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Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML12083A242
Person / Time
Site:	Hope Creek
Issue date:	03/05/2012
From:	Fish T H; Operations Branch I
To:	; Public Service Enterprise Group
	Jackson D E
Shared Package
ML113070699	List: IR 05000354/2012301; ML12061A285; ML12083A212; ML12083A223; ML12083A235; ML12083A242; ML12111A179; ML12111A188; ML12111A190; ML12111A200; ML12111A202; ML12172A046;
References
	TAC U01845
	Download: ML12083A242 (438)
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TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EO D JOB PERFORMANCE MEASURE Hope Creek Administrative Conduct Weekly Power Distribution Lineup 2630010201 305H-JPM.zZ024 REV #: 01 NOH05JPZZ24E D RO [[J SRO D

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:

EOD ROW IMPORTANCE FACTOR: STAD SROD 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: 0 SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 23

TQ-AA-106-0303 NAME: ____________________

_ 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 hours0.333 days 0.0476 weeks 0.011 months 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 lAW the ESO instructions. 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-ST.ZZ-0001, POWER DISTRIBUTION LINEUP -WEEKLY to Technical Specification 4.8.1.1.1.a Page 3 of 23 JPM: 22024 Rev: 01 SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. ELEMENT OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # NAME: DATE: EVAL StU Ttt-r\A-106-0303

________________

_ COMMENTS (Required for UNSAT CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue. CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: N/A

CUE Provide the operator with a copy of the partially completed procedure HC.OP-ST.ZZ-0001 (0). Operator reviews precautions and limitations.

Operator reviews precautions and limitations.

CUE IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.

N/A Operator determines beginning step of the procedure.

Operator determines correct beginning step to be 5.1. Page 4 of 23 JPM: ZZ024 Rev: 01 SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. 5.0 ELEMENT Power Distribution Lineup OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD N/A * # NAME: DATE: EVAL S/U Ttt-,.,.A-1 06-0303 COMMENTS (Required for UNSAT evaluati 5.1 LOG test start time in the Control Room IOg(5). 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

5.2 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: JOB PERFORMANCE MEASURE SYSTEM:

TASK: Conduct Weekly Power Distribution (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

J ENSURE that all prerequisites have Operator ensures that the been satisfied lAW Section 2.0 of this are 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. -IF asked, "No other testing maintenance is in progress that NA adversely affect the performance this Page 6 of 23

TQ-I"\A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup ("'Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSA T NO.

StU evaluation)

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

initials [TIS 4.16KV SWITCHGEAR 10A401 4.16KV SWITCHGEAR 10A402 4.16KV SWITCHGEAR 10A403 4.16KV SWITCHGEAR 10A404 OFFSITE TO Page 7 of 23

TQ-r\A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. ELEMENT 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.

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. ....... -_._....... __._....... (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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. Operator determines that this step is not required and marks step as N/A. Page 8 of 23

5.6 06-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTEM:

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

PERFORM Power Distribution Operator observes the breaker by completing Attachment positions, (and bus Voltage for 4.16KV busses) of those breakers in Attachment 2

4.16KV SWITCHGEAR 10A401 4.16KV SWITCHGEAR 10A402 4.16KV SWITCHGEAR 10A403 4.16KV SWITCHGEAR 10A404 OFFSITE TO ONSITE DISTRIBUTION The operator notes the positions/voltages on the attachment, enters SAT, and initials as the I performer. Page 9 of 23 TQ-J"\A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) 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 AND REQUIRED positions used to JUSTIFY its use in Section 2.1.4 of this surveillance, marks those Attachment 1 . UNSA T and informs the Examiner Note: See attached grading key. Operator initials the step. LOG test end time in Control -Log entry completed.

Operator initials the step. -SUBMIT this procedure to SM/CRS for review AND of Attachment 1 Page 10 of 23 TGt-",A-106-0303 JPM: Rev: ZZ024 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE:

________________

__ SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. CUE ELEMENT WHEN operator informs you the task is complete, OR the JPM has been terminated for (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL SJU COMMENTS (Required for UNSA T eva I 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".

N/A STOP TIME: Page 11 of23

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

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT Page 12 of 23

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Emergency Diesel Generator AG400 has a mechanical problem and is declared inoperable.

It is expected to return in 8 hours0.333 days 0.0476 weeks 0.011 months 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 lAW the ESO instructions. 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-ST.ZZ-0001, POWER DISTRIBUTION LINEUP -WEEKLY to satisfy Technical Specification 4.8.1.1.1.a only. Page 13 of 23

JOB PERFORMANCE SIMULATOR SETUP INI1"IALIZE the simulator to 100% power, ENSURE associated Schedule file open and ENSURE associated Events file 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 Page 14 of 23

JOB PERFORMANCE SIMULATOR SETUP Initial @Time Event . Action Description Page 15 of 23 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ024 Date Description Validation I ______-+_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 1/3112. Avg PSEG Internal Use Onlv HC.OP-ST.ZZ-0001 (Q) ATTACHMENT Page 6 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution Lineup (Continued)

SATI. EQUIPMENT NOMENCLATURE REQUIRED ACTUAL UNSAT PERF ! CHANNEL A 4.16KV SWGR 10A401 40101 ALTERNATE FEEDER BKR TO 10A401 OPEN OPEN SA T Initials 40103 10A401 FEED TO 10B450 CLOSED CLOSED SA T Initials i

40107 EDG AG400 OUTPUT BKR TO 10A401 OPEN SA T Initials 40108 NORMAL FEEDER BKR TO BUS 1 CLOSED SA T Initials CLOSED SAT Initials

4272 SAT Initials

EBUS CIRCLE ONE: CRIDS (A7061) 4245 -4370 Fluke 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 (Le., HI grid voltage and/or 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 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 Buses 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, 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 1 BX501: A321 0, A3487, A7076, A7071 Rev.1S PSEG Internal Use Only HC.OP-ST.ZZ-0001 (Q) ATTACHMENT Page INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution Lineup (Continued)

SATI EQUIPMENT NOMENCLATURE REQUIRED ACTUAL UNSAT PERF CHANNELC 4.16KV SWGR 10A403 40301 ALTERNATE FEEDER BKR TO 10A403 OPEN OPEN SA T Initials*

40303 10A403 FEED TO 10B470 CLOSED CLOSED SA T Initials 40307 EDG CG400 OUTPUT BKR TO 10A403 OPEN SA T Initials NORMAL FEEDER BKR TO BUS 10A403 SA T Initials 10A403 FEED TO 10B430 SA T Initials NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLASS 1 STATION SERVICE TRANSFORMER (SST) (1AX501 THE FOLLOWING READING (USE CRIDS CIRCLE ONE 4272 SA T Initials 4245 -4370 Fluke 121.14-125.0

The asterisk indi ptance 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).

[70038637]

(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 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.

[700387701 (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 paints 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 1 BX501: A3210, A3487, A7076, A7071 Rev.15 * *

PSEG Internal Use Only (Q) ATTACHMENT Page 12 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution Lineup (Continued)

SATI EQUIPMENT NOMENCLATURE REQUIRED ACTUAL UNSAT PERF CHANNEL B 4.16KV SWGR 10A402 40201 NORMAL FEEDER BKR TO 10A402 CLOSED CLOSED SAT Initials 40203 10A402 FEED TO 10B460 CLOSED CLOSED SAT Initials i 40207 EDG BG400 OUTPUT BKR TO 10A402 OPEN SAT Initials 40208 AL TERNATE FEEDER BKR TO BUS OPEN SAT Initials i 10A402 Initials A NORMAL 2 BUS ALIGNMENT

[(2) H STATION SERVICE THE FOLLOWING 4253 SAT Initials 4245 -4370 Fluke 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 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 (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 ENTER TIS 3.8.1.1.a Action Statement.

IF Bus Voltage 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 Buses 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, 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.1S * *

PSEG Internal Use Only HC.OP-ST.ZZ-0001 (Q) ATTACHMENT Page 15 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution Lineup (Continued)

SATI EQUIPMENT NOMENCLATURE REQUIRED ACTUAL UNSAT PERF CHANNEL 0 4.16KV SWGR 10A404 40401 NORMAL FEEDER BKR TO 10A404 CLOSED CLOSED SAT Initials*

40403 10A401 FEED TO 10B480 CLOSED CLOSED SAT Initials 40407 EDG AG400 OUTPUT BKR TO 10A404 OPEN OPEN SAT Initials' 40408 AL TERNATE FEEDER BKR TO BUS 10A404 OPEN SAT Initials, 10A401 FEED TO 108440 CLOSED SAT Initials A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV (1) 4.16 KV NON-1E BUS ON H STATION SERVICE TRANSFORMER (SST) )] WITH TAP CHANGER IN AUTO, RD THE FOLLOWING READING (USE INDICATION (FLUKE SECONDARY>>

4253 SAT Initials 4245 -4370 Fluke odel 121.14 -125.0

The cates 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 retumed 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 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 Buses 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, 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 HC.OP-ST.ZZ-0001 (a) ATTACHMENT Page 24 of INPLANT DATA POWER DISTRIBUTION LINEUP -1.0 Power Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SATI UNSAT PERF OFFSITE TO ONSITE DISTRIBUTION

+ BS4-5 13KV BUS SECTION 4-5 BKR CLOSED CLOSED SAT Initials

BS6-7 13KV BUS SECTION 6-7 BKR CLOSED OPEN Initials

2T60 STA XFMR T2 CIRCUIT SWITCHER CLOSED CLOSED SAT Initials*

4T60 STAXFMR T4 CIRCUIT SWITCHER CLOSED CLOSED SAT Initials

BS3-4 500KV BUS SECTION 3-4 BKR CLOSED CLOSED SAT Initials

BS6-5 500KV BUS SECTION 6-5 BKR CLOSED CLOSED SAT Initials

BS7-8 13KV BUS SECTION 7-8 BKR OPEN Initials

BS2-3 13KV BUS SECTION 2-3 BKR )Initials

BS1-2 13KV BUS SECTION 1-2 BKR Initials

BS9-0 13KV BUS SECTION 9-10 BKR Initials

1T60 STAXFMR T1 CIRCUIT SWITCH Initials

3T60 CLOSED CLOSED Initials*

BS1-3 CLOSED CLOSED SAT i Initials

BS5-1 CLOSED CLOSED SAT Initials

BS2-6 5 CLOSED CLOSED SAT Initials

AVAILABLE NOTE: The above alignment represents the normal lineup of the 500Kv/13.8Kv 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 feeds (10X 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 I F 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. Salem Unit 3 Turbine Generator is only required when in an extended A or B EDG outage. Rev.15 PSEG Internal Use HC.OP-ST.ZZ-0001 CQ} ATTACHMENT Page 2 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.

or 4.8.1.1.1.a and the test is considered:

2.1.1 SATISFACTORY

(All acceptance criteri 2.1.2 statement has been implemented.

DATE-TIME Rev.1S TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

,----. EO DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Administrative Complete The Daily Surveillance Logs 4010010201 30SH-JPM.ZZ016 REV #: 01 NOH05JPZZ16E D SRO Archie E. Faulkner DATE: 1/14/12 Instructor

<<K 'C fit; Ie.. DATE: , DATE: cntotlL: J/?D/J).t Training Department

STATION: Hope Creek JPM NUMBER: ZZ016 REV: 01 SYS"rEM: Administrative TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs ALTERNATE PATH: 0 KIA NUMBER: 2.1.18 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY:

RO SRO EOD ROCKJ STAD SROD 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: 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 18

TQ-AA-106-0303 NAME: 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 61-74 of Attachment 1a) lAW HC.OP-DL.ZZ-0026.

Page 3 of 18

3.1 JPM: Rev: 01 SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP NO. ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER Operator repeats back the Initiating START TIME: Operator obtains the correct procedure.

COMPLETE Attachment 1 (all subsections) daily. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. I WA Operator obtains procedure HC.OP-DL.ZZ-0026 Operator records readings for Items 61-74 of Attachment 1a for the Day Shift. Examiner Note: lAW the Initiating Cue, only Items 61-74 of Attachment 1a 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.

06-0303 NAME: DATE: COMMENTS* EVAL (Required for UNSAT # I S/U evaluati

Page 4 of 18

TCl-.--.A-106-0303 JPM: OPERATOR TRAINING PROGRAM NAME: Rev: 01 SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. PROVIDE Operator reading from Exhibit 1 for any missing or inoperable indicators IF in OP CON 4 or 5, THEN COMPLETE Attachment 2 as follows daily: COMPLETE Attachment 4 to perform surveillances required by Special Test Exceptions as necessary. ENTER the Operational and date on each page of the log the blanks COMPLETE the applicable subsections of Attachment 3 as directed by the SM/CRS to satisfy Surveillance Requirements which require accelerated surveillances due to conditions.

DATE: ________________

_JOB PERFORMANCE MEASURE (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluatio N/A Operator determines this step does not apply. Operator determines this step does not apply. Examiner Note: lAW the Initiating Cue, only Items of Attachment 1a are required.

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

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

Ttt-nA-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: Rev: 01 SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP NO. ELEMENT 3.6 COMPLETE all surveillances as indicated in each log. IF a Technical Specification Surveillance cannot be successfully completed OR is out-of-spec, THEN IMMEDIATELY NOTIFY the SM/CRS AND the Duty RO AND corrective action initiated shall be noted in the comments section. CUE Repeat back message from Operator on Item 65 deviation.

3.6.1 IF a work order is issued to repair an abnormal reading, THEN NOTE the work order number in the comment section. 3.6.2 IF an Action Statement Log Sheet is issued due to a failed surveillance, OR one is already issued that covers the failed surveillance, THEN NOTE the Action Statement Log Sheet Index Number in the comments section. DATE: ________________

_JOB PERFORMANCE MEASURE (*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluatio WHEN the deviation for Item 65 (RPV LEVEL 3) is recognized to exceed MAX DEVIATION of THEN Operator notifies CRS of unsatisfactory N/A Examiner Note: Since no work order number will be provided to the operator, this step will not apply. Examiner Note: Since no Action Statement Log Sheet Index Number will be provided to the operator, this step will not apply. Page 6 of 18

TQ-AA-106-0303 JPM: OPERATOR TRAINING PROGRAM NAME: Rev: 01 SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. IF a surveillance item is out-of-spec or not successfully completed, THEN REFER to step 3.11 for T/S reference numbers and notes. IF performing a channel check requires a comparison THEN RECORD the between the high and low value trip The trip status is indicated by the Note: following: The trip light for instruments supplied with trip lights The a/arm(s) AND/OR automatic actions for instruments not supplied by trip lights. DATE: ________________

_JOB PERFORMANCE MEASURE {*Denotes a Critical COMMENTS* {#Denotes a Sequential Step} EVAL (Required for UNSAT STANDARD # S/U evaluation WHEN the deviation for Item 65 (RPV LEVEL 3) is recognized to exceed the MAX DEVIATION of 4, THEN Operator refers to Step 3.11 for Item 65 T/S reference numbers and notes. Operator performs channels checks on

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

Page 7 of 18

--3.8 JPM: ZZ016 Rev: 01 SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period: OBTAIN a blank copy of the respective sheet, COMPLETE surveillance, (including time and date) ANNOTATE on the sheet and in comments section, as necessary, why the additional check was performed ATTACH sheet to existing daily log package.

06-0303 NAME: ________________

_OPERATOR TRAINING PROGRAM DATE: ________________

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

Operator determines this step does not apply. Page 8 of 18 I JPM: ZZ016 Rev: 01 Administrative TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. COMPLY with the requirements regarding log numbers followed by "at sign" IF a surveillance log item number DOES NOT have an "at sign" (@)following it, THEN, instrument(s) or methods other than that designated in the log item may be used to satisfy that surveillance requirement as long as an assessment of the equivalency of the alternative instrumenUmethod has been made and the results have been noted in the comments section. An example of what constitutes an "acceptable" equivalency review can be found under Activity 0140 of Order 70023885. IF a surveillance log item number has an "at sign" (@) following it THEN, ONLY the instrument(s) specified in the log item may be used to satisfy that surveillance requirement, except that I&C can take voltage readings on the instrument(s) and the results compared before declaring the system inoperable.

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: TQ-MA-106-0303

________________

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

Operator takes all readings from the identified instrument.

Operator takes all readings from the identified instrument.

Page 9 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 COMMENTS (Required for UNSA T evaluation S/U Ill!eMr------------II 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 N/A operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: Page 10 of 18 I HC.OP-DL.ZZ

.6(Q) Surveillance Log -Control Room -Day Shift Operational Condition Date Today's Date , OPER PANEL 10C609 PANEL 10C611 INST MAX ACCEPT ABLE LIMITS ITEM SURVEILLANCE COND !NST VALUE INST VALUE INST VALUE INST VALUE DEVIATION DEVIATION MIN NORM MAX , , I "" 61@ RPV PRESSURE 1,2 N678A 1010 N678C 1010 N678S 980 N678D 980 30 100 --1037 NO 62@ DRYWELL 1,2;3 N650A 0.5 N650C 0.4 N650a 0.3 N650D 0.4 0.2 1 ----1.68 NOTE 29. _..., 63@ CONDENSER VACUUM 1,2,3 N675A 27.0 N675C 26.5 N675a 26.5 N675D 27.0 0.5 2.5 8.5 --NO 64@' MSL PRESSURE 1 N676A 950 N676C 950 N676S 940 N676D 960 ...2Q. 80 756 ._---NO _. ", 65@ RPVLEVEL3 1,2,3 N680A 42 N680C 34 N680B 34 N680D 35 i( 8 ) 4 12.5 --66@ NORTH SDV LEVEL 1,2;5 N/A N/A N601C 0 N/A N/A N601D 0 --0-10 ----72 , " (NOTE 61) 67@ SOUTH SDV LEVEL 1,2,5 N601A 0 N/A N/A N6Dia 0 N/A N/A 0 --' ---72 {;,,10 , ' ..68@ MSLAFLOW "'. 1,2,3 N686A 79 Ne86C 80 N686B 79 N686D 69 it,*!!,!,!!,*

162.. 8 69@ MSL S FLOW 1,2,3 N687A 79 N6S7C 75 N687S 68 N687D 80 UI ilk

',,--162.8 70@ MSLCFLOW 1,2,3 N688A 72 N688C 78 N688a 68 N688D 77 i ........ ,10* ... >*'*,;i 18"';'" ---162.8 71@ MSLD FLOW 1,2,3 N689A 81 N689C 78 N689B 75 N689D 79 6'\,!I;", 18 ----162.8 -6 "',

72@ RPV LEVEL 2 (NOTE 27 ..) 1,2,3,* N681A 30 30 N6B1S 35 15 -38 NO-, NOTE29, ,'" @ RPVLEVEL 1 1,2,3 N684A N/A N684C N/A N684a N/A N684D", _N/,A,<l,ll, NlA -129 ---NO 73@ RWCU dF (NOTE 56., 57.) 1,2,3 XR11497 0 N/A ',". NfA I', NfA N/A XR11499 o 0 20 -----56 " ", " " RM-11 ..

L::!-MSL RADIATION 1.,2.3 9RX509 9RX511 2.7 (NOTE 53.) --NO (NOTES 53 .., 54 .. ) NOTE 55.; NORM *______*. H'" .. -.:--;--":":':._, ... ,-,";"-':":",

..

......_u._ .....

---..... _.----_ , .. .-. --,.. ---... ..-..._ NOTE ALSO REQUIRED WHEN SECONDARY REQUIRED TO BE IN EFFECT lAW TIS:, {7002177S], . NOTE RM-11 10 MINUTE AVERAGE SHOULD BE USED TO OBTAIN CHANNEL VALUES. MSL RADIATION MAX DEVIATION WITH THE H2 INJECTION SYS OUT OF SERVICE IS 20. WITH THE H2 INJECTION SYS IN SERVICE, MAX DEVIATION CALCULATED BY ADDING OPERABLE CHANNEL VALUES, DIVIDING RESULT BYNUM8ER OF 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.

Nl;.IMAC READINGS SHOULD BE TAKEN 3 -4 SECONDS INTO THE CPU SELF-TEST (PRESS ANY KEY; PRESS "ETC" KEY; PRESS "DISPLAY TEST STATUS" WHENARROW14AS 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

'fc.", NOTE IF RM-11 IS AVAILABLE, AND. WHENEVER RX POWER IS ABOVE 94% RTP AND CONSTANT FOR THE PREVIOUS 2 HOURS (NO TRANSIENT IN PROGRESS).

PERFORM MSL AVERAGE FULL POWER BACKGROUND CHECK BELOW. FORANYVAKUE OF c < 0.834, DECLARE THERRESPONDING MSLRMS INOPERABLE.

IF ANY VALUE FOR c IS < 0.85 OR> 1.2 C;!: 20%) THEN ARE-EVALUATION OF THE 3X NORMAL SETPOINT MAY BE DESIRED USING HC.SE-GP.SP-0001(Q).

NOTIFY 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 (NQ,,;rRANSIENT IN NOTE 55.: DURING OPERATIONAL CONDITIONS 1 AND 2 WITH MECHANllfA't*VACUUM PUMP<s"lN-SERVICE AND ANY MAIN STEAM LINE NOT ISOLATED, THE MSL RADIATION CHANNEL CHECK BETWEEN THE ALPHA AND BRAVO CHANNELS (9RX509/9RX51 0, K61 OAIK61 DB) ALSO MECHANICAL VACUUM PUMP TRIP INSTRUMENTATION CHANNEL CHECK lAW TIS 4.3.1 O.a. NOTE 56.:INITIATE NOTIFICATION WHEN DEVIATION BETWEEN CHANNEli!tJA'jIIlD

[)REACHES 9 GPM TO ENSURE THAT THE PROBLEM CAUSING THE DEVIATION IS CORRECTED.

NOTE 57.:IF LE!>KDETECTION MONITOR INDICATES

"<<<" FOR FLOW, UNDER "NORM" TO OBTAIN (MAY RESULT IN,NEGATIVE VALUE MSL AVERAGE FULL POWER BACKGROUND MSLRMSA MSLRMS B MSLRMS C MSLRMS D a RM-11 LAST HOURLY AVERAGE 37.5 38.5 35.8 b RM-11 HI SETPOINT 130 125 121 c c =a I b x 3 (RATIO OF ACTUAL TO BASELINE AFPB) 0.850 .865 .924 .887 .856 Page 11 of 18

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

RESPONSE:

--...------..

--...--..

RESULT: SAT UNSAT QUESTION:

.. RESPONSE:

RESULT: SAT UNSAT Page 12 of 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, 1 OC611 AND MSL Radiation (Items 61-74 of Attachment 1a) lAW HC.OP-DL.ZZ-0026.

Page 13 of 18

JOB PERFORMANCE MEASURE Surveillance Log -Control Room -Day Shift Operational Condition Date , OPER PANEL 10C609 PANEL 10C611 INST MAX ACCEPTABLE LIMITS ITEM SURVEILLANCE COND INST VALUE INST VALUE INST VALUE INST VALUE DEVIATION DEVIATION MIN NORM MAX ..--'--, 61@ RPVPRESSURE 1,2 N678A N678C N6788 100 1037 NO 62@ DRYWELLPRESSURE 1,2,3 N650A N650C N650B N650D 1 -----1.68 .. .... NOTE 29 2.5 .....63@ CONDENSER VACUUM 1,2,3 N675A N675C N675B 8.5 -----NO 64@ MSL PRESSURE 1 N676A N676C N676B N676D SO 756 -----4 " 65@ RPVLEVEL3 1.2,3 N680A N680C N6BOB 12:5 ------NO 66@ NORTH SOV LEVEL 1,2,5 N/A N/A N601C N/A N/A N601D 10 ---72 (NOTE 67@ SOUTHSDV LEVEL 1.2.5 N60iA N/A NfA N601B N/A N/A 10 -----72 .. .. , (NOTE61) . 68@ MSLAFLOW 1,2.3 N68SA N686C N686B N686D 18 -----' 162.8 69@ MSLB FLOW 1,2,3 N687A N687C N687B N687D 18 -----162.8 70@ MSLCFLOW 1,2,3 N6SSA N688C N68SB N68SD 18 ----162.8 71@ MSLDFLOW 1,2,3 N689A N689C N689B N689D ---18 ---162.S NO ,72@ RPV, LEVEL 2 (NOTE 1,2,3: N681A N681S N681D 15 ,38 -----NO NOTE 29. ..'..' @ RPVLEVEL 1 1,2,3 N684A N/A N684C N/A N684S N/A N684D N/A N/A N/A -129 ----73@ I" RWCU dF (NOTE 56., 57.) 1,2,3 XR11497 N/A N/A N/A NfA XR11499 20 ---56 * ... "'. , RM-11 74@ MSL RADIATION 9RX509 9RX51 0 9RX511 ---NO Ii (NOTE 53.) I(NOTES 53 .. , 54 .. )

NOTE 55 .. I NOTE: FOR ANY INSTRUMENT FOUND TRIPPED. PLACE A 'T' IN THE VALUE BLOCK ALONG WITH THE INSTRUMENT VALUE AND RECORD "YES" IN THE INST TRIPPED COLUMN. FOR NON-INDICATING TRiP UNiTS, CIRCLE THE TRIP UNIT DESIGNATOR IN RED AND RECORD "YES"!N THE !NST 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 (0) -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. [70021778]

NOTE 53. RM-1110 MINUTE AVERAGE SHOULD BE USED TO OBTAIN CHANNEL VALUES. MSL RADIATION MAX DEVIATION WITH THE H2 INJECTION 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 K610A, K61 DB, K610C, OR K610D (NUMAC) SHOULD BE USED AT PANEL 10C635/10C636.

NUMAC READINGS SHOULD BE TAKEN 3 -4 SECONDS INTO THE CPU (PRESS ANY'" KEY; PRESS "ETC" ... KEY; PRESS "DISPLAY TEST STATUS" ... KEY) WHEN ARROW HAS BEEN AT THE "CPU MODULE" LOCATION FOR 3 -4 SECONDS. TO RESTORE NUMAC DISPLAY EXIT'" KEY; PRESS ETC'" KEY; PRESS DISPLAY OFF'" KEY).

NOTE 54.: IF RM-11 IS AVAILABLE, AND, WHENEVER RX POWER IS ABOVE 94% RTP AND HAS BEEN 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 CORRESPONDING MSLRMS INOPERABLE.

IF ANY VALUE FOR ciS < 0,85 OR > 1.2 (:I: 20%) THEN A RE-EVALUATION OF THE 3X NORMAL SETPOINT MAY BE DESIRED USING HC.SE-GP.SP-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 ALPHA AND BRAVO CHANNELS (9RX509/9RX510, K61 OA/K61 OB) ALSO SA TIS FIES 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.

U,...,'-'L...,..,f"-"" .. '*".'..I'1 ... ,'_" ........ -_.-..........

". .....u ...*...... _ ....... , ....._ ... 'I, ....................................... , *. " ...... " ........ _ .... ...,.w..... __.....

...............

,........ ,'-..... ...............

- .** _........ ,., .......... MSl AVERAGE FULL POWER BACKGROUND CHECK MIN MSLRMSA MSLRMSB MSLRMSC MSLRMS D RM-11 LAST HOURLY AVERAGE --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, Put Simulator in COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Page 15 of 18

JOB PERFORMANCE SIMULATOR SETUP None None None None None None None None None None Insert malfunction RP18A to 43.00 Insert malfunction RM9509 Insert malfunction RM9510 Insert malfunction RM9511

Insert malfunction RM9512 to 36.80000 RPS Level Xmitter LT-N080A Failure 9RX509, MSL 'A' -Main Steam Line ChanA 9RX510. MSL 'B' -Main Steam Line Chan B 9RX511. MSL 'C' -Main Steam Line Chan C 9RX512, MSL 'D' -Main Steam Line . Chan D Page 16 of 18 1 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ016 Date Description Reference procedure change only. No changes to actions. No TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EOD DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Reactor Recirculation Perform a Reactor Recirculation Pump Quick Restart 2020160101 305H-JPM.ZZ011 REV#: 01 NOH05JPZZ11 E D RO []] STAD SRO Archie E. Faulkner DATE: 1/14/12 Instructor DATE: DATE: }/Ig//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: KIA NUMBER: 2.2.40 D APPLICABILITY:

EOD RO[]] IMPORTANCE FACTOR: STAD SROD 3.4 RO 4.7 SRO 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: 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 16

TQ-AA-106-0303 NAME: DATE: SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 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 3 of 16

TCot-",A-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 CUE PROVIDE the operator the initiating cue. 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.

G.12 ENSURE Differential Temperature requirements are met by completing Attachment

2. [TIS 4.4.1.4] (*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # I S/U Operator repeats back initiating cue. I N/A Operator obtains procedure HC.OP-AB.RPV-0003.

Operator determines correct beginning step to be G.12. Operator obtains Attachment Page 4 of 16 TQ-#"\A*106-0303 NAME: ________________

_JPM: OPERATOR TRAINING PROGRAM DATE: ________________

_Rev: 01 JOB PERFORMANCE SYSTEM: Reactor TASK: Perform a Reactor Recirculation Pump Quick (*Denotes a Critical Step) * (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

StU evaluation) ..... ** "....

Attachment .. I <

... ....*. >**". -REACTOR VESSEL TO BOTTOM 1.0 HEAD DRAIN LINE DIFFERENTIAL NA TEMPERATURE CRITERIA Rx Pressure Vessel Steam Coolant Saturation Temperature. Operator reads Note 1 . Pressure and Steam Tables) (Note 1) Operator determines RPV pressure 885 psig. (900 psia) Operator determines Steam space

Coolant Saturation Temperature to be 900 psi a = 532 degF (Steam Tables) Operator records value in space provided on Attachment 1 . ---_...... ...... -_-.Page 5 of 16

1.2 JPM: ZZ011 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)

EVAL (Required for UNSAT NO. STANDARD # StU evaluation)

Steam Table as part of this Note 1 attachment may be utilized determine temperature rounding numbers in a conservative For a more accurate conversion from pressure to temperature a detailed set of steam tables should Bottom Head Drain Temperature. (Note 2)

Operator accesses CRIDS terminal.

Point A2942) -RWCU Flow required for accurate Note 2 Bottom Head Drain Coolant Operator reads Note 2.Temperature indication.

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-",A-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 1.3 < 145°F between Rx Pressure Vessel Steam Space Coolant AND Bottom Head Drain Line Coolant (A B). [TIS 4.4.1.4J 1.4 Time Readings taken: 2.0 REACTOR VESSEL TO RECIRCULATION LOOP DIFFERENTIAL TEMPERATURE CRITERIA.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator subtracts value of step 1.2 from value of step 1.1. and determines value of 65 degF +/- 1 F. Operator records value in space provided.

Operator records current time in space provided.

NA COMMENTS* EVAL (Required for UNSA T # S/U evaluation)

--* Page 7 of 16 I

--2.1 TQ-AA*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* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

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

OR above 400 0 F -CRIDS pOints and A222 for A loop (A223 and for 8 loop). IF below 400°F AND 650-831 not available, THEN have I&C obtain temperatures using ohm values (reference RTD values to calibration data in using

-' Page 8 of 16

2.2 JPM: 22011 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 01 JOB PERFORMANCE SYSTEM: Reactor TASK: Perform a Reactor Recirculation Pump Quick (*Denotes a Critical Step) COMMENTS STEP

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

Operator determines Idle Recirc Loop Temp for A Loop is above 400 F. Operator obtains value of 510 degF from CRIDS point A221 or A222. r Temperature of coolant in the Pressure Vessel. (RX Pressure Operator reads Note 1.Steam Tables) (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..nA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 SYSTEM: TASK: 2.3 2.4 CUE JOB PERFORMANCE MEASURE Reactor Recirculation Perform a Reactor Recirculation Pump Quick Restart 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: _____ ENSURE Differential Temperature requirements are met by completing Attachment

2. [TIS 4.4.1.4] 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: (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator determines differential temp < 50 Examiner Actual value is 22 degF .:t 1Operator records current time in Operator initials step G.12. NIA DATE: ________________* #

EVAL StU *

COMMENTS (Required for UNSAT Page 10 of 16

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

RESPONSE:

RESULT: SAT lINSAT 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 PERFORMANCE 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:

Event Page 13 of 16

JOB PERFORMANCE SIMULATOR SETUP Page 14 of 16 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ011 '-R-e-v-#-rr i Required?

