ML12111A202: Difference between revisions

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| number = ML12111A202
| number = ML12111A202
| issue date = 01/23/2012
| issue date = 01/23/2012
| title = Hope Creek - Draft Operating Exam (Sections a, B, and C) (Folder 2)
| title = Draft Operating Exam (Sections a, B, and C) (Folder 2)
| author name =  
| author name =  
| author affiliation = NRC/RGN-I/DRS/OB
| author affiliation = NRC/RGN-I/DRS/OB

Revision as of 15:16, 4 April 2019

Draft Operating Exam (Sections a, B, and C) (Folder 2)
ML12111A202
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 01/23/2012
From:
Operations Branch I
To:
Public Service Enterprise Group
Jackson D E
Shared Package
ML113070699 List:
References
TAC U01845
Download: ML12111A202 (389)


Text

--JOB PERFORMANCE STATION: Hope Creek SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup TASK NUM BER: 2630010201 JPM NUMBER: 30SH-JPM.ZZ024 REV #: 01 SAP BI:T: NOH05JPZZ24E ALTERNATE PATH: D APPLICABILITY:

EO RO STA SRO 00 DEVELOPED BY: Archie E. Faulkner DATE: 1/12/12 REVIEWED BY: APPROVED BY: DATE: qy-qJL }/)1 Q Training Department


STATION: Hope Creek JPM NUMBER: ZZ024 REV: 01 SYSTEM: Administrative TASK NUMBER: 2630010201 TASK: Conduct Weekly Power Distribution Lineup ALTERNATE PATH: D KIA NUMBER: 2.1.31 APPLICABILITY:

EO D RO [KJ STA D IMPORTANCE FACTOR: SRO D 4.2 RO 3.9 SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-ST.ZZ-0001, Revision 33 TOOLS, EQUIPMENT AND PROCEDURES:

Partially completed HC.OP-ST.ZZ-0001 ESTIMATED COMPLETION TIME: 27 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 23



DATE: SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup TASK NUMBER: 2630010201 INITIAL CONDITIONS: Emergency Diesel Generator AG400 has a mechanical problem and is declared inoperable.

It is expected to return in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is determined to be a short term outage. Station Power Transformer 1T-60 was removed from service due to cooling fan malfunctions.

The switchyard was re-aligned to support tagging. HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, is due. Salem Unit 3 Gas Turbine Generator is available. This procedure is being performed to satisfy Technical Specification Surveillance requirement 4.8.1.1.1.a.

INITIATING CUE: Perform HC.OP-STZZ-0001, POWER DISTRIBUTION LINEUP -WEEKLY to Technical Specification 4.8.1.1.1.a Page 3 of 23


TQ-I-\A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM:

TASK: Conduct Weekly Power Distribution (*Denotes a Critical Step) *STEP ELEMENT (#Denotes a Sequential Step)NO. #STANDARD CUE PROVIDE the operator the Operator repeats back initiating cue. CUE ENTER START TIME Operator repeats back the Cue: I START TIME: CUE Provide the operator with a copy the partially completed Operator reviews precautions and limitations.

Operator reviews precautions and limitations.

CUE IE excessive time is taken precautions and THEN INFORM operator that all N/A satisfied. COMMENTS (Required for UNSAT evaluation Operator determines beginning step Operator determines correct beginning of the procedure.

step to be 5.1. Page 4 of 23


5.0 TQ-MA-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM:

TASK: Conduct Weekly Power Distribution (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #STANDARD evaluati S/U Power Distribution Lineup N/A 5.1 LOG test start time in the Control Room log(s). Operator requests that the start time be logged in the Control Room log. CUE The test start time has been logged in the Control Room log. Operator initials the step. Page 5 of 23


TQ-l-'l.A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative T,L\.SK: Conduct Weekly Power Distribution Lineup STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.2 ENSURE

that all prerequisites have been satisfied lAW Section 2.0 of this procedure.

Operator ensures that the prerequisites are satisfied:

  • Observes that permission to complete the test has been given by the OSIeRS.
  • Operator completes Att. 1. Section 3.
  • Ensures no other testing or maintenance is in progress that will adversely affect the performance of this test. Operator initials the step. CUE IF asked. "No other testing or maintenance is in progress that will adversely affect the performance of this test." NA Page 6 of 23


TQ-kA-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

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

StU 5.3 ENSURE Attachment 1, Section 1.0 Operator observes that Attachment 1 , of the SM/CRS Data and Signature Section 1.0 of the SM/CRS Data Sheet has been completed Signature Sheet has been Regular Surveillance or Retest and Regular Surveillance is , , Operator initials the step. Operator determines that TIS Surveillance 4.8.1.1.1.a 5.4 lE performing this procedure to satisfy sections only are to be completed and PERFORM the following sections:

initials step. [TIS 4.B.1.1.1.a] 4.16KV SWITCHGEAR 10A401 4.16KV SWITCHGEAR 10A402 4.16KV SWITCHGEAR 10A403 4.16KV SWITCHGEAR 10A404 OFFSITE TO Page 7 of 23


TQ-.kA-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD

  • EVAL # Stu COMMENTS (Required for UNSAT evaluation) 5.4.1 When in an extended outage for A or B EDG, VERIFY, through Salem operations, that Salem Unit 3 Gas Turbine Generator is available to supply Hope Creek #2 Station Power Transformer AND LOG ON OFFSITE TO ONSITE DISTRIBUTION.

Operator determines the outage of A EDG is not an extended outage. Examiner Note: The field on Attachment 2 for the Salem Unit 3 Gas Turbine is not required but may be filled in by the operator since the status is listed on the Initial Conditions sheet. 5.5 RECORD M&TE identification numbers and calibration due dates for test equipment utilized for this test on Attachment 3 and the PSEG Nuclear Home Page. Operator determines that this step is not required and marks step as N/A.

Page 8 of 23


TQ-hA-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluation)

5.6 PERFORM

Power Distribution Lineup by completing Attachment

2. Operator observes the breaker positions, (and bus Voltage for the 4.16KV busses) of those breakers listed in Attachment 2 for:
  • OFFSITE TO ONSITE DISTRIBUTION The operator notes the positions/voltages on the attachment, enters SAT, and initials as the performer.

Page 9 of 23


TQ-hl""\-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup COMMENTS (*Denotes a Critical Step) *STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step) NO. # evaluation)

STANDARD StU 5.7 IF any indication not specified in Operator determines that the lineup

  • Attachment 2 was used to satisfy this specified in Attachment 2 was not in surveillance THEN DOCUMENT REQUIRED positions used to JUSTIFY its use in Section 2.1.4 this surveillance, marks those Attachment 1 UNSAT and informs the CRS. Examiner Note: See attached grading key. Operator initials the step. .... ...... .._---_.. 5.8 LOG test end time in Control CUE Log entry completed.

Operator initials the step. 5.9 SUBMIT this procedure to the SM/CRS for review AND completion of Attachment

1.

Page 10 of 23


TQ-kA-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) ELEMENT EVAL (Required for UNSAT NO. #STANDARD S/U evaluation WHEN operator informs you the task OR the JPM has been terminated other

...!...:....:.=.:...::.

RECORD the STOP CUE N/A REPEAT BACK any message from the operator on the status of the JPM, and state "This JPM is complete", STOP TIME: Page 11 of 23


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ZZ024 TASK: Conduct Weekly Power Distribution Lineup TASK NUMBER: 2630010201 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT TQ*AA*106*0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Emergency Diesel Generator AG400 has a mechanical problem and is declared inoperable.

It is expected to return in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is determined to be a short term outage. Station Power Transformer 1 T-60 was removed from service due to cooling malfunctions.

The switchyard was re-aligned to support HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, is due. Salem Unit 3 Gas Turbine Generator is available. This procedure is being performed to satisfy Technical Specification requirement INITIATING CUE: Perform HC.OP-ST.zZ-0001, POWER DISTRIBUTION LINEUP WEEKLY to satisfy Technical Specification 4.8.1.1.1.a only. Paae 13 of 23


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to 100% power, MOL. ENSURE associated Schedule file open and running. ENSURE associated Events file open. Complete Section 1 for Regular Surveillance and 4.8.1.1.1.a Setup Electrical Distribution System as noted on page 24 of Attachment COMPLETE "Simulator Ready-for-Training/Examination Event code: *

Description:

Event code:

Description:

Event code:

Description:

Page 14 of23

JOB PERFORMANCE SIMULATOR SETUP . Event Action Page 15 of 23 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ024 Date Description Validation Required?

1/12/12 Modified Malfunction, Remote, Override, and Event list sections Y for TREX event syntax. Updated Reference procedure revision numbers and step numbers. Validated with 2 ROs 1/3/12. Avg completion time is 27 minutes.

PSEG Internal Use Only HC.OP-ST.ZZ-0001 (0) ATTACHMENT Page 6 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE SATI REQUIRED ACTUAL UNSAT PERF CHANNEL A 4.16KV SWGR 10A401 40101 ALTERNATE FEEDER BKR TO 10A401 OPEN OPEN SAT 40103 10A401 FEED TO 10B450 CLOSED CLOSED SAT 40107 EDG AG400 OUTPUT BKR TO 10A401 OPEN SAT 40108 NORMAL FEEDER BKR TO BUS 1 D SAT 40110 10A401 FEED TO 10B410 CLOSED SAT IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 1E BUSES AND (1) 4.16 KV NON-1E BUS ON EACH STATI()N SERVICE TRANSFORME 01, 1 BX501)] WITH TAP CHANGER IN AUTO, RECORD THE: FOLLOWING REAe!>NG AS PRIMARY INDICATION (FLUKE SECONDARY)) (NOTES 2,3,4,&6) . 4.16 KV Bus 10A401 Voltage IF IN AN ABNORM ON (1) SST' (NOTES 2, 4.16 KV Bus CIR CIRCLE ONE: CRIDS (A7061) 4173 -4370 4245 -4370 10A401 Voltaqe Fluke Model 45) 121.14 -125.0 4272 SAT Initials Initials Initials Initials Initials Initials * * *

  • The asteris"\

indicates Acceptance Criteria -in order to satisfy the requirements of the acceptance criteria, the SAT/UNSAT block must be marked SAT. (2) Voltage outside MINIMAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage. IF Bus Voltage is outside the MINIMAX take Manual control of Load Tap Changer and ADJUST until voltage is within range. Voltage> MAX with Load Tap Changer on 1 position is normal during certain conditions (Le., HI grid voltage andlor no loads on bus.) (NOTE: If in a normal 2 bus alignment with tap changer in manual and voltage remains within established limits, tap changer should be returned to AUTO. (RefElr to the appropriate CRIDS point for the Station Service Transformer Sec. Voltage).

[70038637]

(3) Instructions on the use of a Fluke (Model 45) to obtain Bus Voltage Values can be found in HC.OP-SO.MC-0001(Z), Fluke (Model 45) Hookup and Voltage Readings at PT Secondary.

(4) IF Bus Volta!Je cannot be adjusted>

MIN, DECLARE the respective offsite circuit of the A.C. electrical power source INOP AND ENTER TIS 3.8.1.1.a Action Statement.

IF Bus cannot be adjusted < MAX, GENERATE notification to Hope Creek Electrical

/ I&C, System Engineering documenting each voltage operating limit violation (start & stop times), so that 4.16 KV System Engineer can track and analyze voltage levels, lAW Notification 20184742.

[70038770]

(6) 4.16 KV Bus3s supplied from a common Station Service Transformer (1AX501, 1 BX501) have the same voltage and associated GRIDS points should read the same discounting instrument loop inaccuracies.

If in normal 2 bus (or less) alignment, any of the following CRIDS points are considered equivalent and may be substituted for any other if one or more is a failed in:licator: (For 1AX501:

A3209, A3484, A7061 , A7066) (For 1 BX501: A3210, A3487, A7076, A7071 Rev.15 1 OA403 Voltage IF IN AN ABNORMAL BUS ALiGNM ON (1) SST; OR, (4) 4.16 KV CL :1 ) 119.09 -125.0 CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS AND (2) 4.16 KV NON-1E BUS ON (1) SST) PSEG Internal Use Only HC.O P-ST.ZZ-0001 (Q) ATTACHMENT Page 9 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 PowHr Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE SATI REQUIRED ACTUAL UNSAT PERF CHANNEL C 4.16KV SWGR 10A403 OPEN 40301 ALTERNATE FEEDER BKR TO 10A403 SED SA T Initials OPEN CLOSED CLOSED SAT Initials *10A403 FEED TO 10B470 40303 Manual cont*ol of Load Tap Changer and ADJUST until voltage is within range. Voltage> MAX with Load Tap Changer on 1 pOSition is normal during certain conditions (i.e., HI grid voltage andlor no loads on bus.) (NOTE: If in a normal 2 bus alignment with tap changer in manual and voltage remains within established limits, tap changer should be returned to AUTO. (Refer to the appropriate CRIDS point for the Station Service Transformer Sec. Voltage).

[70038637]

(3) Instructions on the use of a Fluke (Model 45) to obtain Bus Voltage Values can be found in HC.OP-SO.MC-0001 (Z), Fluke (Model 45) Hookup and Voltage Readings at PT Secondary.

(4) IF Bus Voltage cannot be adjusted>

MIN, DECLARE the respective offsite circuit of the A.C. electrical power source INOP AND ENTEf;: TIS 3.8.1.1.a Action Statement.

IF Bus VoltWle cannot be adjusted < MAX, GENERATE notification to Hope Creek Electrical I I&C, System Engineering documenting each voltage operating limit violation (start & stop times), so that 4.16 KV System Engineer can track and analyze voltage levels, lAW Notification 20184742.

[70038770]

(6) 4.16 KV BUS3S supplied from a common Station Service Transformer (1 AX501, 1 BX501) have the same voltage and associated CRIDS points should read the Same discounting instrument loop inaccuracies.

If in normal 2 bus (or less) alignment, any of the following CRIDS points are considered equivalent and may be substituted for any other if one or more is a failed in:licator: (For 1 AX501: A3209, A3484, A7061 , A7066) (For 1 BX501: A321 0, A3487, A7076, A7071 Rev.15 40307 EDG CG400 OUTPUT BKR TO 10A403 OPEN OPEN SA T 40308 NORMAL FEEDER BKR TO BUS 10A403 SA T 40310 10A403 FEED TO 10B430 IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLASS 1E BU EACH STATION SERVICE TRANSFORMER (SST) (1AX501..

X50 SAT 4. KV NON-1E BUS ON H TAP CHANGER IN AUTO, RECORD THE FOLLOWING READING (USE CRIDS AS* INDICATION (FLUKE SECONDARY)) (NOTES 2,3,4,&6) 4173-4370 4.16 KVBus SAT 4272 (NOTES 2, 3, 4, & 6) 4.16 KVBus 4245 -4370 10A403 Voltage Fluke (Model 45) 121.14 -125.0

  • The asterisk indicate cceptance Criteria -in order to satisfy the requirements of the acceptance criteria, the SAT/UNSAT block must be marked SAT. (2) Voltage outs de MINIMAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage. IF Bus Voltage is outside the MINIMAX take Initials Initials Initials * *Initials PSEG Internal Use Only HC.OP-ST.ZZ-0001 (Q) ATTACHMENT Page 12 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SATI UNSAT PERF CHANNEL B 4.16KV SWGR 10A402 40201 CLOSED 40203 NORMAL FEEDER BKR TO 10A402 10A402 FEED TO 10B460 EDG BG400 OUTPUT BKR TO 40208 ALTERNATE FEEDER BKR TO 10A402 FEED TO 108420 SAT CLOSED Initials Initials SAT CLOSED

  • SAT Initials OPEN OPEN SAT Initials Initials CLOSED SAT
  • IIF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 K BUSES AND (1) 4.16 KV NON-1E BUS ON EACH STATION SERVICE TRANSFORMER ( ", 1 BX501}] WITH TAP CHANGER IN AUTO, RECORD THE FOLLOWING ( PRIMARY INDICATION (FLUKE SECONDARY)) (NOTES 2,3,4,&6) 14.16 KV Bus 10A402 Voltaqe IF IN AN ABNOR ON (1) SST; a CIRC 4173-4370 4253 SAT Initials

  • NOTES 2, 3, 4, 4.16 KV Bus 4245 -4370 10A402 Voltaqe Fluke (Model 45) 121.14 -125.0
  • The asterisk indicates Acceptance Criteria -in order to satisfy the requirements of the acceptance criteria.

the SAT/UNSAT block must be marked SAT. (2) Voltage outside MINIMAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage. IF Bus Voltage is outside the MIN/MAX take Manual control of Load Tap Changer and ADJUST until voltage is within range. Voltage> MAX with Load Tap Changer on 1 position is normal during certain conditions (i.e., HI grid voltage and/or no loads on bus.) (NOTE: If in a normal 2 bus alignment tap changer in manual and voltage remains within established limits, tap changer should be returned to AUTO. (RefEr to the appropriate CRIDS point for the Station Service Transformer Sec. Voltage).

[70038637]

(3) Instructions on the use of a Fluke (Model 45) to obtain Bus Voltage Values can be found in HC.OP-SO.MC-0001(Z), Fluke (Model 45) I-ookup and Voltage Readings at PT Secondary.

(4) IF Bus Voltage cannot be adjusted>

MI N, DECLARE the respective offsite circuit of the A.C. electrical power source INOP AND ENTER TIS 3.8.1.1.a Action Statement.

IF Bus Voltage cannot be adjusted < MAX, GENERATE notification to Hope Creek Electrical/l&C, System Engineering documenting each voltage operating limit violation (start &stop times), so that 4.16 KV System Engineer can track and analyze voltage levels, lAW Notification 20184742.

[70038770]

(6) 4.16 KV BUS(lS supplied from a common Station Service Transformer (1AX501, 1 BX501) have the same voltage and associated CRIDS points should read the same discounting instrument loop inaccuracies. If in normal 2 bus (or less) alignment, Giny of the following CRIDS points are considered equivalent and may be substituted for any other if one or more is a failed indicator: (For 1AX501: A3209, A3484, A7061, A7066) (For 1BX501: A3210, A3487, A7076, A7071 Rev.15 PSEG Internal Use Only HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 2 Page 15 of 33 INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 POWEU Distribution Lineup (Continued)

I EQUIP ME'_JT-!-___N_O_IVI_E_N_C_L_A_T_U_R_E

___

A_C_T_U_A_L....L...._SA_T_I

......_P_ER_F-., _ UNSAT! , CHANNEL 4.16KV SWGR 10A404 Initials Initials *SAT CLOSED Initials 40407 EDG AG400 OUTPUT BKR TO 10A404 OPEN SAT OPEN OPEN SAT Initials 40401 NORMAL FEEDER BKR TO 10A404 CLOSED CLOSED 40403 10A401 FEED TO 10B480 CLOSED SAT Initials.

__-!--'I10A404 *I 40410 10A401 FEED TO 10B440 ,IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLAS (1) 4.16 KV NON-1E BUS ON lEACH STATION SERVICE TRANSFORMER (SST) 50 501)] WITH TAP CHANGER IN AUTO, RECORD THE FOLLOWING READING (USE C RI ARY INDICATION (FLUKE SECONDARY)) (NOTES 2,3,4,&6) 4.16 KV Bus 10A404 Voltage IF IN AN ABNORMAL ON (1) SST; OR, (4) 4. 4173-4370 4253 SAT 4245 -4370 Fluke (Model 45 121.14 125.0 Initials *

  • The asterisk Icates Acceptance Criteria -in order to satisfy the requirements of the acceptance criteria, the SAT/UNSAT block must be marked SAT. (2) Voltage outside MINIMAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage. IF Bus Voltage is outside the MINIMAX take Manual control of Load Tap Changer and ADJUST until voltage is within range. Voltage> MAX with Load Tap Changer on 1 position is normal during certain conditions (Le., HI grid voltage andlor no loads on bus.) (NOTE: If in a normal 2 bus alignment with tap changer in manual and voltage remains within established limits, tap changer should be returned to AUTO. (Refer to the appropriate CRIDS point for the Station Service Transformer Sec. Voltage).

[70038637J (3) Instructions on the use of a Fluke (ModeI4S) to obtain Bus Voltage Values can be found in HC.OP-SO.MC-0001 (Z), Fluke (Model 4S) Hookup and Voltage Readings at PT Secondary.

(4) IF Bus Voltage cannot be adjusted>

MIN, DECLARE the respective offsite circuit of the A.C. electrical power source INOP AND ENTER TIS 3.8.1.1.a Action Statement.

IF Bus Voltage cannot be adjusted < MAX, GENERATE notification to Hope Creek Electrical/l&C, System Engineering each voltage operating limit violation (start & stop times), so that 4.16 KV System Engineer can track and analyze voltE.ge levels, lAW Notification 20184742.

[70038770]

(6) 4.16 KV Buses supplied from a common Station Service Transformer (1AXS01, 1 BXS01) have the same voltage and associated CRIDS pOints should read the same discounting instrument loop inaccuracies.

If in normal 2 bus (or less) alignment, any of the following CRIDS points are considered equivalent and may be substituted for any other if one or more is a failed indicator: (For 1AX501: A3209, A3484, A7061 , A7066) (For 1BX501: A3210, A3487, A7076, A7071 Rev.15 PSEG Internal Use Only HC.OP-ST.ZZ-0001 (Q) ATTACHMENT Page 24 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution (Continued}

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SATI PERF UNSAT OFFSITE TO ONSITE DISTRIBUTION BS4-5 13KV BUS SECTION 4-5 BKR CLOSED CLOSED SAT Initials 13KV BUS SECTION 6-7 BKR CLOSED OPEN Initials i STAXFMR T2 CIRCUIT SWITCHER CLOSED CLOSED SAT Initials 4T60 STA XFMR T4 CIRCUIT SWITCHER CLOSED CLOSED SAT Initials I BS3-4 500KV BUS SECTION 3-4 BKR CLOSED CLOSED SAT

  • Initials i 500KV BUS SECTION 6-5 BKR CLOSED CLOSED BS7-8 13KV BUS SECTION 7-8 BKR OPEN BS2-3 13KV BUS SECTION 2-3 BKR BS1-2 13KV BUS SECTION 1-2 BKR BS9-0 13KV BUS SECTION 9-10 BKR 3T60 CLOSED CLOSED SAT Initials.

BS1-3 CLOSED CLOSED SAT Initials . BS5-1 CLOSED CLOSED SAT Initials + * * * * * * *

  • i 85#2-6 5 CLOSED CLOSED SA T Initials
  • AVAILABLE

+ NOTE:: The above alignment represents the normal lineup of the 500KvJ13.8Kv Switchyards.

Deviations may exist while still maintaining two independent offsite power source separation.

IF actual alignment deviates from the above, CONSULT Electrical Drawing E-0001-0 to determine if proper separation exists, and lAW the following criteria:

500Kv Bus Sections 1 & 2 energized by two offsite sources (Red Lion 5015, New Freedom 5023, or Salem X-Tie 5037). Two fl:;eds (1 OX and 20X) into a split 13.8Kv Yard, with each feed supplying power to an energized separate Station Service Transformer (AX501 and BX501). An independent offsite feed is considered available to the safety related distribution system IF all four of the 1 E infeed breakers are OPERABLE.

IF less than 4 breakers are OPERABLE, CONSIDER the offsite feed inoperable and comply with ACTION 3.8.1.1 as appropriate.

  1. Salem Unit 3 Turbine Generator is only required when in an extended A or B EDG outage. Rev.15

2.1.1 SATISFACTORY

(All acceptance criteri DATE-TIME 2.1.2 DATE-TIME PSEG Internal Use HC.OP-ST.ZZ-0001 (Q) ATTACHMENT Page 2 of SM/CRS DATA AND SIGNATURE POWER DISTRIBUTION LINEUP -POST TEST INFORMATION The data acquired during the performance of this test has been reviewed for completeness and compliance with Technical Specification 4.8.3.1, 4.8.3.2, 4.8.1.1.1.a and the test is considered:

Rev.15 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201

..IPM NUMBER: 305H-JPM.ZZ016 REV#: 01 SAP BET: NOH05JPZZ16E ALTERNATE PATH: D APPLICABILITY:

EO RO [KJ STA SRO DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: <<K -CtitJl DATE: APPROVED BY: DATE: cnt0lL:: )J?D)})I Training Department


STATION: Hope Creek JPM NUMBER: ZZ016 REV: 01 SYSTEM: Administrative TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs ALTERNATE PATH: D KIA NUMBER: 2.1.18 APPLICABILITY:

EOD ROCK] S IMPORTANCE FACTOR: 3.6 RO TAD SROD 3.8 SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-DL.ZZ-0026 Rev. 129 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 16 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: ___I'J_/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:

SIGNATURE:

___________

_ Page 2 of 18


DATE: ____________________

__ SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 INITIAL CONDITIONS:

1. The Plant has been in OPCON 1 at 100% power, steady state, for 7 days. INITIATING CUE: Complete the Day Shift Daily Surveillance Logs for 10C609, 1 OC611 AND MSL Radiation (Items (31-74 of Attachment 1a) lAW HC.OP-DL.ZZ-0026.

Page 3 of 18


TO-I"\A-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM:

TASK: Complete The Daily Surveillance I STEP NO. CUE CUE ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: Operator obtains the correct procedure.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. N/A Operator obtains procedure HC.OP-DL.ZZ-0026

  • # EVAL StU COMMENTS (Required for UNSAT evaluation)

_ 3.1 COMPLETE Attachment 1 (all subsections) daily. Operator records readings for Items 61-74 of Attachment 1 a for the Day Shift. Examiner Note: lAW the Initiating Cue, only Items 61-74 of Attachment 1 a are required.

Refer to Exhibit 1 for expected values. Values are typical and may not exactly match observed values. Readings are SAT if they are within +/-1 meter division of actual reading.

  • Page 4 of 18

TQ-.....""'-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM:

TASK: Complete The Daily Surveillance STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # COMMENTS (Required for UNSA T evaluation 3.2 IF in OP CON 4 or 5, THEN Operator determines this step does not COMPLETE Attachment 2 as follows apply. daily: 3.3 COMPLETE Attachment 4 to perform Operator determines this step does not surveillances required by Special Test apply. Exceptions as necessary.

Examiner Note: lAW the Initiating Cue, only Items 61-74 of Attachment 1 a are required.

3.4 ENTER

the Operational Condition and date on each page of the log the blanks provided.

Operator enters the Operational Condition and date in the blanks provided.

3.5 COMPLETE

the applicable subsections of Attachment 3 as directed by the SM/CRS to satisfy Surveillance Requirements which require accelerated surveillances due to off-normal conditions.

Operator determines this step does not apply. Examiner Note: lAW the Initiating Cue, only Items 61-74 of Attachment 1a are required.

Page 5 of 18



TQ-J'"\A-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM:

TASK: Complete The Daily Surveillance COMMENTS (*Denotes a Critical Step) *STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO. # eval STANDARD S/U 3.6 COMPLETE all surveillances as WHEN the deviation for Item 65 (RPV indicated in each LEVEL 3) is recognized to exceed IF a Technical MAX DEVIATION of Surveillance cannot be THEN Operator notifies CRS of completed OR is unsatisfactory THEN IMMEDIATELY NOTIFY SM/CRS AND the Duty AND corrective action initiated be noted in the comments Repeat back message from Operator on Item 65 CUE Examiner Note: Since no work abnormal reading, THEN NOTE 3.6.1 IF a work order is issued to repair an number will be provided to the operator, work order number in the comment this step will not Examiner Note: Since no issued due to a failed 3.6.2 IE an Action Statement Log Sheet is Statement Log Sheet Index Number will OR one is already issued that covers be provided to the operator, this the failed surveillance, THEN will not the Action Statement Log Sheet Number in the comments Page 6 of 18 TQ-nA-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: __________________

_ Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM:

TASK: Complete The Daily Surveillance COMMENTS (*Denotes a Critical Step) *STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD evaluatio StU 3.6.3 IF a surveillance item is out-of-spec or WHEN the deviation for Item 65 (RPV not successfully completed, LEVEL 3) is recognized to exceed THEN REFER to step 3.11 for MAX DEVIATION of reference numbers and THEN Operator refers to Step 3.11 for Item 65 TIS reference numbers and notes. Operator performs channels checks on 3.7 IF performing a channel check that

  • requires a comparison between Attachment 1 a Items 61-74, record the difference between the high and THEN RECORD the value and trip status, and between the high and low value the value for Item 65 exceeds the trip DEVIATION of 4. Examiner Note: Critical portion is recognizing the Item 65 deviation exceeds the MAX DEVIATION.

Note: The trip status is indicated by the following: The trip light for supplied with trip The alarm(s) ANDIOR actions for instruments supplied by trip Page 7 of 18


TQ-,....A-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL Stu COMMENTS (Required for UNSAT evaluation) 3.8 For checks which are performed after the logs have been taken for the time period, or, when a check is performed more than once during an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period: OBTAIN a blank copy of the respective sheet, COMPLETE surveillance, (including time and date) AN NOT ATE on the sheet and in comments section, as necessary, why the additional check was performed ATTACH sheetto existing daily log package. Operator determines this step does not apply. Page 8 of 18


TQ-I'-<I"\-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs (*Denotes a Critical Step) COMMENTS*STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)NO. # S/U evaluatL __ , STANDARD 3.9 COMPLY with the requirements regarding log numbers followed by "at sign" lE a surveillance log item number DOES NOT have an "at sign" (@) following THEN, instrument(s) or methods than that designated in the log item be used to satisfy that requirement as long as an assessment 3.9.1 Operator takes all readings from the the eq uivalency of the alternative identified instrument.

instrument/method has been made the results have been noted in comments section. An example of constitutes an "acceptable" review can be found under Activity of Order lE a surveillance log item number has an "at sign" (@) following THEN, ONLY the instrument(s) in the log item may be used to satisfy 3.9.2 Operator takes all readings from the surveillance requirement, except that identified can take voltage readings on instrument(s) and the results before declaring the system Page 9 of 18



TQ-hA-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP NO. CUE ELEMENT WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

N/A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL COMMENTS (Required for UNSAT evaluati STOP TIME: Page 10 of 18


NUMAC KEY) WI-lEN HC.OP-DL.ZZ-t J(Q) Surveillance Log -Control Room -Day Shift Operational Condition Date Today's Date ITEM SURVEILLANCE OPER COND INST PANEL 10C609 VALUE I INST VALUE INST PANEL 10C611 VALUE I INST VALUE INST I MAX DEVIATION DEVIATION ACCEPTABLE LIMITS MIN I NORM I MAX INST TRIPPED YES/NO a:-1.ee.. RPV rRESSUR[ 1,2 No7SA DRYWELL PRESSURE 11.2,3 I N650A NOTE 29. 1010 i'>i678C iOiO N678ts +___+1_. -: NO 980 N678D 81:lU 30 -62@ 63@ 1 CONDENSER VACUUM 64@ 1 MSL PRESSURE RPV L[VEL 3 1 66@ I NORTH SDV LEVEL (NOTE 61) 67@ I SOUTH SDV LEVEL (NOTE61) 68@ I MSL A FLOW 69@ MSL B FLOW 70@ MSL C FLOW @ RPV LEVEL 1 73@ RWCU dF (NOTE 56., 57.) I 74@ MSL RADIATION (NOTES 53.., 54 ..) 1,2,3 1,2,5 1,2,5 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 N675A N676A N680A N/A N60iA N686A N687A N688A N684A XR1i497 0.5 27.0 950 42 N/A o 79 79 72 N/A o N650C N675C N676C N68QC N60iC N/A N686C N687C N688C N61 N684C N/A 0.4 26.5 950 34 o N/A 80 75 78 N/A N/A N650B 0.3 N675B I 26.5 N676S I 940 N680B I 34 N/A TN/A N601B 1 0 N650D N675D N676D N680D N60iD N/A 0.4 0.2 0 -..2 Ie i N/A 0 N/A 1 N/A IXR114991 01 0 NO NO NO NO FOR ANY INSTRUMENT FOUND TRIPPED, PLACE A 'T' IN FOR NON-INDICATING TRIP UNITS, CIRCLE THE TRIP UNIT DESIGNATOR IN RED AND RECORD THE INST TRIPPED COLUMN. NOTE WHEN IN OPER COND 5 -WITH ANY CONTROL ROD WITHDRAWN.

NOT APPLICABLE TO CONTROL RODS REMOVED PER SPECIFICATION 3.9.10.1 OR 3.9.10.2.

NOTE (*) -WHEN HANDLING RECENTLY IRRADIATED FUEL IN THE SECONDARY CONTAINMENT AND DURIN<JOPEr-<ATlOr,s WITH A POTENTIAL FOR DRAINING THE REACTOR VESSEL. NOTE ALSO REQUIRED WHEN SECONDARY CONTAINMENT REQUIRED TO BE IN EFFECT lAW TIS; [70 NOTE RM-11 10 MINUTE AVERAGE SHOULD BE USED TO OBTAIN CHANNEL VALUES. MSL oAn,Afl"" "",\if"j'iON WITH THE H2 INJECTION SYS OUT OF SERVICE IS 20. WITH THE H2 INJECTION SYS IN SERVICE, MAX DEVIATION CALCULATED!3Y ADDING OPERABLE CHANNEL VALUES, DIVIDING OPERABLE CHANNELS, THEN MULTIPLYING RESULT BY (0.4). IF RM-11 UNAVAILABLE, K610A, K610B, K610C, OR K610D (NUMAC) SHOULD BE USED AT PANEL 10C635/10C636.

BE TAKEN 3 -4 SECONDS INTO THE CPU SELF-TEST A.(PRESS ANY KEY; PRESS "ETC" KEY; PRESS "DISPLAY TEST STATUS" BEEN AT THE "CPU MODULE" LOCATION FOR 3 -4 SECONDS. TO RESTORE NUMAC DISPLAY (PRESS EXIT KEY; PRESS ETC KEY; PRESS DISPLAY OFF KEY). [700012301"A NOTE 54.: IF RM*11 IS AVAILABLE, AND, WHENEVER RX POWER IS ABOVE 94% RTP ANDHAS !3EEN CONSTANT FOR THE PREVIOUS 2 HOURS (NO TRANSIENT IN PROGRESS), PERFORM MSL AVERAGE FULL POWER BACKGROUND CHECK BELOW. FOR ANY VAKUE OF c < 0.834, DECLARE THE MSLRMS INOPERABLE.

IF ANY VALUE FOR ciS < 0.85 OR > 1.2 (2: 20%) THEN A RE-EVALUATION OF THE 3X NORMAL SET POINT MAY BE DESIRED USING HC.SE-GP.SP-0001 (0). NOTIFY RMS SYSTEM ENGINEER FOR SUPPORT IN RE-EVALUATION.

KEEP IN MIND THAT THIS CHECK IS ONLY VALID WHEN RX POWER IS ABOVE 94%, AND CONSTANT FOR THE PREVIOUS 2 HOURS (NO TRMJSICNT IN Pf\OGRESS).

NOTE 55.: DURING OPERATIONAL CONDITIONS 1 AND 2 WITH MECHANICAtVACUUM PUMP(S) IN-SERVICE AND ANY MAIN STEAM LINE NOT ISOLATED, THE MSL RADIATION CHANNEL CHECK BETWEEN THE ALPHA AND BRAVO CHANNELS (9RX509/9RX51 0, K61 OAlK61 OB) ALSO SATISFIES A MECHANICAL VACUUM PUMP TRIP INSTRUMENTATION CHANNEL CHECK lAW TIS 4.3.10.a.

NOTE 56.: INITIATE NOTIFICATION WHEN DEVIATION BETWEEN CHANNELS 'A AND 0 REACHES 9 GPM TO ENSURE THAT THE PROBLEM CAUSING THE DEVIATION IS CORRECTED.

NOTE 57.: . _ .........................

'H .......

.... *................ , ** L-..... ."'-"." .....-... ,' .........

.. .. . .. ........ "-

.* ---_. _..MSLRMS B MSLRMS C MSLRMS 0 MSLRMS A ,-_ MIN MSLAVERAGE FULL POWER BACKGROUND CHECK 35.8 36.8 37.5 38.5 a RM-11 LAST HOURLY AVERAGE 130 125 121 129 RM-11 HI SETPOINT b .924 c c 0.850 .865 .887 .856a / b x 3 (RATIO OF ACTUAL TO BASELINE AFPB) Page 11 of 18



JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ZZ016 TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: UNSAT SAT ,--I_---I Page 120f 18

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Plant has been in OPCON 1 at 100% power, steady state, for 7 days. INITIATING CUE: Complete the Day Shift Daily Surveillance Logs for 10C609, 10C611 AND MSL Radiation (Items (>1-74 of Attachment 1a) lAW HC.OP-DL.ZZ-0026.

