<6rar~7.~d*.* *.*. '. ...*. . ' plant conditions are stable.

Examiner's descretion, TH EN Ensures no scram setpoints have rT~!GGtR~~?-~f*' .......... ,.. . been exceeded.

! _ :_:"_ - _'.-' - :":"i,--"-,', r ',',,'-.

Crew recognizes RPS }2 scram by:

=> OHA C3-A5 "REACTOR SCRAM TRIP LOGIC 82"

=> OHA C5-A 1 "NEUTRON MONITORING SYSTEM" RPS Trip Logie 82 NORMAL/RESET status lights extinguished

=> Pilot Scram Valve Solenoid LOGIC 8 NORMAL status lights for all four groups extinguished.

Crew recognizes 'D' APRM Upscale by:

=> OHA C3-C5 "APRM SYS 8 UPSCALE TRIPIINOP"

=> C3-D4 "APRM UPSCALE" APRM 0 "UPSC TR OR INOP" status light

=> APRM D "UPSC ALARM" status light

=> APRM 'D' indicating 125% on 10C650 and CRI DS

Crew terminates control rod Immediate Operator withdrawal. Action lAW A8.IC-0004.

HPI USED:

STAR 0 ESG-NRC-S1 Page 7 of 27 Rev.: 01

RO observes normal indications on the other APRM's and reports that "0" APRM has failed upscale.

RO refers to AR.ZZ-0009 alarm response procedure for OHA C3 C5 and the associated digital alarm point response procedure for 02444.

CRS enters AB.IC-0004:

~ Condition B

CRS references AB.IC-0003:

~ Condition B

RO informs the CRS to ensure compliance with Tech Spec 3.3.1.

CRS reviews Technical Specifications 3.3.1 for RPS Instrumentation, 3.3.6 for Rod Block Instrumentation AND 3.3.11.a OPRMS.

CRS determines that the "0" APRM can be bypassed and only a tracking LCO is needed since the minimum number of APRMs per trip system remain operable for both the RPS, Rod Block, and OPRM functions.

CRS directs the RO to bypass the "0" APRM.

RO places APRM RPS TRI P HPI USED:

CHANNEL A(B) MONITOR STAR 0 BYPASS joystick in "0" APRM PEER CHECK 0 position.

ESG-NRC-S1 Page 8 of 27 Rev.: 01

r V. SCENARIO GUIDI; SEQUENCE ANDEXPECTEDRESPONSE

. Event I InstruaorActivity ExpebtedPI~ritlStuaenl Respol1s~

RO resets the "B" channel Y2 scram.

RO resets alarms as applicable.

RO reports that the "0" APRM is bypassed and that the Y2 scram is reset.

CRS contacts /&C OR Work Control to initiate corrective action to repair the "0" APRM.

CRS directs the RO to continue with Group 9B control rod withd raw of the Reactor Engineering Pull Sheet.

RO pulls the next two control HPJ USED:

rods from position 00 to position STAR 0

08. The RO monitors control rod PEER CHECK 0 position and NI response during OP BARRIERS 0 rod withd raws.

CRS directs the PO to swap the SJAE to "B" in accordance with HC.OP-SO.CG-0001 starting at 5.4.3.1

PO commences swapping SJAE in accordance with CRS directions by:

=;> AFTER 30 minutes, OPEN HPJ USED:

lAW the Turnover Sheet, >30 HV-1956B - AIR EJECTOR STAR 0 minutes has elapsed.

"B" JET SUCT 3RD STAGE. PEER CHECK 0 FLAGGING 0 MONITOR the following Air Ejector 3rd Stage parameters for appropriate response while bringing the SJAE on line. (1 OC650A):

ESG-NRC-S1 Page 9 of 27 Rev.: 01

f V. SCENARIOGUI DE SEQUENCE AND . EXPECTEDRESPONSE Ev~nt I InstructorActivity o 3rd Stage Suction flow (rising) as indicated on FR-20218 - SJAE 3rd STAGE SUCTION FLOW.

o 3rd Stage Suction pressure (lowering) as indicated on PI-19548 SJAE TRAIN "8" PRESSURES STG 3 SUCT.

= OPEN HV-19638 AIR HPI USED:

EJECTOR "8" SECOND STAR 0 STAGE JET STM INLET. PEER CHECK 0 FLAGGING 0 If requested, Operators have

= DIRECT a Qualified Operator, or Maintenance (I&C) been briefed and are standing personnel to adjust PIC-by.

20188 SJAE "8" Main Stm Supply Pressure Control Valve, as necessary to control steam pressure 145 to 150 psig during warm-up.

OPEN HV-19628-AIR HPI USED:

EJECTOR "8" SECOND STAR 0 STAGE ,JET SUCT. PEER CHECK 0 FLAGGING 0 08SERVE SJAE 2nd Stage Suction pressure decreasing on PI-19668 SJAE TRAIN "8" PRESSURES STG 2 SUCT (10C650A).

= OPEN HV-19678 - AIR HPI USED:

EJECTOR "8" FIRST STAGE STAR 0 JET STM INLET. PEER CHECK 0 FLAGGING 0 ESG-NRC-S1 Page 10 of 27 Rev.: 01

SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE .

Event I Jnstructor'Aclivity HPJ USED:

STAR 0 PEER CHECK 0 FLAGGING 0

=> DIRECT a Qualified Operator, or Maintenance (I&C) personnel to adjust PIC 20188 SJAE "8" Main Stm Supply Pressure Control Valve, as necessary, to control steam pressure 145 to 150 psig during warm-up.

NOTE:

Closing the following valves will isolate the "A" SJAE from the Main Condenser. IF Condenser vacuum begins dropping rapidly, they may be re-opened to restore flow.

CLOSE HV-1968 A1, A2, A3 HPJ USED:

AIR EJECTOR "Al! FIRST STAR 0 STAGE JET SUCT. PEER CHECK 0 FLAGGING 0 NOTE:

Gaseous Radwaste System flow may be monitored using the following indications:

A3431 RECM8 OFF-GAS FLOW TO HOLD PIPE

1HAFI-5665 HOLD UP PIPE OUT FLOW

A9343 OFF-GAS TREATMENT DISCHARGE FLOW

=> ADJUST PIC-19648 AIR EJECTOR "8" EXH PRESS, as necessary to maintain SJAE 3rd Stage Outlet < 11 pSig, AND flow through the Gaseous Radwaste System <

75 scfm (1900 #/hr).

ESG-NRC-S1 Page 11 of 27 Rev.: 01

SCENARIO GUU:UfSEQUENCEANDEXPECTEr.)RESPONSE*

PT-N076DFailure:

Crew recognizes '0' NSSSS After the Crew assumes the instrument failure by:

watch and atthe discretion of OHA C8-B5 "NSSSS OUTBO the Lead Examiner, TRIGGER ISLN SYS OUT OF SVCE" ET-2 CD' NSSSS* MSL ~ Amber NSSSS CH 0 "TRIP Pressure Transmitter Fails UNIT IN CAL OR GROSS High). FAIL" light CRIOS D2665 "MSIV INBO SYS OUT OF SVCE CH 0"

~ CRIOS D2666 "NON-MSIV INBO SYS OUT OF SVCE CH 0"

RO/PO reference ARP.

Crew inspects 10C611 panel trip This will prevent the '0' units and finds B21-N6760 is I\lSSSS Channel from failed upscale with a Gross Fail generating an MSIV Trip in. isolation sig'lal on Low Main Steam Line pressure.

Transmitter is located in TB

Crew contacts Maintenance to Electrical Mezzanine. troubleshoot.

LE dispatched to transmitter, THEN REPORT there is no visible damage to transmitter.

CRS recognize the following T/S TIS Table 3.3.2-1 Trip applies Function 3c.

=;. Isolation Actuation Instru mentation 3.3.2 action b.1.c applies (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to place in a tripped condition).

If requested, after an

Crew may implement HC.OP appropriate delay, support GP.ZZ-0011 to place trip units actions of placing trip units in into tripped condition.

tripped condition by changing MALF MS09D severity to O.

ESG-NRC-S1 Page 12 of 27 Rev.: 01

'I. " .

SCENARIO GUIDE SEQUENCE AND EXPECliD RESPONSE .....

',. EVe,nt II ostructor Activ~ty HV-2016B Failure Closed:

Crew recognizes 'B SJAE After the B SJAE is in service malfunction by:

and at the discretion of the => aHA A4-02 "SJAE B 3RO Lead Examiner, STAGE STM FLOW La" TRIGGER ET-3 (HV-2016B drives closed.)

This renders B SJAE ineffectlve. Main condenser vacuum will slowly de rade.

CRS implements AB.BOP-0006:

=> Condition A

=> Condition B

PO implements AB.BOP-0006:

=> Condition A

=> Condition B

=> Recognizes HV-2016B closed

=> NOTI FY The Radwaste Operator

=> VERI FY Offgas is in-service.

=> PLACE the standby SJAE in service lAW EITHER of the following:

AB-0001

SO.CG-0001.

CRS directs PO to place standby SJAE in -service.

PO opens HV-1968 A1, A2, A3. HPI USED:

STAR 0 ESG-NRC-S1 Page 13 of 27 Rev.: 01

Loss of Vacuum:

Crew recognizes elevated After A SJAE is placed in condenser in-leakage and service, ORat the Lead degrading vacuum by:

Examiners discretion, Lowering Main Gen MWe TRIGGER ET-7 (Main => OHA A4-F3 "OFFGAS Condenser Exhaust Boot RECOMB PNL OOC327" Leak). => RM11 9AX343 Offgas Flow alarm CRIDS A9343 "OFFGAS TREATMENT DISCHARGE FLOW" rising Various Main Condenser vacuum indications degrading

CRS implements AB.BOP-0006:

Condition A

=> Condition G IF dispatched to Off Gas,

Crew dispatches RWEO to Off THEN TRIGGER ET-8 to Gas.

ACKNOWLEDGE the alarm AND REPORT there is a "High Gas Flow to Holdup Pipe" alarm in on OOC327. Flows and dip's throughout the system are abnormally high.

RO reduces power as necessary Immediate Operator to maintain the MAIN Action lAW CONDENSER VACUUM LO AB.BOP-0006.

alarms clear lAW SPRI.

HPI USED:

STAR 0 IF directed to check

Crew verifies Condensate Drain Condensate Drain Tank level Tank levels controlling properly.

controllers, (Condensate Drain Tank Level THEN REPORT Condensate can be seen on CRIDS Page 19)

Drain Tank level controllers are working properly.

ESG-NRC-S1 Page 14 of 27 Rev.: 01

EjcpectedPI~ntJstJdent .* R,~~~onse I

lE directed to check position of

Crew directs RBEO to verify the RC-V005, RC-V005 is aligned to CRW.

THEN REPORT it is aligned to CRW.

IF directed to verify proper

Crew directs Chemistry to verify HWCI operation, proper operation of HWCI.

THEN REPORT HWCI is (HWCI flows can be seen on operating properly. CRIDS Page 231).

IF directed to place a water

Crew directs NEO to place water seal on Vacuum Breakers and seal on Vacuum Breakers and Condenser Neck Seals, Condenser Neck Seals.

THEN OBTAIN AB.BOP-0006 Att 2 and REPORT actions after appropriate time delays.

CRS determines condenser Retainment Override in pressure cannot be maintained AB. BOP-0006.

< 6.5" HgA and directs:

=> Reducing recirc pumps to minimum speed Locking the Mode Switch in SHUTDOWN NOTE: When the reactor is HPI USED:

RO scrammed, main condenser Reduces recirc pumps to STARD vacuum leak increases severity minimum speed to 10% and Reactor Feed => Locks the Mode Switch in pumps will trip. SHUTDOWN

RO performs scram actions lAW HPI USED:

AB.ZZ-0001 Attachment 1. STARD HARD CARD D

CRS implements EOP-101.

ESG-NRC-S1 Page 15 of 27 Rev.: 01

. Event rl[1~trucf()rActivity .*. .~xpectedPlantlStuderl!iResponse \.

LOP with EDG Failures:

Crew recognizes Loss of Offsite When the Main Generator Power by:

output breakers are opened =; OHA "STA SERVICE after the Main Turbine trip, TRANSFORMER TROUBLE" OR, at the direction oftheLead for all transformers Examiner, =; TRIP indication for all 500 KV TRIGGER ET-S. breakers Flashing TRIP lights for all previously closed bus infeeds.

=; Numerous OVLD/PWR FAIL lights.

Crew recognizes failure of the 'A' EDG to start and load by:

=> Engine STOP light Output breaker TRI Plight

=> OVLD/PWR lights on 'A' Channel components

RO/PO start the 'A' EDG and Immediate Operator ensure it loads. Action lAW AB .ZZ-O135.

HPJ USED:

STAR 0 IF directed to locally start the

Crew starts the sA' EDG by

'A' EDG, EITHER:

THEN DELETE Malfunction Pressing the lA' EDG START DG07A. pushbutton in the Control Room, OR Directing an operator to locally start the lA' EDG.

Crew recognizes failure of the 'B' EDG to start and load by:

=> Engine STOP light

=;> Output breaker TRIP light

=> OVLD/PWR lights on 'B' Channel components ESG-NRC-S1 Page 16 of 27 Rev.: 01

SGENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE IE directed to locally start tile

RO/PO attempt to start the 'B' Immediate Operator

'B' EDG, EDG. Action lAW THEN REPORT 'B' EDG has a AB.ZZ-0135.

large lube oil pipe break and oil is all over the engine room floor. HPJ USED:

STAR 0

PO maintains RPV water level as HPJ USED:

directed by CRS lAW STAR 0 AB.ZZ-0001 Attachment 14. HARD CARD 0 NOTE: MSIVs will close on the

CRS directs maintaining reactor LOP. pressure below 1037 psig with SRVs.

RO/PO control RPV pressure HPI USED:

with SRVs as directed by CRS STAR 0 lAW AB.ZZ-0001 Att 13. HARD CARD 0

CRS directs RPV water level control with RCIC.

RCICOverspeed/HPCI F001

PO manually initiates RCIC lAW May have already faUure: ,.' 's\; ******* ****.*;;:\> AB.lZ-0001 Att. 6. initiated on RPV LVL 2 WhenRGICiDitiat~~eI!hir depending on power automati9aUyorl"rlan~ally, level at time of scram.

RCIC turbjne.~peed ,:"UI; increas~; ~ntII.,~ripping. on overspeed.,;.' ...*...*..

I.HPG1', F001wlllnoLopen.

ESG-I\JRC-S1 Page 17 of 27 Rev.: 01

Crew recognizes RCIC turbine trip by:

OHA B1-A1 "RCIC TURBINE TRIP"

} OHA B1-E2 "RCIC PUMP DISCHARGE FLOW LO"

} TURBINE TRIP SOLENOID ENGRZ status light

} HV-4282 Valve position

} CRIDS D2400 "RCIC TURBINE TRIP"

~ RCIC speed and flow indications IE dispatched to RCIC,

Crew dispatches NEO and THEN REPORT the overspeed Maintenance to RCIC.

trip linkage is tripped.

dispatched to HPCI,

Crew recognizes HPCI failure by:

THEN REPORT the F001 valve :::} HPCI F001 remains closed appears closed. after an initiation signal.

IE directed to open HV-F001

locally, THEN REPORT the valve will not move by hand.

CRS orders injection with 'A' SLC pump.

Crew starts 'A' SLC pump.

Crew may request EOP-323

WHEN RPV water level drops to implementation. If so, -129",

TRIGGER ET-10. THEI\J the Crew inhibits ADS.

ESG-NRC-S1 Page 18 of 27 Rev,: 01

Event I Il1 structorActivity Expected .PIantlSlude nt Response LE directed to align for two CRD

CRS orders injection with two CRD pumps will trip on pump injection, CRD pumps. low suction pressure THEN PERFORM the due to suction filter following: clogging.

Crew aligns CRD for 2 pump REFER to SO.BF-0001 Sect injection.

5.4.

TRIGGER ET-11 (Suction filter).

SET Remote Function for Stby CRD pump discharge valve to 0% (CD01/CD02).

REPORT Stby CRD pump ready for start.

WHEN Stby CRD is running, THEN RAMP discharge valve to 100% open.

LE directed to manually open HV-F003, THEN REPORT you have opened the valve.

(There is no function for this.)

AFTER HV-F003 is open, THEN TRIGGER ET-12.

WHEN two minutes have

elapsed, THEN MODIFY Malfunctions CD09A1B to control injection.

LE instrument air pressure is

zero, THEN REPORT the FCVs do not seem to be responding.

LE directed to reset the RCIC

Crew attempts to reset overspeed trip, AND after the overspeed trip lAW S0.8D-0001 Trip Throttle valve actuator has Section 5.7.

been closed, THEN after RPV Level 1 is

reached,

DELETE Malfunction RC01

TOGGLE Remote Function RC02 to RESET

REPORT the linkage has been re-Iatched.