1 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 :

STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: ALTERNATE PATH: APPLICABILITY:

.----, EO DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Administrative Respond To An Abnormal Release Of Gaseous Radioactivity

-Calculate Noble Gas Release Release Rates 4000270401 305H-JPM.zZ019 REV #:

D RO [RJ ST A '------' SRO Archie E. Faulkner DATE: 1/14/12 Instructor L 1!r!:L-e-11'Cft DATE: DATE:

J/loTraining Department

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

-Calculate Noble Gas Release Release Rates ALTERNATE KIA NUMBER: 295938 EA 1.01 APPLICABILITY:

EOD ROW IMPORTANCE FACTOR: STAD SROD 3.9 RO 4.2 SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0004 Rev. 5 HC.OP-DL.ZZ-0026 Rev. 128 TOOLS, EQUIPMENT AND PROCEDURES:

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

EVALUATOR'S DATE: Page 2 of 13

TQ*AA*106*0303 NAME: DATE: Adm inistrative 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 channel9AX300 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 3 of 13

TQ-I-\A-106-0303 JPM: OPERATOR TRAINING 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 (*Denotes a Critical Step) I COMMENTS STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

Stu evaluation PROVIDE the operator the initiating Operator repeats back initiating cue. cue. ENTER START TIME Operator repeats back the Coo: I START TIME: Operator obtains the correct Operator obtains procedure.

Operator determines beginning step Operator determines correct of the procedure.

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

JPM: ZZ019 OPERATOR TRAINING PROGRAM Rev: 01 JOB PERFORMANCE MEASURE DATE: ________SYSTEM:

TASK: Respond To An Abnormal Release Of Gaseous Radioactivity

-Calculate Noble Gas Release Release (*Denotes a Critical Step) STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation) 1E the effluent (!-ICi/sec) channel on the RM-11 is NOT operating for a specific plant vent, CALCULATE the Noble Gas release rate for that vent using the

_. *

472 = Plant Vent Exh IJCi/sec (n.g.) !-ICi/cc (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 plant 472 -The conversion factor in units of 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-DL.ZZ-0026 (provided).

49613.9 CFM ....... L Page 5 of 13 TQ*nA-106-0303 JPM: ZZ019 OPERATOR TRAINING 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 STEP ELEMENT NO. 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) I

COMMENTS (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD StU# Operator calculates the NPV Noble Gas release Calculated Value 3.65E-7IJCi/cc

49613.9 CFM

472 =8.547 uCi/sec (+ 0.5} N/A Page 6 of 13

JOB PERFORMANCE MEASURE OPERATOR TRAINING EVALUATOR FOLLOWUP QUESTION 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 HC.OP-DL.ZZ-0026(Q)

JOB PERFORMANCE MEASURE ATTACHMENT 3u Radioactive Gaseous Effluent Monitoring (North Plant Vent) TIS 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 Page 1 ofl 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 hours0.125 days 0.0179 weeks 0.00411 months to ensure that the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 BeGS DATE: Today's Date Location Auxffllrb/Radwaste PARAMETER NORM NOW COMMENTS SOLID RADW ASTE EXH FAN A318 17,000 17358 -----1----

-........j---

-+---+--SOLID RADWASTE EXH FAN 8318 17,000 17163 CHEMLAB EXH r--------------j-----CHEMLABEXH OFFGAS 10022 45.9TOTAL FLOW 49613.9 I I ESTIMATED TOTAL FLOW REPORTED TO RAD PRO (YES) Yes

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

Initial 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 ET# Event code: I I

Description:

I I Event code:

I I 1 Event code:

I I Page 10 of 13 I

JOB PERFORMANCE SIMULATOR SETUP Action Description None None Insert malfunction RM9590 to 0.00000 9RX590, NPV EFF -North Plant Vent Noble Gas Effluent None None Insert malfunction RM9591 to 0.00000 9RX591 , NPV HIGH -North Plant VentH Noble Gas None None Insert malfunction RM9602 to 3.65E-7 9RX602, NPV LOW -North Plant Vent Range Noble Gas None None Insert malfunction RM9603 to 0.00000 9RX603, NPV MID -North Plant Vent Mid Range Noble Gas None None Insert malfunction CC03 SPDS CRT failure . Event Action Description Page 11 of 13 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ019 I Rev# Date Description Validation Required?

1 1/14/12 Converted JPM 22019 to new JPM format. Since Critical JPM y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted. JPM Modified values for new results. Validation performed with I 2 ROs on 1/3/12. Avg completion time was 10 minutes. I TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EO DEVELOPED BY: !/ REVIEWED BY:\., APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Administrative Perform On-Line Risk Controls Evaluation H303000015 305H-JPM.ZZ045 REV #: 02 NOH05JPZZ45E D RO STA SRO [KJ Steve Dennis DATE: 2/8/12 Instructor DATE:

DATE: 9?tcru: l.\..lls",,,\

Training Department

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

RO SRO EoD RoD STAD SROCK] EVALUATION SETTING/METHO D: Classroom/Perform

REFERENCES:

WC-HC-105 M-103-1 TOOLS, EQUIPMENT AND PROCEDURES:

WC-HC-105 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 SIGNATURE:

DATE: Page 2 of 15

NAME: DATE: SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation TASK NUMBER: H303000015 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 to vent the transmitter and process line using valves: 1-CE-V9942 1-CE-V9943 1-CE-V9941 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: "Vent CE-FISL-3597" 11. The WO number is "12345678" 12. Work has been determined not to be an IPA lAW HU-AA-1211 INITIATING CUE: You are directed to: lAW WC-HC-1 05, Work Activity Risk Management, Step 4.2.3.2, 1) Assign and document a Production Risk level 2) Complete the Production Risk Evaluation Data Sheet -Exhibit 5, Page 1. Page 3 of 15 JPM: ZZ045 Rev: 02 SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation STEP NO. ELEMENT OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # I NAME: DATE: EVAL StU TQ-r\A-106-0303

________________

_ COMMENTS (Required for UNSAT eval CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue. CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: I N/A Operator obtains the correct procedure.

Operator obtains procedure 105. Operator determines beginning step of the procedure.

Operator determines correct beginning step to be 4.2. WC::HC-105WORK ACTIVITY RISK MANAGEMENT" Classify the risk (Work Activity Owner) Page 4 of 15

TQ-rtA-106-0303 NAME: ________________

__JPM: ZZ045 OPERATOR TRAINING PROGRAM DATE: ________________

__Rev: 02 JOB PERFORMANCE SYSTEM:

TASK' Perform On-Line Risk Controls

(*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) Review the activity against the defined Medium, High and Very High Operator reviews Exhibit 1 risk activities listed in Exhibit 1, Screened Work Activities for Prescreened Work Activities.

Compliance and Production 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 Page 1 of 4 Production Risk Evaluation Data Operator obtains task description from Description of Task: Initial Conditions sheet. Operator fills in "Isolate CE-FISL-3597." Operator obtains WO number from WONo: Initial Conditions sheet. Operator fills in "12345678" Page 5 of 15 JPM: ZZ045 Rev: 02 SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation STEP ELEMENT NO. 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.

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

Y N Ttc-I"'\A-106-0303 NAME: ________________

__OPERATOR TRAINING PROGRAM DATE: ________________

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

Operator determines this work is NOT within a WCD boundry.

Operator checks YES. Page 6 of 15 TQ-I"'\A-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 02 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 StU COMMENTS (Required for UNSAT evaluation)

I If question 1 above is answered Yes, then continue at Question 2. 2. Could the activity cause equipment

actuations that could cause a loss of planned generation?

Operator checks YES. Y N 3. Does the activity involve instrument, fuse, circuit board removal/installations that could cause a loss of planned generation?

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

Operator checks NO. Y N Page 7 of 15

JPM: ZZ045 Rev: 02 SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation STEP ELEMENT NO. Does the activity pressurization of common lines that could cause a loss planned Y N Does the activity involve placing of jumpers or disconnection of "daisy chains" that could cause a loss of planned generation?

Y N Could the activity cause vibration near 7. vibration sensitive equipment that could cause a loss of planned generation?

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

Y N TQ-l"\A-106*0303 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # stu evaluation)

Operator checks YES. Operator checks NO. Operator checks NO. Operator checks NO. Page 8 of 15 I

06-0303 NAME: ________________

__JPM: ZZ045 OPERATOR TRAINING PROGRAM DATE: ________________

__Rev: 02 JOB PERFORMANCE SYSTEM:

TASK' Perform On-Line Risk Controls

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

During the activity, could a single 9. human error or omission cause a of planned Operator checks Y Is the activity a non-routine activity the switchyard? Y N Operator checks If any question 2 through 10 answered YES, then include completed form in a sub operation in Operator determines the activity is the work order. The activity is a production Production Risk

-Performed By: Operator signs in Performed By: space. Production Risk? Y

Operator checks YES. '---

Page 9 of 15 TQ-AA-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 02 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 stu COMMENTS (Required for UNSA T eval 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 N/A operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: Page 10 of 15 TQ-AA-106-0303 JOB PERFORMANCE MEASURE WC-HC-105 Revision 1 Page 32 of 41 Page 'I or Production Risk Evaluation Description ofTasJt: Isolate CE-FISL-3597 WO No.: __

_____ WOfiI; ael.ivities that are entirely bounded and contained within a Wed bound.ary irpuding Worker Blcx:king Tags and are not the same on llie Production Risk System Matrix cause relay or component:

acruation, . other mom alarms orposifion Production Risk Activity 2 through 10 is answered YES, then include this oompletw form in a SI.Ib operation lIle wmk order. The actidy is a Production Risk Periom1ed 8y: 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 ,---.J 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-3597 is reading erratically in the field. The 12 Hour Maintenance Supervisor wants to vent the transmitter and process line using valves: a.1-CE-V9942 b.1-CE-V9943 c.1-CE-V9941 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: "Vent CE-FISL-3597" 11. The WO nllmber is "12345678" 12. Work has been determined not to be an IPA lAW HU-AA-1211 INITIATING CUE: You are directed to: lAW WC-HC-105, Work Activity Risk Management, Step 4.2.3.2, 1) Assign and document a Production Risk level 2) Complete the Production Risk Evaluation Data Sheet -Exhibit 5, Page 1. Page 13 of 15 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ045 Date Validation I

11/7/11 New Admin JPM. Validation required.

Validated with 2 SROs. Y Validated avg time 20 minutes. 1 214/12

Revised initiating Cue 2 2/8/12 Revised initiating cue and actual isolation points for work being I TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EOD DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Conduct of Operations Complete The Daily Surveillance Logs 4010010201 305H-JPM.ZZ017 REV #: 02 ***NRC ADMIN JPM SRO D RO LJ STA D SRO [KJ Archie Faulkner DATE: 1/14/12 Instructor DATE: I j tr/;2 DATE: Training Department I/Ir

STATION: Hope Creek JPM NUMBER: ZZ017 REV: 02 SYSTEM: Conduct of Operations TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs ALTERNATE PATH: D KIA NUMBER: 2.1.18 APPLICABILITY:

EOD ROO IMPORTANCE FACTOR: STAD SROCK] 3.6 RO 3.8 SRO EVALUATION SETTING/METHOD:

Classroom/Perform

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: 7 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 12

DATE: SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 INITIAL CONDrnONS:

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. INITIA1"ING 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 JPM: ZZ017 Rev: 02 SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. CUE PROVIDE the operator the initiating cue AND a paper copy of HC.OP-DL.ZZ-0026{Q).

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: Operator determines beginning step of the procedure.

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. * # NAME: DATE: EVAL S/U TQ*",A-106-0303 COMMENTS (Required for UNSAT eva I N/A Operator determines correct beginning step to be 2.1. Page 4 of 12 JPM: Rev: 02 SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs STEP NO. ELEMENT 2.1 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):

2.1.1 The SM/CRS shall implement the log at the beginning of each day by completing , Section A; Log Initiation, listing those Attachments that require performance due to present conditions.

Also, the present Operational Condition shall be listed. OPERATOR TRAINING JOB PERFORMANCE (*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.

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 TIS 4.7.3 due to current River Water level. Operator checks Attachment 3k on Attachment 1 Section A Log Initiation.

Page 5 of 12 NAME: DATE: TQ-i"\A-106-0303

________________

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

I I I I * * *

--JPM: 2Z017 Rev: 02 SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD 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 SPY RMS Inoperable.

Operator checks Attachment 3t on Attachment 1 Section A Log Initiation.

Operator places a "1" in the Operational Condition blank. Operator determines Attachment 3z is required for tracking purposes Operator checks Attachment 3z on Attachment 1 Section A Log Initiation.

TQ-AA-106-0303 NAME: DATE: ________________

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

I *

I ---_._..... Page 6 of 12

2.1 JPM: ZZ017 Rev: 02 SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs STEP ELEMENT NO. 2.1.1 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. 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: OPERATOR TRAINING JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator checks Attachment 5 on Attachment 1 Section A Log Initiation.

Examiner Note: Although not specifically required by the current conditions, Attachment 5 is typically used each day to track surveillance procedures and would be needed the first time a surveillance procedure with an action time is actually logged on. N/A TQ-MA-106-0303 NAME: DATE: ________________

__ COMMENTS* EVAL (Required for UNSAT # I Stu eva I 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 Page 1 of 1 Surveillance Log Date T odays Date LOG INITIATION 1.0perational Condition 1 2.Check (,/') Attachments to be performed 1 ,/' 3c 3g 3m,/' 3s 3w 2 3d 3h,/' 3p 3t,/' 3x 3e 3j 3q 3u 3y B. LOG

., 3r 3v Ensure compliance with TIS by using TIS reference numbers and surveillance item note(s), as any log item(s) requiring additional action. \) Operators signature below ctio ttachment 1 and any Attachment checked comp Attachment 1a V

Control RoomK$

_____Attachment 1 Auxiliary Bldg ___"______________

_ Attachment 1 c Reactor Bldg Attachment 1 d Turbine Bldg MID Signature below indicates review of all required attachments checked

(,/') above has been completed, and approved for compliance with TIS requirements.

Day (Review Before Eve (Review Before 2100) Mid (Review Before 0500) SM/CRS SM/CRS LOG COMPLETION 1.0perational Condition Check (,/') Attachments that have been performed 3c 3g 3m 3s 3w 4a 3d 3h 3p 3t 3x 3e 3j 3q 3u 3y 3f 3k 3r 3v 3z Page 9 of 12

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 crr 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 01 11/8/08 02 1/3/12 02 2/8/12 Validation Re uired? y Converted ZZ017 to new JPM format. Since Critical actions are now uniquely identified by the format, all identifying critical portion of action were redundant and Removed reference to T-Factor and Attachment 3b due deletion of T-Factor from Tech Specs. Replaced with

Storm Warning and Attachment 3j. Updated reference procedure revision numbers. Deleted Storm Y Warning and added River Level and RCIC 1ST Attachments 3k and 3m. Validated with 2 SROs on 1/3/12. Avg completion is 7 Editorial change for clarification

-attachment 3z may be checked -not critical I I I TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EOD DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Administrative Review Operations Department Tests for Completeness and Compliance with Acceptance 305H-JPM.zZ027 REV#:

D RO STA SRO 00 Archie E. Faulkner DATE: 1/14/12 Instructor

/<t:( -e f:t"CfZ DATE: DATE: iJ0il< }ller IIi

Training Department

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

EoD RoD IMPORTANCE FACTOR: STAD SROW RO 3.4 SRO EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

HC.OP-IS.BC-0003 Rev. 43 ER-AA-321 Rev. 11 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 DATE: Page 2 of 13

NAME:

DATE:

SYSTEM: Administrative TASK: 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: 1) Perform the CRS review of the completed HC.OP-IS.BC-0003.

2) Correct discrepancies, if any 3) Document required actions, if any Page 3 of 13

JOB PERFORMANCE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria (*Denotes a Critical COMMENTS I* STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

S/U evaluati PROVIDE the operator the initiating Operator repeats back initiating cue. cue. PROVIDE marked up copy of IS.BC-0003 and Vibration data NIA ENTER START TIME Operator repeats back the I START TIME: SUBMIT the procedure to the Operator commences the OS/CRS for review AND of Attachment Operator determines correct Operator determines beginning step to be of the Page 4 of 13

TQ*AA*106*0303 JOB PERFORMANCE MEASURE JPM: 22027 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 ELEMENT NO. Make the necessary corrections and continue with the review. Make the necessary corrections and continue with the review. (*Denotes a Critical Step) I* (#Denotes a Sequential Step) EVAL STANDARD # S/U 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. N/A Operator corrects the

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. N/A COMMENTS (Required for UNSAT evaluation Operator corrects the error. Page 5 of 13

JOB PERFORMANCE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria STEP NO. ELEMENT CUE Make the necessary corrections and continue with the review. 2.1 The data acquired during the performance of this test has been reviewed for completeness and compliance with Technical Specification 6.8.4.i, 4.S.1.b.2, 4.6.2.3.b, 4.6.2.2.b, and 4.3.7.4 and the test is considered:

(*Denotes a Critical Step) COMMENTS I* (#Denotes a Sequential Step) EVAL (Required for UNSA T STANDARD # Stu Operator determines that the differential pressure is within the REQUIRED ACTION range. N/A Operator changes the SAT to UNSAT.

Operator reviews the data entered for completeness and compliance with Technical Specifications.

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

S/U evaluation) UNSATISFACTORY (Any test Operator completes the evaluations are marked TAKE action lAW Specifications and GENERATE Operator notes that data flagged ACCEPTANCE CRITERIA was Operator signs in Step Operator determines B RHR Pump is INOPERABLE for Operator determines the most limiting Tech Spec is 3.6.2.3 Action (Suppression Pool Cooling 72 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 TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria (*Denotes a Critical COMMENTS I* STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

S/U evaluatio Operator determines that a

NOTIFICATION must be generated. A Notification will be written by N/A another operator. WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. N/A REPEAT BACK any message from operator on the status of the JPM, then state "This JPM is STOP TIME: Page 8 of 13

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

.__.__..

RESPONSE:

.--.--..--..--..

---.--...--..*RESULT: SAT UNSAT QUESTION:

._----------RESPONSE:

..RESULT: SAT Page 9 of 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 CUE: 1) Perform the CRS review of the completed HC.OP-IS.BC-0003.

2) Correct discrepancies, if any 3) Document required actions, if any Page 10 of 13

JOB PERFORMANCE MEASURE 1.0 IBP-202 RHR PUMP Report printed on: TODAY 2.0 Vibration monitoring system results: Report generated on: TODAY 09:00 AM Acquired:

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

14 A. Maximum level: 0.2182 inls at MIV RECOMMENDATIONS:

2.2 THERE

ARE NO RECOMMENDATIONS DIAGNOSES:

2.3 NO F AUL TS HA VE BEEN DETECTED POSITION LEGEND: OK: 0.119 inls at MIH Alarm level: 0.213 inls OK: 0.218 inls at Ml V Alarm level: 0.240 inls OK: 0.076 in/s at MIA Alarm level: 0.110 inls OK: 0.193 inls at M2H Alarm level: 0.400 inls OK: 0.211 inls at M2V Alarm level: 0.400 inls OK: 0.114 inls at M2A Alarm level: 0.400 inls OK: 0.108 inls at PIH Alarm level: 0.300 inls OK: 0.126 inls at PI V Alarm level: 0.300 inls OK: 0.081 inls at PIA Alarm level: 0.300 inls Page 11 of 13 TQ-AA-106*0303 JOB PERFORMANCE MEASURE REVISION JPM NUMBER: i iDescription 2 Modified Admin JPM due to changes in Validation required.

Validated with 2SROs on 1/3/12.

TASK JPM SAP BET: ALTERNATE PATH: APPLICABILITY:

EO D DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Radiation Control Verify Compliance with Gaseous Release Permit 2990420302 30SH-J P M .ZZ003 REV #: 02 NOHOS..'PZZ03E D RO D STA SRO []] Archie Faulkner DATE: 1/14/12 Instructor

'(I<. -e h t:.-l( DATE:

DATE:

III!Training Department

STATION: Hope Creek JPM NUMBER: 22003 REV: 02 SYSTEM: Radiation Control TASK NUMBER: 2990420302 TASK: Verify Compliance with Gaseous Release Permit ALTERNATE PATH: D KiA NUMBER: 2.3.6 IMPORTANCE FACTOR: 2.0 3.8 APPLICABILITY:

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

Classroom/Perform

REFERENCES:

OP-HC-103-105 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-106-0303 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.

INIl"IATING CUE: Review AND Close Out today's Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit in accordance with OP-HC-1 03-1 05. Page 3 of 13

JPM: ZZ003 Rev: 02 SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit STEP NO. ELEMENT CUE PROVIDE the operator the initiating cue AND: o Prepared OP-HC-1 03-1 05 log Forms 1 & 2 (Attached) o Copy of OP-HC-1 03-1 05 CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: Operator determines beginning step of the procedure.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. I N/A Operator determines correct beginning step to be 4.4.6.

EVAL # I S/U TQ-I"\A-106-0303 COMMENTS (Required for UNSAT evaluati OPERATOR TRAINING JOB PERFORMANCE Page 4 of 13

4.4.6 TQ*",A-106-0303 JPM: ZZ003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit CUE ELEMENT The SM/CRS should verify calculations, sign in the space for verification and close and enter the time and IF the operator requests the NCO make THEN DIRECT the operator to any required

(*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U eval 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. 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. N/A Page 5 of 13 JPM: ZZ003 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit STEP NO. ELEMENT 4.4.6 The SM/CRS should verify the calculations, sign in the appropriate space for verification and close out and enter the time and date. 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 makes corrections to Form 2 Stop times and Total Hours. Examiner Note: Refer to Examiners Copy for appropriate corrections.

N/A NAME: DATE: TQ-I"\A-106-0303

________________

_ * #

EVAL stu COMMENTS (Required for UNSAT evaluation Page 6 of 13

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

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE: ...... ----------------------------------------------RESULT: SAT UNSAT

TQ-AA-106-0303 JOB PERFORMANCE MEASURE 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 Calculate Total Hours Open During Previous Year (Note 1) 452 hrs NUMBER OF HOURS

__ _ (=) 24 4/3/11 6/25/11 8/30/11 8/31/11 DatelTime Jolin Smitli TodaylO100 SM/CRS verification and authorization DatelTime .J1narew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2) START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Condition 1, 2, or 3 was entered with valv open e/line Time at which valvelline was closed or Condition 4 or 5 was entered with valvel1ine opened Total number of hours valve/line opened this cycle (NOTE 3) 0436 0800 .:t-§43 1252 M 5.0 Total number of hours valves/line open this permit: NCO performing calculations )Indy qranatelli DatelTime rtodizy/.Now

'[)ate/7UNe SM/CRS Closing permit ____ ___ ____DatelTime 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 in accordance with OP-HC-103-105.

OP-HC-1 03-1 05 0[Af]@ @[Af](1):7 Revision 0

@@[?)7 Page 7 of 8 FORM 1 Page of__ CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG 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 SeD 5.5 28.0 S. West SeD 6/25/1118.5 24 G. Williams 7'1(W 3.5 22.0 G. Cloon 7'1(W 8/30/11 22.0 24 W. Holmes 1( 24.00 46.0 P. Price 1( 8/31/11 46.0 24 B. Lee C£ 2.5 48.5 V. Bonovan C£ Today 35.5 24 A. Jones JS , ,--_.-----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

@@[?W Page 8 of 8 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING.

OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: ___T_C?day 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) (-) 3-=-5....'-.5

__ DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 4/3/11 5.5 OR 24, whichever is less) 6/25/11 Hours authorized this date (max 24 hours1 days 0.143 weeks 0.0329 months ) 8/30/11 24.0 8/31/11 NCO performing calculation DatelTime Jolin Smitli Today/0100 SM/CRS verification and authorization DatelTime Jlncfrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2) START TIME STOP TIME TOTAL HOURS Time at which valvelline 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 valvelline Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) Total number of hours valves/line open this permit: ___--=1.c::0.:...:.S'--

___ NCO perform i ng calculations

___-'-jl_ndi-'!ry'-'<..Ci_ra_na_t_e_flt._t

___ DatelTime SM/CRS Closing permit ____________ DatelTime 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-1 04 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.)

OP-HC-1 03-1 05 Revision 0 Page 8 of 8 REVISION HISTORY JPM NUMBER: ZZ003 Rev# ' Date 01 12/6/08 \ 02 I 1/14/12 I I -"" Description 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.

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 Re CI uires validation Updated reference procedure revision.

Changed names on Attachments.

Corrected typo on Initiating Conditions Cue Sheet. Updated dates to be relevant to current year. Validated with 2 , SROs on 1/3112. Average completion time was 9 minutes. Validation:

y Y STATION: SYSTEM: TASK: TASK NUMBER: JPM NUMBER: SAP BET: ALTERNATE PATH: APPLICABILITY:

EO DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Administrative DutieslReporting Requirements Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition 2000500302/2000020505 305H-JPM.ECG003 REV#:

D RO D STA []] SRO [KJ Archie E. Faulkner DATE: 1/14/12 Instructor DATE:

DATE:

}/Jg' /11... Training Department i

STATION: Hope Creek JPM NUMBER: ECG003 SYSTEM: Administrative Duties/Reporting Requirements TASK NUMBER: 2000500302/2000020505 Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event And/Or Plant Condition ALTERNATE PATH: KIA NUMBER: 2.4.38 APPLICABILITY:

EoD RoD IMPORTANCE FACTOR: STAW SROW 2.2 RO 4.0 SRO EVALUATION SETTING/METHOD:

SimulatorlPerform or In Plant/Sim ulate

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: I 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 1.59E+04 !-ICi/sec Noble Gas and 1.59E+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-r\A-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__JOB PERFORMANCE MEASURE SYSTEM: TASK: CUE CUE ECG Section LlV.C ECG Section Administrative Duties/Reporting Requirements Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event AndlOr Plant Condition I* I COMMENTS ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains the correct procedure.

Classification:

To use this ECG volume, follow this sequence: ASSESS the event and/or plant conditions and DETERMINE which ECG section(s) is most appropriate. REFER to Section EAL Flowchart diagram(s), and identify the Initiating Conditions that are related to the evenUcondition that has occurred or is ongoing. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. N/A Operator obtains Hope Creek Event Classification Guide. Operator assesses the initial conditions, and determines that Table 3, Fission Product Barriers, 6.1 Radiological Releases/Occurances, and 9.0, Hazards-lnternaI/External, are the appropriate ECG sections.

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.

EVAL (Required for UNSAT # S/U eval.....

Page 4 of 19 i.IV.C

TQ*",A*106*0303 ECG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_JOB PERFORMANCE SYSTEM: Administrative Duties/Reporting TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant

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

ECG 3. REVIEW the associated EALs Section compared to the event SELECT the highest emergency or reportable level. If identification of an EAL questionable, refer to IV.A Operator reviews the EALs in section 6.1 and 9.5, and determines that EAL #If there is any doubt with regard to 6.1.2.d and 9.5.2 is the highest assessment of a particular EAL, emergency action level met or the ECG Technical Basis exceeded (ALERT). Document should be Words contained in an EAL are bold face are either values associated with that level or are words that are in the basis for that specific ECG 4. If an EAL has been entered, Section equal level EALs or lower LlV.C EALs and RALs are not Examiner Note: Filling out the NRC to be reported as long as the Data Sheet is beyond the scope of this applicable information is JPM.communicated to the NRC Attachment 5, NRC Data -_._........ -Page 5 of 19 TQ-I"\A-106*0303 NAME: ________________

_ECG003 OPERATOR TRAINING PROGRAM DATE: ________________

_JOB PERFORMANCE SYSTEM: Administrative Duties/Reporting TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant

(*Denotes a Critical Step) COMMENTS STEP

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

Table If the Loss or Potential Loss is Operator reads NOTE. 3.0 considered IMMINENT (may occur NOTE within 2 hours0.0833 days 0.0119 weeks 0.00274 months ), USE judgement classify as if the threshold I

Table In the table review the Emergency Operator reviews the EALs of all 3.0 Action Levels of all columns and columns, and determines that all 1. identify which need further review. columns need further review. Table For each of the three barriers, Operator determines that the following 3.0 I determine the EAL with the highest EALs have been exceeded and 2. point value. No more than one EAL represent the highest value met or I should be selected for each barrier. exceeded for the respective 3.1.1.a; 3.2.2.b or 3.2.1.b; 3.3.2.b or 3.3.2.d. I I Table Add the pOint values for the three Operator adds the values, and enters 3.0 barriers and enter the total below: the value 9 in the appropriate space. 3. I Examiners Note: Determining this value for future use is critical; marking it I on Table 3.0 is not. I I ---...... Page 6 of 19

TQ-AA-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_JOB PERFORMANCE SYSTEM: Administrative Duties/Reporting TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for NO. STANDARD # S/U Classify based on the point value sum Operator determines that this 3.0 as follows: classification is higher than the 4. classification on EALs 6.1.2.d or 9.5.2 Ifllle Oassifyas:

Ref*rto: and classifies the event as a General sums: Emergency based on Table 3.0. 1,2 UNUSUAL EVENT ATI.1 3,4 ALERT ATI.2 5,6,7,8 SITE AREA ATI.3 9,10 GENERAL ATIA -_...... __._..... __.... __._. __.... __..... __._..... __...---------..-'--------...--'----

Page 7 of 19

TQ-I"\A-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__JOB PERFORMANCE SYSTEM: Administrative Duties/Reporting TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant

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

SIU evaluati ECG 5. The ST A is responsible Section perform an LlV.C verification of the IF 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 the Examiner Note: Due to time SM fill the ST A role, independent assessing and/or nature of verification of the EAL administration, Operator may classification will be delegated to request a another on-shift IF the Operator requests the to independently verify the N/A THEN INFORM the Operator ST AliA is not Page 8 of 19

06-0303 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* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation)

I ECG 6. IDENTIFY and IMPLEMENT Section referenced Attachment Action Required.

Refer to iv, HC Emergency Operator identifies and implements Description Table, which is a ECG Attachment 4.guide for correct wording for entry on the ICMF all ECG I. EMERGENCY COORDINATOR Atl. 4 {Ee} LOG SHEET A. If a security event is progress, THEN, Operator determines this step is not the prompt actions of applicable.

EP.ZZ-0102, EC Attachment 10, prior Page 9 of 19

TQ-I"\A-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__JOB PERFORMANCE SYSTEM: Administrative Duties/Reporting TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant STEP ELEMENT NO. ECG DECLARE A GENERAL 4 EMERGENCY AT HOPE CREEK EAL #(s) , , DECLARED AT hrs on time date C. NOTIFICATIONS Att. 4 CALL the communicators to the Control Room CUE After 2 minutes, report as the communicators and give your name as CM1 and CM2. -(*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation)

I 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 time_(15 min.} Initialing the step is not critical. I Operator calls the communicator using the plant page. N/A Page 10 of 19 TQ-I"\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 COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

ECG 2. ACTIVATE "ERO Emergency Operator activates the ERO per posted Att.4 Callout" per posted instructions instructions titled Training titled: "Emergency Callout Emergency Callout Activation" Examiner Note: ENSURE the is using the Simulator Activation Caution A Protective Operator reads CAUTION. Recommendation (PAR) SHALL be made on the Initial Contact Message Form (ICMF). ECG MAKE A PAR as follows: Operator Refers to APPENDIX 1,

Att. 4 determines that a GE Based 9 PointsREFER to PAR is PAR Flowchart on Pg. 3 DETERMINE the appropriate

[EVACUATE ALL SECTORS PAR. lE a Radiologically PAR is Examiner available, THEN Shelter Sectors and Distance is left the two PARs and choose blank for a 9 point GE. the most appropriate for inclusion on the ICMF. --_..........

__._..........

__._....... Page 11 of 19

---ECG003 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Administrative Duties/Reporting Requirements DATE: ________________TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition STEP ELEMENT NO. CUE If asked, a Radiologically Based PAR is not available.

ECG COMPLETE the INITIAL Att.4 CONTACT MESSAGE FORM (ICMF) (last page of this attachment). IF time allows, OST AIN an accuracy peer check of the completed ICMF. (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation)

N/A 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.

Operator requests a Peer Check of the completed ICMF. Page 12 of 19

ECG003 OPERATOR TRAINING PROGRAM NAME: ________________DATE: ________________JOB PERFORMANCE SYSTEM: Administrative Duties/Reporting TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant STEP NO. ELEMENT CUE IF the Operator requests a Peer Check, THEN INFORM the Operator a Peer Check has been performed as requested.