Page 13 of 18


HC.OP-DL.ZZ-0026(Q)

JOB PERFORMANCE MEASURE Surveillance Log -Control Room -Day Shift Operational Condition Date I PANEL 10C609 PANEL 10C611 I __ INS! _.. 1 MAX ,LIMITS I SUR\JEILLl\NCE

,......r'\r-..ln

lC'T I \ '" I I I INST I 'fA I I I iNST I VALUE I iNST I VALUE Ut:VIAIIUN Ut:VIAIIUN MIN NORM MAX II'Cvl VI"'\L-uL V!-\LUC RPV PRESSURE 1,2 N678A N678C N678B N678D 100 1037 62@ DRYWELL PRESSURE 1,2,3 N650A N650C N650B N650D 1 1.68 NOTE 29. ---63@ CONDENSER VACUUM 1,2,3 N675A N675C N675B N67SD 2.S 8.5 64@ MSL PRESSURE 1 N676A N676C N676B N676D 80 756 65@ RPV LEVEL 3 1,2,3 N680A N680C N680B N680D 4 12.5 66@ NORTH SDV LEVEL 1,2,5 N/A N/A N601C N/A N/A N601D 10 72 (NOTE 61) 67@ SOUTH SDV LEVEL 1,2,5 N601A N/A N/A N601B N/A N/A 10 72 -(NOTE61) 68@ MSL A FLOW 1,2,3 N686A N686C N686B N686D 18 162.8 69@ MSL B FLOW 1,2,3 N687A N687C N687S N687D 18 162.870@ MSLC FLOW 1,2,3 N688A N688C N688B N688D 18 162.8 71@ MSL D FLOW 1,2,3 N689A N689C N689B N689D 18 162.8 72@ RPV LEVEL 2 (NOTE 27) 1,2,3: N681A N681B N681D 15 -38 NOTE 29. @ RPV LEVEL 1 1.2,3 N684A N/A N684C N/A N684B N/A N684D N/A N/A N/A -129 73@ RWCU dF (NOTE 56., 57.) 1.2.3 XR11497 .N/A N/A N/A N/A XR11499 20 56 RM-11 .. MSL RADIATION 1.2,3 9RXS09 ___u_ PRX510 [m u ---j9RX511 L--Jr (NOTES 53..,54.. ) NOTE 55** _. . _. -:-=.. --_.. hlr rI::* c,",o AI\IV II\ICTDIIUC:fl.IT Cl'llll\ln TCIDDcn DI Arc A IT' ltd TUC: \ll\IIIC QI f"If""1.(" AI (')f\If:::

\J\JITU Tl-Il: !I\ICTRf U..U::t\.IT \IAI lit:" Ahln r:n::rnOfl hVa::Q" ,1\, Tl..U= Ihl<':.T INST TRIPPED YES/NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO FOR NON-INDICATING TRIP UNITS, CIRCLE THE TRIP UNIT DESIGNATOR IN RED AND RECORD "YES" IN THE INST TRIPPED COLUMN. NOTE 61 WHEN IN OPER COND 5-WITH ANY CONTROL ROD WITHDRAWN.

NOT APPLICABLE TO CONTROL RODS REMOVED PER SPECIFICATION 3.9.10.1 OR 3.9.10.2.

NOTE 27 (*) -WHEN HANDLING RECENTLY IRRADIATED FUEL IN THE SECONDARY CONTAINMENT AND DURING OPERATIONS WITH A POTENTIAL FOR DRAINING THE REACTOR VESSEL. NOTE 29 ALSO REQUIRED WHEN SECONDARY CONTAINMENT REQUIRED TO BE IN EFFECT lAW TIS. [70021778J NOTE 53. RM-11 10 MINUTE AVERAGE SHOULD BE USED TO OBTAIN CHANNEL VALUES. MSL RADIATION MAX DEVIATION WITH THE H21NJECTION SYS OUT OF SERVICE IS 20. WITH THE H2 INJECTION SYS IN SERVICE, MAX DEVIATION CALCULATED BY ADDING OPERABLE CHANNEL VALUES, DIVIDING RESULT BY NUMBER OF OPERABLE CHANNELS, THEN MULTIPLYING RESULT BY (0.4). IF RM-11 UNAVAILABl.E, K610A, K610B, K610C, OR K610D (NUMAC) SHOULD BE USED AT PANEL10C635110C636.

NUMAC READINGS SHOULD BE TAKEN 3 --I SECONDS INTO THE CPU SELF-TEST ANY KEY; PRESS "ETC" KEY; PRESS "DISPLAY TEST STATUS" KEY) WHEN ARROW HAS BEEN ATTHE "CPU MODULE" LOCATION FOR 3 -4 SECONDS. TO RESTORE NUMAC DISPLAY (PRESS A A A A KEY; PRESS ETC KEY; PRESS DISPLAY OFF [700012301 NOTE 54IF RM-11 IS AVAILABLE, AND, WHENEVER RX POWER IS 94% RTP AND HAS BEEN CONSTANT FOR THE PREVIOUS 2 HOURS (NO TRANSIENT IN PROGRESS), PERFORM MSL AVERAGE FULL POWER BACKGROUND CHECK BELOW. FOR ANYVAKUE OF c < 0.834, DECLARE THE CORRESPONDING MSLRMS INOPERABLE.

IF ANY VALUE FOR c IS < 0.85 OR > 1.2 (+. 20%) THEN A RE-EVAl.UATION OF THE 3X NORMAL SETPOINT MAY BE DESIRED USING HC.SE-GPBP-0001(Q).

NOTIFY RMS SYSTEM ENGINEER FOR SUPPORT IN RE-EVALUATION.

KEEP IN MIND THAT THIS CHECK IS ONLY VALID WHEN RX POWER IS ABOVE 94%, AND CONSTANT FOR THE PREVIOUS 2 HOURS (NO TRANSIENT IN PROGRESS).

NOTE 55.: DURING OPERATIONAL CONDITIONS 1 AND 2 WITH MECHANICAL VACUUM PUMP(S) IN-SERVICE AND ANY MAIN STEAM LINE NOT ISOLATED, THE MSL RADIATION CHANNEL CHECK BETWEEN THE Al.PHA AND BRAVO CHANNELS (9RX50919RX510, K610AIK610B)

ALSO SATISFIES A MECHANICAL VACUUM PUMP TRIP INSTRUMENTATION CHANNEL CHECK lAW TIS 4.3.10.a.

NOTE 56.:INITIATE NOTIFICATION WHEN DEVIATION BETWEEN CHANNELS A AND 0 REACHES 9 GPM TO ENSURE THAT THE PROBLEM CAUSING THE DEVIATION IS CORRECTED.

NOTE 57.: *

...........

I '-"-' , , ...... , ..."'........ ,, ** ""'" '" ..... ......,' ...... ,..,\ I l-..............

__ I.....,' '" , ............

".,

  • _ ...... ' .... _....,. .. .. , ............................. , ..........

__ ......................................... .. ........................ , ..... , ...................

.....,.. ........ .....................

MSL AVERAGE FULL POWER BACKGROUND CHECK MIN MSLRMSA MSLRMS B MSLRMS C MSLRMS 0 a RM-11 LAST HOURLY AVERAGE b RM-11 HI SETPOINT c c'" a I b x 3 (RATIO OF ACTUAL TO BASELINE AFPB) 0.850


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to 100% power, MOL. Put Simulator in FREEZE. COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Page 15 of 18

JOB PERFORMANCE SIMULATOR SETUP Event None None None None None None None None None Insert malfunction RP18A to 43.00 RPS Level Xmitter LT-N080A Failure Insert malfunction RM9509 to 9RX509, MSL 'A' -Main Steam Line 37.50000 ChanA Insert malfunction RM9510 to 9RX510, MSL '8' -Main Steam Line 38.50000 Chan 8 Insert malfunction RM9511 to 9RX511, MSL 'C' -Main Steam Line 35.80000 Chan C Insert malfunction RM9512 to 9RX512, MSL 'D' -Main Steam Line 36.80000 Chan D Page 16 of 18 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM "'UMBER: ZZ016 ; I Rev# Date I Description Validation Required?

1 1/14/12 Reference procedure change only. No changes to operator N ; I I JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Recirculation TASK:: Perform a Reactor Recirculation Pump Quick Restart TASK: NUM BER: 2020160101 JPM NUMBER: 30SH-JPM.ZZ011 REV #: 01 SAP BET: NOH05JPZZ11 E ALTERNATE PATH: D APPLIGABILlTY:

EO D RO [IJ STA D SRO D DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: <"12--()"')rOtc DATE:

lOR rations Representative APPROVED BY: DATE:1//8'/J '2 Training Department


STATION: Hope Creek JPM NUMBER: ZZ011 REV: 01 SYSTEM: Reactor Recirculation TASK NUMBER: 2020160101 TASK: Perform a Reactor Recirculation Pump Quick Restart ALTERNATE PATH: KJA NUMBER: 2.2.40IMPORTANCE FACTOR: 3.4 4.7 APPLICABILITY:

RO SRO EOD ROOO STAD SROD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP*AB.RPV-0003 Rev 23 TOOLS, EQUIPMENT AND PROCEDURES:

Steam Tables/Calculator ESTIMATED COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: I\I/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 16



TQ-AA-106*0303 NAME: DATE: SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 INITIAIL CONDITIONS:

1. The Reactor was scrammed when both Reactor Recirculation Pumps tripped. 2. Evidence of thermal stratification is present. 3. Actions have been taken in accordance with HC.OP-AB.RPV-0003 through step G.11. INITIATING CUE: ComplBte HC.OP-AB.RPV-0003 step G.12 as necessary for restart of A Reactor Recirc Pump. Page 3 of 16

G.12 TQ".MA-106-0303 JPM: 22011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD evaluation)

CUE S/U PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTER START TIME Operator repeats back the Cue: I START TIME: Operator obtains the correct Operator obtains HC.OP-AB.RPV-0003. . Operator determines correct of the Operator determines beginning step step to be G.12. Operator obtains requirements are met by ENSURE Differential Temperature Attachment Attachment

2. [TIS Page 4 of 16

TQ-MA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor TASK: Perform a Reactor Recirculation Pump Quick STEP NO. 1.0 (*Denotes a Critical Step) ELEMENT (#Denotes a Sequential Step) STANDARD HC.OP-AB-RPV-0003 Attachment 2 REACTOR VESSEL TO BOTTOM HEAD DRAIN LINE DIFFERENTIAL TEMPERATURE CRITERIA NA * # EVAL StU COMMENTS (Required for UNSAT evaluation) 1.1 Rx Pressure Vessel Steam Space Coolant Saturation Temperature. (Rx Pressure and Steam Tables) (Note 1) Operator reads Note 1.

Operator determines RPV pressure 885 psig. (900 psia) Operator determines Steam space Coolant Saturation Temperature to be 900 psia 532 degF (Steam Tables)

  • I I Operator records value in space provided on Attachment
1. Page 5 of 16

TQ-AA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor TASK: Perform a Reactor Recirculation Pumo Quick -STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

Note 1 Steam Table as part of this attachment may be utilized to determine temperature rounding the numbers in a conservative fashion. For a more accurate conversion from pressure to temperature a more detailed set of steam tables should be utilized.

NA 1.2 Bottom Head Drain Coolant Temperature. (Note 2) (Computer Point A2942) Operator accesses CRI DS terminal.

Note 2 RWCU Flow required for accurate Bottom Head Drain Coolant Temperature indication.

Operator reads Note 2. Operator determines RWCU is in service and the Bottom Head Drain Coolant Temperature is valid. Operator obtains value of 467 degF from CRIDS point A2942.

  • Page 6 of 16

TQ-MA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.3 < 145°F between Rx Pressure Vessel Steam Space Coolant AND Bottom Head Drain Line Coolant (A -B). [TIS 4.4.1.4] Operator subtracts value of step 1 from value of step 1.1. and determines value of 65 degF + 1 F.

  • Operator records value in space provided. 1.4 Time Readings taken: Operator records current time in space provided.
  • 2.0 REACTOR VESSEL TO RECIRCULATION LOOP DIFFERENTIAL TEMPERATURE CRITERIA.

NA Page 7 of 16


TQ-AA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor TASK: Perform a Reactor Recirculation Pump Quick STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

2.1 Temperature

of the Rx Coolant within the idle loop to be started up. (Note 3) Operator reads Note 3. Note 3 Use TR-650-831 Recirc Pump Suction Loop A(8) (if available)

OR if above 400° F -CRIDS paints A221 and A222 for A loop (A223 and A224 for B loop). IF below 400°F AND 650-831 not available, THEN have I&C obtain temperatures using RTD ohm values (reference RTD ohm values to calibration data in TDR using HC.OP-GP.ZZ-0008(Q))

NA Page 8 of 16



TQ-.kA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor TASK: Perform a Reactor Recirculation Pump Quick STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD

  • EVAL # Stu COMMENTS (Required for UNSAT evaluation)

Operator determines Idle Recirc Loop Temp for A Loop is above 400 F. Operator obtains value of 510 degF from CRIOS point A221 or A222.

2.2 Temperature

of coolant in the Rx Pressure Vessel. (RX Pressure and Steam Tables) (Note 1) Operator reads Note 1.

  • Operator determines RPV pressure is 885 psig. (900 psia) Operator determines Steam space Coolant Saturation Temperature to be: 900 psia = 532 degF (Steam Tables) Operator records value in space provided on Attachment
1. Page 9 of 16

TQ-",1\-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart STEP NO. 2.3 2.4 ELEMENT < 50°F between the Rx Coolant within the loop not in operation AND the Coolant in the Rx Pressure Vessel B). [TIS 4.4.1.4] Time Readings taken: ______ (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines differential temp is < 50 F. Examiner Note: Actual value is 22 degF + 1 F. Operator records current time in space provided.

  • # *
  • EVAL S/U COMMENTS {Required for UNSAT evaluati HC.OP-AB-RPV-0003 G.12 ENSURE Differential Temperature requirements are met by completing Attachment
2. [TIS 4.4.1.4] Operator initials step G.12.
  • CUE WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD the STOP 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 10 of 16


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: ..IPM Number: ZZ011 TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 11 of 16

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Reactor was scrammed when both Reactor Recirculation Pumps tripped. 2. Evidence of thermal stratification is present. 3. Actions have been taken in accordance with HC.OP-AB.RPV-0003 through step G.11. INITIATING CUE: Complete HC.OP-AB.RPV-0003 step G.12 as necessary for restart of A Reactor Recirc Pump. Page 12 of 16

JOB PERFORMAI\JCE SIMULATOR SETUP INITIALIZE the simulator to 100% power, Trip both Reactor Recirc Pump Drive Motor Take appropriate Scram actions lAW IMPLEMENT EOP-101 to stabilize plant at 885 psig RPV pressure on IMPLEMENT HC.OP-AB.RPV-0003 up to and including step Acknowledge Put Simulator in MARKUP a copy of HC.OP-AB.RPV-0003 up to and including step ENSURE Mode Switch key is COMPLETE "Simulator Ready-for-Training/Examination Event code:

Description:

Event code:

Description:

Event code:

Description:

Page 13 of 16

JOB PERFORMANCE SIMULATOR SETUP I I I I i I i i I i I Page 14 of 16 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ011 Date I Description I Validation Required?

1/14/12 Converted JPM ZZ011 to new JPM format. Modified all Y temperature values, Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted, JPM completely re-written to to changes in the procedure, Validated with 2 ROs on 1/3/12, Avg completion time was 8 minutes. i I ! i : i I I JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity

-Calculate Noble Gas Release Release Rates TASK NUM BER: 4000270401 JPM NUMBER: 305H-JPM.ZZ019 REV#: 01 SAP BET: NOH05JPZZ19E ALTERNATE PATH: D APPLICABILITY:

EO D RO [KJ STA SRO D DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: }<iz-.cl1'Ck DATE:

APPROVED BY: DATE: CWuw---J//O. Training Department


STATION: Hope Creek JPM NUMBER: ZZ019 REV: 01 SYSTEM: Ad ministrative TASK NUMBER: 4000270401 Respond To An Abnormal Release Of Gaseous Radioactivity

-Calculate Noble Gas Release Release Rates KJA NUMBER: 295938 EA1.01 IMPORTANCE FACTOR: 3.9 4.2 APPLICABILITY:

RO SRO EoD ROW STAD SROD EVALUATION SETTING/METHOD:

Simulator/Perform HC.OP-AB.CONT-0004 Rev. 5 HC.OP-DL.ZZ-0026 Rev. 128 ALTERNATE PATH: TOOLS, EQUIPMENT AND PROCEDURES:

Calculator ESTIMATED COMPLETION TIME: 10 TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A JPM PERFORMED BY: GRADE: SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S DATE: Page 2 of 13



DATE: Administrative Respond To An Abnormal Release Of Gaseous Radioactivity

-Calculate Noble Gas Release Release Rates TASK 4000270401 INITIAL CONDITIONS: North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590. SPDS is unavailable. Abnormal HC.OP-AB.CONT-0004 is being executed to determine and stop release of NPV Exh Flow instrumentation channel 9AX300 is inoperable.

Flow is being estimated in accordance with HC.OP-DL.lZ-0026(Q), Attachment 3u (Provided).

INITIATING CUE: Determine the Release Rate of NOBLE GAS from the NPV in accordance with AB.CONT-0004, Action A.4. Page 3 of 13


TQ-MA-106-0303 ZZ019 OPERATOR PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

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

-Calculate Noble Gas Release Release Rates CUE PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

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

Operator obtains Operator obtains the correct HC.OP-AB.CONT-0004.

Operator determines correct of the Operator determines beginning step step to be A.4 DETERMINE the Total Release Rates AA Operator determines that to of Noble Gas and Iodine as the Noble Gas release from the USE the SPDS Noble Gas the formulas in Table "A" must be used. OR USE one of the Formulas in Page 4 of 13



TQ-kA-106-0303 JPM: ZZ019 OPERATOR TRAINING PROGRAM NAME:

Rev: JOB PERFORMANCE MEASURE DATE:

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

-Calculate Noble Gas Release Release Rates (*Denotes a Critical Step) STEP ELEMENT (#Denotes a Sequential Step) NO. STANDARD IF the effluent (IJCi/sec) channel on the RM-11 is NOT operating for a specific plant vent, THEN CALCULATE the Noble Gas release rate for that vent using the following:

  • 472 = Plant Vent Exh lCi/sl ( I .)IJCilcc (n.g.) Flow in cfm IJCi/sec (n.g.) -the calculated release rate from the specified plant vent (Noble IJCi/cc (n.g.) -The concentration of Noble Gas obtained from the RM-11 (the channel will be highlighted in GREEN) OR from an actual sample of the plant vent 472 -The conversion factor in units of cc/sec/cfm Operator manipulates the RM-11 terminal to obtain the value of NPV Noble Gas release from the 9RX602 Low Range detector and enters the value into the formula. 3.65E-7 uCi/cc. Operator transfers the Plant Vent Exh Flow value from Attachment 3u of HC.OP-OL.ZZ-0026 (provided).

49613.9 CFM * # *

  • COMMENTS (Required for UNSAT EVAL evaluation)

S/U ------------

... Page 5 of 13 TQ-AA-106-0303 JPM: ZZ019 Rev: 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE:

__________________

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

-Calculate Noble Gas Release Release Rates COMMENTS (*Denotes a Critical Step) I

  • STEP {Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO. #STANDARD evaluation S/U Operator calculates the NPV Noble Gas
  • release rate. Calculated Value = 3.65E-7
  • 472 = 8.547 uCi/sec (+/- 0.5) WHEN operator informs you the task OR the JPM has been terminated other CUE ..!...:....!.=..:...;.

RECORD the STOP TIME. REPEAT BACK any message from operator on the status of the JPM, then state "This JPM is STOP TIME: Page 6 of 13



JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ZZ019 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity

-Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT; SAT UNSAT Page 7 of 13

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590. SPDS is unavailable. Abnormal HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity. NPV Exh Flow instrumentation channel 9AX300 is inoperable.

Flow is being estimated in accordance with HC.OP-DL.zZ-0026(Q), Attachment 3u (Provided).

INITIATING CUE: Determine the Release Rate of NOBLE GAS from the NPV in accordance with AB.CONT-0004, Action A.4. Page 8 of 13 H c.o P-D L.ZZ-0026(Q) JOB PERFORMANCE MEASURE ATTACHMENT 3u Page 1 of 1 Radioactive Gaseous Effluent Monitoring (North Plant Vent) TIS 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 if the North Plant Vent Flow Rate Monitor is then Effluent Releases via this pathway may continue for up to 30 days provided flow rate is estimated at least once per Readings are taken every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to ensure that the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Tech Spec Action limit is not exceeded per requirements and after a change in the ventilation If flow indication(s) become unavailable, then the "NORM" flow value may be logged for the specific fan RCGS DATE: Today's Date Location Anxffnrh/Radwastc

-ENTER TIME or EACH READING BELOW PARAMETER NORM NOW COMMENTS SOLID RADWASTE EXH rAN A318 17,000 17358 B318 17,000 17163 SOLID RADWASTE EXH FAN " ,ex' tl -_ -, ' A307 7,500 7528 B307 7,500 7519 CHEM LAB EXH CHEM LAB EXH OFFGAS DISCHARGE 10022 OR 45:9F15665 , :, " I TOTAL FLOW 49613.9 ESTIMATED TOTAL FLOW REPORTED TO RAD PRO '-(YES) Yes


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to 100% power, MOL. INSERT Malfunctions:

  • RM9590 @ O.OE+OO
  • RM9591 @ O.OE+OO
  • RM9602 @ 3.65E-7
  • RM9603 @ O.OE+OO
  • CC03 SPDS CRT Failure Acknowledge alarms. Put Simulator in FREEZE. ENSURE SPDS and CRIDS Displays are ENSURE MARKUP copy of HC.OP-DL.ZZ-0026 Attachment 3u COMPLETE "Simulator Ready-for-Training/Examination

==

Description:==

Event code:

Description:

Page 10 of 13 TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATORSETUP INSTRUCTIONS (OPTIONAL) None None None None None None None None Insert malfunction RM9590 to 0.00000 9RX590, NPV EFF -North Plant Vent Noble Gas Effluent Insert malfunction RM9591 to 0.00000 9RX591 , NPV HIGH -North Plant Vent High Range Noble Gas Insert malfunction RM9602 to 3.65E-7 9RX602, NPV LOW -North Plant Vent Range Noble Gas Insert malfunction RM9603 to 0.00000 9RX603, NPV MID -North Plant Vent Mid Range Noble Gas Insert malfunction CC03 SPOS CRT failure Page 11 of 13 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ019 Rev # Date Description Validation Required?

1 1/14/12 Converted JPM ZZ019 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. JPM Modified values for new res'ults.

Validation performed with 2 ROs on 1/3/12. Avg completion time was 10 minutes. Y JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation TASK NUMBER: H303000015 JPM NUMBER: 305H-JPM.ZZ045 REV#: 01 SAP BET: NOH05J PZZ45E ALTERNATE PATH: D APPLICABILITY:

EO RoD STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/16/12 Instructor REVIEWED BY:

DATE: I /;. rations Representative APPROVED BY: DATE:

l/lg Lll Training Department


STATION: Hope Creek JPM NUMBER: ZZ045 REV: 01 SYSTEM: Administrative TASK NUMBER: H303000015 Perform On-Line Risk Controls Evaluation ALTERNATE PATH: KIA NUMBER: 2.1.25 IMPORTANCE FACTOR: 4.2 APPLICABILITY:

RO SRO EoD ROD STAD SROW EVALUATION SETTING/METHOD:

Classroom/Perform WC-HC-105 Rev. 0 M-103-1 TOOLS, EQUIPMENT AND PROCEDURES:

WC-HC-105 Rev. 0 Marked up copy of M-103-1 ESTIMATED COMPLETION TIME: 20 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 DATE: Page 2 of 15



TQ-AA-106-0303 NAME: DATE: SYSTEM: Adm inistrative TASK: Perform On-Line Risk Controls Evaluation TASK NUMBER: H30300001S INITIAL CONDITIONS: The plant is at 100 percent power. Channel D Work week. On-line risk color is Green. Stator Water Cooling System CE-FISL-3597 is reading erratically in the field. The 12 Hour Maintenance Supervisor wants Operations to manipulate the following valves: 1-CE-V9955

-close 1-CE-V9956

-close 1-CE-V9950

-open EOOS is not available. The Site Risk Management Engineer (SRME) is not available. All other equipment is operable. No other work is scheduled.

10. The "Description of Task" is: "Isolate CE-FISL-3597" 11. The WO number is "12345678" INITIATING CUE: The SM has directed you to: 1) Review the activity against the pre-defined Medium, High, and Very High risk activities listed in Exhibit 1, Prescreened Work Activities lAW WC-HC-1 05 Step 4.2.3.2, AND State the Production Risk Level here: ______ AND 3) 2) Complete the Production Risk Evaluation Data Sheet Exhibit 5 Page 1. Page 3 of 1S


TQ-M.A-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM:

TASK: Perform On-Line Risk Controls

(*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. # evaluation CUE STANDARD S/U PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTER START TIME Operator repeats back the Cue: I START TIME: Operator obtains the correct Operator obtains procedure Operator determines beginning Operator determines correct of the step to be WORKACTIVITY RISK

4.2.3 Classify

the risk (Work Activity Owner) Page 4 of 15



TQ-"...1"\-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Administrative TASK* Perform On-Line Risk Controls Evaluation STEP NO. 4.2.3.2

(*Denotes a Critical Step) ELEMENT (#Denotes a Sequential Step) STANDARD Review the activity against the defined Medium, High and Very High Operator reviews Exhibit 1 Pre-risk activities listed in Exhibit 1, Screened Work Activities for Regulatory Prescreened Work Activities.

Compliance and Production Risk. Operator recognizes: "An activity that has been screened as a Production Risk activity by Operations".

System "CE" is listed in Exhibit 5 (Production Risk)

Operator determines the Risk is High Exhibit 5 Page 1 of 4 Production Risk Evaluation Data Description of Task: Operator obtains task description from Initial Conditions sheet. * #

  • EVAL Stu COMMENTS (Required for UNSAT evaluation)

Operator fills in "Isolate CE-FISL-3597." WONo:

Operator obtains WO number from Initial Conditions sheet. Operator fills in "12345678" Page 5 of 15


TQ-kM-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

Work activities that are entirely bounded and contained within a Work Clearance Document (WCD) boundary including Worker Blocking Tags and are not in the same or adjacent panel or near systems on the Station Production Risk System Matrix are not a production risk. This means that work activities cannot cause relay or component actuation, in systems or components outside of the WCD boundary other than control room alarms or position indication changes. Operator determines this work is NOT within a WCD boundry. Production Risk Activity Screening:

1. Is the work activity on a system that is on the Station Production Risk System Matrix (attached) or near production sensitive equipment?

Y N Operator checks YES.

  • Page 6 of 15

TQ-kA-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK" Perform On-Line Risk Controls Evaluation STEP NO. ELEMENT If question 1 above is answered Yes, then continue at Question 2. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

2. Could the activity cause equipment actuations that could cause a loss of planned generation?

Y N Operator checks YES.

  • 3. Does the activity involve instrument, fuse, circuit board removallinstallations that could cause a loss of planned generation?

Y N Operator checks NO. 4. Will the activity cause a 1/2 scram or 1/2 trip that could cause a loss of planned generation?

Y N Operator checks NO.

Page 7 of 15



TQ-,...A-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM:

TASK: Perform On-Line Risk Controls STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL stU COMMENTS (Required for UNSAT evaluation)

5. Does the activity involve pressurization of common sensing lines that could cause a loss of planned generation?

Y N Operator checks YES.

6. Does the activity involve placing of jumpers or disconnection of "daisy chains" that could cause a loss of planned generation?

Y N Operator checks NO. 7. Could the activity cause vibration near vibration sensitive equipment that could cause a loss of planned generation?

Y N Operator checks NO.

8. Is a special procedure or JIT training required to mitigate the threat to generation?

Y N Operator checks NO. Page 8 of 15







TQ-MA-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U During the activity, could a single 9.

  • human error or omission cause a of planned Operator checks YES. Y N Is the activity a non-routine activity the switchyard? Y 10. Operator checks NO. If any question 2 through 10 answered YES, then include completed form in a sub operation Operator determines the activity is a the work order. The activity is a prod uction risk. Production Risk activity.

Performed By: Operator signs in Performed By: space. *Production Risk? Y N Operator checks YES. Page 9 of 15


TQ-I'\A-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: Rev: JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM:

TASK: Perform On-Line Risk Controls COMMENTS (*Denotes a Critical Step) *STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)NO. # S/U evaluation STANDARD WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD the STOP CUE REPEAT BACK any message from operator on the status of the JPM, then state "This JPM is STOP TIME: Page 10 of 15 boul"lda ludIng Worker Blocking Tags and are not in the same or on the Production Risk System Matrix art! not a cannot cause or com pon.erIt acru.ation, in system"> oth*'f than centrol room al.3fIDS or position indicaliQ.l1)

<;"...,'" j:KJnlE!!

or near systEms mJeal1:5 that work actiltities WeD Production Risk ActiYity Screening:

1. Is !he worK ac.tiil1ty on a system that is near production sensitive equipment?

Y

___ """" lat1!3che,j)or Station PfI)d!"C':jOfl; at non-routine acthtii:j in Y JOB PERFORMANCE Exhibit 5 Page 1 of 4 Production Risk Evaluation Data Dt;S':'riptioo of Task Isolate CE-FISL-3597 No.: _________ 12345678 Work activities that <:Ire enUrel]' oounded and <:onbinedwit.nin a Work Oearan,;:;e oorumeni!

{WeD} IF question 1 is NO, THENt!1[s'!!s NOT Ris.k Activity. , ' If Question 1 above is continue at Que<;.tion

2. a loss of plaMed generation?

lines tf.j,3t could cause a Ilos'S of "U"n...."',..;

...*..

jumpers or riiSOO,r=-ctkm of gdaisy ch3ins' that could cause a N cause vibration near vt:or"uol'1 s.ensElivE e Q Ui P me:nt-\j3t couJd catJse " loss of

..,r;,,"'? Y N or J!T training required the threat to generation? , could a sing]*' human error Of omission cause a 1055 of planne-d N --""'-.___ N If any question 2 through 1[j is answered' YES. then inc/ude !his completed form in a sub operation !ll", work order. The aCltP/i:t'f is a Production Risk Perlormed Sy: Operator Production Risk? Y L N __Page 11 of 15


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ZZ045 TASK: Perform On-Line Risk Controls Evaluation TASK NUMBER: H303000015 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 12 of 15

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The plant is at 100 percent power. Channel D Work week. On-line risk color is Green. Stator Water Cooling System CE-FISL-3S97 is reading erratically in the field. The 12 Hour Maintenance Supervisor wants Operations to manipulate the following valves: 1-CE-V99S5

-close 1-CE-V99S6

-close 1-CE-V99SO

-open EOOS is not available. The Site Risk Management Engineer (SRME) is not available. All other equipment is operable. No other work is scheduled. The "Description of Task" is: "Isolate CE-FISL-3597" 11. The WO number is "12345678" INITIATING CUE: The SM has directed you to: 1) Review the activity against the pre-defined Medium, High, and Very High risk activities listed in Exhibit 1, Prescreened Work Activities lAW WC-HC-1 05 Step 4.2.3.2, AND 2) State the Production Risk Level here: ______ AND 3) Complete the Production Risk Evaluation Data Sheet Exhibit 5 Page 1. Page 13 of 15 I TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY ..IPM NUMBER: 22045 Rev# i Date Description Validation Required?

0 I i 11/7/11 New Admin JPM. Validation required.

Validated with 2 SROs. Validated avg time 20 minutes. Y I JOB PERFORMANCE MEASURE Hope Creek Conduct of Operations Complete The Daily Surveillance Logs TASK 4010010201 JPM 305H-JPM.ZZ017 REV#: 02 ***NRC ADMIN ..IPM SRO A2*** SAP NOH05JPZZ17E ALTERNATE PATH: D APPLICABILITY:

EO SRO D RO D STA D [KJ DEVELOPED BY: Archie DATE: 1/14/12 Instructor REVIEWED BY: DATE::(j£-'-CII!;r/;2 APPROVED DATE:fllr (/z Training Department

STATION: ..IPM NUMBER: SYSTEM: TASK NUMBER: TASK: Hope Creek ZZ017 Conduct of Operations 4010010201 Complete The Daily Surveillance Logs REV: 02 ALTERNATE PATH: D KIA NUMBER: IMPORTANCE FACTOR: APPLICABILITY:

EOD ROO STAD SRO [KJ EVALUATION SETTING/METHOD:

Classroom/Perform 3.6 RO 2.1.18 3.8 SRO

REFERENCES:

HC.OP-DL.ZZ-0026 Rev 129 TOOLS, EQUIPMENT AND PROCEDURES:

Paper copies of HC.OP-DL.ZZ-0026 Attachment 1 Page 1 of 1 ESTIMATED COMPLETION TIME: TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 7 N/A lVlinutes Minutes ..IPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: I\J/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 12



TQ-AA-106-0303 NAME: DATE: SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 INITIAL CONDITIONS: 1 . The Plant is in OPCON 1 at 35% power 2. A plant startup from a forced outage is in progress lAW HC.OP-IO.ZZ-0003.

3. RCIC 1ST is in progress and being turned over. 4. River level is at 95.1 feet due to recent heavy rains. 5. River temperature is 83 degF but is NOT expected to exceed 85 degF. 6. All EDGs, SACS, and SSW pumps are operable.
7. The SPV Effluent RMS is inoperable and has been CIT for repairs. INITIATING CUE: You are the Control Room IMPLEMENT the Daily Surveillance Logs for today lAW HC.OP-DL.ZZ-0026 IDENTIFY all required Attachments for current plant Page 3 of 12


TQ-AA-106-0303 JPM: ZZ017 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of TASK: Complete The Daily Surveillance (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD eval StU CUE PROVIDE the operator the cue AND a paper copy Operator repeats back initiating CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME: Operator determines beginning step Operator determines correct of the step to be 2.1.

______________________

___'----_____________________

Page 4 of 12



TO-I"\",-106-0303 JPM: ZZ017 OPERATOR TRAINING PROGRAM NAME: Rev: JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of TASK: Complete The Daily Surveillance STEP NO. 2.1 ELEMENT Shift Manager/Control Room Supervisor

-the SM/CRS is responsible to implement, review, and ensure completion of the log including (CRS has primary responsibility for all log reviews and documentation):

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Examiner Note: Examiner Copy Exhibit 1 is provided for reference.

Operator determines Attachment 1 is required due to current Operational Condition.

  • # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.1 The SM/CRS shall implement the log at the beginning of each day by completing Attachment 1, Section A; Log Initiation, listing those Attachments that require performance due to present conditions.

Also, the present Operational Condition shall be listed. Operator checks Attachment 1 on Attachment 1 Section A Log Initiation.

Operator determined Attachment 3m is required due to RCIC 1ST adding heat to the Suppression Pool.

  • Operator checks Attachment 3m on Attachment 1 Section A Log Initiation.
  • Operator determines Attachment 3k is required lAW Item 1 and T/S 4.7.3 due to current River Water level. Operator checks Attachment 3k on Attachment 1 Section A Log Initiation.
  • Page 5 of 12

TQ-M.A-106-0303 JPM: 7 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL Stu COMMENTS (Required for UNSAT evaluation)

Operator determines Attachment 3h is required lAW Item 1 and TIS 4.7.1.3.b.1 due to current River Water temperature.

Operator checks Attachment 3h on

  • Attachment 1 Section A Log Initiation.

Operator determines Attachment 3t is required lAW Item 42 due to SPV RMS Inoperable.

Operator checks Attachment 3t on

  • Attachment 1 Section A Log Initiation.

Operator places a "1" in the Operational Condition blank. Page 6 of 12


2.1 TQ-AA-106-0303 JPM: ZZ017 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Conduct of TASK: Complete The Daily Surveillance COMMENTS (*Denotes a Critical Step) *STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO. evaluation)

STANDARD # S/U Operator checks Attachment 5 on Attachment 1 Section A Log Initiation.

2.1.1 The SM/CRS shall implement the log at the beginning of day by completing Examiner Note: Although 1, Section A; Log specifically required by the current conditions, Attachment 5 is typically listing those Attachments that used each day to track surveillance require performance due to procedures and would be needed the present conditions.

Also, the first time a surveillance procedure with present Operational Condition an action time is actually logged shall be 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 12


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ZZ017 TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 8 of 12 TQ-AA-106*0303 JOB PERFORMANCE MEASURE ATTACHMENT 1 Page 1 of 1 Surveillance Log Date T odays Date A. LOG INITIATION 1.0perational Condition 1 2.Check (./) Attachments to be performed 1 ./ 3c 3g 3m./ 3s 3w 4a 2 3d 3h./ 3p 3t./ 3x 4b 3e 3j 3q 3u 3y 4c B. LOG v" 3r 3v v" 1. Ensure compliance with TIS by using

.15 TIS reference numbers and surveillance item note(s), as any log item(s) requiring additional action. \). 2. Operators signature below ctio Attac1unent checked comp ttachment 1 and any Attachment1a Control _ _____ Attachment 1 Auxiliary Bldg Attachment 1c Reactor Bldg _ Attachment 1 d Turbine Bldg DAY EVE MID 3. Signature below indicates review of all required attachments checked (./) above has been completed, and approved for compliance with TIS requirements.