ESG-NRC-S1 Page 19 of 27 Rev.: 01

SCENARIOGUI DE SEQtJENGEAN DEXPEctED~ESp6NSE***.

EventflnstrLlctor;Activity** Expected PlabtlStudentRe$pons~

Before RPV water level reaches -185" Compensated RPV Level, and without Emergency Depressurization, Crew resets RCIC Overspeed trip and uses RCtC to inject to the reactor.

PO controls RPV water level with HPI USED:

RCIC lAW AB.ZZ-0001 Att. 6. STAR 0 HARD CARD 0 As ESOC, REPORT it will take

Crew contacts ESOC for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to restore estimated time to restoration of Offsite power to Artificial Island. Offsite power.

CRS implements AB.ZZ-0135.

CRS enters EOP-1 02.

Crew places 'B' RHR in HPI USED:

Suppression Pool cooling to STAR 0 support RCICfSRV operation HARDCARD 0 lAW HC.OP-AB.ZZ-0001 Attachment 3.

CRS directs restoring PCIG to SRVs and Rx Bldg to Torus Vac Bkrs.

ROfPO restore PCIG to SRVs HPI USED:

and Rx Bldg to Torus Vac Bkrs STAR 0 lAW AB.zZ-0001 Att. 9. HARD CARD 0 PEER CHECK 0 Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when:

RPV level is being maintained above -161"

Suppression Pool Cooling is i in service ESG-NRC-S1 Page 20 of 27 Rev.: 01

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-1 04-1 01 Procedure Use and Adherence J. OP-AA-1 01-111-1 003 Use of Procedures K. HU-AA-1081 Fundamentals Toolkit L. HU-AA-1211 Briefing M. OP-AA-1 01-111-1 004 Operations Standards N. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel O. OP-AA-106-101-1001 Event Response Guidelines P. OP-AA-1 08-114 Post Transient Review Q. OP-HC-1 08-115-1 001 Operability Assessment and Equipment Control Program R. OP-HC-1 08-1 06-1 001 Equipment Operational Control S. OP-AA-1 01-112-1 002 On-Line Risk Assessment T. HC.OP-AB.BOP-0006 Main Condenser Vacuum U. HC.OP-AB.IC-0003 Reactor Protection System V. HC.OP-AB.IC-0004 Neutron Monitoring W. HC.OP-AB.ZZ-0001 Transient Plant Conditions X. HC.OP-AB.ZZ-0135 Station Blackout IILoss Of Offsite Power!! Diesel Generator Malfunction

y. HC.OP-EO.ZZ-0101 RPV Control Z. HC.oP-EO.ZZ-0102 Primary Containment Control AA. HC.OP-EO.ZZ-0323 RHR Shutdown Cooling Injection Valve Isolation Override BB. HC.OP-IO.zZ-0003 Startup From Cold Shutdown to Rated Power CC. HC.OP-SO.CG-0001 Condenser Air Removal System Operation DO. HC.OP-SO.SF-0001 Reactor Manual Control ESG-NRC-S1 Page 21 of 27 Rev.: 01

ESG-NRC-S1! 01 1.

Crew starts the 'A' EDG by EITHER:

Pressing the 'A' EDG START pushbutton in the Control Room, OR Directing an operator to locally start the 'A' EDG.

KIA 2.0 Generic Knowledges and Abilities 2.1.8 Ability to coordinate personnel activities outside of the control room RO 3.8 SRO 3.6 KIA 295003 Partial or Complete Loss of A.C. Power AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER AA 1.02 Emergency generators RO 4.2 SRO 4.3 AA 1.03 Systems necessary to assure safe plant shutdown RO 4.4 SRO 4.4 The '8' RHR pump is not available due to the failure of '8' EDG. This leaves the 'A' RHR pump as the only immediately available means of removing decay heat from the containment. Initiation of RHR for decay heat removal is one of the operator actions important to preventing core damage in our PRA. Energization of the 10A401 bus makes the 'A' SLC pump available for injection which will prolong the time before adequate core cooling will be lost and Emergency Depressurization is required.

2.

Before RPV water level reaches -185" Compensated RPV Level, and without Emergency Depressurization, Crew resets RCIC Overspeed trip and uses RCIC to inject to the reactor.

KIA 217000 Reactor Core Isolation Cooling System A4 Ability to manually operate and monitor in the control room:

A4.02 Turbine Trip and Throttle valve reset RO 3.9 SRO 3.9 KIA 295031 Reactor Low Water Level EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL.:

EA 1,05 Reactor Core Isolation Cooling System RO: 4.3 SRO 4.3 The RCIC Turbine has tripped on overs peed but is recoverable using the SOP and manual action frol1 the control room. The loss of RPV water inventory is via SRVs cycling for pressure control. RCIC is the only High Pressure injection system that will be available with adequate capacity to maintain RPV water level. If RPV water level is allowed to drop below -185", the fuel will be uncovered and the fuel cladding will be challenged. This would escalate the event to a Site Area Emergency. HC.OP-SO.BD-0001 Section 5.7 has the necessary guidance to step the operator through resetting the RCIC Turbine with an Initiation Signal present. The rate of level drop in this scenario is very slow and provides more than adequate time to execute the guidance and restore RPV level with RCIC without Emergency Depressurization.

ESG-NRC-S1 Page 22 of 27 Rev.: 01

ESG-NRC-S1 f 01 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT Y Loss Of Offsite Power/SSO Internal Flooding

~--

LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN KEY EQUIPMENT YIN KEY EQUIPMENT Hard Torus Vent SLC Y HPCI CRD 1E 4.16KV Bus 1 E 125VDC SACS Hx/Pump EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power NB RHR SRVs RCIC Condensate/Feedwater SSW Pump -~-

PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION Y Aligning RHR for Suppression Pool Cooling

_ _ .~ Emergency Venting of Primary Containment Emergency Depressurize RPV WIO High Pressure Injection

_ _ _ Initiating LP ECCS with No High Pressure Injection Available

_._~ Restoration of AC Power after a LOP (EDG I Offsite}

_ _ _ Monitoring and Control of SACS heat loads

- - - Preventing LVL 8 trip of Feedwater during a transient

_ _ _ Align Core Spray Suction to CST when at NPSH limits

_ ..__ ._ Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus

_.~_ Inhibit ADS during ATWS Complete this evaluation form for each ESG.

ESG-NRC-S1 Page 23 of 27 Rev.: 01

Rx Power: 90%

WorkWeek: A Risk Color: Green Activities Completed Last Shift:

Startup to 90% power Major Activities Next 12 Hours:

Continue with Startup by withdrawing Control Rods then Reactor Recirc to 100% power.

Place 8 SJAE in service; remove A SJAE from service for scheduled maintenance.

o OP-SO.CG-0001 completed up step 5.4.3.1.

o A SJAE has been warming >30 minutes.

o Operators have been briefed and are standing by in the field.

Protected Equipment:

None Tagged Equipment:

None Reactivity:

RE guidance: Rod pull Group 98 rods to 08, then use Reactor Recirc to 100% power at <1%

per minute.

Continuous rod withdraw is allowed.

ESG-NRC-S1 Page 24 of 27 Rev.: 01

SCENARIO TITLE: NRC SCENARIO 2 SCENARIO NUMBER: ESG-NRC-S2 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 50-60 minutes REVISION NUMBER: 01 PROGRAM: '--_----...J L.O. REQUAL

,----c:-----, INITIAL LICENSE

'---_--'10TH ER REVISION

SUMMARY

1. Added 3 additional control rods stuck at position 48 per Chief Examiner request.

2. Added guidance for the simulator operator to maintain CRD Drive Water Pressure <100 psig while trying to drive rods post-scram per Chief Examiner request.

PREPARED BY: 8/2/10 APPROVED BY:

APPROVED BY:

Shift Operations Supervisor or Designee DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an " *.")

A. Turbine Bypass Valve Testing - Monthly B. RRCS Pressure Transmitter Failure - Low C. Loss Of Feedwater Heating D. Feedwater Level Sensor Failure - High E. Recirc Pump 'B' Dual Seal Failure F. Recirc Pump 'B' Discharge Valve Failure To Close G. Manual Scram With 5 Control Rods Not Full In H. High Drywell Pressure I. EHC Pressure Xrnitter Fails The scenario begins with the plant at 100% power. RCIC is tagged for scheduled maintenance.

Turbine Bypass Valve Testing - Monthly HC.OP-ST.AC-0005 will be performed. The PT-N403A RRCS Pressure Transmitter will fail downscale. After Tech Specs for the failure are identified, the 6A feedwater heater will develop a tube rupture due to flow accelerated corrosion. The heater will require isolation and power reduction will be required. After the loss of FWH is addressed, The N004C DFCS level transmitter will fail high. DFCS will continue to operate in Three Element control on the remaining two transmitters. The SRO enter Tech Specs. After Tech Spec actions for the level sensor are identified, the 'B" Reactor Recirc pump will suffer a dual seal failure. When isolating the pump, the pump discharge valve will fail to close requiring a manual scram. When the plant is scrammed, 5 control rods will remain at their original positions, requiring EOP-1 01A entry. The unisolated recirc pump leakage will result in a high drywell pressure condition. After the main turbine trips, one EHC Pressure Xmitter will fail driving the crew to manually isolate the MSIVs for pressure control. The scenario ends when RPV water level is being maintained with HPCI, RPV pressure controlled with MSIVs closed, and all control rods inserted full in.

ESG-NRC-S2 Page 2 of 26 Rev.: 01

INITIALIZE the simulator to 100% power, MOL.

CIT RCIC as follows.

1. CLOSE the HV-4282

2. CLOSE the HV-F007

3. CLOSE the HV-F008

4. ALLOW RCIC supply pressure to decay to 0 psig

5. CLOSE the HV-F025

6. CLOSE the HV-F026 Description PLACE red bezel covers on the following RCIC controls:

HV-F007

HV-F008

HV-F076

HV-F045

HV-F025

HV-F026 ENSURE Data Collection is trending the following parameters as a minimum:

W/R Reactor Water Level

W/R RPV Pressure

Feedwater Temp to RPV: c91a1744 and c91a1746 or equivalent

Core Thermal Power 5 Minute Average: c91ctp5m or equivalent At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

_ _ _ (80091396 0270)

COMPLETE the Simulator Ready for Training/Examination Checklist.

ESG-NRC-S2 Page 3 of 26 Rev.: 01

COMMAND:

PURPOSE:

. EVENT ACTION:

COMMAND:

PURPOSE:

EVENT ACTION: I msv13xxa(7) <= 0.95 II 6A FWH Extraction Steam Isolation 6 COMMAND: dmffw366a2 PURPOSE: Deletes failed shut dump valve to simulate sluggish operation i EVENT ACTION: fwvhr60a <= 0.25 II HV-1753A valve position 7 I COMMAND:

PURPOSE: Tnggers Cross Flow alarm trouble when 6A FWH valved out.

EVENT ACTION: et._array(9) II Trigger ET-9 9 COMMAND: dmf CD032231 I* PURPOSE: Deletes stuck control Rod 22-31 I EVENT ACTION:* et_array(10) /I Trigger ET-10 10 COMMAND: dmf CD033843 PURPOSE: Deletes stuck control Rod 38-43 EVENT ACTION: et_array(14) 1/ Trigger ET-14 14 COMMAND: dmf CD032227 PURPOSE: Deletes stuck control Rod 22-27

~---+---+----------~-

EVENT ACTION: et_array(15) II Trigger ET-15 15 COMMAND: dmf CD033019 PURPOSE: Deletes stuck control Rod 30-19 eCarray( 16) II Trigger ET-16 CD03827 stuck control Rod 38-27 ESG-NRC-S2 Page 4 of 26 Rev.: 01

I FW366A2 6A FWH Dump Valve Failed Shut 0%

. CD032231 Control Rod 22-31 stuck NONE CD033843 Control Rod 38-43 stuck NONE CD032227 Control Rod 22-27 stuck NONE CD033019 Control Rod 30**19 stuck NONE CD033827 Control Rod 38-27 stuck RZ02E RRCS Pressure Transmitter PT-N403E Fails AN-D1E1 Cry Wolf OHA 01-01 RRCS Trouble FW12A 6A FWH Tube Leak 4:00 ET-2 0% 80%

AN-83F2 Cry Wolf Cross Flow Alarm Trouble ET-7 RR058 BP201 Recirc Pump 100%

RR068 BP201 Recire Pump I 100%

RR3181 B Recirc Loop Leak 3:00 10:00 ET-8 0% 20%

~ ..

FW29C OFCS Level Xmtr N004C Failure ET-3 100%

TU16A OEHC Pressure Transmitter CHPT-1 001A ET-5 1050 I TC01-1 BPV #1 Failure

, TC01*2 BPV #2 Failure

Initial i ip..... _ _ _ _ _ _ _ _ _ _ _ _ _ _-+----'---'-"--_ _- - - - - ' ---1-~-'--I--""""""""""~ ~---"---'-----1 D_e_sc_r.....tio_n

-==-tET015 GROUP 6A HV-F007 RCIC Steam Supply

r. Iisol ET016 GROUP 6A HV-F076 RCIC Steam Supply Isol ET017 GROUP 6A Isol HV12 Steam tunnel unit PP04 00-3 Cross Flow Correction Factor Applied i----t AN28 OHA B3-F2 Cross Flow Alarmrrrbi 00:05 NORM EP09 EOP 320 ARI Fuses 4 min REMOVE i EP10 EOP 320 ARI Fuses 4 min REMOVE 6 min ET-11 INSTALL 6 min ET-11 i ET-11 ESG-NRC-S2 Page 5 of 26 Rev.: 01

9510 A 01 RCIC 9510 C LO HV-F045 OPEN light NONE OFF i

J!

9510 B LO RCIC HV-F045 CLOSED light OFF

~..

1958 A 01 RCIC HV-F025 OPEN Pb NONE

..OFF[

. 90526 B LO RCIC HV-F025 CLOSED light NONE i OFF I

[9516 A 01 RCIC HV-F026 ?PEN Pb NONE OFF I 90527 B LO RCIC HV-F026 CLOSED light i NONE OFF I

f

9545 A 01 RCIC Manual Initiation Pb J NONE I I OFF I

3A43 F 01 HV-F031 B CLOSED-DISCHARGE ET-8 I OFF L VALVE ESG-NRC-S2 Page 6 of 26 Rev.: 01

Perform Turbine Bypass

CRS directs Turbine Bypass Valve Testing Monthly:

N Valve Testing - Monthly to be performed.

PO performs Turbine Bypass Valve Testing - Monthly lAW HC.OP-ST.AC-0005 from the OEHC HMI screen as follows:

PO selects TESTS

PO selects BPV rEST

PO selects BYPASS VALVE #1

PO selects TEST ON

After the valve reaches full open, PO selects TEST OFF.

PO verifies plant parameters stabilize and return to normal.

NOTE: Only the first 2 valves

PO repeats test for each of 8 need to be performed before other TBV's.

moving on to the next event.

Crew recognizes RRCS Failure PT-N403E output can by: be seen on the SPOS

=> OHA 01-E1 "RRCS Reactor Pressure Point Examiner, TROUBLE" Status display.

TRIGGER ET*1 (RRCS => RRCS Channel A Logic B Pressure Transmitter PT "RRCS LOGIC B TROUBLE" N403E Failure Low) light ESG-NRC-S2 Page 7 of 26 Rev.: 01

LE dispatched to RRCS,

Crew dispatches ABEO and/or THEN REPORT there is an Maintenance to RRCS cabinets "ATM CAL/GROSS FAILURE" 10C601/602.

light lit on 10C601 and PT-N403E is reading 0 psig.

LE dispatched to RRCS to perform DL-26 Attach 1 b Form 1,

THEN PROVIDE DL-26 Attach 1 b Form 1, filled out as provided on attached sheet.

LE dispatched to transmitter at instrument rack C005, THEN REPORT no visible problem at instrument rack.

CRS/STAliA recognize the Place the inoperable following Tech Spec action channel in a tripped applies: condition within one

ATWS Recirculation Pump hour.

Trip System Instrumentation 3.3.4.1 action b 6A FWH Tube Rupture:

Crew recognizes trip of 6A FWH The 6A FWH dump After the Crew completes and loss of feedwater heating valve will not open until Turbine BypassValveTesting by: after the feedwater Monthly, => OHA A7-E2 "FEEDWATER heater trip setpoint is OR HEATER TRIP" reached.

at the discretion of the Lead ::::; 6A FWH Flashing HTR TRIP Examiner, light TRrGGERET*2 (6AFWH Tube => CRIDS D2996 "Feedwater Rupture with Sluggish Dump . Heater AE1 06" Valve response). 6A FWH Extraction Steam valve HV-1365A closing

=> Lowering feed water line temperatures

Crew announces trip of the 6A FWH on the plant page.