6. PROVIDE the ICMF to the Primary Communicator (CM1) and DIRECT the Communicator to implement ECG Attachment

6. CUE LOG the time the ICMF is provided to CM1. LOG TIME: _____ Role-playas CM1 and repeat back the direction as given. (*Denotes a Critical Step)

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

Operator provides the ICMF to CM1 and directs implementation of Att.6. 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"\A-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 COMMENTS I* I STEP (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U ECG 7. DIRECT the Secondary Operator directs CM2 to implement Att. Att.4 Communicator (CM2) to a for a GENERAL implement ECG Attachment for a GENERAL ROLE-PLAYas CM2 and BACK the direction as given. 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, then state "This JPM is STOP TIME: Page 14 of 19

JOB PERFORMANCE MEASURE OPERATOR TRAINING EVALUATOR FOLLOWUP QUESTION 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:

RESULT: SAT UNSAT Page 15 of 19 L TQ-AA-106-0303 JOB PERFORMANCE MEASURE ECG ATT4 Pg. 50f5 INITIAL CONTACT :MESSAGE FORt"! THIS IS (Not Required) , COtvfivfUNICATOR IN THE .iJ CONTROL ROOM (NMffi) DTSC DEOF AT THE HOPE CREEK l\iLJCLEAR GENERATING STATION. TIa. THIS IS NOTIFICATION OF A GENERAL EI\>1ERGENCY

\\lHICH WAS DECLARED AT Todays Time ON Date (TIME -24 HOUR CLOCK) (DATE) EAL #(5) 3.1.1.a , 3.2.1.b or 3.2.2.b ,3.3.2.b or 3.3.2.d DESCRIPTION OF EVENT: Potential Loss of F Loss of Reactor Coolant System Barriet::a lIb. THIS IS NOTIFICATION OF A PROTECTIVE AC UPGRWE \VHICH WAS lvLIDE AT ____Reason for PAR Upgrade: III. see NOTE }. tbr release definition IV. (From): 224 WJ1\'D SPEED: _"",-21-,--_

iSPDS) (DEGREES) (MPH) v. rl WE RECOMlvIEr..'D EV AClTATION AS FOLLOWS Sectors A" Dist. -Miles 0-5 o \VE SHELTERING AS FOLLOWS Fa WE RECO:tv11vfEND THE USE OF KI IN ACCORDANCE WITH STATE PROCEDTJRES Performer's Initials EC Initials (Approval to Transmit ICMF) ReGS 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. 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 1.59E+04 !-ICi/sec Noble Gas and 1.59E+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 17 of 19 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ECG003 Rev# I Date Description Validation Required?

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

TASK JPM SAP JOB PERFORMANCE MEASURE Hope Creek Feedwater Respond To Rising Orywell Pressure 4000510401 305H-JPM.AE004 NOH05JPAE04E ALTERNATE PATH: APPLICABILITY:

EO DEVELOPED BY: REVIEWED BY: APPROVED BY: RO []] STA Steve j'<C /<-ct-ztr/rc 0 rations Representative Training Department REV #: 06 SRO I X I DATE: 2/15/12 DATE:

?!22//z DATE:

STATION: Hope Creek JPM NUMBER: AE004 REV: 06 SYSTEM: Feedwater TASK NUMBER: 4000510401 TASK: Respond To Rising Drywell Pressure ALTERNATE PATH: KIA NUMBER: 223001 A2.01 IMPORTANCE FACTOR: 4.3 4.4 APPLICABILITY:

EO 0 RO [KJ STA 0 SRO [KJ RO SRO EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

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 SIGNATURE:

DATE: Page 2 of 18

TQ-AA-106-0303 NAME: DATE: SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure TASK NUMBER: 4000510401 INITIAL CONDITIONS: 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 pumps 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

JPM: Rev: 06 SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP NO. 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 reviews precautions and limitations. IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.

Operator determines beginning step of the procedure.

TCt-I"\A-106-0303 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__JOB PERFORMANCE MEASURE (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # I S/U evaluat Operator repeats back initiating cue. I N/A Operator obtains procedure HC.OP-SO.AE-0001.

Operator reviews precautions N/A Operator determines correct step to be Page 4 of 18

TU-r'\A-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME: Rev: 06 SYSTEM: TASK: NOTE 5.18.1 CUE 5.18.2 Feedwater Respond To Rising Drywell Pressure ELEMENT The HPCI AND the RCIC Jockey Pump Loops are used to maintain a water seal in the Feedwater lines between the inboard AND outboard containment isolation valves following a LOCA. ENSURE all prerequisites of Section 2.1 are satisfied.

IF excessive time is taken THEN INFORM operator that all ENSURE the following valves

BJ-HV-8278, HPCI DSCH THRU FW ISLN MOV JOB PERFORMANCE MEASURE DATE: (*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # I S/U evalu N/A Operator ensures that all prerequisites have been satisfied.

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

N/A Operator observes the HPCI DSCH THRU FW ISLN MOV HV8278 OPEN light is illuminated and CLSD light is extinguished.

Page 5 of 18

JPM: AE004 Rev: 06 SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP ELEMENT NO. INFORM the Operator the trip of the HPCI Jockey pump will be investigated by another operator.

DIRECT the Operator to place a water seal on the 'A' & '8' Feedwater lines using the RCIC jockey pump.

06-0303 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__JOB PERFORMANCE MEASURE (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # I S/U eval Y N Flagging Operator presses the HV8278 CLOSE

pushbutton.

Examiner note: 30 seconds after pressing the HV8278 CLOSE pb, the AP228 HPCI Jockey Pump will trip. 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. N/A Page 6 of 18

JPM: AE004 Rev: 06 SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP ELEMENT NO. Operator determines step 5.18.3 of the procedure is now applicable.

BD-HV-F013, RCIC PUMP DSCH TOFW

HV-F032A, FW INLET CHK VL V TQ-I"\A-106-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: (*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # I S/U eval Operator continues to complete step 5.18.2. Operator observes the F013 CLSD light illuminated and the OPEN light extinguished.

Operator observes the FW INLET CHK VL V HVF032A OPEN light is illuminated and the CLOSE light is extinguished. Y N Flagging Operator presses the HVF032A CLOSE

pushbutton.

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

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

HV-F032B, FW INLET CHK VL Page 7 of 18

________________

___ 5.18.3 JPM: AE004 Rev: 06 SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP ELEMENT NO.

HV-4144, FW LINE CROSS-TIE ISL VLV IF AP228, HPCI JOCKEY PUMP will 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:

OPERATOR TRAINING PROGRAM NAME: DATE: JOB PERFORMANCE MEASURE {*Denotes a Critical Step} * (#Denotes a Sequential Step) EVAL STANDARD # S/U Operator presses the HVF032B CLOSE

pushbutton.

Operator observes the HVF032B CLOSE light illuminates and the OPEN light extinguishes.

Operator observes the HV-4144, FW LINE CROSS-TIE ISL VLV CLOSE light is illuminated and OPEN light is extinguished.

Based on current conditions, Operator determines that this step now applies. TQ-nA-106-0303 COMMENTS (Required for UNSAT Y N Flagging Page 8 of 18

---8 TQ-I"\A-106-0303 JPM: OPERATOR TRAINING PROGRAM NAME: Rev: 06 JOB PERFORMANCE MEASURE DATE: SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

S/U evaluation) Operator inserts key and places the

PLACE the keylock switch for HV-Keylock switch for the HV-4144, FW 4144, FW LINE CROSS-TIE ISLN CROSS TIE LINE ISLN, in the ON VL V, in the ON position to arm the control Examiner Note: OHA 83-D2 FEEDWATER LINE FILL ALT MODE will alarm. Operator observes the HV-4144, FW OPEN HV-4144, FW LINE LINE CROSS-TIE ISL VLV CLOSE light TIE ISL VLV. is illuminated and OPEN light is extinguished. Y N Flagging OperatOi presses the FW CROSS TIE

LINE ISLN HV-4144 OPEN pushbutton.

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

--_._........_-_ ... Page 9 of 18

JPM: AE004 Rev: 06 SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP NO. ELEMENT 5.18.4. IF AP228, HPCI JOCKEY PUMP is to be used to seal one or both Feedwater lines, THEN PERFORM the following:

\ OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Based on current conditions, Operator determines that this step does not apply and continues at step 5.18.5. * # NAME: DATE: EVAL S/U COMMENTS (Required for UNSA T evalualio 5.18.5 I IF the BP228, RCIC JOCKEY PUMP is to be used to seal one or both Feedwater lines, THEN PERFORM the following:

5.18.5. A PLACE the NORM/BYPASS Keylock Switch for BO-HV-F013, RCIC PUMP DSCH TO FW, in the BYPASS position to arm the Control Switch. Operator inserts key and places the Keylock switch for the RCIC HVF013 in the BYPASS position.

Examiner Note: OHA B3-D2 FEEDWATER LINE FILL ALT MODE will alarm. # Y N Flagging Page 10 of 18

JPM: AE004 OPERATOR TRAINING PROGRAM Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure (*Denotes a Critical Step) STEP (#Denotes a Sequential Step) NO. STANDARD 5.18.5. OPEN BD-HV-F013, RCIC PUMP Operator observes the RCIC PUMP DSCH TO FW. DSCH TO FW HVF013 CLSD light is illuminated and OPEN light is extinguished.

Operator presses the HVF013 OPEN pushbutton.

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

5.18.5. OPEN BD-HV-F012, RCIC PUMP Operator observes the HVF012 OPEN DSCH VLV. light is illuminated and CLSD light is extinguished.

5.18.5. WHEN required, THEN START Operator observes the RCIC JOCKEY BP228, RCIC JOCKEY PUMP. PUMP red RUNNING light is illuminated and green STOPPED light is extinguished.

Page 11 of 18 Tte-nA-106-0303 NAME: DATE: ________________

__ COMMENTS* EVAL (Required for UNSAT # S/U evaluation) Y N Flagging* *

TCt-I"\A-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluatior 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 N/A 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 Drywell 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 D is being implemented.

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

JOB PERFORMANCE SIMULATOR SETUP Initial INITIALIZE the simulator to 100% power, MOL. INSERT Malfunction CR01 at 100% using ET-1. WHEN MSL Radiation levels reach 3xNFPB, INSERT Malfunction MS01 at 100% using ET-2. INSERT Malfunction RM9635 to 5211 and RM9636 to 5185 to raise DAPA RMS readings using ET-3. IMPLEMENT EOP-101 and EOP-102. ENSURE MSIVs are closed. TRIP all PCPs and SCPs. ESTABLISH RPV water level control with Core Spray. 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 removed. COMPLETE "Simulator Ready-for-Training/Examination Checklist".

ET # Event code: 4

Description:

Event code:

Description:

Event code:

Description:

ZDHP278C >=1.0 /I HPCI 8278 CLOSE pb pressed. Trips HPCI Jockey Pump Page 15 of 18 JOB PERFORMANCE SIMULATOR SETUP None None None None None None None None None None None None None None None None None None None None None i None None Insert malfunction CR01 to 100.00000 on event 1 Insert malfunction MS01 to 100.00000 on event 2 Insert malfunction RM9635 to 5211.00000 on event 3 Insert malfunction RM9636 to 5185.00000 on event 3 Insert malfunction AN-B1 E4 after 30 on event 4 Insert malfunction AN-B1 F3 after 30 on event 4 Insert remote IA 10 to RUN Insert remote ET066 to FAIL_OPEN on event 2 Remove remote ET066 to FAIL_OPEN on event 4 Insert override 9S139_A_DI after 30 to Off on event 4 Insert override 9S138_A_LO after 30 to On on event 4 Insert override 9DS111_B_LO after 30 to Off on event 4 Insert override 9M6_R_AO after from 95.00000 to 0 in 5 on event Fuel cladding leak Steam line break in drywell 9RX635, DAPA 'A' -Drywell Atmos Post-Accident Chan 'A' 9RX636, DAPA 'B' -Drywell Atmps Post-Accident Chan 'B' CRYWOLF ANN B1 E4 HPCI JOCKEY PUMP 1 AP228 TROUBLE CRYWOLF ANN B1 F3 HPCI COMPONENT O/PF IAi0 Temporary station air compressor ET066 HV-8278 HPCI to FW ET066 HV-8278 HPCI to FW HPCI JOCKEY START/STOP (DI) AP228 OVLD/PWR FAIL (LO) AP228 STOPPED (AO) Page 16 of 18 TQ*AA*106*0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AE004 Rev#

Date Description I Validation i Required?

01 12/3/07 Revision 53 of HC.OP-SO.AE-0001 renumbered former N 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.

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. 02 9/29/09 This change is editorial, validation not require(j.

I Complete revision due to procedure section revision.

Validated

! Y with 2 operators from 'A' Shift. Average completion time was 12 minutes. 03 8/12/10

Updated Reference procedure revision ! N changes to operator actions. No validation required.

04 8/2/11 Modified Malfunction, Remote, Override, and Event list sections N 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 validCition required.

05 1/14/12 . Updated Reference procedure revision numbers only. No N 1----+------+'

_c_h__a-,n......e_sto operator actions. No validation required.

____--+-____----j 06 2/15/12 Steps 5.18.C and 5.18.D changed to critical steps. Revalidated y _______

__.____________________

TASK NUM JPM SAP ALTERNATE PATH: APPLICABILITY:

EOD DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Residual Heat Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop 2050120101 305H-JPM.BC015 REV#: 04 NOH05JPBC15E 0] RO STA SRO D Steve Dennis DATE: 2/16/12 Instructor

-" j-(fL ......t VIL DATE:

perations Representative DATE: oumk I) a'2 I!L ; Training Department

STATION: Hope Creek JPM NUMBER: BC015 REV: 04 SYSTEM: Residual Heat Removal TASK NUMBER: 2050120101 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop ALTERNATE PATH: W KIA NUMBER: 205000 A4.03 IMPORTANCE FACTOR: 3.6 3.5 APPLICABILITY:

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

Simulator/Perform

REFERENCES:

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

None. ESTIMATED COMPLETION TIME: 33 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 22 I

NAME: DATE: 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 hours8.333 days 1.19 weeks 0.274 months . 3. 'S' 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. SC-HV-F007 A and SC-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

TCt-I'\.A-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: ________________

_ SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP NO. CUE CUE CUE ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains procedure HC.OP-SO.BC-0002 Operator reviews precautions and limitations. I F excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.

Operator determines beginning step of the procedure.

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

Operator reviews precautions and limitations.

N/A Operator determines correct beginning step to be 5.3.1. Page 40f22 COMMENTS* EVAL (Required for UNSAT # Stu eval

06-0303 JPM: BC015 Rev: 04 SYSTEM: Residual Heat Removal OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP (*Denotes a Critical Step) NO. ELEMENT (#Denotes a Sequential Step) STANDARD * # NAME: DATE: EVAL Stu COMMENTS (Required for UNSAT evaluation)

5.3.1 ENSURE

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

NOTE BC-HV-F027 A(B) RHR LOOP A(B) 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 NOTE. Page 5 of 22 TQ-MA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME:

Rev: 04 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 S/U COMMENTS (Required for UNSAT evaluation)

I CAUTION While in shutdown cooling, the Operator reads CAUTION. following valves shall be closed to prevent uncontrolled drainage from the Reactor Vessel: [CO-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*F007 A(B) RHR PMP A(B) MIN FLOW 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] Page 6 of 22

TQ-I"\A-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling STEP ELEMENT NO. I PERFORM the following to prepare loop to be placed in Shutdown Cooling: IF a flush on the loop to be placed in Shutdown Cooling is required, THEN REFER TO Steps 5.2.5 through 5.2.14. ENSURE the following Valves are B CLOSED: BC-HV-F003A(B)

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

A(B) RHR PMP SUPP POOL SUCT MOV (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation Operator determines step 5.3.2.A. does not apply. Operator observes the BC-HV-F003A RHR HX A OUTLET VL V CLSD light illuminated and OPEN is extinguished.

Operator observes the BC-HV-F004A A RHRPMPSUPPPOOLSUCTMOV CLSD light illuminated and OPEN is extinguished.

Page 7 of 22

TQ-AA-106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

BC-HV-F007 A(S) RHR PUMP Operator observes the BC-HV-F007 A is MIN FLOW TAGGED CLOSED and breaker 212041 OPEN AND Attachment 1 BC-HV-F024A(B)

RHR LOOP Operator observes the BC-HV-F024A TEST RET RHR LOOP A TEST RET MOV light illuminated and OPEN BC-HV-F027A(B)

RHR LOOP Operator observes the BC-HV-F027 A is SUPP POOL SPRAY HDR ISLN TAGGED CLOSED and breaker 212081 OPEN AND Attachment NOTE Operator reads This section may be continued the valve is re-positioned and breaker opened (step signoff after safety Page 8 of 22

TQ*AA*106-0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

5.3.2. VERIFY

BC-HV-F007A(B) Operator observes the BC-HV-F007 A is CLOSED THEN TAG breaker 52-TAGGED CLOSED and breaker 212041(52-222041)

OPEN AND 212041 OPEN AND INITIAL Attachment

1. Attachment -----NOTE Operator reads NOTE. 1-BC-V315 (V314) SUP POOL HDR MAN ISLN VL V may be CLOSED instead of tagging associated breaker for the F027A(B) (if required to outage activities), although F027A(B) must still be This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

5.3.2. VERIFY

BC-HV-F027 A(B) Operator observes the BC-HV-F027 A is CLOSED AND TAG breaker 52-TAGGED CLOSED and breaker 212083 (52-222083)

OPEN AND 212081 OPEN AND INITIAL Attachment

1. Attachment 1 Page 9 of 22

JPM: BC015 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) OPEN BC-HV-F006A(B)

RHR PMP Operator presses BC-HV-F006A RHR A(B) SUCT FROM RECIRC for the PMP A SUCT FROM RECIRC RHR Loop to be placed in SID Operator observes the BC-HV-FOO6A RHR PMP A SUCT FROM RECIRC OPEN light illuminated and CLSD extinguishes.

NOTE Operator reads 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. , Page 10 of 22 TCol-J"\A*106*0303 NAME: ________________

__JPM: BC015 OPERATOR TRAINING PROGRAM DATE: ________________

__Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop 5.3.4. 5.3.5. 5.3.5. A CUE ELEMENT IF prewarming of the Loop of RHR to be placed in SID Cooling is required THEN, PERFORM Steps 5.2.26 OR 5.2.27 of this procedure to equalize temperatures; OTHERWISE PROCEED. I SECURE the inservice Shutdown Cooling Loop as follows: ENSURE 1-BC-V262 (1-BC-V212), ECCS Jockey Pmp D(C) DISCH to RHR Loop B(A) is LOCKED OPEN (local), AND INITIAL Attachment

1. The valve is in the position requested.

NOTE Steps 5.3.5.B through 5.3.5.C should be performed in rapid succession.

(*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U Operator determines step 5.3.4 does not apply. Operator contacts Equipment Operator and directs opening 1-BC-V262.

Operator reads NOTE. Page 11 of 22

JPM: BC015 OPERATOR TRAINING PROGRAM Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP (*Denotes a Critical Step) NO. ELEMENT (#Denotes a Sequential Step) STANDARD * # NAME: DATE: EVAL S/U

________________

_ COMMENTS (Required for UNSAT evaluation) 5.3.5. 8 CLOSE 8C-HV-F0158(A)

RHR LOOP 8(A) RET TO RECIRC AND INITIAL Attachment 1 . Operator presses and holds the HV-F0158 RHR LOOP 8 RET TO RECIRC CLSD pb.

I 5.3.5. C WHEN 8C-HV-F0158(A)

RHR LOOP 8(A) RET TO RECIRC is fully closed, THEN, IMMEDIATELY STOP B(A)P202 RHR PUMP. Operator observes the 8C-HV-F0158 RHR LOOP 8 RET TO RECIRC CLSD light illuminated and OPEN is extinguished.

-Operator presses BP202 RHR PUMP STOP pb.

Page 12 of 22

JPM: BC015 OPERATOR TRAINING PROGRAM NAME: Rev: 04 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation) Operator presses the BC-HV-F006B

CLOSE BC-HV-F006B(A)

RHR 0 RHR PMP B(A) SUCT FROM B(A) SUCT FROM RECIRC AND CLSD INITIAL Attachment Operator observes the BC-HV-F006B RHR PMP B(A) SUCT FROM RECIRC CLSD light illuminated and OPEN is extinguished. ENSURE SACS is in service to the Operator observes the RHR Heat Exchanger for the RHR OPEN light illuminated and CLSD loop to be placed in service lAW HC.OP-SO.EG-0001 Operator observes RHR A HX SACS Flow approximately 9000 gpm. Page 13 of 22 TQ-AA-106-0303 JPM: Rev: BC015 04 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: 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 S/U COMMENTS (Required for UNSAT evaluation)

CAUTION Manual OR automatic opening of 8C-HV-F007 A(8) RHR PMP A(B) MIN FLOW MOV will drain Reactor Vessel to Suppression Pool. Operator reads CAUTION. If BC-HV-FO 15 A(BA RHR LOOP A(BA RET TO RECIRC does NOT oTlen immediatel'l.

to establish flow l then the RHR flumfl should be secured. 8C-HV-F027 A(8) RHR LOOP A(B) 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 14 of 22

JPM: BC015 OPERATOR TRAINING PROGRAM Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation) START RHR PUMP A(B)P202 AND Operator presses the AP202 START IMMEDIATEL Y THROTTLE OPEN BC-HV-F015A(8)

RHR LOOP RET TO RECIRC LOOP UNTIL R603A(B) OR FR-R60BA(B)

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

3000 Operator observes the AP202 START light illuminated and STOP light extinguishes.

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.

Page 15 of 22

TQ-",A*106*0303 JPM: BC015 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP NO. ELEMENT Examiner Note: F015A will fail closed and not establish flow. Operator must secure the pump lAW the preceding caution. If the pump is not tripped within 2 minutes, a preinserted malfunction will cause the pump to trip at the 2 minute mark. 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) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation Operator observes the FI-R603A OR FR-R60BA -CRIDS A3137, LOOP A FLOW indicates 0 gpm. Operator determines CAUTION applies. Operator presses AP202 STOP pb.

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 hours8.333 days 1.19 weeks 0.274 months . 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 Transfer RHR Shutdown Cooling to the A RHR The required shutdown cooling flow for the 'A' RHR pump is between 9500 -10,000 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-F007A is closed. ENSURE EG-HV-2S12A is ENSURE associated Schedule File is OPEN BC-HV-F007A breaker using OPEN BC-HV-F027A breaker using PLACE red bezel covers on the BC-HV-F007B AND the PLACE red bezel covers on the BC-HV-F007A AND the Page 19 of 22 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

None None None None None None None None None None none none none none Insert remote RH30B to TAGGED Insert remote ET006 to RACK_CLOSE Insert remote RH30A to TAGGED on event 1 Insert remote ET005 to RACK_CLOSE on event 2 Insert remote RH29A to FAIL_CLOSE BC-HV-F015 B increase PB depressed zxxxxx.x Inserts XXXX after 120 seconds on event 4 RH30 HV-F007B RHR Pump A Min Flow Valve ET006 GROUP 3B HV-F027B RHR Supp. Pool Spray RH30 HV-F007A RHR Pump A Min Flow Valve ET005 GROUP 3B HV-F027A RHR Supp. Pool Spray RH29 GROUP 3E HV-F015A RHR SOC Return Isol Causes event 4 to insert Trips "A" RHR pump Page 20 of 22 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: BC015 Rev # Date Description Validation Required?

3 5/3/11 Converted to new JPM format. Old JPM was a duplicate of ...IPM Y BC-009. Completely rewrote JPM for new task. Validated with 2 operators from "C" Shift. Avg completion time 33 minutes. 4 2/16/12 Step 5.3.5.D. revised as critical.

Added malfunction to trip the Y "AI! RHR pump 2 minutes after the increase button is depressed on the BC-HV-F015 B at step 5.3.7. Revalidated with 2 ROs 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 #: 02 SAP BET: NOH05JPCG03E ALTERNATE PATH: D APPLICABILITY:

EO RO STA SRO[KJ DEVELOPED BY: Steve Dennis DATE: 2/16/12 Instructor REVIEWED BY: DATE:

APPROVED BY: °ntCJ1L--DATE:

Training Department

STATION: Hope Creek JPM NUMBER: CG003 REV: 02 SYSTEM: Condenser Air Removal TASK NUMBER: 4000580401 TASK: Respond To A Main Condenser Low Vacuum ALTERNATE PATH: D KIA NUMBER: __271000 A4.04 IMPORTANCE FACTOR: 3.4 3.5 APPLICABILITY:

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

Simulator/Perform

REFERENCES:

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

ESTIMATED COMPLETION

,.IME: 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

,.IME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 18

TQ-AA-106-0303 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

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

__Rev: 02 JOB PERFORMANCE MEASURE 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.

OPEN HV-1957A (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. * # EVAL S/U COMMENTS (Required for UNSAT eval**...

N/A Operator obtains procedure HC.OP-AB.ZZ-0001 Attachment

11. Operator determines correct beginning step to be 1.0. Operator presses the HV-1957A OPEN pushbutton.

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

Page 4 of 18

JPM: CG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 02 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)

2.0 Operator

presses the HV-1955A OPEN Y N FlaggingOPEN HV-1955A.

Operator observes the HV-1955A OPEN light illuminates and the CLOSE light extinguishes. OPEN HV-2016A (HV-2020A if the Y N Flagging 3.0

SJAE's are being supplied by Aux. Stm) THEN OBSERVE 145-150 psig (with Operator presses the HV-2016A Main Steam supplying)

OR 175 psig (Aux Steam supplying) on -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. Page 5 of 18

JPM: OPERATOR TRAINING Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD 4.0 ENSURE PIC-1964A is in AUTO at 11 psig. 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 UP/DOWN Arrows as necessary to place the setpoint indicator on 11 psig. Operator presses the HV-1959A OPEN OPEN HV-1959A.

pushbutton.

Operator observes the HV-1959A OPEN light illuminates and the CLOSE light extinguishes. Operator presses the HV-1956A OPEN OPEN HV-1956A.

pushbutton.

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

_L Page 6 of 18 Tc.t-AA-106-0303 COMMENTS* EVAL (Required for UNSAT # StU evaluation) Y N Flagging* # Y N Flagging* Y N Flagging* # Y N Flagging* #

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

_Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum (*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) OBSERVE the following 3rd r-----.. I II Operator observes the FR-2021A SJAE 3FR-2021 A increasing stage flow r*_* Operator observes the PIC-1954A SJAE 3PI-1954A lowering.

stage pressure Operator presses the HV-1963A Y N FlaggingOPEN HV-1963A.

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

_.Operator presses the HV-1962A OPEN

Y N Flagging OPEN HV-1962A.

pushbutton.

Operator observes the HV-1962A OPEN light illuminates and the CLOSE light extinguishes.

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

lowering.

--........ --....... ......--.-....... --_....... __._....... __....... __....... ---Page 7 of 18

JPM: CG003 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 02 J08 PERFORMANCE SYSTEM: Condenser Air TASK: Respond To A Main Condenser Low (*Denotes a Critical Step) * (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

S/U evaluation) Operator presses the HV-1967 A OPEN YN Flagging* OPEN pushbutton.

Operator observes the HV-1963A OPEN light illuminates and the CLOSE light extinguishes. Operator presses the HV-1968 A 1, A2, A3,

Y N OPEN HV-1968 A1, A2, A3. OPEN

Operator observes the HV-1968A1, A2, A3, OPEN light illuminates and the CLOSE light extinguishes. Operator observes all "A "SJAE valves VERIFY valve operated in Steps 1.0 thru open.12.0 have successfully repositioned. Operator presses the HV-1968 81,82,83, Y N Flagging* CLOSE HV-1968 CLOSE pushbutton.

Operator observes the HV-196881, 82, 83 CLOSE light illuminates and the OPEN light extinguishes.

Page 8 of 18

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

___Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP ELEMENT NO. MONITOR PIC-1964A for the following indications:

SJAE 3rd stage outlet < 11 psig. Gaseous Radwaste Flow < 75 scfm (1900 #/hr). CUE IF asked as Radwaste Operator, for Offgas Flow, THEN REPORT that Offgas flow is approximately 35 scfm. Five minutes AFTER closing HV-1968 16.0 B1, B2, B3, CLOSE the following valves: "Five minutes have elapsed." (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT eval 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 CRIDS 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. Page 9 of 18 JPM: CG003 Rev: 02 SYSTEM: Condenser Air Removal OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TASK: Respond To A Main Condenser Low Vacuum STEP (*Denotes a Critical Step) NO. ELEMENT (#Denotes a Sequential Step) STANDARD

HV-1967B Operator presses the HV-1967B CLOSE pushbutton.

# NAME: DATE: EVAL S/U TQ-AA-106-0303 COMMENTS (Required for UNSAT evaluation) Y N Flagging Operator observes the HV-1967B CLOSE light illuminates and the OPEN light extinguishes.

HV-1963B Operator presses the HV-1963B CLOSE pushbutton. Y N Flagging Operator observes the HV-1963B CLOSE light illuminates and the OPEN light extinguishes.

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

HV-1955B Operator presses the HV-1955B CLOSE pushbutton. Y N Flagging Page 10 of 18 JPM: CG003 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum STEP (*Denotes a Critical Step) NO. ELEMENT (#Denotes a Sequential Step) STANDARD * # NAME: DATE: EVAL S/U TQ-rlA-106-0303

________________

__ COMMENTS (Required for UNSAT evaluation)

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

HV-1956B Operator presses the HV-1956B CLOSE pushbutton. Y N Flagging Operator observes the HV-1956B CLOSE light illuminates and the OPEN light extinguishes.

HV-1957B Operator presses the HV-1957B CLOSE pushbutton.

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

HV-1959B Operator presses the HV-1959B CLOSE pushbutton. Y N Flagging Operator observes the HV-1959B CLOSE light illuminates and the OPEN light extinguishes. Page 11 of 18 TQ-I"\A-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 SYSTEM: Condenser Air Removal JOB PERFORMANCE MEASURE DATE:

TASK: Respond To A Main Condenser Low Vacuum STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT eval

HV-2016B (2020B if SJAE supplied by Aux Steam) Operator presses the HV-2016B CLOSE pushbutton. Y N Flagging Operator observes the HV-2016B CLOSE light illuminates and the OPEN light extinguishes.

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".

N/A STOP TIME: Page 12 of 18

06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING EVALUATOR FOLLOWUP QUESTION 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, MOL. ENSURE B SJAE Train in service. INSERT Override 5M26_L_AO to 3.20. INSERT Malfunction MC01 at 12.0%. WHEN Main condenser vacuum alarms, THEN MODIFY Malfunction MC01 as necessary to maintain 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: 2

Description:

Event code:

Description:

Event code: Descri ption: ZLMC1968(1)

>=1.0 & MONVAR(31) Removes malfunction MC01 when SJAE swap Page 15 of 18

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL) i Initial @Time Event Action Description Insert malfunction MC01 to 12.00000 Low pressure turbine exhaust bellows None None on event 1 leak Initial @Time Event Action Description PIC 1964B AIR EJECTOR B STA MAN None Insert override 5M26_L_AO to 3.20 PRESSURE (AO) Page 16 of 18

JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: CG003 !Rev# Description Validation Required?

01 Converted JPM CG003 to new JPM format. Since Critical JPM actions are now uniquely identified by the format, all identifying critical portion of action were redundant and This change is editorial Validation is required to completion times. Validated with 2 ROs on 1/3/12. completion time was 13 02 2/16/12

Step 14.0 revised to a critical step.

Revalidated by an RO and I

TASK ..IPM SAP ALTERNATE PATH: APPLICABILITY:

EOD DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Containment Atmosphere Control Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches 2000950501 305H-JPM.GS005 REV#: 04 NOH05JPGS05E 00 RO [KJ STA D SRO [KJ Archie E. Faulkner DATE: 1/14/12 Instructor 1<t2-ce f-z.-vtc DATE: , DATE: CWCflL }//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: __2_9_5_02_4_E_A_1_.1_9

__ IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY:

RO SRO EO D RO []] STA D 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

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 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 3 of 21 TQ-AA-106-0303 NAME: ________________

__JPM: GS005 OPERATOR TRAINING PROGRAM DATE: ________________

___Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Containment Atmosphere Control TASK: STEP NO. Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches (*Denotes a Critical Step) I

ELEMENT (#Denotes a Sequential Step) STANDARD # EVAL StU COMMENTS (Required for UNSAT evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue. CUE I ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtainsllocates procedure HC.OP-EO.ZZ-0318.