Day (Review Before 1300) Eve (Review Before 2100) Mid (Review Before 0500) SM/eRS SM/eRS SM/eRS C. LOG COMPLETION 1 .Operational Condition

2. 1 2 Check (./) Attachments that have been performed 3c 3g 3m 3s 3d 3h 3p 3t 3e 3j 3q 3u 3f 3k 3r 3v 3w 3x 3y 3z 4a 4b 4c 5 Page 9 of 12 TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
1. The Plant is in OPCON 1 at 35% power 2. A plant startup from a forced outage is in progress lAW HC.OP-IO.ZZ-0003.
3. RCIC 1ST is in progress and being turned over. 4. River level is at 95.1 feet due to recent heavy rains. 5. River temperature is 83 degF but is NOT expected to exceed 85 degF. 6. All EDGs, SACS, and SSW pumps are operable.
7. The SPV Effluent RMS is inoperable and has been CIT for repairs. INITIATING CUE: You are the Control Room IMPLEMENT the Daily Surveillance Logs for today lAW HC.OP-DL.ZZ-0026 AND all required Attachments for current plant TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ017 Rev # Date Description Validation Required?

01 11/8/08 Converted ZZ017 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. Y Removed reference to T-Factor and Attachment 3b due to deletion of T-Factor from Tech Specs. Replaced with Severe Storm Warning and Attachment 3j. 02 1/3/12 Updated reference procedure revision numbers. Deleted Storm Warning and added River Level and RCIC 1ST Attachments 3k and 3m. Validated with 2 SROs on 1/3/12. Avg completion time is 7 minutes. Y JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK NUMBER: 2990060302 JPM NUMBER: 30SH-JPM.ZZ027 REV #: 02 SAP BET: NOH05JPZZ27E ALTERNATE PATH: D APPLICABILITY:

EO RO STA SRO D D DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: V DATE: ,-! APPROVED BY: 9lJ031 < DATE: )/11 III* Training Department

STATION: JPM NUMBER: SYSTEM: TASK NUMBER: TASK: Hope Creek ZZ027 REV: 02 Administrative 2990060302 Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria KIA NUMBER: 2.2.12 ALTERNATE PATH: D IMPORTANCE FACTOR: APPLICABILITY:

EoD ROD STAD SROCK] EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

HC.OP-IS.BC-0003 Rev. 43 ER-AA-321 Rev. 11 3.4 RO SRO TOOLS, EQUIPMENT AND PROCEDURES:

Marked up copy of HC.OP-IS.BC-0003 Rev. 43 Calculator ESTIMATED COMPLETION TIME: 27 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 13



Administrative Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK NUMBER: 2990060302 INITIAL CONDITIONS: The Plant is at 100 percent power with all equipment operable. HC.OP-IS.BC-0003, BP202, B Residual Heat Removal Pump In-Service Test, has just been completed.

INITIATING CUE: Perform the CRS review of the completed HC.OP-IS.BC-0003.

Page 3 of 13


TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Administrative Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK: COMMENTS (*Denotes a Critical Step) # I* STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD StU evaluati CUE PROVIDE the operator the initiating Operator repeats back cue.cue. CUE PROVIDE marked up copy of IS.BC-0003 and Vibration data NIA CUE ENTER START TIME Operator repeats back the Cue: I START TIME: Operator commences the OS/CRS for review AND of Attachment SUBMIT the procedure to the 5.43 Operator determines correct Operator determines beginning 2.0 step to be of the Page 4 of 13 TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Administrative Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK: COMMENTS (*Denotes a Critical Step) I

  • STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluati Operator determines that the Discharge Pressure recorded on Attachment 3, Steps 5.23.3.8, for the pump is incorrect:
  • The wrong Discharge Pressure was used. It should be 146.6 psig. Make the necessary corrections N/A CUE and continue with the review. Operator corrects the error
  • Operator determines that the Delta Pressure recorded on Attachment 3, Steps 5.23.4.8 and C, for the pump is incorrect:
  • A math error was made. It should be 140.1 psig. CUE Make the necessary corrections N/A and continue with the review. Operator corrects the error. Page 5 of 13


2.1 TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM:

TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance

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

Operator determines that the differential pressure is within the REQUIRED ACTION range. N/A Make the necessary corrections CUE and continue with the review. RS1QS Operator changes the SAT to UNSAT.

  • Operator reviews the data entered for completeness and compliance with The data acquired during the performance of this test has been Technical Specifications.

reviewed for completeness and compliance with Technical Specification 6.8.4.i, 4.5.1.b.2, 4.6.2.3.b, 4.6.2.2.b, and 4.3.7.4 and the test is considered:

Page 6 of 13


TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Administrative TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # COMMENTS I EVAL (Required for UNSAT S/U evaluation) i 2.1.2 UNSATISFACTORY (Any test evaluations are marked UNSAT). Operator completes the review. TAKE action lAW Technical i Specifications and GENERATE a Notification. Operator notes that data flagged as ACCEPTANCE CRITERIA was marked UNSAT. Operator signs in Step 2.1.2.

  • Operator determines B RHR Pump is

i Operator determines the most limiting Tech Spec is 3.6.2.3 Action a. (Suppression Pool Cooling 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

  • Page 7 of 13


TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM: Administrative Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK: COMMENTS (*Denotes a Critical Step) *I STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluati Operator determines that a

  • NOTIFICATION must be generated.

CUE A Notification will be written by N/A another operator.

CUE WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD the STOP 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 13


JOB PERFORMANCE MEASURE OPERATOR TRAINING EVALUATOR FOLLOWUP QUESTION NAME: DATE: ..IPM Number: ZZ027 TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK NUMBER: 2990060302 QUESTION:

RESPONSE:

UNSAT RESUL T: SAT QUESTION:

RESPONSE:

RESULT: SAT Page 9 of 13

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The Plant is at 100 percent power with all equipment operable. HC.OP-IS.BC-0003, BP202, B Residual Heat Removal Pump In-Service Test, has just been completed.

INITIATING Perform the CRS review of the completed Page 10 of 13 TQ-AA-106-0303 JOB PERFORMANCE MEASURE 1.0 IBP-202 RHR PUMP Report printed on: TODAY 2.0 Vibration monitoring systen1 results: Report generated on: TODAY 09:00 AM Acquired:

TODAY 07: 10 AM 1 xM = 1187 RPM Averages:

14 A. Maximum level: 0.2182 in/s at M1V RECOMMENDATIONS:

2.2 THERE

ARE NO RECOMMENDATIONS DIAGNOSES:

2.3 NO FAULTS HAVE BEEN DETECTED POSITION LEGE:-JD:

POSITION Ml IS: MOTOR TOP POSITION M2 IS: MOTOR BOTTOYI POSITION PI IS: PUMP 2.3.1 OVERALL LEVEL OK: 0.119 in/s atM1H Alarm level: 0.213 in/s OK: 0.218 in/s at MI V Alarm level: 0.240 in/s OK: 0.076 in/s at MIA Alarm level: 0.110 in/s OK: 0.193 in/s at M2H Alarm level: OAOO in/s OK: 0.211 in/s at M2V Alarm level: OAOO in/s OK: 0.114 in/s at M2A Alarm level: OAOO in/s OK: 0.108 in/s at PI H Alarm level: 0.300 in/s OK: 0.126 in/s at PI V Alarm level: 0.300 in/s OK: 0.081 in/s at PIA Alarm level: 0.300 in/s Page 11 of 13 I TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ027 Description Validation Required?

  • 11/7/11 y Modified Admin JPM due to changes in reference procedure.

Validation required.

Validated with 2SROs on 1/3/12. Avg completion time 27 minutes.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TAsK NUM BER: 2990420302 JPM NUMBER: 305H-JPM.zZ003 REV #: 02 SAP BET: NOH05JPZZ03E ALTERNATE PATH: D APPLICABILITY:

EO RO STA D SRO [KJ DEVELOPED BY: Archie Faulkner DATE: 1/14/12 Instructor I/;8-!:(REVIEWED BY: _.-J f<R.. -e 1-1"C1( DATE: APPROVED BY: DATE:

J/lr It) Training Department


STATION: Hope Creek JPM NUMBER: ZZ003 REV: 02 SYSTEM: Radiation Control TASK NUMBER: 2990420302 TASK: Verify Compliance with Gaseous Release Permit ALTERNATE PATH: KIA NUMBER: 2.3.6IMPORTANCE FACTOR: 2.0 3.8 APPLICABILITY:

RO SRO EOD ROO EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-HC-1 03-1 05 Rev 1 TOOLS, EQUIPMENT AND PROCEDURES:

Prepared OP-HC-1 03-1 05 Form 2, Calculator ESTIMATED COMPLETION TIME: 9 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 13


TQ-AA-1 06-0303 NAME: DATE: SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 INITIAL CONDITIONS: A plant shutdown is in progress for a Refueling outage. The Reactor is shutdown. At 0200 today Purging of the Primary Containment commenced. At 0436, the Purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation, due to a damper problem. At 0800, Purging of Primary Containment re-commenced. At 1252 today Operational Condition 4 was entered. At 1548 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE: Review AND Close Out today's Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit and Log in accordance with OP-HC-103-105.

Page 3 of 13


06-0303 JPM: ZZ003 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit COMMENTS (*Denotes a Critical Step) *STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD evaluatio S/U CUE PROVIDE the cue o Prepared OP-HC-1 03-1 05 log Operator repeats back initiating Forms 1 & 2 o Copy of OP-HC-103-105 CUE I ENTER START TIME!....!.!.-!:...=.:....!

Operator repeats back the Cue: I START TIME: Operator determines beginning step Operator determines correct of the step to be 4.4.6. Page 4 of 13 TQ-kl"\-106-0303 NAME: __________________

_JPM: ZZ003 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit STEP NO. 4.4.6 ELEMENT The SM/CRS should verify the calculations, sign in the appropriate space for verification and close out and enter the time and date. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator reviews Form 2. Operator recognizes NCO incorrectly rounded down from 2.6 to 2.5 instead of rounding up to 3.0 lAW 4.4.3 during calculation of first purge period. * #

  • EVAL S/U COMMENTS (Required for UNSAT evaluatio Operator recognizes NCO incorrectly used securing of purge lineup for end time of second purge period instead of using entry into OPCON 4 time lAW step 4.4.2.
  • CUE I F the operator requests the NCO to make changes, THEN DIRECT the operator to make N/A any required changes. Page 5 of 13

4.4.6 TQ-AA-106-0303 JPM: ZZ003 OPERATOR TRAINING PROGRAM NAME: DATE: __________________

_Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit COMMENTS (*Denotes a Critical Step) *STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # evaluatio STANDARD stU calculations, sign in the The SM/CRS should verify the Operator makes corrections to Form 2 Stop times and Total space for verification and close Examiner Note: Refer to Examiners and enter the time and date. Copy for appropriate corrections.

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

STOP TIME: Page 6 of 13



JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ZZ003 TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 QUESTION:


........

RESPONSE:

UNSAT RESULT: SAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT TQ-AA-106-0303 JOB PERFORMANCE MEASURE FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: Calculate Total Hours Open During Previous Year (Note 1) NUMBER OF HOURS 020020001 452 hrs (-) 35.5 line 1 minus line 2 4/3/11 6/25/11 8/30/11 8/31/11 2.5 1 s) Jofin Smitfi DatefTime TodayJ0100 SM/CRS verification and authorization DatefTime )Indrew Jones SECTION C VALVE/LINE OPEN TIME (Note 2) START TIME STOP TIME Time at which valve/line was open or Time at which valvelline was closed or Condition 1, 2, or 3 was entered with valvelline Condition 4 or 5 was entered with valve/line open opened TodayJ0130 TOTAL HOURS Total number of hours valve/line opened this cycle (NOTE 3) 6.a 3.0 Total number of hours valves/line open this permit: .w.,a 8.0 NCO perform ing calcu lations ______

_______ DatefTime rJod"ay/Now SM/CRS Closing permit ___________ "Date/7i1He DatefTime Note 1: The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier. Note 2: Completed Form 2 should be filed in the AP-104 binder in the control room. Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: A plant shutdown is in progress for a Refueling outage. The Reactor is shutdown. At 0200 today Purging of the Primary Containment commenced. At 0436, the Purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation, due to a damper problem. At 0800, Purging of Primary Containment re-commenced. At 1252 today Operational Condition 4 was entered. At 1548 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE: Review AND Close Out today's Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit and Log in accordance with OP-HC-103-105.

[?[]O [?[] @[?[](1)J OP-HC*1 03-1 05 Revision 0

@@[P)J Page 7 of 8 FORM 1 Page of__ CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO PREVo AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL YEAR THIS PERMIT PERMIT PREVIOUS (Note 1) PERMIT YEAR (Note 1) 4/3/11 22.5 24 H. David S(}) 5.5 28.0 S. West S(}) 6/25/11 18.5 24 G. Williams cT'1(W 3.5 22.0 G. Cloon crgzW 8/30/11 22.0 24 W. Holmes '1( 24.00 46.0 P. Price CJ( *i CE CE 8/31/11 46.0 24 B. Lee 2.5 48.5 V. Bonovan , Today 35.5 24 A. Jones JS .... _...... r*** Note1:The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

OP-HC-1 03-1 05 Revision 0

@@[PW Page 8 of 8 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: 020020001 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1) Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) H 35.5 DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 {=} 24 4/3/11 5.5 OR 24, whichever is less) 6/25/11 3.5 Hours authorized this date (max 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) \;S;'\.. 24. '., 8/30/11 24.0 8/31/11 2.5 NCO performing calculation Date/Time Jolin Smitli SM/CRS verification and authorization Date/Time flndrew Jones SECTION C VALVE/LINE OPEN TIME (Note 2) START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 0436 2.5 0800 1548 8.0 Total number of hours valves/line open this permit: 10.5 NCO performing calculations JI1ufy qranate{[i Date/Time

%day/:Now SM/CRS Closing permit Date/Time Note The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier. Note Completed Form 2 should be filed in the AP-104 binder in the control room. Note When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

OP-HC-103-105 Revision 0 Page 8 of 8 REVISION HISTORY JPM NUMBER: ZZ003 Rev # Date Description Validation Required?

01 12/6/08 Converted JPM ZZ003 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.

Y 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, validation not required.

Governing procedure changed methodology for calculating hours. Requires validation.

02 1/14/12 Updated reference procedure revision.

Changed names on Attachments.

Updated dates to be relevant to current year. Validated with 2 SROs on 1/3/12. Average completion time was 19 minutes. Y 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 JPM NUMBER: 305H-JPM.ECG003 REV #: 05 SAP BET: NOH05JPCL03E ALTERNATE PATH: D APPLICABILITY:

EO D RO D STA [KJ SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY:

DATE: Ijrlt 2 APPROVED BY: DATE:

V16/1 1u Training Department


Hope Creek JPM NUMBER: ECG003 SYSTEM: Administrative Duties/Reporting Requirements TASK NUMBER: 2000500302/2000020505 Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition ALTERNATE PATH: D APPLICABILITY:

EOD RO S KIA NUMBER: 2.4.38 IMPORTANCE FACTOR: 2.2 4.0 RO SRO TA[[] SRO[[] EVALUATION SETTING/METHOD:

Simulator/Perform or In Plant/Simulate

REFERENCES:

Hope Creek Event Classification Guide, TOC Rev 98 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 D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: / Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 19



NAME: DATE: Administrative Duties/Reporting Requirements Utilize The ECG To Determine The Emergency Classification And/Or Reportabilitv Of An Event And/Or Plant Condition TASK 2000500302/2000020505 INITIAL CONDITIONS: With the plant operating at 100% power, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1 g. Control Room Annunciator C6-C4 is in. ON Panel 10C673: The SMA-3 Event Indicator 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. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer. A LOCA results. The Reactor is successfully scrammed, with RPV level dropping rapidly to -180"; then stabilizing between -150" and -180", being maintained using all available ECCS. Drywell Pressure peaked at 44 psig, then dropped to < 2 psig over the next seconds, and continues to slowly The current 33 ft. elevation wind direction is from 224 0 at 21 mph. Plant Effluent activity is 1.S9E+04 !-ICi/sec Noble Gas and 1.S9E+01 !-ICi/sec 1-131. 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 3 of 19 TQ-Af\-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: ________________

__ JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Administrative Duties/Reporting Requirements TASK: STEP NO. Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition ELEMENT (*Denotes a Critical Step) I* I COMMENTS (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # StU evaluation CUE PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTER START OPERATOR REPEATS BACK N/A INITIATING START Operator obtains procedure.

correct Operator obtains Hope Creek Event Classification Guide. ECG Section LIV.C Classification:

To use this ECG volume, follow this sequence:

1. ASSESS the event and/or plant conditions and DETERMINE which ECG section(s) is most appropriate.

Operator assesses the initial conditions, and determines that Table 3, Fission Product Barriers, 6.1 Radiological Releases/Occurances, and 9.0, Hazards-Internal/External, are the appropriate ECG sections.

ECG Section LlV.C 2. REFER to Section EAL Flowchart diagram(s), and identify the Initiating Conditions that are related to the event/condition has occurred or is ongoing. Operator refers to Table 3.0 and Flowchart Diagrams and identifies that the Initial Conditions for Table 3.0, EALs 6.1.2.d and 9.5.2 are related to the event that has occurred.

Page 4 of 19 TQ-kA-106-0303 ECG003 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 AndlOr Plant Condition STEP NO. ECG Section i.IV.C 3. ELEMENT REVI EW the associated EALs as compared to the event and SELECT the highest appropriate emergency or reportable action level. If identification of an EAL is questionable, refer to paragraph IV.A above. If there is any doubt with regard to assessment of a particular EAL, the ECG Technical Basis Document should be reviewed.

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. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator reviews the EALs in section 6.1 and 9.5, and determines that EAL # 6.1.2.d and 9.5.2 is the highest emergency action level met or exceeded (ALERT). * # EVAL SIU COMMENTS (Required for UNSAT evaluation)

ECG Section LlV.C 4. If an EAL has been entered, then equal level EALs or lower level EALs and RALs are not required to be reported as long as the applicable information is communicated to the NRC using Attachment 5, NRC Data Sheet. Examiner Note: Filling out the NRC Data Sheet is beyond the scope of this JPM. Page 5 of 19


TQ-#'\1-\-106-0303 ECG003 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) (Required for UNSAT ELEMENT EVAL NO. #STANDARD stu If the Loss or Potential Loss is Operator reads NOTE. 3.0 considered IMMINENT (may occur NOTE within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />), USE judgement classify as if the threshold Table Operator reviews the EALs of all In the table review the Emergency 3.0 columns, and determines that all Action Levels of all columns and 1. columns need further review. identify which need further review. Table Operator determines that the following For each of the three barriers, 3.0 EALs have been exceeded and determine the EAL with the highest 2. represent the highest value met should be selected for each point value. No more than one EAL exceeded for the respective column: 3.1.1.a; 3.2.2.b or 3.2.1.b; and 3.3.2.b or 3.3.2.d. Table Operator adds the values, and enters Add the point values for the three 3.0 the value 9 in the appropriate space. barriers and enter the total below: 3. Examiners Note: Determining this value for future use is critical; marking it on Table 3.0 is not. Page 6 of 19



TQ-hrl-106-0303 ECG003 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 (Required for UNSAT (#Denotes a Sequential Step) EVAL NO. # evaluation)

STANDARD StU Operator determines that this as Ifsum UNUSUAL classification is higher than classification on EALs 6.1.2.d or 9.5.2 Referto: and classifies the event as a General Emergency based on Table 3.0. An. An. An. Page 7 of 19 Table 3.0 4. Classify based on the point value sum t;:;-I TQ-k.A-106-0303 ECG003 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 I* I STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluatio The ST A is responsible to Section ECG perform an independent LIV.C verification of the EAL IE time permits, classification.

The STA THEN Operator requests STAIIA verification does not alleviate the verification of classification.

requirement of the SM to make timely classification.

Should Examiner Note: Due to time SM fill the STA role, assessing andlor nature of verification of the administration, Operator may classification will be delegated request a another on-shift CUE IE the Operator requests the ST AliA to independently verify the EAL Classification, N/A THEN INFORM the Operator STAIIA is not Page 8 of 19 TQ-AA.-106-0303 ECG003 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 STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluation)

ECG 6. IDENTIFY and IMPLEMENT the Section referenced Attachment under LlV.C Action Required.

Refer to Section iv, HC Emergency Classification Description Table, which is a guide for correct description wording for entry on the ICMF for all EALs.

Operator identifies and implements ECG Attachment

4.

ECG Att. 4 I. EMERGENCY COORDINATOR (EC) LOG SHEET A. If a security event is in progress, THEN, IMPLEMENT the prompt actions of EP.zZ-0102, EC Response, Attachment 10, prior to classification.

Operator determines this step is not applicable. Page 9 of 19 TQ-AA-106-0303 ECG003 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 STEP NO. ECG AtL 4 ELEMENT B. DECLARE A GENERAL EMERGENCY AT HOPE CREEK EAL #(s) , , DECLARED AT hrs on time date (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator declares a General Emergency, places the EAL # s 3.1.1.a; and 3.2.1.b or 3.2.2.b; and 3.3.2.b or 3.3.2.d, time and date in the appropriate spots in attachment 4, and initials the step as the EC. Examiners Note: ENTER the declaration time that the operator entered on Att. 4. The difference between the START TIME and the "DECLARED AT" TIME is the first critical timej15 min.) Initialing the step is not critical.

  • #
  • EVAL StU COMMENTS (Required for UNSAT evaluation)

ECG Att.4 C. NOTIFICATIONS

1. CALL the communicators to the Control Room Operator calls the communicator using the plant page. CUE After 2 minutes, report as the communicators and give your name as CM1 and CM2. N/A Page 10 of 19 TQ-kA-106*0303 ECG003 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 STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL stu COMMENTS (Required for UNSAT evaluation)

ECG Att. 4 2. ACTIVATE "ERO Emergency Callout" per posted instructions Operator activates the ERO per posted 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.

Caution ECG Att. 4 A Protective Action Recommendation (PAR) SHALL be made on the Initial Contact Message Form (ICMF). 3. MAKE A PAR as follows: a. REFER to Predetermined PAR Flowchart on Pg. 3 and DETERMINE the appropriate PAR. b. LE a Radiologically Based PAR is IMMEDIATELY available, THEN COMPARE the two PARs and choose the most appropriate for Operator reads CAUTION. Operator Refers to APPENDIX 1, determines that a GE Based 9 Points PAR is appropriate

[EVACUATE ALL SECTORS 0-5 MILES]. Examiner Note: Shelter Sectors and Distance is left blank for a 9 point GE.

  • inclusion on the ICMF. -Page 11 of 19 TQ-HA-106-0303 ECG003 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 AndlOr Plant Condition STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL SIU COMMENTS (Required for UNSAT evaluation)

CUE If asked, a Radiologically Based PAR is not available.

N/A ECG Att. 4 4. COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment).

Operator Completes the ICMF. Examiners Note: See the attached 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 EALs 3.1.1.a; and 3.2.1.b or 3.2.2.b; and 3.3.2.b or 3.3.2.d. The operator may place the Examiner's name as the Communicator or tell the Examiner to place his/her name as the Communicator.

  • -5. IF time allows, OBTAIN an accuracy peer check of the completed ICMF. Operator requests a Peer Check of the completed leMF. Page 12 of 19 TQ-AA-106-0303 ECG003 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 STEP NO. CUE ELEMENT I F the Operator requests a Peer Check, THEN INFORM the Operator a Peer Check has been performed as requested.

N/A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluation)

6. PROVIDE the ICMF to the Primary Communicator (CM1) and DIRECT the Communicator to implement ECG Attachment
6. Operator provides the ICMF to CM1 and directs implementation of Att.6.
  • CUE LOG the time the ICMF is provided to CM1. LOG TIME: Role-playas CM1 and repeat back the direction as given. Examiners Note: The difference between the "DECLARED AT" TIME and this LOG TIME is the second critical time (13 min.) Page 13 of 19 TQ-I'\#"\-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: ________________

__ JOB PERFORMANCE MEASURE DATE: ________________

__ 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 I* I STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # SIU evaluatio ECG 7. DIRECT the Secondary Operator directs CM2 to implement AU. Att.4 8 for a GENERAL implement ECG Attachment for a GENERAL Communicator (CM2) to CUE ROLE-PLAYas CM2 and BACK the direction as N/A WHEN operator informs you the task OR the JPM has been terminated other CUE -'-'-..:.=.:...::.

RECORD the STOP time. REPEAT BACK any message from operator on the status of the JPM, then state "This JPM is STOP TIME: Page 14 of 19


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ECG003 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 Page1Sof19 JOB PERFORMANCE 1. ITa. ITb. INITIAL CONTACT .MESSAGE FOR.'I ECG ATT4 Pg. 50f5 THIS IS (Not Required) , C01vllvfUNICATOR IN THE l:J CONTROL ROm..! (NAlvlE) AT THE HOPE CREEK NUCLEAR GENERATING STATION. DTSC DEOF THIS IS NOTIFICATION OF A GENER4..L El\IERGENCY

\VHICH WAS DECLARED AT Todays Time ON Todays Date (TL>vIE -24 HOUR CLOCK) (DATE) EAL 3.1.1.a , 3.2.1.b or 3.2.2.b , 3.3.2.b or 3.3.2.d DESCRIPTION OF EVEl';'T:

Potential Loss of Fuel Clad Barrier. Loss of Reactor Coolant System Barrier,and LOSSJJf Containment Barrier. D Reason for PAR Upgrade: ------....:.-..

..-.-.-..

..-.. ill. of 1.20E+04 !lCi/sec Noble IV. } see NOTE for release definition . (From): 224 \\ThD SPEED: .........2'-.!.1__ Computer lSPDS) (DEGREES) (tvfPH) oI \VE RECOM1I.:EEl'lTI EVACUATION AS FOLLOWS Dist.-Miles 0-5 D \v'E RECOM1I.'lEl'llJ SHELTERING AS FOLLOWS o \VE REC01\llv1END lliE USE OF KI IN ACCORDAJ.'fCE

\\1TH PROCEDURES HCGS Performer's Initials EC Initials (Approval to Transm it ICl\IF) Rev. 09 Page 16 of 19

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: With the plant operating at 100% power, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1 g. Control Room Annunciator C6-C4 is in. ON Panel 10C673: The SMA-3 Event Indicator 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. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer. A LOCA results. The Reactor is successfully scrammed, with RPV level dropping rapidly to -180"; then stabilizing between -150" and -180", being maintained using all available ECCS. Orywell Pressure peaked at 44 psig, then dropped to < 2 psig over the next seconds, and continues to slowly The current 33 ft. elevation wind direction is from 224 0 at 21 mph. Plant Effluent activity is 1.59E+04 J,JCi/sec Noble Gas and 1.59E+01 J,JCi/sec 1-131. 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 17 of 19 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ECG003 1:), Date Description ValidationRequired?

  • Updated Reference procedure revision number. This change is 05 1/14/12 Y editorial.

Converted JPM ECG003 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.

Modified conditions to change PAR to 9 point. Modified MET data for wind speed and direction Modified ICMF release rate data to indicate a release is in progress, but at an ALERT level. Validated with 2 SROs on 1/3/12. Avg completion time was 13 minutes.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure TASK NUMBER: 4000510401

,"'PM NUM BER: 305H-JPM.AE004 REV #: 05 SAP BET: NOH05JPAE04E ALTERNATE PATH: [KJ APPLICABI LlTY: EO D RO STA D SRO []] DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED By:a /'(K ?:-IS tic DATE: d&z APPROVED BY: DATE:

Training Department

STATION: Hope Creek JPIVI NUIVIBER:

AE004 REV: 05 SYSTEM: Feedwater TASK NUMBER: 4000510401 Respond To Rising Orywell Pressure ALTERNATE PATH: KIA NUMBER: __2_23_0_0_1_A_2._0_1

__ IMPORTANCE FACTOR: 4.3 4.4 APPLICABILITY:

RO SRO EOD RO[]] STAD SRO[]] EVALUATION SETTING/METHOD:

Simulator/Perform HC.OP-AB.CONT-0001 Rev 2 HC.OP-SO.AE-0001 Rev 66 TOOLS, EQUIPMENT AND PROCEDURES:

Keys for RCIC HV-F013, HPCI HV-8278, FW Cross-Tie HV-4144 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 DATE: Page 2 of 18



TQ-AA-106-0303 NAME: DATE: SYSTEM: Feedwater TASK: Respond To Rising Orywell Pressure TASK NUMBER: 4000510401 INITIAL CONDITIONS: 1 The plant was at 100% power when a LOCA with indications of major fuel failure occurred. The plant is depressurized. The HPCI and RCIC jockey purnps are available. RPV water level is being maintained with Core Spray pumps by another operator. HC.OP-AB.CONT-0001 Condition D is being implemented.

INITIATING CUE: You are the Plant Place a water seal on both the 'A' AND 'B' feedwater headers lAW Page 3 of 18


TQ-J-\A-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure COMMENTS (*Denotes a Critical Step) *STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO. # evaluati STANDARD S/U PROVIDE the operator the initiating CUE Operator repeats back initiating cue. cue. CUE ENTER START TIME Operator repeats back the Cue: I N/A START TIME: Operator obtains Operator obtains the Operator reviews precautions Operator reviews precautions and limitations.

IE excessive time is taken precautions and CUE N/A THEN INFORM operator that all Operator determines correct of the Operator determines beginning step step to be 5.17.1. Page 4 of 18 TQ-kA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM:

TASK: Respond To Rising Drywell

(*Denotes a Critical Step) COMMENTS STEP (#Denotes a Sequential Step) (Required for UNSAT ELEMENT EVAL NO. #STANDARD S/U evaluatio

  • NOTE The HPCI AND the RCIC Jockey Pump Loops are used to maintain a water seal in the Feedwater lines N/A between the inboard AND containment isolation valves a Operator ensures that all prerequisites 5.17.1 ENSURE all prerequisites of Section have been satisfied.

2.17 are satisfied.

Examiner Note: The Initial Conditions state that the HPCI and RCIC jockey pumps are available.

IE excessive time is taken reviewing CUE prerequisites, N/A THEN INFORM operator that all ENSURE the following valves 5.17.2

  • 8J-HV-8278, HPCI DSCH THRU Operator observes the HPCI DSCH FW ISLN MOV THRU FW ISLN MOV HV8278 OPEN light is illuminated and CLSD light is extinguished.

Page 5 of 18



TQ-kA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the HV8278 CLOSE pushbutton.

Examiner note: 30 seconds after pressing the HV8278 CLOSE pb, the AP228 HPCI Jockey Pump will trip. * #

  • EVAL S/U COMMENTS (Required for UNSAT evaluation Y N Flagging Operator observes the HV8278 CLSD light illuminates and the OPEN light extinguishes.

Operator recognizes HPCI Jockey Pump trip by OHAs and OVLD/PWR FAIL indication.

Operator informs CRS of HPCI Jockey pump trip. CUE INFORM the Operator the trip of the HPCI Jockey pump will be investigated by another operator.

N/A DIRECT the Operator to place a water seal on the 'A' & 'B' Feedwater lines using the RCIC jockey pump. Page 6 of 18 TASK: Respond To Rising Drywell Pressure STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT eval Operator determines step 5.17.3 of Operator continues to complete step the procedure is now applicable.

5.17.2. TQ-MA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Feedwater

  • BD-HV-F013, RCIC PUMP DSCH Operator observes the F013 CLSD light TOFW illuminated and the OPEN light extinguished . Y N Flagging Operator presses the HVF032A CLOSE
  • pushbutton.
  • HV-F032A, FW INLET CHK I
  • HV-F032B, FW INLET CHK VLV Operator observes the FW INLET CHK VL V HVF032A OPEN light is illuminated and the CLOSE light is extinguished.

Operator observes the HVF032A CLOSE light illuminates and the OPEN light extinguishes.

Operator observes the FW INLET CHK VL V HV-F032B OPEN light is illuminated and CLOSE light is extinguished.

Page 7 of 18


TQ-.kA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM:

TASK: Respond To Rising Drywell STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluatio Operator presses the HVF032B CLOSE pushbutton.

  • Y N Flagging Operator observes the HVF032B CLOSE light illuminates and the OPEN light extinguishes.
  • HV-4144, FW LINE CROSS-TIE ISL VLV Operator observes the HV-4144, FW LINE CROSS-TIE ISL VLV CLOSE light is illuminated and OPEN light is extinguished.

5.17.3 IF AP228, HPCI JOCKEY PUMP be used to seal the B Feedwater Line, OR BP228, RCIC JOCKEY PUMP will be used to seal the A Feedwater Line, THEN PERFORM the following:

Based on current conditions, Operator determines that this step now applies. Page 8 of 18


TQ-I-'\A-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: DATE: __________________

_Rev: 05 JOB PERFORMANCE MEASURE SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # COMMENTS EVAL (Required for UNSAT S/U evaluation) 5.17.3. A. PLACE the keylock switch for 4144, FW LINE CROSS-TIE ISLN VL V, in the ON position to arm the control switch. Operator inserts key and places the Keylock switch for the HV-4144, FW CROSS TIE LINE ISLN, in the ON position Examiner Note: OHA 83-02 FEEDWATER LINE FILLALT MODE will alarm. * # 5.17.3. 8 OPEN HV-4144, FW LINE TIE ISL VLV. Operator observes the HV-4144, FW LINE CROSS-TIE ISL VLV CLOSE light is illuminated and OPEN light is extinguished.

Operator presses the FW CROSS TIE LINE ISLN HV-4144 OPEN pushbutton.

  • --Y N Flagging Operator observes the OPEN light illuminates and the CLOSED light extinguishes. .........-.....Page 9 of 18 TQ-I-\A-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) (Required for UNSA T EVAL ELEMENT NO. # evaluati IF AP228, HPCI JOCKEY PUMP is to STANDARD S/U 5.17.4. be used to seal one or both Based on current conditions, Operator Feedwater lines, determines that this step does not apply and continues at step 5.17.5. THEN PERFORM the following:

I IF the BP228, RCIC JOCKEY PUMP 5.17.5 I is to be used to seal one or Feedwater THEN PERFORM the following: Y N Flagging Operator inserts key and places the 5.17.5. *PLACE the NORM/BYPASS Keylock Keylock switch for the RCIC HVF013 A Switch for BO-HV-F013, RCIC PUMP #the BYPASS position.

OSCH TO FW, in the position to arm the Control Examiner Note: OHA B3-02 FEEOWATER LINE FILL ALT MODE will alarm. Page 10 of 18


TQ-kA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM:

TASK: Respond To Rising Drywell

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

S/U Operator observes the RCIC 5.17.5. OPEN BO-HV-F013, RCIC PUMP OSCH TO FW HVF013 CLSO light is illuminated and OPEN light is extinguished.

OSCH TO FW. Y N Flagging* pushbutton.

Operator presses the HVF013 OPEN ------..

Operator observes the OPEN light illuminates and the CLSO light extinguishes.

Operator observes the HVF012 5.17.5. OPEN BO-HV-F012, RCIC PUMP light is illuminated and CLSO light is extinguished.

DSCH VLV. i Operator observes the RCIC JOCKEY WHEN required, THEN START 5.17.5. PUMP red RUNNING light is illuminated and green STOPPED light is extinguished.

BP228, RCIC JOCKEY PUMP. 0 Page 11 of 18


TQ-,...1'\-106*0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM:

TASK: Respond To Rising Drywell

(*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) (Required for UNSAT ELEMENT EVAL NO. #STANDARD Stu evaluation CUE WHEN operator informs you the task OR the JPM has been other THEN RECORD the STOP 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


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: AE004 TASK: Respond To Rising Orywell Pressure TASK NUMBER: 4000510401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 13 of 18

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant was at 100% power when a LOCA with indications of major fuel failure occurred.
2. The plant is depressurized.
3. The HPCI and RCIC jockey pumps are available.
4. RPV water level is being maintained with Core Spray pumps by another operator.
5. HC.OP-AB.CONT-0001 Condition 0 is being implemented.

INITIATING CUE: You are the Plant Place a water seal on both the 'A' AND '8' feedwater headers lAW Page 14 of 18


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to 100% power, INSERT Malfunction CR01 at 100% using WHEN MSL Radiation levels reach THEN INSERT Malfunction MS01 at 100% using INSERT Malfunction RM9635 to 5211 and RM9636 to 5185 to raise DAPA RMS readings using IMPLEMENT EOP-101 and ENSURE MSIVs are TRIP all PCPs and ESTABLISH RPV water level control with Core ENSURE associated Schedule file open and running ..ENSURE associated Events file open. ENSURE a copy of HC.OP-SO.AE-0001 is available. ENSURE Mode Switch key is COMPLETE "Simulator Ready-for-Training/Examination Event code: . ZDHP278C >=1.0 II HPCI 8278 CLOSE pb pressed.