ESG-NRC-S2 Page 8 of 26 Rev.: 01

Monitor Items:

Crew recognizes leak in 6A The tube leak will cause

FW line Temp A FWH by: a small vessel level c91a1744 ::::> RFPTs speed increasing transient (:::::2 inches).

FW line Temp B ::::? RFP discharge flows rising c91a1746 with lowering feed flow to reactor vessel

? Total Condensate flow rising

? 3/4/5A FWH drain flow rising

> 6A FWH level rising

RO reduces and maintains HPI USED:

reactor power to establish less STAR 0 than 1185 MWe Main Turbine PEER CHECK 0 Load lAW the SPRI. FLAGGING 0 Immediate Operator Action lAW AS.SOP-OOOi.

Crew restores/maintains the Core Thermal Power 5 Minute Average to::: 3848 MWth.

lE dispatched to ACi 02,

Crew dispatched TBEO to THEN REPORT: AC102 panel.

6A FWH level is high on all indicators

There is a 100% air signal on the drain valve

There is a 0% air signal on the dump valve

CRS implements AB.BOp-OaOi:

> Condition A

> Condition B

Crew ensures automatic actions occur:

? HV-1365A extraction steam isolation closes

? HV-1366A/1367N1359A drains open ESG~NRC~S2 Page 9 of 26 Rev.: 01

PO performs the following: HPI USED:

} Closes HV-1753A STAR 0

} Closes HV-1768A PEER CHECK 0

=::> Ensures extraction steam isolated to 6A FWH lAW SO.AF-0001 Section 5.6

IE feedwater temperature drops more than 10 degrees due to the Loss of Feedwater Heating, THEN CRS directs RO to reduce reactor power to 80% and maintain it there.

lE directed to monitor/control

IF directed, HPJ USED:

recirc MG oil temps, THEN RO reduces and STAR 0 THEN MONITOR: maintains reactor power 80% PEER CHECK 0

rrtoila(1) for 'A' MG lAW SPRI.

rrtoila(2) for 'B' MG

CRS implements AB.RPV-0001:

=> Condition A

=> Condition B lE directed to set Cross Flow to

Crew contacts RE.

NOT APPLIED, THEN TRIGGER ET-4.

lE reactor power was reduced by 15%,

THEN CRS recognize the following actions apply:

=> TIS Table 4.4.5-1 Item 4(b)

} ODCM Table 4.11.2.1.2-1 Items (c) & (f)

ESG-NRC-S2 Page 10 of 26 Rev.: 01

DFCS Level Transmitter

Crew recognizes N004A failure Failure: by:

After the Crew assumes the :::? OHA B1-F5 "FEEOWATER watch TRIGGERET-3 (OFCS 2/3 LOGIC SENSOR FAIL" Level Transmitter POT-N004C => OHA B3-F1 "DFCS Fails Upscale) at the discretion ALARMITRBL" ofthe Lead Examiner. => DFCS "HIGH LVL TRIP C" status light

? CRIDS 02100 "RFPT C HIGH REACTOR LEVEL 8"

? CRIOS 05272 "AlBIC REACTOR LVL 8 SENSOR FAILURE"

? DFCS "REACTOR LEVEL C HIABS" OFCS "REACTOR LEVEL C IOBAO" DFCS "REACTOR LEVEL C HIOEV"

=> LI-R608C indication on 10C650C.

RO/PO validate current RPV level with redundant instruments.

PO monitors DFCS and ensures it continues to control RPV water level.

As RBEO, REPORT there are

Crew dispatches RBEO to no visible problems at the 'C' inspect the 'C' Instrument rack.

Instrument rack.

Crew contacts Maintenance to troubleshoot.

Crew contacts Operations Management.

CRS recognize the following Must restore the N004C Tech Specs apply: to OPERABLE within 7 Feedwater/Main Turbine Trip days or be in at least System Actuation STARTUP within the Instrumentation next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.3.9 action b ESG-NRC-S2 Page 11 of 26 Rev.: 01

- e~~~v*~jp~tIRE,!;,~~9U~~iCEANP,~ie;~§!Mie

""'"'"'";;....;.o.~""""

Recire Pump Dual Seal

Crew recognizes leak in the Failure: drywell by:

Afterthe Crew addresses the C1-F5 COMP PT IN ALARM DFCS Level Transmitter and at ~ OHA C6-B 1 "OLD SYSTEM the discretion of the Lead ALARMfTRBL" Examiner, TRIGGER ET-8. ~ RM11 9AX314 OLD Floor Drain Flow alarm

~ Rising drywell pressure

CRS implements AB.CONT-0006:

~ Condition A

=> Condition C

CRS implements AB.CONT-0001 :

~ Condition A

RO/PO ensure drywell cooling is In this case, this is maximized. accomplished by opening cooling coil

RO/PO check: valves.

~ SRV temperatures

=> Recirc pump seals IE directed to report local seal

Crew recognizes 'B' Recirc pressures on the 'B' Recirc pump dual seal failure by:

pump, CRIDS 02925 "RECIRC THEN use the following PUMP B SEAL LKG FLOW Monitor Items: HI"

'B, Recirc #1 Seal => Rising seal temperatures rrpsl1 (2)

'B' Recirc #2 Seal rrpsI2(2)

CRS references AB.RPV-0003: Due to the F031 B failure

=> Condition E to close, the recirc pump cannot be isolated.

RO implements AB.RPV-0003: HPI USED:

=> Condition E STAR 0 PEER CHECK 0 ESG-NRC-S2 Page 12 of 26 Rev.: 01

IF dispatched to the breaker for

RO determines F031 B did not HV-F031 B, close and the B recirc pump is THEN REPORT the breaker not isolated and informs the looks normal. CRS.

CRS determines drywell Retainment Override in pressure cannot be maintained AB.CONT-0001.

< 1.5 psig and directs:

~ Reducing recirc pumps to minimum speed

~ Locking the Mode Switch in SHUTDOWN

RO HPI USED:

Reduces A recirc pump to STAR 0 minimum speed PEER CHECK 0

~ Locks the Mode Switch in SHUTDOWN Manual Scram with 5 Rods

RO recognizes 5 control rods Stuck: are stuck at position 48 and informs the CRS that the reactor is not shut down.

RO performs scram actions lAW HPI USED:

AB.lZ-0001 Att. 1. STAR 0 HARD CARD 0

CRS implements EOP-1 01 A.

PO stabilizes and maintains HPI USED:

RPV level as directed by CRS. STAR 0 HARD CARD 0 ESG-NRC-S2 Page 13 of 26 Rev.. 01

After scram actions are

CRS directs bypassing the RWM complete, TRIGGER ET-9 and and commencing manual rod ET-10 to delete Malfunctions insertion.

CD032231 and CD033443 to allow manual insertion of control rods.

RO/PO bypass RWM and insert HPI USED:

control rods lAW STAR 0 RE.AB.ZZ-0001 Att. 2. HARD CARD 0 OP BARRIERS 0 REFER to the appropriate EOP

CRS may direct performance of The timing, order, and and SUPPORT Crew requests the following EOPs: priority of the EOP for EOPs lAW with the EO.zZ-0320 "Defeating ARI performance may vary.

following: and RPS Interlocks"

~ EO.ZZ-0322 "Core Spray EOP-320: ET-11 Injection Valve Override" EOP-322: ET-12 High Drywell Pressure:

Crew recognizes Drywell The high dryvvell pressure will Pressure Above 1.68# EOP occur approximately 7. minutes entry condition by:

after the seal failure is initiated. ~ OHA A7-D4 "DRYWELL PRESSURE HI/HI" OHA CS-BS "DRYWELL PRESSURE HI"

~ Various system initiations and isolations.

CRS enters EOP-1 02, re-enters EOP-101A.

RO/PO verify automatic actions.

CRS directs ensuring isolations occur lAW either:

~ SO.SM-0001 OR AB.CONT-0002 ESG-NRC-S2 Page 14 of 26 Rev.: 01

RO/PO ensure isolations occur lAW either:

~ SO.SM-0001 OR

~ AB.CONT-0002 IE crew does not restore 1E

CRS directs restoring 1E 480 breakers, VAC breakers.

THEN maintain Main Steam Tunnel Temps below 140F as necessary using Monitor Item mstunl.

RO/PO restore 1E 480 VAC breakers lAW AB.ZZ-0001 Att. 12.

CRS directs placing A & B RHR pumps in Suppression Pool Cooling & Suppression Chamber Spray.

RO/PO place A & B RHR pumps in Suppression Pool Cooling and Suppression Chamber Spray lAW AB.zZ-0001 Att. 3.

Uncontrolled Lowering of

Crew recognizes uncontrolled RPV Pressure: lowering of pressure by:

5 minutes a.fterthe manual ~ OHA 03-05 "EHC UNIT scram,OR, PANEL 1 OC363" at the Lead Exacl1iners ~ OHA E1-F5 "COMPUTER PT discretion. TRIGGERET-5. IN ALARM" OHA 03-05 "EHC UNIT PANEL 10C363"

~ OHA C8-B3 "NSSSS ISLN SIG-MN STM PRESSURE LO"

=> Various reactor pressure indications Bypass valves opening ESG-NRC-S2 Page 15 of 26 Rev.: 01

CRS implements AB.RPV-0005:

~ Retainment Override 2

PO maintains RPV water level as directed by CRS lAW AB.ZZ-0001 Attachment 14.

WHEN reactor pressure lowers to 550 psig, THEN CRS directs closing the MSIVs, HV-F016, and HV-F019.

ROfPO closes the MSIVs, HPI USED:

HV-F016, and HV-F019. STAR 0 PEER CHECK 0 May cause RPV water level to shrink to LVL 2.

Crew closes at least one MSIV RECORD the reactor in each steam line before pressure at which the reactor pressure drops below steam lines were 382 psig. isolated.

Pressure: - - -

CRS directs RPV pressure control with HPCI and/or SRVs.

RO/PO control RPV pressu re as HPI USED:

directed by CRS with: STAR 0 HPCIIAW AB.lZ-0001 Att 6 HARD CARD 0

~ SRVs lAW AB.lZ-0001 Att 13 NOTE: OVERRIDE BF-HV

Crew restarts a CRD Pump and F003 as necessary to maintain sets up CRD to drive rods.

drive water pressure <100 psid while rods are being driven.

ESG-NRC-S2 Page 16 of 26 Rev.: 01

CREW fully inserts control rods via RMCS and/or manual scram(s) lAW HC.OP-EO.zZ-0320 to place the reactor in a shutdown condition.

CRS directs restoring PCIG to SRVs and Torus to Rx Bldg Vacuum breakers.

RO/PO restore PCIG to SRVs and Torus to Rx Bldg Vacuum breakers lAW AB.ZZ-0001 Att. 9.

Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when:

RPV level is being maintained above -161"

Suppression Po()1 Cooling is in service ESG-NRC-S2 Page 17 of 26 Rev,: 01

A TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-1 04-1 01 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1 003 Use of Procedures M. OP-AA-1 01-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-1 01-111-1 004 Operations Standards O. OP-AA-1 01-112-1 002 On-Line Risk Assessment P. OP-AA-106-101-1001 Event Response Guidelines Q. OP-HC-108-106-1001 Equipment Operational Control R. OP-AA-108-114 Post Transient Review S. OP-HC-1 08-115-1 001 Operability Assessment and Equipment Control Program

1. OP-AA-106-101-1001 Event Response Guideiines U. OP-HC-1 08-115-1 001 Operability Assessment and Equipment Control Program V. HC.OP-ST.AC-0005 Turbine Bypass Valve Testing - Monthly W. HC.OP-SO.AF-0001 Extraction Steam, Heater Vents And Drains System Operation X. HC.OP-SO.SM-0001 Isolation Systems Operation Y. HC.OP-DL.ZZ-0026 Surveillance Log Z. HC.OP-IO.zZ-0006 Power Changes During Operation AA. HC.OP-AB.zZ-0001 Transient Plant Conditions BB. HC.OP-AB.RPV-0001 Reactor Power CC. HC.OP-AB.RPV-0003 Recirculation System DD. HC.OP-AB.RPV-0004 Reactor Level Control EE. HC.OP-AB.BOP-0001 Feedwater Heating FF. HC.OP-AB.ZZ-OOO Reactor Scram GG. HC.OP-EO.ZZ-0101 RPV Control HH. HC.OP-EO.zZ-0101A ATWS II. HC.oP-EO.zZ-0102 Primary Containment Control ESG-t\IRC-S2 Page 18 of 26 Rev.: 01

ESG*NRC*S2 / 01 1.

Crew restores/maintains the Core Thermal Power 5 Minute Average to ~ 3848 MWth.

KIA 295001 Reactor Feedwater System A2 Ability to (a) predict the impacts of the following on the Reactor Feedwater System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions of operations:

A2.04 Loss of Extraction Steam RO 3.3 SRO 3.4 KIA 2.2 Equipment Control 2.2.22 Knowledge of limiting conditions for operations and safety limits RO.4.0 SRO 4.7 The loss of feedwater heating due to the trip of the 6A FWH will drive reactor power to above the licensed limit. Peak power in this transient with no operator action is just over 102% power. This would constitute a violation of our Operating License. HC.OP-IO.zZ-0006 defines a 5 minute average of 3848 MWth as exceeding the Licensed Power Limit. Taking the Immediate Operator Actions lAW either AB.BOP-0001 or AB.RPV-0001 will prevent this violation.

2.

Crew closes at least one MSIV in each steam line before reactor pressure drops below 382 psig.

KIA 241000 ReactorlTurbine Pressure Regulating System A2 Ability to (a) predict the impacts of the following on the REACTORITURBINE PRESSURE REGULATING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 Failed open/closed bypass valve(s) RO: 4.1 SRO: 4.2 KIA] 239001 Main and Reheat Steam System A4 Ability to manually operate and/or monitor in the control room:

A4.01 MSIVs R0:4.2 SRO: 4.0 Tech Spec 3.4.6.1, Reactor Coolant System PressureiTemperature Limits, specifies a maximum allowable cooldown of 100 degF in anyone hour period. HC.OP-AB.RPV-0005 Retainment Overrides require closing the MSIVs and HV-F016/F019 if reactor pressure reaches 550 psig during an uncontrolled depressurization with the reactor shutdown.

The scenario starts with reactor pressure at approximately 1004 psig. This equates to 1019 psia.

This places saturation temperature between 544 (995 psia) and 548 (1028 psia) degF. The saturation pressure for 444 degF is 397 psia or 382 psig. Closing the MSIVs after pressure drops below 382 psig is certain to cause the Tech Spec cooldown limit to be violated.

The scenario is modeled such that it will take at least three minutes for pressure to drop from 785 psig to 382 psig. This provides ample time to implement the AB.RPV-0005 and close the MSIVs.

Note that for purposes of satisfying the critical task, it is only necessary to close one valve in each flow path. Also, subsequent actions which may cause additional cooldown, such as overfeeding due to the pressure reduction, are not encompassed by this critical task. Other actions that may cause excessive cooldown should be evaluated under the various Crew and individual competencies.

ESG-NRC-S2 Page 19 of 26 Rev.: 01

3.

CREW fully inserts control rods via RMCS and/or manual scram(s) lAW HC.OP-EO.ZZ-0320 to place the reactor in a shutdown condition.

KIA 295006 SCRAM AA1.01 Reactor Protection System RO 4.6 SRO 4.6 AA 1.07 Ability to operate and/or monitor the following as they apply to SCRAM: Control rod position RO 4.1 SRO 4.1 AA2.02 Ability to determine andfor interpret the following as they apply to SCRAM Control rod position RO 4.3 SRO 4.4 Manually inserting all control rods, OR, implementing HC.OP-EO.zZ-0320, provides the only methods for control rod insertion and substantial negative reactivity addition. It is critical for the crew to implement one of these methods to insert control rods and shut the reactor down.

ESG-NRC-S2 Page 20 of 26 Rev.: 01

ESG-NRC-S2/ 01 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT

- - - Loss Of Offsite PowerlSBO Internal Flooding LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW

_ .. Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY EQUIPMENT Hard Torus Vent SLC HPCI CRD

_ _ _ 1E 4.16KV Bus _ _ _ 1E 125VDC

_ _ _ SACS Hx/Pump EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power NBRHR SRVs

_-,,-Y_ RCIC Condensate/Feedwater

___ SSW Pump PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION

_ _ _Y__ Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment Emergency Depressurize RPV W/O High Pressure Injection initiating LP ECCS with No High Pressure Injection Available

_ _ _ _ _ Restoration of AC Power after a LOP (EDG IOffsite)

Monitoring and Control of SACS heat loads

~_._._._~ Preventin~1 LVL 8 trip of Feedwater during a transient Align Core Spray Suction to CST when at NPSH limits Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus Inhibit ADS during ATWS Complete this evaluation form for each ESG.

