Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML12083A242
Person / Time
Site:	Hope Creek
Issue date:	03/05/2012
From:	Todd Fish; Operations Branch I
To:	; Public Service Enterprise Group
	Jackson D
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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JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup TASK NUMBER: 2630010201 JPM NUMBER: 305H-JPM.zZ024 REV #: 01 SAP BET: NOH05JPZZ24E ALTERNATE PATH: D APPLICABILITY:

EO D RO ((J STA~---, SRO D

TQ-AA-106-0303 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 IMPORTANCE FACTOR: 4.2 3.9 APPLICABILITY: RO SRO EOD ROW STAD SROD 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:

1. 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.

2. 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.

3. HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, is due.

4. Salem Unit 3 Gas Turbine Generator is available.

5. 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 3 of 23

Ttt-r\A-106-0303 JPM: 22024 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

(*Denotes a Critical Step) COMMENTS STEP

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

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

CUE ENTER START TIME AFTER

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

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

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

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

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.

Page 4 of 23

Ttt- ,.,.A-1 06-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluati 5.0 Power Distribution Lineup N/A 5.1 LOG test start time in the Control Operator requests that the start time be Room IOg(5). 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

TCt~rlA-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) J 5.2 ENSURE that all prerequisites have Operator ensures that the prerequisites been satisfied lAW Section 2.0 of this are satisfied:

procedure.

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.

I---

Operator initials the step.

CUE IF asked, "No other testing or maintenance is in progress that will NA adversely affect the performance of this test."

Page 6 of 23

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

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

("'Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) I 5.3 ENSURE Attachment 1, Section 1.0 Operator observes that Attachment 1, of the SM/CRS Data and Signature Section 1.0 of the SM/CRS Data and Sheet has been completed and Signature Sheet has been completed Regular Surveillance or Retest is and Regular Surveillance is indicated.

indicated.

Operator initials the step.

[---------

5.4 IF performing this procedure to satisfy Operator determines that these TIS Surveillance 4.8.1.1.1.a ONLY, sections only are to be completed and PERFORM the following sections: initials step.

[TIS 4.8.1.1.1.a]

4.16KV SWITCHGEAR 10A401

4.16KV SWITCHGEAR 10A402

4.16KV SWITCHGEAR 10A403

4.16KV SWITCHGEAR 10A404

OFFSITE TO ONSITE DISTRIBUTION 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.4.1 When in an extended outage for A or Operator determines the outage of A B EDG, VERIFY, through Salem EDG is not an extended outage.

operations, that Salem Unit 3 Gas Turbine Generator is available to supply Hope Creek #2 Station Power Examiner Note: The field on Transformer AND LOG ON OFFSITE Attachment 2 for the Salem Unit 3 Gas TO ONSITE DISTRIBUTION. Turbine is not required but may be filled in by the operator since the status is listed on the Initial Conditions sheet.

5.5 RECORD M& TE identification Operator determines that this step is numbers and calibration due dates for not required and marks step as N/A.

test equipment utilized for this test on Attachment 3 and the PSEG Nuclear Home Page.

~- ....... - -_._....... __ _

Page 8 of 23

TQ-~-1 06-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) 5.6 PERFORM Power Distribution Lineup Operator observes the breaker by completing Attachment 2. positions, (and bus Voltage for the 4.16KV busses) of those breakers listed in Attachment 2 for:

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.

~ I Page 9 of 23

TQ-J"\A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME:

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

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.7 IF any indication not specified in Operator determines that the lineup

Attachment 2 was used to satisfy this specified in Attachment 2 was not in the surveillance THEN DOCUMENT AND REQUIRED positions used to satisfy JUSTIFY its use in Section 2.1.4 of this surveillance, marks those as Attachment 1 . UNSAT and informs the CRS.

Examiner Note: See attached grading key.