Description:

Trips HPCI Jockey Pump Event code: .

Description:

Event code:

Description:

. Page 15 of 18 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

  • Initial @Time Event Action Description None None Insert malfunction CR01 to 100.00000 on event 1 Fuel cladding leak None None Insert malfunction MS01 to 100.00000 on event 2 Steam line break in drywell None None Insert malfunction RM9635 to 5211.00000 on event 3 9RX635, DAPA 'A' -Drywell Atmos Post-Accident Chan 'A' None None Insert malfunction RM9636 to 5185.00000 on event 3 9RX636, DAPA 'B' -Drywell Atmps Post-Accident Chan 'B' None None Insert malfunction AN-B1 E4 after 30 on event 4 CRYWOLF ANN B1 E4 HPCI JOCKEY PUMP 1AP228 TROUBLE None None Insert malfunction AN-B1 F3 after 30 on event 4 CRYWOLF ANN B1 F3 HPCI COMPONENT O/PF Initial !@Time Event None None None None None None Action Description Insert remote IA10 to RUN IA 10 Temporary station air compressor Insert remote ET066 to FAIL_OPEN ET066 HV-8278 HPCI to FW on event 2 Remove remote ET066 to FAIL_OPEN ET066 HV-8278 HPCI to FW on event 4 None Insert override 9S139_A_DI after 30 to Off on event 4 HPCI JOCKEY START/STOP (DI) None Insert override 9S138_A_LO after 30 i to On on event 4 AP228 OVLD/PWR FAIL (LO) None ! Insert override 9DS111_B_LO after 30 to Off on event 4 AP228 STOPPED (LO) None
  • Insert override 9M6_R_AO after 30 . from 95.00000 to 0 in 5 on event 4 PI-4891 R (AO) Page16of18 TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AE004 Rev # Date I Description Validation Required?

I 01 12/3107 Revision 53 of HC.OP-SO.AE-0001 renumbered former Feedwater Line Fill section from 5.16 to 5.17 with NO change in action steps. JPM AE004 updated to reflect this re-numbering of steps. No change in actions, validation not required.

N Converted JPM AE004 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.

Added procedure Note text to Element section. This is for examiner reference only and has no associated student actions. This change is editorial, validation not required.

02 I 9/29/09 Complete revision due to procedure section revision.

Validated with 2 operators from 'A' Shift. Average completion time was 12 minutes. Y 03 I 8/12/10 Updated Reference procedure revision numbers only. No changes to operator actions. No validation required.

N 04 8/2111 Modified Malfunction, Remote, Override, and Event list sections . for TREX event syntax. Added Override to HV-8278 to maintain ! valve operation as before DCP. Updated Reference procedure revision numbers only. No changes to operator actions. No validation required.

N 05 1/14/12 Updated Reference procedure revision numbers only. No changes to operator actions. No validation required.

N JOB PERFORMANCE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 JPM NUMBER: 305H-JPM .BC015 REV #: 03 SAP BET: NOH05JPBC15E ALTERNATE PATH: 0 APPLICABILITY:

EO RO [KJ STA SRO I X I DEVELOPED BY: Archie E. Faulkner DATE: 9/13/11 Instructor REVIEWED BY: DATE: , Operations Representative APPROVED BY: O((Ju DATE: Q/2 o/([ Training Department


STATION: Hope Creek JPM NUMBER: BC015 REV: 03 SYSTEM: Residual Heat Removal TASK NUMBER: 2050120101 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop ALTERNATE PATH: KiA NUMBER: 205000 A4.03 APPLICABILITY:

EO D RO [KJ STA D IMPORTANCE FACTOR: 3.6 RO SRO [KJ 3.5 SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-SO.BC-0002 Rev. 27 TOOLS, EQUIPMENT AND PROCEDURES:

None. ESTIMATED COMPLETION TIME: 33 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 UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of22



SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 INITIAL CONDITIONS:

1. The plant is in OPCON 4. 2. The reactor has been shutdown for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. 3. '8' RHR pump has been in shutdown cooling at 10,000 gpm for several hours. 4. RCS temperature is 100 degF. 6. A SACS and SSW loops are aligned to support the evolution.
6. BC-HV-F007 A and BC-HV-F027 A have been tagged closed to support the evolution.
7. Flush of A RHR Loop is not required.
8. Field operators have been briefed and are standing by on location.

INITIATING CUE: You are an extra Transfer RHR Shutdown Cooling to the A RHR The required shutdown cooling flow for the 'A' RHR pump is between 9500 -10,000 Page 3 of 22



TQ-.kA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT ELEMENT NO. #STANDARD StU evaluatio CUE PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains procedure HC.OP-SO.BC-0002 Operator obtains the correct procedure.

Operator reviews precautions Operator reviews precautions and limitations.

CUE IE excessive time is taken precautions and THEN INFORM operator that all Operator determines correct of the Operator determines beginning step step to be 5.3.1. Page 4 of 22


TQ-kA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.3.1 ENSURE

all Prerequisites have been satisfied lAW Section 2.3. Operator reviews prerequisites.

Operator reads NOTE.

NOTE BC-HV-F027A(B)

RHR LOOP A(8) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool IF opened while the associated RHR pump is in shutdown cooling. Page 5 of 22



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

CAUTION While in shutdown cooling, the following valves shall be closed to prevent uncontrolled drainage from the Reactor Vessel: [CD-389B, 6080, CO-157E, CO-567E]

  • BC-HV-F004A(B)

RHR PMP A(B) SUPP POOL SUCT MOV

  • BC-HV-F024A(B)

RHR LOOP A(B) TEST RET MOV

  • BC-HV-F010A(B)

RHR LOOP C(O) TEST RET MOV

  • BC-HV-F027 A(B) RHR LOOP A(B) SUPP POOL SPRAY HOR ISLN IF the Reactor is in Mode 4 or Refuel or if a mode change is not desired, the delay in starting the second RHR Loop after having secured the first Loop should not approach the "Time to Boil" value. [PR 971028283]

Operator reads CAUTION. I TQ-.I-'\A-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Page 6 of 22 I


TQ-hM.-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling (*Denotes a Critical Step)STEP NO. ELEMENT (#Denotes a Sequential Step) 5.3.2 PERFORM the following to prepare loop to be placed in Shutdown Cooling: 5.3.2. A I F a flush on the loop to be placed Shutdown Cooling is required, THEN REFER TO Steps 5.2.5 through 5.2.14. ENSURE the following Valves are B CLOSED: 8C-HV-F003A(8)

RHR HX A(8) OUTLETVLV BC-HV-F004A(B)

A(B) RHR PMP SUPP POOL SUCT MOV STANDARD Operator determines step 5.3.2.A. does not apply. Operator observes the 8C-HV-F003A RHR HX A OUTLET VL V CLSD light illuminated and OPEN is extinguished.

Operator observes the BC-HV-F004A A RHR PMP SUPP POOL SUCT MOV CLSD light illuminated and OPEN is extinguished.

  • # EVAL. S/U COMMENTS (Required for UNSAT evaluatio Page 7 of 22

TQ-MA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling STEP NO, ELEMENT 8C-HV-F007A(8)

RHR PUMP A(B) MIN FLOW MOV (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes the BC-HV-F007 A is TAGGED CLOSED and breaker 212041 OPEN AND INITIAL Attachment 1 . * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

BC-HV-F024A(B)

RHR LOOP A(B) TEST RET MOV BC-HV-F027A(B)

RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV NOTE This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

Operator observes the BC-HV-F024A RHR LOOP A TEST RET MOV CLSD light illuminated and OPEN is extinguished. Operator observes the BC-HV-F027 A is TAGGED CLOSED and breaker 212081 OPEN AND INITIAL Attachment

1.

Operator reads NOTE. Page 8 of 22


TQ-nA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluation)

5.3.2. VERIFY

BC-HV-F007 A(B) is Operator observes the BC-HV-F007 A is C CLOSED THEN TAG breaker 212041 (52-222041)

OPEN AND INITIAL Attachment

1. TAGGED CLOSED and breaker 212041 OPEN AND INITIAL Attachment
1. NOTE 1-BC-V315 (V314) SUP POOL SPRY HDR MAN ISLN VLV may be tagged CLOSED instead of tagging the associated breaker for the F027 A(B) (if required to support outage activities), although F027 A(B) must still be closed. This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

Operator reads NOTE. 5.3.2. VERIFY BC-HV-F027 A(B) is Operator observes the BC-HV-F027 A is D CLOSED AND TAG breaker 212083 (52-222083)

OPEN AND INITIAL Attachment

1. TAGGED CLOSED and breaker 212081 OPEN AND INITIAL Attachment
1. Page 9 of 22

TQ-.n.A-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP NO. 5.3.3. ELEMENT OPEN BC-HV-F006A(B)

RHR PMP A(B) SUCT FROM RECIRC for the RH R Loop to be placed in SID Cooling. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses BC-HV-F006A RHR PMP A SUCT FROM RECIRC OPEN pb. * #

  • EVAL stu COMMENTS (Required for UNSAT evaluation)

NOTE RHR Loop B OR RHR Loop A prewarming is required IF the differential temperature between the Reactor Vessel water AND the RHR Loop to be utilized is greater than 100°F. Operator observes the BC-HV-FOO6A RHR PMP A SUCT FROM RECIRC OPEN light illuminated and CLSD extinguishes.

Operator reads NOTE. Page 10 of 22 TQ-nA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE M DATE: __________________

__ SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop COMMENTS (*Denotes a Critical Step) *STEP ELEMENT (Required for UNSA T (#Denotes a Sequential Step) EVAL NO. #STANDARD evaluation StU 5.3.4. IF RHR to Operator determines step 5.3.4 be placed in SID Cooling is required not THEN, PERFORM Steps 5.2.26 5.2.27 of this procedure to temperatures;

5.3.5. SECURE

the inservice Shutdown Cooling Loop as follows: Operator contacts Equipment ENSURE 1-BC-V262 (1-BC-V212), 5.3.5. and directs opening RHR Loop 8(A) is LOCKED (local), AND INITIAL Attachment ECCS Jockey Pmp D(C) DISCH to T he valve is in th e position CUE requested.

NOTE Operator reads NOTE.

Page 11 of 22


06-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling STEP NO. 5.3.5. B ELEMENT CLOSE BC-HV-F015B(A)

RHR LOOP B(A) RET TO RECIRC AND INITIAL Attachment 1 . (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses and holds the HV-F015B RHR LOOP B RET TO RECIRC CLSD pb. * #

  • EVAL S/U COMMENTS (Required for UNSAT evaluation) i 5.3.5. C L ______ WHEN BC-HV-F015B(A)

RHR LOOP B(A) RET TO RECIRC is fully closed, THEN, IMMEDIATELY STOP B(A)P202 RHR PUMP. Operator observes the BC-HV-F015B RHR LOOP B RET TO RECIRC CLSD light illuminated and OPEN is extinguished.

Operator presses BP202 RHR PUMP STOP pb.

  • Page 12 of 22


STEP NO. ELEMENT (*Denotes a Critical Step) * (#Denotes a Sequential Step) STANDARD # EVAL stu COMMENTS (Required for UNSAT evaluation) 5.3.5. 0 CLOSE 8C-HV-F0068(A)

RHR PMP 8(A) SUCT FROM RECIRC AND INITIAL Attachment

1. Operator presses the 8C-HV-F0068 RHR PMP 8(A) SUCT FROM RECIRC CLSD pb. Operator observes the 8C-HV-F0068 RHR PMP 8(A) SUCT FROM RECIRC CLSD light illuminated and OPEN is extinguished.

-5.3.6. ENSURE SACS is in service to the RHR Heat Exchanger for the RHR loop to be placed in service lAW HC.OP-SO.EG-0001 (0). Operator observes the HV-2512A OPEN light illuminated and CLSD light extinguished. Operator observes RHR A HX SACS Flow approximately 9000 gpm. ...TQ-kA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Page 13 of 22 I


TQ-M.A-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL Stu COMMENTS (Required for UNSAT evaluation)

CAUTION Manual OR automatic opening of BC-HV-F007 A(B) RHR PMP A(S) MIN FLOW MOV will drain Reactor Vessel to Suppression Pool. If BC-HV-F01S A(B) RHR LOOP A(B) RET TO RECIRC does NOT open immediately to establish flow, then the RHR pump should be secured. BC-HV-F027 A(B) RHR LOOP A(S) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR pump is in shutdown cooling. Operator reads CAUTION. Page 14 of 22


TQ-nA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD

  • EVAL # StU COMMENTS (Required for UNSAT evaluation)

5.3.7. START

RHR PUMP A(8)P202 AND IMMEDIATELY THROTTLE OPEN BC-HV-F015A(8)

RHR LOOP A(B) RET TO RECIRC LOOP UNTIL R603A(B) OR FR-R60SA(8)

-CRIDS A3137(A3139), LOOP A(B) FLOW indicates::::::

3000 gpm. Operator presses the AP202 START pb.

  • Operator observes the AP202 START light illuminated and STOP light extinguishes.

Examiner Note: F015A will fail closed and not establish flow. Operator should secure the pump. Operator immediately presses and holds the BC-HV-F015A RHR LOOP A RET TO RECIRC LOOP OPEN pb.

Operator observes the CLSD light remains illuminated.

Operator observes the FI-R603A OR FR-R60SA -CRIDS A3137, LOOP A FLOW indicates 0 gpm. Page 15 of 22 TQ-M.A-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 03 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) ELEMENT (Required for UNSAT EVAL NO. #STANDARD evaluation stu Operator determines CAUTION applies. *Operator presses AP202 STOP pb. CUE WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD the STOP REPEAT BACK any message from operator on the status of the JPM, then state "This JPM is STOP TIME: Page 16 of 22


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: BC015 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 17 of 22

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is in OPCON 4. 2. The reactor has been shutdown for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. 3. 'B' RHR pump has been in shutdown cooling at 10,000 gpm for several hours. 4. RCS temperature is 100 degF. 5. A SACS and SSW loops are aligned to support the evolution.
6. BC-HV-F007A and BC-HV-F027A have been tagged closed to support the evolution.
7. Flush of A RHR Loop is not required.
8. Field operators have been briefed and are standing by on location.

INITIATING CUE: You are an extra NCO. Transfer RHR Shutdown Cooling to the A RHR loop. The required shutdown cooling flow for the 'A' RHR pump is between 9500 -10,000 gpm. Page 18 of 22


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to an OPCON 4 IC with 'B' RHR in Shutdown Cooling at 10,000 gpm and an RCS temp of =100 degF. OPEN BC-HV-F007B breaker OPEN BC-HV-F027B breaker ENSURE BC-HV-F003A is closed. ENSURE BC-HV-F004A is closed, ENSURE BC-HV-F007 A is closed. ENSURE EG-HV-2S12A is open. ENSURE associated Schedule File is loaded. OPEN BC-HV-F007A breaker using ET-1. OPEN BC-HV-F027A breaker using ET-2. PLACE red bezel covers on the BC-HV-F007B AND the BC-HV-F027B.

PLACE red bezel covers on the BC-HV-F007 A AND the BC-HV-F027 A. Page 19 of 22

JOB PERFORMANCE SIMULATOR SETUP None None None None None None None None None None Insert remote RH30B to TAGGED RH30 HV-F007B RHR Pump A Min Flow Valve Insert remote ET006 to RACK_CLOSE ET006 GROUP 3B HV-F027B RHR Supp. Pool Spray Insert remote RH30A to TAGGED on RH30 HV-F007A RHR Pump A Min Flow event 1

  • Valve Insert remote ET005 to RACK_CLOSE ET005 GROUP 3B HV-F027A RHR

Required?

3 5/3/11 Converted to new JPM format. Old JPM was a duplicate of ...1 PM BC-009. Completely rewrote JPM for new task. Validated with 2 operators from "c" Shift. Avg completion time 33 minutes. I . y I I I I I JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum TASK NUMBER: 4000580401 JPM NUMBER: 305H-JPM.CG003 REV #: 01 SAP BET: NOHOSJPCG03E ALTERNATE PATH: D APPLICABILITY:

EO RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 REVIEWED BY: DATE: 1/06 APPROVED BY: DATE: II/gilt Training Department


06-0303 STATION: Hope Creek JPM NUMBER: CG003 REV: 01 SYSTEM: Condenser Air Removal TASK NUMBER: 4000580401 Respond To A Main Condenser Low Vacuum ALTERNATE KIA NUMBER: 271000 A4.04 APPLICABILITY:

EOD S IMPORTANCE FACTOR: 3.4 TAD SRO[]] RO 3.5 SRO EVALUATION SETTING/METHOD:

Simulator/Perform HC.OP-AB.BOP-0006 Rev 14 HC.OP-AB.ZZ-0001 Rev 23 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 13 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 DATE: Page 2 of 18



NAME: DATE: SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum TASK NUMBER: 4000580401 INITIAL CONDITIONS: The plant is operating at 100% power. Main Condenser vacuum is degrading due to fluctuations in 3 rd Stage SJAE flow. Troubleshooting has determined that PIC-1964B, AIR EJECTOR B EXH PRESS, has an electronics problem and failure of the valve is imminent. HC.OP-AB.BOP-0006, Main Condenser Vacuum, is being implemented. Radwaste Operator has been notified. Offgas is in service. INITIATING CUE: Place SJAE A in service on Main Steam accordance with HC.OP-AB.ZZ-0001.

Page 3 of 18


TQ-AA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP NO. CUE CUE ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: Operator obtains the correct procedure.

Operator determines beginning step of the procedure.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. N/A Operator obtains procedure HC.OP-AB.zZ-0001 Attachment

11. Operator determines correct beginning step to be 1.0.
  • EV AL # stu COMMENTS (Required for UNSAT evaluation)

I 1.0 OPEN HV-1957A.

Operator presses the HV-1957 A OPEN pushbutton.

  • # Y N Flagging Operator observes the HV-1957A OPEN light illuminates and the CLOSE light extinguishes.

-Page 4 of 18


TQ-I-\A-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP NO. 2.0 ELEMENT OPEN HV-1955A.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the HV-1955A OPEN pushbutton.

Operator observes the HV-1955A OPEN light illuminates and the CLOSE light extinguishes.

  • # * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

Y N Flagging 3.0 OPEN HV-2016A (HV-2020A if the SJAE's are being supplied by Aux. Stm) THEN OBSERVE 145-150 psig (with Main Steam supplying)

OR approximately 175 psig (Aux Steam supplying) on 2022A. Operator presses the HV-2016A OPEN pushbutton.

Operator observes the HV-2016A OPEN light illuminates and the CLOSE light extinguishes.

Operator observes the PIC-2022A SJAE steam supply pressure at approximately 145-150 psig. * # Y N Flagging Page 5 of 18


TQ-J.\A-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP NO. 4.0 5.0 ELEMENT ENSURE PIC-1964A is in AUTO at 11 psig. OPEN HV-1959A.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the PIC-1964A AUTO pushbutton.

Operator observes the PIC-1964A is in AUTO light illuminates and the MAN light extinguishes.

Operator presses the PIC-1964A UPIDOWN Arrows as necessary to place the setpoint indicator on 11 psig.

Operator presses the HV-1959A OPEN pushbutton.

Operator observes the HV-1959A OPEN light illuminates and the CLOSE light extinguishes.

  • # * # * * # EVAL stu COMMENTS (Required for UNSAT evaluation) Y N Flagging Y N Flagging Y N Flagging 6.0 OPEN HV-1956A.

Operator presses the HV-1956A OPEN pushbutton.

Operator observes the HV-1956A OPEN light illuminates and the CLOSE light extinguishes.

  • # Y N Flagging Page 6 of 18


JPM: CG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #STANDARD S/U evaluation)

OBSERVE the following 3rd

7.0 Operator

observes the FR-2021A SJAE 3FR-2021 A stage flow increasing. Operator observes the PIC-1954A SJAE 3PI-1 954A stage pressure lowering. Y N Flagging Operator presses the HV-1963A OPEN *8.0 pushbutton.

OPEN HV-1963A.

  1. I Operator observes the HV-1963A OPEN light illuminates and the CLOSE light extinguishes. Y N Flagging Operator presses the HV-1962A OPEN *9.0 pushbutton.

OPEN HV-1962A.

  1. Operator observes the HV-1962A OPEN light illuminates and the CLOSE light exting uishes.

10.0 Operator observes the PI-1966A SJAE 2 rd OBSERVE 2nd stage pressure PI-1966A stage pressure lowering.

lowering. Page 7 of 18


TQ-MA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: DATE: __________________

_Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP NO. 11.0 12.0 ELEMENT OPEN HV-1967A OPEN HV-1968 A1, A2, A3. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the HV-1967A OPEN pushbutton.

Operator observes the HV-1963A OPEN light illuminates and the CLOSE light extinguishes.

Operator presses the HV-1968 A 1, A2, A3, OPEN pushbutton.

Operator observes the HV-1968A1, A2, A3, OPEN light illuminates and the CLOSE light extinguishes.

  • # * # * # EVAL stU COMMENTS (Required for UNSAT evaluation)

Y N Flagging Y N Flagging I I 13.0 14.0 VERIFY valve operated in Steps 1.0 thru 12.0 have successfully repositioned.

CLOSE HV-1968 B1, B2, B3. Operator observes all "A "SJAE valves open. Operator presses the HV-1968 B1, B2, B3, CLOSE pushbutton. Y N Flagging Operator observes the HV-1968B1, B2, B3 CLOSE light illuminates and the OPEN light extinguishes. Page 8 of 18


TQ-A.A-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP NO. ELEMENT 15.0 MONITOR PIC-1964A for the following indications:

CUE 16.0 CUE SJAE 3rd stage outlet < 11 psig. Gaseous Radwaste (1900 #/hr). < 75 scfm IF asked as Radwaste Operator, for Offgas Flow, THEN REPORT that Offgas flow is approximately 35 scfm. Five minutes AFTER closing HV-1968 B 1, B2, B3, CLOSE the following valves: "Five minutes have elapsed." (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes the PIC-1964A SJAE 3 rd stage outlet pressure at approximately 11 psig. Operator observes the Gaseous Radwaste Flow <75 scfm. Examiner Note: Operator should check CRIOS points A3431 or A9343 for indication of Offgas Treatment Flow. Operator may request Radwaste to provide flow indication from 1 5665. It will take a few minutes for flow to lower to < 75 scfm. * # EVAL stU COMMENTS (Required for UNSAT evaluatio Page 9 of 18



TQ-AA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Condenser Air Respond To A Main Condenser Low Vacuum STEP NO.

  • HV-1967B
  • HV-1963B ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the HV-1967B CLOSE pushbutton.

Operator observes the HV-1967B CLOSE light illuminates and the OPEN light extinguishes.

Operator presses the HV-1963B CLOSE pushbutton.

  • # EVAL StU COMMENTS (Required for UNSAT evaluation) Y N Flagging Y N Flagging .* HV-1962B
  • HV-1955B Operator observes the HV-1963B CLOSE light illuminates and the OPEN light extinguishes.

Operator presses the HV-1962B CLOSE pushbutton.

Operator observes the HV-1962B CLOSE light illuminates and the OPEN light extinguishes . Operator presses the HV-1955B CLOSE pushbutton.

Y N Flagging Y N Flagging Page 10 of 18


TQ-AA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: DATE: __________________

_Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP (*Denotes a Critical Step)

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

Operator observes the HV-1955B CLOSE light illuminates and the OPEN light extinguishes.

  • HV-1956B Operator presses the HV-1956B CLOSE pushbutton.

YN Flagging Operator observes the HV-1956B CLOSE light illuminates and the OPEN light extinguishes.

1--------

  • HV-1957B Operator presses the HV-1957B CLOSE pushbutton. Y N Flagging

-Operator observes the HV-1957B CLOSE light illuminates and the OPEN light I extinguishes.

  • HV-1959B Operator presses the HV-1959B CLOSE Y N Flagging I pushbutton.

I Operator observes the HV-1959B CLOSE light illuminates and the OPEN light extinguishes.

IPage 11 of 18


TQ-AA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD evaluation S/U Y N Flagging Operator presses the HV-2016B CLOSE

  • HV-2016B (2020B if SJAE supplied by pushbutton.

Aux Steam) Operator observes the HV-2016B CLOSE light illuminates and the OPEN light extinguishes.

WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD the STOP CUE 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


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: CG003 TASK: Respond To A Main Condenser Low Vacuum TASK NUMBER: 4000580401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 13 of 18

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The plant is operating at 100% power. Main Condenser vacuum is degrading due to fluctuations in 3 rd Stage SJAE flow. Troubleshooting has determined that PIC-1964B, AIR EJECTOR B EXH PRESS, has an electronics problem and failure of the valve is imminent. HC.OP-AB.BOP-0006, Main Condenser Vacuum, is being implemented. Radwaste Operator has been notified. Offgas is in service. INITIATING CUE: Place SJAE A in service on Main Steam accordance with HC.OP-AB.ZZ-0001.

Page 14 of 18


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to 100% power, ENSURE B SJAE Train in INSERT Override 5M26_L_AO to INSERT Malfunction MC01 at WHEN Main condenser vacuum alarms, MODIFY Malfunction MC01 as necessary to vacuum steady in IMPLEMENT AB.BOP-0005.

Markup procedure to step ENSURE a copy of HC.OP-AB.BOP-0005 is ENSURE a copy of HC.OP-AB.zZ-0001 Attachment 11 is COMPLETE "Simulator Ready-for-Training/Examination Event code: ! ZLMC1968(1)

>=1.0 &

Description:

Removes malfunction MC01 when SJAE swap complete.

Page 15 of 18 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Initial l\lone None Action Description Insert malfunction MC01 to 12.00000 Low pressure turbine exhaust bellows on event 1 leak I Description None Action Insert override 5M26_L_AO to 3.20 PIC 19648 AIR EJECTOR 8 STA MAN PRESSURE (AO) Page 16 of 18 01 nn\.IQrT<>n JPM CG003 to new "IPM format. time was 13 minutes. TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: CG003 Description Since Critical "IPM are now uniquely identified by the format, all statements critical portion of action were redundant and deleted. change is editorial.

Validation is required to establish times. Validated with 2 ROs on 1/3/12. Avg JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 20009S0S01

..IPM NUMBER: 30SH-JPM.GSOOS REV #: 04 SAP BET: NOH05JPGS05E ALTERNATE PATH: W APPLICABILITY:

EO RO [K] STA '---' SRO I X I DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: 1<f/l..<e f-z;vlZ..

DATE: 'kdt;Z , APPROVED BY: DATE:) //r))l I Training Department


STATION: Hope Creek JPM NUMBER: GS005 REV: 04 SYSTEM: Containment Atmosphere Control TASK NUMBER: 2000950501 Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches ALTERNATE PATH: W KIA NUMBER: 295024 EA1.19 IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY:

EO D RO []] STA D SRO []] RO SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0318(Q)

Rev. 7 TOOLS, EQUIPMENT AND PROCEDURES:

None 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 UNSATISFACTORY:

EVALUATOR'S DATE: Page 2 of 21



TQ-AA-106-0303 NAME: DATE: Containment Atmosphere Control Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK 2000950501 INITIAL CONDITIONS: The 'B' RHR pump suction was isolated due to a leak. The Plant experienced a large break LOCA. HC.OP-EO.ZZ-0102, Primary Containment Control has been implemented. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising. Suppression Pool Level indicates approximately 83 inches. The Emergency Instrument Air Compressor has been restored The Control Room Emergency Filtration System is operating in Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001 FRVS is in operation in accordance with HC.OP-SO.GU-0001(Q). The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

10.Salem Operations has been notified that containment venting will be performed.

11. The Aux. Bldg. EO is standing by at panel 1 Y-F404. 12.The Reactor Building is inaccessible and has been evacuated.

INITIATING CUE: Vent the Containment via the Hard Torus Vent lAW HC.OP-EO.zZ-0318.

Notify the CRS when venting has commenced.

Page 3 of 21


JPM: GS005 OPERATOR TRAINING PROGRAM NAME: DATE: __________________

_Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches COMMENTS (*Denotes a Critical Step) I

  • STEP (#Denotes a Sequential Step) (Required for UNSAT ELEMENT EVAL NO. #STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTERSTARTTIMEAFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains/locates procedure HC.OP-EO.ZZ-0318.

Operator obtains the correct procedure.

Operator reviews precautions and limitations.

Operator reviews precautions and limitations.

CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines correct beginning Operator determines beginning step step to be 5.1.1.of the procedure Page 4of21


TQ-f\A-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: DATE: __________________

_Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches (*Denotes a Critical Step) I

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

S/U 5.1.1 VENT the containment via the Hard Operator reviews Prerequisites Torus Vent as ensures Prerequisites complete. ENSURE that all have been satisfied in with Section 2.0 of this CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.

Operator notifies the CRS to notifiy Officer that containment 5.1.1 B. NOTIFY the Emergency Duty EDO that containment venting via via the Hard Torus Vent will Hard Torus Vent will be CUE Acknowledge the to the t Operator directs the field operator to *C. In the Lower Relay Room, Elev I 5.1.1 install fuse F22 at panel 1 YF404. 102'atpaneI1YF404(see

  1. Attachment 2), INSTALL F22 (6 amp fuse). Page 5 of 21 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: TQ-I-\A-106-0303 Rev: 04 SYSTEM: TASK: JOB PERFORMANCE MEASURE Containment Atmosphere Control Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches DATE:

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

CUE WHEN directed to install 1YF404 fuse F22, THEN TRIGGER ET-3 AND REPORT the fuse is installed. i<**::;:ii:;:

1..

I')) i:

I" / )/) 5.1.1 D. DEPRESS ISLN OVRD and OPEN GS-HV-4964 SUPP CHMBR TO CPCS DMP. Operator depresses the ISLN OVRD pushbutton for the HV-4964. * #

-Operator observes the amber RIDDEN indicator illuminates. Operator depresses the HV4964 OPEN PB. * # Operator observes the red OPEN indicator illuminates and the green CLSD indicator extinguishes.

5.1.1 E. ANNOUNCE that containment venting will commence at the South end of the Reactor Building via the Hard Torus Vent. Operator announces containment venting will commence at the South end of the Reactor Building via the Hard Torus Vent over the plant paging system. Page 6 of21


TQ-AA-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Containment Atmosphere TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 (*Denotes a Critical Step) COMMENTS STEP

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

Stu 5.1.1 F. When HV-4964 SUPP CHMBR TO Operator observes that the CPCS DMP is full open, OPEN indicator is OPEN GS-HV-11541 Operator observes that the HV4964 VENT ISOLATION VALVE. CLSD indicator is extinguished.

Operator rotates HV11541 keylock

  • switch to the OPEN position.

Operator observes the red HV11541 OPEN indicator REMAINS EXTINGUISHED and the green CLOSED indicator REMAINS ILLUMINATED.

I Operator informs CRS. Examiner Note: Based on the and direct Operator to continue CUE Repeat back report from Operator Conditions, the Reactor Building is NOT implement the procedure until accessible.

Manually opening the .. lHV-11541 is not an option. vent path is established.

  • ........ . Page 7 of 21


TQ-MA-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: SYSTEM: Containment Atmosphere TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 STEP NO. 5.1.1 ELEMENT G. When drywell pressure can be maintained below 60 psig, then CLOSE GS-HV-11541 TORUS VENT ISOLATION VALVE. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines drywell pressure is not being maintained below 60 pSig, continues on in the procedure.

  • # EVAL S/U COMMENTS (Required for UNSAT evaluation)

I 5.1.1 -H. REPEAT steps 5.1.1.E thru 5.1.1.G as necessary to reduce and maintain drywell pressure below 65 pSig. Operator determines repeating these steps will not establish a vent path. -5.1.1 I. If actions taken to reduce containment pressure have been unsuccessful, then continue in this procedure.

Operator determined actions taken thus far have not been successful, continues in the procedure. 5.1.2 VENT the containment via the Suppression Chamber supply and ILRT piping as follows: -Operator determines this path is not available since it requires access to the Reactor Building and the reactor Building is not accessible. Page 8 of 21



TQ-kA-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: SYSTEM: Containment Atmosphere TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 I COMMENTS (*Oenotes a Critical Step)

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

S/U CUE IF the Operator requests the status of the "angled piping downstream of 1-GS-V058", THEN INFORM the Operator the piping has NOT been rotated to align the vent path and the Reactor Building is NOT accessible.

Operator determines this path is supply and ILRT piping as 5.1.3 VENT the containment via the Orywell available since it requires access to the Reactor Building and the reactor Building is not accessible.

Operator determines the Suppression Chamber 2" exhaust 5.1.4 VENT the containment via the Chamber 2" exhaust is the next most follows: preferable path. Examiner Note: 3.1.4 states: The selection of vent paths has been presented in priority order. However, if it can be determined that a particular path is unavailable or undesirable, the section addressing that vent path may be omitted (see Attachment 4). Page 9 of 21




TQMJ-\A M 106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: SYSTEM: Containment Atmosphere TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 (*Denotes a Critical Step) COMMENTS*STEP (Required for UNSAT ELEMENT (#Denotes a Sequential Step) EVAL NO. # evaluation)

STANDARD S/U Operator reviews Prerequisites have been satisfied in A. ENSURE that all prerequisites

1.4 ensures

Prerequisites with Section 2.0 of this If excessive time is taken reviewing CUE ' 'i Prerequisites, inform operator that all are satisfied.

I:'" ",,','.i<>*

",i'" ,",',,'-.'

    • '.',' Operator notifies the CRS to notifiy Officer that containment venting 5.1.4 B. NOTIFY the Emergency Duty EDO that containment venting of the Suppression Chamber to Suppression Chamber to the Reactor Building will Building will be

.: ," ,i c',.'*, CUE Acknowledge the communication to the EDO.

i ....'. ',' .'.'.: Operator presses the DRYWELL C. DEPRESS ISLN OVRD and 5.1.4 OPEN GT-HD-9372A Drwl PURGE SHUT OFF DMPRS ISLN #OVRD pushbutton.

Vent Exh Dmpr. -Operator observes the pushbutton backlights. Page 10 of 21


TQ-MA-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: __________

_ SYSTEM: Containment Atmosphere TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the DRYWELL PURGE SHUT OFF DMPRS HD9372A OPEN pushbutton.

  • # * # EVAL StU COMMENTS (Required for UNSAT evaluation) 5.1.4 5.1.4 D. DEPRESS ISLN OVRD and OPEN GS-HV-4964 SUpp CHMBR TO CPCS DMP. E. ANNOUNCE containment venting of the Suppression Chamber to the Reactor Building.

Operator observes the red HD9372A OPEN light illuminates and green CLOSED light extinguishes.

Operator observes the amber RIDDEN light for the HV-4964 ISLN OVRD is already illuminated. Operator observes red HV4964 OPEN light is already illuminated and green CLSD light is already extinguished.

Examiner Note: It is only critical the HV-4964 is open. It is not critical whether it was left open from step 5.1 .1.C, or closed and then re-opened at this step. Operator announces containment venting of the Suppression Chamber to the Reactor Building over the plant page. * # I I I , I I Page 11 of 21 5.1.4 TQ-J-\A-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: __________ Rev: 04 JOB PERFORMANCE MEASURE DATE: __________ SYSTEM: Containment Atmosphere TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. # evaluation)

STANDARD S/U F. When GS-HV-4964 SUPP Operator observes red HV4964 CHMBR TO CPCS DMP is light is illuminated and green open, then DEPRESS light is OVRD and OPEN SUPP CHMBR N2 M/U Operator presses ISLN OVRD for the

  • HV4963. # Operator observes the amber RIDDEN light illuminates. Operator presses the HV4963 OPEN
  • pushbutton.
  1. Operator observes the red OPEN light illuminates and green CLSD light extinguishes. WHEN Vent path has established, TRIGGER ET-6 CUE reduce Drywell Pressure.

Page 12 of21


TQ-JI"\A-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches COMMENTS (Required for UNSAT evaluation)

(*Denotes a Critical Step) I

  • STEP NO. ELEMENT (#Denotes a Sequential Step) STANDARD # 5.1.4 G. When drywell pressure can be maintained below 60 psig, then CLOSE GS-HV-4963 SUPP CHMBR N2 M/U EXH and HV-4964 SUPP CHMBR TO CPCS DMP. CUE WHEN operator informs you the task is complete, OR the J PM 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: Operator informs CRS that drywell venting has commenced and monitors drywell pressure.

EVAL S/U Page 13 of 21

JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: GS005 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 QUESTION: RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:


.. RESULT: SAT UNSAT L.__ Page 14 of 21

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The 'B' RHR pump suction was isolated due to a leak. The Plant experienced a large break LOCA. HC.OP-EO.ZZ-0102, Primary Containment Control has been implemented. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising. Suppression Pool Level indicates approximately 83 inches. The Emergency Instrument Air Compressor has been restored The Control Room Emergency Filtration System is operating in Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001 FRVS is in operation in accordance with HC.OP-SO.GU-0001 (0). The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

10. Salem Operations has been notified that containment venting will be performed.

11.The Aux. Bldg. EO is standing by at paneI1Y-F404.