ESG-NRC-S2 Page 21 of 26 Rev.: 01

Rx Power: 100%

Work Week: B Activities Completed Last Shift:

Major Activities Next 12 Hours:

Perform HC.OP-ST.AC-0005 Turbine Bypass Valve Testing - Monthly.

Protected Equipment:

HPCI Tagged Equipment:

RCIC ESG-NRC-S2 Page 22 of 26 Rev.: 01

SCENARIO TITLE: NRC SCENARIO 3 SCENARIO NUMBER: ESG*NRC*S3 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 50-60 minutes REVISION NUMBER: 01 PROGRAM: ~-'-----J L.O. REQUAL x I INITIAL LICENSE L...-_---JI OTH ER REVISION

SUMMARY

1. Added text to Stuck Open SRV event to trigger when power is stable.

2. Deleted generator MWe from Turnover.

3. Added drywell spray valve malfunction to summary description PREPARED BY: 8/4/10 DATE APPROVED BY:

APPROVED BY:

Shift Operations Supervisor or Designee DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an " *.")

A. Place H2/02 Analyzer In Service B. Raise Reactor Power Using Recirc C. Stuck Open SRV D. A SACS Pump Trip With D Failure to Auto Start E. Spurious TACS Isolation F. TACS Valve Failure To Reopen G. HPCI Steam Line Leak In DW With Loss Of Feedwater H. RCIC Flow transmitter failure I. B RHR Pump Trip J. Downcomer Break With Emergency Depressurization The scenario begins with the plant at 84.5% power, with the 'A' RFPT OOS. Power was reduced to 84.5% to remove the 'A' RFPT from service due to speed oscillations. Power ascension is ready to begin. The PO will place the "A" Containment H2/02 Analyzer in service for surveillance. The RO will begin power ascension to 89.5% using Recirc. After 89.5% power is reached, the "L" SRV will stick open. After the SRV is closed and Tech Specs are addressed, A SACS pump will trip. D SACS Pump will fail to automatically start. TACS will require manual action to complete the swap. After swap actions are completed, one TACS Isolation valve closes and cannot be opened, forcing a manual scram. Afterthe scram, the 1&2 FWHs will isolate due to level ringing, and the bypass around them will fail to open. RCIC Flow transmitter fails when RCIC is started but RCIC can be controlled manually. A leak will develop on the HPCI Steam line inside of the drywell. B RHR Pump trips when automatically started on high drywell pressure. The Dryvvell to Suppression Chamber Downcomer is broken, and the remaining RHR Loop Drywell Spray valve will malfunction which will drive the crew into an Emergency Depressurization. The scenario ends when the reactor is depressurized.

ESG-NRC-S3 Page 2 of26 Rev.: 01

INITIALIZE the simulator to 100% power, MOL, EPU.

REDUCE reactor power to 84.5%.

REMOVE the 'A' RFPT from service lAW SO.AE-0001 Section 5.10 up through the point of reducing lube oil temperature to 90 degF.

INITIAL SO.AE-0001 Section 5.10 up through the point of reducing lube oil temperature to 90 degF.

-~--

PREPARE an SO.AE-0001 Attachment 3 for 'A' RFPT pump casing d/t.

PLACE an Operational Barrier on the 'A' RFPT RESET pushbutton.

INITIAL IO.ZZ-0006 for the power reduction.

At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

(800913960270)

ENSURE Data Collection is trending the following parameters:

W IR RPV Pressure

W/R Reactor Water Level

Fuel Zone Reactor Water Level

Drywell Pressure

W/R Suppression Pool Level COMPLETE the Simulator Ready for Training/Examination Checklist.

ESG-NRC-S3 Page 3 of 26 Rev.: 01

EVENT ACTION: crqnmi <= 10 II Reactor power < 10%

5 COMMAND:

PURPOSE: Initiates loss of feedwater.

" EVENT ACTION: rent >= 1 6 COMMAND:

\" PURPOSE: Fails RCIC flow transmitter on pump startup EVENT ACTION:

7 COMMAND:

PURPOSE:

EVENT ACTION: pcpdw >= 16.7 II Triggers on DW pressure >2.0 psig 8 COMMAND: mmf hp07 10 PURPOSE: Trips B RHR Pump and increases dryweilleak

" EVENT ACTION: rhv021 (1) >= 0.01 II Drywell Spray Valve F021 A opening 9 I COMMAND:

PURPOSE: Triggers failure of Drywell Spray valve i EVENT ACTION: rrprv <= 750 II Reactor Pressure in psia 10 I COMMAND:

" PURPOSE:

Inserts downcomer break if Crew depressurizes to ensure PSP is reached.

EVENT ACTION:

11 I COMMAND:

PURPOSE:

I EVENT ACTION:

zdads4(11) >= 1.0 II F013L control switches 12 i I COMMAND: dmf ad0210

PURPOSE: Deletes stuck open SRV when control switch is cycled.

EVENT ACTION: "

COMMAND:

PURPOSE:

ESG-t\IRC-S3 Page 4 of 26 Rev.: 01

~~~D~e~sc=n='Pt=io~n__________________________+--=~~~~~~~~==-+~~=-~~~~

AD08L ADS/Relief valve F013L (MS LINE C) accoustic monitor failure AD02LO ADS/Relief valve F013L (MS LlI\IE C) ET-1 sticks open I i I CW15D DP210 SACS pump Auto-Start Failure --- --- I ET-2 --- --

i CW10A AP210 SACS Pump Trip 00:01 --- ET-2 I --- --

I I FW30A Heater 2A hi level switch failure I --- !

--- ET-5 --- I --

i FW30B Heater 2B hi level switch failure --- I --- ET-5 --- --

I FW30C Heater 2C hi level switch failure --- I

--- ET-5 --- i RC05 RCIC flow transmitter failure --- I --- ET-6 --- I 100 I

I HP07 HPCI steam line break inside the dryvvell --- I 05:00 ET-7 --- I 0.5 I RH04B RHR pump BP202 trip --- I

--- ET-S I --

I I I PC04 Oowncomer break I

--- I --- ET-10 I --- I --

Description PP04 00-3 Crossflow Applied i AN28 CROSSFLOW ALARMITRBL I NM04 APRM A gain (Range: O.SOO 1.500)

+------~------~------~-----+----~

NMOS APRM C gain (Range: 0.800 - 1.500)

NM08 APRM E gain (Range:

NM05APRM NONE 1.095 5A53 D DI HV-2522E OPEN-TACS ISLN VLVS

SAS3 F DI HV-2522E VLVS ESG-NRC-S3 Page 5 of 26 Rev.: 01

Place "An H2I02 Analyzer In

PO places "A" H2/02 Analyzer in Service: service lAW HC.OP-SO.GS-0002 Crew places H2/02 Analyzer in Section 5.2.5 as follows:

.\ service after assu.. min g th.e

. watch. ..

~ OPEN one (1) of the following H2/02 Analyzer 1AC200 suction valve combinations, RECORD component on Attachment 1 AND INITIAL:

~ HV-4959A AND HV-4965A HPI USED:

H2/02 ANLZR SUPP STAR 0 CHAMBER SUCT. PEER CHECK 0 FLAGGING 0

~ OPEN HV-4966A AND HV 5022A H2/02ANLZR RET AND INITIAL Attachment 1.

~ VERIFY HV-5741A H2/02 ANLZR H2 SUP HDR is open AND INITIAL Attachment 1.

~ VERIFY the FUNCTION SELECTOR Switch for Hz/Oz Analyzer 1AC200 is in SAMPLE AND INITIAL Attachment 1.

~ PLACE the MODE Switch for Hz/02 Analyzer 1AC200 to ANALYZE AND INITIAL Attachment 1.

ENSURE the CONTROL AT THIS PNL light is on. IF not, PRESS REMOTE SELECTOR PB.

ESG-NRC-S3 Page 6 of 26 Rev.: 01

Power Ascension:

CRS directs raising power to Crew commences reactor 89.5% using RE guidance and power ascension after 10-0006.

i assuming the watch.

As RE PROVIDE the following

RO monitors the following when guidance: changing Recirc Pump speed:

SPRI and Enhanced =:> XR-R603A,8,C,D - C51 Stability Guidance are valid (NEUTRON MONITORING) for the remainder of the APRM maneuver =:> 831-FR-R614 RECIRC LOOP

Power has been steady for A(8) FLOW the last hour. FR-R611A(B) RECIRC LOOP

Target rod line has been A(B) JET PUMP FLOW reached. =:> PDR-R613/FR- FR-R613 CORE PLATE DI FF

Raise power to 89.5% with reactor recirculation and PRESS/JET PUMP FLOW hold for thermal limit checks.

RO raises Reactor Recirc Pump HPI USED:

speed by intermittently pressing STAR 0 INCREASE pushbutton on SIC PEER CHECK 0 R621A(B) PUMP A(8) SPD OP BARRIERS 0 CONT.

Stuck Open SRV:

Crew recognizes SRV open by: RECORD time SRV At the discretion of the Lead =:> OHA C1-A3 "ADS/SAFETY open.

Examiner, RELIEF VALVE NOT CLOSED" TIME: - - - -

AND when power is stable, TRIGGER ET-1 (PSV-F013L =:> Flashing red alarm light on Inadvertent Opening). TRR-614 Acoustic Monitor open indication for "L" SRV

=:> Lowering MWe

=:> Steam Flow to Feed Flow mismatch

=:> RPV level swell ESG-NRC-S3 Page 7 of 26 Rev.: 01

>. " ? <' ' ~";j~'%5"i' _-: -~~ ".' ,. _'~, ,-- ../.,~

V.;~~i.\;SCENARlOGU1DE}SEdbENCE*ANbEXPECJED.RESp6NSE'**'

, *"'\"7",,,',:',':f'>';'-';"*""" ~>,\,~~<_>- /::"--;, ,',~> "'\,jz+ \<'- ;i", " <' ~i,;< ,':'-:/F ~"<'}:::;:0tt-':::',:,~.0'!{ ", "j'.'y'w ,-B,', ,.,,;

PO may check Acoustic Monitor Indication on 10C605 panel behind control console.

Monitor Items:

PO cycles SRV control switch in Immediate Operator

PSV-F013L Position attempt to close the SRV. Action lAW advpos(11} AB.RPV-0006.

HPI USED:

STAR 0

Before more than two minutes RECORD elapsed time has elapsed from SRV SRV was open:

opening, CREW closes F013L by cycling F013L AUTO/OPEN control switches to OPEN and TIME: _ __

back to AUTO.

CRS implements AB.RPV-0006.

Crew recognizes SRV is closed.

Crew contacts Maintenance.

CRS recognize the following Must restore within 30 Tech Spec action applies: days or initiate actions SRVs 3.4.2.1.b Tracking lAW TIS 6.9.2

=> 4.6.4.1.b Primary Must close valve within Containment Vacuum 2 minutes Breaker surveillance required.

Must perform surv within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ESG-NRC-S3 Page 8 of 26 Rev.: 01

Loss of AP210 SACS pump:

Crew recognizes trip of AP21 0 At the discretion of the Lead SACS pump by:

Examiner, TRIGGER ET-2 => OHA A1-E4 "SACS LOOP A (Trip of AP21 0 SACS pump* TROUBLE" wfFailure of DP210 to Auto CRIDS 04710 "SACS PUMP Start). AP210 TRBL"

=> Flashing STOP light for AP210

Crew recognizes loss of TACS The DP210 SACS by: pump will fail to OHA A 1-B4 "SACSITACS automatically start.

LOOP PRESS LO"

=> Failure of DP21 0 to start Status lights for HV-2522 and HV-2496 valves.

SACS loop flows

CRS directs ensuring TACS swaps to 'B' SACS loop lAW either:

AB.ZZ-0001 OR

=> AB.COOL-0002

PO ensures TACS swaps to 'B' HPI USED:

SACS loop lAW either: STAR 0

=> AB.ZZ-0001 Att. 10 HARD CARD 0 OR

=> AB.COOL-0002 lE dispatched to investigate

CRS implements Iso-Phase Bus Duct Cooling AB.COOL-0002:

Pnl 1OC116 alarm, => Condition B THEN TRIGGER ET-3 to acknowledge the alarm AND REPORT alarm was LOW CLG WATER FLOW.

(Local alarm will clear if TACS has been restored and still be in ifTACS is NOT restored)

ESG-NRC-S3 Page 9 of 26 Rev.: 01

, _. ~ ~ v,

-~ oJ _.

£~';~4£r'"'Y

lE TACS is not restored, lE the Crew scrams, THEN CRS directs: THEN the LOCA will Reducing Recirc to minimum automatically be

, Locking the Mode switch in inserted SHUTDOWN

The Crew either swaps TA CS to the tB' SACS loop lAW AB.lZ-0001 Attachment 10 or AB.COOL-0002 Condition B or Scrams the reactor.

PO starts second SSW pump in HPI USED:

'B' SSW loop. STAR 0 HARD CARD 0 lE dispatched to AP21 0 SACS

Crew dispatches RBEO and/or pump, Maintenance to investigate the THEN REPORT the following: loss of the AP21 0 SACS pump.

The motor is hot to the touch

There is charring around the motor vents

There is an acrid odor

There is no indication of fire dispatched to AP210 SACS

Crew dispatches ABEO and/or pump breaker, Maintenance to the breaker for THEN REPORT the 50A and the AP21 0 SACS pump 50B relays have target flags (52-40104).

dropped.

Crew contacts maintenance to investigate the trip of the AP21 0 SACS pump AND the failure of the DP210 SACS pump to auto-start.

ESG-NRC-S3 Page 10 of 26 Rev.: 01

IE TB Chillers are lost during TACS swap, THEN Crew recognizes loss by:

=;> OHA E5-E1 "CHILLED WTR SYSTEM TROUBLE"

=;> Rising drywell temperature and pressure

=;> Rising steam tunnel temperature Chilled water Supply/Return temperature on 10C651 E IE dispatched to the TB Chilled

IE TB Chillers are lost, If chillers are not Water Pane110C152, THEN THEN CRS implements restored, drywell REPORT the Chillers tripped AB.CONT-0001 : pressure will rise by on low evaporator water flow. =;> Condition A about 0.5 psig.

=;> Condition E

RO/PO ensures drywell cooling HPI USED:

is maximized. STAR 0 PEER CHECK 0

Crew restores TB chillers to HPJ USED:

service. STAR 0 PEER CHECK 0

CRS recognize the following Given the relatively Tech Spec applies: short assessment

> Safety Auxiliaries Cooling period that will be 3.7.1.1 Action a.1.a observed during the OR scenario, the Crew may 3.7.1.1 Action a.3.a or may not declare the DP210 INOPERABLE.

ESG-NRC-S3 Page 11 of 26 Rev.: 01

r TAGS Isolation! Manual

Crew recognizes loss of TACS Scram: by:

At the discretion of the Lead => OHA A1-B4 "SACSlTACS Examiner, TRIGGER ET-4 LOOP PRESS LO" (Closure of HV-2522E). => OHA A 1-E5 "SACS LOOP B TROUBLE"

> Status lights for HV-2522 and HV-2496 valves.

=> SACS loop flows IF dispatched to open HV

PO attempts to re-open HV 2522E locally, 2522E.

REPORT the valve will not open.

CRS implements AB.COOL-0002:

=> Condition C

=> Retainment Override

WHEN the Crew determines TACS cannot be restored, THEN CRS directs:

=> Reducing recirc pumps to minimum speed

=> Locking the Mode Switch in SHUTDOWN

RO:

=> Reduces recirc pumps to minimum speed

=> Locks the Mode Switch in SHUTDOWI\J

RO performs scram actions lAW AB.ZZ-0001 Att. 1 ESG-NRC-S3 Page 12 of 26 Rev.: 01

"-';---;:;'k:,-' '~~;~"~j:;-~~\>?kt{;_,;-_;':'.~"::;~~;".:_"'-~(::';'

',C;-" ,'Co,,, !Ffp~ct~d,el~rtV~!t,ij~~~t~BesPon§~

Crew recognizes RPV Level Below 12.5" EOP entry condition by:

==> OHA C5-A4 "RPV WATER LEVEL LO" OHA A7-D5 "RPV LEVEL 3"

==> Various water level indicators Lossbf Condensate:

Crew recognizes 1&2 FWH trip When the reactor is' scrammed, by:

the 1&2 FWHs will isolate. The OHA A7-E2 "FEEDWATER bypass valve around the 1&2 HEATER TRIP" FWHs is failed. ENSURE ET-5 ==> Flashing HTR TRIP lights for activates. FWH #2A1B/C

=> Condensate Inlet and Outlet valves stroking shut for FWH 1&2A1B/C

ROfPO attemptto open bypass HPI USED:

around 1&2 FWHs lAW STARD AB.ZZ-0001 Attachment 14. HARD CARD D PEER CHECK D

RO/PO recognize HV-1625 will not open and inform CRS.

CRS directs RPV water level control with RCIC and/or HPCI.

RO/PO inject with RCIC and/or HPJ USED:

HPCI lAW AB.zZ-0001 STARD Attachment 6. HARD CARD D RCIC Flow Transmitter

RO/PO recognizes RCIC flow Failure: transmitter failure and takes When the RCICis initiated, manual control of RCIC Flow flow indication Will peg high, Controller.

resulting in speed oscillations.

RO/PO places RCIC Flow controller in Manual.

ESG-NRC-S3 Page 13 of 26 Rev.: 01

RO/PO uses UP/DOWN arrow pushbuttons to control RCIC speed and flow to maintain RPV water level.

HPCI Steam Line Leak in

Crew recognizes LOCA Drywell: condition:

5 minutesafier the manual :::;> OHA C6-81 HDLD SYSTEM scram, ALARMITRB L" OR, ~ RM11 9AX314 DLD FLOOR at the discretion of the Lead DRN FLOW alarm Examiner, ~ RM11 9AX317/318/320 DLD TRIGGERET-7. CCM alarms OHA D3-C3 "DRYWELL SUMP LEVEL HI/LO"

~ OHA A4-F5 "COMPUTER PT IN ALARM"

~ OHA A 7-E4 "ORYWELL PRESSURE HI/LO"

=> Rising Oryvvell Pressure on various indicators

CRS implements AB.CONT Based on the rate of 0006: dryvvell pressure rise

=> Condition A (::::6 minutes to 1.68#),

=> Condition B some or all of these

=> Condition C Conditions may not be entered.

CRS implements AB.CONT 0001 :

~ Condition A

RO/PO ensures dryvvell cooling maximized.

Crew checks

=> Recirc pump seal parameters

~ SRV temperatures ESG-NRC-S3 Page 14 of 26 Rev.: 01

Crew recognizes Drywell Pressure Above 1.68# EOP entry condition by:

~ OHA A7-D4 "DRYWELL PRESSURE HI/HI"

~ Various drywell pressure indications.

~ Various system initiations and isolations.

CRS enters EOP-1 02, re-enters EOP-101.

RO/PO verify automatic actions.

RO/PO determines B RHR pump tripped after start.

LE dispatched to investigate trip

Crew dispatches NEO and/or of B RHR Pump, Maintenance to breaker for B THEN as ABEO, REPORT the RHR pump (52-40206).

breaker overcurrent flags are tripped.

dispatched to investigate trip

Crew dispatches NEO and/or of B RHR Pump, Maintenance to B RHR pump.

THEN as RBEO, REPORT there is an acrid odor in the pump room, but NO fire.

CRS verifies isolations and monitors containment performance.

ESG-NRC-S3 Page 15 of 26 Rev.: 01

CRS directs placing AP202 RHR pump in Suppression Pool Cooling and Suppression Chamber Spray.

RO/PO place AP202 RHR pump HPJ USED:

in Suppression Pool Cooling and STARD Suppression Chamber Spray HARD CARD D lAW AB.zZ-0001 Att. 3.

WHEN Suppression Chamber pressure exceeds 9.5 psig, THEN CRS directs initiating drywell spray.

RO/PO place AP202 RHR pump HPJ USED:

in Drywell Spray lAW STARD AB.zZ-0001 Att.2. HARD CARD D BP202 is not available due to pump trip.

Crew recognizes failure of HV-F021A by:

=- OHA A6-B1 "RHR LOOP A TROUBLE"

=- Flashing OVLD/PWR FAIL

=> Loss of position indication No indication of drywell spray flow CRIDS 04465 "RHR CONT SPY OUTBD HV-F021A OPF" IF dispatched to investigate trip

Crew dispatches NEO and of HV-F021 A breaker, Maintenance to breaker for THEN REPORT the breaker is HV-F021A (52-451062).

tripped and will not reset.

ESG-NRC-S3 Page 16 of 26 Rev.: 01

CRS recognizes containment not performing properly by:

=> Suppression Chamber pressure approaching Action Required area of PSP curve

=> Suppression Chamber airspace temperature significantly above water temperature Drywell Pressure response I.E necessa ry,

WHEN the Crew determines THEN REDUCE the ramp time Suppression Chamber pressure on malfunction HP07 to raise cannot be maintained below the Supp Pool pressure. Action Required region of the PSP curve, THEN the CRS implements EOP-202 to Emergency Depressurize.

Crew prevents injection from Core Spray and LPCI pumps not required for adequate core cooling.

RO/PO open ADS valves lAW HPI USED:

AB.ZZ-0001 Attachment 13. STAR 0 HARD CARD 0

Crew actuates five SRVs before Suppression Chamber pressure has been in the Action Required region of the PSP curve for over three minutes.

NOTE:

Preventing entry into the Action Required Region of the PSP curve satisfies this critical task.

ESG-NRC-S3 Page 17 of 26 Rev.: 01

Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

~ OHA C8-F1 "SUPPR POOL TEMP HIGH"

~ Flashing 95 degree status light on 10C650C

~ RM11 9AX833/834 alarm

=;> Various Suppression Pool temperature indicators

CRS re-enters EOP-1 02.

CRS directs restoring PCIG to SRVs.

RO/PO restore PCIG to SRVs HPI USED:

lAW AB.zZ-0001 Att. 9. STAR 0 HARD CARD 0 Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when:

1. RPV level is being maintained above -129"

2. The reactorhas been Emergency Depressurized ESG-NRC-S3 Page 18 of 26 Rev,: 01

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Human Performance Tools and Verification Practices I. HU-AA-1081 Fundamentals Toolkit J. HU-AA-1 04-1 01 Procedure Use and Adherence K. HU-AA-1211 Briefing L. OP-AA-106-101-1001 Event Response Guidelines M. OP-AA-1 01-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-101-111-1004 Operations Standards O. OP-AA-108-114 Post Transient Review P. OP-HC-108-106-1001 Equipment Operational Control Q. OP-HC-1 08-115-1 001 Operability Assessment and Equipment Control Program R. HC.OP-AB.ZZ-0001 Transient Plant Conditions S. HC.OP-AB.CONT-0001 Drywell Pressure T. HC.OP-AB.CONT-0006 Drywell Leakage U. HC.OP-AB.COOL-0002 SACS Malfunction V. HC.OP-AB.RPV-0001 Reactor Power

'IV. HC.OP-AB.RPV-0006 Safety Relief Valve X. HC.OP-AB.RPV-0004 Reactor Level Control Y. HC.OP-AB.COOL-0002 SafetyfTurbine Auxiliaries Cooling System Z. HC.OP-AB.ZZ-OOO Reactor Scram AA. HC.OP-DL.ZZ-0026 Surveillance Log BB. HC.OP-EO.ZZ-0101 RPV Control CC. HC.OP-EO.ZZ-0102 Primary Containment Control DD. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization EE. HC.OP-IO.ZZ-0006 Power Changes During Operation FF. HC.OP-SO.GS-0002 Hydrogen/Oxygen Analyzer System Operation GG. HC.RE-IO.zZ-0001 Core Operations Guidelines ESG-NRC-S3 Page 19 of 26 Rev.: 01

ESG*NRC*S3 I 01 1.

Before more than two minutes has elapsed from SRVopening, CREW closes F013L by cycling F013L AUTO/OPEN control switches to OPEN and back to AUTO.

KIA 239002 Safety Relief valves A2. Ability to (a) predict the impacts of the following on the RELI EF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

A2.03 Stuck open SRV RO 4.1 SRO 4.2 A4 Ability to manually operate and/or monitor in the control room:

A4.01 SRV's RO 4.4 SRO 4.4 Immediate Operator Actions in AB.RPV-0006 direct cycling the SRV control switch in an attempt to close the SRV. Cycling the control switches cycles the SRV pilot valve, and may result in clearing debris or reseating the pilot valve such that the SRV closes. Failing to perform this action would result in the SRV remaining open for more than two minutes, which would require a manual scram lAW with Tech Specs. This would result in an unnecessary scram transient. Two minutes is adequate time to validate the SRV is open and cycle the appropriate control switch.

2.

The Crew either swaps TACS to the IB! SACS loop lAW AB.ZZ-0001 Attachment 10 or AB. COOL-0002 Condition B OR Scrams the reactor.

KIA 295018 Partial or Complete Loss of Component Cooling Water AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

AA1.0'1 Backup systems RO 3.3 SRO 3.4 AA2 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

AA2.03 Cause for partial or complete loss TACS has failed to automatically transfer to the 'B' SACS loop. Both AB.ZZ-0001 Attachment 10 and AB.COOL-0002 Condition A provide guidance on how to complete a transfer of TACS to the Standby SACS loop. Failure to complete the transfer will ultimately result in loss Stator Water Cooling Turbine Runback and main turbine trip. If TACS is not restored, AB.COOL-0002 directs scramming the plant. AB.BOP-0002 directs scramming the reactor if stator water cooling cannot be restored in two minutes. Since it takes about eighteen minutes for stator water to reach the Runback setpoint, ample time is provided to either restore TACS or direct scram actions. If TACS is NOT restored, the Crew must manually scram.