Operator initials the step.

~~~

5.8 LOG test end time in Control Room log{s).

CUE Log entry completed. Operator initials the step.

5.9 SUBMIT this procedure to the SM/CRS for review AND completion of Attachment 1.

-~ -~

Page 10 of 23

TGt-",A-106-0303 JPM: ZZ024 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Administrative TASK: Conduct Weekly Power Distribution Lineup

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD SJU eva I

~AAW~o~'------~*--*---------_-_'----~

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

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

STOP TIME:

Page 11 of23

TQ-AA-106-0303 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 UNSAT Page 12 of 23

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

1. 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.

2. 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.

3. HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, is due.

4. Salem Unit 3 Gas Turbine Generator is available.

5. 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

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

INI1"IALIZE the simulator to 100% power, MOL.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

Complete Section 1 for Regular Surveillance and 4.8.1.1.1.a ONLY.

Setup Electrical Distribution System as noted on page 24 of Attachment 2.

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

Page 14 of 23

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

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 2 Page 6 of 33 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY 1.0 Power Distribution Lineup (Continued)

. EQUIPMENT SATI 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, 1BX501 ) 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 2 Page 90f33 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY 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, 1BXS01 ) 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 HC.OP~ST.ZZ-0001 (Q)

ATTACHMENT 2 Page 12 of 33 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY 1.0 Power Distribution Lineup (Continued)

SATI EQUIPMENT NOMENCLATURE REQUIRED ACTUAL PERF UNSAT 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) 4.

H STATION SERVICE TRANSFORMER THE FOLLOWING READI~

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 2 Page 15 of 33 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY 1.0 Power Distribution Lineup (Continued)

SATI EQUIPMENT NOMENCLATURE REQUIRED ACTUAL PERF UNSAT 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 ALTERNATE FEEDER BKR TO BUS OPEN SAT Initials, 10A404 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, 1BX501) have the same voltage and associated CRIDS points should read the same discounting instrument loop inaccuracies. If in normal 2 bus (or less) alignment, any of the following CRIDS points are considered equivalent and may be substituted for any other if one or more is a failed indicator: (For 1AX501; A3209, A3484, A7061 , A7066) (For 1BX501: A3210, A3487, A7076, A7071 Rev.15

PSEG Internal Use Only HC.OP-ST.ZZ-0001 (a)

ATTACHMENT 2 Page 24 of 33 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY 1.0 Power Distribution Lineup (Continued)

SATI PERF EQUIPMENT NOMENCLATURE REQUIRED ACTUAL UNSAT 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 IF all four of the 1E 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 Only HC.OP-ST.ZZ-0001 CQ}

ATTACHMENT 1 Page 2 of3 SM/CRS DATA AND SIGNATURE SHEET POWER DISTRIBUTION LINEUP - WEEKLY 2.0 POST TEST INFORMATION 2.1 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

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 JPM NUMBER: 30SH-JPM.ZZ016 REV #: 01 SAP BET: NOH05JPZZ16E ALTERNATE PATH: D APPLICABILITY:

EO SRO DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: <<K fit; Ie..

'C DATE: Ih-v/;~

APPROVED BY: cntotlL:

Training Department DATE: J/?D/J).

t

TQ-AA-106-0303 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, 1OC611 AND MSL Radiation (Items 61-74 of Attachment 1a) lAW HC.OP-DL.ZZ-0026.

Page 3 of 18

T~~I"\A-1 06-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

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

CUE ENTER START TIME AFTER Operator repeats back the Initiating C~: I WA START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-DL.ZZ-0026 3.1 COMPLETE Attachment 1 (all Operator records readings for Items

subsections) daily. 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.

Page 4 of 18

TCl-.--.A-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluatio CUE PROVIDE Operator reading from N/A Exhibit 1 for any missing or inoperable indicators 3.2 IF in OP CON 4 or 5, THEN Operator determines this step does not COMPLETE Attachment 2 as follows apply.

daily:

3.3 COMPLETE Attachment 4 to perform Operator determines this step does not surveillances required by Special Test apply.

Exceptions as necessary. Examiner Note: lAW the Initiating Cue, only Items 61~74 of Attachment 1a are required.

3.4 ENTER the Operational Condition Operator enters the Operational and date on each page of the log in Condition and date in the blanks the blanks provided. provided.

3.5 COMPLETE the applicable Operator determines this step does not subsections of Attachment 3 as apply.

directed by the SM/CRS to satisfy Examiner Note: lAW the Initiating Cue, Surveillance Requirements which require accelerated surveillances due only Items 61-74 of Attachment 1a are to off~normal conditions. required.

Page 5 of 18

Ttt-nA-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluatio 3.6 COMPLETE all surveillances as WHEN the deviation for Item 65 (RPV

indicated in each log. LEVEL 3) is recognized to exceed the IF a Technical Specification MAX DEVIATION of 4, Surveillance cannot be successfully THEN Operator notifies CRS of the completed OR is out-of-spec, unsatisfactory reading.

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 N/A Operator on Item 65 deviation.

3.6.1 IF a work order is issued to repair an Examiner Note: Since no work order abnormal reading, THEN NOTE the number will be provided to the operator, work order number in the comment this step will not apply.

section.

3.6.2 IF an Action Statement Log Sheet is Examiner Note: Since no Action issued due to a failed surveillance, Statement Log Sheet Index Number will OR one is already issued that covers be provided to the operator, this step the failed surveillance, THEN NOTE will not apply.

the Action Statement Log Sheet Index Number in the comments section.

Page 6 of 18

TQ-AA-106-0303 JPM: 22016 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs

{*Denotes a Critical Step} COMMENTS STEP

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

STANDARD S/U evaluation 3.6.3 IF a surveillance item is out-of-spec or WHEN the deviation for Item 65 (RPV not successfully completed, LEVEL 3) is recognized to exceed the THEN REFER to step 3.11 for T/S MAX DEVIATION of 4, reference numbers and notes. THEN Operator refers to Step 3.11 for Item 65 T/S reference numbers and notes.

3.7 IF performing a channel check that Operator performs channels checks on

requires a comparison between Attachment 1a Items 61-74, recording channels, the difference between the high and low THEN RECORD the difference value and trip status, and recognizes between the high and low value and the value for Item 65 exceeds the MAX trip status. DEVIATION of 4.

Examiner Note: Critical portion is recognizing the Item 65 deviation exceeds the MAX DEVIATION.

Note: The trip status is indicated by the following:

The trip light for instruments supplied with trip lights

The a/arm(s) AND/OR automatic actions for instruments not supplied by trip lights.

Page 7 of 18

TQ~MA~1 06-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME: _________________

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs

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

EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 3.8 For checks which are performed after Operator determines this step does not the logs have been taken for the time apply.

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 I 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.

Page 8 of 18

TQ-MA-106-0303 JPM: ZZ016 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Administrative TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

S/U ~oowl'oof----------""",

STANDARD evaluati 3.9 COMPLY with the following requirements regarding log item numbers followed by an "at sign" (@):

3.9.1 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 Operator takes all readings from the the equivalency of the alternative identified instrument.

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.

3.9.2 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 Operator takes all readings from the can take voltage readings on the identified instrument.

instrument(s) and the results compared before declaring the system inoperable.

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

("'Denotes a Critical Step)

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

STANDARD 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.

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

STOP TIME:

Page 10 of 18

HC.OP-DL.ZZ* .6(Q)

Surveillance Log - Control Room -Day Shift Operational Condition 1 Date Today's Date OPER PANEL 10C609 PANEL 10C611 INST MAX ACCEPTABLE LIMITS INST ITEM SURVEILLANCE COND !NST VALUE INST VALUE INST VALUE INST VALUE DEVIATION DEVIATION MIN NORM MAX TRIPPED I

, I YES/NO

,~- ~-~,~-

61@ RPV PRESSURE 1,2 N678A 1010 N678C 1010 N678S 980 N678D

~-

980 30 100 1037 NO 62@ DRYWELL PRESSURE 1,2;3 N650A 0.5 N650C 0.4 N650a 0.3 N650D 0.4 0.2 1 -- -- 1.68 NO 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@'

65@

MSL PRESSURE RPVLEVEL3 ",

1 1,2,3 N676A N680A 950 42 N676C N680C 950 34 N676S N680B 940 34 N676D N680D 960 35 i(

...2Q.

8 )

80 4

756 12.5 NO NO 66@

NORTH SDV LEVEL

" (NOTE 61) 1,2;5 N/A N/A N601C 0 N/A N/A N601D 0 - 10 -- -- 72 NO 67@ SOUTH SDV LEVEL (NOTE61) 1,2,5 N601A 0 N/A N/A N6Dia 0 N/A N/A 0 {;,,10 --' ---, 72 NO

~-~

68@ MSLAFLOW "'. 1,2,3 N686A 79 Ne86C 80 N686B 79 N686D 69 it,*!!,!,!!,* i(i,\;;;i,;~.8 -- --- 162.. 8 NO

~-~

69@ MSL S FLOW 1,2,3 N687A 79 N6S7C 75 N687S 68 N687D 80 f~rl'; UI ilk ***i~>,."" ',,- 162.8 NO 70@ MSLCFLOW 1,2,3 N688A 72 N688C 78 N688a 68 N688D 77 i ........ ,10* . . >*'*,;i 18"';'" -- - 162.8 NO 71@ MSLD FLOW 1,2,3 N689A 81 N689C 78 N689B 75 N689D 79 6'\, !I;", 18 -- -- 162.8 NO 1_\;

72@ RPV LEVEL 2 (NOTE 27..) 1,2,3,* N681A 30 30 N6B1S 35 N681D 6 "', "'l~~'

15 -38 - - NO

, NOTE29.* '" ,

@ RPVLEVEL 1 1,2,3 N684A N/A N684C N/A N684a N/A N684D", _N/,A,<l,ll, ~t'llN/A NlA -129 - -- NO 73@ RWCU dF (NOTE 56., 57.) 1,2,3 XR11497 0 N/A ',". NfA I', NfA N/A XR11499 o ~': i"'i'~ 0 20 --- -- 56 NO L::!- .. ~ib"i~; ".~?i' RM-11 37:l9RX~38.5

~5;i~~~ ij!;'i~+}" l~~f} I~

MSL RADIATION 1.,2.3 9RX509 9RX511 2.7 (NOTE 53.) NO (NOTES 53.., 54.. ) NOTE 55.; NORM

.-~-- -- - ..... _.- ---_ .. ~ .. ~_. -.:--;--":":':._, ... ,-,";"-':":", ~_.~ .. ~:...::-::..:..~.~ ......_u._ , ~' ..... ..

~

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

, ~.

_ _ _ _ _ _ *. H'"

NOTE 29 ALSO REQUIRED WHEN SECONDARY CON~IAINMENT REQUIRED TO BE IN EFFECT lAW TIS:, {7002177S], .

NOTE 53. 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" ~.KEY) 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 54.: IF RM-11 IS AVAILABLE, AND. WHENEVER RX POWER IS ABOVE 94% RTP AND ~AS;l3EEN 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 RMSl'~YST5M 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 P'~GRESS).

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 SAT~FI5$j~ 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, AD~¥I!~.R;fiiPW V~LUES UNDER "NORM" C~LUMN TO OBTAIN REA~II'lG. (MAY RESULT IN,NEGATIVE VALUE MSL AVERAGE FULL POWER BACKGROUND CHECK MSLRMSA MSLRMS B MSLRMS C MSLRMS D a RM-11 LAST HOURLY AVERAGE 37.5 38.5 35.8 36.8 f----fl b RM-11 HI SETPOINT 130 125 121 129 c c = a I b x 3 (RATIO OF ACTUAL TO BASELINE AFPB) 0.850 .865 .924 .887 .856 Page 11 of 18

TQ-AA-106-0303 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

TQ-AA-106-0303 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, 1OC611 AND MSL Radiation (Items 61-74 of Attachment 1a) lAW HC.OP-DL.ZZ-0026.

Page 13 of 18

HC.OP-DL.ZZ-OU26(Q)

JOB PERFORMANCE MEASURE Surveillance Log - Control Room -Day Shift Operational Condition Date OPER PANEL 10C609 PANEL 10C611 INST MAX ACCEPTABLE LIMITS INST ITEM SURVEILLANCE COND INST VALUE INST VALUE INST VALUE INST VALUE DEVIATION DEVIATION MIN NORM MAX TRIPPED YES/NO 61@ RPVPRESSURE 1,2 N678A N678C N6788 N678D 100 1037 NO 62@ DRYWELLPRESSURE 1,2,3 N650A N650C N650B N650D 1 -- --- 1.68 NO

.. .... NOTE 29

63@ CONDENSER VACUUM 1,2,3 N675A N675C N675B N675D

--- c --

2.5 ..... 8.5 --- -- NO 64@ MSL PRESSURE 1 N676A N676C N676B N676D SO 756 -- --- NO 65@ RPVLEVEL3 1.2,3 N680A N680C N6BOB N680D "

4 .... 12:5 --- --- NO 66@ NORTH SOV LEVEL (NOTE 61) 1,2,5 N/A N/A N601C N/A N/A N601D 10 - -- 72 NO 67@ SOUTHSDV LEVEL

.. , (NOTE61) 1.2.5 N60iA N/A NfA N601B N/A N/A 10 -- ---, 72 NO 68@ MSLAFLOW 1,2.3 N68SA N686C N686B N686D 18 -- ---' 162.8 NO 69@ MSLB FLOW 1,2,3 N687A N687C N687B N687D 18 -- --- 162.8 NO 70@ MSLCFLOW 1,2,3 N6SSA N688C N68SB N68SD 18 -- -- 162.8 NO 71@ MSLDFLOW 1,2,3 N689A N689C

--- - N689B N689D 18 --- 162.S NO

,72@ RPV, LEVEL 2 (NOTE 27) 1,2,3:

NOTE 29.

N681A N681S N681D 15 ,38 -- --- NO

@ RPVLEVEL 1 1,2,3 N684A N/A N684C N/A N684S N/A N684D N/A N/A N/A -129 --- - NO 73@ I" RWCU dF (NOTE 56., 57.) 1,2,3 XR11497 N/A N/A N/A NfA XR11499 20 - -- 56

NO I --

, RM-11 ...

IiNOTE I --- IN~~I 74@ MSL RADIATION 9RX509 9RX51 0 9RX511 9RX512 (NOTE 53.) NO 1,2,3 (NOTES 53.. , 54..) 55..

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 UNAVAILABLE, 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 SELF-TEST (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 (PRESS EXIT'" KEY; PRESS ETC'" KEY; PRESS DISPLAY OFF'" KEY). [70001230]

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.

NOTE571~:

U,...,'-'L...,..,f"-"" .. '*".'..I'1 ... , ' _ " . . . . ~, ...., . , .......... -_.- .......... " . "'_l'*~ .....u ...*...... _ ....... , ..... _ ... 'I, ....................................... , *." ...... " ........ _ .... ...,.w..... __ ..... ~H'._~ ...... !'-~......... ,........ ,'-..... ~ ...............~"""':.._~ **. ~_ ** _........ _,

MSl AVERAGE FULL POWER BACKGROUND CHECK MIN MSLRMSA MSLRMSB MSLRMSC MSLRMS D RM-11 LAST HOURLY AVERAGE