Operator obtains the correct procedure.

Operator reviews precautions and limitations.

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

Operator determines beginning step of the procedure Operator determines correct beginning step to be 5.1.1. Page 4 of 21

TQ*AA*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 STEP NO. ELEMENT 5.1.1 VENT the containment via the Hard Torus Vent as follows: A. ENSURE that all prerequisites have been satisfied in accordance with Section 2.0 of this procedure.

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

5.1.1 B. NOTIFY the Emergency Duty Officer that containment venting via the Hard Torus Vent will be performed.

CUE Acknowledge the communication to the EDO. 5.1.1 C. In the Lower Relay Room, Elev 102'atpanel1YF404(see Attachment 2), INSTALL F22 (6 amp fuse). (*Denotes a Critical Step) I

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

Operator reviews Prerequisites and ensures Prerequisites complete.

Operator notifies the CRS to notifiy the EDO that containment venting via the Hard Torus Vent will be performed.

Operator directs the field operator to

install fuse F22 at panel 1 YF404. # Page 5 of 21

JPM: OPERATOR TRAINING PROGRAM 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) * (#Denotes a Sequential Step) NO.

WHEN directed to install 1YF404 fuse F22, THEN TRIGGER ET-3 AND REPORT the fuse is installed. " D. DEPRESS ISLN OVRD and Operator depresses the ISLN OVRD ---* OPEN GS-HV-4964 SUPP pushbutton for the HV-4964. #CHMBR TO CPCS DMP. 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. E. ANNOUNCE that containment Operator announces venting will commence at the venting will commence at the South South end of the Reactor Building of the Reactor Building via the via the Hard Torus Vent. Torus Vent over the plant system. TQ-I"\A-106-0303 NAME: DATE: ________________

__ COMMENTS EVAL (Required for UNSAT StU evaluation) I I I I Page 6 of21

JPM: GS005 OPERATOR TRAINING PROGRAM Rev: 04 JOB PERFORMANCE MEASURE SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches STEP ELEMENT NO. F. When HV-4964 SUPP CHMBR TO CPCS DMP is full open, then OPEN GS-HV-11541 TORUS VENT ISOLATION VALVE. Repeat back report from Operator and direct Operator to continue to implement the procedure until a vent path is established.

(*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes that the HV4964 OPEN indicator is illuminated.

Operator observes that the HV4964 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.

Operator informs CRS. Examiner Note: Based on the Initial Conditions, the Reactor Building is NOT accessible.

Manually opening the HV-11541 is not an option. * # * .';':;. ;>.. ilillill" , TQ-MA-106-0303 COMMENTS EVAL (Required for UNSAT S/U evaluation)

"' ..*

...111 1 111: Ii! Page 7 of 21

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

I 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.

I Page 8 of 21 TQ-AA-106-0303 NAME: ________________

__JPM: GS005 OPERATOR TRAINING PROGRAM 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 (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

stu evaluation) 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. VENT the containment via the Drywell Operator determines this path is not supply and ILRT piping as available since it requires access to Reactor Building and the Building is not VENT the containment via the Operator determines the Suppression Suppression Chamber 2" exhaust as 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 TQ-Jo\A-106-0303 NAME: ________________

__JPM: GS005 OPERATOR TRAINING PROGRAM Rev: 04 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Containment Atmosphere Control TASK: STEP NO. Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches (*Denotes a Critical Step) I

ELEMENT (#Denotes a Sequential Step) STANDARD # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.4 A. ENSURE that all prerequisites have been satisfied in accordance with Section 2.0 of this procedure.

Operator reviews Prerequisites and ensures Prerequisites complete.

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

5.1.4 B. NOTIFY the Emergency Duty Officer that containment venting of the Suppression Chamber to the Reactor Building will be performed.

Operator notifies the CRS to notifiy the EDO that containment venting of the Suppression Chamber to the Reactor Building will be performed.

CUE Acknowledge the communication to the EDO. 5.1.4 C. DEPRESS ISLN OVRD and OPEN GT-HD-9372A Drwl Purge Vent Exh Dmpr. Operator presses the DRYWELL PURGE SHUT OFF DMPRS ISLN OVRD pushbutton.

# Operator observes the pushbutton backlights.

Page 10 of 21

TQ*I"\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 COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)

Operator presses the DRYWELL

PURGE SHUT OFF DMPRS HD9372A #OPEN pushbutton.

Operator observes the red HD9372A OPEN light illuminates and green CLOSED light extinguishes. D. DEPRESS ISLN OVRD and Operator observes the amber OPEN GS-HV-4964 SUPP RIDDEN light for the HV-4964 CHMBR TO CPCS DMP. OVRD is already 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. E. ANNOUNCE containment venting Operator announces containment of the Suppression Chamber to venting of the Suppression Chamber #the Reactor the Reactor Building over the --_.-Page 11 of 21

TQ-",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 COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) F. When GS-HV-4964 SUPP Operator observes red HV4964 CHMBR TO CPCS DMP is full light is illuminated and green open, then DEPRESS ISLN light is OVRD and OPEN SUPP CHMBR N2 M/U Operator presses ISLN OVRD for the

HV4963. # Operator observes the amber RIDDEN light illuminates.

1-----Operator presses the HV4963 OPEN

pushbutton.

Operator observes the red OPEN light illuminates and green CLSD light extinguishes. WHEN Vent path has established, TRIGGER ET-6 reduce Drywell Page 12 of 21

TQ-I"'\A-106-0303 JPM: GS005 OPERATOR TRAINING PROGRAM 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 COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation) G. When drywell pressure can be Operator informs CRS that maintained below 60 psig, then venting has commenced and CLOSE GS-HV-4963 SUPP drywell CHMBR N2 M/U EXH and HV-4964 SUPP CHMBR CPCS 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, and then state "This JPM is STOP TIME: I 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 Page 14 of21

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

JOB PERFORMANCE 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 CLOSE the MSIVs and IMPLEMENT EOP-101 AND EOP-102 AFTER drywell pressure is raised to approximately 60 RESTORE Instrument Air lAW PLACE Temporary Air Compressor in Trend OW pressure using Insight Item OPEN OVERRIDE and close BCHV-F017 PLACE 'A' RHR pump in drywell spray with the exception of opening the HV-F021 FAIL OPEN an ADS USE Insight Item rhv021(1 ) (set to -0.00 to 0.2) to crack open the F021A as necessary to establish pressure at 60 psig and rising Trigger ET -5 to stabilize OW pressure indications at 62 USE Insight Item rhv017(1) (set to -0.00 to 0.1) to crack open the F017 A as necessary to establish rising RPV ENSLIRE CREF is in service in the ISOLATE/RECIRC Mode lAW ENSURE FRVS is in Service lAW COMPLETE "SimUlator Ready-for-Training/Examination Checklist".

TQ-AA-106-0303 JOB PERFORMANCE MEASURE 2 Event code:

Description:

pcpdw >= 16.2 1/ Drywell Pressure in psia Inserts Feedwater line break and LOCA after drywell preheated 6 Event code:

Description:

ZLHVDPDO(1)

>= 1.0 & ZLPCBLO(2)

>= 1.0 & ZLPCISVO(2)

>= 1.0 9372A + 4963 + 4964 Open lights ON /I Lowers DW press with vent path established.

Event code: Descri ption:

TQ-AA-106-0303 JOB PERFORMANCE MEASURE None None Insert malfunction FW32 to 100.00000 on event 2 None None Insert malfunction FW04A after 60 on event 2 None None Insert malfunction FW04B after 60 on event 2 None None Insert malfunction FW04C after 60 on event 2 None None Insert malfunction MS01 after 90 to 4.00000 on event 2 None None Insert malfunction PC04 on event 4 None None Insert remote RH23B to TAGGED None None Insert remote RH20A to RACK_OUT None None Insert remote ET067 to INSTALLED on event 3 None None Insert remote IAi0 to RUN None None Insert remote EP38 to Emergency Description Feedwater line break inside containment Secondary condensate pump APi37 trip Secondary condensate pump BP137 trip Secondary condensate pump CP137 trip Steam line break in drywell Downcomer break RH23 RHR Pump B RH20 HV-F021A RHR CTMT SPRAY ET067 HV -11541 Torus vent IA 1 0 T em porary station air com pressor EP38 EOP-319, Restoring Instrument Air in an Emergency TQ-AA-106-0303 JOB PERFORMANCE MEASURE None Insert override 6S151 _A_DI to Off HV-11541 OPEN KEY SW (DI) i Insert override 6AR11_B_AO to PRESSURE DRYWELL PR-4960A2

! None 28.00000 on event 5 WIDE RANGE Insert override 6AR11_R-.AO to PRESSURECHAMBER I None None 28.00000 on event 5

WIDE RANGE Insert override 6AR13_B_AO to PRESSURE DRYWELL None None 26.00000 on event 5 WIDE RANGE Insert override 6AR13_R_AO to PRESSURE CHAMBER None None 26.00000 on event 5 WIDE RANGE (AO)

Insert override 6AR11_B_AO after 1 PRESSURE DRYWELL PR-4960A2 None None to 22.00000 in 60 on event 6 WIDE RANGE Insert override 6AR11_R_AO after 1 PRESSURECHAMBER None None to 22.00000 in 60 on event 6 WIDE RANGE (AO) : Insert override 6AR13_B_AO after 1 PRESSURE DRYWELL PR-4960B2 None None *to 22.00000 in 60 on event 6 WIDE RANGE (AO) Insert override 6AR13_R_AO after 1 PRESSURE CHAMBER PR-4960B1 None None *to 22.00000 in 60 on event 6 . WIDE RANGE (AO)

TQ*AA*106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: GS005 Rev # Date Description Validation Required?

01 9/4/2008 This revision converts to HC LOR format, documents validation, Y 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. Corrected typo error at step 5.1.4. F Updated Reference procedure revision number. No Operator actions changed. Added Remote functions for Temp Air Compressor and 319 02 5/6/10 This revision updates the turnover sheet to suppression pool N level from 80 to 83 inches. No changes to operator actions. No validation required.

03 5/9/11 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.

04 1/14/12 Added Overrides to freeze OW pressure indications to prevent Y Simulator aborts. Adds Trigger to delete Overrides when flowpath established.

No changes to operator actions. Validated with 2 ROs on 1/4/12. Avg completion time was 15 minutes.

TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EO DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Control Rod and Drive Mechanism Respond To An Uncoupled Control rod 4000040401 305H-JPM.BF011 REV #: 01 NOH05..IPBF11 E [[] RO OC STA D SRO [K] Archie E. Faulkner DATE: 9/14/11 Instructor . DATE: ///y/;/I I Operations Representative DATE: l}/111( Training Department TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EOD DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Control Rod and Drive Mechanism Respond To An Uncoupled Control rod 4000040401 305H-JPM.BF011 REV #: 01 NOH05JPBF11 E 0 RO [K] STA D SRO [K] Archie E. Faulkner DATE: 9/14/11 Instructor Operations DATE: Training Department

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

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

Simulator/Perform

REFERENCES:

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 ..IPM 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

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 JPM: Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP NO. 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 reviews precautions and limitations. IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator repeats back initiating cue. N/A Examiner Cue: PROVIDE the Operator with the mark-up copy of HC.OP-ST .BF-0001.

Operator reviews precautions and limitations.

# NAME: DATE: EVAL S/U TQ-AA-106-0303

________________

__ COMMENTS (Required for UNSAT N/A Page 4 of 21 TQ-AA-106-0303 NAME: ________________

__JPM: BF011 OPERATOR TRAINING PROGRAM Rev: 01 SYSTEM: TASK: 5.1 CUE 5.2 CUE 5.3 Control Rod and Drive Mechanism Respond To An Uncoupled Control rod ELEMENT Operator determines beginning step of the procedure.

LOG test start time in the Control Room log(s). The start time for HC.OP-ST.BF0001 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.

DATE: ________________

__JOB PERFORMANCE MEASURE (*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U eva I Operator determines correct beginning step to be 5.1. Operator requests the procedure be logged in the Control Room log. 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.

Page 5 of 21

JPM: BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. OBTAIN a computer printout of the current Control Rod Provide copy of 00-7. IF 00-7 printout not available, THEN direct operator to use PPC terminal. OBSERVE proper response of Nuclear Instrumentation OR inserting all Control SELECT a withdrawn Control Rod AND RECORD the initial Control Rod position on Attachment

2. IF Control Rod is at position RECORD final Control Rod Attachment

2. All other blocks are N/A for this rod. OPERATOR TRAINING JOB PERFORMANCE (*Denotes a Critical Step) * (#Denotes a Sequential Step) STANDARD # Operator prints 00-7 from PPC computer terminal.

Operator reviews 00-7 for rod 38-03 position.

Operator reviews the requirement to observe proper response of the Nuclear Instrumentation while withdrawing OR inserting all Control Rods. Operator presses ROD SELECT

MODULE 38-03 pushbutton.

Operator records the initial rod position of 48 on Attachment

2. Page 6 of 21 TQ-/"\A-106-0303 NAME: DATE: COMMENTS EVAL (Required for UNSAT S/U evaluation) Y N Y N

---

BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. OBSERVE approximately 6 gpm total flow through both the insert AND withdraw Stabilizing Valves as indicated on CRID's point B2117. The following two steps will the 1-BF-V138, Cooling Header Check Valve, as required TIS 4.0.5. If a "failed position" is encountered when a single notch insertion is attempted, an alternate position may be selected to insert the rod, provided that guidance is obtained from Reactor Engineering.

In this situation the remarks section of Attachment 3 should document the alternate position utilized. INSERT the selected Control Rod one notch (or as directed by Reactor Engineering)

AND PERFORM the following:

[TIS 4.1.3.1.2, TIS 4.1.3.7] OPERATOR TRAINING JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes approximately 6 gpm total flow through both the insert AND withdraw Stabilizing Valves as indicated on CRID's point 82117. Operator reads NOTE. Operator momentarily presses the ROD MOTION CONTROLS INSERT pushbutton.

Ttt-AA-106-0303 NAME: DATE: ________________

__ COMMENTS* EVAL (Required for UNSAT # S/U evaluation) Y N Flagging* Y N Barriers # Page 7 of21

JPM: Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP NO. ELEMENT ENSURE proper operation of the RPIS. IF the Control Rod was inserted beyond its intended position, THEN IMMEDIATELY WITHDRAW the Control Rod to its intended position AND CONTACT Reactor Engineering . . IF the control rod does not insert to 5.9.3 the next notch after one attempt, PERFORM the following: INDICATE the condition of RPIS indication on Attachment

2. IF 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 TRAINING JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator observes the CONTROL ROD POSITION FOUR ROD DISPLAY, RWM, or CRIDS indicates control rod movement to position 46. 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.

Operator recognizes this step is not applicable and continues at step 5.9.4 Operator then indicates the RPIS indication is SAT on Attachment

2. 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.

NAME: DATE: TQ-AA-106-0303

________________

___ * # EVAL S/U COMMENTS (Required for UNSAT evaluation) Page 80f21

JPM: BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. 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 the uncoupling check. [80009340]

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 position 48 AND PERFORM following while giving the Control Rod a continuous signal: [TIS 4.1.3.6, TIS OBSERVE the following as indication of the Control Rod being coupled: ROD OVERTRA VEL alarm does NOT annunciate.

OPERATOR TRAINING JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator reads NOTE and determines the NOTE is not applicable.

Operator simultaneously presses AND holds both the WITHDRAW pushbutton AND the CONTINUOUS WITHDRAW pushbutton.

N/A Operator observes OHA C6-F3 ROD OVERTRA VEL DOES annunciate.

Page 9 of 21 TQ-AA*106-0303 NAME: DATE: ________________

_ COMMENTS* EVAL (Required for UNSAT # StU evaluation) Y N Barriers* #

---JPM: BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. -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. B. INDICATE on Attachment 2 the condition of Coupling Check. TQ-AA-106-0303 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # StU evaluation)

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

Operator observes the red FULL OUT light on the Fu" Core Display EXTINGUISHES. Operator observes RPIS does NOT indicate position 48. Operator recognizes the expected response of the Nuclear Instrumentation while withdrawing the Control Rod. Examiner Note: The expected response for a rod from 46 to 48 is negligible.

I ! Operator indicates the coupling check is UNSAT on Attachment

2. i Page 10 of 21

JPM: BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. PERFORM the following for stall flow: D. IF the CRD over travels, THEN IMPLEMENT HC.OP-AB.IC-0001 (Q), Control Rod. Acknowledge the report and DIRECT the Operator to implement Condition D of HC.OP-AB.lC-0001.

OPERATOR TRAINING JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Based on the Initial Conditions, Operator determines Stall Flow is NOT required.

Operator marks the step "N/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 uncoupled control rod and entry condition into HC.OP-AB.IC-0001.

N/A HC.OP-AB.lC-0001 Condition D Uncoupled Rod and Movement Permitted by RWM OBTAIN Reactor Engineering Operator requests Reactor Engineering guidance to recouple the Control Rod. guidance to recouple the Control Rod. Page 11 of 21 OATE: ________________* EVAL # I S/U COMMENTS (Required for UNSAT evaluation 0.1

0.2 TQ-A.A-106*0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: Rev: 01 SYSTEM: TASK: CUE 0.2.a D.2.b Control Rod and Drive Mechanism Respond To An Uncoupled Control rod ELEMENT INFORM the Operator that Engineer's guidance in IF Reactor Engineering CANNOT be THEN RECOUPLE the Control as INSERT the CRO no more than notches from the point of Single Notch WITHDRAW the Rod to its original position AND expected JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD N/A Operator determines step 0.2 is applicable.

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. DATE: ________________

_ COMMENTS* EVAL (Required for UNSAT # stu evaluation

Y N Flagging# N

___-i Operator observes correct response of the control rod. Page 12 of 21 JPM: BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. PERFORM a coupling check on associated control rod lAW 0001. Provide operator 2 nd marked copy of OPERATOR TRAINING JOB PERFORMANCE NIA (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD NIA HC.OP*ST 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 OVERTRA VEL alarm does NOT annunciate. Red Full Out light illuminates on the Full Core Display. Operator simultaneously presses AND holds both the WITHDRAW pushbutton AND the CONTINUOUS WITHDRAW pushbutton.

Operator observes OHA C6-F3 ROD OVERTRA VEL does NOT annunciate.

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

TQ*""A*106*0303 NAME:

DATE: ________________

__

COMMENTS EVAL (Required for UNSA T # I

__.:..:.::.:.=.;;;;.;;.;..;.,;...:.-_--, evalu * # Y N Barriers Page 13 of 21

JPM: BF011 Rev: 01 SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod STEP ELEMENT NO. RPIS indicates the Control Rod is full out (48). Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. INDICATE on Attachment 2 the condition of Coupling Check. -----.-..........

--.-..........

---.-TQ-AA-106-0303 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

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

Operator observes RPIS indicates Control Rod is full out Operator recognizes the expected response of the Instrumentation while withdrawing Control Examiner Note: The response for a rod at 48 is Operator indicates the coupling is SAT on Attachment Page 14 of 21 I JPM: Rev: BF011 01 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE: TQ-AA-106-0303

________________

__ ________________

__ 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 evaluati HC.OP-AB.lC-0001 Condition D Uncoupled Rod and Movement Permitted by RWM D.3 RESTRICT all further withdrawals of this rod to Single Notch movement until repairs have been completed.

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

I Nt A STOP TIME: Page 15 of21

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

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT 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 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 17 of21

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 5.1 initialed.

ENSURE 00-7 for IC#2 is available COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Event code: Icvposx(6)

> 770 II Rod 38-030vertravel 1

Description:

Senses 38-03 withdrawn past Event code:

et_array(1)

>= 1.0 & Icvposx(6)

<

Description:

Rod 38-03 Overtravel and inserted II Deletes uncoupled rod after it has been inserted more than one notch lAW Event 2 Page 18 of 21

JOB PERFORMANCE SIMULATOR SETUP None Insert malfunction CD043803 Control Rod 38-03 uncoupled Insert malfunction CD043803 on event None Control Rod 38-03 uncoupled 2 delete in 1 Insert override 3A81_G_DI to On on ROD SELECT -ROD DRIFT RESET (01). event 1 Page 19 of 21 TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: BF011 Rev # Date Validation Required?

01 9/14/11 This revision converts to HC LOR format, documents validation, and Y 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 i minutes. i i i I l TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EO 0 DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Reactor Auxiliaries Cooling Respond To A Reactor Auxiliary Cooling Malfunction 4000230401 305H-JPM.ED002 REV #: 06 NOH05JPED02E 0 RO [KJ STA SRO [KJ_._' Steve Dennis DATE: 2/16/12 Instructor

/<1<. -cf't,VL DATE: 9ttCf'JJ---

DATE:

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: c==J

____2_12_0_0_0_A_2_.0_1

___ IMPORTANCE FACTOR: 3.7 3.9 APPLICABILITY:

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

2 of 14

NAME: DATE: 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 "N 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 TCt-r\A-106-0303 NAME: ________________

_JPM: S8010 OPERATOR TRAINING PROGRAM DATE: ________________

_Rev: 05 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

(*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation) PROVIDE the operator the initiating Operator repeats back initiating cue. ' .JiLl!llENTER START TIME OPERA TOR REPEATS T'i .INITIATING CUE: .3" H ".i1'iN": f: START TIME:

it Operator obtains Operator obtains the correct procedure.

Operator determines beginning step Operator determines correct of the procedure.

step to be RESTORE Normal Power to the Operator determines restoration of affected Bus. Power to the bus is not possible lAW (if possible)

Conditions Page 4 of 14

TQ-AA-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 05 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction STEP NO. CAUT 1 ELEMENT 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. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator reviews Caution 1. * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

A2 IF Normal Power cannot be restored:

a. VERIFY Alternate Power is available.

Operator verifies Alternate Power is available by observing the ALTERNATE A FEED liaht on 10C610 is illuminated.

CUE If contacted as the NEO to verify Alternate power is available, REPORT Alternate power appears to be available.

N/A b. TRANSFER Power to the Alternate Power Supply by POSITIONING the RPS MG SET TRANSFER SWITCH to the Alternate position.

[CD324X] Operator turns the RPS MG SET TRANSFER SWITCH to the ALT A position.

# Page 5 of 14

A.3 TQ-AA-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 05 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

(*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation) RESET the 1/2 Scram as Operator turns the key for the RPS A 1 Trip Logic to RESET and back to TURN the key for the Affected # RPS channel(s) to the TURN the key BACK to NORMAL. Operator turns the key for the RPS A2 Trip

Logic to RESET and back to NORMAL. # VERIFY the Scram is reset. Operator verifies the scram is reset observing the 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

TQ-AA-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection TASK: Respond To A Reactor Protection System

(*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSA T NO. STANDARD # StU evaluation) IF the MSIV's are OPEN Operator presses the NUCLEAR STEAM THEN RESET the tripped NSSSS SUPPL Y SHUTOFF SYSTEM Logic as follows: LOGIC A pushbutton. PRESS the NUCLEAR SUPPL Y SHUTOFF TRIP LOGIC A(B,C,D) RESET -Operator presses the NUCLEAR STEAM

SUPPL Y SHUTOFF SYSTEM TRIP #LOGIC C RESET pushbutton. I VERIFY MSIV TRIP LOGIC Operator verifies the MSIV TRIP LOGIC TRI PPED goes off. TRIPPED light for LOGIC A Operator verifies the MSIV TRIP LOGIC TRIPPED light for LOGIC C is extinguished.

Page 7 of 14 TQ-AA-106-0303 JPM: SB010 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: TASK: Reactor Protection System 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, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time. N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: Page 8 of 14

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 i

JOB PERFORMANCE Initial INITIALIZE the simulator to 100% power, INSERT malfunction AFTER RWCU trips and conditions stabilize, ACKNOWLEDGE all overhead and RM11 ENSURE associated Schedule file open and ENSURE associated Events file COMPLETE "Simulator Ready-for-Training/Examination Checklist".

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Initial @Time Event Action Description None None Insert malfunction RP02A RPS MG Set A failure TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 88010 lRev# ' Date Description i Validation Required?

04 9/4/2008 This revision converts to HC LOR format, documents validation, y 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. Updated Reference procedure revision number. No change to a erator actions. 05 12/30/11 Revised Initial Conditions from 97% to 100%. Modified N Malfunction, Remote, Override, and Event list sections for TREX I' event syntax. Updated Reference procedure revision numbers :----__t--____:----o_n_ly,,_.

_N_o_c_h_a_n,9

.....e_s_t_o_operator actions. No validation required.,

STATION: Hope Creek JPM NUMBER: ED002 REV: 06 SYSTEM: Reactor Auxiliaries Cooling System TASK NUMBER: 4000230401 TASK: Respond To A Reactor Auxiliary Cooling Malfunction ALTERNATE PATH: KIA NUMBER: 295018 AA2.02 1M PORTANCE FACTOR: 3.3 3.4 APPLICABILITY:

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

Simulator/Perform

REFERENCES:

HC.OP-SO.ED-0001 HC.OP-AR.ZZ-0002 HC.OP-AB.COOL-0003 TOOLS, EQUIPMENT AND PROCEDURES:

None 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 UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 19

NAME: DATE: 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 You are the Plant Place the BP209 RACS pump in service and secure the AP209 RACS Page 3 of 19

TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction STEP NO. ELEMENT CUE PROVIDE the operator the initiating cue. CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains the correct procedure.

Operator reviews precautions and limitations.

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

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-SO.EO-0001.

Operator reviews precautions and limitations.

N/A Operator determines correct beginning step to be 5.3.1. DATE: COMMENTS* EVAL (Required for UNSAT # S/U Page 4 of 19

TQ-",A-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 06 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Auxiliaries Cooling TASK: Respond To A Reactor Auxiliary Cooling 5.3.1 CUE 5.3.2 ELEMENT ENSURE all prerequisites have been satisfied lAW Section 2.3. Reactor Auxiliaries Cooling Water System is in service. If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.

ENSURE that one of the following valves are OPEN (10C651A):

ED-HV-2537A(B)

HX INLET VLVS. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator ensures that all prerequisites have been satisfied.

Operator then initials the appropriate procedure step. * # I EVAL S/U COMMENTS (Required for UNSAT eva I N/A On 10C651A operator observes the HX INLET VALVES:

HXAE217 INLET red HV2537A 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-AA-106-0303 NAME: ________________

__JPM: OPERATOR TRAINING PROGRAM DATE: ________________

__Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

-STEP ELEMENT NO. OBSERVE the following lights are off for the RACS Pumps going in service: OVLD/PWR FAIL *

INOP

REMOTE For the 1AP209 and/or 1 BP209, as applicable, ENSURE RACS PMP 1 AP209 BKR 52-41011, and/or 1 BP209 BKR 52-42011 CLOSED is on. (10C650E) IF returning a pump to service that has been isolated and drained, PERFORM the following steps as necessary to correct/prevent air binding, otherwise, PROCEED to Step 5.3.6 for a normal start of a standby pump: (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation)

Operator observes the REACTOR AUXILIARIES COOLING PUMPS PUMP Bamber OVLD/PWR FAIL, INOP, and white REMOTE lights are extinguished.

On 10C650E operator observes the RACS PMP BP209 BRKR 52-42011 red CLOSED light is illuminated and green TRIPPED light is extinguished.

Operator determines to proceed to Step 5.3.6, since the Initiating Cue states that the pump was not isolated.

Page 6 of 19

TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: Rev: 06 JOB PERFORMANCE MEASURE DATE: ________________

__ SYSTEM: Reactor Auxiliaries Cooling TASK: Respond To A Reactor Auxiliary Cooling STEP NO. ELEMENT 5.3.6 PRESS REACTOR AUXILIARIES COOLING PUMP A(B)(C) START PB (10C651A).

START comes on. 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 lIS RACS pumps' motor amps. 5.3.7 PRESS REACTOR AUXILIARIES COOLING PUMP B(A)(C) STOP PB. STOP comes on. (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator presses the AUXILIARIES COOLING PUMP B BP209 START Operator observes: The red BP209 START illuminates and the green light AI-6461 is < 180 amps and settles at approximately the same value as the "AI! and "C" RACS pumps' amps. Operator presses the AUXILIARIES COOLING PUMP A STOP Operator observes the green light illuminates and the red START light COMMENTS* EVAL (Required for UNSAT # S/U evaluation)

# * # Page 7 of 19 I

TCol-riA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

_Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

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

N/A Operations Fundamental:

5 seconds after the 'A' RACS pump been secured, the Operator Control Board Awareness the

OHA A2-E2, "RACS TROUBLE"

CRIDS 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.

N/A N/A OPERATOR ACTION: 1. REFER to HC.OP-AB.COOL-0003(Q);

Reactor Auxiliary Cooling System. 2. ENSURE compliance with Operator refers to Technical Specifications HC.OP-AB.COOL-0003.

Containment Isolation Valves. 3. ENSURE compliance Technical Specifications Secondary Containment

,-Page 8 of 19 I A.1 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: ________________DATE: ________________Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction STEP NO. CUE N/A COND A ELEMENT Direct the Operator to perform Condition

'A' of HC.OP-AB.COOL-0003 Reactor Auxiliary Cooling System. HC.OP-AB.COOL-0003 Date/Time PRESS the START P.B. for any available RACS pump in standby. (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # evaluation S/U N/A N/A Operator enters the current Date/Time in the spaces provided.

Operator presses the REACTOR 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

A.2 TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: DATE: ________________

__Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction CUE ELEMENT Respond to any reports of the 'A' RACS pump failure to start by directing the operator to continue implementing Condition

'A' of IF a second RACS Pump CANNOT be placed in service, THEN ISOLATE RACS to the out of service Off-Gas Train as follows: IF the Common Off-Gas Train is in service, THEN CLOSE HV-2S77. IF Unit 1 Off-Gas Train is in service, THEN CLOSE HV-7712A1.

(*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL {Required for UNSAT STANDARD # I StU eval N/A Operator observes the OFF GAS 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 HV2S77 OPEN light extinguishes.

Page 10 of 19 TQ-I"\A-106*0303 JPM: Rev: ED002 06 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE:

________________

_ SYSTEM: TASK: Reactor Auxiliaries Cooling System Respond To A Reactor Auxiliary Cooling Malfunction STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT eval CUE If the Operator Closes HV2577 the JPM may be terminated.

If the operator closes the HV7712A1, allow 1 minute to recognize the mistake and then terminate the JPM. N/A Leaving the HV7712A1 closed and/or causing an isolation of the Common Offgas Train is failure criteria.

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".

N/A 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 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 Page 13 of 19 JOB PERFORMANCE SIMULATOR SETUP 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 ENSURE NON -1 E BKR 52-42011 is OPEN Deseri' ENSURE simulator is reset. Event code:

cwnra209 <= 0.5 II AP209 RACS pump normalized pump speed

Description:

! Trips BP209 RACS pump after the AP209 RACS pump is stopped Event code:

Description:

Page 14 of 19

JOB PERFORMANCE SIMULATOR SETUP Initial None RACS pump BP209 trip Descri i AP209 START-REACTOR None Insert override 5A33_E_DI to Off AUXILIARIES COOLING PUMP-PUMP Page 15 of 19

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

CW08B Trip of BP209 RACS pump. 5 sec 5A33 E 01 AP209 RACS pump start pushbutton.

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 Y converts to HC LOR format, documents validation, and generates estima!t:l9completion time. 02 8/26/08 Updated reference procedure revisions.

Corrected previous typo N error in procedure step A.2. No change in operator actions from previous revision.

No validation required.

03 9/9109 Updated reference procedure revisions.

No change in operator N actions from previous revision.

No validation required.

04 9/12/11 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.

05 12/30/11 Updated reference procedure revisions.

No change in operator N actions from previous revision.

No validation required.

06 2116/12 Added critical Step at 5.3.4 -NON -1 E BKR 52-42011 is OPEN Y for setup and must be closed during JPM performance.

Revalidated by an RO and SRO

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 TASK ...'PM SAP ALTERNATE PATH: APPLICABILITY:

EO DEVELOPED BY: REVIEWED BY: APPROVED BY: ERFORMANC Hope Main Install Jumpers To Bypass MSIV Low Level Interlock 2000010501/200059054 305H-JPM.AB001 REV#: NOH05JPAB01 D RO [KJ ST A '------' SRO [KJ Archie E. Faulkner DATE: 9/4/08 Instructor DATE:

Operations Representative DATE: Training Department gztg:JJ--

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: D KIA NUMBER: 239001 A2.03 IMPORTANCE FACTOR: 4.0 4.2 APPLICABILITY:

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

Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0301, Rev. 6 TOOLS 1 EQUIPMENT AND PROCEDURES:

None ESTIMATED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: D SAT 0 UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE: Page 2 of 13 NAME: DATE: 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 AB001 Rev: 07 SYSTEM: Main Steam OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE:

TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock STEP NO. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT evaluation)

I CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue. ENTER START TIME AFTER OPERA TOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains and locates procedure HC.OP-EO.zZ-0301.