12. The Reactor Building is inaccessible and has been evacuated.

INITIATING CUE: Vent the Containment via the Hard Torus Vent lAW HC.OP-EO.ZZ-0318.

Notify the CRS when venting has commenced.

Page 15 of 21 TQ*AA*106*0303 JOB PERFORMANCE MEASURE i INITIALIZE the simulator to 100% power, MOL, EPU. CLOSE the BC-HV-F004B RHR pump suction valve. ISOLATE drywell cooling by closing the inboard and outboard drywell chilled water isolation valves. TRIGGER ET-1 and ESTABLISH post large break LOCA conditions with a downcomer break and drywell pressure approximately 60 pSig. Malfunctions may be modified as necessary.

CLOSE the MSIVs and drains. IMPLEMENT EOP-101 AND EOP-102 AFTER drywell pressure is raised to approximately 60 psig. ! RESTORE Instrument Air lAW EOP-319. : PLACE Temporary Air Compressor in service. Trend DW pressure using Insight Item MONVAR(19)

OPEN BCHV-F016A I OVERRIDE and close BCHV-F017A PLACE 'A' RHR pump in drywell spray with the exception of opening the HV-F021 A. FAIL OPEN an ADS SRV. USE Insight Item rhv021(1 ) (set to -0.00 to 0.2) to crack open the F021A as necessary to establish drywell i pressure at 60 psig and rising slowly. Trigger ET-5 to stabilize DW pressure indications at 62 psig. I USE Insight Item rhv017(1) (set to -0.00 to 0.1) to crack open the F017 A as necessary to establish slowly rising RPV level. I ENSURE CREF is in service in the ISOLATE/RECIRC Mode lAW SO.GK-0001.

I ENSURE FRVS is in Service lAW SO.GU-0001.

i I Description I COMPLETE "Simulator Ready-for-Training/Examination Checklist".

TQ*AA*106-0303 JOB PERFORMANCE MEASURE pcpdw>= 16.2 II Drywell Pressure in psia i Inserts Feedwater line break and LOCA after drywell preheated ZLHVDPDO(1)

>= 1.0 & ZLPCBLO(2)

>= 1.0 & ZLPCISVO(2)

>= 1.0 6 9372A + 4963 + 4964 Open lights ON II Lowers DW established.

Event code:

Description:

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Initial @Time Event Action Description None None Insert malfunction FW32 to Feedwater line break inside 100.00000 on event 2 containment l\Jone None Insert malfunction FW04A after 60 on Secondary condensate pump AP137 event 2 trip None None Insert malfunction FW04B after 60 on Secondary condensate pump BP137 event 2 trip None Non Insert malfunction FW04C after 60 on Secondary condensate pump CP137 event 2 trip None None Insert malfunction MS01 after 90 to Steam line break in drywell 4.00000 on event 2 None None Insert malfunction PC04 on event 4 Downcomer break None None Insert remote RH23B to TAGGED RH23 RHR Pump B None None None None None None None None Insert remote RH20A to RACK_OUT Insert remote ET067 to INSTALLED on event 3 Insert remote IA 10 to RUN Insert remote EP38 to Emergency RH20 HV-F021A RHR CTMT SPRAY ET067 HV-11S41 Torus vent IA 10 T em porary station air com pressor EP38 EOP-319, Restoring Instrume Air in an Emergency

JOB PERFORMANCE

  • Description None Insert override 6S151 _A_DI to Dff i HV-11541 DPEN KEY SW (DI) Insert override 6AR11_B_AD to I PRESSURE DRYWELL PR-4960A2 . None 28.00000 on event 5
  • WIDE RANGE (AD) Insert override 6AR11_R_AD to PRESSURECHAMBER PR-4960A 1 None I i 28.00000 on event 5 WIDE RANGE (AD) *Insert override 6AR13_B_AD to PRESSURE DRYWELL PR-4960B2 None 26.00000 on event 5 WIDE RANGE (AD) *Insert override 6AR13_R_AD to i PRESSURE CHAMBER PR-4960B1 None 26.00000 on event 5
  • WIDE RANGE *Insert override 6AR11_B_AD after 1 PRESSURE DRYWELL l\lone to 22.00000 in 60 on event 6 WIDE RANGE (AD) i Insert override 6AR11_R_AD after 1 PRESSURECHAMBER PR-4960A1 None None WIDE RANGE (AD)*to 22.00000 in 60 on event 6 i Insert override 6AR13_B_AD after 1 None None i
  • to 22.00000 in 60 on event 6 , None ' I nsert override None I to 22.00000 in , I PRESSURE DRYWELL PR-4960B2 WIDE RAI\lGE (AD)

TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: G8005 Rev # I Date Validation Required?

y 01 9/4/2008 This revision converts to HC LOR format, documents and generates estimated completion Since Critical JPM actions are now uniquely identified by format, all statements identifying critical portion of action redundant and Corrected typo error at step 5.1.4.F Updated Reference procedure revision number. No Operator i actions changed I Added Remote functions for Temp Air Compressor and 319 I I N I This revision updates the turnover sheet to suppression pool level from 80 to 83 inches. No changes to operator actions. No 02 i 5/6/10 i validation Modified Malfunction, Remote, Override, and Event list sections N for TREX event syntax. Updated Reference procedure revision numbers only. No changes to operator actions. No validation required . 5/9/11 ... --. I i 04 1/14/12 Added Overrides to freeze OW pressure indications to prevent Y i Simulator aborts. Adds Trigger to delete Overrides when I flowpath established.

No changes to operator actions. Validated with 2 ROs on 1/4/12. Avg completion time was 15 I minutes, i i JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod TASK NUMBER: 4000040401 JPM NUMBER: 305H-JPM.BF011 REV#: 01 SAP BET: NOH05JPBF11 E ALTERNATE PATH: IT] APPLICABILITY:

EO RO STA SRO D 00 D DEVELOPED BY: Archie E. Faulkner DATE: 9/14/11 Instructor REVIEWED BY: fi DATE: ///y/;/.. 7 /Operations Representative APPROVED BY: DATE:Ullll1 IV Training Department


STATION: Hope Creek JPM NUMBER: BF011 REV: 01 SYSTEM: Control Rod and Drive Mechanism TASK NUMBER: 4000040401 Respond To An Uncoupled Control rod ALTERNATE PATH: [KJ KIA NUMBER: 201003A2.02 IMPORTANCE FACTOR: 3.7 3.8 APPLICABILITY:

EO D RO [KJ STA D SRO [KJ RO SRO EVALUATION SETTING/METHOD:

Simulator/Perform HC.OP-ST.BF-0001 Rev 31 HC.OP-AB.IC-0001 Rev 14 TOOLS, EQUIPMENT AND PROCEDURES:

00-7 for IC-2 rod positions.

Signed on copy of OP.ST.BF-0001 for rod 38-03 only. ESTIMATED COMPLETION TIME: 33 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 21 i



TQ-AA-106-0303 NAME: DATE: SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod TASK NUMBER: 4000040401 INITIAL CONDITIONS: The Plant is operating at 100% power. Maintenance was performed on the position indication circuit of rod 38-03 The maintenance is complete. As part of the retest requirements, performance of HC.OP-ST.BF-0001 Control Rod Drive Exercise -Weekly is required for control rod 38-03 only. The "ON DUTY" Reactor Engineer has been notified that control rod 38-03 will be exercised lAW HC.OP-ST.BF-0001. The Reactor Engineer has approved exercising rod 38-03 at 100% power. Stall flows are NOT required.

INITIATING CUE: Exercise control rod 38-03 lAW HC.OP-ST.BF-0001.

Page 3 of 21



TQ-MA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP NO. ELEMENT CUE PROVIDE the operator the initiating cue. CUE ENTER START TIME AFTER Operator repeats back the Initiating

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue.

  • COMMENTS EVAL (Required for UNSAT # S/U evaluation)

N/ASTART Examiner Cue: PROVIDE the Operator obtains the correct Operator with the mark-up copy of procedure.

HC.OP-ST.BF-0001.

Operator reviews precautions and limitations.

Operator reviews precautions and limitations.

CUE IF excessive time is reviewing precautions IIlimitations, N/A THEN INFORM operator that all are satisfied. KX JOOOO< Page 4 of 21


TQ-J-\.A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: ________________

_ SYSTEM: Control Rod and Drive TASK: Respond To An Uncoupled Control STEP NO. ELEMENT Operator determines beginning step of the procedure.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines correct beginning step to be 5.1. * # EVAL StU COMMENTS (Required for UNSAT evaluation) 5.1 LOG test start time in the Control Room log(s). Operator requests the procedure be logged in the Control Room log. CUE 5.2 CUE 5.3 The start time for 0001 for retest of rod 38-03 only, has been logged in the Control Room log. ENSURE all prerequisites of Section 2.0 are satisfied.

If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.

ENSURE Attachment 1, Section 1.0 has been completed AND Regular Surveillance OR Retest is indicated.

Examiner Note: It is not critical to initial the procedure steps. Operator ensures that all prerequisites have been satisfied.

N/A Operator observes Attachment 1, Section 1.0 has been completed AND Retest is indicated. g§ Page 5 of 21



TQ-,",A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) ELEMENT EVAL (Required for UNSAT NO. #STANDARD S/U evaluation)

Operator prints 00-7 from of the current Control Rod

5.4 OBTAIN

a computer printout (OD-7) computer terminal.

I Operator reviews 00-7 for rod 38-03 CUE Provide copy of OD-7. IF OD-7 i I printout not available, THEN direct position.

operator to use ppe terminal.

I i Operator reviews the requirement Nuclear Instrumentation OBSERVE proper response of the 5.5 observe proper response of the Instrumentation while OR inserting all Control OR inserting all Control Rods. Y N Flagging 5.6 Operator presses ROD SELECT SELECT a withdrawn Control Rod AND RECORD the initial Control Y N Barriers MODULE 38-03 pushbutton.

  1. I position on Attachment
2. i !Operator records the initial rod position of 48 on Attachment
2. I5.7 IF Control Rod is at position 00, RECORD final Control Rod position on Attachment
2. All other blocks are for this Page 6 of 21

indicated on CRID's point B2117. TQ"AA-106-0303 1 OPERATOR PROGRAM Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod (*Denotes a Critical Step) COMMENTS*STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step) NO. #STANDARD S/U evaluation)

Operator obselVes approximately through both the insert 5.8 OBSERVE ClPproximately 6 gpm total gpm total flow through both the Stabilizing Valves AND withdraw Stabilizing Valves as indicated on CRID's point B2117. Operator reads the 1-BF-V138, Cooling Header Check Valve, as required NOTE The following two steps will exercise TIS 4.0.5. If a "failed position" is a single notch insertion attempted, an alternate position selected to insert the rod, that guidance is obtained Reactor Engineering.

In this tile remarks section of Attachment should document the position Y N Flagging Operator momentarily presses the ROD 5.9 INSERT the selected Control Rod one

  • as directed by Reactor Y N Barriers # MOTION CONTROLS INSERT Engineering)

AND following:

[TIS 4.1.3.1.2, TIS Page 7 of 21


TQ-I-\.A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Control Rod and Drive TASK: Respond To An Uncoupled Control STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL stU COMMENTS (Required for UNSAT evaluation)

5.9.1 ENSURE

proper operation of the RPIS. Operator observes the CONTROL ROD POSITION FOUR ROD DISPLAY, RWM, or CRIDS indicates control rod movement to position 46. 5.9.2 IF the Control Rod was inserted beyond its intended position, THEN IMMEDIATELY WITHDRAW the Control Rod to its intended position AND CONTACT Reactor Engineering.

Examiner Note: IF the Operator inserts the Control Rod beyond position 46, THEN the Operator IMMEDIATELY withdraws the Control Rod to position 46 AND contacts Reactor Engineering.

5.9.3 IF the control rod does not insert to the next notch after one attempt, PERFORM the following:

Operator recognizes this step is not applicable and continues at step 5.9.4 5.9.4 INDICATE the condition of RPIS indication on Attachment

2. Operator then indicates the RPIS indication is SAT on Attachment
2. 5.10 IE the position recorded in Step 5.7 is an intermediate position, THEN PERFORM Step 5.10.1, otherwise, GO TO Step 5.10.2 to return the control rod to its original position:

Operator determines the position recorded in Step 5.7 is NOT an intermediate position, continues at step 5.10.2 to return the control rod to its original position.

Page 8 of 21


5.10.2 JPM: Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod NOTE IF drive water pressure was increased to withdraw a control rod from position 46, the same or slightly higher pressure should be used to perform uncoupling check. [80009340J Control Rods experiencing coupling problems should be single-notched to 48 (with settle) prior to using continuous withdraw to verify coupling.

WITHDRAW the control rod to position 48 AND PERFORM the following while giving the selected Control Rod a continuous withdraw signal: [TIS 4.1.3.6, TIS 4.1.3.7] OBSERVE the following as indication of the Control Rod being coupled: ROD OVERTRAVEL alarm does NOT annunciate.

TQ-kA M 106-0303 OPERATOR TRAINING PROGRAM NAME: __________________

_ JOB PERFORMANCE MEASURE DATE: ________________

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

Operator reads NOTE and determines the NOTE is not applicable. Y N Barriers Operator simultaneously presses AND

  • holds both the WITHDRAW pushbutton
  1. AND the CONTINUOUS WITHDRAW pushbutton.

NIA Operator observes OHA C6-F3 ROD OVERTRAVEL DOES annunciate.

-_I I Page 9 of 21



TQ-M.A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Control Rod and Drive TASK: Respond To An Uncoupled Control STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

Operator releases both the WITHDRAW pushbutton AND the CONTINUOUS WITHDRAW pushbutton.

Operator observes the red FULL OUT light on the Full Core Display

2. Red Full Out light illuminates on the Full Core Display_
3. RP1S indicates the Control Rod is full out (48). Operator observes RPIS does NOT indicate position 48. 4. Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. B. INDICATE on Attachment 2 the condition of Coupling Check.

Operator recognizes the expected response of the Nuclear I nstrumentation while withd rawing the Control Rod. Examiner Note: The expected response for a rod from 46 to 48 is negligible.

Operator indicates the coupling check is UNSAT on Attachment

2. Page 10 of 21

TQ-.kA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Control Rod and Drive TASK: Respond To An Uncoupled Control (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # evaluation STANDARD S/U Based on the Initial C, PERFORM the following for stall Operator determines Stall Flow is NOT required.

Operator marks the step uN/A", Examiner Note: Due to the failed coupling check, this step may not be performed until later, or may not be performed at all. Operator informs the CRS of THEN D. IF the CRD over travels, control rod and entry condition HC.OP-AB.IC-0001 Control CUE Acknowledge the report and DIRECT the Operator to implement N/A Condition D of HC.OP-AB.lC-0001.

HC.OP-AB.lC-0001 Condition D Uncoupled Rod and Movement Permitted by RWM Operator requests Reactor guidance to recouple the Control OBTAIN Reactor Engineering guidance to recouple the Control Rod. Page 11 of 21 D.1





0.2 TQ-MA-106-0303 BF011 OPERATOR TRAINING PROGRAM NAME: 01 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. CUE INFORM the Operator that Reactor Engineer's guidance in NOT available.

IF Reactor Engineering CAN NOT be THEN RECOUPLE the Control as

(*Denotes a Critical Step) * (#Denotes a Sequential Step) EVAL STANDARD # S/U N/A Operator determines step D.2 is applicable.

COMMENTS (Required for UNSA T evaluation) 0.2.a INSERT the CRD no more than 2 notches from the point of discovery. D.2.b Single Notch WITHDRAW the Control Rod to original position AND VERIFY ,.., v,",,,,,,f,,, response

  • Operator single notch inserts rod 38-03 to position 46 using INSERT PB. Examiner Note: Due to the rod being at Overtravel, it will take two single notch insertions to insert the rod to 46. The first insertion will settle the rod at 48 and may bring in OHA C6-E3 ROD DRIFT. IF ROD DRIFT alarm comes in, THEN operator will respond using OHA C6-E3 Alarm Response Procedure and determine rod 38-03 caused the alarm. Operator single notch withdraws rod 38-03 to position 48. Operator observes correct response of the control rod. * # Y N Y N Flagging Barriers Page 12 of 21


TQ-I-\A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Control Rod and Drive TASK: Respond To An Uncoupled Control (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential EVAL (Required for UNSAT NO.

  1. StU evaluation)

D.2.c PERFORM a coupling check on the NIA associated control rod lAW 0001. NIA CUE Provide operator 2 nd marked up copy of HC.OP-ST.BF-0001.

HC.OP-ST.BF-0001 Operator simultaneously presses AND position 5.10.2 WITHDRAW the control rod to holds both the WITHDRAW pushbutton Y N Barriers #AND the CONTINUOUS giving the selected AND PERFORM the following while Rod a continuous withdraw [TIS 4.1.3.6, TIS Operator observes OHA C6-F3 indication of the Control A. OBSERVE the following as OVERTRAVEL does NOT being ROD OVERTRAVEL alarm NOT , Operator observes the red FULL the Full Core

2. Red Full Out light illuminates on light on the Full Core Display illuminates.

Page 13 of 21


TQ-J-'\A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

__ SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

3. RPIS indicates the Control Rod is full out (48). Operator observes RPIS indicates the Control Rod is full out (48). 4. Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. Operator recognizes the expected response of the Nuclear Instrumentation while withdrawing the Control Rod. Examiner Note: The expected response for a rod at 48 is negligible.

B. INDICATE on Attachment 2 the condition of Coupling Check. Operator indicates the coupling check is SAT on Attachment

2. Page 14 of 21


D.3 06-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM: Control Rod and Drive TASK: Respond To An Uncoupled Control (*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD S/U evaluation)

HC.OP-AB.IC-0001 Condition D Uncoupled Rod and Movement Permitted by RWM ------------+--1

---j RESTRICT all further withdrawals of Operator informs the CRS that all this rod to Single Notch movement further withdrawals of this rod should be Y N Barriers repairs have been completed.

restricted to Single repairs have been completed.

CUE WHEN operator informs you the task the JPM has been terminated other RECORD the STOP N/A REPEAT BACK operator on the state "This JPM is STOP TIME: Page 15 of 21


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: BF011 TASK: Respond To An Uncoupled Control rod TASK NUMBER: 4000040401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: UNSAT SAT I '----------" Page 16 of 21

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The Plant is operating at 100% power. Maintenance was performed on the position indication circuit of rod 38-03 Tile maintenance is complete. As part of the retest requirements, performance of HC.OP-ST.BF-0001 Control Rod Drive Exercise -Weekly is required for control rod 38-03 only. The "ON DUTY" Reactor Engineer has been notified that control rod 38-03 will be exercised lAW HC.OP-ST.BF-0001. The Reactor Engineer has approved exercising rod 38-03 at 100% power. Stall flows are I\JOT required.

INITIATING CUE: Exercise control rod 38-03 lAW HC.OP-ST.BF-0001, Page 17 of 21


JOB PERFORMANCE SIMULATOR SETUP INITIALIZE the simulator to IC#2, 100% power, MOL. SELECT rod 02-19 on the Rod Select Module. ENSURE CRD Drive Water pressure 260 -270 psid. ENSURE associated Schedule file open and running. ENSURE associated Events file open. Description ENSURE two copies of HC.OP-ST.BF-0001 are available, marked up for rod 38-03 ONLY, and with Step ENSURE OD-7 for IC#2 is COMPLETE "Simulator Ready-for-Training/Examination Initial Event code: Icvposx(6)::>

770 II Rod 38-03 Overtravel

==

Description:==

Senses 38-03 withdrawn past 48. Event code:

  • et_array(1)
>= 1.0 & Icvposx(6)

< 740

Description:

Rod 38-03 Overtravel and inserted 1/ Deletes uncoupled rod after it has been inserted Event more than one notch lAW AB Page 18 of 21 TQ*AA*106*0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNOTIONSCHEDULE* " , > '?'<,-->,'" '",/:.'; ,,' >"f /.,.-'< ..

,,<'i i">i 'I" i}'T";: ,i'" Initial @Time Event Action Description None None Insert malfunction CD043803 Control Rod 38-03 uncoupled None None Insert malfunction CD043803 on event 2 delete in 1 Control Rod 38-03 uncoupled Description Initial @Time I Event Action "OVERRfDEscHEDurE*

i 10"', " 'i, '<', " @Time Event Action Description Initial Insert override 3A81 G_DI to On on ROD SELECT -ROD DRIFT RESET (DI) event 1 Page 19 of 21 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: BF011 Rev# Date Description Validation Required?

01 9/14/11 This revision converts to HC LOR format, documents validation, and generates estimated completion time. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted. Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. Updated Reference procedure revision numbers only. Rewrote steps for uncoupled rod with no RE guidance.

Validated with 2 operators from "C" Shift 9/13/11. Avg completion time 33 minutes. Y I JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction TASK NUMBER: 4000110401 JPM NUMBER: 305H-JPM.SB010 REV #: 05 SAP BET: NOH05JPSB10E ALTERNATE PATH: D APPLICABILITY:

EOD RO []] STA D SRO []] DEVELOPED BY: Archie E. Faulkner DATE: 12/30/11 Instructor REVIEWED BY: !'(k..-

DATE:

APPROVED BY: DATE:

}/)r/)2 Training Department


STATION: Hope Creek JPM NUMBER: S8010 REV: 05 SYSTEM: Reactor Protection System TASK NUMBER: 4000110401 TASK: Respond To A Reactor Protection System Malfunction ALTERNATE PATH: D KIA NUMBER: __2_12_0_0_0_A_2._0_1

__ APPLICABILITY:

EO D RO []] IMPORTANCE FACTOR: STA D SRO 3.7 RO 3.9 SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.IC-0003, Rev 04 TOOLS, EQUIPMENT AND PROCEDURES:

None ESTIMATED COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes ..IPM 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



SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction TASK NUMBER: 4000110401 INITIAL CONDITIONS: The plant was operating at 100% power when the 'A' RPS MG set tripped due to a bearing problem. Restoration of the 'A' RPS MG set is not possible at this time. There is no damage to the 'A' RPS bus. INITIATING CUE: Perform Condition A of Restoration of isolated equipment is not necessary at this Page 3 of 14 A.1 TQ-nA-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: __________________

_ Rev: 05 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction COMMENTS (*Denotes a Critical Step) *STEP (Required for UNSAT (#Denotes a Sequential Step) EVAL ELEMENT NO. # evaluation)

STANDARD stu CUE PROVIDE the operator the Operator repeats back initiating cue. ENTER START TIME OPERATOR REPEATS CUE N/A INITIATING CUE: ...START TIME: .. Operator obtains the correct procedure.

Operator obtains procedure Operator determines correct beginning Operator determines beginning step step to be A.1 . of the procedure.

Operator determines restoration of Normal RESTORE Normal Power to the Power to the bus is not possible lAW Initial affected Bus. Conditions provided. (if possible)

Page 4 of 14



TQ-MA-106-0303 SB010 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction STEP NO. ELEMENT (*Denotes a Critical Step) * (#Denotes a Sequential Step) EVAL STANDARD # S/U COMMENTS (Required for UNSAT evaluation)

CAUT 1 1. The RPS MG Set Transfer Switch is a "Break before Make" type switch. Positioning it to the wrong position will result in a full scram. Operator reviews Caution 1.

A.2 lE Normal Power cannot be restored:

a. VERIFY Alternate Power is available.

Operator verifies Alternate Power is available by observing the ALTERNATE A FEED light on 10C610 is illuminated.

CUE If contacted as the NEO to verify Alternate power is available, REPORT Alternate power appears to be available.

b. TRANSFER Power to the Alternate Power Supply by POSITIONING the RPS MG SET TRANSFER SWITCH to the Alternate position.

[CD324X] N/A I; : :' . "

Operator turns the RPS MG SET

  • TRANSFER SWITCH to the ALTA position.
  1. Page 5 of 14 TQ-J-lA-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor Protection TASK: Respond To A Reactor Protection System STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

A.3 RESET the 1/2 Scram as follows: a. TURN the key for the Affected RPS channel(s) to the RESET position.

b. TURN the key BACK to NORMAL. Operator turns the key for the RPS A 1 Trip Logic to RESET and back to NORMAL. * # Operator turns the key for the RPS A2 Trip Logic to RESET and back to NORMAL. * # c. VERIFY the Scram is reset. Operator verifies the scram is reset by observing the following:
  • RPS TRIP LOGIC A 1 and A2 NORMAL/RESET lights are illuminated
  • All four PILOT SCRAM VALVE SOLENOID LOGIC A NORMAL lights are illuminated
  • REACTOR SCRAM TRIP LOGIC A 1 and A2 OHAs are no longer illuminated Page 6 of 14

06-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

A.4 IF the MSIV's are OPEN THEN RESET the tripped NSSSS Logic as follows: a. PRESS the NUCLEAR STEAM SUPPL Y SHUTOFF SYSTEM TRIP LOGIC A(8,C,D) RESET Pb. Operator presses the NUCLEAR STEAM SUPPL Y SHUTOFF SYSTEM TRIP LOGIC A pushbutton.

  • #

Operator presses the NUCLEAR STEAM SUPPL Y SHUTOFF SYSTEM TRIP LOGIC C RESET pushbutton.

  • # b. VERIFY MSIV TRIP LOGIC TRIPPED goes off. Operator verifies the MSIV TRIP LOGIC TRIPPED light for LOGIC A is extinguished.

Operator verifies the MSIV TRIP LOGIC TRIPPED light for LOGIC C is extinguished.

Page 7 of 14



TQ-r-.A-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL stU COMMENTS (Required for UNSAT evaluation)

WHEN operator informs you the task is complete, 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: N/A Page 8 of 14


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: SB010 TASK: Respond To A Reactor Protection System Malfunction TASK NUMBER: 4000110401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 9 of 14

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The plant was operating at 100% power when the "A' RPS MG set tripped due to a bearing problem. Restoration of the 'A' RPS MG set is not possible at this time. There is no damage to the "A' RPS bus. INITIATING CUE: Perform Condition A of Restoration of isolated equipment is not necessary at this Page 10 of 14 TQ-AA-106-0303 JOB PERFORMANCE MEASURE ,'/'" , ':, Ie:... > ,"' Initial INITIALIZE the simulator to 100% power, MOL. INSERT malfunction RP02A. AFTER RWCU trips and conditions stabilize, ACKNOWLEDGE all overhead and RM11 alarms. ENSURE associated Schedule file open and running. ENSURE associated Events file open. Initial COMPLETE "Simulator Ready-for-Training/Examination Initial ET # Event code:

Description:

Event code:

Description:

Event code:

Description:

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Action None None Insert malfunction RP02A RPS MG Set A failure Initial @Time Event Action Description TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: S8010 Rev# 04 05 ! Date 9/4/2008 12130/11 Description This revision converts to HC LOR format, documents validation, and generates estimated completion time. Since Critical JPM actions are now uniquely identified by the format, ali statements identifying critical portion of action were redundant and deleted. Updated Reference procedure revision number. No change to operator actions. Revised Initial Conditions from 97% to 100%. Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. Updated Reference procedure revision numbers only. No changes to operator actions. No validation required.

Validation Required?

Y N I I JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 JPM NUMBER: 305H-JPM.ED002 REV#: 05 SAP BET: NOH05JPED02E ALTERNATE PATH: 0 APPLICABILITY:

EO RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 12/22/11 Instructor REVIEWED BY: 0,z-ufi-oc DATE: APPROVED BY: DATE:J flail< I Training Department

STATION: Hope Creek JPM NUMBER: ED002 REV: 05 SYSTEM: Reactor Auxiliaries Cooling System TASK NUMBER: 4000230401 TASK: Respond To A Reactor Auxiliary Cooling Malfunction ALTERNATE PATH: W KIA NUMBER: 295018 AA2.02 IMPORTANCE FACTOR: APPLICABILITY:

EOD ROCK] STAD SRO CK] EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-SO.ED-0001 Rev 23 HC.OP-AR.ZZ-0002 Rev 21 HC.OP-AB.COOL-0003 Rev 4 TOOLS, EQUIPMENT AND PROCEDURES:

None ESTIMATED COMPLETION TIME: 13 3.3 RO Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: I\J/A Minutes 3.4 SRO ..IPM 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 19



SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 INITIAL CONDITIONS: The RACS System is in service with the AP209 and CP209 RACS pumps running. AP209 RACS pump is scheduled for an oil change. The Reactor Building EO has been briefed and is stationed at the BP209 RACS pump. The BP209 has NOT been isolated since the last time it was in service and is ready for a start. INITIATING CUE: You are the Plant Place the BP209 RACS pump in service and secure the AP209 RACS Page 3 of 19 TQ-hM-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor Auxiliaries Cooling TASK: Respond To A Reactor Auxiliary Cooling

(*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 N/A INITIATING CUE: START TIME: Operator obtains the correct procedure.

Operator obtains procedure HC.OP-SO.ED-0001.

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 Operator determines beginning Operator determines correct beginning of the procedure.

step to be 5.3.1. Page 4 of 19 TQ-M.A-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction COMMENTS (*Denotes a Critical Step) *STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step) NO. # eval S/U STANDARD Operator ensures that all prerequisites

5.3.1 ENSURE

all prerequisites have have been satisfied lAW Section Operator then initials the Reactor Auxiliaries Cooling Water procedure step. System is in service. If excessive time is taken prerequisites, inform operator CUE N/A all are satisfied.

On 1 OC651 A operator observes the HX INLET VALVES: 5.3.2 ENSURE that one of the following valves are OPEN ED-HV-2537A(B)

HX INLET HX AE217 INLET red HV2537 A OPEN light is illuminated and green CLOSE light is extinguished HX BE217 INLET red HV2537B OPEN light is illuminated and green CLOSE light is extinguished.

Page 5 of 19


--TQ-kA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor Auxiliaries Cooling TASK: Respond To A Reactor Auxiliary Cooling COMMENTS (*Denotes a Critical Step) *STEP (Required for UNSA T ELEMENT (#Denotes a Sequential Step) EVAL NO. # evaluation)

STANDARD S/U 5.3.3 OBSERVE the following lights are for the RACS Operator observes the REACTOR going in service: AUXILIARIES COOLING PUMP Bamber OVLD/PWR

  • OVLD/PWR FAIL INOP, and white REMOTE lights are
  • INOP extinguished.
  • REMOTE For the 1 AP209 and/or 1 BP209, 5.3.4 On 10C650E operator observes the ENSURE RACS PMP 1AP209 BKR RACS PMP BP209 BRKR 52-42011 52-41011, red CLOSED light is illuminated and and/or 1 BP209 BKR 52-42011 green TRIPPED light is extinguished.

CLOSED is on. (10C650E) 5.3.5 IF returning a pump to service that has been isolated and drained, PERFORM the following steps as Operator determines to proceed to Step necessary to correct/prevent air 5.3.6, since the Initiating Cue states binding, otherwise, PROCEED to that the pump was not isolated.

Step 5.3.6 for a normal start of standby Page 6 of 19


TQ-,...",,-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 05 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction STEP NO. 5.3.6 ELEMENT PRESS REACTOR AUXILIARIES COOLING PUMP A(B)(C) START PB (10C651A).

START comes on. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the REACTOR AUXILIARIES COOLING PUMPS PUMP B BP209 START pushbutton.

  • # * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

OBSERVE AI-6460 (AI-6461)

REACTOR AUXILIARIES COOLING PUMP A(B)(C) MOT AMPS settles at < 180 amps AND is approximately the same as the other I/S RACS pumps' motor amps. Operator observes:

  • The red BP209 START light illuminates and the green STOP light extinguishes.
  • AI-6461 is < 180 amps and settles at approximately the same value as the "An and "C" RACS pumps' amps. 5.3.7 PRESS REACTOR AUXILIARIES COOLING PUMP B(A)(C) STOP PB. STOP comes on. Operator presses the REACTOR AUXILIARI COOLI NG PU M PS PUMP A STOP pushbutton.
  • # L __________

Operator observes the green STOP light illuminates and the red AP209 START light extinguishes.

  • Page 7 of 19


TQ-kA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Auxiliaries Cooling TASK: Respond To A Reactor Auxiliary Cooling COMMENTS (*Denotes a Critical Step) *STEP ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. # evaluation)

STANDARD S/U 5 seconds after the 'A' RACS pump been secured, the Operator Control Board N/A Operations Fundamental:

the following: OHA A2-E2, "RACS TROUBLE" CRIOS 05762 RACS PUMP BP209 TRBL Amber OVLD/PWR FAIL is flashing Red BP209 START light is extinguished. Green STOP light is flashing. AI-6461 reads 0 amps. HC.OP-AR.ZZ-0002 N/A N/A ATT OPERATOR ACTION: E2 1. REFER HC.OP-AB.COOL-0003(Q); Auxiliary Cooling 2. ENSURE compliance with Operator refers to Technical Specifications 3.6.3 HC.OP-AB.COOL-0003.

Containment Isolation Valves. 3. ENSURE compliance Technical Specifications

3.6.5 Secondary

Containment Page 8 of 19



A.1 TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Auxiliaries Cooling TASK: Respond To A Reactor Auxiliary Cooling

(*Denotes a Critical Step) COMMENTS STEP

  • ELEMENT (#Denotes a Sequential Step) (Required for UNSAT EVAL NO. #STANDARD S/U evaluation CUE Direct the Operator to perform Condition

'A' of HC.OP-AB.COOL-0003 Reactor Auxiliary Cooling HC.OP-AB.COOL-0003 N/A N/A COND Date/Time Operator enters the current Date/Time in the spaces provided.

A PRESS the START P.B. for any Operator presses the available RACS pump in AUXILIARIES COOLING PUMPS PUMP A AP209 START pushbutton.

Operator observes: The red AP209 START light remains extinguished and the green STOP light remains illuminated. Motor amps continue to indicate O. Page 9 of 19


TQ-,",,,,-106-0303 ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction COMMENTS(*Denotes a Critical Step) * (Required for UNSAT I

  • STANDARD # StU SNO (#Denotes a Sequential Step) EVAL evalu I Respond to any reports of the 'A' RACS pump failure to start by directing the operator to continue N/A implementing Condition

'A' LE a second RACS Pump CANNOT be placed in service, THEN ISOLATE RACS to the out of service Off-Gas Train as follows: LE the Common Off-Gas Train is in service, THEN CLOSE HV-2577. LE Unit 1 Off-Gas Train is in service, -'-'--'.=-=-=-

CLOSE HV-7712A1.

Operator observes the OFFGAS RECOMB TRAIN SELECT: COM TRAIN red OPEN light illuminated and green CLOSE light extinguished. TRAIN 1 red OPEN light extinguished and green CLOSE light illuminated.

Operator presses the OFF GAS CLR

  • CNDS COOLING 10E306 UNIT 1 green CLOSE pushbutton.

Operator observes the green CLOSE light illuminates and red HV2577 OPEN light extinguishes.

Page 10 of 19


TQ-kA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: __________________

_ Rev: 05 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction COMMENTS (*Denotes a Critical Step) *STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step) NO. # S/U evaluati STANDARD wvoJ CUE If the Operator Closes HV2577 JPM may be terminated.

If operator closes the allow 1 minute to recognize mistake and then terminate N/A Leaving the HV7712A 1 closed causing an isolation of the Offgas Train is failure CUE WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD REPEAT BACK any message from operator on the status of the JPM, then state "This JPM is STOP TIME: Page 11 of 19


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: ED002 TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 12 of 19

JOB PERFORMANCE INITIAL CONDITIONS:

1. The RACS System is in service with the AP209 and CP209 RACS pumps running. 2. AP209 RACS pump is scheduled for an oil change. 3. The Reactor Building EO has been briefed and is stationed at the BP209 RACS pump. 4. The BP209 has NOT been isolated since the last time it was in service and is ready for a start. INITIATING CUE: You are the Plant Place the BP209 RACS pump in service and secure the AP209 RACS Page 13 of 19 TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

'I:. INITIALIZE the simulator to any IC with the Main Generator ENSURE the 'A' & 'C' RACS pumps are in service and the 'B' RACS pump is in ENSURE the Common Offgas Train is in service and HV-2577 is ENSURE associated Schedule file open and ENSURE associated Events file Initial I ENSURE simulator is Event code:

Description:

I cwnra209 <= 0.5 /I AP209 RACS pump normalized pump speed Trips BP209 RACS pump after the AP209 RACS pump is stopped Event code:

Description:

Page 14 of 19

JOB PERFORMANCE SIMULATOR SETUP None I None Action Insert malfunction CW08B after 5 on event 1 Initial None Insert override 5A33_E_DI to Off AP209 START-REACTOR AUXILIARIES COOLING PUMP-PUMP Page 15 of 19

JOB PERFORMANCE SIMULATOR SETUP (OPTIONAL)

CW08B Trip of BP209 RACS pump. 5A33 E 01 AP209 RACS pump start pushbutton.

NONE OFF Page 16 of 19 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ED002 Rev # Date Description Validation Required?