--I-- RM-11 HI SETPOINT

--- C------" - -

c =a I b x 3 (RATIO OF ACTUAL TO BASELINE AFPB) 0.850

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

INITIALIZE the simulator to 100% power, MOL.

Put Simulator in FREEZE.

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

Page 15 of 18

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

None None Insert malfunction RP18A to 43.00 RPS Level Xmitter LT-N080A Failure Insert malfunction RM9509 to 9RX509, MSL 'A' - Main Steam Line None None 37.50000 ChanA Insert malfunction RM9510 to 9RX510. MSL 'B' - Main Steam Line None None 38.50000 Chan B Insert malfunction RM9511 to 9RX511. MSL 'C' - Main Steam Line None None 35.80000 Chan C

Insert malfunction RM9512 to 9RX512, MSL 'D' - Main Steam Line None None . Chan D 36.80000 Page 16 of 18

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ016 Date Description 1 1/14/12 Reference procedure change only. No changes to nncr,;ur.

actions. No validation

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 JPM NUMBER: 305H-JPM.ZZ011 REV#: 01 SAP BET: NOH05JPZZ11 E ALTERNATE PATH:

D APPLICABILITY:

EOD RO [ ] ] STAD SRO DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: DATE:

APPROVED BY: DATE: }/Ig //2 Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: ZZ011 REV: 01 SYSTEM: Reactor Recirculation TASK NUMBER: 2020160101 TASK: Perform a Reactor Recirculation Pump Quick Restart ALTERNATE PATH: D KIA NUMBER:

2.2.40 IMPORTANCE FACTOR: 3.4 4.7 APPLICABILITY: RO SRO EOD RO[)) STAD SROD EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

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

Steam Tables/Calculator ESTIMATED COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - -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 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 # I S/U CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

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

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.RPV-0003.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be G.12.

G.12 ENSURE Differential Temperature Operator obtains HC.OP-AB.RPV-0003 requirements are met by completing Attachment 2.

Attachment 2. [TIS 4.4.1.4]

Page 4 of 16

TQ-#"\A*106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME: _________________

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

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

STANDARD StU evaluation)

I

.. *****HC.OP.;AB-RPV~00b3 Attachment 2 * * ". ..

1.0 REACTOR VESSEL TO BOTTOM HEAD DRAIN LINE DIFFERENTIAL TEMPERATURE CRITERIA NA 1.1 Rx Pressure Vessel Steam Space Coolant Saturation Temperature. (Rx Pressure and Steam Tables) (Note 1) Operator reads Note 1.

Operator determines RPV pressure 885 psig. (900 psia)

Operator determines Steam space

Coolant Saturation Temperature to be 900 psi a = 532 degF (Steam Tables)

Operator records value in space provided on Attachment 1 .

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

Page 5 of 16

TQ-AA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor 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)

Note 1 Steam Table as part of this attachment may be utilized to determine temperature rounding the numbers in a conservative fashion.

For a more accurate conversion from NA pressure to temperature a more detailed set of steam tables should be utilized.

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

- -~~-

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

Operator determines RWCU is in service and the Bottom Head Drain Coolant Temperature is valid.

i~-

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 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 S/U evaluation) I 1.3 < 145°F between Rx Pressure Vessel

Steam Space Coolant AND Bottom Operator subtracts value of step 1.2 Head Drain Line Coolant (A B). [TIS from value of step 1.1. and determines 4.4.1.4J value of 65 degF +/- 1F.

Operator records value in space provided.

~ -

1.4 Time Readings taken: Operator records current time in space

provided.

~-

r--

2.0 REACTOR VESSEL TO RECIRCULATION LOOP DIFFERENTIAL TEMPERATURE NA CRITERIA.

Page 7 of 16

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 STEP

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

STANDARD S/U evaluation) J 2.1 Temperature of the Rx Coolant within the idle loop to be started up.

Operator reads Note 3.

(Note 3)

- ~ -

Note 3 Use TR-650-831 Recirc Pump Suction Loop A(8) (if available) OR if above 400 0 F - CRIDS pOints A221 and A222 for A loop (A223 and A224 for 8 loop). IF below 400°F AND TR 650-831 not available, THEN have NA I&C obtain temperatures using RTD

-' ohm values (reference RTD ohm values to calibration data in TOR using HC.OP-GP.zZ-0008(Q))

Page 8 of 16

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

Operator determines RPV pressure is

885 psig. (900 psia)

Operator determines Steam space Coolant Saturation Temperature to be:

900 psia =532 degF (Steam Tables)

Operator records value in space provided on Attachment 1.

Page 9 of 16

TQ..nA-106-0303 JPM: ZZ011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU 2.3 < 50°F between the Rx Coolant within

Operator determines differential temp is the loop not in operation AND the

< 50 F.

Coolant in the Rx Pressure Vessel (A B). [TIS 4.4.1.4] Examiner Note:

Actual value is 22 degF .:t 1F.

2.4 Time Readings taken: _ _ _ __ Operator records current time in space

provided.

ENSURE Differential Temperature requirements are met by completing Operator initials step G.12.

Attachment 2. [TIS 4.4.1.4]

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

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

STOP TIME:

Page 10 of 16

TQ-AA-106-0303 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

TQ-AA-106-0303 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

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

INITIALIZE the simulator to 100% power, MOL.

Trip both Reactor Recirc Pump Drive Motor Breakers.

Take appropriate Scram actions lAW HC.OP-AB.ZZ-0001.

IMPLEMENT EOP-101 to stabilize plant at 885 psig RPV pressure on DEHC.

IMPLEMENT HC.OP-AB.RPV-0003 up to and including step G.11.

Acknowledge alarms.

Put Simulator in FREEZE.

MARKUP a copy of HC.OP-AB.RPV-0003 up to and including step G.11.

ENSURE Mode Switch key is removed.

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

Event code:

Description:

Event code:

Description:

Page 13 of 16

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

Page 14 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ011

'-R-e-v-#-rr---D-a-te----r------------------D-e-s-cr-ip-t-io-n------------------~V--aI-id--at~

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

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 JPM NUMBER: 305H-JPM.zZ019 REV #: 01 SAP BET: NOH05JPZZ19E ALTERNATE PATH: D APPLICABILITY:

EO RO [RJ STA '------' SRO DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY:

L

(~/Z-e-11 'Cft DATE: 1!r!:L APPROVED BY: ~uuy--- DATE: J/lo/)~

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: ZZ019 REV: 01 SYSTEM: Administrative TASK NUMBER: 4000270401 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates ALTERNATE PATH: D KIA NUMBER: 295938 EA 1.01

-~---

IMPORTANCE FACTOR: 3.9 4.2 APPLICABILITY: RO SRO EOD ROW STAD SROD 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 SIGNATURE: DATE:

Page 2 of 13

TQ*AA*106*0303 NAME:

DATE:

SYSTEM: Adm inistrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 INITIAL CONDITIONS:

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590.

2. SPDS is unavailable.

3. Abnormal HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity.

4. 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 HC.OP AB.CONT-0004, Action A.4.

Page 3 of 13

TQ-I-\A-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

(*Denotes a Critical Step) I

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

STANDARD Stu evaluation CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Coo: I WA START TIME:

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

Operator determines beginning step Operator determines correct beginning of the procedure. step to be A.4 A.4 DETERMINE the Total Release Rates Operator determines that to calculate of Noble Gas and Iodine as follows: the Noble Gas release from the NPV USE the SPDS Noble Gas Total. the formulas in Table "A" must be used.

OR USE one of the Formulas in Table "A".

Page 4 of 13

TQ-I"'\A-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

(*Denotes a Critical Step) COMMENTS STEP

EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)

NO. #

STANDARD StU evaluation) 1E the effluent (!-ICi/sec) channel on the RM-11 is NOT operating for a specific plant vent, THEN

_. CALCULATE the Noble Gas release rate for that vent using the following:

472 =

Plant Vent Exh IJCi/sec (n.g.)

!-ICi/cc (n.g.)

Flow in cfm Where:

IJCi/sec (n.g.) - the calculated release rate from the specified plant vent (Noble Gas)

IJCi/cc (n.g.) - The concentration of Noble Gas obtained from the RM-11 (the operable channel will be highlighted in GREEN) OR from an actual sample of the plant vent 472 - The conversion factor in units of cc/sec/cfm Operator manipulates the RM-11

terminal to obtain the value of NPV Noble Gas release from the 9RX602 Low Range detector and enters the value into the formula.

3.65E-7 uCi/cc.

Operator transfers the Plant Vent Exh

Flow value from Attachment 3u of HC.OP-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

(*Denotes a Critical Step) I

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

STANDARD StU Operator calculates the NPV Noble Gas

release rate.

Calculated Value =

3.65E-7IJCi/cc

49613.9 CFM

472

= 8.547 uCi/sec (+ 0.5}

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

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

STOP TIME:

Page 6 of 13

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

DATE:

JPM Number: ZZ019 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 QUESTION:

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

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

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 7 of 13

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

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590.

2. SPDS is unavailable.

3. Abnormal HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity.

4. 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 HC.OP AB.CONT-0004, Action A.4.

Page 8 of 13

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

JOB PERFORMANCE MEASURE ATTACHMENT 3u Page 1 ofl Radioactive Gaseous Effluent Monitoring (North Plant Vent)

TIS 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 If the North Plant Vent Flow Rate Monitor is Inoperable, then Effluent Releases via this pathway may continue for up to 30 days provided flow rate is estimated at least once per 4 hours0.167 days 0.0238 weeks 0.00548 months .

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 administrative requirements and after a change in the ventilation line-up.

If flow indication(s) become unavailable, then the "NORM" flow value may be logged for the specific fan alignment.

BeGS DATE: Today's Date Location Auxffllrb/Radwaste PARAMETER NORM NOW COMMENTS SOLID RADWASTE EXH FAN A318 17,000 17358

1---- - . . . . . . . . j - - - -+---+-- --+

SOLID RADWASTE EXH FAN 8318 17,000 17163 CHEMLAB EXH r CHEMLABEXH

j----- :::;+:::~~ ~~~~ -\--

OFFGAS HA-XR 10022 OR HA 45.9 FI5665 TOTAL 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)

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 off.

ENSURE MARKUP copy of HC.OP-Dl.ZZ-0026 Attachment 3u available.

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

Initial ET#

Event code: I I I

Description:

I Event code: I I

I

Description:

I Event code: I 1 I

Description:

I Page 10 of 13

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

Action Description 9RX590, NPV EFF - North Plant Vent None None Insert malfunction RM9590 to 0.00000 Noble Gas Effluent 9RX591 , NPV HIGH - North Plant None None Insert malfunction RM9591 to 0.00000 VentH Noble Gas 9RX602, NPV LOW - North Plant None None Insert malfunction RM9602 to 3.65E-7 Vent Range Noble Gas 9RX603, NPV MID - North Plant Vent None None Insert malfunction RM9603 to 0.00000 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

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation TASK NUMBER: H303000015 JPM NUMBER: 305H-JPM.ZZ045 REV #: 02 SAP BET: NOH05JPZZ45E ALTERNATE PATH: D APPLICABILITY:

EO RO STA SRO [KJ DEVELOPED BY: Steve Dennis DATE: 2/8/12 Instructor

/

cl-/O)~

REVIEWED BY:\., DATE:

APPROVED BY: 9? tcru: l.\..lls",,,\

Training Department DATE: ?/q/}~

TQ-AA-106-0303 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/METHOD: 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

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Administrative TASK: Perform On-Line Risk Controls Evaluation TASK NUMBER: H303000015 INITIAL CONDITIONS:

1. The plant is at 100 percent power.

2. Channel D Work week.

3. On-line risk color is Green.

4. Stator Water Cooling System CE-FISL-3597 is reading erratically in the field.

5. 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

6. EOOS is not available.

7. The Site Risk Management Engineer (SRME) is not available.

8. All other equipment is operable.

9. 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

TQ-r\A-106-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD # I StU eval CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

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

Operator obtains the correct Operator obtains procedure WC-HC procedure. 105.

Operator determines beginning step Operator determines correct beginning of the procedure. 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 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 4.2.3.2 Review the activity against the pre defined Medium, High and Very High Operator reviews Exhibit 1 Pre-risk activities listed in Exhibit 1, Screened Work Activities for Regulatory Prescreened Work Activities. Compliance and Production Risk.

Operator recognizes:

"An activity that has been screened as a Production Risk activity by Operations". System "CE" is listed in Exhibit 5 (Production Risk)

Operator determines the Risk is High

Exhibit 5 Page 1 of 4 Production Risk Evaluation Data Description of Task: Operator obtains task description from Initial Conditions sheet.