ESG-NRC-S3 Page 20 of 26 Rev.: 01

3.

Crew actuates five SRVs before Suppression Chamber pressure has been in the Action Required region of the PSP curve for over three minutes.

KIA 295024 High Drywell Pressure EA2 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

EA2.04 Suppression chamber pressure RO 3.9 SRO 3.9 KIA 223001 Primary Containment Systems and Auxiliaries A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions of operations:

A2.02 Steam bypass of the suppressions pool RO 3.9 SRO 4.1 If suppression chamber pressure cannot be maintained below the pressure suppression pressure (PSP), EOPs direct actions to emergency depressurize the reactor. A lOCA condition while in the action required region of the Pressure Suppression Pressure curve, could cause design containment limits to be exceeded. Three minutes is allowed to give the operator time to evaluate conditions and direct emergency depressurization actions. Preventing entry into the Action Required Region of the PSP curve satisfies this critical task.

ESG-NRC-S3 Page 21 of 26 Rev.: 01

ESG-NRC-S3/01 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN Loss Of Offsite PowerlSBO Internal Flooding

_ ' - LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening Y Manual Scram COMPONENTITRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN KEY EQUIPMENT YIN KEY EQUIPMENT Hard Torus Vent SLC HPCI CRD 1 E 4.16KV Bus 1E 125VDC SACS Hx/Pum p EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power AlB RHR SRVs RCIC Condensate/F eedwater SSW Pump _._- PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION

_ _ _ Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment

_ _ _ Emergency Depressurize RPV W/O High Pressure Injection Initiating LP ECCS with No High Pressure Injection Available

_ _ _ Restoration of AC Power after a LOP (EDG I Offsite)

Monitoring and Control of SACS heat loads Preventing LVL 8 trip of Feedwater during a transient Align Core Spray Suction to CST when at NPSH limits

---.~

Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus Inhibit ADS during ATWS Complete this evaluation form for each ESG.

ESG-NRC-S3 Page 22 of 26 Rev.: 01

Rx Power: -84.5%

Activities Completed Last Shift:

Removed 'A' RFPT from service Major Activities Next 12 Hours:

Complete troubleshooting activities on 'A' RFPT.

Raise power to 89.5% lAW 10-0006.

Place the "An Containment H2/02 in service for weekly 02 concentration surveillance.

Protected Equipment:

None Tagged Equipment:

None Reactivity:

Raise power to 89.5% using Reactor Recirc at:::'1 % per minute and hold for RE thermal limit checks.

ESG-NRC-S3 Page 23 of 26 Rev.: 01

SCENARIO TITLE: NRC SCENARIO 4 SCENARIO NUMBER: ESG-NRC-S4 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 60-70 minutes REVISION NUMBER: 00 PROGRAM: x I LO. REQUAL X I INITIAL LICENSE OTHER REVISION

SUMMARY

PREPARED BY: Archie E Faulkner 7/1/10 Instructor APPROVED BY: cnrCVo~

LORT Group Lead or Designee 7/1/1'0

' DATE APPROVED BY: ~Mfl Shift Operations Supervisor or Designee 7(; (IU DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an " *.")

A. Reduce Reactor Power With Reactor Recire B. Remove "A" RFPT From Service C. Recirc Flow Unit Failure Downscale D. Primary Condensate Pump Trip With Partial Runbaek Failure E. Main Turbine Vibrations F. Main Turbine Trip With Half Core ATWS G. Start Up Level Control Valve Fails Closed H. "An SLC Pump Trips after Start.

I. MSIV Spurious Closure The scenario begins with the plant at 90% power. After turnover, the power reduction from 90 to 84.5% will be accomplished using Recirc per RE instructions. "A" RFPT will be removed from service for planned maintenance on the oil system. The "C" Recirc Flow Unit will fail downscale resulting in rod blocks and /'2 scram. After Tech Specs have been addressed, "B" Primary Condensate Pump trips with a failure of one Recirc Pump to runback. Once power has stabilized, Main Turbine vibrations will rise, requiring a reactor scram, The scram will result in a half-core ATWS. During the scram transient, the SULCV will fail closed, resulting in a loss of the ability to feed the reactor vessel with feedwater. "A" SLC Pump trips and is not recoverable. HPCI will be manually operated to maintain RPV level above -185". The MSIVs will spuriously close while EOP-301 is being implemented, forcing pressure control with SRV's. The scenario ends when the reactor is shutdown either by manual rod insertion, or implementation of EOP-0320.

ESG-NRC-S4 Page 2 of 26 Rev.: 00

Initial INITIALIZE the simulator to 100% power, MOL.

REDUCE Reactor Power to 90.0% with Recirc Pumps.

l I

I PREPF6ft TRA[NING(i;~;;: RM11set points, procedures, bezel covers) .,

~",'

~, <'" . ' ..' '. '." >, .<y'.;"

Initial Description IN ITIAL 10-6 for the power reduction.

At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

(800913960270)

ENSURE Data Collection is trending the following parameters as a minimum:

W/R Reactor Water L.evel

W/R RPV Pressure

Fuel Zone Reactor Water Level

Suppression Pool temperature COMPLETE "Simulator Ready-for-Training/Examination Checklist".

ESG-NRC-S4 Page 3 of 26 Rev.: 00

>= 0.50 II SLC Pump 'A' Start 5

MSIVs when Rx power <5%

9 ESG-NRC-S4 Page 4 of 26 Rev.: 00

FW10A 'A' RFPT Control Signal Failure RP07 Half-core ATWS - right side NONE SL04B BP208 SLC Pump Failure to Auto Start NONE I RR30B Failure of Intrm Runback NONE NM12C Recirc Flow Summer failure ET-1 0%

FW01 B Condensate pump BP1 02 trip ET-2 TU1508 Turbine bearing #8 vibration high 15:00 ET-4 6 21 TU1208 Turbine bearing #8 high temperature 15:00 ET-4 100 Failure 00:30 ET-5 ET-6 FW11 Feedwater Bypass Level control valve ET-14 0 0 PP04 00-3 Crossflow Applied AN28 CROSSFLOW ALARMITRBL NORM I TU03 Main Turbine Lube Oil Temperature NONE 115 AS DIRECTED CW15 TACS clg valve, AE-126, to recirc MIG set ET-3 48 25 A (0-100%)

CW16 TACS clg valve, BE-126, to recirc MIG set ET-3 48 B (0-100%)

6 min ET-12 8 min BYPASS 3 min EMERG 4 min REMOVE 4 min VE 6 min INSTALL ESG-NRC-S4 Page 5 of 26 Rev,: 00

V.: ..SCEN~~IO GUlDESEQUENCE AND EXPEC-r,EO:RESPONSE<

Eip~cted *plahitS,tudentResponse

, * <~ , .' ' ,

Power Reduction:

CRS directs reduction of Reactor Crew continues reactor power power in accordance with red uction after assuming the HC.OP-IO.zZ-0006.

watch.

As RE PROVIDE the following

CRS directs continuing the power guidance: reduction to 84.5% using RE

SPRI and Enhanced guidance.

Stability Guidance are valid for the remainder of the maneuver

Power has been steady for the last hour

Lower power to 84.5% with Recirc.

RO reduces power with Recirc HPI USED:

using provided RE guidance. STAR 0 PEER CHECK 0 OP BARRIERS 0 Remove "A" RFPT From

CRS directs removal of "A" RFPT Service: from service using HC.OP After the Crew assumes the SO.AE-0001.

watch.

Crew removes "A" RFPT from HPI USED:

service using HC.OP-SO.AE STAR 0 0001 section 5.10. PEER CHECK 0 OP BARRI ERS 0 RECIRC LOOP FLOW

Crew monitors Reactor power, SUMMER 'C' FAILURE: pressure, and level and ensure At the discretion of the lead plant conditions are stable.

Examiner, Ensures no scram setpoints have TRIGGER ET-1 (RECIRC been exceeded.

LOOP FLOW SUMMER FAILURE to 0 percent).

ESG-NRC-S4 Page 6 of 26 Rev.: 00

"i,.';-'

"v. ,~'. c;~tiNKRlb,~U[DE'.~~QUENCEAN[)\~,~picTEDJi~~~q,N~E'*'*'

'5' h;:i'c<. .

.. ::;. ,.I~ :,>/:./:,;,'-,' ".' ._:~; .*

,.",,::;r;~})K i.:,:.. :' *

Crew recognizes RPS Yz scram by:

~ OHA C3-A3 "REACTOR SCRAM TRIP LOGIC A2"

~ OHA C5-A1 "NEUTRON MONITORING SYSTEM"

=- RPS Trip Logic A2 NORMAL/RESET status lights extinguished Pilot Scram Valve Solenoid LOGIC A NORMAL status lights for all four groups extinguished.

~ GRIDS 02125 NEUTRON MON SYST SCRAM W

~ CRIDS 02131 "REACTOR SCRAM W TRIP"

~ CRIDS 02132 "REACTOR SCRAM Y TRI P"

Crew recognizes 'A', 'C', and 'E' APRMs Upscale by:

~ OHA C3-C4 "APRM SYS A UPSCALE TRI PII NOP"

~ C3-D4 "APRM UPSCALE"

~ APRMs A,C, and E "UPSG TR OR INOP" status lights

=:> APRM A,C, and E "UPSC ALARM" status lights

=:> CRIOS 04303 "APRM CH A UPSCALE THERMAL TRIP"

~ CRIOS 04306 "APRM CH C UPSCALE THERMAL TRIP"

Crew recognizes 'C' RECIRC LOOP FLOW SUMMER FAILURE Downscale by:

~ FLOW UNIT C and A "COMPAR" status lights

=:> APRM A, C, and E "UPSC ALARM" status lights

~ GRIDS C026 ITHER RBM CHANNEL UPSCALE"

=- CRIOS G049 "RECIRC FLOW COMPR OUT LIMITS" ESG-NRC-S4 Page 7 of 26 Rev.: 00

CRS implements AB.IC-0004:

=;, Condition F

CRS references AB.IC-0003:

=;, Condition B

RO bypasses 'C' Flow Unit. HPI USED:

STAR 0 PEER CHECK 0

CRS refers to DD.ZZ-0020 for a failed PPC Sensor.

CRS directs Reactor Engineering to evaluate the flow unit failure on the PPC.

IF directed to place the Flow

RO directs I&C to place the Unit C MODE Switch in the MODE Switch, on the applicable unlabeled position, THEN flow unit, to the "UNLABELED" CHANGE Malfunction NM12C position between STANDBY and Final value to 100%. ZERO.

RO verifies RPS trip clear.

RO resets RPS trip as follows: HPI USED:

TURN the affected RPS Trip STAR 0 Logic key to RESET, AND PEER CHECK 0 RETURN to the NORMAL position.

=;, VERIFY that RPS is reset.

CRS determine no Tech Spec actions required. Enter Tracking Action statement for:

=;, Table 3.3.6-1 Function 6 ESG-NRC-S4 Page 8 of 26 Rev.: 00

'8' PCP Trip:

Crew recognizes BP1 02 PCP trip TRIGGER ET-2 afterthe Crew by:

assumes the watch at the OHA A6-F2 "CONDENSATE discretion of the Lead TRAIN B TROUBLE" Examiner. ::=;> Flashing PRI CNDS PUMPS PUMP B STOP light OVLD/PWR FAIL light CRIDS 02302 "PRI CNOS PUMP BP1 02 MOTOR MALF"

PO monitors feedwater response to PCP trip.

RO verifies reactor recirc pump intermediate runbacks.

RO determines intermediate runback did not occur on "B" Recirc pump and runs back speed manually to 45% speed.

Crew announces trip of'S' PCP on the plant page.

CRS implements AB.RPV-0004:

=;> Condition 0

PO closes HV-1680B PCP HPI USED:

discharge valve. STAR 0 PEER CHECK 0

RO resets Feedwater PCP HPI USED:

Runback. STAR 0 PEER CHECK 0

CRS implements AB.RPV-0003:

Condition B ESG-NRC-S4 Page 9 of 26 Rev.: 00

RO monitors for power oscillations.

CRS implements AB.RPV-0001:

=> Condition B

CRS monitors:

=> Critical plant parameters

=> Location on Pwr/Flow map

RO/PO ensure Main Generator MWe and MVAR are within limits.

IF directed to monitor/control

RO/PO direct TBEO to recirc MG oil temps, monitor/control reactor recirc MG THEN TRIGGER ET-3 and oil temps.

MONITOR:

rrtoila(1) for 'A' MG

rrtoila(2) for '8' MG IE dispatched to investigate the

Crew dispatches TBEO and trip of BP1 02, Maintenance to investigate the THEN REPORT: trip of the BP102 PCP.

The pump motor is hot to the touch

The breaker (52-12005) has target flags up on 51A and 51 B Time Overcurrent relays.

As RE, REPORT:

Crew contacts RE.

Thermal Limits are SAT

If rodline needs to be reduced, use CRAM rods.

CRS implements 10.zZ-0006 for the power reduction.

ESG-NRC-S4 Page 10 of 26 Rev.: 00

Crew references Power Maneuvering Surveillance Requirements in OP-HC-108 115-1001.

CRS notifies Shift Rad Pro and Shift Chem Tech to take samples lAW:

Reactor Coolant System Specific Activity TIS Table 4.4.5-1 Item 4(b)

~ ODCM Table 4.11.2.1.2-1 Items (c) & (f)

Turbine High Vibrations:

Crew recognizes Main Turbine #8 Bearing will reach 11 At the discretion of the Lead High Vibration by: mils in about 8.5 Examiner, ~ OHA D3-C5 'TURBINE minutes.

TRIGGERET-4. GENERATOR VIB HI"

~ CRIDS A2526 "MAIN TURB BRG 8 VIB X PROBE"

=> System 1 indication

CRS implements AB.BOP-0002:

Condition B SUPPORT requests to raise

Crew directs TBEO to raise MTLO temperature using MTLO temperature (110 120°F)

Remote Function TU03.

As System Operator,

Crew co-ordinates with System HPI USED:

PROVIDE an acceptable band Operator to adjust Main STAR D of 300-475 MVARS. Generator MVAR loading. PEER CHECK D i.E contacted as Engineering,

Crew contacts Engineering for THEN REPORT the vibration additional guidance.

readings appear valid and the limitations in the abnormal should be followed.

ESG-NRC-S4 Page 11 of 26 Rev.: 00

LE contacted as Operations

Crew contacts Operations Manager for concurrence to Manager for concurrence to commence a controlled commence a controlled shutdown lAW 10-0004, shutdown lAW 10-0004.

THEN CONCUR with SM recommendation.

LE dispatched to check bearing

WHEN bearing #8 reaches 11 HPJ USED:

drains, mils, STAR 0 THEN wait until vibration THEN Crew: PEER CHECK 0 reaches 15 mils and REPORT Reduces recirc pump speed the floor was vibrating and it to minimum.

did not appear safe to => Locks the Mode Switch in approach the Main Turbine. SHUTDOWN.

=> Immediately trips the Main Turbine.

ATWS>4%:

Crew recognizes Scram The half core ATWS is already Condition and Reactor Power inserted on the right side of the Above 4% EOP entry condition:

core.B SLC Pump will fail to APRM indications automatically start if needed. It Absence of rod FULL IN lights will start manually from the on the right side of Full Core Control Room. Display

=> Rod position indications

RO performs scram actions lAW HPI USED:

AB.ZZ-0001 Attachment 1. STAR 0 HARD CARD 0

CRS implements EOP-101A.

PO stabilizes and maintains RPV level as directed by CRS.

CRS directs:

=> Initiating SLC

=> Verifying RWCU Isolates

RO/PO initiate SLC and verify HPI USED:

RWCU isolates. STAR 0 PEER CHECK 0 ESG-NRC-S4 Page 12 of 26 Rev.: 00

Crew starls BP208 SLC pump ENTER Supp Pool before Suppression Pool temp when BP208 SLC temperature reaches 110 pump is started:

degrees. Temp: _ __

Trip of SlC Pump:

Crew recognizes trip of AP208 The AP2Q8 SlC pump will trip SLC pump by:

30 seconds after starting. ~ OHA C1-B1 "SLC PUMPNALVE O/PF"

~ OHA C1-F1 "SLC/RRCS INITIATION FAILURE"

~ CRIDS D3022 "SLC INJ PMP AP208 TROUBLE TRBL" Flashing STOP light for AP208 IE dispatched to investigate trip

Crew dispatches NEO and of AP208, Maintenance to investigate trip of THEN REPORT the motor is AP208 SLC pump.

hot to the touch and the breaker will not reset.

(52-212063)

CRS directs:

~ Verifying Recirc runback to minimum

~ Tripping reactor recire pumps

RO/PO: HPJ USED:

=> Verify Recirc runback to STAR 0 minimum PEER CHECK 0

=> Trip reactor recirc pumps May already be tripped on EOC-RPT.

CRS directs inhibiting ADS.

RO/PO inhibit ADS lAW HPJ USED:

AB.lZ-0001 Att 13. STAR 0 HARD CARD 0 ESG-NRC-S4 Page 13 of 26 Rev.: 00

CREW prevents an This Critical Task is not uncontrolled depressurization applicable if RPV level during A TWS conditions by never reaches 29".

preventing ADS ACTUATION. See justification for failure criteria.

REFER to the appropriate EOP

CRS directs performance of the The timing, order, and and SUPPORT Crew requests following EOPs: priority of the EOP for EOPs lAW with the EO.ZZ-0320 "Defeating ARI performance may vary.

following. Validated execution and RPS Interlocks" time delays are built-in: =:> EO.ZZ-0301 "Bypassing EOP-311: ET*8 MSIV Isolation Interlocks" EOP-319: ET*9 =:> EO.zZ-0311 "Bypassing EOP-320: ET*10 Primary Containment EOP-322: ET*11 Instrument Gas Isolation Interlocks" IE EOP-301 is requested, =:> EO.zZ-0319 "Restoring THEN delay implementation Instrument Air in an until the MSIVs are closed and Emergency" TRIGGER ET*12. EO.ZZ-0322 "Core Spray Injection Valve Override"

CRS directs terminating and preventing injection to the RPV with the exception of:

=:> SLC

=:> CRD

=:> RCIC

RO/PO terminate and prevent HPI USED:

injection lAW AB.ZZ-0001: STAR 0

=:> Attachment 16 (1 OC651) HARD CARD 0

=:> Attachment 17 (1 OC650)

CRS directs maintaining RPV Typically, the lower end water level between -50" and of the level band is set

-185". above -129".

ESG-NRC-S4 Page 14 of 26 Rev.: 00

RO/PO control level as directed HPI USED:

by CRS with: STAR 0 Feedwater lAW AB.zZ-0001 HARD CARD 0 Att. 14 If the turbine trips

,;:> RCIC lAW AB.ZZ-0001 Att.6 before the reactor is

,;:> HPCI lAW EOP-322 scrammed, an RRCS feedwater runback may occur.

SULCV Fails Closed:

Crew recognizes SULCV will not The SULCV will fail erosed after re-open following "Terminate And the scram. Prevent" actions.

RO/PO control level as directed HPI USED:

by CRS with: STAR 0

,;:> RCIC lAW AB.ZZ-0001 Att. 6 HARD CARD 0 HPCI lAW EOP-322 If the turbine trips before the reactor is scrammed, an RRCS feedwater runback may occur.

Crew lowers RPV level to -50 11, and ensures adequate core cooling by maintaining or restoring RPV level above

-185" without Emergency Depressurizing.

CRS directs bypassing the RWM and commencing manual rod insertion.