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.

Page 4 of 13 AB001 OPERATOR TRAINING PROGRAM Rev: 07 JOB PERFORMANCE MEASURE DATE: __________....... SYSTEM: Main TASK: Install Jumpers To Bypass MSIV Low Level Isolation

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

4.0 EQUIPMENT

Operator obtains the following required *equipment: EOP-301 Implementation Kit (OS EOP-301 Implementation Kit from NSS Office EOP Drawer) Office EOP drawer Contents:

4 Banana Plug Jumpers OR 1 Flashlight Key #9 from OS Office or key from OR break glass key holder in OSC for OSC Key #9 for EOP Locker in OSC EOP locker (obtain from OS office or break red AND key holder glass in OSC) EOP-301 Implementation kit from the AND EOP Locker in EOP-301 Implementation Kit Locker in OSC). Examiner Note: After operator Contents:

4 Banana Plug Jumpers demonstrated ability to required equipment, ensure that 1 Flashlight equipment is returned to its appropriate storage location.

Operator determines beginning step Operator determines the correct of the beginning step to be 5.2. ENSl1REthat allprerequisiteshave Operator ensures that all prerequisites been satisfied JAW Section 2.0 of this have been satisfied.

procedure.

__

___ Ifexcessive time is taken reviewing , prerequisites, inform operator that ,,: all are satisfied. " Page 5 of 13 Tl A-106-0303 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

(*Denotes a Critical COMMENTS* ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # StU evaluation) At panel 10C609 Div. 1 (front) Operator installs jumper between the INSTALL a jumper in the red and red and black jacks labeled B21 black jacks labeled: K212A T1-M1 B21H-K212A T1-M1 OP-EO.ZZ-301 (fourth column, first the jumper has been installed as you have indicated.

/:';'., '.' . r At panel 10C609 Div 3 (front) Operator installs jumper between the *INSTALL a jumper in the red and red and black jacks labeled 821 black jacks labeled: K212C T1-M1 B21H-K212C T1-M1 OP-EO.ZZ-301 (fourth column, first .The jumper has been installed as I*I*. .' N you have

..... I; '.i. . :. I, ........, At panel 1 OC611 Div. 2 (front) Operator installs jumper between the *INSTALL a jumper in the red and red and black jacks labeled 821 black jacks labeled: K212B T1-M1 B21H-K212B T1-M1 OP-EO.ZZ-301 (10C611 (fourth column, first CUE The jumper has been installed as I',* .' I**** *.you have I.... * , Page 6 of 13 Tt... .A-106-0303 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 5.2.5 At panel 10C611 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) CUE The jumper has been installed as you have indicated.

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

Operator installs jumper between the *red and black jacks labeled 821 K212D T1-M1 HC.OP-EOZZ-0301 (10C611).

Page 7 of 13

JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUr,,1ENTATION 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: SAT UNSAT Page 8 of 13 TQ-AA-106 a 0303 JOB PERFORMANCE MEASURE INITIAL COND!TIONS: 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-106 m 0303 JOB PERFORMANCE SIMULATOR SETUP

INITIALIZE the simulator to 97 power, MOL. Lock the reactor Mode Switch in Shutdown Take actions of HC.OP-AB.zZ-0001 Attachment 1 Initiate SLC. Trip the Main Turbine. Ensure the MSIVs are open. Ensure the Main Condenser is available . . Place the simulator into Freeze. i Initial i COMPLETE "Simulator Ready-for-TrainingfExamination EVENT ACTION: COMMAND:

EVENT ACTION: 2 Page 10 of 13

JOB PERFORMANCE SIMULATOR SETUP INSTRJCTIONS (OPTIONAL) 07 Half Core ATWS -Right None ET-1 EP02 EOP-311 Bypass PCIG (-129") isolation EP05 EOP-319 LOCA Level 2 interlock EMERG Initial Descri tion Page 11 of 13 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AB001 I Rev # 07 Date 9/4/2008 1 Description This revision converts to HC LOR format, documents validation, and generates estimated completion time. Since Critical 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. Validation Required?

Y ..... I TASK JPM SAP ALTERNATE PATH: APPLICABILITY:

EO DEVELOPED BY: REVIEWED BY: APPROVED BY: JOB PERFORMANCE MEASURE Hope Creek Safety Auxiliaries Cooling Water Respond To A SACS Malfunction 400780401 305H-JPM.EG003 REV #: 17 NOH05JPEG03E D RO [KJ STA D SRO [KJ Archie E. Faulkner DATE: 12/30/11 Instructor DATE: I;; c/;z DATE:1/1 Training Department

STATION: Hope Creek JPM NUMBER: EG003 REV: 17 SYSTEM: Safety Auxiliaries Cooling Water TASK NUMBER: 400780401 TASK: Respond To A SACS Malfunction ALTERNATE PATH: D KIA NUMBER: __4_00_0_0_0_A_2._0_1

__ APPLICABILITY:

EOD ROCK] IMPORTANCE FACTOR: STAD SROCK] 3.3 RO 3.4 SRO EVALUATION SETTING/METHOD:

Reactor Building/Simulate

REFERENCES:

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

TQ-AA-106-0303 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, Safety/Turbine Auxiliaries Cooling System, is Components are being realigned lAW Section 5.12 of HC.OP-SO.EG-0001. The '0' 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 CUE: 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

,.-\-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: ________________

__ Rev: 17 SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction STEP NO. ELEMENT PROVIDE the operator the initiating cue. ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: START TIME: Operator obtains/locates procedure HC.OP-SO.EG-0001.

Operator reviews precautions and limitations. If excessive time is taken reviewing Precautions and Limitations, inform operator that all are satisfied. FRVS CLG COIL DVH-213 LP B SUP 1-EG-V689 LOCKED CLOSED JOB PERFORMANCE DATE: ________________

__ (*Denotes a Critical COMMENTS* (#Denotes a Sequential EVAL (Required for UNSAT #

Stu eval Operator repeats back initiating cue. N/A Operator locates the proper procedure.

Operator reviews precautions and limitations.

Examiner Note: The sequence critical portion of the following steps is to close the 1-EG-V689 AND 1-EG-V692 BEFORE opening the 1-EG-V703 OR 1-EG-V702.

Operator unlocks 1-EG-V689.

Examiner Note: Support operator's requests for Verifier.

Page 4 of 12 10

TO-*..--\-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 SYSTEM: TASK: CUE CUE CUE ATT.3 CUE Safety Auxiliaries Cooling Water Respond To A SACS Malfunction 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.

JOB PERFORMANCE MEASURE DATE: (*Denotes a Critical Step) COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # StU evaluatio N/A 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 operators requests for Verifier.

N/A Page 5 of 12 11

TQ-",A-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction STEP NO. ELEMENT CUE The valve indicated has been rotated in the direction stated and has come to hard stop. CUE The lock is installed on the valve indicated.

ATT.3 FRVS CLG COIL DVH-213 LP A SUP 12 1-EG-V703 LOCKED OPEN CUE The lock has been removed from the valve indicated.

JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD Operator closes 1-EG-V692.

N/A Operator reinstalls a locking device on valve 1-EG-V692.

N/A Operator unlocks 1-EG-V703.

Examiner Note: Support operator's requests for Verifier.

N/A Operator opens 1-EG-V703.

DATE: ________________

_ COMMENTS* EVAL {Required for UNSAT # S/U * # * # Page 6 of 12

13 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: Rev: 17 SYSTEM: TASK: Safety Auxiliaries Cooling Water Respond To A SACS Malfunction 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. JOB PERFORMANCE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD N/A 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. Page 7 of 12 DATE: COMMENTS* EVAL (Required for UNSAT #

evaluation

#

TQ-, ,r\-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. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluati 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 U NSAT ,-I____-----' QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 9 of 12

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: SACS Loop B has been declared inoperable. HC.OP-AB.COOL-0002, Safety/Turbine 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 I Rev#

Date Validation Required?

y 13 8/28/2008 Revised to new JPM format. Revalidated .JPM time. Updated reference procedure revision number. Operator actions did not change. 14 12/1/2008 Updated Procedure revision numbers. No effect on JPM. N 15 9/9109 Updated Procedure revision numbers. No change to operator N

actions. No validation required.

I *16 4/27/10 Updated Procedure revision numbers. No change to operator N actions. No validation required.

17 5/9111 Updated Procedure revision numbers. No change to operator N actions. No validation reguired.

STATION: 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 APPLICABILITY:

EO D RO [KJ IMPORTANCE FACTOR: STA D SRO [KJ 4.1 RO 4.2 SRO EVALUATION SETTING/METHOD:

Plant/Simulate

REFERENCES:

HC.OP-AB.RPV-0006 Rev. 3 TOOLS, EQUIPMENT AND PROCEDURES:

HC.OP-AB.RPV-0006 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 SIGNATURE:

DATE: Page 2 of 12

TQ-AA-106-0303 NAME: DATE: SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve TASK NUMBER: 4000210401 INITIAL CONDITIONS:

1. The Reactor is shutdown due to the "0" SRV being electrically held open with both Logic Train Band 0 solenoids. HC.OP-AB.RPV-0006 Safety Relief Valve, is being executed. Attempts to close the SRV from the Main Control Room have INITIATING CUE: Use the fuse pullers provided (simulated) to pull the fuses for the "0" SRV lAW HC.OP-AB.RPV-0006.

Page 3 of 12

TQ-AA-106-0303 JPM: AB00302 OPERATOR TRAINING PROGRAM NAME: Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________

_ SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve STEP NO. (. Denotes a Critical Element of a Critical Step) ELEMENT CUE PROVIDE the operator the initiating cue. ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME: Operator obtains the correct procedure.

...... Operator reviews Immediate Operator Actions, Retainment Overrides, applicable Cautions and Notes. 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. (*Denotes a Critical Step) STANDARD *

EVAL S/U COMMENTS (Required for UNSAT Operator repeats back initiating cue. I N/A Operator obtains procedure HC.OP-AB.RPV-0006 Operator reviews Immediate Operator Actions, Retainment Overrides, applicable Cautions and Notes. 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

JPM: AB00302 OPERA TOR 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 COMMENTS(*Denotes a Critical Step)

of a Critical EVAL (Required for UNSATSTANDARD eS/U evah Y N STAR Att 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 (Panel labeled H11-P628)

DIV 2). The fuse that you have indicated is N/A pulled. I Y N STAR Att At panel 10C628 (ADS DIV 2) the Operator simulates pulling fuse I

I operator pulls fuse 821 C F4D F10. Logic 821 C F4D F10 at panel 10C628 (ADS 8 (Panel labeled H11-P628)

DIV2}. The fuse that you have indicated is N/A pulled. Att At panel 10C631 (ADS DIV 4) the Operator simulates pulling fuse I

I I Y N STAR operator pulls fuse 821 C F7D F9. Logic 821C F7D F9 at panel10C631 (ADS D (Panel labeled H 11-P631 ) DIV 4). The fuse that you have indicated is N/A pulled. Y N STAR Att At panel10C631 (ADS DIV 4) the Operator simulates pulling fuse operator pulls fuse 821 C F8D F10. Logic 821 C F8D F10 at panel 10C631 (ADS D (Panel labeled H11-P631)

DIV 4). The fuse that you have indicated is N/A pulled. Page 5 of 12 TQ-rlA-106-0303 Rev: AB00302 02 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: DATE:

SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve STEP NO. (e Denotes a Critical Element of a Critical Step) ELEMENT (*Denotes a Critical Step) STANDARD *

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".

N/A STOP TIME: Page 6 of 12

OPERATOR TRAINING EVALUATOR FOLLOWUP QUESTION NAME: DATE: JPM Number: AB00302 TASK: Respond to a Failed Open Safety Relief Valve TASK NUMBER: 4000210401 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT Page 7 of 12

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: AB00302 REV#: 02 ENSURE a copy of HC.OP-AB.RPV-0006 is available.

EVENT 1 Page 8 of 12

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: AB00302 REV#: 02 NONE NONE NONE NONE NONE NONE NONE Page 9 of 12

JOB PERFORMANCE MEASURE REVISION JPM NUMBER: Il.... __ Rev # Date Description 02 5/7/09 Updated to new ..IPM Template.

Revised to add both SRV D Y

solenoids.

Validated with operators from A Shift. Avg time 13

minutes. Page 10 of 12

JOB PERFORMANCE MEASURE INITIAL CONDITIONS: The Reactor is shutdown due to the "0" SRV being electrically held open with both Logic Train Band 0 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.

INITIATING CUE: Use the fuse pullers provided (simulated) to pull the fuses for the "0" SRV lAW 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: NOH05JPPK01E ALTERNATE PATH: D APPLICABILITY:

EO [KJ RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor I /;;. d;;.:<.REVIEWED BY: DATE: APPROVED BY: DATE: WCW-///t//? Training Department

STATION: Hope Creek JPM NUMBER: PK001 REV: 02 SYSTEM: DC Electrical Distribution TASK NUMBER: 4000020404 TASK: Respond To A Station Blackout ALTERNATE PATH: D KIA NUMBER: __2_9_5_0_03_.AA_1_.0_4

__ IMPORTANCE FACTOR: 3.6 3.7 APPLICABILITY:

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

PlantlPeliorm

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 i

TQ-AA-106-0303 NAIVI E: 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/OIESEL GENERATOR MALFUNCTION has been completed through step 4.5.4. INITIATING IMPLEMENT Attachment 3, Radwaste Building Actions of Page 3 of 14

________________

__ JPM: Rev: 02 SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP NO. 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.

OPERATOR TRAINING NAME: JOB PERFORMANCE DATE: (*Denotes a Critical Step) * (#Denotes a Sequential Step) EVAL STANDARD StU# Operator repeats back initiating cue. m N/A _ Operator obtains procedure HC.OP-AB.ZZ-0135(Q).

Operator determines correct beginning step to be 4.5.5. I Operator locates Attachment

3. I I COMMENTS (Required for UNSAT evaluation)

Page 4 of 14 JPM: PK001 Rev: 02 SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP ELEMENT NO. Attach OPEN the circuit breakers in 3 following tables when plant entered an Step CLOSE the circuit breakers in the following tables when restoring offsite power. All are ARC Flash Category O. 18D318 0 Circuit 12 The breaker you have indicated is open. o Circuit 19 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U eval Examiner Note: A map showing panel locations is provided on the bottom of Attachment

3. Operator locates panel 1 B0318 in Room 3449. Operator simulates opening breaker 12 I

on 80318. N/A Operator simulates opening breaker 19

on 80318. Page 5 of 14

JPM: PK001 Rev: 02 SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP ELEMENT NO. 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 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE DATE: ________________(*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation)

N/A Operator simulates opening breaker 24 on 80318. N/A Operator simulates opening breaker 27 on 80318. N/A Operator locates panel1A0318 in Room 3449. Operator simulates opening breaker 12

on A0318. Page 6 of 14

JPM: PK001 Rev: 02 SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP ELEMENT NO. The breaker you have indicated is open. o Circuit The breaker you have indicated is open. o Circuit 28 The breaker you have indicated is open. 1DD318 o Circuit 11 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE DATE: ________________(*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluatio N/A Operator simulates opening breaker 27 on AD318. N/A Operator simulates opening breaker 28 on AD318. N/A Operator locates panel 100318 in Room 3432. Operator simulates opening breaker 11

on 00318. Page 7 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM Rev: 02 JOB PERFORMANCE MEASURE DATE: ________________SYSTEM: DC Electrical TASK: Respond To A Station

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

S/U eval The breaker you have is open. Circuit 12 Operator simulates opening breaker on The breaker you have is open. Circuit 14 Operator simulates opening breaker 14 on The breaker you have is open. Circuit 27 Operator simulates opening breaker 27 on The breaker you have is open. Page 8 of 14

JPM: PK001 Rev: 02 SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout STEP ELEMENT NO. 1CD318 o Circuit 11 The breaker you have indicated is open. o Circuit 12 The breaker you have indicated is open. o Circuit 14 CUE The breaker you have indicated is open. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical COMMENTS* (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluatio Operator locates panel 1 CD318 in Room 3432. Operator simulates opening breaker 11

on CD318. N/A Operator simulates opening breaker 12 on CD318. N/A Operator simulates opening breaker 14 on CD318. 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. ELEMENT (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # EVAL StU COMMENTS (Required for UNSAT eval o Circuit 27 Operator simulates opening breaker 27 on CD318. CUE The breaker you have indicated is open, 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 N/A operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: Page 10 of 14

JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUIVIENTATION NAME: DATE: JPM Number: PK001 TASK: Respond To A Station Blackout TASK NUMBER: 4000020404 QUESTION:

RESPONSE:

RESULT: SAT UNSAT QUESTION:

RESPONSE:

RESULT: SAT UNSAT 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/DIESEL 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 # Date Description Validation Required?

00 10/13/09 Converted NRC 2007 JPM 009 to new JPM format. This revision Y includes latest revision to HC.OP-AB.ZZ-0135.

Validated with 2 operators from "AI! Shift. Estimated Completion time 20 minutes. 01 5/12/11 Updated Reference procedure revision numbers only. No N changes to operator actions. No validation required.

02 1/14/12 Updated Reference procedure revision numbers only. No N changes to operator actions. No validation required.

SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM: REVISION

SUMMARY

1. NOTE added to delay ET-5 PREPARED BY: APPROVED BY: APPROVED BY: NRC SCENARIO Effective when 80 01 '---_-----'

L.O. X I INITIAL '---_-----'

OTH until RPV level has recovered to ..:..12.5 inches. Steve Dennis 2/15/12 Instructor DATE . r DATE LORT Group t6ad or Designee 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 ! Manual scram LOP! 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. "A" 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 steam 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). "A" 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: 01

INITIALIZE the simulator to full power, MOL. ENSURE A CRD pump is in service. ENSURE B T ACS 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. CIT 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 'B' EHC 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 equivalent COMPLETE the Simulator Ready for Training/Examination Checklist.

Initial ET # Event code:

Description:

Event code:

Description:

Event code:

Description:

Event code:

Description:

ESG-NRC-S1 Page 3 of 24 Rev: 01 Initial @Time Event Description None None Insert malfunction TC07B EHC pump B trip None None Insert malfunction DGO 1 A Diesel generator A failure to start Diesel generator B emergency start signal None None Insert malfunction DG07B failure Diesel generator B breaker failure to auto None None Insert malfunction DG08B close None None Insert malfunction DGO I C Diesel generator C failure to start None None Insert malfunction DG02D Diesel generator D failure Insert malfunction MS09A to 100.00000 Steam line header pressure transmitter N076A None None on event 1 fails None None Insert malfunction CD 1 OA 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 lOA403 None None Insert malfunction CWl4A on event 3 Service water pump AP502 fail to auto start Insert malfunction RR31Al to 20.00000 in Recirc loop A small break [V] (1 gpm, None None 600 on event gpm) Seismic Event II None None Insert malfunction PC07B on event 5 None None Insert malfunction EG 12 on event 5 Loss of all off site power I None None Insert malfunction HP06M on event 5 HPCI aux oil pump -oil line break None None Insert malfunction RCO] on event 5 RCIC turbine overspeed Insert malfunction RR31A2 to 4.00000 in Recirc loop A large break [V] (1 None 60 on event 5 gpm, 1000/0-60000 gpm) Insert malfunction DG07B on event 7 Diesel generator B emergency start signal Non ne delete in 1 failure Insert malfunction RCO 1 on event 8 delete None RCIC turbine overspeed Insert malfunction DGOIA after 1 on None Diesel generator A failure to start 12 delete in 1 * , ESG-NRC-S1 Page 4 of Rev: 01 I None Insert remote Re02 after 5 to RESET on event 8 None None Insert remote HP08 to TAGGED on event None None Insert remote eXIl after 60 to OPEN on event 11 None None Insert remote eX15 after 120 to OPEN on event 11 None None I11.'lert remote eXl? after 180 to OPEN on event 11 RC02 RCIC overspeed trip reset HP08 HPCI Aux Oil Pump eXIl ex valve AP-V041 to Core Spray header A eXI5 ex valve AP-V044 to RHR header A eXl? ex valve AP-V04? to RHR headerC Raise Power with Recirc: After the Crew assumes the watch.

Failure: After.the Crew assumes the watch and at the discretion of the Lead Examiner,TRIGGER ET-1 ('A' NSSSS MSL Pressure Transmitter Fails High). Transmitter is located in TB Electrical Mezzanine.

IF dispatched to transmitter, THEN REPORT there is no visible damage to transmitter. 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.

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 An CRIDS D2636 "NON-MSIV INBD SYS OUT OF SVCE CHAO! 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 'A' NSSSS Channel from generating an MSIV isolation signal on Low Main Steam Line pressure.

ESG-NRC-S1 Page 6 of Rev: 01 TIS Table 3.3.2-1 Trip

CRS recognize the following TIS Function 3c. applies Isolation Actuation Instrumentation

3.3.2 action

b.1.c applies (24 hours1 days 0.143 weeks 0.0329 months to place in a tripped condition).

If requested, after an

Crew may implement appropriate delay, support GP.ZZ-0011 to place trip units actions of placing trip units in into tripped condition tripped condition by changing MALF MS09A severity to O. A CRD Pump Trip:

RO recognizes

'A' CRD pump After the Crew addresses Tech trip by: Specs for the PT-N076A and at =:> OHA C6-F2 "CRD SYSTEM the discretion of the Lead TROUBLE" Examiner, TRIGGER ET-2. =:> CRIDS D2244 "CRD WATER PUMP A MOTOR" Flashing OVLD/POWER FAILURE bezel for A CRD Pump" IF dispatched to investigate the

RO reference ARP. CRD Pump trip, THEN REPORT the A CRD pump speed changer inboard bearing has overheated.

IF dispatched to investigate the trip of A CRD Pump Breaker, THEN REPORT breaker 43711 is tripped on overcurrent. RO starts "B" CRD pump lAW ARP as follows: PLACE DRIVE WTR FLOW controller in MANUAL AND SET to O. ESG-NRC-S1 Page 7 of Rev: 01 Earthquake/10A403 Bus After the Crew restores and at the discretion of Lead PLAY the Earthquake Sound Effect (if available) at .rTIedium volume for about 20 seconds OR ANNOUNCE "You feel motion then. it stops" TRIGGER"ET w3 (Seismic Eventl10A403 Bus Loss) IE Crew calls Earthquake THEN REPORT a event of 6.0 on Richter centered 12 miles east Wilmington, IF Crew calls THEN REPORT the system is 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 1 OC650C Loud rumbling (if

Crew monitors critical parameters to determine if plant is stable.

CRS implements AB.MISC-0001

Condition E Condition F AB.MISC-0001 actions provided for reference only. Due to the pace of the scenario, it is unlikely they will be implemented.

Page 8 of 24 Rev: 01 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 FDR TO USS XFMER BRKR MALF => OHA D3-E3 120VAC UPS TROUBLE => Flashing TRIP lights for 10A403 Infeed breakers CRS implements AB.zZ-0172.

ESG-NRC-S1 Page 9 of Rev: 01 IE dispatched to align AP to 'A' Core Spray and A & C RHR THEN: TRIGGER ET*11 to open AP-V044N04 7 N041 CRS directs PO to complete AB.ZZ-0172 Subsequent Actions. PO ensures A SACS pump is in service. PO ensures B T ACS 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.B.3.1.a.3.

a) Action a. applies (B hours to energize the channel).

=> 3.B.1.1 Perform Power Distribution lineup within one hour. Page 10 of 24 TIS Rev: 01 Small Break LOCA: 20 minutes after the earthquake OR, at the discretion of the Lead Examiner, TRIGGER ET-4. Crew recognizes LOCA condition: OHA C6-B1 "DLD SYSTEM ALARMITRBL" RM11 9AX314 DLD FLOOR DRN FLOW alarm RM11 9AX317/318/320 OLD CCM alarms OHA D3-C3 "DRYWELL SUMP LEVEL HI/LO" OHA A4-F5 "COMPUTER PT IN ALARM" OHA A7-E4 "DRYWELL PRESSURE HI/LO" Rising Drywell Pressure on various indicators CRS implements 0006: Condition A Condition B Condition C CRS implements 0001: Condition A 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-I'JRC-S1 Page 11 of Rev: 01 Aftershock/LOP/LOCA:

NOTE: Ensure RPV level has recovered to +12.5 before ET -5 is triggered.

At the Lead Examiners discretion, PLAY the Sound Effect (if available) at medium v()lumefor about 20 seconds OR ANNOUNCE "You Jeel moti.on 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: => aHA C5-A4 "RPV WATER LEVEL La" => aHA A 7 -D5 "RPV LEVEL 3" => Various water level indicators

Crew recognizes Loss of Offsite Power by: => aHA "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: 01

.' ? '. .. . ..

SCENARIO G IF directed to start the 'B' THEN TRIGGER ET-7 REPORT 'B' EOG IE dispatched to investigate failure of '0' EOGs to THEN REPORT '0' EOG Lube Oil Low Shutdown alarm. There is on '0' EOG room Crew recognizes failure of the A/B/O EOGs to start and load by: Engine STOP lights Output breaker TRIP lights OVLO/PWR lights on associated Channel components RO/PO attempt to start the A/B/O EOGs. RO/PO close 'B' EOG output breaker. Crew starts the 18' EDG by EITHER: Pressing the 18' EDG START pushbutton in the Control Room, OR Directing an operator to locally start the 18' EDG, AND Closes 18' EDG output breaker. CRS implements AB.zZ-0135. Crew dispatches NEO and/or Maintenance to investigate failure of 0 EOG to start. Only 'B' EOG will start from the Control Room. 'C' EOG 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: 01 IE dispatched to investigate failure of the "A' EDG to THEN REPORT there is blown fuse on DC Circuit 3 the AC421 IF directed to start the using either local THEN REPORT it did not (AR.KJ-0001 Att. IE 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 IF dispatched to RCIC THEN REPORT the device is Crew dispatches NEO and/or 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: 01 IF 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 HIILO" => Various Suppression Pool level indicators CRS recognize RPV level continues to lower and Emergency Depressurization is required. WHEN RPV water level reaches -129", THEN 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: 01

* *

IF directed to restore the 'A'

EDG to service, AND after level has been restored with 'B' EDG, THEN TRIGGER ET-12 AI\ID 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-102. 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: 01 Termination Requirement:

RO/PO places 'A' RHR pump The scenario should be Drywell Spray lAW terminated at the discretion the Lead Examiner The reactor has been depressurized RPV water level is being maintained above -129" Drywell Spray is initiated.

ESG-NRC-S1 Page 17 of Rev: 01 A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG) G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel J. OP-AA-1 01-111-1004 Operations Standards K. OP-AA-101-112-1002 On-Line Risk Assessment L. OP-AA-106-101-1001 Event Response Guidelines M. OP-HC-108-106-1001 Equipment Operational Control N. OP-AA-1 08-114 Post Transient Review O. OP-HC-1 08-115-1 001 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: 01 ESG-NRC-S1/01

1. Crew starts the tB' EDG by Pressing the 'B' EDG START pushbutton in the Control OR Directing an operator to locally start the tB' EDG, AND Closes tB' 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. AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF AA 1.02 Emergency generators RO 4.2 SRO AA 1.03 Systems necessary to assure safe plant shutdown RO 4.4 SRO The 'A' RHR pump is not available because of failure of 'A' 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 1 OA401, 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 Before 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". KIA 295031 Reactor Low Water EA 1. 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: 01

ESG-NRC-S1 101 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT Y Loss Of Offsite Power/SBO 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 COMPONENT/TRAIN/SYSTEM THAT INCREASES CORE DAMAGE YIN KEY KEY EQUIPMENT 1 E 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 ___ A1BRHR ___ 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 OPERATOR ACTION 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 Rev: 01 Rx Power: WorkWeek: Risk Color: Activities Completed Last Tagged BP116 EHC pump for discharge line leak Major Activities Next 12 Release BP116 after leak Protected AP116 EHC Tagged BP116 EHC ESG-NRC-S1 Page 21 of 24 Rev: 01

EXAMINATION SCENARIO GUIDE (ESG) 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 tllis form to each scenario reviewed. CHECK ESG-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 events. 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 ___ 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. 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). Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

___ 8. If time compression techniques are used, scenario summary clearly so indicates.

___ 9. The simulator modeling is not altered. 10. All crew competencies can be evaluated.

11. Appropriate reference materials are available (SOERs, LERs, etc.) 12. Proper critical task methodology used lAW NRC procedures.

ESG-NRC-S1 Page 22 of Rev.: 01

---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-S1 ESG: SELF*CHECK

1. Total malfunctions inserted:

4-8/10-14 2. Malfunctions that occur after EOP entry: 1-4/3-6 3. Abnormal Events: 1-2/2-3 4. Major Transients:

1-2/2-3 5. EOPs used beyond primary scram response EOP: 1-3/3-5 6. EOP Contingency Procedures used: 0-3/1-3 7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes) 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.: 01

EXAMINATION SCENARIO GUIDE (con't) Crew Validation Rev: 00 Date Validated: Validated with a 3 man crew from B Shift. Runtime 80 Validation Comments Disposition y/////////////////////////////////////////////////////////////////

////////////////////////////////////////////////////////////////////////////////////////////////////////////////, The crew thought the scenario was pretty tough for a 3 man crew. -=-D=is.:.:.agliLr..c::.e-=-e.:.....;R...;..e:.;.m'-'-a=i:.;.ns:.;.a:.;.s:.;.i;.::.s-=-.

______________

_ Crew Validation Rev: Date Validation Comments W//////////////////////////////////////////////////////////////////////////////////////////////

//////////////////////////////////////////////////////////////////////////////////, ESG-NRC-S1 Page 24 of 24 Rev.: 01 SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM: REVISION

SUMMARY

NRC SCENARIO 2 ESG-NRC-S2 Effective when approved.

75 minutes 01 x I L.O. REQUAL INITIAL LICENSE OTHER'-------" 1. Added a malfunction to trip the RFPT operating for level control following the A TWS 2. Minor Typo changes PREPARED BY: Steven Dennis 2/15/12 Instructor APPROVED BY: 'DATE APPROVED BY: 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 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 RFPT Trip 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 scram. 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 operating RFPT will trip requiring use of another RFPT or RCIC for level control. 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.: 01

INITIALIZE the simulator to 100% power, 3840 MWt REDUCE Reactor power to 84.5% using reactor recirc pumps and control Stick control rod 46-47 at position 00 using ETRemove C RFPT from service and place recirc at 1000 rpm lAW Remove Crossflow from service and clear Overhead ENSURE A EHC Pump is in ENSURE associated Schedule file open and ENSURE associated Events file INITIAL 10-6 for Power APPLY 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 Data Collection is trending the following parameters as a

W/R Reactor Water Level

W/R RPV Pressure

Fuel Zone Reactor Water Level

Suppression Pool COMPLETE "Simulator Ready-for-Training/Examination ESG-NRC-S2 Page 3 of 29 Rev.: 01

Initial

ET # 2 Event code:

Description:

LCPNEP01 >= 300 Deletes malfunction when drive pressure is 300 psig Event code:

Description:

Event code:

Description:

Event code:

Description:

Event code:

Description:

ESG-NRC-S2 Page 4 of 29 Rev.: 01 None None None None None N one None None None None None None None ne None ne No ne None None None None None None N N None None None None None Insert malfunction RP07 Insert malfunction CUIIA Insert malfunction CUIIB Insert malfunction HP 14 Insert malfunction HP 15 Insert malfunction HP 16 Insert malfunction HP06E Insert malfunction CD034647 Insert malfunction CD034647 after I on event 2 delete in 1 Insert malfunction NM 12B to 0 on event 3 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 TCOI-to after 380 on event 4 Insert malfunction FW26Aon event 24 Insert malfunction FW26B on event 25 Insert malfunction FW29C on event 26 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 HPCI HV-8278 failure to auto open HPCI HV-F059 failure to auto open HPCI aux oil pump failure to auto start Control Rod 46-47 stuck Control Rod 46-47 stuck Flow summer K607B failure EHC pump A trip EHC pump discharge filter plugging Main generator trip All turbine bypass valves fail closed Trips "A" RFPT Trips "B" RFPT Trips "C" RFPT ESG-NRC-S2 Page 5 of 29 Rev.: 01 Initial @Time Event None None None None None None None None None None None None None None None None None None None None None None None None Action Insert remote PP04 to NO Insert remote AN28 to NORM Insert remote EPOI after 360 to BYPASS on event 5 Insert remote EP02 after 480 to BYPASS on event 6 Insert remote EP38 after 180 to Emergency on event 7 Insert remote EP09 after 240 to REMOVED on event 8 Insert remote EPlO after 240 to REMOVED on event 8 Insert remote EPI1 after 360 INSTALLED on event Insert remote EP 13 after 360 INSTALLED on event Insert remote EP 12 after 720 ALLED on event Insert remote EP14 after 720 INSTALLED on event Insert remote EP35 after 180 to FAIL CLOSE on event 9 Description PP04 OD-3 Crossflow Applied AN28 CROSSFLOW ALARM/TRBL EPOl EOP-30I, bypass MSIV (-129") isolation interlock EP02 EOP-311, bypass PCIG (-129") isolation interlock EP38 EO P -319, Restoring Instrument Air in an Emergency EP09 EOP-320 (step 5.1.2), AR1 valve fuses F6A1F5A EPlO EOP-320 (step 5.1.4), ARl valve fuses F6BiF5B EOP-320 (step 5.2.2), RPS division 1 3 EOP-320 (step 5.2.3), RPS division 3 jumper EP12 EOP-320 (step 5.2.4), RPS division jumper EP14 EOP-320 (step 5.2.5), RPS division 4 jumper EP35 EOP-322 HV-F006 HPCI to CS ESG-NRC-S2 Page 6 of 29 Rev.: 01 Place C RFPT in service: After the Crew assumes the watch. Raise Reactor Power with Control After the Crew assumes NOTE: Operator may notch withdraw the rods, necessary, in which case CONTINUOUS PB is NOT 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 FOUR ROD indicates the control position The associated Full Display (white) numbered identification light comes 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 01\1 momentarily. The WITHDRAW (white) comes ON and CONTINUOUS (white) light comes Page 7 of Rev.: 01 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 OVERTRAVEL alarm does NOT annunciate.