~~~~-~ --~

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

~-~

WONo: Operator obtains WO number from Initial Conditions sheet.

Operator fills in "12345678"

-~ -~ --~

Page 5 of 15

Ttc-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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

Work activities that are entirely bounded and contained within a Work Clearance Document (WCD) boundary including Worker Blocking Tags and are not in the same or adjacent panel or near systems on the Station Production Risk System Matrix are not a production risk. This Operator determines this work is NOT means that work activities cannot within a WCD boundry.

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:

1. Is the work activity on a system that is

on the Station Production Risk System Matrix (attached) or near production sensitive equipment? Operator checks YES.

Y N 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

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

STANDARD StU 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

TQ-l"\A-106*0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD # stu evaluation) I

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

Y N

6. Does the activity involve placing of jumpers or disconnection of "daisy chains" that could cause a loss of planned generation? Operator checks NO.

Y N Could the activity cause vibration near 7.

vibration sensitive equipment that could cause a loss of planned generation? Operator checks NO.

Y N

~-- ,----~

Is a special procedure or JIT training 8.

required to mitigate the threat to generation?

Operator checks NO.

Y N Page 8 of 15

TQ~l"\A~1 06-0303 JPM: ZZ045 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation)

During the activity, could a single 9.

human error or omission cause a loss of planned generation?

Operator checks YES.

Y N I---

10. Is the activity a non-routine activity in the switchyard? Y N Operator checks NO.

If any question 2 through 10 is answered YES, then include this completed form in a sub operation in Operator determines the activity is a the work order. The activity is a production risk.

Production Risk activity.

Performed By:

Operator signs in Performed By: space.

Production Risk? Y N

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

(*Denotes a Critical Step) COMMENTS STEP

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

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

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

STOP TIME:

Page 10 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE WC-HC-105 Revision 1 Page 32 of 41 ExhibitS Page 'I or 4.

Production Risk Evaluation Data Description ofTasJt: Isolate CE-FISL-3597 WO No.: _ _ 1---,,~_ _ _ __

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 S~ Production Risk System Matrix

~ cause relay or component: acruation, .

other lhanoon~ mom alarms orposifion Production Risk Activity ~ing:

2 through 10 is answered YES, then include this oompletw form in a SI.Ib operation in lIle wmk order. The actidy is a Production Risk activity.

Periom1ed 8y: Operator Name Production Risk? Y L N _ __

Page 11 of 15

TQ-AA-106-0303 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

,---.J UNSAT QUESTION:

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

RESPONSE

RESULT: SAT UNSAT Page 12 of 15

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

1. The plant is at 100 percent power.

2. Channel D Work week.

3. On-line risk color is Green.

4. Stator Water Cooling System CE-FISL-3597 is reading erratically in the field.

5. 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

6. EOOS is not available.

7. The Site Risk Management Engineer (SRME) is not available.

8. All other equipment is operable.

9. 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 ~.. Description I Validation eqUired?

11/7/11 i

I New Admin JPM. Validation required. Validated with 2 SROs.

Validated avg time 20 minutes. ~ Y 1 214/12

Revised initiating Cue N 2 2/8/12 Revised initiating cue and actual isolation points for work being Y I performed

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 JPM NUMBER: 305H-JPM.ZZ017 REV #: 02

- - NRC ADMIN JPM SRO A2***

SAP BET: NOH05JPZZ17E ALTERNATE PATH: D APPLICABILITY:

EOD RO LJ STA D SRO [KJ DEVELOPED BY: Archie Faulkner DATE: 1/14/12 Instructor REVIEWED BY: :.c~'-(.-G~ DATE: I j tr/;2 APPROVED BY: ~jcrli DATE: I/Ir Itz Training Department

TQ-AA-106-0303 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 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EOD ROO STAD SROCK]

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

TQ-AA-106-0303 NAME:

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 CUE:

You are the Control Room Supervisor.

IMPLEMENT the Daily Surveillance Logs for today lAW HC.OP-DL.ZZ-0026 AND IDENTIFY all required Attachments for current plant conditions.

Page 3 of 12

TQ*",A-106-0303 JPM: ZZ017 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eva CUE PROVIDE the operator the initiating cue AND a paper copy of Operator repeats back initiating cue.

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

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

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 2.1.