RO/PO align CRD for ATWS HPI USED:

operation lAW AB.zZ-0001 STAR 0 Attachment 18. HARD CARD 0

RO/PO bypass RWM and insert HPI USED:

control rods lAW RE-AB.ZZ-0001 STAR 0 Attachment. 1. HARD CARD 0 ESG-NRC-S4 Page 15 of 26 Rev.: 00

E*(lect~~: '~I~Q~§fli~e~***;

>'2'.,- ___ c' ,'- ',.'.' \/*'-';-*5<",>-";-//" - -,"-

."..:-"_'c;""" ,,-,',

CRS directs stabilizing pressure 800 to 1000 psig with EHC lAW AB.ZZ-0001 Attachment 15.

ROfPO control pressure as HPI USED:

directed by CRS with: STAR 0

=> EHC HARD CARD 0 Spurious MSIV Crosure:

Crew recognizes the MSIV When power lowers to 5 Closure by:

percent, all MSIVs will close, => OHA C8-A1 "NSSSS MSIV forcing pressure control with LOGIC A INITIATED" SRVs. ENSURE ET-6 OHA C8-A2 "NSSSS MS!V becomes active. LOGIC C INITIATED"

=> OHA C8-A3 "NSSSS MSIV LOGIC B INITIATED"

=> OHA C8-A4 "NSSSS MSIV LOGIC D INITIATED"

=:> MSIV valve position indicator lights

CRS directs stabilizing pressure When pressure control 800 to 1000 psig with: swaps to SRVs,

=> SRVs maintaining RPV water level between -50" and

-129" will be challenging due to shrink and swell and changing reactor pressure.

RO/PO control pressure as HPI USED:

directed by CRS with: STAR 0

=:> SRVs lAW AB.ZZ-0001 HARD CARD 0 Att. 13 ESG-NRC-S4 Page 16 of 26 Rev.: 00

Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

OHA C8-F1 "SUPPR POOL TEMP HIGH"

=> Flashing 95 degree status light on 10C650C

=> RM11 9AX833/834 alarm Various Suppression Pool temperature indicators

CRS implements EOP-102.

CRS directs placing RHR in Suppression Pool Cooling.

RO/PO place RHR in Supp Pool HPI USED:

Cooling lAW AB.ZZ-0001 Att. 3. STAR 0 HARD CARD 0

l.E Suppression Pool temperature is >110 degrees, AND Reactor power is >4%,

AND SRVs are open or cycling, TH EN Crew terminates and prevents injection to the RPV with the exception of SLC, CRD, and RCIC, UNTIL Reactor power is <4%,

OR RPV level reaches -129",

OR SRVs remain closed.

l.E RPV level reaches -129", HPI USED:

THEN RO/PO terminate and STAR 0 prevents injection from Core HARD CARD 0 Spray lAW AB.ZZ-0001 Attachment 16.

WHEN the Crew has reset

WHEN EOP-320 Section 5.1 and HPI USED:

RPS, 5.2 are complete, STAR 0 THEN DELETE Malfunction THEN the Crew implements RP07 to allow full rod insertion EOP-320 Section 5.3 and reset on the next scram. RPS.

ESG-NRC-S4 Page 17 of 26 Rev.. 00

At the Lead Examiners

WHEN OHA C6-E4 clears, HPJ USED:

discretion, MODIFY Monitor THEN the Crew initiates a STAR 0 Item Iclsdv to accelerate manual scram lAW EOP-320 draining of the SDV. Section 5.3.

CREW fully inserts al/ control rods via RMCS and/or manual scram(s) lAW HC.Op*EO.ZZ*0320.

Crew recognizes the reactor is shutdown by:

=> SPDS ALL RODS IN

=> RWM Confirm Shutdown

=> CRIDS Rod positions

CRS directs terminating SLC injection.

RO/PO terminate SLC injection. HPI USED:

STAR 0 Termination Requirement:

CRS exits EOP-1 01A, enters The scenario may be EOP-101.

terminated at the discretion of the Lead Examiner when:

RPV Level is being maintained above -185" AND

.* All rods are fully inserted ESG-f\IRC-S4 Page 18 of 26 Rev.: 00

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. HU-AA-10S1 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1004 Operations Standards M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines O. OP-AA-1 OS-114 Post Transient Review P. OP-HC-'IOS-115-1001 Operability Assessment and Equipment Control Program Q. OP-HC-108-106-1001 Equipment Operational Control R. HC.OP-SO.AE-0001 Feedwater System Operation S. HC.OP*SO.BB-0001 Reactor Recirculation System Operation T. HC.OP-DD.ZZ-0020 Review of Core Performance Information U. HC.OP-Dl.ZZ-0026 Surveillance Log V. HC.OP-AB.ZZ-0001 Transient Plant Conditions W. HC.Op*AB.RPV*Q001 Reactor Power X. HC.OP-AB.RPV-0003 Recirculation System Y. HC.OP*AB.RPV-0004 Reactor Level Control Z. HC.OP-AB.BOP-0002 Main Turbine AA. HC.OP-AB.IC-0004 Neutron Monitoring BB. HC.OP-AB.ZZ-OOO Reactor Scram CC. HC.OP-EO.ZZ-0101 RPV Control DD. HC.OP-EO.ZZ-0101A ATWS-RPV Control EE. HC.OP-EO.ZZ-0102 Primary Containment Control FF. HC.RE-RABB-0002 Core Flow Determination GG. HC.RE*AB.ZZ-0001 Transient Plant Conditions HH. HC.RE-AB.ZZ-0001 Insertion of Control Rods in Response to an ATWS II. HC.OP*AB.ZZ-0001 Transient Plant Conditions JJ. HC.OP-IO.zZ-0004 Power Changes During Operation KK. HC.OP-IO.ZZ-0006 Shutdown From Rated Power To Cold Shutdown ESG-NRC-S4 Page 19 of 26 Rev.: 00

"yn:,,>< ESG cRrtlcAL TASKRA i~

TIO~AL' t~v> ~ ~[ ~ ~~ ;;;i)/;:

"::. > 'J ESG-NRC-S41 00 1.

CREW prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUA TlON.

KIA 218000 Automatic Depressurization System A4 Ability to manually operate and/or monitor in the control room:

A4.04 ADS inhibit RO 4.1 SRO 4.1 Given the current ATWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor. EOPs direct this action under the current conditions.

This critical task is only applicable if RPV water level goes below -129". Failure to satisfactorily complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure to less than 700 psig.

2.

Crew starts BP208 SLC pump before Suppression Pool temperature reaches 110 degrees.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA 1.04 SBlC RO 4.5 SRO 4.5 EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA2.04 Suppression Pool Temperature RO 4.0 SRO 4.1 The Boron initiation injection Temperature above about 9% power is 110°F. The post scram power level in this scenario is greater than 9%. The MSIVs spuriously close resulting in rejection of ali heat to containment. The AP208 SLC pump fails trips on start, and the BP208 SLC pump fails to auto start. Crew action is required to commence SLC injection before the BIIT is reached.

3.

Crew lowers RPV level to -50", and ensures adequate core cooling by maintaining or restoring RPV level above -185" without Emergency Depressurizing.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA2.02 Reactor water level RO 4.1 SRO 4.2 lowering RPV level during an ATWS with reactor power >4% is a key strategy for controlling reactor power. Maintaining adequate Core cooling under ATWS conditions is accomplished by maintaining/restoring level above -185". HPCI and RCIC are capable of maintaining level under the current conditions. An Emergency Depressurization is not warranted and would result in a large injection of cold water and the potential displacement of boron from the core.

ESG-NRC-S4 Page 20 of 26 Rev.: 00

4.

CREW fully inserts all control rods via RMCS and/or manual scram(s) lAW HC.OP-EO.ZZ-0320.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. Abiiity to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA 1.01 Reactor Protection System RO 4.6 SRO 4.6 EA 1.07 RMCS RO 3.9 SRO 4.0 Manually inserting all control rods, OR, implementing HC.OP-EO.zZ-0320, provides the only methods for control rod insertion and substantial negative reactivity addition. It is critical for the crew to implement one of these methods to insert control rods and shut the reactor down. Failure to initiate these actions may result in requiring RPV level to be lowered to or below TAF to reduce power to <4%. This represents a significant challenge to maintaining adequate core cooling.

ESG-NRC-S4 Page 21 of 26 Rev.: 00

ESG-NRC-S4/00 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN -EVENT

- YIN EVENT Loss Of Offsite PowerlSBO Internal Flooding LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Y Loss of Feedwater Loss of Instrument Air Y Inadvertent MSIV Closure Y Inadvertent SRV Opening Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN KEY EQUIPMENT YIN KEY EQUIPMENT Hard Torus Vent SLC HPCI CRD 1E 4.16KV Bus 1E 125VDC SACS HxlPump EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power AlB RHR SRVs RCIC Condensate/Feedwater SSW Pump Y PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION

_ _ _ Aligning RHR for Suppression Pool Cooling Emergency Venting of Primary Containment Emergency Depressurize RPV WIO High Pressure Injection

_ _ _ Initiating LP E.CCS with 1\10 High Pressure Injection Available

_ _ _ Restoration of AC Power after a LOP (EDG IOffsite)

_ _ _ Monitoring and Control of SACS heat loads

_ _ _ Preventing LVL. 8 trip of Feedwater during a transient

_ _ _ Align Core Spray Suction to CST when at NPSH limits Cross-Tie De**Energized BID 125VDC Battery Charger to Energized Bus

_ _ _ Inhibit ADS during ATWS Complete this evaluation form for each ESG.

ESG-NRC-S4 Page 22 of 26 Rev.: 00

Rx Power: 90%

Work Week: A Risk Color: Green Activities Completed Last Shift:

Entered AB.RPV-0004 Condition C due to control signal failure on "An RFPT.

Reduced power to 90%.

Major Activities Next 12 Hours:

Continue power reduction to 84.5% with Recirc lAW RE SPRI guidance and 10-6 Remove "An RFPT from service.

Troubleshoot 'A' RFPT control signal failure.

Protected Equipment:

None Tagged Equipment:

None ESG-NRC-S4 Page 23 of 26 Rev.: 00

SCENARIO TITLE: NRC SCENARIO 5 SCENARIO NUMBER: ESG-NRC-S5 (Spare)

EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 60-75 minutes REVISION NUMBER: 00 PROGRAM: x I L.O. REQUAL X I INITIAL LICENSE L---_--' OTHER REVISION

SUMMARY

1.

PREPARED BY: 7i1/10 APPROVED BY:

LORT Group Lead or Designee 7/J J/U DATE APPROVED BY:

Shift Operations Supervisor or Designee DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an "*.")

A. Power Reduction (Optional).

B. Swap SSW Pumps C. SSW Pump Malfunction (TS SRO)

D. Single Reactor Recirc Pump Runaway E. Reactor Recirc Pump Trip (TS SRO)

F. Fuel Failure wit!"1 Manual Scram G. Torus Leak I Emergency Depressurization The scenario begins with the plant at 100% power. 'B' EHC Pump is tagged for maintenance.

After turnover, the power reduction from 100 to 95% will be accomplished using Recirc per RE instructions (Optional). SSW Pumps will be swapped for planned maintenance. After pump swap, "0" SSW pump will malfunction requiring entering Tech Spec LCO. After Tech Specs have been addressed, the 'B' Reactor Recirculation pump will runaway to it's upper mechanical stops.

Operator action Will be necessary to reduce reactor power to less than or equal to original power level. After AB-RPV-0001/003 actions are taken and Tech Specs have been addressed, "S" Recirc Pump vibrations will climb into the Danger level. This will require a manual pump trip.

Once power has stabilized, fuel damage symptoms will begin and increase in magnitude, requiring a reactor scram. After the MSIV's are closed, an unisolable leak will develop on the Torus requiring an Emergency Depressurization. The scenario ends when the reactor is depressurized by the SRVs, and reactor level stabilized between RPV Level 2 and 8.

ESG-NRC-S5 (Spare) Page 2 of 25 Rev.: 00

PLACE red bezel cover on '8' EHC pump.

INITIAL 10-6 for the power reduction. (Optional)

Prepare a REMA for the power reduction evolution. (Optional)

At a minimum review the Scenario Reference section and CLEAN the balded EOPs, A8s and SOPs listed.

(80091396 0270)

ENSURE Data Collection is

W/R Reactor Water

WIR RPV Pressure

Suppression Pool level

Suppression Pool temperature I COMPLETE "Simulator Ready-for-Training/Examination Checklist".

I Initial ET # . Description EVENT ACTION: crqnmi <= 25 1/ Reactor Power <25%

8 COMMAND: mmf cr01 50 PURPOSE: Inserts Fuel Cladding failure if Crew scrams during Recire Runaway EVENT ACTION:* msvf022(1} <= 0.0 II msvf028(1) <= 0.0 1/ 'A' MSL isolated 9 COMMAND:

PURPOSE:

EVENT ACTION: msvf022(2) <= 0.0 II msvf028(2} <= 0.0 II '8' MSL isolated 10 COMMAND:

PURPOSE: I Detects '8' MSL isolation ESG-NRC-S5 (Spare) Page 3 of 25 Rev.: 00

msvf022(3) <= 0.0 II msvf028(3) <= 0.0 II 'C' MSL isolated I. - I EVENT ACTION:

11 COMMAND:

I.

L ! __P_U_R_P_O_S_E_:T-D_e_t_e_ct_s_'C_'_M_S_L_i_so_l_at_io_n____________________________________~

i ! EVENT ACTION: msvf022(4) <= 0.0 II msvf028(4) <= 0.0 1/ '0' MSL isolated 12 COMMAI\IO:

PURPOSE: Detects '0' MSL isolation I ACTION:* msvfdrn1(1) <= 0.0 II msvfdrn1(2) <= 0.0 // F016 or F019 shut COMMAND:

PURPOSE: Detects MSL drain isolation r----+---+-.~--------~-

crqnmi <= 7 II Reactor Power <7%

imf rm9509 118 180 Ramps MSL rad to 3xNFPB after reactor scrammed.**

<= 7 /1 Reactor Power <7%

rm951 0 127180 MSL rad to 3xNFPB after reactor scrammed.**

EVENT ACTION: crqnmi <= 7 II Reactor Power <7%

16 i COMMAND: imfrm9511119180

PURPOSE: Ramps MSL rad to 3xNFPB after reactor scrammed.**

EVENT ACTION: crqnmi <= 7 /1 Reactor Power <7%

17 COMMAND: imf rm9512 122 180 I PURPOSE: Ramps MSL rad to 3xNFPB after reactor scrammed.**

EVENT ACTION: et_array(9) >= 1.0 && et_array(13) >= 1.0 18 COMMAND:. imf rm950919 60 PURPOSE:

Removes high radiation from 'A' MSL EVENT ACTION: et_array(10) >= 1.0 && et_array(13) >= 1.0 19 COMMAND: imf rm9510 19 60 PURPOSE: Removes high radiation from 'B' MSL EVENT ACTION: et_array(11) >= 1.0 && et_array(13) >= 1.0 20 COMMAND: imf rm9511 15 60 PURPOSE: Removes high radiation from 'C' MSL EVENT ACTION: et_.array{12} >= 1.0 && et_array(13) >= 1.0 COMMAND: imf rm9512 18 60 PURPOSE: i Removes high radiation from '0' MSL r----+---+----------~~

EVENT ACTION: Pclsp <= 11911 Indicated SP level 22 COMMAND: dmfpc06 PURPOSE: Removes torus leak at 25" to prevent reaching Simulator Limits ESG-NRC-S5 (Spare) Page 4 of 25 Rev.: 00

Description TC07S EHC pump B trip CW11D Service water pump 0 marsh grass ET-1 50 intrusion RR08B Recirc system B controller fails high I RR26B2 Recirc pump BP201 elevated (added to 20

calc) Pump Vib CW05D SSW Pump 0 trip PC06 Suppression pool break 50

. RH09A 'A' RHR pump Room Flooded 00:02:10 CR01 Fuel Cladding Leak 00:05:00 ET-8 30%

RM9509 MSL 'A' Radiation 00:05:00 ET-8 35.4* 11S**

RM9510 MSL 'B' Radiation 00:05:00 ET-S 38.5* 127**

RM9511 MSL 'C' Radiation 00:05:00 ET-S 35.8* 119**

RM9512 MSL '0' Radiation 00:05:00 ET-S 36.S* 122**

PP04 00-3 Crossflow Applied 00:00:00 ET-3 NO AN28 CROSSFLOW ALARMITRBL 00:00:05 ET-3 NORM ESG-NRC-S5 (Spare) Page 5 of 25 Rev.: 00

Power Reduction (Optional):

CRS directs reduction of Reactor Call as System Operatorfor power in accordance with Hope Creek Station to perform

HC.OP-IO.zZ-0006.

an emergency loadreduction to

1200 MWeasrapidly as possible without exceeding

. limits for grid stability.

IF contacted as RE THEN

CRS directs continuing the power PROVIDE the following reduction to 95% using RE guidance: guidance.

Use SPRI for the maneuver

RO reduces power with Recirc HPI USED:

using provided RE guidance. STAR 0 PEER CHECK 0 OP BARRIERS 0 Swap Service Water Pumps:

CRS directs removal of "B" SSW After the Crew assumes the from service using HC.OP watch. SO.EA-0001.

PO removes "B" SSW from HPI USED:

service using HC.OP-SO.EA STAR 0 0001 section 5.6. PEER CHECK 0

PO places "0" SSW in service using HC.OP-SO.EA-0001 section 5.6.

SSW Pump "D" Malfunction:

Crew recognizes 0 SSW strainer At thedfscretion of the lead Hi OP to the strainer by:

Examiner, =;> A1-C3 SSWS INTAKE 0 TRIGGER ET-1 (Service water TROUBLE pump 0 marsh grass intrusion =;> 03974 SSW STRAIf\IER 0 to 50%). OIFF HI HI STRAINER PRESSURE DIP 05526 SSW STRAINER 0 DRIVE OPF ESG-NRC-S5 (Spare) Page 6 of 25 Rev.: 00

WHEN requested as Yard

CRS implements Operator, REPORT "0" SSW AB.COOL-0001 :

pump strainer is not rotating =::> Condition A and the screen is covered with

=::> Condition 0 grass.

The breaker for the strainer is tripped and will not reset.

IE the crew does not remove

Crew removes "0" SSW pump the "0" SSW pump from from service lAW: HPJ USED:

service, THEN TRIGGER ET-6 AB.ZZ-0001 Att 19 STAR 0 to trip the pump.

Crew places "B" SSW pump in service lAW: HPJ USED:

AB.zZ-0001 Att 19 STAR 0

CRS recognize the following 30 day LCO Tech Spec applies:

~ Station Service Water 3.7.1.2 Action a

Crew contacts maintenance.

Crew recognizes "B" Reactor runaway: . Recirculation pump runaway by:

TRIGGER ET-2, fiVe minutes =::> OHA C3-04 "APRM after Tech Specs have been UPSCALE" addressed ORat the discretion =::> Reactor power >100%

of the Lead Examiner. =::> CRIDS 02900 "RECIRC MG B SPEED CONTROL SIG FAIL"

~ CRIDS 02931 "RECIRC MG B DRIVE TUBE LOCK TRBL"

=::> SIC-R621 B SPEED OEMND and SPEED Upscale

=::> 10C650C Recirc and Jet pump indications ESG-NRC-S5 (Spare) Page 7 of 25 Rev.: 00

RO performs the following: HPI USED:

==> Presses SCOOP TUBE TRIP STAR 0 for "B" Recirc Pump PEER CHECK 0

==> Reduces "AU Recire Pump Immediate Operator speed to reduce power to Action lAW pre-transient value AB.RPV-0001.

(Recire pumps are already in manual.)

Crew reduces power to S 3840 RECORD the time that MWt within two minutes of power was above 3840 recirc pump runaway. MWt.

TIME: _ _ __

CRS implements AB.RPV-0001:

Condition F SUPPORT requests for local

Crew checks Recirc Loop Flow operation of '8' Recire MG mismatch lAW ST.BB-0001.

scoop tube using Remote Function RR10.