01 7/23/07 Originally developed for ILOT NRC exam in 2005. This revision converts to HC LOR format, documents validation, and generates estimated completion time. Y 02 8/26/08 Updated reference procedure revisions.

Corrected previous typo error in procedure step A.2. No change in operator actions from previous revision.

No validation required.

N 03 9/9/09 Updated reference procedure revisions.

No change in operator actions from previous revision.

No validation required.

N 04 9/12/11 Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. Updated Reference procedure revision numbers only. No changes to operator actions. No validation required.

1\1 03 12/30/11 Updated reference procedure revisions.

No change in operator actions from previous revision.

No validation required.

1\1

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The RACS System is in service with the AP209 and CP209 RACS pumps running. 2. AP209 RACS pump is scheduled for an oil change. 3. The Reactor Building EO has been briefed and is stationed at the BP209 RACS pump. 4. The BP209 has NOT been isolated since the last time it was in service and is ready for a start. INITIATING CUE: You are the Plant Place the BP209 RACS pump in service and secure the AP209 RACS J RFORMANCE MEASUR STATION: Hope Creek SYSTEM: Main Steam Install Jumpers To Bypass MSIV Low Leve! Isolation Interlock TASK NUMBER: 2000010501/200059054 JPM NUMBER: 305H-JPM.AB001 REV#: 07 SAP BET: NOH05JPAB01 E ALTERNATE PATH: D APPLICABILITY: EO RO STA [] SRO []] DEVELOPED BY: Archie E.

DATE: 9/4/08 Instructor REVIEWED BY: DATE: 9-1:;'-08 J2I1l:L Operations Representative APPROVED BY: DATE: 3Jj-CflL--

Training Department


STATIOr..!:

Hope Creek JPM NUMBER: AB001 REV: 07 SYSTEM: Main Steam TASK NUMBER: 2000010501/200059054 TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock ALTERNATE PATH: KIA NUMBER: 239001 A2.03 IMPORTANCE FACTOR: 4.0 4.2 APPLICABILITY:

RO SRO EOD ROW STAD SROW EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0301, Rev. 6 TOOLS, EQUIPMENT AND PROCEDURES:

None ESTIMATED COMPLETION TIME: 0; Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes

...--.....--------.--------------------_l 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 13

'i 06*0303 NAf\'1E: OJ\. SYSTEM: Main Steam TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock TASK NUMBER: 2000010501/200059054 INITIAL CONDITIONS: The Reactor is at 32% power following a full core ATWS. The Main Turbine is tripped. The MSIVs are open. The Main Condenser is available. HC.OP-EO.zZ-0101A, ATWS -RPV Control, is being executed. HC.OP-EO.ZZ-0311, Bypassing Primary Containment Instrument Gas Interlocks, and HC.OP-EO.zZ-0319, Restoring Instrument Air in an Emergency, have been completed. There is no indication of fuel cladding failure or main steam line break. INITIATING CUE: Bypass the MSIV Low RPV Water Level Isolation Interlock lAW HC.OP-EO.zZ-0301.

Page 3 of 13

JPM: AB001 OPERATOR TRAINING PROGRAM NAME: Rev: 07 JOB PERFORMANCE MEASURE DATE: _______________

_ SYSTEM: Main Steam TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSA T evaluation)

.....,."..,.."..

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue. CUE ENTER START TIME AFTER ,>

-" ... OPERATOR REPEATS BACK INITIATING CUE: , START TIME: Operator obtains and locates procedure HC.OP-EO.ZZ-0301.

Operator obtains the correct procedure.

'-' I** " i , Operator reviews precautions and limitations.

Operator reviews precautions and limitations. ---------,------------, CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

";', .. t, Page 4 of 13 I I I I ---

JPM: AB001 OPERATOR TRAINING PROGRAM NAME: Rev: 07 JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Steam TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

4.0 EQUIPMENT

REQUIRED Operator obtains the following required equipment:

  • 4.1 EOP-301 Implementation Kit (OS Office EOP Drawer) Contents:

4 Banana Plug Jumpers 1 Flashlight EOP-301 Implementation Kit from NSS Office EOP drawer OR Key #9 from OS Office or key from OR break glass key holder in OSC for OSC 4.2 5.2.1 Key #9 for EOP Locker in OSC (obtain from OS office or break red key holder glass in OSC) AND EOP-301 Implementation Kit (EOP Locker in OSC). Contents:

4 Banana Plug Jumpers 1 Flashlight Operator determines beginning step of the procedure.

ENSURE that all prerequisites have been satisfied lAW Section 2.0 of this procedure.

EOP locker AND EOP-301 Implementation kit from the EOP Locker in OSC. Examiner Note: After operator has demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location.

Operator determines the correct beginning step to be 5.2. Operator ensures that all prerequisites have been satisfied. _J -CUE If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.

.... .. Page 5 of 13 I T" A-106-0303 JPM: AB001 OPERATOR TRAINING PROGRAM NAME: Rev: 07 JOB PERFORMANCE MEASURE DATE: SYSTEM: Main TASK: Install Jumpers To Bypass MSIV Low Level Isolation I I STEP NO. 5.2.2 ELEMENT At panel 10C609 Div. 1 (front) INSTALL a jumper in the red and black jacks labeled: B21H-K212A T1-M1 OP-EO.ZZ-301 (fourth column, first row) (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator installs jumper between the red and black jacks labeled 821 K212A T1-M1 HC.OP-EO.zZ-0301 (10C609) * #

  • EVAL stu COMMENTS (Required for UNSA T evaluation)

I CUE 5.2.3 The jumper has been installed as you have indicated.

At panel 10C609 Div 3 (front) INSTALL a jumper in the red and black jacks labeled: B21H-K212C T1-M1 OP-EO.ZZ-301 (fourth column, first row) Operator installs jumper between the red and black jacks labeled 821 K212C T1-M1 HC.OP-EO.zZ-0301 (10C609)

  • CUE The jumper has been installed as-you have indicated.

I --:

I 5.2.4 At panel10C611 Div. 2 (front) INSTALL a jumper in the red and black jacks labeled: B21 H-K212B T1-M1 OP-EO.ZZ-301 (fourth column, first row) Operator installs jumper between the red and black jacks labeled 821 K2128 T1-M1 HC.OP-EO.zZ-0301 (10C611).

  • CUE The jumper has been installed as you have indicated.
Page 6 of 13

Tl... .A-106-0303 JPM: AB001 OPERATOR TRAINING PROGRAM NAME: Rev: 07 JOB PERFORMANCE MEASURE DATE: __________

_ SYSTEM: Main TASK: Install Jumpers To Bypass MSIV Low Level Isolation STEP NO. 5.2.5 CUE ELEMENT At panel 1 OC611 Div. 4 (front) INSTALL a jumper in the red and black jacks labeled: B21H-K212D T1-M1 OP-EO.ZZ-301 (fourth column, first row) The jumper has been installed as you have indicated.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator installs jumper between the red and black jacks labeled 821 K212D T1-M1 HC.OP-EO.ZZ-0301 (1 OC611). * #

  • EVAL S/U COMMENTS (Required for UNSAT evaluation)

, 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 7 of 13


06-0303 JOB PERFORMANCE MEASURE OPER..d.TOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: AB001 TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock TASK NUMBER: 2000010501/200059054 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: UNSAT ,-----I_----'SAT L-I_---' Page 8 of 13 TQ-AA*1 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The Reactor is at 32% power following a full core ATWS. The Main Turbine is tripped. The MSIVs are open. The Main Condenser is available. HC.OP-EO.ZZ-0101A, ATWS -RPV Control, is being executed. HC.OP-EO.ZZ-0311, Bypassing Primary Containment Instrument Gas Interlocks, and HC.OP-EO.ZZ-0319, Restoring Instrument Air in an Emergency, have been completed. There is no indication of fuel cladding failure or main steam line break. INITIATING CUE: Bypass the MSIV Low RPV Water Level Isolation Interlock lAW HC.OP-EO.zZ-0301.

Page 9 of 13 TQ-AA-1 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

,',':;"

',:: "".'__ .... ,:':. , " "-' . ,---,---><@';/J4:-

-

INITIALIZE the simulator to 97 power, Lock the reactor Mode Switch in Take actions of HC.OP-AB.ZZ-0001 Attachment Initiate Trip the Main Ensure the MSIVs are Ensure the Main Condenser is Place the simulator into COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Description EVENT ACTION: COMMAND: PURPOSE: 2 Page 10 of 13

JOB PERFORMANCE SIMULATOR SETUP Initial Left Side RP07 Half Core ATWS -Right Side EG11 Main Generator Trip

JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AB001 Rev # Date 9/4/2008 Description This revision converts to HC LOR format, documents validation, and generates estimated completion time. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted. Revised power level from 48% to 32% based on IC and current core model. Added Remote functions for EOP 311 and 319 implementation.

Updated Reference procedure revision number. No change to operator actions. I Validation Required?

Y I I TQ-AAg"106-0303 JOB PERFORIv1ANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: AB001 REV#: TASK: Install Jumpers To Bypass MSIV Low Level Isolation 1. Task description and number, JPM description and number are ci 2. Knowledge and Abilities (KIA) references are If p.,. 3. Performance location specified (in-plant, control room, or a L,7 4. Initial setup conditions are a 77 5. Initiating and terminating cues are properly 6. Task standards identified and verified by SME fl...¥: 7. Critical steps meet the specified criteria and are identified with an asterisk Q (--J-8. Verify the JPM steps rnatch the rnost current revision of the f1 4% 9. Pilot test the f1l..-v a. verify cues both verbal and visual are free of b. ensure performance time is accurate VALIDATED BY: Qualification Level Required:

RO Eel Q.o '1-II-D{?

Name Qual Signature Date k' ;M;vI!LJ)!l

.0(;; Name Qual Signature Date JOB PERFORMANCE STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: ALTERNATE PATH: APPLICABILITY:

r-EO Hope Safety Auxiliaries Cooling Respond To A SACS 400780401 30SH-JPM.EG003 REV*#: 17 NOH05JPEG03E D RO STA SRO[KJ D DEVELOPED BY: Archie E. Faulkner DATE: 12/30/11 Instructor REVIEWED' BY: -----/

DATE: 1/& c/;z. perations APPROVED BY: DATE:1/1 Training Department


I STATION: Hope Creek JPM NUMBER: EG003 REV: 17 SYSTEM: Safety Auxiliaries Cooling Water TASK NUMBER: 400780401 TASK: Respond To A SACS Malfunction ALTERNATE PATH: KIA NUMBER: 400000 A2.01 IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY:

EO D RO [K] STA D SRO [K] RO SRO EVALUATION SETTING/METHOD:

Reactor Building/Simulate HC.OP-SO.EG-0001, Rev 45 HC.OP-AB.COOL-0002, Rev 7 Annotated copy of HC.OP-SO.EG-0001, valve TOOLS, EQUIPMENT AND PROCEDURES:

locking devices. ESTIMATED COMPLETION TIME: 20 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 UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 12

NAME: __________________

__ DATE: __________________

__ SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction TASK NUMBER: 400780401 INITIAL CONDITIONS: SACS Loop B has been declared inoperable. HC.OP-AB.COOL-0002, SafetylTurbine Auxiliaries Cooling System, is Components are being realigned lAW Section 5.12 of HC.OP-SO.EG-0001. The 'D! EDG Coolers AND Room Coolers have been cross tied to the 'A' SACS loop lAW HC.OP-SO.EG-0001 Attachment 3 Part A. INITIATING Cross Tie the 'D' FRVS Recirculation Unit to the 'A' SACS Loop in the sequence in HC.OP-SO.EG-0001 Attachment 3 Part WCM update and tagging will be performed by another Page 3 of 12


JPM: EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 JOB PERFORMANCE MEASURE DATE: SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction

(*Denotes a Critical Step) COMMENTS*STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #STANDARD Stu evaluation CUE PROVIDE the operator the Operator repeats back initiating cue. cue. CUE ENTER START TIME OPERATOR REPEATS INITIATING CUE: START TIME: Operator locates the proper Operator obtains/locates procedure Operator reviews precautions Operator reviews precautions and limitations.

Examiner Note: The sequence Precautions and If excessive time is taken reviewing CUE portion of the following steps is to close the 1-EG-V689 AND inform operator that all are BEFORE opening the 1-EG-V703 OR 1-EG-V702.

Operator unlocks 1-EG-V689.

FRVS CLG COIL DVH-213 LP B SUP ATT.3 Examiner Note: Support operator's requests for Verifier.

1-EG-V689 LOCKED CLOSED Page 4 of 12 10


TO-. .A-1 06-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction STEP NO. CUE CUE CUE ATT.3 11 CUE ELEMENT The lock has been removed from the valve indicated.

The valve indicated has been rotated in the direction stated and has come to hard stop. The lock is installed on the valve indicated.

FRVS CLG COIL DVH-213 LP B RTN 1-EG-V692 LOCKED CLOSED The lock has been removed from the valve indicated.

N/A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator closes 1-EG-V689.

N/A Operator reinstalls a locking device on valve 1-EG-V689.

N/A Operator unlocks 1-EG-V692.

Examiner Note: Support operator's requests for Verifier.

N/A * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

Page 5 of 12



12 TQ-.,....,..\-106-0303 EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 JOB PERFORMANCE MEASURE DATE: SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction

(*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step) EVAL ELEMENT (Required for UNSAT NO. #STANDARD S/U evaluatio Operator closes 1-EG-V692.

  • # The valve indicated has been N/A CUE rotated in the direction stated has come to hard Operator reinstalls a locking device on valve 1-EG-V692.

The lock is installed on the valve N/A CUE indicated.

Operator unlocks 1-EG-V703.

FRVS CLG COIL DVH-213 LP A SUP ATT.3 Examiner Note: Support operator's requests for Verifier.

1-EG-V703 LOCKED OPEN The lock has been removed from N/A CUE the valve indicated.

Operator opens 1-EG-V703.

  • # Page 6 of 12


TQ-n.r\-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 JOB PERFORMANCE MEASURE DATE: SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction STEP NO. CUE CUE ATT.3 13 CUE CUE ELEMENT The valve indicated has been rotated in the direction stated and has come to hard stop. The lock is installed on the valve indicated.

FRVS CLG COIL DVH-213 LP A RET 1-EG-V702 LOCKED OPEN The lock has been removed from the valve indicated.

The valve indicated has been rotated in the direction stated and has come to hard stop. N/A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator reinstalls a locking device on valve 1-EG-V703.

N/A Operator unlocks 1-EG-V702.

Examiner Note: Support operator's requests for Verifier.

N/A Operator opens 1-EG-V702.

N/A * # EVAL S/U COMMENTS (Required for UNSAT evaluation Page 7 of 12


TQ-,...r\-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 17 JOB PERFORMANCE MEASURE DATE: SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation Operator reinstalls a locking device on valve 1-EG-V702.

CUE The lock is installed on the valve indicated.

N/A 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 8 of 12


JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: EG003 TASK: Respond To A SACS Malfunction TASK NUMBER: 400780401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

UNSAT RESULT: SAT Page 9 of 12

JOB PERFORMANCE INITIAL CONDITIONS: SACS Loop B has been declared inoperable. HC.OP-AB.COOL-0002, SafetylTurbine Auxiliaries Cooling System, is being implemented. Components are being realigned lAW Section 5.12 of HC.OP-SO.EG-0001. The '0' EOG Coolers ANO Room Coolers have been cross tied to the 'A' SACS loop lAW HC.OP-SO.EG-0001 Attachment 3 Part A. INITIATING CUE: Cross Tie the '0' FRVS Recirculation Unit to the 'A' SACS Loop in the sequence presented HC.OP-SO.EG-0001 Attachment 3 Part WCM update and tagging will be performed by another Page 10 of 12 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: EG003 Rev # Date Description Validation Required?

13 8/28/2008 Revised to new JPM format. Revalidated JPM time. Updated reference procedure revision number. Operator actions did not change. y 14 12/1/2008 Updated Procedure revision numbers. No effect on JPM. N 15 9;9109 Updated Procedure revision numbers. No change to operator actions. No validation required.

N 16 4/27/10 Updated Procedure revision numbers. No change to operator actions. No validation required.

N 17 5/9;11 Updated Procedure revision numbers. No change to operator actions. No validation required.

N TASK JPM SAP BET: ALTERNATE PATH: APPLICABI LlTY: EO r:_._1 DEVELOPED BY: JOB PERFORMANCE MEASURE Hope Creek Main Steam Respond to a Failed Open Safety Relief Valve 4000210401 305H-JPM.AB003 REV #: 02 NOH05JPAB03E D RO STA SRO []] Archie E. Faulkner DATE: 5/7/2009 Instructor ,I '.REVIEWED BY: DATE: 7f?lAYf/ I/Operations Representative I APPROVED BY: 1t<10k DATE: 1 Jl11/D1 Training Department

Hope Creek JPM NUMBER: AB00302 REV: 02 SYSTEM: Main Steam TASK NUMBER: 4000210401 TASK: Respond to a Failed Open Safety Relief Valve ALTERNATE PATH: D KIA NUMBER: 239002 A2.03 IMPORTANCE FACTOR: 4.1 APPLICABILITY:

RO SRO EO D RO []] STA D SRO []] EVALUATION SETIING/METHOD:

PlanUSimulate

REFERENCES:

HC.OP-AB.RPV-0006 Rev. 3 TOOLS, EQUIPMENT AND PROCEDURES:

HC.OP-AB.RPV-0006 ESTIMATED COMPLETION TIME: 13 TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A J PM 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 12 4.2 TQ-AA-106-0303 NAME: __________________

_ DATE: __________________

_ SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve TASK NUMBER: 4000210401 INITIAL CONDITIONS: The Reactor is shutdown due to the "D" SRV being electrically held open with both Logic Train Band D solenoids. HC.OP-AB.RPV-0006 Safety Relief Valve, is being executed. Attempts to close the SRV from the Main Control Room have u ns u ccessfu INITIATING CUE: Use the fuse pullers provided (simulated) to pull the fuses for the "D" SRV lAW HC.OP-AB.

RPV-0006.

Page 3 of 12



T .A-106-030 JPM: AB00302 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve (e Denotes a Critical Element COMMENTS*STEP (*Denotes a Critical Step) EVAL of a Critical Step) (Required for UNSAT NO. STANDARD ., S/U ELEMENT 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 the correct procedure.

Operator reviews Immediate Operator Actions, Retainment Overrides, applicable Cautions and Notes. Operator obtains procedure HC.OP-AB.RPV-0006 Operator reviews Immediate Operator Actions, Retainment Overrides, applicable Cautions and Notes. A.3 Operator determines beginning step of the procedure.

IF the SRV solenoid cannot be energized from the Control Room, THEN REMOVE SRV fuses associated with the energized logic lAW Attachment

2. Operator determines correct beginning step to be A.3 Operator determines this step applies and reviews Attachment
2. EXAMINER NOTE: The sequence for pulling the fuses is not critical.

Placing the fuses in a storage bag is not critical.

Page 4 of 12 T .A-106-030 JPM: AB00302 Rev: 02 SYSTEM: Main Steam OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Respond to a Failed Open Safety Relief Valve NAME: DATE: (e Denotes a Critical Element COMMENTS STEP *(*Denotes a Critical Step) EVAL of a Critical Step) (Required for UNSAT NO. STANDARD

  • S/U ELEMENT evaluati Y N STAR Att 2 At panel 10C628 (ADS DIV 2) the *Operator simulates pulling fuse operator pulls fuse 821 C F3D F9. Logic 821 C F3D F9 at panel 10C628 (ADS 8 DIV 2). CUE The fuse that you have indicated is N/A pulled. Att 2 At panel 10C628 (ADS DIV 2) the Operator simulates pulling fuse Logic operator pulls fuse 821 C F4D F10. 821 C F4D F10 at panel 10C628 (ADS 8 DIV 2). CUE The fuse that you have indicated is pulled. N/A Att 2 At panel10C631 (ADS DIV 4) the Operator simulates pulling fuse Logic operator pulls fuse 821 C F7D F9. 821C F7D F9 at panel10C631 (ADS o DIV 4). Y N STAR* Y N STAR* The fuse that you have indicated is CUE N/A pulled. Y N STAR At panel10C631 (ADS DIV 4) the Att 2 Operator simulates pulling operator pulls fuse 821 C F8D B21C F8D F10 at panel10C631 (ADS DIV 4). Logic o The fuse that you have indicated is CUE N/A pulled. Page 5 of 12


1 .A-106-030 JPM: AB00302 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve COMMENTS (. Denotes a Critical Element *STEP (*Denotes a Critical Step) EVAL (Required for UNSAT of a Critical Step) NO. STANDARD

  • S/U evaluati ELEMENT CUE WHEN operator informs you the task OR the JPM has been terminated other THEN RECORD the STOP 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


OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: AB00302 TASK: Respond to a Failed Open Safety Relief Valve TASK NUMBER: 4000210401 QUESTION:

RESPONSE:

RESULT: UNSAT SAT L-I_----...l QUESTION:

..-----------------------------------------------_

..RESPONSE:

UNSAT RESULT: SAT Page 7 of 12 TQ*AA*106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: AB00302 REV#: 02 Initial ! Initial Description

! ENSURE a copy of HC.OP-AB.RPV-0006 is available.

EVENT ACTION:

Page 8 of 12

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: AB00302 REV#: 02 Page 9 of 12

JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AB00302 I Rev # : Date 02 JPM Template, Revised to add both SRV 0 with operators from A Shift. Avg time 13 y Page 10 of 12

JOB PERFORMANCE INITIAL CONDITIONS: The Reactor is shutdown due to the "D" SRV being electrically held open with both Logic Train Band D solenoids. HC.OP-AB.RPV-0006 Safety Relief Valve, is being executed. Attempts to close the SRV from the Main Control Room have been unsuccessful.

Use the fuse pullers provided (simulated) to pull the fuses for the "D" SRV lAW HC.OP* AB.RPV-0006.

Page 12 of 12 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout TASK NUMBER: 4000020404 JPM NUMBER: 305H-JPM.PK001 REV #: 02 SAP BET: NOH05JPPK01 E ALTERNATE PATH: D APPLICABILITY:

EO [KJ RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor DATE: If;;. o/;.:z APPROVED BY: DATE: OftfUfJJ-;//6//< Training Department REVIEWED BY: 1-<fl,I i eratio


STATION: Hope Creek JPM NUMBER: PK001 REV: 02 SYSTEM: DC Electrical Distribution TASK NUMBER: 4000020404 TASK: Respond To A Station Blackout ALTERNATE PATH: KIA NUMBER: 295003.AA 1.04 IMPORTANCE FACTOR: 3.6 3.7 APPLICABILITY:

EO []] RO []] STA D SRO []] RO SRO EVALUATION SETTING/METHOD:

Plant/Perform

REFERENCES:

HC.OP-AB.ZZ-0135 Rev 35 TOOLS, EQUIPMENT AND PROCEDURES:

HC.OP-AB.ZZ-0135 ESTIMATED COMPLETION TIME: 20 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


DATE: SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout TASK NUMBER: 4000020404 INITIAL CONDITIONS: The plant is in OPCON 3. A loss of all offsite and onsite AC power occurred 15 minutes ago. HC.OP-AB.zZ-0135, STATION BLACKOUT IILOSS OF OFFSITE POWERI/DIESEL GENERATOR MALFUNCTION has been completed through step 4.5.4. INITIATING IMPLEMENT Attachment 3, Radwaste Building Actions of Page 3 of 14


JPM: PK001 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step)ELEMENT EVAL (Required for UNSAT NO. #STANDARD S/U evaluati CUE PROVIDE the operator the initiating Operator repeats back initiating cue. cue. CUE ENTER START TIME Operator repeats back the Cue: I START TIME: Operator obtains the correct Operator obtains Operator determines beginning Operator determines correct of the step to be Operator locates Attachment Page 4 of 14 JPM: PK001 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM: TASK: DC Electrical Distribution Respond To A Station Blackout STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluati Attach OPEN the circuit breakers in the 3 following tables when plant has Step entered an S80. 1. CLOSE the circuit breakers in the following tables when restoring offsite power. All are ARC Flash Category O. 1B0318 0 Circuit 12 Examiner Note: A map showing panel locations is provided on the bottom of Attachment

3. Operator locates panel 1 80318 in Room 3449. Operator simulates opening breaker 12 on 80318. I
  • CUE The breaker you have indicated is open. o Circuit 19 N/A Operator simulates opening breaker 19 on 80318.
  • Page 5 of 14


JPM: PK001 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP NO. ELEMENT CUE The breaker you have indicated is open. o Circuit 24 CUE The breaker you have indicated is open. o Circuit 27 CUE The breaker you have indicated is open. 1AD318 o Circuit 12 N/A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator simulates opening breaker 24 on 80318. N/A Operator simulates opening breaker 27 on 80318. N/A Operator locates panel 1 A0318 in Room 3449. Operator simulates opening breaker 12 on A0318. * #

  • EVAL S/U COMMENTS (Required for UNSAT evaluation Page 6 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

_ SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout *

  • COMMENTS (Required for UNSAT (*Denotes a Critical Step) STEP (#Denotes a Sequential Step) ELEMENT NO. STANDARD CUE The breaker you have is N/A Operator simulates opening breaker 27 on A0318. o Circuit 27 CUE The breaker you have is N/A Operator simulates opening breaker 28 on A0318. o Circuit 28 CUE The breaker you have is N/A Operator locates panel 100318 in Room 3432. 1DD318 Operator simulates opening breaker 11 on 00318. o Circuit 11 Page 7 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP NO. ELEMENT CUE The breaker you have indicated is open. o Circuit 12 CUE The breaker you have indicated is open. o Circuit 14 CUE The breaker you have indicated is open. o Circuit 27 CUE The breaker you have indicated is open. N/A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator simulates opening breaker 12 on 00318. N/A Operator simulates opening breaker 14 on 00318. N/A Operator simulates opening breaker 27 on 00318. N/A * # EVAL S/U COMMENTS (Required for UNSAT evaluatio Page 8 of 14


JPM: PK001 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout (*Denotes a Critical Step) COMMENTS*STEP (#Denotes a Sequential Step)ELEMENT EVAL (Required for UNSAT NO. #STANDARD S/U evaluatio Operator locates panel 1 CD318 Room 3432. 1CD318 Operator simulates opening breaker 11

  • on CD318. o Circuit 11 CUE The breaker you have is N/A Operator simulates opening breaker 12 Circuit on CUE The breaker you have is N/A Operator simulates opening breaker 14 on CD318. o Circuit 14 The breaker you have is CUE N/A Page 9 of 14 JPM: PK001 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP NO. o Circuit 27 ELEMENT CUE The breaker you have indicated is open. 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: (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator simulates opening breaker 27 on CD318, N/A N/A * #

  • EVAL stu COMMENTS (Required for UNSAT evaluation Page 10 of 14

JOB PERFORMANCE MEASURE OPERATOR TRAINING EVALUATOR FOLLOWUP QUESTION NAME: DATE: JPM Number: PK001 TASK: Respond To A Station Blackout TASK NUMBER: 4000020404 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

UNSAT RESULT: SAT Page 11 of 14

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The plant is in OPCON 3. A loss of all offsite and onsite AC power occurred 15 minutes ago. HC.OP-AB.ZZ-0135, STATION BLACKOUT IILOSS OF OFFSITE POWERI/OIESEL GENERATOR MALFUNCTION has been completed through step 4.5.4. INITIATING IMPLEMENT Attachment 3, Radwaste Building Actions of Page 12 of 14 TQ*AA*106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: PK001 Rev # I Date Description 00 10/13/09 I Converted NRC 2007JPM 009 to new JPM format. This revision includes latest revision to HC.OP-AB.ZZ-0135.

Validated with 2 . ODerators from "A" Shift. Estimated ComDletion time 20 minutes. 01 5/12/11 Updated Reference procedure revision numbers only. No N chanqes to oDerator actions. No validation required.

02 Updated Reference procedure revision numbers onlv. No N chanqes to operator 1/14/12 PSEG Internal Use H C.OP-AB.ZZ-O ATTACHMENT RAD WASTE BUILDING ACTIONS DC LOAD OPEN the circuit breakers in the following tables when plant has entered an S80. CLOSE the circuit breakers in the following tables when restoring offsite power. All are ARC Flash Category O. LOCATION PANEL # CIRCUIT # LOAD (840 W) OPEN CLOSE 124' Radwaste 1BD318

  • 12 19 STA SERV XFMR A PROT 1 BC654 TACS SOLV 1AC658A RM 3449 24 27 PNL,BUS PROT 1 DC654D STA SERV XFMR PROT PNL 1 EC654A LOCATION PANEL # CIRCUIT # LOAD (580 W) OPEN CLOSE 124' 12 STA SRV XFMR A PROT PNL 1 BC654 Radwaste 1AD318
  • 27 STA SERV C PROT RLY 1 EC654B RM 3449 28 PNL,BUS PROT 1 DC654C RLY LOCATION PANEL # CIRCUIT # LOAD (840 W) OPEN CLOSE 124' Radwaste RM 3432 lOD318
  • 11 12 14 27 PNL,BUS PROT 1 DC654B BtU STA SERV XFMR PROT PNL 1CC654B PROCESS INST CAB 10C613 STA SERV XFMR PROT PNL 1 FC654A LOCATION PANEL # CIRCUIT # LOAD (570 W) OPEN CLOSE 124' Radwaste RM 3432 1CD318
  • 11 12 14 27 PNL,BUS PROT 1 DC654A XFMR B PROTECT REC PNL 1 CC654A CAB,FDWTR

& RECIRC INST 10C612 STA SERV XFMR D PNL 1 FC654B ] *"0 / ;:s * ;. ....-=: r----r r --I., . loc%3 fil RFP Governor Panels Hope Creek Page 45 of Rev 36 SCENARIO TITLE: NRC SCENARIO 4 SCENARIO NUMBER: ESG-NRC-S4 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION:

60-75 minutes REVISION NUMBER: 04 PROGRAM: LO.REQUAL INITIAL LICENSE OTHER'------' REVISION

SUMMARY

1. Updated PRA checklist.
2. Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. 3. Deleted RR Pump Trip per Chief Examiner Outline review. 4. Changed to Low Power Scenario per Chief Examiner Outline review. 5. Added Rod Drift Out per Chief Examiner Outline review. 6. Changed IC power level to 3% 7. Added setup guidance for markup of HC.OP-SO.EA-0001
8. Revised Ramp rate for ET-16 to same as ET-8 per validation crew request. PREPARED BY: Archie E. Faulkner 1/14/12 Instructor DATE APPROVED BY: }/i7LORT Group Lead or Designee DATE ( "l) I/lrl..z APPROVED BY:

i-,<p..'.eivv

/L fons Supervisor or Designee DATE Enabling Objectives 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 " *.") Raise reactor power with control rods Control rod 26-03 drifts out (TS SRO) Swap SSW Pumps SSW Pump Malfunction (TS SRO) Single Reactor Recirc Pump Runaway Fuel Failure with Scram Torus Leak I Emergency Depressurization RHR HX Inlet Valve F047S fails closed The scenario starts with the plant at approximately 3% power at rated pressure.

The crew will withdraw Control Rods to 8% power in preparation to place the reactor Mode Switch to Run. During the rod withdrawal, rod 26-03 drifts out. This results in an Abnormal Procedure and Tech Spec entry. The crew will insert the rod with RMCS or SRI Test Switches.

When the rod reaches full-in, the malfunction will be removed. After TS have been addressed, SSW Pumps will be swapped for planned maintenance.

After pump swap, "An SSW pump will malfunction requiring entering Tech Spec LCO. After Tech Specs have been addressed, the'S' Reactor Recirculation pump will runaway to it's upper mechanical stops. After AS-RPV-0001/003 actions are taken and Tech Specs have been addressed, US" 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.

When S Loop of RHR is placed in Suppression Pool Cooling, SC-HV-F047S will fail to open, forcing the crew to swap to the A RHR Loop for containment cooling. The scenario ends when the reactor is depressurized by the SRVs, reactor level stabilized between RPV Level 2 and 8 and Suppression Pool Cooling in service on the A RHR Loop. ESG-NRC-S4 Page 2 of Rev.: 04 INITIALIZE the simulator to 3% power, MOL. INITIALIZE the simulator to 3% power IIC, BOL. Pull step 409 INSERT control rods through step 409. ENSURE 'A' EHC pump is in service. crr 'B' EHC pump as follows: 1. INSERT Malfunction TC07B 2. PLACE 'B' EHC pump in MAN INITIAL IO.zZ-0003 Section 5.3 up to and including step INITIAL HC.OP-SO.EA-0001 for pump At a rio Reference section and CLEAN the bolded EOPs, ABs and SOPs listed. (80091396 ENSURE Data Collection is trending the following parameters as a

  • W/R Reactor Water Level
  • W/R RPV Pressure
  • Suppression Pool level
  • Suppression Pool COMPLETE "Simulator Ready-for-Training/Examination i ENSURE associated Schedule file open and running. ENSURE associated Events file open. ESG-NRC-S4 Page 3 of 28 Rev.: 04 code: 10

Description:

11 Event code: 12 I

Description:

Event 0 13 14 i

Description:

Event code: 15 I

Description:

Event code: 16 I

Description:

Event code: 17 I

Description:

18 Triggers Torus leak when MSIVs and MSL Drains isolated crqnmi <= 2 Reactor Power <2% Illnserts Fuel Cladding failure if Crew scrams during Recirc Runaway msvf022(1)

<= 0.0 I msvf028(1)

<= 0.0 Detects 'A' MSL isolation msvf022(2)

<= 0.0 I msvf028(2)

<= 0.0 Detects 'B' MSL isolation msvf022(3)

<= 0.0 I msvf028(3)

<= 0.0 Detects 'C' MSL isolation msvf022(4)

<= 0.0 I msvf028(4)

<= 0.0 Detects 'D' MSL isolation msvfdrn1(1)

<= 0.0 I msvfdrn1(2)

<= 0.0 F016 or F019 shut /I Detects MSL drain isolation crqnmi <= 2 Reactor Power <2% II Ramps MSL rad to 3xNFPB after reactor scrammed.**

et_array(11)

>= 1.0 & et_array(15)

>= 1.0 Removes high radiation from 'A' MSL

  • et_array(12)

>= 1.0 & et_array(15)

>= 1.0

  • Removes high radiation from 'B' MSL rray(13) >= 1.0 & eCarray(15}

>= 1.0 oves high radiation from 'C' MSL eCarray(14}

>= 1.0 & et_array(15)

>= 1.0 Removes high radiation from 'D' MSL Event code: I Pclsp <= 119 21 I

Description:

Indicated SP levell/Removes torus leak at 25" to prevent reaching Simulator Limits 7 et_array(11)

>= 1.0 & et_array(12)

>= 1.0 & eCarray(13)

>= 1.0 & et_array(14)

>= 1.0 & et_array(15)

>= 1.0 ** Value to be 12 mrlhr above current 3xNFPB Hi-Hi Alarm setpoint for I.C. ESG-NRC-S4 Page 4 of 28 Rev.: 04

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./;., Initial @Time Event Action Description None None Insert malfunction TC07B ERC pump B trip None None Insert malfunction CD022603 Control Rod 26-03 drift out None None Insert malfunction CW23A to 50.00000 on Service water strainer A fouling event 1 None None Insert malfunction RR08B on event 2 Recirc system B speed controller fails high None None Insert malfunction RR26B2 to 20.00000 in Recirc pump BP201 elevated (added to calc) 300 on event 4 Pump Vib None None Insert malfunction CW05A on event 6 Service water pump AP502 trip None None Insert malfunction PC06 after 180 to Suppression pool break 50.00000 on event 7 None None Insert malfunction RH03B on event 7 RHR RX inlet valve F047B fails closed None None Insert malfunction RH09 A after 210 on RHR pump AP202 room flood (Rm 4113) event 7 None None Insert malfunction CROI to 30.00000 in Fuel cladding leak 300 on event 8 None None Insert malfunction RM9509 to 118.00000 9RX509, MSL 'A' -Main Steam Line Chan A in 300 on event 8 None None Insert malfunction RM9510 to 127.00000 9RX510, MSL 'B' -Main Steam Line Chan B in 300 on event 8 None None Insert malfunction RM9511 to 119.00000 9RX511, MSL 'C' -Main Steam Line Chan C in 300 on event 8 None None Insert malfunction RM9512 to 122.00000 9RX512, MSL 'D' -Main Steam Line Chan D in 300 on event 8 None None Insert malfunction CRO 1 after 1 to Fuel cladding leak 50.00000 on event 10 None None Insert malfunction RM9509 after 1 to 9RX509, MSL 'A' -Main Steam Line Chan A 118.00000 in 300 on event 16 None None Insert malfunction RM9 510 after 1 to 9RX510, MSL 'B' -Main Steam Line Chan B 127.00000 in 300 on event 16 None None Insert malfunction RM9511 after 1 to 9RX511, MSL 'Co -Main Steam Line Chan C 119.00000 in 300 on event 16 None None Insert malfunction RM9512 after 1 to 9RX512, MSL 'D' -Main Steam Line Chan D 122.00000 in 300 on event 16 None None Insert malfunction RM9509 to 19.00000 in 9RX509, MSL 'A' -Main Steam Line Chan A 60 on event 17 None None Insert malfunction RM9510 to 19.00000 in 9RX510, MSL 'B' -Main Steam Line Chan B 60 on event 18 None None Insert malfunction RM9511 to 15.00000 in 9RX51 1, MSL 'Co -Main Steam Line Chan C 60 on event 19 None None Insert malfunction RM9512 to 18.00000 in 9RX512, MSL 'D' -Main Steam Line Chan D 60 on event 20 None None Insert malfunction PC06 after 1 to Suppression pool break 50.00000 on event 21 delete in I -

None None None None None None None None Insert malfunction CD032603 on event 26 Insert malfunction CD052603 on event 27 Insert malfunction AN-C6C3 after 60 on event 27 Insert malfunction CD062603 on event 28 Control Rod 26-03 stuck Control Rod 26-03 accumulator trouble CRYWOLF ANN C6C3 CRD HYDR UNIT TEMP HI Control Rod 26-03 SCRAM ,@Time I Event Initial Action Description

.. Initial @Time I Event Action Description None None Insert override 5A8 E LO to Off HV-23568 OPEN--LOOP B-YARD DUMP VALVE (LO) None None Insert override 5A8 F LO to On HV-23568 CLOSE--LOOP B-YARD DUMP VALVE (LO) None None Insert override 5A3 E LO to Off HV-2256A OPEN-LOOP A-YARD DUMP VALVE (LO) None None Insert override 5A3 F LO to On HV-2256A CLOSE-LOOP A-YARD DUMP VALVE (LO) ESG-NRC-S4 Page 6 of 28 Rev.: 04

'. \!.,;;*...*....Raise Reactor Power with

watch. NOTE: LPRM downscale alarms can be expected.