Page 4 of 12

TQ-i"\A-106-0303 JPM: ZZ017 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

I 2.1 Shift Manager/Control Room Examiner Note: Examiner Copy I I

I Supervisor - the SM/CRS is Exhibit 1 is provided for reference.

responsible to implement, review, and ensure completion of the log including Operator determines Attachment 1 is (CRS has primary responsibility for all required due to current Operational log reviews and documentation): Condition.

2.1.1 The SM/CRS shall implement Operator checks Attachment 1 on

the log at the beginning of each day Attachment 1 Section A Log Initiation.

by completing Attachment 1 , Section A; Log Initiation, listing those Attachments that require performance Operator determined Attachment 3m is due to present conditions. Also, the required due to RCIC 1ST adding heat present Operational Condition shall to the Suppression Pool.

be listed.

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

TQ-AA-106-0303 JPM: 2Z017 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) I 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.

-- I Operator determines Attachment 3z is required for tracking purposes Operator checks Attachment 3z on Attachment 1 Section A Log Initiation.

Page 6 of 12

TQ-MA-106-0303 JPM: ZZ017 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Conduct of Operations TASK: Complete The Daily Surveillance Logs

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # I Stu STANDARD eva I 2.1 2.1.1 The SM/CRS shall implement Operator checks Attachment 5 on the log at the beginning of each Attachment 1 Section A Log Initiation.

day by completing Attachment Examiner Note: Although not 1, Section A; Log Initiation, specifically required by the current listing those Attachments that conditions, Attachment 5 is typically require performance due to used each day to track surveillance procedures and would be needed the present conditions. Also, the first time a surveillance procedure with present Operational Condition an action time is actually logged on.

shall be listed.

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

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

STOP TIME:

Page 7 of 12

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

DATE:

JPM Number: ZZ017 TASK: Complete The Daily Surveillance Logs TASK NUMBER: 4010010201 QUESTION:

RESPONSE

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

RESULT: SAT UNSAT QUESTION:

RESPONSE

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

RESULT: SAT UNSAT Page 8 of 12

TQ-AA*106-0303 JOB PERFORMANCE MEASURE ATTACHMENT 1 Page 1 of 1 Surveillance Log Date Todays Date A. LOG INITIATION 1.0perational Condition 1 2.Check (,/') Attachments to be performed 1 ,/' 3c 3g 3m,/' 3s 3w 4a 2 3d 3h,/' 3p 3t,/' 3x 4b 3e 3j 3q 3u 3y 4c B.

LOG PE:FORMAN~: ., 3r 3v 3~~~"

1. Ensure compliance with TIS by using procedurer21~~.15 TIS reference numbers and surveillance item note(s), as \'9lic~r any log item(s) requiring additional action. ~\ ) ~

2. Operators signature below in~~~riate~Ub ctio ttachment 1 and any Attachment checked ~Webeen comp Attachment 1a ~WO\\)V ~ ~Q\Vc)'\

Control RoomK$ ~~ ~ ,~J,._.L.-

Attachment 1 ~

Auxiliary Bldg _ _ _"_ _ _ _ _ _ _ _ _ _ _ _ _ __

Attachment 1c Reactor Bldg Attachment 1d Turbine Bldg MID

3. Signature below indicates review of all required attachments checked (,/') above has been completed, and approved for compliance with TIS requirements.

Day (Review Before 1300) Eve (Review Before 2100) Mid (Review Before 0500)

SM/CRS SM/CRS SM/CRS C. LOG COMPLETION 1.0perational Condition

2. Check (,/') Attachments that have been performed 1 3c 3g 3m 3s 3w 4a 2 3d 3h 3p 3t 3x 4b 3e 3j 3q 3u 3y 4c 3f 3k 3r 3v 3z 5 Page 9 of 12

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

1. The Plant is in OPCON 1 at 35% power

2. A plant startup from a forced outage is in progress lAW HC.OP-IO.ZZ-0003.

3. RCIC 1ST is in progress and being turned over.

4. River level is at 95.1 feet due to recent heavy rains.

5. River temperature is 83 degF but is NOT expected to exceed 85 degF.

6. All EDGs, SACS, and SSW pumps are operable.

7. The SPV Effluent RMS is inoperable and has been crr for repairs.

INITIATING CUE:

You are the Control Room Supervisor.

IMPLEMENT the Daily Surveillance Logs for today lAW HC.OP-DL.ZZ-0026 AND IDENTIFY all required Attachments for current plant conditions.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ017 Rev # Date Description Validation Re uired?

01 11/8/08 Converted ZZ017 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.

Removed reference to T-Factor and Attachment 3b due to deletion of T-Factor from Tech Specs. Replaced with Severe

Storm Warning and Attachment 3j.

02 1/3/12 Updated reference procedure revision numbers. Deleted Storm Y Warning and added River Level and RCIC 1ST Attachments 3k and 3m. Validated with 2 SROs on 1/3/12. Avg completion time is 7 minutes.

02 2/8/12 Editorial change for clarification - attachment 3z may be N checked - not critical I I

I

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK NUMBER: 2990060302 JPM NUMBER: 305H-JPM.zZ027 REV#: 02 SAP BET: NOH05JPZZ27E ALTERNATE PATH: D APPLICABILITY:

EOD RO STA SRO 00 DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: /<t:( -e f:t"CfZ DATE: l/rrJ2 APPROVED BY:

iJ0il<

Training Department DATE: }ller IIi

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: ZZ027 REV: 02 SYSTEM: Administrative TASK NUMBER: 2990060302 TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria ALTERNATE PATH: 0 KIA NUMBER: 2.2.12 IMPORTANCE FACTOR: 3.4 APPLICABILITY: RO SRO EoD RoD STAD SROW 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 SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Administrative TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria TASK NUMBER: 2990060302 INITIAL CONDITIONS:

1. The Plant is at 100 percent power with all equipment operable.

2. 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

TQ-AA-106*0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

I TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria EVAL COMMENTS (Required for UNSAT STANDARD # S/U evaluati CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE PROVIDE marked up copy of HC.OP IS.BC-0003 and Vibration data sheet. NIA CUE ENTER START TIME AFTER Operator repeats back the Initiating C~: I NM START TIME:

5.43 SUBMIT the procedure to the Operator commences the review.

OS/CRS for review AND completion of Attachment 1.

2.0 Operator determines correct beginning Operator determines beginning step step to be 2.0.

of the procedure.

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

STEP ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

I

EVAL COMMENTS (Required for UNSAT NO.

STANDARD # S/U evaluation 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.

CUE Make the necessary corrections N/A and continue with the review.

Operator corrects the error

Operator determines that the Delta Pressure recorded on Attachment 3, Steps 5.23.4.8 and C, for the pump is incorrect:

A math error was made. It should be 140.1 psig.

CUE Make the necessary corrections N/A and continue with the review.

Operator corrects the error.

Page 5 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM: ZZ027 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Administrative STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

I TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria EVAL COMMENTS (Required for UNSAT STANDARD # Stu Operator determines that the differential pressure is within the REQUIRED ACTION range.

CUE Make the necessary corrections N/A and continue with the review.

Operator changes the SAT to UNSAT.

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

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:

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

STANDARD S/U evaluation) 2.1.2 UNSATISFACTORY (Any test Operator completes the review.

evaluations are marked UNSAT).

TAKE action lAW Technical Specifications and GENERATE a Notification.

Operator notes that data flagged as ACCEPTANCE CRITERIA was marked UNSAT.

Operator signs in Step 2.1.2.

Operator determines B RHR Pump is

INOPERABLE for Technical Specifications.

Operator determines the most limiting

Tech Spec is 3.6.2.3 Action a.

(Suppression Pool Cooling 72 hours3 days 0.429 weeks 0.0986 months )

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 STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

I TASK: Review Operations Department Tests for Completeness and Compliance with Acceptance Criteria EVAL COMMENTS (Required for UNSAT STANDARD # S/U evaluatio Operator determines that a

NOTIFICATION must be generated.

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

CUE WHEN operator informs you the task 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 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION 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 UNSAT Page 9 of 13

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Plant is at 100 percent power with all equipment operable.

2. 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

TQ-AA-106-0303 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 AULTS HAVE 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 HISTORY JPM NUMBER: 22027 i Rev# i Description 2 11/7/11 Modified Admin JPM due to changes in reference Validation required. Validated with 2SROs on 1/3/12. Avg

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 JPM NUMBER: 30SH-J PM .ZZ003 REV #: 02 SAP BET: NOHOS..'PZZ03E ALTERNATE PATH: D APPLICABILITY:

EO D RO D STA SRO [ ] ]

DEVELOPED BY: Archie Faulkner DATE: 1/14/12 Instructor REVIEWED BY: '(I<. -e h t:.-l( DATE: 1/!8-)~

APPROVED BY: ~r~~

Training Department DATE: III! //1

TQ-AA-106-0303 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:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. 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.

5. At 0800, Purging of Primary Containment re-commenced.

6. At 1252 today Operational Condition 4 was entered.

7. 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

TQ-I"\A-106-0303 JPM: ZZ003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # I S/U STANDARD evaluati CUE PROVIDE the operator the initiating cue AND:

o Prepared OP-HC-1 03-1 05 log Operator repeats back initiating cue.