ESG-NRC-S2 Page 8 of Rev.: 01 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 NOTE: Crew may request RE in both directions to guidance.

Respond that a determine the exact condition withdraw signal then an insert of the Control Rod. signal may be attempted. Verifies drive water flow fluctuates normally.

ESG-NRC-S2 Page 9 of Rev.: 01 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. ENSURE ET-2 triggers when drive water pressure dp >300 psid. This deletes stuck rod malfunction.

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 29 Rev.: 01 Flow Unit Failure: Atthe Lead TRIGGER EJ -3 (8 APRM Unit 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 Yz scram by: OHA C3-A4 "REACTOR SCRAM TRIP LOGIC 81" OHA C3-A5 "REACTOR SCRAM TRIP LOGIC 82" OHA C5-A 1 "NEUTRON MONITORING SYSTEM" RPS Trip Logic 81 NORMAL/RESET 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.: 01 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 => APRM B, D, and F ALARM" status: ::;> CRIDS D4305 "APRIVI CH UPSCALE THERMAL. :::;> CRIDS D4307 "APRIVI CH UPSCALE THERMAL :::;> CRIDS D4309 "APRM CH UPSCALE THERMAL. Crew recognizes

'B' RECIRC LOOP FLOW SUMMER FAILURE Downscale by: => FLOW UNIT Band B "COMPAR" status :::;> APRM B, D, and F ALARM" status :::;> CRIDS C026 "EITHER CHANNEL

> CRIDS C049 FLOW COMPR OUT CRS implements AB.lC-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 Rev.: 01 IF directed to place the Unit B MODE Switch in unlabeled position, CHANGE Malfunction Final value to Trip of 'A' EHC After the Crew resets RPS addresses Tech at the discretion of the TRIGGER ET*4 (Loss of I F dispatched to the pump, THEN REPORT motor is very hot to the

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.

=> VERI FY 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: =>

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.: 01 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 discharge REFER to Section THEN REPORT the filter transfer handle will

CRS implements AB.BOP-0003.

Crew recognizes BP116 discharge filter clogging by: OHA D3-F5 "TURB HYDR PUMP TROUBLE" 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.: 01 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 Att. 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 10C651C 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 SBLe pump start. RO/PO inform CRS of failure to automatically isolate. ESG-NRC-S2 Page 15 of Rev.: 01 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 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 Att. 13. CREW prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUATION.

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.: 01

Trip of RFPT

Once the crew has established level control with feedwater, observe which RFPT is in service and then trip

it as follows: ET* 24 -Trips "A" RFPT ET-25 -Trips "6" RFPT ET Trips "C" RFPT * *

CRS directs terminating and preventing injection to the RPV with the exception of: :::> SLC :::> CRD RCIC RO/PO terminate and injection from HPCI, RHR feedwater/condensate AB.ZZ-0001 :::> Attachment 16 (1 :::> Attachment 17 (1 CRS directs maintaining water level between -50" -185" with feedwater Crew recognizes trip of RFPT and establishes flow with RFPT in standby or CRS directs bypassing the and commencing manual RO/PO bypass RWM and control rods lAW IF EOP-322 is complete RPV water level reaches THEN CRS directs RPV water level between and -185" with HPCI and 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.: 01 IF EOP-322 is NOT complete before RPV water level reaches -129", 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-101A.

In this case, with Suppression Pool temperature below 110°, the upper RPV level limit is -50".) RO/PO initiate HPCI as directed byCRS. RO/PO recognize HPCI components fail to auto-initiate and align components lAW AB.2Z-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 T AF) 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.: 01 ENSURE HPCI flow is :5 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. IF the MSIVs close, THEN the CRS directs pressure control with the SRVs. IE directed, THEN RO/PO control pressure with SRVs lAW AB.ZZ-0001 Att. 13. IF RPV level reaches -129", THEN CRS directs restoring: 1 E Breakers PCIG to IF directed, THEN RO/PO restore 1 E breakers lAW AB.ZZ-0001 Att.12. IE 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.: 01 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 IF 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 RM 11 9AX833/834 alarm Various Suppression Pool temperature indicators CRS implements EOP-1 02. CRS directs placing RHR in Suppression Pool Cooling. RO/PO place RHR in Supp Pool Cooling lAW AB.ZZ-0001 Att. 3. IE 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.: 01 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.: 01 A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JT A Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG) G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1 004 Operations Standards M. OP-AA-101-111 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 Q. OP-HC-1 08-1 06-1 001 Equipment Operational Control R. HC.OP-DO.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.lC*0001 Control Rod BB. HC.OP*AB.lC*0003 Reactor Protection System CC. HC.OP-AB.lC-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.: 01 ESG-NRC*S2 I 1. CREW prevents an uncontrolled depressurization during A TWS conditions preventing ADS KIA 218000 Automatic Depressurization A4 Ability to manually operate and/or monitor in the control A4.04 ADS inhibit RO 4.1 SRO 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: EA1.02 RRCS RO 3.8 SRO 4.0 EA1.04 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-101A.

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.ZZ-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.: 01

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: EA1.01 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.: 01

ESG*NRC-S2 I 01 HOPE CREEK ESG .. PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT YIN EVENT Loss Of Offsite Power/SBO 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 COMPONENTITRAIN/SYSTEM THAT INCREASES CORE DAMAGE YIN KEY EQUIPMENT YIN KEY EQUIPMENT 1E 4.16KV Bus 120VAC 481 Inverter Hard Torus Vent Switchgear Room Cooler 1 E 125VDC Bus RCIC SACS Loop SSW Ventilation SSW Loop 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 OPERATOR ACTION ___ Emergency Depressurize RPV W/O 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 ___ Initiating LP ECCS with No High Pressure Injection

___ Monitoring and Control of SACS heat Complete this evaluation form for each ESG. ESG-NRC-S2 Page 25 of 29 Rev.: 01 Rx Power: WorkWeek: 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 Aand B Tagged ESG-NRC-S2 Page 26 of 29 Rev.: 01

EXAMINATION SCENARIO GUIDE REVIEW N ALiDATION 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. CHECK ESG-NRC-S2 The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events. 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. 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). Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

___ 8. If time compression techniques are used, scenario summary clearly so indicates. The simulator modeling is not altered. 10. All crew competencies can be evaluated.

11. Appropriate reference materials are available (SOERs, LERs, etc.) 12. Proper critical task methodology used lAW NRC procedures.

ESG-NRC-S2 Page 27 of Rev.: 01

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-52 ESG: SELF-CHECK

1. Total malfunctions inserted:

4-8/10-14

___ 2. Malfunctions that occur after EOP entry: 1-4/3-6 3. Abnormal Events: 1-2/2-3 ___ 4. Major Transients:

1-2/2-3 5. EOPs used beyond primary scram response EOP: 1-3/3-5 ___ 6. EOP Contingency Procedures used: 0-3/1-3 7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes) 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-S2 Page 28 of 29 Rev.: 01

EXAMINATION SCENARIO GUIDE (ESG) VALIDATION Crew Validation Rev: 00 Date Validated: Validated with one 3 man crew from B Shift. Runtime was 75 Validation Comments RPV level control by operators kept level above -129Added MT trip and TBV fail closed after 6 minutes on ET-4 to pressure control to Crew Validation Rev: Date Validated:

Validation Disposition

'//7///////////////////////////////////$/////////////////$////////////////$/////////$/////////////////$///$//////////////////////

/////////////////////////////////////h ESG-NRC-S2 Page 29 of Rev.: 01 SCENARIO TITLE: NRC SCENARIO 3 SCENARIO NUMBER: ESG-NRC-S3 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION:

80 minutes REVISION NUMBER: 01 PROGRAM: L--_---'I L.a. REQUAL x I INITIAL LICENSE L--_---' OTHER REVISION

SUMMARY

1. Scenario 3 is now the spare. 2. Added Fuel failure at MSL leak to drive entry into EOP 103. 3. Added Overrides for Offgas Pretreatment RMS. 4. Deleted Rod Drift out malfunction.

5. Moved MSL Drain F019 failure to separate event for SRO TS cal!. PREPARED BY: Archie E. Faulkner 1/12112 Instructor DATE APPROVED BY: O}([

Jdr/Jz. LORT Group Lead or Designee DATE APPROVED BY: DATE Enabling Objectives The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions. (Critical tasks within this examination scenario guide are identified with an " *.") Raise reactor power with control rods IRM "0" fails upscale MSL Drain HV-F019 Failure RFPT "A" trips Main Steam Tunnel leak with Fuel Leak 2 Control Rods stick at position 48 Failure of MSIVs and MSL Drains to auto close CRD Flow Control Valve 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, a 0 IRM fails upscale causing a half scram and rod block. This results in an Abnormal Procedure and Tech Spec entry. After TS have been addressed, Main Steam Line Drain valve AB-HV-F019's power supply breaker will trip open. This a Primary Containment Isolation valve with a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LCO action time. After TS have been addressed, "A" RFP Turbine will trip resulting in a loss of Feedwater.

The crew will bring on-line the idling RFPT to restore Feedwater to the RPV. Once Feedwater has been restored, the plant will develop a steam leak in the steam tunnel requiring the unit to be shutdown.

2 control rods will be stuck at position 48 after the scram. High Main Steam Tunnel temperature will close the Main Steam Isolation Valves. Both 0 MSIVs and Main Steam Line Drain F016 valve will fail to auto close while Turbine Bypass Valve #1 will fail open, causing a lowering RPV pressure with the Reactor not shutdown.

The crew must manually close the valves to stop the cooldown.

The in-service CRD Flow Control Valve will fail closed after the scram requiring operator action to re-establish Drive Water Pressure.

The RO will drive both Control Rods to 00 to shutdown the reactor. ESG-NRC-S3 Page 2 of Rev: 01 INITIALIZE the simulator to 3% power IIC, BOL. Pull step INSERT control rods through step ENSURE both MS Tunnel Coolers in INITIAL IO.zZ-0003 Section 5.3 up to and including step ENSURE Insight is trending the following

Reactor power

W/R Reactor Water Level

W /R Reactor Pressure COMPLETE the Simulator Ready for Training/Examination Checklist.

ZCRPSUDN >= Reactor Mode Switch in Event LCPNEP01>=200&ZCRPSUDN>=1 12

Description:

Deletes malfunction when drive pressure is 200 psig with MS in SO. Event code: LUIVI.;:II.;:lOv

>=

Description:

ABHVF016 CLOSE PB Event 15

Description:

Event cription:

Main Steam Tunnel Temp> 160 F and MS in SO fails TBV #1 Event code:

ESG-NRC-S3 Page 3 of 25 Rev: 01 ne None None None None None None None None None None None None None None None None None None None None None None None None None None None Insert malfunction CD032259 Insert malfunction CD032655 Insert malfunction MS 19D Insert malfunction MS20D Insert malfunction RM9621 to 1.04000 Insert malfunction RM9622 to 1.25000 Insert malfunction NM06D to 100.00000 on event 1 Insert malfunction FW26A on event 3 Insert malfunction MS04D to 100.00000 on event 5 Insert malfunction CR01 to 100.00000 on event 5 Insert malfunction CD09 A after 60 to 0.00000 on event 12 Insert malfunction CD09A after 5 delete in Ion event 11 Insert malfunction CD032259 after 1 delete in 1 on event 6 Insert malfunction CD032655 after 1 delete in 1 on event 6 Insert malfunction TCOl-l on event 16 Control Rod 22-59 stuck Control Rod 26-55 stuck MSIV F022D fail to auto isolation MSIV F028D fail to auto isolation 9RX621, OG RMS Offgas Pretreatment ChanA 9RX622, OG RMS -Offgas Pretreatment ChanB IRM channel D reads high or low 105 trip Steam line D leak in tunnel Fuel cladding leak Drive water flow control valve F002A failure Drive water flow control valve F002A failure Control Rod 22-59 stuck Control Rod 26-55 stuck Turbine bypass valve BPV-l failure ESG-NRC-S3 Page 4 of 25 Rev: 01 OP-HC-1 03-1 05 Revision 0 Page 5 of 25 Initial @Time Event None None None None None None None None None 14 None None Action Insert remote HV12 to RUN on event 5 Insert remote CD 1 0 after 5 to ON on event 11 Insert remote CD09 after 5 to OFF on event 11 Insert remote MS 11 to TAGGED Insert remote MS11 to UNTAGGED Insert remote MS12 to TAGGED on event 15 Description Steam Tunnel Unit Cooler BV216 COl 0 CRD FCV B CD09 CRD FCV A MS11 Main Steam Line Drain Valve, AB HV-F016 MS11 Main Steam Line Drain Valve, AB HV-F016 MS12 Main Steam Line Drain Valve, AB HV-F019 OP*HC*1 03*1 05 Revision 0 Page 6 of 25 None None Insert override 3A107 A LO to Orf None None Insert override 3A107 E LO to On None None Insert override 3A107 F LO to Off None None Insert override 7DS 11 A LO to On None None Insert override 7DS 11 B LO to Off None None Insert override 7DS 1 B LO to Off None 14 Remove override lOS 111 C LO to On None 14 Remove override lOS 111 B LO to Ofr None 14 Remove override 3AlO7 A LO to Off None 14 Remove override 3AI07 E LO to On None 14 Remove override 3AI07 F LO to orr None 14 Remove override 7DS 1 to On None 14 Remove override 7DS 11 B LO to Orf HV-F016 OPEN-CTMT INBD STEAMLINE DRAIN HEADER ISLN-INBD (LO) HV-F016 CLOSE-CTMT INBD STEAMLINE DRAIN HEADER ISLN-INBD (LO) HV-F016 OPEN-CONTAINMENT ISOLATION V ALVES-MAIN STEAM DRAIN LINE HV-FO 16 CLOSED-CONTAINMENT ISOLATION VALVES-MAIN STEAM DRAIN LINE OUTBD-CONT AINMENT ISOLATION V ALVES-MOV OVLDlPWR FAIL (LO) HV-F016A OPEN (LO) HV-F016A CLOSED (LO) HV-F016 OVLD/PWRFAIL-CTMT INBD STEAMLINE DRAIN HEADER ISLN-INBD HV-F016 OPEN-CTMT INBD STEAMLINE DRAIN HEADER ISLN-INBD (LO) HV-F016 CLOSE-CTMT INBD STEAMLINE DRAIN HEADER ISLN-INBD (LO) HV-FOI6 OPEN-CONTAINMENT ISOLATION VALVES-MAIN STEAM DRAIN LINE HV-F016 CLOSED-CONTAINMENT ISOLATION V ALVES-MAIN STEAM DRAIN LINE Raise Reactor Power with Control Rods: After the Crew assumes the 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. 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 (10C650C). 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-S3 Page 7 of Rev: 01 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.

2. Red Full Out light illuminates on the Full Core Display. ESG-NRC-S3 Page 8 of Rev: 01

'0' IRM Fails Afterreactor power has at the discretion of the Examiner, TRIGGER NOTE: Trigger when there NO rod motion to prevent Drift alarm and

3. 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.

Crew recognizes IRM failure by: OHA C3-A5 "REACTOR SCRAM TRIP LOGIC B2" "'> OHA C3-C3 "IRM C/D/G/H UPSCALE INOPITRIP" OHA C3-D3 "IRM UPSCALE" OHA C5-A1 "NEUTRON MONITORING SYSTEM TRIP" OHA C6-D3 "ROD OUT MOTION BLOCK" '0' IRM "UPSC TR OR INOP" and "UPSC ALARM" status lights Crew terminates rod withdrawal. RO validates no unexpected rise in power on redundant instruments. CRS implements AB.IC-0004:

"'> Condition A

RO bypasses '0' IRM and resets RPS A1 trip lAW AB.IC-0004.

Crew contacts Maintenance to troubleshoot.

Page 9 of Rev: 01 Note: This AB covers the same actions as AB-IC-0004 and may not be performed.

MSL Drain AB*HV-F019 After reactor power has at the discretion of the Examiner, TRIGGER (HV-F019 Breaker Crew contacts Operations Management. CRS implements AB.IC-0003:

==> Condition B CRS recognize the following Tech Specs apply: ==> Reactor Protection System Instrumentation

3.3.1 Control

Rod 3.3.6 Crew recognizes AB-HV-F019 failure by: ==> OHA C8-E5 "MAIN STEAM STP/ORN VALVE O/PF " ==> 02285 MS DR OUTBO ISO V HV-F0190PF

==> CONTAINMENT ISOLATION VALVE O/PF ==> 04675 CONT ISLN MOV VLV OPF RO implements ==> RO implements 0012: ==> 01-B3 CRS recognize the following Tech Specs apply: ==> Primary Containment Isolation Valves 3.6.3 For both TIS, still meet the Minimum Operable Channels per Trip Function.

Tracking Action statement only. CRS may refer to AB.CONT-0002 but no actions are applicable.

ESG-NRC-S3 Page 10 of Rev: 01

'A'RFPT Trip: TRIGGER ET-3 at the discretion of the IF the reactor scrams, TRIGGER ET*5 Main Tunnel IF dispatched to investigate trip of AP1 THEN The RFPT is slowing down. There is nothing else obviously wrong at the RFPT. Crew recognizes AP1 01 RFPT trip by: => OHA B3-E1 "RFP TURBINE TRIP" => RFP "A" TURB MODE TRIP light => OHA B3-F1 DFCS TROUBLE PO monitors feedwater response to RFPT trip. Crew announces trip of 'A' RFPT on the plant page. CRS implements AB.RPV-0004:

=> Condition A PO presses RFPT B SPEED CTRLR SPD DEMAND INC t pushbutton as required to establish approximately 150 to 450 psid across the Startup Valves to achieve positive response on the startup valves with B RFPT. Crew dispatches TBEO and Maintenance to investigate the trip of the AP101 RFPT. ESG-NRC-S3 Page 11 of Rev: 01 Steam in the steam tunnel/Fuel Leak: TRIGGER the Steam Tunnel) when .

for the trip of'A' R.FPTor at the Lead Examiner's discretion. . Crew recognizes Steam Tunnel temp rising: => A2541 Stm Tunnel Clr Inlet temp in alarm. => OHA D3-A3 MN STIVl/RWCU AREA TEMP HI CRS directs PO to implement HC.OP-AB.BOP-0005, Condition A: PO implements 0005, Condition A: Isolate the source of the leak if known. Monitor the following to determine the source of leak: Main Steam Flow indication Feedwater Flow indication RWCU System => Ensures TB Chilled Water Supply Temp is <55F. => HV-9532-1 and HV-9532-2 are open. ESG-NRC-S3 Page 12 of Rev: 01 IF dispatched to perform BOP-0005 actions, THEN REPORT: Action A3: Steam Tunnel supply and return back draft dampers -both sets are open. Action A5: Place Both Steam Tunnel cooling fans in service by placing REMOTE FUNCTION HV11 and HV12 in RUN. Action A6: GU-HD9395A and 9395B are closed. This alarm may not High alarm is 2.5 ESG-NRC-S3 Ensure proper positioning of Steam Tunnel Supply Ar-.,ID Return Backdraft dampers Ensure both Steam Tunnel cooling Fans in-service at panel 1 EC281. Ensure GU-HD9395A AND GU-HD9395B are closed. CRS assigns a crewmember to monitor Steam Tunnel temperature.

CRS implements AB.CONT-0004, Condition A Direct Radiation Protection to enter RP-ARSP-0001 Monitor for indications of fuel damage Monitor activity at the exhaust ducts to localize the source of the activity Determine the Total Release Rates CRS implements AB.CONT-0004, Condition C. Monitor for indications of a steam leak Crew responds to RM-11 "High Alarm" for 9RX620 for the Tech Support Center ARM. Page 13 of Rev: 01 The CRS may take conservative action and scram before 145 degrees. CRS enters HC.OP-EO.ZZ-01 03, and monitors the leak. CRS briefs the crew on plant conditions and contingencies for a rising Main Steam Tunnel temperature. Crew monitors AB.BOP-0005 Retainment Override. CRS directs a manual Scram when Steam Tunnel temperature 2:145 degrees lAW Retainment RO takes actions to manually scram the reactor lAW AB.ZZ-0001. PO takes action to control, restore and maintain RPV level with Feedwater. CRS implements 0101A based on entry condition of RPV Level and directs actions to stabilize the plant. RO performs scram actions lAW HC.OP-AB.ZZ-0001 CRS may transfer level and pressure control to RCIC and SRVs in anticipation of MSIV closure. ESG-NRC-S3 Page 14 of Rev: 01 Crew recognizes D Inboard, Outboard MSIV and MSL drain valves have not closed on High Steam Tunnel Temperature. CRS directs closing MSIVs and drains to isolate steam leak. RO closes the MSIVs and drains. Crew closes at least one MSIV in each steam line and MSL drain valve F016 before reactor pressure drops below 345 psig. The CRS directs the PO to restore and maintain RPV level -20 to +20 inches with RCIC. The CRS directs the PO to restore and maintain RPV pressure 800 to 1000 psig with HPCI and SRVs. ESG-NRC-S3 Page 15 of Rev: 01 IE directed to manually scram the rods locally from the SRI Test switches, THEN REPORT that high radiation at those 2 HCUs prevents access to the test switches at this time. RO determines that two Control Rods are not fully inserted, and reactor NOT shutdown under all conditions without boron and informs CRS: => RWM "CONFIRM SHUTDOWN" screen CRI DS Page 249 Full Core Display FULL OUT light Four rod display SPDS "ALL RODS INSERTED" NO RO determines rods 22-59 and 26-55 remained at position 48 after the scram. CRS directs RPV pressure control via the Pressure Control hard card and maintain RPV pressure 800 -1000 psig. CRS directs RO to attempt to insert the stuck rods. RO determines CRD drive water pressure is too low to drive the stuck control rods and informs CRS: Can use "List Rods" on RWM CONFIRM SHUTDOWN screen to identify rod not inserted.

ESG-NRC-S3 Page 16 of Rev: 01 IF dispatched to investigate the CRD FCV, THEN REPORT the A FCV is closed. IF directed to swap the CRD FCV, THEN TRIGGER ET-11 and REPORT the B FCV is in service. NOTE: WHEN Drive Water pressure is > 200 psid, THEN ENSURE Malfunctions CD032259 and CD032655 are deleted. RO determines CRD FCV failed closed by observing: HV-F002A green light illuminated and red Drive Water Pressure responding to operator Crew dispatches RBEO and Maintenance to investigate the A CRD FCV. RO directs RBEO to swap FCV to standby FCV. RO establishes Drive Water DP approximately 260-450 psid lAW HC.OP-AB-ZZ-0001 Attachment

18. RO selects and drives both control rods in to 00. CREW fully inserts all control rods via RMCS. RO reports the Reactor is shutdown. CRS exits EOP-101A and enters EOP-101. RO/PO coordinate transfer of Reactor Pressure and RPV level control. Page 17 of Rev: 01 Crew places 'B' RHR in Suppression Pool cooling to support RCIC/SRV operation lAW HC.OP-AB.ZZ-0001 Attachment 3 ESG-NRC-S3 Page 18 of Rev: 01 A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG) G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-1 04-1 01 Procedure Use and Adherence J. OP-AA-101-111-1003 Use of Procedures K. HU-AA-1081 Fundamentals Toolkit L. HU-AA-1211 Briefing M. OP-AA-101-111-1004 Operations Standards N. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel O. OP-AA-106-101-1001 Event Response Guidelines P. OP-AA-108-114 Post Transient Review Q. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program R. OP-HC-1 08-106-1001 Equipment Operational Control S. OP-AA-101-112-1002 On-Line Risk Assessment T. HC.OP-AB.lC-0004 Neutron Monitoring U. HC.OP-AB.IC-0003 Reactor Protection System V. HC.OP-AB.BOP-0005 Main Steam Tunnel Temperature W. HC.OP-AB.CONT-0004 Radioactive Gaseous Release X. HC.OP-AB.lC-0001 Control Rod Y. HC.OP-AB.RPV-0004 Reactor Level Control Z. HC.OP-AB.ZZ-0001 Transient Plant Conditions AA. HC.OP-EO.ZZ-0101 RPV Control BB. HC.OP-EO.ZZ-0101A ATWS-RPV Control CC. HC.OP-EO.ZZ-0103/4 Reactor Building and Rad Release DD. HC.OP-IO.ZZ-0003 Startup From Cold Shutdown to Rated Power EE. HC.OP-SO.AE-0001 Feedwater System Operation FF. HC.OP-SO.SF-0001 Reactor Manual Control GG. ESG-NRC-S3 Page 19 of 25 Rev: 01 ESG*NRC*S3! 1. Crew closes at least one MSIV in each steam line and MSL drain valve F016 reactor pressure drops below 345 K/Al239001 Main and Reheat Steam A4 Ability to manually operate and/or monitor in the control A4.01 MSIVs R0:4.2 SRO: 4.0 Tech Spec 3.4.6.1, Reactor Coolant System PressurelTemperature Limits, specifies a maximum allowable cooldown of 100 degF in anyone hour period. HC.OP-AB.RPV-0005 Retainment Overrides require closing the MSIVs and HV-F016/F019 if reactor pressure reaches 550 psig during an uncontrolled depressurization with the reactor shutdown.

The scenario starts with reactor pressure at approximately 905 psig. This equates to 920 psia. This places saturation temperature between 532 (900 psia) and 538 (950 psia) degF. The saturation pressure for 434 degF is 360 psia or 345 psig. Closing the MSIVs after pressure drops below 345 psig is a certain to cause the Tech Spec cooldown limit to be violated.

The scenario is modeled such that it will take at least three minutes for pressure to drop from 785 psig to 345 psig. This provides ample time to implement the AB.RPV-0005 and close the MSIVs. Note that for purposes of satisfying the critical task, it is only necessary to close one valve in each flow path. Also, subsequent actions which may cause additional cooldown, such as overfeeding due to the pressure reduction, are not encompassed by this critical task. 2. CREW fully inserts all control rods via RMCS. KIA 295015 Incomplete Scram AA1. Ability to operate and/or monitor the following as they apply to Incomplete Scram: AA 1.01 CRD Hydraulics RO 3.8 SRO 3.9 AA 1.03 RMCS RO 3.6 SRO 3.8 Manually inserting all control rods, provides the method for control rod insertion and placing the reactor in a shutdown status. It is critical for the crew to place the standby Flow Control Valve to establish drive water dIp to insert control rods and shut the reactor down. The 2 stuck rods are adjacent and could remain critical in a local area. ESG-NRC-S3 Page 20 of Rev: 01

ESG-NRC-S3/

01 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT YIN Loss Of Offsite Power/SBO Internal Flooding 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 COMPONENT/TRAIN/SYSTEM THAT INCREASES CORE DAMAGE KEY EQUIPMENT 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 ___ AlBRHR ___ RACS Heat HPCI Core Spray Loop Torus DIW Vacuum

___ EDG ___ SACS Heat OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION ___ Emergency Depressurize RPV WIO High Pressure

___ Emergency Venting of Primary

___ 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 Complete this evaluation form for each ESG. ESG-NRC-S3 Page 21 of 25 Rev: 01 Rx Power: 3% MWe (May vary slightly):

0 WorkWeek:

B Activities Completed Last Shift:

Reactor Startup in progress to step 5.3.43 of 10-3

A RFPT feeding RPV in MAN via SULCV in Single Element control

B RFPT warmed up at 1000 rpm lAW HC.OP-SO.AE-0001 Sect 5.7. Major Activities Next 12 Hours: Continue with Startup by withdrawing Control Rods @ <15%/hour.

Protected Equipment:

None Heightened Awareness:

None Tagged Equipment:

None Reactivity: Rod pull step 409. Continuous rod withdraw is allowed. RE-Some LPRM downscale and SRM Short Period alarms may occur during withdraw of rods. Contact RE for guidance.

ESG-NRC-S3 Page 22 of Rev: 01

---EXAMINATION SCENARIO GUIDE (ESG) 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 reviewed. CHECK ESG-REVIEWER:

1. 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 events. ___ 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 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. 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). Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. If time compression techniques are used, scenario summary clearly so indicates. The simulator modeling is not altered. 10. All crew competencies can be evaluated.

11. Appropriate reference materials are available (SOERs, LERs, etc.) 12. Proper critical task methodology used lAW NRC procedures.

ESG-NRC-S3 Page 23 of Rev.: 01

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: SELF-CHECK

1. Total malfunctions inserted: 2. Malfunctions that occur after EOP entry: 3. Abnormal Events: ___ 4. Major Transients: 5. EOPs entered requiring substantive actions: ___ 6. EOP Contingency Procedures requiring substantive actions: ___ 7. Approximate scenario run time: 60-90 8. Critical Tasks: 9. Technical Specifications are exercised during the test Comments:

ESG-NRC-S3 Page 24 of 25 Rev.: 01

EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't) Crew Validation Rev: 00 Date Validated:

1/4/2012 Validated with 3 man crew from B Shift. Runtine was 60 minutes. Validation Comments Disposition

'/////////////////7//7///////////////////////////////////7//////////////7////////////////////////////////////////////7//////////////////

Add status of Feedwater to Turnover Sheet -cA-"g>L.r-'..e..::..e.c...:E:::..:d:..:..it:..:..o:....ria=I'-;;:.

Slow MS Tunnel temp rise. Too fast. Agree. Placed 2 nd steam tunnel cooler i/s. Crew Validation Rev: Date Validated:

Validation Comments Disposition ij'/////////////////////////////////////////////////////////7/////

////////////////7///////////////////////////////////////////////////////////.1/0"///////////////////////////////4 ESG-NRC-S3 Page 25 of 25 Rev.: 01 SCENARIO TITLE: NRC SCENARIO 4 SCENARIO NUMBER: ESG-NRC-S4 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION:

60-75 minutes REVISION NUMBER: 05 x I L.O. REQUAL X I INITIAL LICENSE '---_-----" OTH ER REVISION

SUMMARY

Removed Recirc PP runaway and high vibration malfunction and replaced with multiple seal failure on'S' Recirc PP. Added malfunction for an ADS valve failure to open malfunction during the Emergency Depressurization.