lE called as RE to determine

Crew determines peak thermal maximum thermal power power during the transient.

reached, THEN REPORT thermal power peaked at 101.2% (3887 MWth).

CRS recognize the following Must restore recirc loop Tech Specs/actions apply: flow mismatch within

==> 2.C(1) Maximum Power Level two hours or declare

==> 2.F Reporting 2.C Violations the B loop not in 3.4.1.3 Action a. Recirculation operation.

Loop Flow IF directed to monitor/control

RO/PO direct TBEO to recirc MG oil temps, monitor/control reactor recirc MG THEN MONITOR: oil temps.

rrtoila(1) for 'A' MG

rrtoila(2) for '8' MG ESG-NRC-S5 (Spare) Page 8 of Rev.: 00

- - .~P.~§t:~.rl~~yStmt~rit,B~$&p9~~~;~

>:':",."">':>"." ")" ;'",'<;, <>::'- '>',"'. ",':'~'-"~;)- ',:-';Z"',,* ), ... ;':-'.--------': "-,--",,,,,,

As RE, REPORT:

Crew contacts RE.

Thermal Limits are SAT

If rod line needs to be reduced, use CRAM rods.

CRS implements 10.ZZ-0006 for the power reduction.

Crew references Power Maneuvering Surveillance Requirements in OP-HC-1 08 115-1001.

CRS notifies Shift Rad Pro and Shift Chem Tech to take samples lAW:

~ Reactor Coolant System Specific Activity TIS Table 4.4.5-1 Item 4(b)

~ ODCM Table 4.11.2.1.2-1 Items (c) & (f)

ReactorRecirculation Pump

Crew recognizes '8' Recirc Pump High Vibrations: high vibrations by:

At the discretion of the Lead ~ OHA C1-E4 "REACTOR

.Examiner, RECIRC PUMP VIB HI" TRIGGER ET*4. ~ OHA C1-F5 "COMPUTER PT IN ALARM"

~ CRIDS D5352 "RECIRC PUMP B VIBRATION HI"

~ CRIDS D2921 "RECIRC PMP MOTOR B VIBRATION HI" CRIDS A2603 "RECIRC PMP B SHAFT RADIAL"

CRS implements AB.RPV-0003:

~ Condition F

Crew implements AB.RPV-0003:

=> Condition F ESG-NRC-S5 (Spare) Page 9 of 25 Rev.: 00

Crew evaluates the following Recirc Pump parameters for degradation ofthe pump(s) in ALARM to validate the condition.

Seal Parameters (Temperature, Pressure, Flow)

~ Pump Parameters (Temperature, Vibration)

~ Motor Parameters (Temperature, Vibration)

Crew contacts Engineering Duty Manager to obtain and assess vibration data.

IF requested, as RE PROVIDE

Crew determines "B" Recirc HPI USED:

guidance to the CRS to reduce Pump Vibration points cannot be STAR 0 reactor power lAW the maintained below the DANGER PEER CHECK 0 Standard Power Reduction limit and performs the following to Instructions (SPRI). remove A(B) Recirc Pump from lE crew manually scrams, service:

THEN TRIGGER ET-8 (Fuel ~ Press PUMP B MOTOR cladding failure). BRKR TRIP push button

PO verifies the Feedwater system is responding automatically and is restoring RPV level between level 4 and 7.

CRS implements AB.RPV-0003:

~ Condition A

~ Condition B As TBEO, ADJUST

Crew implements AB.RPV-0003:

temperature for the Recirc MG ~ Condition A Sets as directed.

~ Condition B

CRS implements AB.RPV-0001:

~ Condition B ESG-NRC-S5 (Spare) Page 10 of 25 Rev.: 00

Crew implements AB.RPV-0001:

=> Condition B

RO/PO monitors and reports power, pressure and level parameters.

CRS verifies core parameters are within the OPRM Enable Region of the Power to Flow Map.

RO/PO closes HV-F031 B Recirc HPJ USED:

pump discharge valve for 5 STAR 0 minutes and then re-opens. PEER CHECK 0

Crew directs the following TS requirements for >15% power change in 1 hour:

, Chem Tech for T.S. 3.4.S.c.1

, Rad Pro Tech for ODCM 3.11.2.1.

CRS directs the following TS requirements:

, 3.4.1.1 Action a. within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of entering Single Loop Operations.

CRS implements 10-0006 for the power reduction and Single Loop Operations.

When requested, remove.

CRS directs the Cross Flow Cross Flow from service, Correction Factor to "Not TRIGGER ET-3. Applied".

CRS directs implementation of DL.ZZ-0026 Att.3v.

ESG-NRC-S5 (Spare) Page 11 of 25 Rev.: 00

Crew implements DL.ZZ-0026 Att.3v.

As Chemistry REMOVE condensate demins from service as required. Notify the Crew prior to removing Beds from service. TRIGGER Remote Malfunction FW01 FWD7 (A-G accordingly).

When requested, as the RE

CRS directs the RE to perform TS REPORT that TS actions will actions to be taken. Raise the MCPR safety limit, lE requested, as RE PROVIDE Reduce MAPLHGR limit guidance to the CRS to reduce ~ Reduce LHGR to the value reactor power lAW the SPRI. specified in the COLR Operating Limits Report.

Fuel Cladding Failure:

Crew recognizes fuel clad IF the Crew scrams 10 minutes after the Recirc damage by: during the Recirc PumpTrip, ~ RM11 9RX621/622 Offgas Runaway, OR, Pretreatment Alarms THEN the Fuel Failure at the Lead Examiners ~ OHA C6-A3 "MN STM LINE will automatically be discretion, RADIATION HI" inserted.

TRIGGER ET-8 (Fuel cladding ~ RM11 9RX509/510/511/512 MSL Radiation levels failure). Alert alarms and readings will reach 3xNFPB

~ CRIDS Page 37 MSL approximately 4 Radiation readings minutes after the failure begins.

CRS implements AB.RPV-0008: If the plant is shutdown,

~ Condition A Condition B actions are

~ Condition B not applicable.

Condition C

RO reduces power lAW Standard Power Reduction Instructions.

ESG-I\lRC-S5 (Spare) Page 12 of 25 Rev.: 00

Crew recognizes HI-HI MSL Radiation levels by:

=> OHA C6-B2 "MN STM LINE RAD HI HI OR INOP"

=> RM11 9RX509/51 0/511 /512 High alarms CRIDS Page A037 MSL Radiation readings

CRS directs:

=> Locking the Mode Switch in SHUTDOWN

=> Closing MSIVs, HV-F016 and HV-F019 steam line drains.

RO locks the Mode Switch in HPJ USED:

SHUTDOWN. STARD PEER CHECK D

RO performs scram actions lAW HPJ USED:

AB.ZZ-0001 Attachment 1. STARD HARD CARD D

PO controls leve! as directed by HPJ USED:

CRS with: STARD

=> Feedwater lAW AB.ZZ-0001 HARD CARD D Attachment 14 HPCI/RCIC lAW AB.ZZ-0001 Attachment 6 ENSURE MSL Radiation

RO/PO close MSIVs, HV-F016 HPI USED:

Malfunctions R1VI9509-RM9512 and HV-F019 steam line drains. STARD ramp down to <20 when the PEER CHECK D Main Steam Lines AND drain lines are isolated.

ESG-NRC-S5 (Spare) Page 13 of 25 Rev.: 00

The Crew inserts a manual The Critical Task is scram and closes at least one satisfied as long as all MSIV in each Main Steam Line lines are isolated. For and the HV-F016 Q! F019 drain instance, closing the valve before MSL radiation has HV-F016, but NOT the been above the Hi-Hi setpoint HV-F019 satisfies for three minutes. isolation of the F016/F019 drain line.

RECORD time (if any) between OHA C6-B2 and reactor scrammed with main steam and drain lines isolated:

TIME: _ _ __

CRS implements AB.RPV-0003:

=> Condition G

lE directed by the CRS, HPI USED:

THEN RO/PO place RHR in STAR 0 Suppression Pool Clg lAW HARD CARD 0 AB.ZZ-0001 Att. 3.

Unisolable Torus Leak:

Crew recognizes torus leak by: It will take The Torus Leakwill begin three => OHA 03-C2 "REACTOR approximately 12.5

, minutes after the MSIVs are BLDG SUMP LVL HI/LO" minutes for Supp Pool isolated of at the Examiners ~ OHA B1-C3 "SUPPRESSION level to reach 38.5".

descretion. POOL LEVEL HIILO" Various Suppression Pool level indicators lowering IF dispatched to the Torus

Crew dispatches personnel to Room to look for a leak, inspect Rx Bldg '54 and Torus THEN REPORT there is a Room for leak.

large, unisolable leak at on the bottom of the torus at Az. 180.

There is about one inch of water on the torus room floor.

ESG-NRC-S5 (Spare) Page 14 of Rev,: 00

asked,

Crew contacts RWEO and THEN REPORT both sump informs them of leak.

pumps are running in both the North and South RB Floor Drain sumps.

Crew recognizes Supp Pool Level Below 74.5 In EOP entry condition by:

=:> OHA B1-C3 "SUPPRESSION POOL LEVEL HIILO"

=> Various Suppression Pool level indicators

CRS implements EOP-1 02.

IE directed to implement

CRS directs M/U to the torus EOP-315 then, lAW EOP-315.

WHEN torus level reaches 45",

MODIFY Remote Functions CS01-CS04 to make-up as directed.

Do NOT open more than two valves.

RO/PO coordinate implementation of EOP-315 with NEO.

RHR Pump Room Flooded:

Crew recognizes Reactor Bldg The 'A' RHR Room flooded Room Floor Level Above Max alarm will be received about 4 Normal Op EOP Entry Condition minutes after.the Torus Leak by:

starts. =:> OHA A6-A5 "RHR PUMP ROOM FLOODED"

=> CRIDS 02891 "RHR PMP ROOM 4113 LSHA403A1"

=> CRIDS 02892 "RHR PMP ROOM 4113 LSH-4403A2"

=> SPDS RB LV/TE indication ESG-I\lRC-S5 (Spare) Page 15 of 25 Rev.: 00

IE dispatched to 'A' RHR room,

CRS implements EOP-103.

THEN, AFTER OHA A6-A5 "RHR ROOM FLOODED" is received, REPORT there is about two inches of water on the floor and it appears to be coming up through a floor drain.

WHEN it is determined that Supp Pool level cannot be maintained above 38.5",

THEN CRS determines Emergency Depressurization is required.

CRS implements EOP-202.

RO/PO opens five ADS SRVs HPI USED:

lAW AB.ZZ-0001 Att. 13. STAR 0 HARD CARD 0 PEER CHECK 0

Crew determines that RECORD Supp Pool Suppression Pool water level level at which ADS was cannot be maintained above initiated.

38.5" and initiates opening of five SRVs before Suppression LEVEL: _ __

Pool level reaches 30 11,

RO/PO maintain RPV level as directed by CRS.

IE Supp Pool level drops to 30",

THEN the Crew ensures HPCI is secured.

ESG-NRC-S5 (Spare) Page 16 of 25 Rev.: 00

WHEN Suppression Pool temperature reaches 95 degrees, THEN Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

=> OHA C8-F1 "SUPPR POOL TEMP HIGH"

=> Flashing 95 degree status light on 10C650C RM11 9AX833 alarm

=> Various Suppression Pool temperature indicators

WHEN Suppression Pool temperature reaches 95 degrees, THEN the CRS re-enters EOP-102.

Termination Requirement:

WHEN directed by the CRS, HPI USED:

The scenario may be THEN RO/PO place RHR in STAR 0 terminated atthe discretion of Suppression Pool Clg lAW HARD CARD 0 the Lead Examinerwhen the AB.ZZ-0001 Att. 3. PEER CHECK 0 RPV has been depressurized FLAGGING 0 lAW EOP-202.

ESG-NRC-S5 (Spare) Page 17 of 25 Rev.: 00

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B, NUREG 1021 Examiner Standards C, JTA Listing D, Probabilistic Risk Assessment E. Technical Specifications F, Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J, HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1 004 Operations Standards M. OP-AA-1 01-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines O. OP-AA-1 08-114 Post Transient Review P. OP-HC-1 08-115-1 001 Operability Assessment and Equipment Control Program Q. OP-HC-108-106-1001 Equipment Operational Control R. HC.OP*SO.BB*0001 Reactor Recirculation System Operation S. HC.oP-DD.ZZ-0020 Review of Core Performance Information T. HC.OP-OL.ZZ-0026 Surveillance Log U. HC.OP-AB.ZZ-0001 Transient Plant Conditions V. HC.OP*AB.RPV-0001 Reactor Power W. HC.OP*AB.RPV-0003 Recirculation System X. HC.OP*AB.RPV-0008 Reactor Coolant Activity Y. HC.OP*AB.CONT-0004 Radioactive Gaseous Release Z. HC.OP-AB.ZZ-OOO Reactor Scram AA. HC.OP*EO.ZZ-0101 RPV Control BB. HC.OP-EO.ZZ-0102 Primary Containment Control CC. HC.OP-EO.ZZ-0103 Reactor Building Control DO. HCRE-RA.BB-0002 Core Flow Determination EE. HC.OP-IO.ZZ-0004 Power Changes During Operation FF. HC.OP-IO.ZZ-0006 Shutdown From Rated Power To Cold Shutdown ESG-NRC-S5 (Spare) Page 18 of 25 Rev.: 00

ESG-NRC-S5 {Spare} I 00 1.

Crew reduces power to :5 3840 MWt within two minutes of recirc pump runaway.

KlA 2.4.49 Conduct of Operations Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. RO: 4.0 SRO: 4.0 KlA 202002 Recirculation Flow Control System A4 Ability to manually operate and/or monitor in the control room:

A4.04 Reactor Power RO: 3.8 SRO: 3.8 KIA 295014 Inadvertent Reactivity Addition AA 1 Ability to operate and/or monitor the following as they apply to Inadvertent Reactivity Addition:

AA1.02 Recirculation Flow Control System RO: 3.8 SRO: 3.8 The 'A' Reactor Recirculation Pump runaway results in the reactor power exceeding the licensed limit. Without operator action, power will stabilize at or slightly above 100.5%. This exceeds the 100% power limitation of 3840 MWth specified in Technical Specification 2.C. Operator action is required to restore reactor power to within licensed limits. The transient will be immediately annunciated by the LPRM UPSCALE OHA. Two minutes is adequate time to recognize the condition and take the appropriate Immediate Operator Actions to reduce power to within licensed limits.

2.

The Crew inserts a manual scram and closes at least one MS/V in each Main Steam Line and the HV-F016 or F019 drain valve before MSL radiation has been above the Hi-Hi setpoint for three minutes.

KlA 239001 Main Steam and Reheat Steam System A2 Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.05 tMain steam line high radiation RO 3.9 SRO 4.2 Hope Creek was originally designed with an automatic reactor scram and MSIV isolation on Hi-Hi MSL Radiation levels. This was designed to limit the release to the public during a Control Rod Drop Accident. As part of an industry effort to reduce spurious MSIV isolations, the automatic scram and MSIV isolations were removed in Tech Spec Amendment 54. One of the three conditions for approval of this amendment was that we would have procedures to expeditiously control significant increases in MSL radioactivity to limit both occupational doses and environmental releases. To meet this requirement, AB.RPV-0008 directs scramming the reactor and closing the MSIVs if a valid MSL Hi-Hi radiation condition exists. In this scenario, three minutes provides adequate time to initiate a manual scram and close the MSIVs and drains. This includes the valve stroking time. In order to accomplish isolation of the release, only one valve in each line need be closed. For instance, closing all valves but the F019 would meet the Critical Task. The failure to close this valve would be applied to the overall performance evaluation.

Isolating the lines BEFORE receiving the Hi-Hi alarms is a conservative action that also satisfies this Critical Task. Scramming prior to the fuel cladding failure and subsequently closing the MS1Vs lAW the above requirements also satisfies this Critical Task.

ESG-NRC-S5 (Spare) Page 19 of 25 Rev.: 00

3.

Crew determines that Suppression Pool water level cannot be maintained above 38.5" and initiates opening of five SRVs before Suppression Pool level reaches 3~.

KiA 295030 Low Suppression Pool Water Level EA2 Abil'ty to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL EA2.01 Suppression Pool level RO 4.1 SRO 4.2 KIA 218000 Automatic Depressurization System A.4 Ability to manually operate and/or monitor in the control room:

A4.01 ADS Valves RO 4.4 SRO 4.4 If Suppression Pool Level drops below 38.5", the downcomer pipes are uncovered and the Pressure Suppression function of the Primary Containment is lost. EOPs direct Emergency Depressurizing if Suppression Pool level cannot be maintained above 38.5". Requiring the Emergency Depressurization to be initiated before Supp Pool Level reaches 30" allows the Crew three minutes to implement this action in this scenario.

ESG-I\lRC-S5 (Spare) Page 20 of 25 Rev.: 00

ESG-NRC-S5 (Spare) I 00 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT YIN EVENT Loss Of Offsite PowerlSBO --- Internal Flooding LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Y Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening Y Manual Scram COMPONENTfTRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN KEY EQUIPMENT YIN KEY EQUIPMENT Hard Torus Vent SLC HPCI CRD 1E4.16KV Bus 1E 125VDC SACS Hx!Pump EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power AlB RHR SRVs RCIC CondensatefFeedwater SSW Pump Y PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION Y Aligning RHR for Suppression Pool Cooling

_ _ _ Emergency Venting of Primary Containment Emergency Depressurize RPV WIO High Pressure Injection Initiating LP ECCS with No High Pressure Injection Available Restoration of AC Power after a LOP (EDG IOffsite)

_ _ _ Monitoring and Control of SACS heat loads

_ _ _ Preventing LVL 8 trip of Feedwater during a transient

___.. __ Align Core Spray Suction to CST when at NPSH limits

_ _ _ Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus

_.._ . _ Inhibit ADS during ATWS Complete this evaluation form for each ESG.

ESG-NRC-S5 (Spare) Page 21 of 25 Rev.: 00

Rx Power: 100%

Work Week: A Risk Color: Green Activities Completed Last Shift:

None Major Activities Next 12 Hours:

Swap in service SSW pumps from "8" to "D".

The "D" SSW Traveling Screen has been run for >30 minutes.

SSW Chlorination has been removed from service.

Protected Equipment:

None Tagged Equipment:

'8' EHC Pump is tagged for maintenance.

ESG-NRC-S5 (Spare) Page 22 of 25 Rev.: 00

v t e Letter Sequence Other
TAC:U01788, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML102600085, ML102600125, ML102600129, ML102600138, ML103410313
MONTHYEAR2010-06-07 [Table View]

ML102600138

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