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: I N/A START TIME:

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 4.4.6.

Page 4 of 13

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

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eval 4.4.6 The SM/CRS should verify the calculations, sign in the appropriate Operator reviews Form 2.

space for verification and close out and enter the time and date.

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.

CUE IF the operator requests the NCO to make changes, THEN DIRECT the operator to make N/A any required changes.

Page 5 of 13

TQ-I"\A-106-0303 JPM: ZZ003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step)

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

STANDARD # stu evaluation 4.4.6 The SM/CRS should verify the Operator makes corrections to Form 2

calculations, sign in the appropriate Stop times and Total Hours.

space for verification and close out Examiner Note: Refer to Examiners and enter the time and date.

Copy for appropriate corrections.

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

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

STOP TIME:

Page 6 of 13

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

DATE:

JPM Number: ZZ003 TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 QUESTION:

RESPONSE

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 ---~!rrt--

Calculate Total Hours Open During Previous Year (Note 1) 452 hrs NUMBER OF HOURS

~:-~:~5_ _

_(=) 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 Time at which valvelline was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valvel1ine opened this cycle open opened (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 SM/CRS Closing permit ____f)_~ S~~. _ _ _ _~

'[)ate/7UNe 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.)

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

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. 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.

5. At 0800, Purging of Primary Containment re-commenced.

6. At 1252 today Operational Condition 4 was entered.

7. 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.

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

@[?[§~U@~ @@[?)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 6/25/11 18.5 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(

t--='------ -------- -

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.

u~o~o~ @~[Sw OP*HC*1 03*1 05 Revision 0

@[?[§~U@~ @@[?W Page 8 of 8 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING. OR PRESSURE CONTROL VALVE PERMIT J----------------~=.;:;..:,..::...;:;;..:.:;".;~-----

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 ing calculations _ _ _-'-jl_ndi-'!ry'-'<..Ci_ra_na_t_e_flt._t_ __ DatelTime ~?day/.Now 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 Description Validation:

R~quired?

01 12/6/08 Converted JPM ZZ003 to new JPM format. Since Critical JPM y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial, validation not required.

Removed references to 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 uires validation CI 02 1/14/12 Updated reference procedure revision. Changed names on Y

\ I Attachments. Corrected typo on Initiating Conditions Cue Sheet.

I Updated dates to be relevant to current year. Validated with 2 I , SROs on 1/3112. Average completion time was 9 minutes.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative DutieslReporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition TASK NUMBER: 2000500302/2000020505 JPM NUMBER: 305H-JPM.ECG003 REV#: 05 SAP BET: NOH05JPCL03E ALTERNATE PATH: D APPLICABILITY:

EO RO D STA [ ] ] SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: ~-e~( DATE: 1;/~2 APPROVED BY: <1r~l

... ~

Training Department DATE: }/Jg' /11

~ i

TQ*AA*106*0303 STATION: Hope Creek JPM NUMBER: ECG003 SYSTEM: Administrative Duties/Reporting Requirements TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event And/Or Plant Condition ALTERNATE PATH: D KIA NUMBER:

2.4.38 IMPORTANCE FACTOR: 2.2 4.0 APPLICABILITY: RO SRO EoD RoD STAW SROW EVALUATION SETTING/METHOD: SimulatorlPerform or In Plant/Simulate

REFERENCES:

Hope Creek Event Classification Guide, TOC Rev 98 TOOLS, EQUIPMENT AND PROCEDURES:

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

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 19

NAME:

DATE:

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

1. With the plant operating at 100% power, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1 g.

2. Control Room Annunciator C6-C4 is in.

3. 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.

4. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer.

5. 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.

6. Drywell Pressure peaked at 44 psig, then dropped to < 2 psig over the next 90 seconds, and continues to slowly drop.

7. The current 33 ft. elevation wind direction is from 224 0 at 21 mph.

8. 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:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD II Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event AndlOr Plant Condition EVAL S/U 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 INITIATING CUE: N/A START TIME:

Operator obtains the correct Operator obtains Hope Creek Event procedure. Classification Guide.

ECG Classification: To use this ECG Section volume, follow this sequence: Operator assesses the initial conditions, and determines that Table 3, Fission LlV.C 1. ASSESS the event and/or plant Product Barriers, 6.1 Radiological conditions and DETERMINE Releases/Occurances, and 9.0, which ECG section(s) is most Hazards-lnternaI/External, are the appropriate. appropriate ECG sections.

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

Page 4 of 19

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

JOB PERFORMANCE MEASURE DATE: _________________

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

ECG 3. REVIEW the associated EALs as Section compared to the event and LIV.C SELECT the highest appropriate emergency or reportable action level. If identification of an EAL is questionable, refer to paragraph IV.A above. Operator reviews the EALs in section If there is any doubt with regard to 6.1 and 9.5, and determines that EAL #

assessment of a particular EAL, 6.1.2.d and 9.5.2 is the highest the ECG Technical Basis emergency action level met or Document should be reviewed. exceeded (ALERT).

Words contained in an EAL that are bold face are either threshold values associated with that action level or are words that are defined in the basis for that specific EAL.

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

communicated to the NRC using Attachment 5, NRC Data Sheet.

Page 5 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 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 and classify as if the threshold is exceeded.

I r---~

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. columns need further review.

identify which need further review.

Table For each of the three barriers, Operator determines that the following 3.0 determine the EAL with the highest EALs have been exceeded and I 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 column:

3.1.1.a; 3.2.2.b or 3.2.1.b; and 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. I 3.

Examiners Note: Determining this I

value for future use is critical; marking it on Table 3.0 is not. I

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

I Page 6 of 19

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

DATE: _________________

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

(*Denotes a Critical Step)

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

STANDARD S/U evaluation)

Table Classify based on the point value sum Operator determines that this 3.0 as follows: classification is higher than the 4.

Ifllle classification on EALs 6.1.2.d or 9.5.2 Oassifyas: Refrto: 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 SITEAREA ATI.3 9,10 GENERAL ATIA Page 7 of 19

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

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

I Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition EVAL COMMENTS (Required for UNSAT STANDARD # SIU evaluati ECG 5. The STA is responsible to Section perform an independent LlV.C verification of the EAL IF time permits, classification. The STA THEN Operator requests STAIIA verification does not alleviate the verification of classification.

requirement of the SM to make a timely classification. Should the Examiner Note: Due to time spent SM fill the STA role, independent assessing and/or nature of JPM verification of the EAL administration, Operator may not classification will be delegated to request a verification.

another on-shift SRO.

CUE IF the Operator requests the STAIIA to independently verify the EAL Classification, THEN INFORM the Operator the N/A STAliA is not available.

Page 8 of 19

TQ-~A-1 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 STEP

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

STANDARD StU evaluation) I ECG 6. IDENTIFY and IMPLEMENT the Section referenced Attachment under i.IV.C Action Required. Refer to Section iv, HC Emergency Classification Description Table, which is a Operator identifies and implements guide for correct description ECG Attachment 4.

wording for entry on the ICMF for all EALs.

ECG I. EMERGENCY COORDINATOR Atl. 4 {Ee} LOG SHEET A. If a security event is in progress, THEN, IMPLEMENT Operator determines this step is not the prompt actions of NC.EP applicable.

EP.ZZ-0102, EC Response, Attachment 10, prior to classification.

Page 9 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 Step) COMMENTS STEP

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

STANDARD S/U evaluation) I ECG B. DECLARE A GENERAL Operator declares a General Att. 4

EMERGENCY AT HOPE Emergency, places the EAL # s 3.1.1.a; CREEK and 3.2.1.b or 3.2.2.b; and 3.3.2.b or EAL #(s) , , 3.3.2.d, time and date in the appropriate spots in attachment 4, and DECLARED AT hrs on initials the step as the EC.

time date 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

~**ECG C. NOTIFICATIONS Operator calls the communicator using Att. 4 the plant page.

1. CALL the communicators to the Control Room CUE After 2 minutes, report as the N/A communicators and give your name as CM1 and CM2.

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 Step)

COMMENTS STEP 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 Use titled: "Emergency Callout Emergency Callout Activation.

Activation" (EP96-003) Examiner Note: ENSURE the operator is using the Simulator Training Activation instructions.

Caution Operator reads CAUTION.

A Protective Action Recommendation (PAR) SHALL be made on the Initial Contact Message Form (ICMF).

c--

ECG 3. MAKE A PAR as follows: Operator Refers to APPENDIX 1,

Att. 4 determines that a GE Based 9 Points

a. REFER to Predetermined PAR Flowchart on Pg. 3 and PAR is appropriate DETERMINE the appropriate [EVACUATE ALL SECTORS 0-5 PAR. MILES].

b. lE a Radiologically Based PAR is IMMEDIATELY Examiner Note:

available, THEN COMPARE 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

TQ-",A-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: _________________

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

(*Denotes a Critical Step)

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

STANDARD S/U evaluation)

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

ECG 4. COMPLETE the INITIAL Operator Completes the ICMF.