As RE, inform crew alarms are expected for this. rod pattern. NOTE: Operator may single notch withdraw the rods, as necessary, in which case the CONTINUOUS WITHDRAW PB is NOT used. RO withdraws Control Rods in accordance with 0001 and CRS directions.

=:> Selected rod PB comes ON (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). At the ROD SELECT MODULE, simultaneously press and hold both the WITHDRAW PB AND the CONTINUOUS WITHDRAW PB and observe the following:

=:> The INSERT (white) light comes ON momentarily. The WITHDRAW (white) light comes ON and the CONTINUOUS WITHDRAW (white) light comes ON. CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod movement.

ESG-NRC-S4 Page 7 of Rev.: 04 Prior to reaching the desired control rod position, simultaneously release both the WITHDRAW PB and the CONTINUOUS WITHDRAW PB and OBSERVE the following: The WITHDRAW (white) light goes OUT. The SETTLE (white) light comes ON for;:: 6 seconds, then goes out. CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod has settled to the desired position. At position 48 the applicable Full Core Display FULL OUT (red) light comes on. Perform a control rod coupling integrity check lAW ST.BF-0001. Perform the following while giving the selected Control Rod a continuous withdraw signal: => Observe the following as indication of the Control Rod being coupled: 1. ROD OVERTRA VEL alarm does NOT annunciate. Red Full Out light illuminates on the Full Core Display. RPIS indicates the Control Rod is full out (48). ESG-NRC-S4 Page 8 of Rev.: 04

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.t<? i::;":.' '0.: _,,' :'h' '. :--, .C " "": .(t :.j; h Rod Drift: Will occur after rod 26-03 is selected and withdrawn.

Pre-Inserted (Control Rod 03 Drifts Out). lE asked, THEN as Reactor Engineer, provide guidance to CRS to continuously insert rod 26-03 to 00 if possible.

.Proper response of Nuclear Instrumentation withdrawing the Control Indicates the completion of movement on the Pull Crew recognizes 26-03 rod => OHA C6-E3 "ROD => Amber DRIFT light for on Full Core => RWM Drifting Rod "DR => CRIDS C078 "ROD => Slight rise in reactor => Various rod indications CRS rnay refer toCRS implements AB.IC-0001:

AB.RPV-0001 but noCondition C actions are applicable. I F a Rod Drift has THEN REFER to Digital Point C078 of RO implements

=> Cause 4 "Drift RO applies a control rod insert signal the direction of the Engineer AND RO releases insert signal. IF the control rod continues drift out or does not to the insert signal ESG-NRC-S4 Page 9 of Rev.: 04 IF directed to place both SRI Test Switches for HCU 26-03 to TEST, THEN TRIGGER ET-28. WHEN dispatched to THEN REPORT the appears => PLACE both SRI test switches (local) to the TEST position to initiate a single control rod scram. => PLACE both SRI test switches to NORM position.

=> => IF the control rod attempts to drift outward again, THEN INSERT to position 00 AND:

  • A. CLOSE BF-V101
  • B. CLOSE BF-V102 => IF the control rod continues to drift out following isolation (e.g. problem is internal to the mechanism)

THEN OPEN BF-V102 and OPEN BF-V101 (reestablishes cooling water flow).

  • Crew dispatches RBEO to 26-03 HCU. ESG-NRC-S4 Page 10 of 28 Rev.: 04 IE directed to electrically AND hydraulically dis-arm 26-03 lAW SO.BF-0002, THEN PERFORM the following: DELETE malfunction CD022603 (drifting rod) and allow 26-03 to settle back to 00. TRIGGER ET-26 (stuck rod) TRIGGER ET-27 (accum trouble) IF isolating Scram pilot Air BF-V116 (as in Isolating for Maintenance section), THEN TRIGGER ET-28. AFTER OHA C6-C3 (CRD TEMP HI) is received, THEN DELETE Malfunction AN-C6C3 REPORT 26-03 is hydraulically dis-armed with cooling water restored.

CRD Hi Temp alarm was 26-03 and is now clear. IF directed only to electrically dis-armed 26-03 lAW SO.BF-0002, THEN TRIGGER ET-26 (stuck rod). Swap Service Water Pumps: After the Crew assumes the watch. CRS recognize the following Tech Spec actions apply: Control Rod Operability 3.1.3.1 action b CRS directs disarming the 26-03 directional control valves within one hour. RO resets the Rod Drift alarm lAW HC.OP-AR.ZZ-0020. CRS directs removal of "C" SSW from service using SO.EA-0001. PO places "A" SSW in service using HC.OP-SO.EA-0001 section 5.6.3.

  • Page 11 of Rev.: 04 As Yard operator, report field actions are complete for starting "An SSW pump. SSW Pump "A" Malfunction:

At the discretion of the lead Examiner, TRIGGER ET-1 (Service water pump A marsh grass intrusion to 50%). WHEN requested as Yard Operator, REPORT "An SSW pump strainer is not rotating and the screen is covered with grass. The breaker for the strainer is tripped and will not reset. the crew does not remove the "A" SSW pump from service, THEN TRIGGER ET-6 to trip the pump. PO removes "C" SSW from service using 0001 section 5.6.5. Crew recognizes "A" SSW strainer Hi DP to the strainer by: => A1-B1 SSWS INTAKE A TROUBLE => D3857 SSW STRAINER A DIFF HI HI STRAINER PRESSURE DIP => D5507 SSW STRAINER A DRIVE OPF CRS implements AB.COOL-0001

=> Condition A Condition 0 Crew removes "A" SSW pump from service AB.ZZ-0001 Att Crew places "C" SSW pump in service AB.ZZ-0001 Att CRS recognize the following Tech Spec applies: => Station Service Water 3.7.1.2 Action a Crew contacts maintenance.

30 day LCO ESG-NRC-S4 Page 12 of Rev.: 04

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....;..... ' "8" Reactor Recirc Pump runaway: TRIGGER ET-2, five minutes after Tech Specs have been addressed OR at the discretion of the Lead Examiner.

SUPPORT requests for local operation of 'B' Recirc MG scoop tube using Remote Function RR10. !E called as RE to determine maximum thermal power reached, THEN REPORT thermal power peaked at 5.2% (200 MWth). Crew recognizes "B" Reactor Recirculation pump runaway by: => Reactor power increases

=> C3-B1 SRM PERIOD => CRIDS D2900 "RECIRC MG B SPEED CONTROL SIG FAIL" => CRIDS D2931 "RECIRC MG B DRIVE TUBE LOCK TRBL" => SIC-R621 B SPEED DEM"ID and SPEED Upscale => 10C650C Recirc and Jet pump indications RO performs the following:

=> Presses SCOOP TUBE TRIP for "B" Recirc Pump Reduces "A" Recirc Pump speed to red uce power to pre-transient value CRS implements AB.RPV-0001:

=> Condition F Crew checks Recirc Loop Flow mismatch lAW ST.BB-0001. Crew determines peak thermal power during the transient. CRS recognize the following Tech Specs/actions apply: => 3.4.1.3 Action a. Recirculation Loop Flow Immediate Operator Action lAW AB.RPV-0001. (A Recirc pump is already in manual at minimum speed.) Must restore recirc loop flow mismatch within two hours or declare the B loop not in operation.

ESG-NRC-S4 Page 13 of Rev.: 04 IE directed to monitor/control recirc MG oil temps, INSIGHT Items: rrtoila(1) for "A' MG rrtoila(2) for 'B' MG As RE, REPORT: Thermal Limits are SAT If rodline needs to be reduced, use Reverse Pull Sequence.

Reactor Recirculation Pump High Vibrations:

At the discretion of the Lead Examiner, TRIGGER ET-4.

  • RO/PO direct TBEO to monitor/control reactor recirc MG oil temps.
  • Crew monitors Offgas Treatment and Main Steam Line Radiation Monitors for indications of Fuel Damage.
  • Crew contacts RE.
  • Crew recognizes

'B' Recirc Pump high vibrations by: => OHA C1-E4 "REACTOR RECIRC PUMP VIB HI" => CRIDS D5352 "RECIRC PUMP B VIBRATION HI" => CRIDS D2921 "RECIRC PMP MOTOR B VIBRATION HI" => CRIDS A2603 "RECIRC PMP B SHAFT RADIAL" => OHA C1-F5 "COMPUTER PT IN ALARM"

  • Crew implements AB.RPV-0003:

=> Condition F ESG-NRC-S4 Page 14 of Rev.: 04

!E requested, THEN as RE PROVIDE guidance to the CRS to reduce reactor power lAW the Standard Power Reduction Instructions (SPRI). !E crew manually scrams, THEN TRIGGER ET-8 (Fuel cladding failure).

AsTBEO, ADJUST temperature for the Recirc MG Sets as directed. Crew evaluates the following Recirc Pump parameters for degradation of the 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. Crew determines "B" Recirc Pump Vibration points cannot be maintained below the DANGER limit and performs the following to remove A(B) Recirc Pump from service: Press PUMP B MOTOR BRKR TRIP push button PO verifies the Feedwater system is responding automatically and is restoring RPV level between level 4 and 7. Crew implements AB.RPV-0003: Condition A RO/PO monitors and reports power, pressure and level parameters.

ESG-NRC-S4 Page 15 of Rev.: 04

Fuel Cladding 10 minutes after the Pump at the Lead TRIGGER ET-8 (Fuel CRS verifies core parameters are within the OPRM Enable Region of the Power to Flow Map. RO/PO closes HV -F031 B Recirc pump discharge valve for 5 minutes and then re-opens. CRS directs the following TS requirements:

=> 3.4.1.1 Action a. within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of entering Single Loop Operations. CRS directs implementation of DL.ZZ-0026 Att.3v. Crew implements DL.zZ-0026 Att.3v. Crew recognizes fuel clad damage by: RM11 9RX621/622 Offgas Pretreatment Alarms OHA C6-A3 "MN STM LINE RADIATION HI" RM119RX509/510/511/512 Alert alarms and readings CRIDS Page 37 MSL Radiation readings CRS implements AB.RPV-0008: Condition A Condition B Condition C IE the Crew scrarns during the Recirc Runaway, THEN the Fuel Failure will automatically be inserted.

MSL Radiation levels will reach 3xNFPB approximately 5 minutes after the failure begins. If the plant is shutdown, Condition B actions are not applicable.

ESG-NRC-S4 Page 16 of Rev: 04

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',-,')K)'" -! ,;0: , ENSURE MSL Radiation Malfunctions RM9509-RM9512 ramp down to <20 when the Main Steam Lines AND drain lines are isolated. RO reduces power lAW RE Guidance (Reverse Pull Crew recognizes HI-HI MSL Radiation levels by: => OHA C6-B2 "MN STM LINE RAD HI HI OR INOP" => RM119RX509/510/511/512 High alarms CRIDS Page A037 MSL Radiation readings CRS directs: => Locking the lVIode Switch in SHUTDOWN Closing MSIVs, HV-F016 and HV-F019 steam line drains. RO locks the Mode Switch in SHUTDOWN. RO performs scram actions lAW AB.ZZ-0001 Attachment

1. PO controls level as directed by CRS with: => Feedwater lAW AB.ZZ-0001 Attachment 14 => HPCI/RCIC lAW AB.zZ-0001 Attachment 6 RO/PO close MSIVs, HV-F016 and HV-F019 stearn line drains. Page 17 of 28 Rev.: 04 Unisolable Torus Leak: The Torus Leak will begin three minutes after the MSIVs are isolated.

LE dispatched to the Torus Room to look for a leak, THEN REPORT there is a 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. The Crew inserts a manual scram and closes at least one MSIV 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. LE RPV Level 2 is reached, TH EN CRS implements AB.RPV-0003:

=> Condition G LE directed by the CRS, THEN RO/PO place RHR in Suppression Pool Clg lAW AB.ZZ-0001 Att. 3. Crew recognizes torus leak by: => OHA D3-C2 "REACTOR BLDG SUMP LVL HI/LO" => OHA B1-C3 "SUPPRESSION POOL LEVEL HI/LO" => Various Suppression Pool level indicators lowering Crew dispatches personnel to inspect Rx Bldg '54 and Torus Room for leak. Page 18 of 28 The Critical Task is satisfied as long as all lines are isolated.

For instance, closing the HV-F016, but NOT the HV-F019 satisfies 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: ____ It will take approximately 12.5 minutes for Supp Pool level to reach 38.5". Rev.: 04 IE asked, THEN REPORT both sump pumps are running in both the North and South RB Floor Drain sumps. IE directed to EOP-315 WHEN torus level reaches INSERT Remote CS01-CS04 to make-up Do NOT open more than RHR Pump Room Flooded: The 'A' RHR Room flooded alarm will be received about 4 minutes after the Torus Leak starts.

  • Crew contacts RWEO and informs them of leak.
  • Crew recognizes Supp Pool Level Below 74.5 In EOP entry condition by: => OHA B1-C3 "SUPPRESSION POOL LEVEL HI/LO" => Various Suppression Pool level indicators
  • RO/PO coordinate implementation of EOP-315 with NEO.
  • Crew recognizes Reactor Bldg Room Floor Level Above Max Normal Op EOP Entry Condition by: => OHA A6-A5 "RHR PUMP ROOM FLOODED" CRIDS D2891 "RHR PMP ROOM 4113 LSH-4403A 1" => CRIDS D2892 "RHR PMP ROOM 4113 LSH-4403A2" => SPDS RB LVITE indication Page 19 of 28 Rev.: 04 IF dispatched to 'A' RHR AFTER OHA A6-A5 ROOM FLOODED" is REPORT there is about inches of water on the floor it appears to be coming through a floor
  • CRS implements EOP-103. 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 lAW AB.ZZ-0001 Att. 13. Crew determines that Suppression Pool water level cannot be maintained above 38.5" and initiates opening of five SRVs before Suppression Pool level reaches 30". RO/PO maintain RPV level as directed by CRS. Supp Pool level drops to 30", THEN the Crew ensures HPCI is secured. RECORD Supp Pool level at which ADS was initiated.

LEVEL: ___ ESG-NRC-S4 Page 20 of Rev.: 04 RHR HX INLET Valve F047B Fails The 'A' RHR HX Inlet HV-F047B will fail closed the Torus leak 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 RM 11 9AX833 alarm Various Suppression Pool temperature indicators WHEN Suppression Pool temperature reaches 95 degrees, THEN the CRS re-enters EOP-102. WHEN directed by the CRS, THEN RO/PO place RHR in Suppression Pool Clg lAW AB.ZZ-0001 AU. 3. Crew recognizes RHR HV-F047B is failed closed. RO/PO places A RHR in Suppression Pool Clg lAW AB.ZZ-0001 AU. 3. Termination Requirement: I

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. 0 P-AA-1 01-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines O. OP-AA-108-114 Post Transient Review P. OP-HC-1 08-115-1 001 Operability Assessment and Equipment Control Program O. OP-HC-1 08-1 06-1 001 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-DLZZ-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. HC.RE-RA.BB-0002 Core Flow Determination EE. HC.OP-IO.ZZ-0004 Shutdown From Rated Power To Cold Shutdown FF. ESG-NRC-S4 Page 22 of 28 Rev.: 04

1. The Crew inserts a manual scram and closes at least one MSIV in each Main Line and the HV-F016 or F019 drain valve before MSL radiation has been above Hi-Hi setpoint for three KIA 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 trlree 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 MSIVs lAW the above requirements also satisfies this Critical Task. 2. Crew determines that Suppression Pool water level cannot be maintained above 38.5" and initiates opening of five SRVs before Suppression Pool level reaches 30". KIA 295030 Low Suppression Pool Water Level EA2 Ability 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-NRC-S4 Page 23 of Rev.: 04


ESG*NRC*S4/

04 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 1 E AC/DC Buses TRANSIENTS:

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 COMPONENT/TRAIN/SYSTEM THAT INCREASES CORE DAMAGE YIN KEY EQUIPMENT YIN 1E 4.16KV Bus 120VAC 481 Inverter Hard Torus Vent SWitchgear Room Cooler 1 E 125VDC Bus RCIC SACS Loop SSW Ventilation SSW Loop Y SSW Pump AlB RHR RACS Heat Exchanger HPCI SLC Core Spray Loop Torus DIW Vacuum Breakers EDG SACS Heat Exchanger OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION ___ Emergency Depressurize RPV WIO High Pressure Injection Emergency Venting of Primary Containment Aligning RHR for Suppression Pool Cooling ___ Restore Switchgear Cooling Control Plant via Remote Shutdown Panel Y Manually Start SW Pump ___ Cross-tie DC Charger to Portable Supply Isolate SW Pipe Rupture in RACS Room Initiating LP ECCS with No High Pressure Injection Available Monitoring and Control of SACS heat loads Complete this evaluation form for each ESG-NRC-S4 Page 24 of 28 Rev.:

Rx Power: Work Week: Risk Color: Activities Completed Last "An RFPT is in service in MAN with the SULCV in AUTO Single Element "S" RFPT is warmed up and available at 1000 Major Activities Next 12 Swap in service SSW pumps from "C" to The "A" SSW Traveling Screen has been run for >30 SSW Chlorination has been removed from Protected Tagged

'S' EHC Pump is tagged for ESG-NRC-S4 Page 25 of 28 Rev.: 04 EXAMINATION SCENARIO GUIDE REVIEWNALIDATION This form is used as guidance for an examination team to conduct a review for the proposed exam scenario( s). Attach a separate copy of this form to each scenario ESG-NRC-S4 REVIEWER:

alf!1 1. The scenario has clearly stated objectives in the scenario. t---I/

The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events. Q: 3. Each event description consists of:

  • The point in the scenario when it is to be initiated
  • The malfunction(s) that are entered to initiate the event
  • The symptoms/cues that will be visible to the crew
  • The expected operator actions (by shift position)
  • The event term ination point (l The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible event has aThe events are valid with regard to physics and thermodynamics.

G Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in appropriate time frame and implements procedures and/or corrective

[} f7 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

U A 8. If time compression techniques are used, scenario summary clearly so indicates.

a f 9. The simulator modeling is not altered. Ct t;/-, 1 O. All crew competencies can be evaluated.

({ 77 11. Appropriate reference materials are available (SOERs. LERs. etc.) e.# 12. Proper critical task methodology used lAW NRC procedures.

ESG-NRC-S4 Page 26 of Rev.: 04 EXAMINATION SCENARIO GUIDE (ESG) "ALIPATION (con't) Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios.

Therefore, to complete this part of the review, the set of scenarios must be available.

The section below should be completed once per scenario set. ESG: NRC-S4 SELF-CHECK a1. N 2. o£'i 3. Total malfunctions inserted:

5-8 Malfunctions that occur after EOP Abnormal Events: 2-4 '3 G entry: 1-2 (2 4. Major Transients:

1-2 EOPs entered requiring substantive actions: 1-2 EOP Contingency Procedures requiring substantive actions: 0-2 I Approximate scenario run time: 60-90 minutes G f) Critical Tasks: 2-3 C-Technical Specifications are exercised during the test: Comments:

ESG-NRC-S4 Page 27 of 28 Rev.. 04


Crew Validation Rev: 04 Date Validated: Validated with 3 man crew. Runtime was 60 Validation Comments Disposition 0'/////////7/7/////////7/////&/7///7///////7/////////7//7//7//////7//7/7/////7/7/////////////////7/7///////7//£0'/////////7/7/7///////£lJL/L:0'ff///7///7/7////////7/////////a Sign preregs in SSW SOP. -'A':-'c=..c:...:e:.Lp-'-'te:....:d:-:-.

Run SSW pump swap before rod movement.

Accepted.

ESG written to do either MSL Rads came up hard on manual scram. Corrected ramp rate for ET-16 to be the same as Crew Validation Rev: Date Validated:

Validation Comments DiWJsition ESG-NRC-S4 Page 28 of 28 Rev.: 04 Instructor APPROVED BY:

APPROVED BY: DATE SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM: REVISION

SUMMARY

PREPARED BY:

NRC SCENARIO 2 ESG*NRC*S2 Effective when approved.

75 minutes 00 L.O. REQUAL INITIAL LICENSE L--_-.JI OTHER Archie E. Faulkner 1/14/12 Enabling Objectives 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 " *.") Raise Power 84.5% to 90% using Control Rodsl Place C RFPT in service Stuck Rod (TS) Flow Unit Fails Downscale wi Half Scram (TS) A EHC Pump Trip Loss of EHC due to Filter Clogging wi Manual Scram ATWS Failure of RWCU to Auto Isolate Failure of HPCI Components to Auto-Initiate The scenario begins with the plant at 84.5% power with power ascension in progress following a load reduction for C RFPT vibration troubleshooting.

The RO will withdraw control rods for the power change. The BOP operator will place the C RFPT in service. Control Rod 46-47 will stick when movement is attempted.

Attempts to free the rod will be successful.

The B APRM Flow Unit will fail downscale resulting in a half scram and rod block. The RO will bypass the Flow Unit and reset the half scrarn. After the Flow Unit failure is addressed, EHC Pump A trips. EHC system filters will clog forcing a manual scram. The scram will result in a half-core A TWS. RWCU Isolation valves HV-F001 and HV-F004 will fail to automatically close on SLC pump start requiring operator action. HPCI components will fail to auto-initiate, and will need to be manually operated to continue to use HPCI. The scenario ends when the reactor is shutdown either by manual rod insertion with RMCS or manual scrams with EOP-320. ESG-NRC-S2 Page 2 of Rev.: 00 INITIALIZE the simulator to 100% power, 3840 MWt EPU. REOUCE Reactor power to 84.5% using reactor recirc pumps and control rods. Stick control rod 46-47 at position 00 using ET -1. Remove C RFPT from service and place recirc at 1000 rpm lAW HC.OP-SO.AE-0001.

Remove Crossflow from service and clear Overhead Alarm. ENSURE A EHC Pump is in service. ENSURE associated Schedule file open and running. ENSURE associated Events file open. INITIAL 10-6 for Power APPL Y Protected Equipment bezel covers to A and B MARKUP HC.OP-SO.AE-0001 Section 5.7 for C ENSURE Move Sheets are available for Control

  • Group 90 Position 00 to 12
  • Group 9E Position 24 to 48
  • Group 90 Position 12 to 22 At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs (80091396 ENSURE Oata Collection is trending the following parameters as a
  • W/R Reactor Water Level
  • W IR RPV Pressure
  • Fuel Zone Reactor Water Level
  • Suppression Pool temperature COMPLETE "Simulator Ready-for-Training/Examination Checklist".

ESG-NRC-S2 Page 3 of 29 Rev.: 00 2 Event code: I LCPNEP01 >= 300

Description:

Deletes malfunction when drive pressure is 300 psig Event code:

Description:

Event code: Descri ption: Event code:

Description:

Event code:

Description:

ESG-NRC-S2 Page 4of29 Rev.: 00

"" MALFUNCTION SCHEDULE: " Initial @Time None None None None Event None None None None Action Insert malfunction RP07 Insert malfunction CUllA Insert malfunction CUllE Insert malfunction HP 14 Description Half-core ATWS -right side RWCU isolation valve FOOl failure to auto close RWCU isolation valve F004 failure to auto close HPCI HV-F006 failure to auto open None None Insert malfunction HP 15 HPCI HV-8278 failure to auto open None None Insert malfunction HP 16 HPCI HV-F059 failure to auto open None None Insert malfunction HP06E HPCI aux oil pump failure to auto start None None None None None None Insert malfunction CD034647 Insert malfunction CD034647 after 1 on event 2 delete in 1 Insert malfunction NM 12B to 0 on event 3 Control Rod 46-47 stuck Control Rod 46-47 stuck Flow summer K607B failure None None None None None None None None Insert malfunction TC07 A on event 4 Insert malfunction TC16 to 100.000 on event 4 Insert malfunction EG 11 after 360 on event 4 Insert malfunction TCOl-lO after 380 on event 4 EHC pump A trip EHC pump discharge filter plugging Main generator trip All turbine bypass valves fail closed ESG-NRC-S2 Page 5 of 29 Rev.: 00 Initial @Tlme i Event Action Description None None Insert remote PP04 to NO PP04 OD-3 Crossflow Applied None None Insert remote AN28 to NOR1Yl AN28 CROSSFLOW ALARMITRBL None I None I Insert ren:.0te EPOI after 360 to BYPASS EPOI EOP-30l, bypass MSN (-129") on event ::> isolation interlock None I None I Insert remote EP02 after 480 to BYPASS EP02 EOP-3 11 , bypass PCIG (-129") on event 6 isolation interlock None I None I Insert remote EP38 after 180 to EP38 EOP-319, Restoring Instrument Air in Emergency on event 7 an None I None I Insert remote EP09 after 240 to EP09 EOP-320 (step 5.l.2), ARI valve fuses REMOVED on event 8 F6A1F5A None I None I Insert remote EP 1 0 after 240 to EP 1 0 EOP-320 (step 5.1.4), ARI valve fuses REMOVED on event 8 F6B!F5B None I None I Insert remote EP 11 after 360 to EP 11 EOP-320 (step 5.2.2), RPS division 1 INST ALLED on event 8 jumper None I None I Insert remote EP l3 after 360 to EPl3 EOP-320 (step 5.2.3), RPS division 3 INSTALLED on event 8 jumper None I None I Insert remote EP12 after no to EP12 EOP-320 (step 5.2.4), RPS division 2 INSTALLED on event 8 jumper None I None I Insert remote EP 14 after no to EP14 EOP-320 (step 5.2.5), RPS division 4 INSTALLED on event 8 jumper None I None I Insert remote EP35 after 180 to FAIL CLOSE on event 9 EP35 EOP-322 HV-F006 HPCI to CS ESG-NRC-S2 Page 6 of 29 Rev.: 00 v ..

  • SCENARldGU;OE'SEQUENCE:

AND EXPECTED RESPONSe};':* ,': <' ";,

Place C RFPT in service: After the Crew assumes the watch. Raise Reactor Power with Control After the Crew assumes NOTE: Operator may single notch withdraw the rods, as necessary, in which case the CONTINUOUS WITHDRAW PB is NOT used. ,,' :,:t:

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-,' : '-."' ',h"; , ......,.,.CRS directs BOP Operator to place C RFPT in service feeding the RPV lAW 0001. BOP Operator places C RFPT in service feeding the RPV lAW HC.OP-SO.AE-0001. CRS directs the RO to raise Reactor power with Control Rods in accordance with RE guidance. RO withdraws Control Rods in accordance with 0001 and CRS directions. Selected rod PB comes ON (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). At the ROD SELECT MODULE, simultaneously press and hold both the WITHDRAW PB AND the CONTII\JUOUS WITHDRAW PB and observe the following: The INSERT (white) light comes ON momentarily. The WITHDRAW (white) light comes ON and the CONTII\JUOUS WITHDRAW (white) light comes ON. ESG-NRC-S2 Page 7 of Rev.: 00

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./ CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod movement. Prior to reaching the desired control rod position, simultaneously release both the WITHDRAW PB and the CONTINUOUS WITHDRAW PB and OBSERVE the following: The WITHDRAW (white) light goes OUT. The SETTLE (white) light comes ON for::::: 6 seconds, then goes out. CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod has settled to the desired position. At position 48 the applicable Full Core Display FULL OUT (red) light comes on. Perform a control rod coupling integrity check lAW ST.BF-0001. Perform the following while giving the selected Control Rod a continuous withdraw signal: => Observe the following as indication of the Control Rod being coupled: 1. ROD OVERTRA VEL alarm does NOT annunciate.

ESG-NRC-S2 Page 8 of Rev.: 00 V.

EventllnstructorAtiitTity

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." Stuck Control Rod 46*47: Preinserted.

Examiner Note: The rod wilt remain stuck until Drive Water Pressure has been intentionally raised to >300 psid. NOTE: Crew may request RE guidance.

Respond that a withdraw signal then an insert signal may be attempted. Red Full Out light illuminates on the Full Core Display. RPIS indicates the Control Rod is full out (48). Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. Indicates the completion of the movement on the Pull Listing. RO determines that Control Rod 46-47 is stuck by observing no change in rod motion on the 4 Rod Display or the RWM and informs the CRS. CRS directs actions in accordance with 0001 : Condition F. RO performs actions in accordance with CRS directions: Verifies no Rod Blocks are present. Attempts to operate the drive in both directions to determine the exact condition of the Control Rod. Verifies drive water flow fluctuates normally.

ESG-NRC-S2 Page 9 of Rev.: 00

..

". \:f!;;'¢i; X ENSURE ET-2 triggers when drive water pressure dp >300 psid. This deletes stuck rod malfunction. Verifies proper operation of the SETTLE, INSERT, AND WITHDRAW lights. VENT Control Rod using CONTINUOUS INSERT PB. ATTEMPT to withdraw Control Rod using WITHDRAW PB (including CONTINUOUS WITHDRAW PB). PERFORM the following:

a. SIMULTANEOUSLY PRESS AND HOLD BOTH the WITHDRAW PB AND the CONTINUOUS WITHDRAW PB. b. MOMENTARILY PRESS and then RELEASE the CONTINUOUS INSERT PB (this step may be repeated).
c. RELEASE BOTH the WITHDRAW PB AND the CONTINUOUS WITHDRAW PB.
  • Performs the following:

=> Raises the drive water pressure in approximately 50 psid increments, not to exceed 500 psid. Attempts to notch in OR notch out the Control Rod at the new pressure increment. RO observes Rod Movement as indicated on the 4 Rod Display or RWM, and notifies the CRS. ESG-NRC-S2 Page 10 of Rev.: 00 Flow Unit Failure: At the Lead TRIGGER ET-3 (8 APRM Unit Failure RO returns the drive water pressure to the normal operating range (260-270 psid on A3015). Crew monitors Reactor power, pressure, and level and ensure plant conditions are stable. Ensures no scram setpoints have been exceeded.

  • Crew recognizes RPS % scram by: => OHA C3-A4 "REACTOR SCRAM TRIP LOGIC 81" => OHA C3-A5 "REACTOR SCRAM TRIP LOGIC 82" => OHA C5-A 1 "NEUTRON MONITORII\JG SYSTEM" => RPS Trip Logic 81 NORMAL/RES ET status lights extinguished

=> RPS Trip Logic 82 NORMAL/RESET status lights extinguished

=> Pilot Scram Valve Solenoid LOGIC 8 NORMAL status lights for all four groups extinguished.

=> CRIDS 02126 NEUTRON MON SYST SCRAM X => CRIDS 02174 "REACTOR SCRAM X TRIP" => CRIDS 02175 "REACTOR SCRAM Z TRIP" ESG-NRC-S2 Page 11 of Rev.: 00

v. SCEN;ARIOGUIDE SEQUENtk;:ANDExPEcT'E:DREsPoNsE
  • "" ';,\{A.. <, , '.\";, <".{/;: c.,-; ">"; " -...," Eventl

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';. ' ./ ".J

... ,:..

,..... Crew recognizes

'B', 'D', and 'F' APRMs Upscale by: OHA C3-C5 "APRM SYS B UPSCALE C3-D4 "APRM APRMs B, D, and F TR OR INOP" status lights APRM B, D, and F "UPSC ALARM" status lights CRIDS D4305 "APRM CH B UPSCALE THERMAL TRIP" CRIDS D4307 "APRM CH D UPSCALE THERMAL TRIP" CRIDS D4309 "APRM CH F UPSCALE THERMAL TRIP" Crew recognizes

'B' RECIRC LOOP FLOW SUMMER FAILURE Downscale by: FLOW UNIT Band B "COM PAR" status lights APRM B, D, and F "UPSC ALARM" status lights CRIDS C026 "EITHER RBM CHANNEL UPSCALE" CRI DS C049 "RECI RC FLOW COMPR OUT LIMITS" CRS implements AB.IC-0004: Condition F CRS references AB.IC-0003: Condition B RO bypasses 'B' Flow Unit. CRS refers to DD.zZ-0020 for a failed PPC Sensor. CRS directs Reactor Engineering to evaluate the flow unit failure on the PPC. Page 12 of 29 Rev.: 00

.... , -.. ",. ,.,-" ';,;,;;> -. N -;;;:a-/.

IF directed to place the Flow Unit B MODE Switch in the unlabeled position, THEN CHANGE Malfunction NM12B Final value to 100%. Trip of 'A' EHC Pump: After the Crew resets RPS addresses Tech at the discretion of the TRIGGER ET-4 (Loss of lE dispatched to the EHC pump, THEN REPORT AP116 motor is very hot to the touch. ESG-NRC-S2 RO directs I&C to place the MODE Switch, on the applicable flow unit, to the "UNLABELED" position between STANDBY and ZERO. RO verifies RPS trip clear.

  • RO resets RPS trip as follows: => TURN the affected RPS Trip Logic key to RESET, AND 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 => 3.3.1 => 3.1.4.3

  • Crew recognizes trip of AP116 EHC pump by: => OHA D3-F5 "TURB HYDR PUMP TROUBLE" => OHA D3-E5 "TURB HYDR RESERVOIR TROUBLE" => CRIDS D5542 "HYDRAULIC FLUID PUMP A TRBL" => CRIDS D5575 "TURBINE HYDRAULIC FLUID PRESS LO" HYDR FLUID PUMP A flashing LOW DISCH PRESS light RO/PO start the BP116 EHC pump. Page 13 of 29 If left in AUTO, the BP116 EHC pump will auto-start in about 50 seconds. Immediate Operator action lAW AB. BOP-0003.

Rev.: 00 InSight Item: EHC Header Pressure tupehchd EHC Pump Disch Pressure tupehc(2)

-15 EHC Pump Filter DIP tupehcdp(2)

EHC Filter The BP116 discharge filter begin clogging after the IF directed to swap BP116 discharge filters, REFER to SO.CH-0001 Section 5.20, THEN REPORT the duplex filter transfer handle will not move.

  • CRS implements AB.BOP-0003.
  • Crew recognizes BP116 discharge filter clogging by: :=:> OHA D3-F5 "TURB HYDR PUMPTROUBL
=:> CRIDS D3629 "MAIN TURB EHC PUMP B FILTER DP HI" HYDR FLUID PUMP B flashing HI FILTER DIP light :=:> Lowering EHC header pressure
  • CRS implements AB.BOP-0003:

Condition A

  • Crew directs TBEO to swap BP116 pump discharge filters.
  • WHEN EHC pressure lowers to 1200 psig, THEN CRS directs locking the Mode Switch in SHUTDOWN.
  • RO locks the Mode switch in SHUTDOWN.

Page 14 of 29 There are no subsequent actions in AB.BOP-0003 for a trip of a pump. With NO discharge filter swap, EHC pressure will reach 1100# in about 6 minutes after the pump trip. EHC header pressure will continue to decay. May direct earlier, based on rate of pressure drop and absence of any remaining compensatory actions. Rev.: 00

,

";., ATWS: Crew recognizes Scram Condition and Reactor Power The half core ATWS is already Above 4% EOP entry condition:

inserted.