PREPARED BY: Steven Dennis 2/15/12 Instructor r;) APPROVED BY: LORT Group Lead or DATE APPROVED :,v1;Ur 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 Dual Seal Failure Fuel Failure with Scram Torus Leak I Emergency Depressurization RHR HX Inlet Valve F047B fails closed ADS valve fails to open 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 'B' Reactor Recirculation inboard seal fails. After AB-RPV-003 actions are initiated the "B" Recirc Pump outboard seal will fail. 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 B Loop of RHR is placed in Suppression Pool Cooling, BC-HV-F047B 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. One ADS valve will fail to open requiring an additional SRV to be opened for the ED. ESG-NRC-S4 Page 2 of Rev.: 05 INITIALIZE the simulator to 3% power, INITIALIZE the simulator to 3% power IIC, BOL. Pull step INSERT control rods through step URE 'A' EHC pump is in service. CIT 'B' 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 SIU Level Control Valve is in AUTO set at 35" PLACE red bezel cover on 'B' EHC INITIAL IO.ZZ-0003 Section 5.3 up to and including step INITIAL HC.OP-SO.EA-0001 for pump At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs ENSURE Data Collection is trending the following parameters as a

W IR Reactor Water Level

W IR RPV Pressure

Suppression Pool level

Suppression Pool temperature COMPLETE "Simulator Ready-for-Training/Examination Checklist", LIRE associated Schedule file open and running. ESG-NRC-S4 Page 3 of 27 Rev.: 05 Event code: et_array(11)

>= 1.0 & eCarray(12)

>= 1.0 & et_array(13)

>= 1.0 & et_array(14)

>= 1.0 7

Description:

& eCarray(15}

>= 1.0 Triggers Torus leak when MSIVs and MSL Drains isolated Event code: crqnmi <= 2 10

Description:

Reactor Power <2% //Inserts Fuel Cladding failure if Crew scrams during Recirc Seal Failure Event code: msvf022(1)

<= 0.0 I msvf028(1)

<= 0.0 11

Description:

Detects 'A' MSL isolation Event code: . msvf022(2)

<= 0.0 I msvf028(2)

<= 12

Description:

Detects 'B' MSL . Event code: ! msvf022(3)

<= 0.0 I msvf028(3)

<= 13

Description:

Detects 'C' MSL Event code: 14 msvf022(4)

<= 0.0 I msvf028(4)

<=

Detects 'D' MSL Event 15 msvfdrn1(1)

<= 0.0 I msvfdrn1(2)

<=

F016 or F019 shut II Detects MSL drain Event crqnmi <= 2 16

Description:

Reactor Power <2% II Ramps MSL rad to 3xNFPB after reactor scrammed.**

Event code: et_array(11)

>= 1.0 & et_array(15)

>= 1.0 17

Description:

Removes high radiation from 'A' Event et_array(12)

>= 1.0 & et_array(15)

>= 1.0 18 *Description:

Removes high radiation from 'B' Event eCarray(13)

>= 1.0 & eCarray(15)

>= 1.0 19

Description:

Removes high radiation from 'C' Event et_array(14)

>= 1.0 & eCarray(15)

>= 1.0 20

Description:

Removes high radiation from 'D' MSL *Event code: *Pclsp <=

Indicated SP levell/Removes torus leak at 25" to prevent reaching Simulator Limits ** Value to be 12 mrlhr above current 3xNFPB Hi-Hi Alarm setpoint for I.C. ESG-NRC-S4 Page 4 of 27 Rev.: 05

.'. '. Initial I@Time Event Action Description None None Insert malfunction TC07B EHC pump B trip None None Insert malfunction CD022603 Control Rod 26-03 drift out Insert malfunction CW23A to 50.00000 on None None Service water strainer A fouling event 1 None None Insert malfunction RR05B on event 2 Recirc pump BP201 inboard seal failure I None None Insert malfunction RR06B in 60 on event 2 Recirc pump BP201 ouboard seal failure I Insert malfunction CW05A on event 6 Service water pump AP502 trip Insert malfunction PC06 after 180 to Suppression pool break 50.00000 on event 7 i "T

T T . malfunction RH03B on event 7 RHR HX inlet valve F047B fails closed Insert malfunction RH09 A after 210 onNone None RHR pump AP202 room flood (Rrn 4113)event 7 Insert malfunction CROI to 30.00000 in None None Fuel cladding leak 300 on event 8 Insert malfunction RM9509 to 118.00000 None None 9RX509, MSL 'A' -Main Steam Line Chan A in 300 on event 8 Insert malfunction RM9510 to 127.00000 None None 9RX51O, MSL 'B' -Main Steam Line Chan B in 300 on event 8 Insert malfunction RM9511 to 119.00000 None None 9RX511, MSL 'C' -Main Steam Line Chan C in 300 on event 8 Insert malfunction RM951 2 to 122.00000 None None 9RX512, MSL 'D' Main Steam Line Chan D in 300 on event 8 Insert malfunction CRO 1 after 1 to None None Fuel cladding leak 50.00000 on event 10 Insert malfunction RM9509 after 1 to None None 9RX509, MSL 'A' Main Steam Line Chan A 118.00000 in 300 on event 16 Insert malfunction RM951 0 after 1 to None None 9RX510, MSL 'B' -Main Steam Line Chan B 127.00000 in 300 on event 16 Insert malfunction RM9511 after 1 to None

T 9RX51 1, MSL 'C' -Main Steam Line Chan C 119.00000 in 300 on event 16 Insert malfunction RM9512 after 1 to None '" 9RX512, MSL 'D' -Main Steam Line Chan D 122.00000 in 300 on event 16 Insert malfunction RM9509 to 19.00000 in None "T. 9RX509, MSL 'A' -Main Steam Line Chan A 60 on event 17 Insert malfunction RM9510 to 19.00000 in None None 9RX51O, MSL 'B' -Main Steam Line Chan B 60 on event 18 Insert malfunction RM9511 to 15.00000 in None None 9RX511, MSL 'e' -Main Steam Line Chan C 60 on event 19 Insert malfunction RM9512 to 18.00000 in None None 9RX512, MSL 'D' -Main Steam Line Chan D 60 on event 20 Insert malfunction PC06 after 1 to None None Suppression pool break 50.00000 on event 21 delete in 1 None None Insert malfunction CD032603 on event 26 Control Rod 26-03 stuck Insert malfunction CD052603 on event 27 Control Rod 26-03 accumulator trouble Insert malfunction AN-C6C3 after 60 on CRYWOLF ANN C6C3 CRD HYDR UNIT I None None None event TEMP HI None None i Insert malfunction CD062603 on event 28 Control Rod 26-03 SCRAM ! None None Insert malfunction AD02CC ADS valve fails to open : HV-23568 OPEN--LOOP B-Y ARD DUMP None None Insert override 5A8 E LO to Off VALVE (LO) B-YARDDUMP i None Insert override 5A8 F LO to On VALVE HV -2256A OPEN-LOOP A-YARD None None i Insert override 5A3 E LO to Off VALVE HV-2256A CLOSE-LOOP A-YARD None None Insert override 5A3 F LO to On VALVE (LO) ESG-NRC-S4 Page 6 of Rev.: 05 Raise Reactor Power with Control Rods: After the Crew assumes the 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. 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 (10C650C). 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.: 05 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.: 05 Rod Will occur after rod 26-03 selected and (Control Rod 03 Drifts IF asked, THEN as Engineer, provide guidance CRS to continuously insert 26-03 to 00 if Proper response of the Nuclear Instrumentation while withdrawing the Control Rod. Indicates the completion of the movement on the Pull Listing.

Crew recognizes 26-03 rod drift by: => OHA C6-E3 "ROD DRIFT" => Amber DRIFT light for 26-03 on Full Core Display => RWM Drifting Rod display "DR 26-03" => CRIDS C078 "ROD DRIFT ALARM" => Slight rise in reactor power => Various rod position indications CRS implements AB.IC-0001:

=> Condition C IF a Rod Drift has occurred THEN REFER to Digital Alarm Point C078 of AR.ZZ-0011. RO implements AR.ZZ-0011

=> Cause 4 "Drift Out" RO applies a continuous control rod insert signal under the direction of the Reactor Engineer AND SM/CRS. RO releases insert signal. I F the control rod continues to drift out or does not respond to the insert signal THEN, Page 9 of 27 CRS may refer to AB.RPV-0001 but no actions are applicable.

Rev.: 05 IF directed to place both SRI Test Switches for HCU 26-03 to TEST, THEN TRIGGER ET-28. 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). WHEN dispatched to 26-03

Crew dispatches RBEO to HCU, THEN REPORT the appears ESG-NRC-S4 Page 10 of Rev.: 05 IF directed to electrically AND

CRS recognize the following hydraulically dis-arm 26-03 Tech Spec actions apply: lAW SO.BF-0002, Control Rod Operability THEN PERFORM the 3.1 .3.1 action b following:

CRS directs disarming the 26-03 DELETE malfunction directional control valves within CD022603 (drifting rod) and one hour. allow 26-03 to settle back to 00. TRIGGER ET-26 (stuck rod) TRIGGER ET-27 (accum trouble) !E 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. !E directed only to electrically dis-armed 26-03 lAW SO.BF-0002, THEN TRIGGER ET-26 (stuck rod).

RO resets the Rod Drift alarm lAW HC.OP-AR.ZZ-0020.

Swap Service Water Pumps:

CRS directs removal of "C" SSW After the Crew assumes the from service using watch. SO.EA-0001. PO places "A" SSW in service using HC.OP-SO.EA-0001 section 5.6.3.

ESG-I\IRC-S4 Page 11 of Rev.: 05 As Yard operator, report field actions are complete for starting "An SSW pump. SSW Pump "Au 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 "A" SSW pump strainer is not rotating and the screen is covered with grass. The breaker for the strainer is tripped and will not reset. !E the crew does not remove the "A" SSW pump from service, THEN TRIGGER ET*6 to trip the pump. PO removes "G" SSW from service using 0001 section 5.6.5. Crew recognizes "An SSW strainer Hi OP to the strainer by: => A1-B1 SSWS INTAKE A TROUBLE => 03857 SSW STRAINER A OIFF HI HI STRAINER PRESSURE DIP => 05507 SSW STRAINER A DRIVE OPF CRS implements AB.COOL-0001

=> Condition A Condition 0 Crew removes "A" SSW pump from service lAW: => AB.ZZ-0001 AU 1 9 Crew places "C" SSW pump in service lAW: => AB.ZZ-0001 Att 1 9 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.: 05 "B" Reactor Recirc Pump Inboard Seal Failure: TRIGGER ET-2, five minutes after Tech Specs have been addressed OR at the discretion of the Lead Examiner.

Reactor Recirculation Pump "B"Outboard Seal 60 seconds after Inboard IF dispatched to report seal pressures on 77' Rx THEN REPORT consistent with (Page OR the following Monitor (Monitor Items are 'B' Recirc Inbd (#1) Seal rrpsI1(2)

-15 = psig 'B' Recirc Outbd

(#2) Seal rrpsI2(2)

-15 = psig

Crew recognizes first stage seal failure on 'B' Recirc pump by: => OHA C1-F5 COMPUTER PT IN ALARM => CRIDS 02927 "RECIRC PUMP B SEAL STAGE FLOW" Rising second stage seal pressure

CRS implements AB.RPV-0003:

Condition 0 Crew recognizes

'B' Recirc pump dual seal failure by: => OHA C1-F5 COMPUTER PT IN ALARM OHA C6-B1 "OLD SYSTEM ALARMITRBL" RM11 9AX314 OLD Floor Drain Flow alarm => RM11 9AX317/318/320 OLD CCM alarms => CRIDS 02925 "RECIRC PUMP B SEAL LKG FLOW" => Rising seal temperatures

=> Rising drywell pressure Lowering seal pressures ESG-NRC-S4 Page 13 of Rev.: 05 CRS implements AB.RPV-0003:

Condition E RO/PO trip and isolate 'B' Reactor Recirc pump lAW AB.RPV-0003 Condition E.

Closes BF-HV-3800B

Closes BG-HV-F106

Ensures HV-F023B is Closed

Closes F031 B CRS implements AB.CONT-001: Condition A RO/PO ensure drywell cooling is maximized. CRS implements AB.CONT-006:

-Condition A PO verifies the Feedwater system is responding automatically and is restoring RPV level between level 4 and 7. Crew validates successful recirc isolation by: Seal pressures Trending DLD flows Trending drywell pressure and temperature CRS verifies core parameters are within the OPRM Enable Region of the Power to Flow Map. ESG-NRC-S4 Page 14 of Rev.: 05 Fuel Cladding*

Failure: 10 minutes after the Pump at the Lead TRIGGER ET-8(tuel 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 hours0.167 days 0.0238 weeks 0.00548 months 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" RM11 9RX509/510/511/512 Alert alarms and readings CRI DS Page 37 MSL Radiation readings CRS implements AB.RPV-0008: Condition A Condition B Condition C RO reduces power lAW RE Guidance (Reverse Pull IF the Crew scrams 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 15 of Rev.: 05 ENSURE MSL Radiation Malfunctions RM9509-RM9512 ramp down to <20 when the Main Steam Lines AND drain lines are isolated. Crew recognizes HI-HI MSL Radiation levels by: =::> OHA C6-B2 liMN STM LINE RAD HI HI OR INOP" =::> RM11 9RX509/510/511/512 High alarms =::> CRIDS Page A037 MSL Radiation readings CRS directs: =::> Locking the Mode Switch in SHUTDOWN Closing MSIVs, HV-F016 and HV-F019 steam line drains. RO locks the Mode Switch in 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.z.z-0001 Attachment 6 RO/PO close MSIVs, HV-F016 and HV-F019 steam line drains. ESG-NRC-S4 Page 16 of Rev.: 05 UnisolableTorus The Torus Leak willbegin minutes afteftheMSIVs IF dispatched to the Room to look for a THEN REPORT there is large, unisolable leak at on bottom of the torus at Az. There is about one inch water on the torus room 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.

IF RPV Level 2 is reached, THEN CRS implements AB.RPV-0003:

=> Condition G

IF 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 HIILO" => 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 17 of 27 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.: 05 IF asked, THEN REPORT both sump pumps are running in both the North and South RB Floor Drain sumps. IF directed to EOP-315 WHEN torus level reaches INSERT Remote CS01-CS04 to make-up Do NOT open more than RHR Pump Room The 'A' RHRRoom alarm will be minutes after the

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

CRS implements EOP-102.

CRS directs MIU to the torus lAW EOP-315.

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-4403A1" => CRIDS D2892 "RHR PMP ROOM 4113 LSH-4403A2" => SPDS RB L VITE indication Page 18 of 27 Rev.: 05 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. Recognizes one ADS valve failed to open and opens an additional SRV (five total should be open) Crew determines that Suppression Pool water level cannot be maintained above 38.5" and initiates opening of five SRVs before Suppression Pool level reaches RO/PO maintain RPV level as directed by CRS. LE 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 19 of Rev.: 05 RHR HX INLET Valve F047B Fails The 'A' RHR HX HV-F047B will fail Ciosed the Torus leak Termination Requirement:

The scenario mCiybe .... terminated at the discretion of the Lead Examiner when the RPV has been degressyrized lAW EOP-202. ....

WHEN Suppression Pool temperature reaches 95 degrees, THEN Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by: => OHA C8-F1 "SUPPR POOL TEMP HIGH" => Flashing 95 degree status light on 10C650C => RM11 9AX833 alarm => Various Suppression Pool temperature indicators

WHEN Suppression Pool temperature reaches 95 degrees, THEN the CRS re-enters EOP-102.

WHEN directed by the CRS, THEN RO/PO place RHR in Suppression Pool Clg lAW AB.ZZ-0001 Att. 3.

Crew recognizes RHR HV-F047B is failed closed.

RO/PO places A RHR in Suppression Pool Clg lAW AB.ZZ-0001 Att. 3.

Page 20 of 27 Rev.: 05 A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG) G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-1 04-1 01 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1 004 Operations Standards M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines O. OP-AA-108-114 Post Transient Review P. OP-HC-108-11S-1001 Operability Assessment and Equipment Control Program Q. OP-HC-108-106-1001 Equipment Operational Control R. HC.OP-SO.BB-0001 Reactor Recirculation System Operation S. HC.OP-DD.ZZ-0020 Review of Core Performance Information T. HC.OP-DL.ZZ-0026 Surveillance Log U. HC.OP-AB.ZZ-0001 Transient Plant Conditions V. HC.OP-AB.RPV-0001 Reactor Power W. HC.OP-AB.RPV-0003 Recirculation System X. HC.OP-AB.RPV-0008 Reactor Coolant Activity Y. HC.OP-AB.CONT-0004 Radioactive Gaseous Release Z. HC.OP-AB.ZZ-OOO Reactor Scram AA. HC.OP-EO.ZZ-0101 RPV Control BB. HC.OP-EO.ZZ-0102 Primary Containment Control CC. HC.OP-EO.ZZ-0103 Reactor Building Control DD. 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 21 of 27 Rev.: 05 ESG-NRC-S41 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 KlA 239001 Main Steam and Reheat Steam System A2 Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.05 tMain steam line high radiation RO 3.9 SRO 4.2 Hope Creek was originally designed with an automatic reactor scram and MSIV isolation on Hi-Hi MSL Radiation levels. This was designed to limit the release to the public during a Control Rod Drop Accident.

As part of an industry effort to reduce spurious MSIV isolations, the automatic scram and MSIV isolations were removed in Tech Spec Amendment

54. One of the three conditions for approval of this amendment was that we would have procedures to expeditiously control significant increases in MSL radioactivity to limit both occupational doses and environmental releases.

To meet this requirement, AB.RPV-0008 directs scramming the reactor and closing the MSIVs if a valid MSL Hi-Hi radiation condition exists. In this scenario, three minutes provides adequate time to initiate a manual scram and close the MSIVs and drains. This includes the valve stroking time. In order to accomplish isolation of the release, only one valve in each line need be closed. For instance, closing all valves but the F019 would meet the Critical Task. The failure to close this valve would be applied to the overall performance evaluation.

Isolating the lines BEFORE receiving the Hi-Hi alarms is a conservative action that also satisfies this Critical Task. Scramming prior to the fuel cladding failure and subsequently closing the 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 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 KlA 218000 Automatic Depressurization 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 22 of Rev.: 05

ESG-NRC-S41 05 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT YIN EVENT Loss Of Offsite Power/SBO LOCA Y Internal Flooding Loss of 1 E ACIDC Buses TRANSIENTS:

LOSS OF SUPPORT SYSTEMS: Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Loss of SSW Loss of SACS Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening COMPONENT/TRAIN/SYSTEM THAT INCREASES CORE DAMAGE YIN KEY EQUIPMENT YIN KEY EQUIPMENT 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 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. ESG-NRC-S4 Page 23 of 27 Rev.: 05 Rx Power: WorkWeek: Risk Color: Activities Completed Last "An RFPT is in service in MAN with the SULCV in AUTO Single Element "8" RFPT is warmed up and available at 1000 Major Activities Next 12 Swap in service SSW pumps from "C" to The "An SSW Traveling Screen has been run for >30 SSW Chlorination has been removed from Protected Tagged

'8' EHC Pump is tagged for ESG-NRC-S4 Page 24 of 27 Rev.: 05

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 reviewed. CHECK ESG-REVIEWER: The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events. 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. The events are valid with regard to physics and thermodynamics.

___ 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.

8. If time compression techniques are used, scenario summary clearly so indicates.

___ 9. The simulator modeling is not altered. 10. All crew competencies can be evaluated.

11. Appropriate reference materials are available (SOERs, LERs, etc.) 12. Proper critical task methodology used lAW NRC procedures.

ESG-NRC-S4 Page 25 of Rev.: 05

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-54 SELF-CHECK

1. Total malfunctions inserted:

5-8 ___ 2. Malfunctions that occur after EOP entry: 1-2 3. Abnormal Events: 2-4 4. Major Transients:

1-2 5. EOPs entered requiring substantive actions: 1-2 ___ 6. EOP Contingency Procedures requiring substantive actions: 0-2 ___ 7. Approximate scenario run time: 60-90 minutes 8. Critical Tasks: 2-3 9. Technical Specifications are exercised during the test:,:::2 Comments:

ESG-NRC-S4 Page 26 of 27 Rev.: 05

Crew Validation Rev: 04 Date Validated: Validated with 3 man crew. Runtime was 60 Validation Comments Disposition W//////////////////////////////////////////////////////////Z0//////////////

////////////////////////////////////////////////////////////////////////////////

//////&&///////fi Sign prereqs in SSW SOP. _A,-::-,-,-cc:...;eCLP...:..: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 Disposition W///////////////////////////////////////////////////////////////////////////

///////////////////////////////////////////////////////////////////

///////////////////////////////fl:, ESG-NRC-S4 Page 27 of 27 Rev.: 05 SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM: REVISION

SUMMARY

Loss of 100410, Turbine Vibrations, LOP/LOCA, Rx Flooding ESG-01S Effective when 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8 19 x L.O. REQUAL 1 X 1 INITIAL LICENSE '---_-----'I OTHER 1 . Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. 2. PREPARED BY: Archie E. Faulkner Instructor APPROVED BY:

LORT Group Lead or Designee APPROVED BY: Sha.ralions or Designee 6/6/11 DATE t DATE 7 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 "*.") A. Loss of 100410 125VDC 1 E Bus Main Turbine High Vibration Loss of Offsite Power LOCA Loss of RPV Level Indication The scenario begins with the plant at 100% power. The 100410 125VDC 1 E bus will be lost due to a fault in the transfer switch. This will not cause a plant transient.

After Tech Specs for the bus are addressed, the Main Turbine will develop high vibrations on the #8 bearing. The vibrations will be of such a magnitude that the reactor will have to be scrammed to support tripping the turbine. Post scram vibrations will require closing the MSIVs and breaking vacuum. Thrown turbine blades will cause a complete loss of vacuum. When the MSIVs are closed, a LOP/LOCA will occur. Due to the loss of the 100410 bus, HPCI will not be available and RPV water level will lower until Emergency Depressurization is required.

During the depressurization, RPV water level indication will be lost, and Reactor Flooding will be required.

The scenario ends when adequate core cooling has been established lAW EOP-206. ESG-015 Page 2 of Rev: 19

INITIALIZE the simulator to 100% power, ENSURE associated Schedule file open and ENSURE associated Events file ENSURE Data Collection is trending the following parameters:

W/R Reactor Pressure

W/R Reactor Water Level

Fuel Zone Reactor Water Level At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ASs and SOPs COMPLETE the Simulator Ready for Training/Examination tc_trip >= 1.0 I tuvib(8) >= 12.5 /1 Turbine tripped or vibration above the action level Drives turbine vibrations to the point where damage is imminent.

Event code: mcpmca >= 10 /I Main condenser pressure>

10 psia

Description:

Removes turbine high vibrations after vacuum is broken. Event code: rrprv <= 415 /I Reactor Pressure < 400 psig 9

Description:

Triggers loss of RPV level indication and raises severity of LOCA ESG-015 Page 3 of 31 Rev: 19 i Initial None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None ESG-015 Insert malfunction ADO 1 malfunction AD06 Insert malfunction DG07B Insert malfunction RH08D Insert malfunction ED 11 A on event 1 Insert malfunction TUl208 from 75.00000 to 100.00000 in 720 on event 3 Insert malfunction TUl508 from 6.00000 to 13.00000 in 720 on event 3 Insert malfunction MCOIA after 300 on event 7 Insert malfunction EG12 on event 4 Insert malfunction RR31A2 to 3.00000 in 600 on event 4 Insert malfunction CD09 A after 90 to 75.00000 on event 6 Insert malfunction CD09B to 0 on event 6 Insert malfunction RR39B to 0 on event 9 Insert malfunction RR39C to 0 on event 9 Insert malfunction FW29 A to 0 on event 9 Insert malfunction FW29B after 60 to 60.00000 on event 9 Insert malfunction FW29C to 25.00000 in 60 on event 9 Insert malfunction RR20B to -150 on event 9 Insert malfunction RZO 1B to 60.00000 on event 9 Insert malfunction RZOIF from -150 to -32 in 15 on event 9 Insert malfunction RR24B after 120 on event 9 Insert malfunction TUl508 to 45.00000 in 180 on event 7 Insert malfunction TU1508 to 0 in 120 on event 8 Insert malfunction RR31A2 to 50.00000 in 300 on event 9 Page 4 of 31 Description Failure of ADS valves to open Failure of low-low set valves to Ann Diesel generator B emergency start signal failure RHR System D auto injection failed to energized Loss of 125 VDC class IE bus 10D41O Turbine bearing #8 high temperature Turbine bearing #8 vibration high Complete Loss of Vacuum Loss of all off site power Recite loop A large break [V] (lOo/a-6000 gpm, 1 gpm) Drive water flow control valve F002A failure Drive water flow control valve F002B failure LT-3622B PM1S Shutdown Range Failure PDT-N017 Upset Range Failure Feedwater level sensor N004A failure Feedwater level sensor N004B failure Feedwater level sensor N004C failure ECCS level transmitter N091B failure RRCS Level Transmitter LT-N402B Failure CS Level Transmitter LT-N402F Failure Reactor level transmitter N085B fails low Turbine bearing #8 vibration high Turbine bearing #8 vibration high Recire loop A large break [V] (10%-6000 gpm, 100%-60000 gpm) Rev: 19 i None 11 Initial @Time Event None None None None None None None None None : None None i : None None i None i I I I I i i I ) i i I i i ESG-015 Action Insert remote CD04 to OPEN on event S Insert remote CD06 to 100.00000 in 60 on event 6 Insert remote CDIO after 120 to ON event Insert remote EP37 after 180 to BYF ASS on event 10 . Insert override 8AR27 _B_AO to 0 on event 9 Insert override 8AR27 G AO to -19 on : event 9 I Insert override 8M13_B_AO to 0 on event .9 i I i Description CD04 CRD suction filter isolation CD06 Drive water press cont bypass V062 CDlO CRD FCVB EP37 EOP-323, Bypass isolation Description REACTOR WATER LEVEL LR-3683B (AO) i REACTOR WATER LEVEL LR-3682B (AO) . LEVEL LI-R60S-B21 (AO) Page 5 of 31 Rev: 19 Loss of 10D410125VDC Bus: Afterthe Grew assumes the watch and at ihediscretion of the Lead Examiner, TRIGGERET-1.

IE dispatched to investigate loss of 10D410, THEN REPORT: Bus indicates 0 volts Both battery chargers DC CKT BREAKER are tripped (AD413/ AD414) There is an acrid odor and indication of flash damage at the battery transfer switch (1 AD412 Rm 5544) There is no indication of fire

Crew recognizes Loss of 1 E 125VDC by: => OHA D3-F2 "125VDC SYSTEM TROUBLE" => CRIDS D4630 "125VDC SWGR 10D410 TRBL" => CRIDS D4633 "125VDC BATT 1AD411 PWR AVAIL NO" Flashing INOP lights on all 10A401 bus breakers => 'A' Channel ECCS "LOGIC PWR FAILURE" lights => Flashing "OVLD/PWR FAIL" lights on HPCI w/loss of position indication

=> Charger and bus voltage indication on 10C650D => CRIDS Page 166

CRS implements AB.ZZ-150.

STAIIA monitor AB.ZZ-0150 implementation.

Crew dispatches ABEO and Maintenance to investigate loss of 10D410 bus. HPI USED: FLAGGING 0 OP BARRIERS 0 (May flag/barrier

'A' EDG to remind of it's unavailability, since the START light is lit) E-0009-1 Sheet 1 ESG-015 Page 6 of Rev: 19 Crew recognizes closure of HV-2197A Backwash valve by 10C651A indication. CRS directs opening HV-2197 A. PO opens HV-2197A. CRS/ST AliA recognize the following Tech Specs actions apply: ==> D.C. Sources -Operating 3.8.2.1 Action a ==> Distribution

-Operating 3.8.3.1 Action b SM contacts Operations Management to initiate a Prompt Investigation. SM determines an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report is required lAW ECG Section 11 .2.2.b (Event/Condition that could have prevented certain Safety Functions) due to the loss of a Single Safety Train System (HPCI). Crew recognizes Main Turbine High Vibration by: ==> OHA D3-C5 "TURBINE GENERATOR VIB HI" ==> CRIDS A2526 "MAIN TURB BRG 8 VIB X PROBE" ==> System 1 indication Loss of control power to 'A' SSW pump motor breaker makes the pump appear stopped to the valve logic. HPI USED: STAR 0 PEER CHECK 0 Need to restore the 1AD411 battery, 1 OD41 0 bus, and one charger in two hours, or be in Hot SID in next 12 hours0.5 days 0.0714 weeks 0.0164 months . #8 Bearing will reach 11 mils in about 9.5 minutes. ESG-015 Page 7 of Rev: 19 SUPPORT requests to raise IVITlO temperature using Remote Function TU03. As System Operator, PROVIDE an acceptable band of 300-425 MVARS. LE contacted as Engineering, THEN REPORT the vibration readings appear valid and the limitations in the abnormal should be followed.

LE contacted as Operations Manager for concurrence to commence a controlled shutdown lAW 10-0004, THEN CONCURR with SM recommendation.

LE dispatched to check bearing drains, THEN wait until vibration reaches 15 mils and REPORT the floor was vibrating and it did not appear safe to approach the Main Turbine. CRS implements AB.BOP-0002: Condition B ST AliA monitors implementation of AB.BOP-0002 and applicability of Retainment Overrides. Crew directs TBEO to raise MTlO temperature (110 120"F) Crew co-ordinates with System Operator to adjust Main Generator MVAR loading. Crew contacts Engineering for additional guidance. Crew contacts Operations Manager for concurrence to commence a controlled shutdown lAW 10-0004. WHEN bearing #8 reaches 11 mils, THEN Crew: Reduces recirc pump speed to locks the Mode Switch Immediately trips the Main Turbine. Page 8 of 31 HPI USED: STAR 0 PEER CHECK 0 HPI USED: STAR 0 PEER CHECK 0 Rev: 19 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Reports Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status lAW HC.OP-AB.ZZ-0001.

Crew personnel should hold all other non-essential communications until after the initial scram report is complete.

The Control Room Supervisor should silence alarms during the scram report and the SM/CRS is not required to make a statement directing the NCO to check the overhead alarms, since these actions are already expected immediately following the scram. During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff lAW HC.OPAB.ZZ-0001.

RO performs scram actions lAW HPI USED: AB.ZZ-0001 Attachment

1. STAR 0 HARD CARD 0 ESG-015 Page 9 of 31 Rev: 19 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION EOP 101 RPV Control. Level Leg Direct an initial band of +12.5" to +54/1 Rx level. This gives a manageable band with level control still in the indicating range. If controlling Reactor Pressure with SRVs and the MSIVs are closed, then the RPV level band assigned should be -20" to +20" to avoid high level trips of injection systems when the reactor is being depressurized and to maintain forced circulation in the RPV. When maintaining RPV level is challenged by a lack of high pressure feed sources, and RPV level can not be maintained above -129", the crew should anticipate the actions that are necessary to implement EOP-202 and emergency depressurize the reactor prior to RPV level reaching 185". Reducing reactor pressure under these conditions in anticipation of implementing EOP-202 is not permitted since RPV level would be further challenged without sufficient high pressure feed sources available to maintain level. CRS implements EOP-101. STAIIA performs the following:

Verifies Rx shutdown => Trends critical plant

=> Monitors EOP PO maintains RPV water level as HPJ USED: directed by CRS lAW STAR 0 AB.ZZ-0001 Attachment

14. HARD CARD 0 ESG-015 Page 10 of Rev: 19 WHEN Malfunction MC01 A inserts, THEN REPORT as TBEO you heard a loud bang on 137' TB and now there is a loud whistling noise. There pieces of turbine blades and other metal on the 137' TB floor. Crew recognizes evidence of physical damage to Main Turbine by: => TBEO report => Rising offgas flow => Degrading condenser vacuum CRS implements AB.BOP-0002:

=> Condition C Crew performs the following:

=> Closes MSIVs and drains => Closes SJAE suction => Closes SJAE steam supply => Opens vacuum breakers CRS directs RPV water level control with RCIC. PO controls RPV water level with RCIC lAW AB.ZZ-0001 Att.6. SM determines a UE Classification is required lAW ECG Section 9.8.1.a (Catastrophic damage to the Main Turbine as evidenced by EITHER one of the following:

Main Turbine casing penetration)

OR 9.8.1.b (Vehicle Crash I Missile Impact with or within ANYone of the following Plant Structures:

Turbine Building). STAIIA turns over with extra SRO or SM to independently assess ECG Classification.

RECORD time of damage report for 15 minute ECG classification.