Att.4 CONTACT MESSAGE FORM Examiners Note: See the attached (ICMF) (last page of this ICMF for an example of what the form attachment). should look like when filled out properly.

Note that the exact words do not have to be in the "DESCRIPTION OF EVENT", but the description must convey the sense of the Initiating Condition for EALs 3.1.1.a; and 3.2.1.b or 3.2.2.b; and 3.3.2.b or 3.3.2.d. The operator may place the Examiner's name as the Communicator or tell the Examiner to place his/her name as the Communicator.

5. IF time allows, OSTAIN an accuracy peer check of the Operator requests a Peer Check of the completed ICMF. completed ICMF.

Page 12 of 19

Ttc-rlA-106-0303 ECG003 OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

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

(*Denotes a Critical Step)

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

STANDARD # StU evaluatio CUE IF the Operator requests a Peer Check, THEN INFORM the Operator a Peer Check has been performed as N/A requested.

6. PROVIDE the ICMF to the

Primary Communicator (CM1) Operator provides the ICMF to CM1 and DIRECT the Communicator and directs implementation of Att.6.

to implement ECG Attachment 6.

CUE LOG the time the ICMF is provided to CM1.

Examiners Note: The difference LOG TIME: _ _ _ __ between the "DECLARED AT" TIME Role-playas CM1 and repeat back and this LOG TIME is the second the direction as given. critical time (13 min.)

Page 13 of 19

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

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD II Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition EVAL S/U COMMENTS (Required for UNSAT ECG 7. DIRECT the Secondary Operator directs CM2 to implement Att.

Att.4 Communicator (CM2) to a for a GENERAL EMERGENCY.

implement ECG Attachment 8 for a GENERAL EMERGENCY.

CUE ROLE-PLAYas CM2 and REPEAT BACK the direction as given. 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.

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 14 of 19

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

---~.

DATE:

JPM Number: ECG003 TASK: Utilize The ECG To Determine The Emergency Classification AndlOr Reportability Of An Event AndlOr Plant Condition TASK NUMBER: 2000500302/2000020505 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 15 of 19

TQ-AA-106-0303 JOB PERFORMANCE MEASURE ECG ATT4 Pg. 50f5 INITIAL CONTACT :MESSAGE FORt"!

L THIS IS (Not Required) , COtvfivfUNICATOR IN THE .iJ CONTROL ROOM (NMffi) DTSC DEOF AT THE HOPE CREEK l\iLJCLEAR GENERATING STATION.

TIa. rI THIS IS NOTIFICATION OF A GENERAL EI\>1ERGENCY \\lHICH WAS DECLARED AT Todays Time ON ~_TQ~ays 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. 0 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-,--_

'--vU'IJUt'-~ iSPDS) (DEGREES) (MPH)

v. Sectors Dist. - Miles rl WE RECOMlvIEr..'D EVAClTATION AS FOLLOWS A" 0-5 o \VE RECO~'1MEr..'D 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

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

1. With the plant operating at 100% power, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1 g.

2. Control Room Annunciator C6-C4 is in.

3. 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.

4. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer.

5. 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.

6. Drywell Pressure peaked at 44 psig, then dropped to < 2 psig over the next 90 seconds, and continues to slowly drop.

0

7. The current 33 ft. elevation wind direction is from 224 at 21 mph.

8. 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.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Feedwater TASK: Respond To Rising Orywell Pressure TASK NUMBER: 4000510401 JPM NUMBER: 305H-JPM.AE004 REV #: 06 SAP BET: NOH05JPAE04E ALTERNATE PATH: []J APPLICABILITY:

EO RO [ ] ] STA SRO I X I DEVELOPED BY: Steve Dennis DATE: 2/15/12 Instructor REVIEWED BY: j'<C /<- ct-ztr/rc DATE: ~;;~j;:z 0 rations Representative APPROVED BY: on!~

Training Department DATE: ?!22//z

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: AE004 REV: 06 SYSTEM: Feedwater TASK NUMBER: 4000510401 TASK: Respond To Rising Drywell Pressure ALTERNATE PATH: W KIA NUMBER: 223001 A2.01 IMPORTANCE FACTOR: 4.3 4.4 APPLICABILITY: RO SRO EO 0 RO [KJ STA 0 SRO [KJ 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:

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 Operator.

Place a water seal on both the 'A' AND 'B' feedwater headers lAW HC.OP-SO.AE-0001.

Page 3 of 18

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

DATE: __________________

Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step)

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

STANDARD # I S/U evaluat CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

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

Operator obtains procedure Operator obtains the correct HC.OP-SO.AE-0001.

procedure.

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

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

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.18.1.

Page 4 of 18

TU-r'\A-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD # I S/U evalu NOTE The HPCI AND the RCIC Jockey Pump Loops are used to maintain a water seal in the Feedwater lines N/A between the inboard AND outboard containment isolation valves following a LOCA.

5.18.1 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.1 are satisfied. have been satisfied.

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

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

5.18.2 ENSURE the following valves are closed:

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

Page 5 of 18

TCt~nA~1 06-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step)

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

STANDARD # I S/U eval Operator presses the HV8278 CLOSE

Y N Flagging 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.

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

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

Page 6 of 18

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

Rev: 06 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD # I S/U eval Operator determines step 5.18.3 of Operator continues to complete step the procedure is now applicable. 5.18.2.

BD-HV-F013, RCIC PUMP DSCH Operator observes the F013 CLSD light TOFW illuminated and the OPEN light extinguished.

HV-F032A, FW INLET CHK VL V Operator observes the FW INLET CHK VLV HVF032A OPEN light is illuminated and the CLOSE light is extinguished.

Operator presses the HVF032A CLOSE

Y N Flagging pushbutton.

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

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

Page 7 of 18

TQ-nA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

{*Denotes a Critical Step} COMMENTS STEP

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

STANDARD S/U Operator presses the HVF032B CLOSE

Y N Flagging pushbutton.

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

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

IF AP228, HPCI JOCKEY PUMP will 5.18.3 be used to seal the B Feedwater Line, OR BP228, RCIC JOCKEY PUMP will Based on current conditions, Operator be used to seal the A Feedwater Line, determines that this step now applies.

THEN PERFORM the following:

Page 8 of 18

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

Rev: 06 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step)

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

STANDARD S/U evaluation) 5.18.3. Operator inserts key and places the

PLACE the keylock switch for HV-Keylock switch for the HV-4144, FW A. 4144, FW LINE CROSS-TIE ISLN CROSS TIE LINE ISLN, in the ON #

VLV, in the ON position to arm the position control switch. Examiner Note: OHA 83-D2 FEEDWATER LINE FILL ALT MODE will alarm.

5.18.3. OPEN HV-4144, FW LINE CROSS Operator observes the HV-4144, FW LINE CROSS-TIE ISL VLV CLOSE light 8 TIE ISL VLV.

is illuminated and OPEN light is extinguished.

OperatOi presses the FW CROSS TIE

Y N Flagging LINE ISLN HV-4144 OPEN pushbutton.

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

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

Page 9 of 18

TQ-AA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evalualio IF AP228, HPCI JOCKEY PUMP is to 5.18.4.

be used to seal one or both Based on current conditions, Operator Feedwater lines, determines that this step does not apply

\ and continues at step 5.18.5.

THEN PERFORM the following:

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. PLACE the NORM/BYPASS Keylock Operator inserts key and places the Y N Flagging A Switch for BO-HV-F013, RCIC PUMP Keylock switch for the RCIC HVF013 in the BYPASS position. #

DSCH TO FW, in the BYPASS position to arm the Control Switch. Examiner Note: OHA B3-D2 FEEDWATER LINE FILL ALT MODE will alarm.

Page 10 of 18

Tte-nA-106-0303 JPM: AE004 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 06 JOB PERFORMANCE MEASURE SYSTEM: Feedwater TASK: Respond To Rising Drywell Pressure

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.18.5. OPEN BD-HV-F013, RCIC PUMP Operator observes the RCIC PUMP B DSCH TO FW. DSCH TO FW HVF013 CLSD light is illuminated and OPEN light is extinguished.

Operator presses the HVF013 OPEN

Y N Flagging 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

C DSCH VLV. light is illuminated and CLSD light is extinguished.

5.18.5. WHEN required, THEN START Operator observes the RCIC JOCKEY

D BP228, RCIC JOCKEY PUMP. PUMP red RUNNING light is illuminated and green STOPPED light is extinguished.

Page 11 of 18

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluatior

~&~~----------------~

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

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

STOP TIME:

Page 12 of 18

TQ-AA-106-0303 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

TQ-AA-106-0303 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 Operator.

Place a water seal on both the 'A' AND 'B' feedwater headers lAW HC.OP-SO.AE-0001.

Page 14 of 18

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

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".

Initial ET #

Event code: ZDHP278C >=1.0 /I HPCI 8278 CLOSE pb pressed.