APRM indications Absence of rod FULL IN lights on the right side of Full Core Display Rod position indications RO performs scram actions lAW AB.ZZ-0001 Art. 1. 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. Crew recognizes RWCU failure to isolate by: HV-F004 OPEN indication on 10C651C and 10C650D HV-F001 OPEN indication on 1 OC651 C and 10C650D RWCU pump running indication on 1 OC651 C RWCU flow indication on CRIDS page 61 and 232 RO/PO isolate RWCU HV-F001 OR HV-F004 following SBLC pump start. RO/PO inform CRS of failure to automatically isolate. ESG-NRC-S2 Page 15 of Rev.: 00 REFER to the appropriate EOP and SUPPORT Crew requests for EOPs lAW with the following.

Validated execution time delays are built-in:

EOP-301: ET-5 EOP-311: ET-6 EOP-319: ET-7 EOP-320: ET-8 EOP-322: ET-9 ESG-NRC-S2 CRS directs: => Verifying Recirc runback to minimum => Tripping reactor recirc pumps RO/PO: => Verify Recirc runback to minimum => Trip reactor recirc pumps Crew verifies bypass valves control pressure. CRS directs inhibiting ADS. RO/PO inhibit ADS lAW AB.ZZ-0001 AU. 13. CREW prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUA TlON.

  • CRS directs performance of the following EOPs: => EO.ZZ-0320 "Defeating ARI and RPS Interlocks" => EO.ZZ-0301 "Bypassing MSIV Isolation Interlocks" => EO.zZ-0311 "Bypassing Primary Containment Instrument Gas Isolation Interlocks" => EO.ZZ-0319 "Restoring Instrument Air in an Emergency" EO.ZZ-0322 "Core Spray Injection Valve Override" Page 16 of 29 Recirc RPT breakers may already be tripped due to Main Turbine Trip. This Critical Task is not applicable if RPV level never reaches -129". See justification for failure criteria.

The timing, order, and priority of the EOP performance may vary. Rev.: 00

  • CRS directs terminating and preventing injection to the RPV with the exception of: => SLC => CRD => RCIC
  • RO/PO terminate and prevent injection from HPCI, RHR and feedwater/condensate lAW AB.ZZ-0001
=> Attachment 16 (1 OC650) => Attachment 17 (10C651)
  • CRS directs bypassing the RWM and commencing manual rod insertion.
  • IF EOP-322 is complete before RPV water level reaches -129", THEN CRS directs maintaining RPV water level between -50" and -185" with HPCI and RCIC. Typically, the lower end of the level band is set above -129". Typically, the lower end of the level band is set above -129". ESG-NRC-S2 Page 17 of 29 Rev.: 00

.

.* IF EOP-322 is NOT complete before RPV water level reaches 29", THEN CRS directs maintaining water level between -129" and -185" with HPCI and RCIC. (After EOP-322 is complete, and injection through the Core Spray line has been terminated, the CRS may use the full level band allowed by EOP-1 01 A. In this case, with Suppression Pool temperature below 110°, the upper RPV level limit is -50".) RO/PO initiate HPCI as directed by CRS. RO/PO recognize HPCI components fail to auto-initiate and align components lAW AB.ZZ-0001 Att. 6. HPCI Aux Oil HPCI HPCI HPCI RO/PO inject with HPCI as necessary to maintain RPV water level as directed by CRS. RO/PO inject lAW EO.zZ-0322 to maintain RPV water level as directed by CRS. IF EOP-322 is complete in the field, RO/PO implements 322 in Control Room as follows: Page 18 of 29 EOP-322 states: "HPCI injection flow should be limited (or secured, if not required to maintain RPV level above TAF) while this procedure is in progress." Hope Creek has defined the intent of "above TAF" in this statement to mean no higher than -129",

Rev.: 00 ENSURE HPCI flow is :s; 3000 gpm CLOSE HV-F006 CREW maintains or restores adequate core cooling by restoring/maintaining Reactor water level to >-185" lAW HC.OP-EO.ZZ-0101A without Emergency Depressurizing. !E the MSIVs close, THEN the CRS directs pressure control with the SRVs. !E directed, THEN RO/PO control pressure with SRVs lAW AB.zZ-0001 Att. 13. !E RPV level reaches -129", THEN CRS directs restoring:

=> 1 E Breakers PCIG to !E directed, THEN RO/PO restore 1 E breakers lAW Att. IF directed, THEN RO/PO restore a CRD pump to service lAW either: OP-AB.ZZ-0001 Attach 18 ESG-NRC-S2 Page 19 of Rev.: 00 WHEN the Crew has reset RPS, THEN DELETE Malfunction RP07 to allow full rod insertion on the next scram. At the Lead Examiners discretion, MODIFY Insight Item Iclsdv to accelerate draining of the SDV. ESG-NRC-S2 lE directed, THEN RO/PO restore PCIG to SRVs lAW AB.zZ-0001 Att. 9 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 Cooling lAW AB.ZZ-0001 Att. 3. lE necessary, THEN RO/PO align SACS to support second RHR Hx lAW SO.EG-0001 Section 5.9. WHEN EOP-320 Section 5.1 and 5.2 are THEN the Crew EOP-320 Section 5.3 and WHEN OHA C6-E4 clears, THEN the Crew initiates a manual scram lAW EOP-320 Section 5.3. Page 20 of 29 Restoring PCIG to the SRVs lAW AB.zZ-0001 Att. 9 is also equivalent to the Control Room actions in EOP-311. Rev.: 00 v;

""', ,:; ,', -**** ** -"'C'-C'.

-_.'

.
:" __' . _. /.' ::7 -.-<

-

.;/"'.".....

I I .", --.' _ :----,-.. -c__,' _m', ,>." / "",.,.' '," . Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when: RPV Level is being maintained above -161" AND All rods are fully inserted CREW fully inserts all 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. CRS exits EOP-101A, enters EOP-101. ESG-NRC-S2 Page 21 of Rev.: 00

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. H U-AA-1211 Briefing L. OP-AA-101-111-1004 Operations Standards M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-1 06-101-1001 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-1 08-1 06-1 001 Equipment Operational Control R. HC.OP-DD.ZZ-0020 Review of Core Performance Information S. HC.OP-SO.AE-0001 Feedwater System Operation T. HC.OP-SO.BF-0001 CRD Hydraulic System Operation U. HC.OP-SO.SF-0001 Reactor Manual Control V. HC.OP-SO.SF-0003 Rod Worth Minimizer Operation W. HC.RE-IO.ZZ-0001 Core Operations Guidelines X. HC.RE-AB.zZ-0001 Insertion of Control Rods in Response to an ATWS Y. HC.OP-AB.ZZ-0001 Transient Plant Conditions Z. HC.OP-AB.BOP-0003 Turbine Hydraulic Pressure AA. HC.OP-AB.IC-0001 Control Rod BB. HC.OP-AB.IC-0003 Reactor Protection System CC. HC.OP-AB.IC-0004 Neutron Monitoring DD. HC.OP-IO.ZZ-0006 Power Changes During Operation EE. HC.OP-AB.ZZ-OOO Reactor Scram FF. HC.OP-EO.ZZ-0101 RPV Control GG. HC.OP-EO.ZZ-0101A ATWS-RPV Control HH. HC.OP-EO.ZZ-0102 Primary Containment Control II. Strategies For Successful Transient Mitigation ESG-NRC-S2 Page 22 of 29 Rev.: 00 ESG-N RC-S2 I 1. CREW prevents an uncontrolled depressurization during A TWS conditions preventing ADS 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 100 psig. 2. RO/PO isolate RWCU HV-F001 OR HV-F004 following SBLC pump start. KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA 1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: EA 1.02 RRCS RO 3.8 SRO 4.0 EA 1.04 SBlC RO 4.5 SRO 4.5 KIA 211000 Standby Liquid Control Systems A3 Ability to monitor automatic operations of the STANDBY LlDUID CONTROL SYSTEM including:

A3.06 RWCU system isolation RO 4.0 SRO 4.1 A4 Ability to manually operate and/or monitor in the control room: A4.06 RWCU system isolation RO 3.9 SRO 3.9 The failure of RWCU HV-F001 and F004 to automatically close will reduce the effectiveness of the SBlC injection.

Crew action is required to correct the incorrect reactivity control before the BIIT is reached as directed by EOP-1 01 A. 3. CREW maintains or restores adequate core cooling by restoring/maintaining Reactor water level to >-185" lAW HC.OP-EO.ZZ-0101A without Emergency Depressurizing.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Power Above APRM Downscale or EA2.02 Reactor water level RO 4.1 SRO 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.

AB.lZ-0001 provides directions on manual initiation of HPCI which will mitigate the automatic initiation failure. 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-S2 Page 23 of Rev.: 00

4. CREW fully inserts all control rods via RMCS and/or manual scram(s)

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA 1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: EA 1.01 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-S2 Page 24 of Rev.: 00


ESG-NRC-S2/00 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN Y/"I EVENT Loss Of Offsite PowerlSBO Internal Flooding LOCA Loss of 1 E AC/DC Buses LOSS OF SUPPORT TRANSIENTS:

SYSTEMS: Y 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 COMPONENT/TRAIN/SYSTEM THAT INCREASES CORE DAMAGE YIN KEY YIN KEY EQUIPMENT 1 E 4.16KV Bus 120VAC 481 Inverter Hard Torus Vent Switchgear Room Cooler 1 E 125VDC Bus RCIC ___ SACS Loop SSW SSW Loop SSW NBRHR ___ RACS Heat HPCI ___ ___ Core Spray Loop Torus DIW Vacuum Breakers EDG ___ SACS Heat Exchanger OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION Emergency Depressurize RPV WIO High Pressure Injection Emergency Venting of Primary Containment Aligning RHR for Suppression Pool Restore Switchgear Control Plant via Remote Shutdown Manually Start SW Cross-tie DC Charger to Portable Isolate SW Pipe Rupture in RACS Initiating LP ECCS with No High Pressure Injection

___ Monitoring and Control of SACS heat loads Complete this evaluation form for each ESG. ESG-NRC-S2 Page 25 of Rev.: 00 Rx Power: Work Week: Risk Color: Activities Completed Last Reduced power to 84.5% for C RFPT vibration Commenced Power ascension lAW C RFPT is in Recirc at -1000 Major Activities Next 12 Return to 100% Protected A and B Tagged ESG-NRC-S2 Page 26 of 29 Rev.: 00 IX. SIMULATO'RESGREVI EWN

' ">1 EXAMINATION SCENARIO GUIDE (ESG) REVIEWNALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s).

Attach a separate copy of this form to each scenario reviewed. ['ilL ESG-NRC-S2 Q i'r 1. The scenario has clearly stated objectives in the o c,/ 2. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does --not cue crew into expected events. a3. Each event description consists of:

  • The point in the scenario when it is to be initiated
  • The malfunction(s) that are entered to initiate the event
  • The symptoms/cues that will be visible to the crew
  • The expected operator actions (by shift position)
  • The event termination point
4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

Qtz,'i 5. The events are valid with regard to physics and thermodynamics.

6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).
7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
1J4--8. If time compression techniques are used, scenario summary clearly so indicates. The simulator modeling is not altered. (l (t 10. All crew competencies can be evaluated.

-D. r111. Appropriate reference materials are available (SOERs, LERs, 0(1 12. Proper critical task methodology used lAW NRC ESG-NRC-S2 Page 27 of 29 Rev.: 00 EXAMINATION SCENARIO GUIDE VALIDATION Note: The following criteria list scenario traits that are numerical In nature. A second set of numbers indicates a range to be met for a set of two scenarios.

Therefore, to complete this part of the review, the set of scenarios must be available.

The section below should be completed once per scenario set. ESG: ESG: SELF-CHECK Total malfunctions inserted:

4-8/10-14 Malfunctions that occur after EOP entry: 1-4/3-6 Abnormal Events: 1-2/2-3 Major Transients:

1-2/2-3 _ 5. EOPs used beyond primary scram response EOP: 1-3/3-5 E-6. EOP Contingency Procedures used: 0-3/1-3 7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes) EOP run time: 40-70% of scenario run time 9. Crew Critical Tasks: 2-5/5-8 1 O. Technical Specifications are exercised during the test Events used in the two scenarios are not repeated (Only Applicable for an exam set) Comments:

ESG-NRC-S2 Page 28 of Rev.. 00


EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Crew Validation Rev: 00 Date Validated:

1/14/12 Validated with one 3 man crew from B Shift. Runtime was 75 minutes. Validation Comments Disposition

//"////////////////////////////////////$/////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////5 RPV level control by operators kept level above -129". Added MT trip and TBV fail closed after 6 minutes on ET -4 to drive pressure control to SRVs. Crew Validation Rev: Date Validated:

Validation Comments Disposition

//"//////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////$///////////////////////5 ESG-NRC-S2 Page 29 of 29 Rev.: 00 SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM: REVISION

SUMMARY

NRC SCENARIO Effective when approved.

80 minutes 00 L.O. REQUAL INITIAL LICENSE OTHER '-------'

1. Added text for power increase with Reactor Recirc. 2. Revised wording of Critical Task for clarity. PREPARED BY: Archie E. Faulkner 1/14/12 Instructor DATE APPROVED BY: ---JJn/J.?,APPROVED BY: /

IhiL DATE Enabling Objectives 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 "*.") Raise Power with Recirc PT-N076A MSL Pressure Fails Upscale A CRD Pump Trip Seismic Event with 10A403 Bus Lockout Small Break LOCA I Manual scram LOPI with A, B, and D EDG Malfunctions HPCI Oil Line Break RCIC Overspeed The scenario begins with the plant at 93% power; MOL. "B" EHC pump is tagged for maintenance.

Reactor power is being raised to 98% with Reactor Recirc. Main Steam Line Pressure Transmitter PT-N076A fails upscale requiring a Tech Spec entry. After TS are addressed, the "A" CRD Pump will trip. The RO will need to place the "B" CRD Pump inservice.

Once CRD is restored, an earthquake will occur. The 10A403 bus will lockout. "An SSW Pump will fail to Auto-start and must be manually started by the operator.

After Tech Specs are addressed for the bus loss, a Small Break LOCA occurs requiring a manual scram. The oil line to HPCI stearn control valve fails and is not recoverable.

RCIC trips on Overspeed.

An aftershock causes a Loss of Offsite Power. "D" EDG fails and is not recoverable. "B" EDG fails to start, but can be started by the operator (Critical Task). RCIC can be recovered with field operator action after RPV Level reaches -129", but is insufficient to prevent reaching TAF. Emergency Depressurization is required before RPV Level reaches -185" (Critical Task). "An EDG can be started after emergency depressurization.

This will allow containment control to be exercised.

The scenario is terminated when the RPV has been depressurized, RPV water level restored to post LOCA level band and Drywell Sprays initiated.

ESG-NRC-S1 Page 2 of Rev: 00

---INITIALIZE the simulator to full power, MOL. ENSURE A CRD pump is in service. ENSURE B TACS Loop is in service. ENSURE C SACS pump is in service. ENSURE C SSW pump is in service. ENSURE AP116 EHC pump is in service. CfT BP116 EHC pump as follows: 1. INSERT Malfunction TC07B 2. PLACE 'B' EHC pump in MAN 3. START 'B' EHC pump and allow it to trip ENSURE associated Schedule file is loaded and running. ENSURE associated Events file open. PLACE red bezel cover on '6' EHC pump. At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs ENSURE Data Collection is trending the following datapool

  • W/R Reactor Water Level: rrln091a or equivalent
  • CRIDS Compensated Fuel Zone Reactor Water Level: B5042 or COMPLETE the Simulator Ready for Training/Examination ESG-NRC-S1 Page 3 of 24 Rev:OC Initial Insert malfunction TC07B EHC pump B trip None I None I Insert malfunction DGO IA Diesel generator A failure to start Kone I None I Insert malfunction DG07B I Diesel generator B emergency start signal failure Kone I None Insert malfunction DG08B Diesel generator B breaker failure to auto close None None Insert malfunction DGO 1 C Diesel generator C failure to start None None Insert malfunction DG02D Diesel generator D failure None I None Insert malfunction MS09A to 100.00000 Steam line header pressure transmitter N076A on event 1 fails None I None Insert malfunction CD10A on event 2 CRD hydraulic pump A trip None None Insert malfunction PC07 A on event 3 Seismic Event I None None Insert malfunction ED 16 on event 3 Loss of 4.16 KV vital bus C 10A403 None None Insert malfunction CWl4A on event 3 Service water pump AP502 fail to auto start None I None I Insert malfunction RR31Al to 20.00000 in Recirc loop A small break [V] (10%--60 gpm, 600 on event 4 1 gpm) None None Insert malfunction PC07B on event 5 Seismic Event II None None Insert malfunction EG 12 on event 5 Loss of all off site povver None I None I Insert malfunction HP06M on event 5 HPCI aux oil pump -oil line break None I None I Insert malfunction RCO 1 on event 5 RCIC turbine overspeed None I None I Insert malfunction RR3lA2 to 4.00000 in Recirc loop A large break [V] (10%-6000 60 on event 5 gpm, 1000/0""60000 gpm) None I None I Insert malfunction DG07B on event 7 Diesel generator B emergency start signal failure delete in 1 None I None i Insert malfunction RCO 1 on event 8 delete I RCIC turbine overspeed , in 1 None I None ' Insert malfunction DGO 1 A after 1 on event I D' 1 A f 'I t' 12 d 1 '1 lese generator at ure to s art e ete in ESG-NRC-S1 Page 4 of 24 Rev: 00 I Insert remote Re02 after 5 to RESET on None I None I Re02 ReIC overspeed trip reset event 8 I Insert remote HP08 to TAGGED on event None I None HP08 HPCI Aux Oil Pump 10 I Insert remote eXll after 60 to OPEN on eXll ex valve AP-V041 to Core Spray None I None event 11 header A I Insert remote eX15 after 120 to OPEN on None I None eX] 5 ex valve AP-V044 to RHR header A event I Insert remote eXl? after 180 to OPEN I eXl? ex valve AP-V04? to RHR header e None I None event 11 Raise Power with Recirc: After the Crew assumes the watch.
  • CRS directs the RO to raise Reactor power with Reactor Recirc in accordance with RE guidance.
  • RO increases Reactor Recirc pump speeds in accordance with HC.OP-SO.BB-0002 and CRS directions.

PT-N076A Failure: . Afterthe Crew assumes the watch and at the discretion of the Lead Examiner, TRIGGER ET-1 CA' NSSSS MSL Pressure Transmitter Fails High). Transmitter is located in Electrical IE dispatched to THEN REPORT there is visible damage to

  • Crew recognizes

'A' NSSSS instrument failure by: => OHA C8-A5 "NSSSS INBD ISLN SYS OUT OF SVCE" => Amber NSSSS CH A "TRIP UNIT IN CAL OR GROSS FAIL" light => CRIDS D2633 "MSIV INBD SYS OUT OF SVCE CH A" CRIDS D2636 "NON-MSIV INBD SYS OUT OF SVCE CHA" RO/PO reference ARP. Crew inspects 10C609 panel trip units and finds B21-N676A is failed upscale with a Gross Fail Trip in. Crew contacts Maintenance to troubleshoot.

This will prevent the 'At NSSSS Channel from generating an MSIV isolation signal on Low Main Steam Line pressure.

ESG-NRC-S1 Page 6 of Rev: 00 If requested, after an appropriate delay, support actions of placing trip units in tripped condition by changing MALF MS09A severity to O. A CRD Pump Trip: After the Crew addresses Tech Specs for the PT -N076A and at the discretion of the Lead Examiner, TRIGGER ET-2. IF dispatched to investigate the CRD Pump trip, THEN REPORT the A CRD pump speed changer inboard bearing has overheated.

IE dispatched to investigate the trip of A CRD Pump Breaker, THEN REPORT breaker 43711 is tripped on overcurrent.

  • CRS recognize the following TIS applies ::;, Isolation Actuation Instrumentation

3.3.2 action

b.1.c applies (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to place in a tripped condition).

  • Crew may implement GP.ZZ-0011 to place trip units into tripped condition
  • RO recognizes

'A' CRD pump trip by: ::;, OHA C6-F2 HCRD SYSTEM TROUBLE" ::;, CRIDS 02244 "CRD WATER PUMP A MOTOR" ::;, Flashing OVLD/POWER FAILURE bezel for A CRD Pump"

  • RO reference ARP. RO starts "B" CRD pump lAW ARP as follows: PLACE DRIVE WTR FLOW controller in MANUAL AND SET to O. Page 7 of 24 TIS Table 3.3.2-1 Trip Function 3c.

Rev: 00 Earthquake/10A403 Bus Loss: After the Crew restores CRD and at the discretion of the Lead Examiner: PLAY the Earthquake Sound Effect (if available) at medium volume for about 20 seconds OR ANNOUNCE "You feel motion then it stops" TRIGGER ET-3 (Seismic Eventl1 OA403 Bus Loss) IF Crew calls National Earthquake Center, THEN REPORT a seismic event of 6.0 on Richter scale centered 12 miles east of Wilmington, DE. IF Crew calls Security, THEN REPORT the Security system is intact. ESG-NRC-S1 START B CRD Pump AND RESTORE system flow to 63 gpm. ADJUST HV-F003 to restore system pressure to normal, IF necessary.

RETURN DRIVE WTR FLOW controller to AUTO.

  • Crew recognizes Seismic Event by: OHA C6-C4 "SEISMIC MON PNL C673" CRIDS D3977 "SEISMIC TROUBLE ALARM TRBL" Response Spectrum Analyzer indications on 10C650C Loud rumbling noise (if available) Crew monitors critical parameters to determine if plant is stable. CRS implements AB.MISC-0001: Condition E Condition F Page 8 of 24 AB.MISC-0001 actions provided for reference only. Due to the pace of the scenario, it is unlikely they will be implemented.

Rev: 00 IF dispatched to 10C673, THEN REPORT: The Event Indicator is WHITE The tape machines have advanced but are not running The Amber Alarm light on the Seismic Switch Power Supply drawer is lit. IF directed to reset 10C673, THEN DELETE Malfunction PC07A. RO/PO implement AR.ZZ-0011 Attachment C4. Crew dispatches ABEO to 10C673. Crew recognizes a seismic event >0.1 g has occurred RO/PO direct ABEO to reset 10C673 lAW SO.SG-0001. RO/PO record Seismic Response Spectrum Analyzer lights on AR.ZZ-0011 Att. C4-1. RO/PO reset Seismic Response Spectrum Analyzer lAW SO.SG-0001. Crew determines a shutdown lAW 10.ZZ-0004 is required. Crew recognizes 10A403 bus loss by: => OHA E3-E2 4.16KV SYS INCOMING BRKR MALF OHA E3-F2 4.16KV FOR TO USS XFMER BRKR MALF OHA 03-E3 120VAC UPS TROUBLE Flashing TRIP lights for 10A403 Infeed breakers CRS implements AB.ZZ-0172.

ESG-NRC-S1 Page 9 of Rev: 00 IE dispatched to align AP to 'A' Core Spray and A & C RHR THEN: TRIGGER ET-11 to open AP-V044N047N041 CRS directs PO to complete AB.ZZ-0172 Subsequent Actions. PO ensures A SACS pump is in service. PO ensures B TACS Loop is in service. PO ensures A SSW pump is in service. PO determines A SSW Pump has failed to auto-start. PO starts A SSW pump as follows: PO places A SSW Pump in MAN. PO presses A SSW Pump START pb. PO ensures B Control Room HVAC Train is in service. PO directs RBEO to align keepfill to "A" Core Spray Loop and "A" and "C" RHR Loops. CRS recognize the following TIS applies 3.8.3.1.a.3.

a) Action a. applies (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to energize the channel). 3.8.1.1 Perform Power Distribution lineup within one hour. Page 10 of 24 TIS Rev: 00 Small Break LOCA: 20 minutes after the at the discretion of the Examiner, TRIGGER i. Crew recognizes LOCA condition:

OHA C6-B 1 "OLD SYSTEM ALARMffRBL" => RM11 9AX314 OLD FLOOR ORN FLOW alarm => RM 11 9AX317/318/320 OLD CCM alarms OHA 03-C3 "ORYWELL SUMP LEVEL HIILO" OHA A4-F5 "COMPUTER PT IN ALARM" OHA A 7 -E4 "ORYWELL PRESSURE HI/LO" => Rising Orywell Pressure on various indicators CRS implements => Condition Condition => Condition CRS implements 0001 => Condition RO/PO ensures drywell cooling maximized. Crew checks => Recirc pump seal parameters

=> SRV temperatures Based on the rate of drywell pressure rise (:::::10 minutes to 1.68#) some or all of these Conditions may not be entered. ESG-NRC-S1 Page 11 of Rev: 00 Aftershock/LOP/LOCA:

At the Lead Examiners discretion, PLAY the Earthquake Sound Effect (ifavailabfe) at medium volume for about 20 seconds OR ANNOUNCE "You feel motion then it stops" TRIGGER ET-5 (LOP/LOCA)

  • WHEN the Crew determines drywell pressure cannot be maintained below 1.5 psig, 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 SHUTDOWN
  • 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
  • Crew recognizes Loss of Offsite Power by: => OHA "STA SERVICE TRANSFORMER TROUBLE" for all transformers

=> TRIP indication for all 500 KV breakers => Flashing TRIP lights for all previously closed bus infeeds. Numerous OVLD/PWR FAIL lights. ESG-NRC-S1 Page 12 of Rev: 00 IF directed to start the 'B' THEN TRIGGER ET*7 REPORT 'B' EDG IF dispatched to investigate failure of 'D' EDGs to THEN REPORT 'D' EDG Lube Oil Low Shutdown alarm. There is on 'D' EDG room Crew recognizes failure of the A/B/D EDGs to start and load by: :::> Engine STOP lights :::> Output breaker TRIP lights OVLD/PWR lights on associated Channel components RO/PO attempt to start the A/BID EDGs. RO/PO close 'B' EDG output breaker. Crew starts the '8' EDG by EITHER: Pressing the '8' EDG START pushbutton in the Control Room, OR Directing an operator to locally start the '8' EDG, AND Closes '8' EDG output breaker. CRS implements AB.zZ-0135. Crew dispatches NEO and/or Maintenance to investigate failure of D EDG to start. Only 'B' EDG will start from the Control Room. 'C' EDG is not available due to the 10A403 bus lockout. Immediate Operator Action lAW AB.ZZ-0135 Immediate Operator Action lAW AB.ZZ-0135.

ESG-NRC-S1 Page 13 of Rev: 00 IF dispatched to investigate the

  • Crew dispatches NEO and/or failure of the 'A' EDG to THEN REPORT there is blown fuse on DC Circuit 3 the AC421 IE directed to start the using either local THEN REPORT it did not (AR.KJ-0001 Att. 37 IF dispatched to check SFR, and SDR relays for THEN 86 lockout relays are reset (AC422, elev 137') Blue buttons on SFR and SDR are out (de-energized) (AC421 elev 102') IE dispatched to determine status of HPCI, THEN REPORT HPCI is idle HPCI Aux oil pump is running. HV-F001 is open Oil in the floor surrounding the pump skid IF directed to open the for the HPCI Aux Oil THEN TRIGGER IE dispatched to RCIC THEN REPORT the device is Maintenance to investigate failure of 'A' EDG to start. Crew recognizes HPCI Oil line break problem by: HPCI Aux Oil Pump running => HV-F001 open => "HPCI INIT AND SEALED IN" light on => HPCI Governor valve closed HPCI Turbine Speed 0 rpm Crew dispatches NEO to investigate RCIC trip. ESG-NRC-S1 Page 14 of Rev: 00

!E directed to reset the RCIC Overspeed device, THEN TRIGGER ET-8. Crew resets Overspeed trip lAW SO.BD-0001. CRS directs injecting with 'B' SLC pump. RO/PO start the 'B' SLC pump. 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 Crew recognizes Supp Pool Level Above 78.5 In EOP entry condition by: => OHA B1-C3 "SUPPRESSION POOL LEVEL HI/LO" => Various Suppression Pool level indicators CRS recognize RPV level continues to lower and Emergency Depressurization is required. WHEN RPV water level reaches -129", TH EN CRS directs inhibiting ADS. Page 15 of 24 Only available injection source. Given the lowering RPV water level, and 'B' RHR being the only available RHR pump, the Crew may not place 'B' RHR in Suppression Pool cooling at this time. Given the LOP and the unavailability of HPCI and RCIC, there is nothing the Crew can do to lower Suppression Pool water level at this time.

Rev: 00

  • * *
  • IF directed to restore the 'A'
  • EDG to service, AND after level has been restored with 'B' EDG, THEN TRIGGER ET-12 AND REPORT the 'A' EDG has been successfully restarted.
  • *
  • RO/PO inhibit ADS AB.ZZ-0001 Att. BEFORE RPV water reaches THEN CRS directs opening ADS RO/PO open five ADS lAW AB.ZZ-0001 Att. WHEN RPV Compensated water level cannot be maintained above -185", THEN Before Compensated RPV water level is below 185", the Crew opens five SRVs to Emergency Depressurize the reactor and then restores RPV water level to above -185". Crew recognizes start of the EDG ;;;:-Diesel engine START ;;;:-Generator breaker light ;;;:-OVLD/PWR FAIL lights extinguished on associated channel loads CRS directs restoring PCIG to the SRVs. RO/PO restores PCIG to the SRVs lAW AB.ZZ-0001 Att.9. CRS directs placing the 'A' RHR pump in Drywell Spray as required by EOP-1 02. The restoration of the 'A' EDG makes the 'A' Core Spray Loop available for RPV water level control. ESG-NRC-S1 Page 16 of 24 Rev: 00 Termination Requirement:

The scenario should be terminated at the discretion of the Lead Examiner when: The reactor has been de pressurized RPV water level is being maintained above -129" Drywell Spray is initiated.

  • RO/PO places 'A' RHR pump in Drywell Spray lAW AB.lZ-0001.

ESG-NRC-S1 Page 17 of Rev: 00 A. TQ-M-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-M-101 Performance Tools and Verification Practices I. OP-M-1 01-111 Roles and Responsibilities of On Shift Personnel J. OP-M-1 01-111-1 004 Operations Standards K. OP-M-1 01-112-1 002 On-Line Risk Assessment L. OP-M-1 06-1 01-1 001 Event Response Guidelines M. OP-HC-108-106-1001 Equipment Operational Control N. OP-M-108-114 Post Transient Review O. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program P. HC.OP-AB.ZZ-0001 Transient Plant Conditions Q. HC.OP-AB.IC-0001 Control Rod R. HC.OP-AB.MISC-0001 Acts of Nature S. HC.OP-AB.ZZ-0172 Loss of 4.16KV Bus 10A403 C Channel T. HC.OP-AB.ZZ-0135 Station Blackout/Loss of Offsite Power/Diesel Generator Malfunction U. HC.OP-AB.ZZ-OOO Reactor Scram V. HC.OP-EO.ZZ-0101 RPV Control W. HC.OP-EO.ZZ-0102 Primary Containment Control X. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization Y. Strategies For Successful Transient Mitigation ESG-NRC-S1 Page 18 of 24 Rev: 00 ESG-NRC-S1! 1. Crew starts the is' EDG by Pressing the is' EDG START pushbutton in the Control OR Directing an operator to locally start the IS' EDG, AND Closes IS' EDG output breaker. KIA 2.0 Generic Knowledges and Abilities

2.1.8 Ability

to coordinate personnel activities outside of the control room RO 3.8 SRO KIA 295003 Partial or Complete Loss of A.C. M1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF M 1.02 Emergency generators RO 4.2 SRO M 1.03 Systems necessary to assure safe plant shutdown RO 4.4 SRO The 'A' RHR pump is not available because of failure of "N EDG. This leaves the '8' 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. RCIC is not able to maintain RPV level under the current LOCA conditions.

Energization of the 10A402 bus makes the '8' SLC pump available for injection which will prolong the time before adequate core cooling will be lost and Emergency Depressurization is required.

The unavailability of 10A401, 10A403 and 10A404 buses leaves limited injection sources available for core reflood following Emergency Depressurization.

Availability of the '8' RHR and Core Spray pumps will reduce the time the core is uncovered.

2. WHEN RPV Compensated water level cannot be maintained above -185", THEN Sefore RPV Compensated water level is below -185", the Crew opens five SRVs to Emergency Depressurize the reactor and then restores RPV water level to above -185", K/A 295031 Reactor Low Water EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER EA1.01 Low Pressure Coolant Injection RO: 4.4 SRO EA 1.06 Automatic depressurization system RO 4.4 SRO EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER EA2.04 Adequate core cooling RO 4.6 SRO When Reactor water level cannot be maintained above -185" with injection to the RPV, adequate core cooling cannot be assured (MSCRWL).

EOPs direct action to initiate emergency depressurization before RPV water level reaches this value if there are injection sources available.

To restore adequate core cooling, the Crew must Emergency Depressurize and restore level with low pressure ECCS. The combination of vital bus losses, and manually inhibiting ADS, prevents the ADS logic from completing to initiate an automatic blowdown.

Crew action is required.

The failure to control the ADS blowdown should be viewed as a procedure use issue. ESG-NRC-S1 Page 19 of Rev: 00


ESG-NRC-S1 100 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT YIN EVENT Loss Of Offsite PowerlSBO Internal Flooding Y LOCA Loss of 1 E AC/DC Buses 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 COMPONENr/TRAIN/SYSTEM THAT INCREASES CORE DAMAGE YIN KEY EQUIPMENT YIN KEY EQUIPMENT Y 1E 4.16KV Bus 120VAC 481 Inverter Hard Torus Vent Switchgear Room Cooler 1 E 125VDC Bus Y RCIC ___ SACS Loop SSW Ventilation

___ SSW Loop SSW Pump ___ AlBRHR RACS Heat Exchanger Y HPCI SLC ___ Core Spray Loop Torus DIW Vacuum Breakers Y EDG SACS Heat Exchanger OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR Y Emergency Depressurize RPV WIO High Pressure Emergency Venting of Primary Y Aligning RHR for Suppression Pool Restore Switchgear Control Plant via Remote Shutdown ___ Manually Start SW Cross-tie DC Charger to Portable Isolate SW Pipe Rupture in RACS Y Initiating LP ECCS with No High Pressure Injection Monitoring and Control of SACS heat Complete this evaluation form for each ESG. ESG-NRC-S1 Page 20 of 24 Rev: 00 Rx Power: 100% Work Week: B Risk Color: Green Activities Completed Last Shift: Tagged BP116 EHC pump for discharge line leak repair. Major Activities Next 12 Hours: Release BP116 after leak repaired.

Protected Equipment:

AP116 EHC pump Taqged Equipment:

BP116 EHC pump ESG-NRC-S1 Page 21 of 24 Rev: 00 EXAMINATION SCENARIO GUIDE REVI EW N ALiDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s).

Attach a separate copy of this form to each scenario rel1iewej . SELF-Cl L r:-t' (CHECK ESG-NRC-S1 REVIEWER: / &

The scenario has clearly stated objectives in the scenario.

2. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected a 0 (' 3. Each event description consists
  • The point in the scenario when it is to be initiated
  • The malfunction(s) that are entered to initiate the event
  • The symptoms/cues that will be visible to the crew
  • The expected operator actions (by shift position)
  • The event termination point The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred. The events are valid with regard to physics and thermodynamics.
5. (llr(j 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

rl!il 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

/lilt-8. If time compression techniques are used, scenario summary clearly so indicates.

a 1;7) 9. The simulator modeling is not altered. n4!-10. All crew competencies can be evaluated.

aS7I11. Appropriate reference materials are available (SOERs, LERs, etc.) --c::: Proper critical task methodology used lAW NRC procedures.

ESG-NRC-S1 Page 22 of Rev.: 00 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't} Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios.

Therefore, to complete this part of the review, the set of scenarios must be available.

The section below should be completed once per scenario set. ESG: NRC-51 ESG: SELF-CHECK Cu::.-;J-.

1. Total malfunctions inserted:

4-8/10-14 7 a 0.1: 2. Malfunctions that occur after EOP entry: 1-4/3-6 Z

3. Abnormal Events: 1-2/2-3 Ufi;}-' 4. Major Transients:

1-2/2-3 \ 6.J;r 5. EOPs used beyond primary scram response EOP: 1-3/3-5 'Z Q!!L 6. EOP Contingency Procedures used:

t Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes) 9 () tJ.!):. 8. EOP run time: 40-70% of scenario run time

9. Crew Critical Tasks: 2-5/5-8
10. Technical Specifications are exercised during the test 11. Events used in the two scenarios are not repeated (Only Applicable for an exam set) Comments:

ESG-NRC-S1 Page 23 of 24 Rev.: 00 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Crew Validation Rev: 00 Date Validated:

2 Validated with a 3 man crew from B Shift. Runtime 80 minutes. Validation Comments Disposition W/7////7////7//////////////7/////7//7//7////////////////7/////

The crew thought the scenario was pretty tough for a 3 man crew. Disagt!lEl.Re

..............m Crew Validation Rev: Date Validated: Validation Comments Disposition W/7//7//////7//7///////7///////7////7/7///7///////7///7/////////7/

ESG-NRC-S1 Page 24 of 24 Rev.: 00