TIME: ___ HPI USED: STAR 0 PEER CHECK 0 HPCI is unavailable due to the loss of 100410. HPI USED: STAR 0 HARD CARD 0 ESG-015 Page 11 of Rev: 19

STAIIA validates UE lAW ECG Section 9.8.1.a OR 9.8.1.b. SM declares UE lAW ECG Section 9.8.1.a OR 9.8.1.b !E Crew does NOT take manual control of pressure, THEN Crew recognizes failure of La-La Set to arm by: =:> Absence of OHA C1-E5 "SRV LO-LO SET =:> OHA D1-A 1 POTENTIAL Safety lifting of F/H/KIM SRVs Various reactor pressure indicators The STA is responsible to perform an I.V. of the EAL Classification.

The ST A verification does not alleviate the requirement of the SM to make a timely classification.

Should the SM fill the ST A role, independent verification of the EAL classification will be delegated to another on-shift SRO. RECORD time UE declared.

Time Declared:

ESG-015 Page 12 of Rev: 19 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Pressure Leg Direct initial band of 800 -1000 psig. The lower limit of 800 psig will not complicate RPV level maintenance and does not challenge RPV cooldown limits. The upper limit of 1000 psig is a round number below 1047 psig. Do NOT allow the use of SRVs to interfere with Bypass valves. As pressure decays pressure bands should be adjusted to accommodate for this decay. Two recommended bands are listed below; however these upper and lower ends of these bands may be adjusted at the discretion of the Control Room Supervisor based on current plant conditions.

The Control Room Supervisor may elect not to utilize a second tier pressure band based on current plant conditions.

LOP/LOCA: CRS directs maintaining reactor pressure below 1037 psig with SRVs. RO/PO control RPV pressure with SRVs as directed by CRS lAW AB.ZZ-0001 Att 13. 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. Crew recognizes failure of the 'B' EDG to start and load by: =:> Engine STOP light =:> Output breaker TRIP light =:> OVLD/PWR lights on 'B' Channel components Page 13 of 31 HPI USED: STAR 0 HARD CARD 0 Rev: 19 IF directed to locally start 'B' THEN DELETE As ESOC, REPORT it will at least 10 hours0.417 days 0.0595 weeks 0.0137 months to Offsite power to Artificial RO/PO start the 'B' EOG and ensure it loads. 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.

Crew contacts ESOC for estimated time to restoration of Offsite power. CRS implements AB.ZZ-0135. Crew recognizes loss of A0481/482 inverters by: => Loss of 'A' Channel PAMS indications Loss of power to 'A' Channel electrical indications on 10C6500 As time and resources permit, CRS implements AB.ZZ-0136 and AB.ZZ-170.

HPI USED: STAR 0 PEER CHECK 0 I mmed iateOperator Action lAW AB.ZZ-0135.

HPI FLAGGING (May flag 'A' channel indicators to remind of unavailability)

Inverters are lost during LOP due to loss of 100410. ESG-015 Page 14 of Rev: 19 Crew recognizes LOCA condition:

=.? OHA D3-C3 "DRYWELL SUMP LVL HI/LO" =.? OHA C6-B1 "DLD SYSTEM ALARMITRBL" =.? RM11 9AX314 OLD FLOOR DRN FLOW alarm =.? Rising Drywell Pressure CRS implements AB.CONT-001:

=.? Condition A STAIIA monitors AB.CONT-0001 implementation. RO/PO ensures drywell cooling maximized. Crew checks Recirc pump seal parameters

=.? SRV temperatures Crew recognizes Drywell Pressure Above 1.68# EOP entry condition by: =.? OHA A7-D4 "DRYWELL PRESSURE HI/HI" =.? OHA C5-B5 "DRYWELL PRESSURE HI" =.? Various system initiations and isolations.

Page 15 of 31 Due to the pace of the LOCA, this may not be implemented.

HPI USED: STAR 0 PEER CHECK 0 There may not be time to maximize cooling before it isolates on high drywell pressure.

RECORD time of High Drywell Pressure for 15 min ECG Classification.

Time: Rev: 19 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION EOP 101 RPV Control Level Leg Direct an initial band of +12.5" to +54" Rx level. This gives a manageable band with level control still in the indicating range. If controlling Reactor Pressure with SRVs and the MSIVs are closed, then the RPV level band assigned should be -20" to +20" to avoid high level trips of injection systems when the reactor is being depressurized and to maintain forced circulation in the RPV. When maintaining RPV level is challenged by a lack of high pressure feed sources, and RPV level can not be maintained above -129", the crew should anticipate the actions that are necessary to implement EOP-202 and emergency depressurize the reactor prior to RPV level reaching 185". Reducing reactor pressure under these conditions in anticipation of implementing EOP-202 is not permitted since RPV level would be further challenged without sufficient high pressure feed sources available to maintain level.

CRS enters EOP-102, re-enters EOP-101. ESG-015 Page 16 of 31 Rev: 19 A trigger point of "RPV level is -100 inches and lowering" is recommended for evaluating the

ST AliA monitors EOP-102 implementation.

need to re-align or not initiate containment sprays [RHR pumps are needed for adequate core cooling (ACC)] based upon the following items: The rate of level drop increases dramatically when RPV level is less than -100 inches. Allows for successful realignment prior to reaching TAF. -Re-emphasizes to the control room team that the focus is on maintaining ACC. Allows for a focused decision over initiating Containment Spray to avoid an EOP-202 Slowdown, with the risk of not having RHR realigned to provide ACe when < T AF. 'Crew resources may not be readily available during the Slowdown event; therefore the strategy of realigning the RHR systems for injection prior to reaching T AF ensures that the systems will inject as soon as pressure is < 360 psig. Up front re-alignment of RHR will afford the crew the opportunity to detect and correct any RHR system failures which would prevent successful injection.

Re-alignment of RHR pumps is not required if there is a HIGH degree of certainty that RPV level will remain above TAF during the event (Le., RCIC is able to maintain>

TAF, but not> -100"). The crew should be prepared to realign pumps should conditions adversely change.

RO/PO verify automatic actions.

Crew recognizes failure of '0' RHR to start and inject by: :::> Absence of OHA A7-B4 "RHR PUMP 0 AUTO START" :::> Pump STOPPED indication

=> Zero motor amps ESG-015 Page 170f31 Rev: 19 PO starts 'D' RHR pump. CRS directs restoring PCIG to SRVs and Rx Bldg to Torus Vac Bkrs. RO/PO restore PCIG to SRVs and Rx Bldg to Torus Vac Bkrs lAW AB.ZZ-0001 Att. 9. SM determines an Alert Classification is required lAW ECG Section 3.2.2.b (Valid High Drywell Pressure). ST AliA turns over with extra SRO or SM to independently assess ECG Classification. STAIIA validates Alert lAW ECG Section 3.2.2.b.

SM declares Alert lAW ECG Section 3.2.2.b. Page 18 of 31 HPI USED: STARD HPI USED: STAR 0 HARD CARD 0 The LOP results in a UE lAW 7.1.1. The STA is responsible to perform an I.V. of the EAL Classification.

The ST A verification does not alleviate the requirement of the SM to make a timely classification.

Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO. RECORD time Alert declared.

Time Declared: Rev: 19 IE directed to align for two CRD pump injection, THEN PERFORM the following:

REFER to SO.BF-0001 Sect TRIGGER ET-5 (Suction SET Remote Function for CRD pump discharge valve 0% (CD01/CD02).

REPORT Stby CRD ready for WHEN Stby CRD is THEN RAMP discharge to 100% IE directed to manually THE"I REPORT you opened the (There is no function for AFTER HV-F003 is THEN TRIGGER WHEN two minutes THEN MODIFY CD09A1B to control IE instrument air pressure THEN REPORT the FCVs not seem to be ST AliA verifies isolations and monitors containment performance. CRS orders injection with two CRD pumps. CRS orders injection with 'B' SLC pump. CRD pumps will trip on low suction pressure due to suction filter clogging.

IF RPV water level reaches -161", THEN RECORD the time for 15 minute ECG Classification:

TIME -161" reached: ___ Crew may request EOP-323

WHEN RPV water level drops to implementation.

If so, -129", TRIGGER ET-10. THEN the Crew inhibits ADS. . ESG-015 Page 19 of Rev: 19 WHEN the Crew determines RPV water level cannot be maintained above -185", THEN between -129" and -185" the CRS implements EOP-202. RO/PO open ADS valves lAW AB.ZZ-0001 Attachment

13. Before RPV water level has been below -185" for two minutes, Crew opens five SRVs to Emergency Depressurize the reactor. IF RPV level reaches-161", THEN SM determines a SAE is required lAW ECG Sections:

3.1.1 .a ( 3pts) AND => 3.2.1.b or 3.2.2.b (4 pts) STAIIA turns over with extra SRO or SM to independently assess ECG Classification.

HPI USED: STAR 0 HARD CARD 0 RECORD the time between -185" (compensated) and five SRVs are opened. TIME: ___ ESG-015 Page 20 of Rev: 19 IF RPV level reaches -161", THEN STA validates a SAE is required lAW ECG Sections:

=;> 3.1.1.a(3pts)

AND =;> 3.2.1.b or 3.2.2.b (4 pts) RO/PO inject with available ECCS lAW AB.zZ-0001:

=;> Att. 4 for B/C/D RHR =;> Att. 4 for 'B' Core Spray loop WHEN RPV pressure is <450 psig, THEN Crew recognizes failure of HV-F017D to open. RO/PO open HV-F017D lAW AB.ZZ-0001 Att. 4. WHEN reactor pressure drops to 400 psig, THEN Crew recognizes inability to determine RPV water level due to widely diverging indications.

The ST A is responsible to perform an I.V. of the EAL Classification.

The ST A verification does not alleviate the requirement of the SM to make a timely classification.

Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO. HPI USED: STAR 0 HARD CARD 0 PEER CHECK 0 ESG-015 Page 21 of Rev: 19 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION EOP-206/EOP 206A RPV Flooding. "Can 5 ADS valves be opened?" This question should be answered strictly based on the present conditions.

This question is NOT asking whether the valves can be opened, it is asking if they are open now. If RPV pressure is too low to maintain an SRV open, the decision steps should be answered "No." Since RPV pressure would be less that 62 psig above suppression chamber pressure in those cases, EOP-206 and EOP-206A would direct implementation of the same steps that would be taken if the SRVs were open, ending at step RF-12 in 206 and RF-30 in EOP-206A.

Available RPV pressure indicators: PI-R605 PAMS PR-R3684B A2802 PT -3684B A3547 RRCS Div 2 Ch A A3548 RRCS Div 2 Ch 8

Local gauges PI-R004A1B Available Supp Chamber pressure indicators: PR-496081 PI-4960B1 A2814 W/R Supp Chbr Press CRS exits EOP-101 and enters EOP-206. CRS directs commencing and raising injection to the MSIVs are flooded. Crew continues injection into the RPV until the RPV has been flooded to the Main Steam Lines as indicated by: :::;-At least 5 SRVs are open AND At least 2 of the RPV Flooded Indications of Table RF-2 can be observed.

RC/P leg was exited when EOP-202 was implemented, RC/L leg is exited when EOP-206 is entered. Cannot achieve MSIV flooding without injection from the '0' RHR pump. ESG-015 Page 22 of Rev: 19 WHEN RPV water level indication is lost, THEN Crew injects into the RPV until at least 2 of the RPV Flooded Indications of Table RF-2 can be observed. IF EOP-206 is successful, THEN SM determines a SAE is required lAW ECG Sections: 3.1.1.a (3 pts) AND 3.2.1.b or 3.2.2.b (4 pts) ST AliA turns over with extra SRO or SM to independently assess ECG Classification.

It will take about 10 minutes for the RPV to fill above the Main Steam Lines. Bases for ECG 3.1.1 , 3.2.1 and 3.3.1 states: If all Reactor Level instrumentation is lost and EOP 206 or EOP 206A is entered, then a SAE is warranted based on EALs 3.1.1 .a & 3.2.1.b (-161"). Successful implementation of EOP 206(A) assures a level at TAF will be maintained.

If EOP 206 is not successful, the process will not restore and maintain reactor level above -185". GE is appropriate based on EALs 3.1.1.b, 3.2.1.b, & 3.3.1. ESG-015 Page 23 of Rev: 19 IF EOP-206 is successful, THEN STA validates a SAE is required lAW ECG Sections:

, 3.1.1.a (3pts) AND: ::;, 3.2.1.b or 3.2.2.b (4 pts) IF EOP-206 is successful, THEN SM declares a SAE lAW ECG Sections:

, 3.1.1.a (3pts) AND: ::;, 3.2.1.b or 3.2.2.b (4 pts) IF EOP-206 is NOT successful, THEN SM declares a GE lAW ECG Sections:

, 3.1.1.b (4 pts) AND 3.2.1.b or 3.2.2.b (4 pts): ::;, 3.3.1 (1 The STA is responsible to perform an I.V. of the EAL Classification.

The ST A verification does not alleviate the requirement of the SM to make a timely classification.

Should the SM fill the ST A role, independent verification of the EAL classification will be delegated to another on-shift SRO. RECORD time SAE declared.

Time Declared: Termination Thefscenariornay .. . terminatedatthe discretion of the Lead Examinerwhen

been established lAW EOp': '206.>

ESG-015 Page 24 of Rev: 19 A. TO-AA-1 06-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JT A Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG) G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-1 04-1 01 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1004 Operations Standards M. OP-AA-1 01-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines O. OP-AA-1 08-114 Post Transient Review P. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program O. OP-HC-1 08-1 06-1 001 Equipment Operational Control R. HC.OP-AB.ZZ-0001 Transient Plant Conditions S. HC.OP-AB.ZZ-0135 Station Blackout/Loss of Offsite Power/Diesel Generator Malfunction T. HC.OP-AB.ZZ-0136 Loss of 120 VAC Inverter U. HC.OP-AB.ZZ-0150 125 VDC Malfunction V. HC.OP-AB.ZZ-0170 Loss of 4.16KV Bus 10A401 A Channel W. HC.OP-AB.BOP-0002 Main Turbine X. HC.OP-AB.CONT-0001 Drywell Pressure Y. HC.OP-AB.ZZ-OOO Reactor Scram Z. HC.OP-EO.ZZ-0101 RPV Control AA. HC.OP-EO.ZZ-0102 Primary Containment Control BB. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization CC. HC.OP-EO.ZZ-0206 RPV Flooding DD. Strategies For Successful Transient Mitigation ESG-015 Page 25 of 31 Rev: 19 ESG-015 I 1 . Crew starts the 'B' EDG by Pressing the 'B' EDG START pushbutton in the Control Directing an operator to locally start the 'B' KIA 295003 Partial or Complete Loss of A.C. AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF AA1.02 Emergency generators RO 4.2 SRO AA 1.03 Systems necessary to assure safe plant shutdown RO 4.4 SRO Due to the loss of 100410, the 'A' EDG and 'A' Channel ECCS components are unavailable.

This leaves the 'B' RHR pump as the only immediately available means of removing decay heat from the containment.

The 'B' RHR pump will be required for injection to successfully implement EOP-206 and ensure adequate core cooling. Additionally, 'B' RHR is the only pump available with a heat exchanger for decay heat removal. 2. Before RPV water level has been below -185" for two minutes, Crew opens five SRVs to Emergency Depressurize the reactor. KIA 295031 Reactor Low Water Level EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA1.01 Low Pressure Coolant Injection RO: 4.4 SRO 4.4 EA1.02 High Pressure Coolant Injection RO: 4.5 SRO 4.5 EA 1.06 Automatic depressurization system RO 4.4 SRO 4.4 EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: EA2.04 Adequate core cooling RO 4.6 SRO 4.8 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 when 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. Two minutes to implement Emergency Depressurization provides an acceptable level of performance.

3. WHEN RPV water level indication is THEN Crew injects into the RPV until at least 2 of the RPV Flooded Indications Table RF-2 can be observed with 5 SRV's KIA 295031 Reactor Low Water EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER EA2.01 Reactor water level RO 4.6 SRO Reactor water level indication has been lost. The only way to ensure adequate core cooling is to successfully implement reactor flooding lAW EOP-206. Successful implementation requires all three available RHR pumps and the available core spray loop. The '0' RHR pump auto start and injection valve automatic opening are failed, and operator action will be required to align the '0' RHR pump for injection and successfully implement EOP-206. ESG-015 Page 26 of Rev: 19 ESG-015 f 19 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT EVENT Y Loss Of Offsite PowerlSBO LOCA Internal Flooding Y TRANSIENTS:

Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Inadvertent MSIV Closure Inadvertent SRV Opening Manual Scram LOSS OF SUPPORT SYSTEMS: Loss of SSW Loss of SACS Loss of Instrument Air COMPONENTfTRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT YIN KEY EQUIPMENT Y Y Y Y Hard Torus Vent HPCI 1 E 4.16KV Bus SACS HxlPump EDG 120VAC 481/482 Inverter AlB RHR RCIC SSW Pump Y Y Y SLC CRD 1E 125VDC KEY SYSTEMS 500KV AC Power SRVs Condensate/F eedwater PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION ___ Aligning RHR for Suppression Pool Cooling ___ Emergency Venting of Primary Containment Y Emergency Depressurize RPV WIG High Pressure Injection

___ Initiating LP ECCS with No High Pressure Injection Available Y Restoration of AC Power after a LOP (EDG /Offsite)

___ Monitoring and Control of SACS heat loads ___ Preventing LVL 8 trip of Feedwater during a transient

___ Align Core Spray Suction to CST when at NPSH limits ___ Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus ___ Inhibit ADS during ATWS Complete this evaluation form for each ESG-015 Page 27 of 31 Rev:

Rx Power: 100% WorkWeek:

A Risk Color: Green Activities Completed Last Shift: None Major Activities Next 12 Hours: None Protected Equipment:

None Tagged Equipment:

None ESG-015 Page 28 of 31 Rev: 19

@@ Line 2: / Line 2: @@
 | number = ML12083A242
 | issue date = 03/05/2012
-| title = Hope Creek - Final Operating Exam (Sections a, B, and C) (Folder 3)
+| title = Final Operating Exam (Sections a, B, and C) (Folder 3)
 | author name = Fish T H
 | author affiliation = NRC/RGN-I/DRS/OB
@@ Line 15: / Line 15: @@
 | page count = 438
 | project = TAC:U01845
-| stage = Other
+| stage = Acceptance Review
 }}
@@ Line 35: / Line 35: @@
 TQ-AA-106-0303 NAME: ____________________
 _ 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 hours and is determined to be a short term outage. Station Power Transformer 1T-60 was removed from service due to cooling fan malfunctions.
+It is expected to return in [[estimated NRC review hours::8 hours]] 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 lAW the ESO instructions. 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-ST.ZZ-0001, POWER DISTRIBUTION LINEUP -WEEKLY to Technical Specification 4.8.1.1.1.a Page 3 of 23 JPM: 22024 Rev: 01 SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup STEP NO. ELEMENT OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE (*Denotes a Critical Step) (#Denotes a Sequential Step) STANDARD * # NAME: DATE: EVAL StU Ttt-r\A-106-0303
@@ Line 82: / Line 82: @@
 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: Emergency Diesel Generator AG400 has a mechanical problem and is declared inoperable.
-It is expected to return in 8 hours and is determined to be a short term outage. Station Power Transformer 1T-60 was removed from service due to cooling fan malfunctions.
+It is expected to return in [[estimated NRC review hours::8 hours]] 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 lAW the ESO instructions. 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-ST.ZZ-0001, POWER DISTRIBUTION LINEUP -WEEKLY to satisfy Technical Specification 4.8.1.1.1.a only. Page 13 of 23
@@ Line 419: / Line 419: @@
 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 HC.OP-DL.ZZ-0026(Q)
-JOB PERFORMANCE MEASURE ATTACHMENT 3u Radioactive Gaseous Effluent Monitoring (North Plant Vent) TIS 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 Page 1 ofl 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 hours to ensure that the 4 hour 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 BeGS DATE: Today's Date Location Auxffllrb/Radwaste PARAMETER NORM NOW COMMENTS SOLID RADW ASTE EXH FAN A318 17,000 17358 -----1----
+JOB PERFORMANCE MEASURE ATTACHMENT 3u Radioactive Gaseous Effluent Monitoring (North Plant Vent) TIS 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 Page 1 ofl 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 [[estimated NRC review hours::3 hours]] to ensure that the 4 hour 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 BeGS DATE: Today's Date Location Auxffllrb/Radwaste PARAMETER NORM NOW COMMENTS SOLID RADW ASTE EXH FAN A318 17,000 17358 -----1----
 -........j---
 -+---+--SOLID RADWASTE EXH FAN 8318 17,000 17163 CHEMLAB EXH r--------------j-----CHEMLABEXH OFFGAS 10022 45.9TOTAL FLOW 49613.9 I I ESTIMATED TOTAL FLOW REPORTED TO RAD PRO (YES) Yes
@@ Line 697: / Line 697: @@
 @@[?W Page 8 of 8 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING.
 OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: ___T_C?day 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) (-) 3-=-5....'-.5
-__ DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 4/3/11 5.5 OR 24, whichever is less) 6/25/11 Hours authorized this date (max 24 hours) 8/30/11 24.0 8/31/11 NCO performing calculation DatelTime Jolin Smitli Today/0100 SM/CRS verification and authorization DatelTime Jlncfrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2) START TIME STOP TIME TOTAL HOURS Time at which valvelline 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 valvelline Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) Total number of hours valves/line open this permit: ___--=1.c::0.:...:.S'--
+__ DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 4/3/11 5.5 OR 24, whichever is less) 6/25/11 Hours authorized this date (max [[estimated NRC review hours::24 hours]]) 8/30/11 24.0 8/31/11 NCO performing calculation DatelTime Jolin Smitli Today/0100 SM/CRS verification and authorization DatelTime Jlncfrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2) START TIME STOP TIME TOTAL HOURS Time at which valvelline 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 valvelline Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) Total number of hours valves/line open this permit: ___--=1.c::0.:...:.S'--
 ___ NCO perform i ng calculations
 ___-'-jl_ndi-'!ry'-'<..Ci_ra_na_t_e_flt._t
@@ Line 745: / Line 745: @@
 (*Denotes a Critical Step) COMMENTS STEP
 * ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. STANDARD # S/U evaluation)
-Table If the Loss or Potential Loss is Operator reads NOTE. 3.0 considered IMMINENT (may occur NOTE within 2 hours), USE judgement classify as if the threshold I
+Table If the Loss or Potential Loss is Operator reads NOTE. 3.0 considered IMMINENT (may occur NOTE within [[estimated NRC review hours::2 hours]]), USE judgement classify as if the threshold I
 Table In the table review the Emergency Operator reviews the EALs of all 3.0 Action Levels of all columns and columns, and determines that all 1. identify which need further review. columns need further review. Table For each of the three barriers, Operator determines that the following 3.0 I determine the EAL with the highest EALs have been exceeded and 2. point value. No more than one EAL represent the highest value met or I should be selected for each barrier. exceeded for the respective 3.1.1.a; 3.2.2.b or 3.2.1.b; 3.3.2.b or 3.3.2.d. I I Table Add the pOint values for the three Operator adds the values, and enters 3.0 barriers and enter the total below: the value 9 in the appropriate space. 3. I Examiners Note: Determining this value for future use is critical; marking it I on Table 3.0 is not. I I ---...... Page 6 of 19
 -----------------
@@ Line 965: / Line 965: @@
 ------------------------
 NAME: DATE: 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 hours. 3. 'S' 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.
+: 1. The plant is in OPCON 4. 2. The reactor has been shutdown for [[estimated NRC review hours::200 hours]]. 3. 'S' 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. SC-HV-F007 A and SC-HV-F027 A have been tagged closed to support the evolution.
 : 7. Flush of A RHR Loop is not required.
@@ Line 1,079: / Line 1,079: @@
 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
-: 1. The plant is in OPCON 4. 2. The reactor has been shutdown for 200 hours. 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.
+: 1. The plant is in OPCON 4. 2. The reactor has been shutdown for [[estimated NRC review hours::200 hours]]. 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.
@@ Line 1,954: / Line 1,954: @@
 ====3.3.2 action====
-b.1.c applies (24 hours to place in a tripped condition).
+b.1.c applies ([[estimated NRC review hours::24 hours]] to place in a tripped condition).
 If requested, after an
 * Crew may implement appropriate delay, support GP.ZZ-0011 to place trip units actions of placing trip units in into tripped condition tripped condition by changing MALF MS09A severity to O. A CRD Pump Trip:
@@ Line 2,365: / Line 2,365: @@
 -Condition A PO verifies the Feedwater system is responding automatically and is restoring RPV level between level 4 and 7. Crew validates successful recirc isolation by: Seal pressures Trending DLD flows Trending drywell pressure and temperature CRS verifies core parameters are within the OPRM Enable Region of the Power to Flow Map. ESG-NRC-S4 Page 14 of Rev.: 05 Fuel Cladding*
 Failure: 10 minutes after the Pump at the Lead TRIGGER ET-8(tuel 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 hours 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" RM11 9RX509/510/511/512 Alert alarms and readings CRI DS Page 37 MSL Radiation readings CRS implements AB.RPV-0008: Condition A Condition B Condition C RO reduces power lAW RE Guidance (Reverse Pull IF the Crew scrams during the Recirc Runaway, THEN the Fuel Failure will automatically be inserted.
+=> 3.4.1.1 Action a. within [[estimated NRC review hours::4 hours]] 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" RM11 9RX509/510/511/512 Alert alarms and readings CRI DS Page 37 MSL Radiation readings CRS implements AB.RPV-0008: Condition A Condition B Condition C RO reduces power lAW RE Guidance (Reverse Pull IF the Crew scrams 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 15 of Rev.: 05 ENSURE MSL Radiation Malfunctions RM9509-RM9512 ramp down to <20 when the Main Steam Lines AND drain lines are isolated. Crew recognizes HI-HI MSL Radiation levels by: =::> OHA C6-B2 liMN STM LINE RAD HI HI OR INOP" =::> RM11 9RX509/510/511/512 High alarms =::> CRIDS Page A037 MSL Radiation readings CRS directs: =::> Locking the Mode Switch in SHUTDOWN Closing MSIVs, HV-F016 and HV-F019 steam line drains. RO locks the Mode Switch in SHUTDOWN. RO performs scram actions lAW AB.ZZ-0001 Attachment
@@ Line 2,455: / Line 2,455: @@
 * Crew dispatches ABEO and Maintenance to investigate loss of 10D410 bus. HPI USED: FLAGGING 0 OP BARRIERS 0 (May flag/barrier
 'A' EDG to remind of it's unavailability, since the START light is lit) E-0009-1 Sheet 1 ESG-015 Page 6 of Rev: 19 Crew recognizes closure of HV-2197A Backwash valve by 10C651A indication. CRS directs opening HV-2197 A. PO opens HV-2197A. CRS/ST AliA recognize the following Tech Specs actions apply: ==> D.C. Sources -Operating 3.8.2.1 Action a ==> Distribution
--Operating 3.8.3.1 Action b SM contacts Operations Management to initiate a Prompt Investigation. SM determines an 8 hour report is required lAW ECG Section 11 .2.2.b (Event/Condition that could have prevented certain Safety Functions) due to the loss of a Single Safety Train System (HPCI). Crew recognizes Main Turbine High Vibration by: ==> OHA D3-C5 "TURBINE GENERATOR VIB HI" ==> CRIDS A2526 "MAIN TURB BRG 8 VIB X PROBE" ==> System 1 indication Loss of control power to 'A' SSW pump motor breaker makes the pump appear stopped to the valve logic. HPI USED: STAR 0 PEER CHECK 0 Need to restore the 1AD411 battery, 1 OD41 0 bus, and one charger in two hours, or be in Hot SID in next 12 hours. #8 Bearing will reach 11 mils in about 9.5 minutes. ESG-015 Page 7 of Rev: 19 SUPPORT requests to raise IVITlO temperature using Remote Function TU03. As System Operator, PROVIDE an acceptable band of 300-425 MVARS. LE contacted as Engineering, THEN REPORT the vibration readings appear valid and the limitations in the abnormal should be followed.
+-Operating 3.8.3.1 Action b SM contacts Operations Management to initiate a Prompt Investigation. SM determines an 8 hour report is required lAW ECG Section 11 .2.2.b (Event/Condition that could have prevented certain Safety Functions) due to the loss of a Single Safety Train System (HPCI). Crew recognizes Main Turbine High Vibration by: ==> OHA D3-C5 "TURBINE GENERATOR VIB HI" ==> CRIDS A2526 "MAIN TURB BRG 8 VIB X PROBE" ==> System 1 indication Loss of control power to 'A' SSW pump motor breaker makes the pump appear stopped to the valve logic. HPI USED: STAR 0 PEER CHECK 0 Need to restore the 1AD411 battery, 1 OD41 0 bus, and one charger in two hours, or be in Hot SID in next [[estimated NRC review hours::12 hours]]. #8 Bearing will reach 11 mils in about 9.5 minutes. ESG-015 Page 7 of Rev: 19 SUPPORT requests to raise IVITlO temperature using Remote Function TU03. As System Operator, PROVIDE an acceptable band of 300-425 MVARS. LE contacted as Engineering, THEN REPORT the vibration readings appear valid and the limitations in the abnormal should be followed.
 LE contacted as Operations Manager for concurrence to commence a controlled shutdown lAW 10-0004, THEN CONCURR with SM recommendation.
 LE dispatched to check bearing drains, THEN wait until vibration reaches 15 mils and REPORT the floor was vibrating and it did not appear safe to approach the Main Turbine. CRS implements AB.BOP-0002: Condition B ST AliA monitors implementation of AB.BOP-0002 and applicability of Retainment Overrides. Crew directs TBEO to raise MTlO temperature (110 120"F) Crew co-ordinates with System Operator to adjust Main Generator MVAR loading. Crew contacts Engineering for additional guidance. Crew contacts Operations Manager for concurrence to commence a controlled shutdown lAW 10-0004. WHEN bearing #8 reaches 11 mils, THEN Crew: Reduces recirc pump speed to locks the Mode Switch Immediately trips the Main Turbine. Page 8 of 31 HPI USED: STAR 0 PEER CHECK 0 HPI USED: STAR 0 PEER CHECK 0 Rev: 19 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Reports Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status lAW HC.OP-AB.ZZ-0001.
@@ Line 2,479: / Line 2,479: @@
 The Control Room Supervisor may elect not to utilize a second tier pressure band based on current plant conditions.
 LOP/LOCA: CRS directs maintaining reactor pressure below 1037 psig with SRVs. RO/PO control RPV pressure with SRVs as directed by CRS lAW AB.ZZ-0001 Att 13. 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. Crew recognizes failure of the 'B' EDG to start and load by: =:> Engine STOP light =:> Output breaker TRIP light =:> OVLD/PWR lights on 'B' Channel components Page 13 of 31 HPI USED: STAR 0 HARD CARD 0 Rev: 19 IF directed to locally start 'B' THEN DELETE As ESOC, REPORT it will at least 10 hours to Offsite power to Artificial RO/PO start the 'B' EOG and ensure it loads. 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.
+=:> TRIP indication for all 500 KV breakers =:> Flashing TRIP lights for all previously closed bus infeeds. =:> Numerous OVLD/PWR FAIL lights. Crew recognizes failure of the 'B' EDG to start and load by: =:> Engine STOP light =:> Output breaker TRIP light =:> OVLD/PWR lights on 'B' Channel components Page 13 of 31 HPI USED: STAR 0 HARD CARD 0 Rev: 19 IF directed to locally start 'B' THEN DELETE As ESOC, REPORT it will at least [[estimated NRC review hours::10 hours]] to Offsite power to Artificial RO/PO start the 'B' EOG and ensure it loads. 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.
 * Crew contacts ESOC for estimated time to restoration of Offsite power. CRS implements AB.ZZ-0135. Crew recognizes loss of A0481/482 inverters by: => Loss of 'A' Channel PAMS indications Loss of power to 'A' Channel electrical indications on 10C6500 As time and resources permit, CRS implements AB.ZZ-0136 and AB.ZZ-170.
 HPI USED: STAR 0 PEER CHECK 0 I mmed iateOperator Action lAW AB.ZZ-0135.

v t e Letter Sequence Acceptance Review
TAC:U01845, (Open)
Initiation Acceptance Administration Questions Answers Results Approval... Other: ML12083A212, ML12083A223, ML12083A235, ML12172A046
MONTHYEAR2012-03-01 [Table View]

ML12083A242: Difference between revisions

Revision as of 15:53, 4 April 2019

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2.1.1 SATISFACTORY

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