4

Description:

Trips HPCI Jockey Pump Event code:

Description:

Event code:

Description:

Page 15 of 18

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Insert malfunction CR01 to 100.00000 None None Fuel cladding leak on event 1 Insert malfunction MS01 to 100.00000 None None Steam line break in drywell on event 2 Insert malfunction RM9635 to 9RX635, DAPA 'A' - Drywell Atmos Post-None None 5211.00000 on event 3 Accident Chan 'A' Insert malfunction RM9636 to 9RX636, DAPA 'B' - Drywell Atmps Post-None None 5185.00000 on event 3 Accident Chan 'B' Insert malfunction AN-B1 E4 after 30 CRYWOLF ANN B1 E4 HPCI JOCKEY None None on event 4 PUMP 1AP228 TROUBLE Insert malfunction AN-B1 F3 after 30 CRYWOLF ANN B1 F3 HPCI None None on event 4 COMPONENT O/PF None None Insert remote IA 10 to RUN IAi0 Temporary station air compressor Insert remote ET066 to FAIL_OPEN None None ET066 HV-8278 HPCI to FW on event 2 Remove remote ET066 to FAIL_OPEN None None ET066 HV-8278 HPCI to FW on event 4 None Insert override 9S139_A_DI after 30 to HPCI JOCKEY START/STOP (DI)

Off on event 4 Insert override 9S138_A_LO after 30 None None AP228 OVLD/PWR FAIL (LO) to On on event 4 i

None None Insert override 9DS111_B_LO after 30 AP228 STOPPED to Off on event 4 Insert override 9M6_R_AO after (AO) from 95.00000 to 0 in 5 on event 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.

This change is editorial, validation not require(j.

02 9/29/09 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

~i _ _ ~ _____ ~._w_it_h_1_R_O_a_n_d_1~S_R_O__._ _ _ _ _ _ _ _ _ _ _ _ _ _ _~ _ _ _ _ _~

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUM BER: 2050120101 JPM NUMBER: 305H-JPM.BC015 REV#: 04 SAP BET: NOH05JPBC15E ALTERNATE PATH: 0]

APPLICABILITY:

EOD RO STA D SRO DEVELOPED BY: Steve Dennis DATE: 2/16/12 Instructor d~fr:2 REVIEWED BY: j-(fL ......t VIL DATE:

perations Representative APPROVED BY:

oumk Training Department DATE: I) ;

a'2 I!L

TQ-AA-106-0303 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: RO SRO EO D RO [ ] ] STA D 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:

I Page 2 of 22

TQ-AA-106-0303 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-F007A and SC-HV-F027A have been tagged closed to support the evolution.

7. Flush of A RHR Loop is not required.

8. Field operators have been briefed and are standing by on location.

INITIATING CUE:

You are an extra NCO.

Transfer RHR Shutdown Cooling to the A RHR loop.

The required shutdown cooling flow for the 'A' RHR pump is between 9500 -10,000 gpm.

Page 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD Stu eval CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains procedure HC.OP-SO.BC-0002 Operator obtains the correct procedure.

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

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

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

Page 40f22

T<:.t-~A-1 06-0303 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

(*Denotes a Critical Step)

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

STANDARD Stu evaluation) 5.3.1 ENSURE all Prerequisites have been Operator reviews prerequisites.

satisfied lAW Section 2.3.

NOTE Operator reads NOTE.

BC-HV-F027A(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.

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

(*Denotes a Critical Step)

COMMENTS STEP EVAL (Required for UNSAT ELEMENT (#Denotes a Sequential Step)

NO. STANDARD # evaluation)

S/U I CAUTION Operator reads CAUTION.

While in shutdown cooling, the following valves shall be closed to prevent uncontrolled drainage from the Reactor Vessel: [CO-389B, CO 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*F007A(B) RHR PMP A(B)

MIN FLOW MOV

BC-HV-F027A(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 Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation 5.3.2 I PERFORM the following to prepare loop to be placed in Shutdown Cooling:

5.3.2. IF a flush on the loop to be placed in Operator determines step 5.3.2.A. does A Shutdown Cooling is required, THEN not apply.

REFER TO Steps 5.2.5 through 5.2.14.

5.3.2. ENSURE the following Valves are B CLOSED:

BC-HV-F003A(B) RHR HX A(B) Operator observes the BC-HV-F003A OUTLETVLV RHR HX A OUTLET VL V CLSD light illuminated and OPEN is extinguished.

BC-HV-F004A(8) A(B) RHR PMP Operator observes the BC-HV-F004A A SUPP POOL SUCT MOV RHRPMPSUPPPOOLSUCTMOV CLSD light illuminated and OPEN is extinguished.

Page 7 of 22

TQ-AA-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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

BC-HV-F007A(S) RHR PUMP A(B) Operator observes the BC-HV-F007 A is MIN FLOW MOV TAGGED CLOSED and breaker 52 212041 OPEN AND INITIAL Attachment 1 .

BC-HV-F024A(B) RHR LOOP A(S) Operator observes the BC-HV-F024A TEST RET MOV RHR LOOP A TEST RET MOV CLSD light illuminated and OPEN is extinguished.

BC-HV-F027A(B) RHR LOOP A(B) Operator observes the BC-HV-F027A is SUPP POOL SPRAY HDR ISLN MOV TAGGED CLOSED and breaker 52 212081 OPEN AND INITIAL Attachment 1.

NOTE Operator reads NOTE.

This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

~--- ---

Page 8 of 22

TQ*AA*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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.3.2. VERIFY BC-HV-F007A(B) is Operator observes the BC-HV-F007A is C CLOSED THEN TAG breaker 52- TAGGED CLOSED and breaker 52 212041(52-222041) OPEN AND 212041 OPEN AND INITIAL INITIAL Attachment 1. Attachment 1.

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

NOTE Operator reads NOTE.

1-BC-V315 (V314) SUP POOL SPRY HDR MAN ISLN VL V may be tagged CLOSED instead of tagging the associated breaker for the BC-HV F027A(B) (if required to support outage activities), although BC-HV F027A(B) must still be closed.

This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

5.3.2. VERIFY BC-HV-F027A(B) is Operator observes the BC-HV-F027A is D CLOSED AND TAG breaker 52- TAGGED CLOSED and breaker 52 212083 (52-222083) OPEN AND 212081 OPEN AND INITIAL INITIAL Attachment 1. Attachment 1 .

Page 9 of 22

TQ-AA-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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.3.3. 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 OPEN RHR Loop to be placed in SID pb.

Cooling.

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 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 Step) COMMENTS STEP

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

STANDARD S/U 5.3.4. IF prewarming of the Loop of RHR to Operator determines step 5.3.4 does be placed in SID Cooling is required not apply.

THEN, PERFORM Steps 5.2.26 OR 5.2.27 of this procedure to equalize temperatures; OTHERWISE PROCEED.

5.3.5. I SECURE the inservice Shutdown Cooling Loop as follows:

5.3.5. ENSURE 1-BC-V262 (1-BC-V212), Operator contacts Equipment Operator A ECCS Jockey Pmp D(C) DISCH to and directs opening 1-BC-V262.

RHR Loop B(A) is LOCKED OPEN (local), AND INITIAL Attachment 1.

The valve is in the position CUE requested.

NOTE Operator reads NOTE.

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

Page 11 of 22

TQ-/"\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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.3.5. CLOSE 8C-HV-F0158(A) RHR LOOP Operator presses and holds the 8C

8 8(A) RET TO RECIRC AND INITIAL HV-F0158 RHR LOOP 8 RET TO Attachment 1 . RECIRC CLSD pb.

I 5.3.5. WHEN 8C-HV-F0158(A) RHR LOOP Operator observes the 8C-HV-F0158 C 8(A) RET TO RECIRC is fully closed, RHR LOOP 8 RET TO RECIRC CLSD THEN, IMMEDIATELY STOP light illuminated and OPEN is B(A)P202 RHR PUMP. extinguished.

Operator presses BP202 RHR PUMP

STOP pb.

~.

Page 12 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) 5.3.5. CLOSE BC-HV-F006B(A) RHR PMP Operator presses the BC-HV-F006B

0 RHR PMP B(A) SUCT FROM RECIRC B(A) SUCT FROM RECIRC AND CLSD pb.

INITIAL Attachment 1.

Operator observes the BC-HV-F006B RHR PMP B(A) SUCT FROM RECIRC CLSD light illuminated and OPEN is extinguished.

5.3.6. ENSURE SACS is in service to the Operator observes the HV-2512A RHR Heat Exchanger for the RHR OPEN light illuminated and CLSD light loop to be placed in service lAW extinguished.

HC.OP-SO.EG-0001 (Q).

~~~~~~~

Operator observes RHR A HX SACS Flow approximately 9000 gpm.

Page 13 of 22

TQ-AA-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

(*Denotes a Critical Step)

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

STANDARD S/U evaluation)

CAUTION Operator reads CAUTION.

Manual OR automatic opening of 8C-HV-F007A(8) RHR PMP A(B)

MIN FLOW MOV will drain Reactor Vessel to Suppression Pool.

If BC-HV-FO 15 A(BA RHR LOOP A(BA RET TO RECIRC does NOT oTlen immediatel'l. to establish flowl then the RHR flumfl should be secured.

8C-HV-F027A(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

TQ-AA-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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) 5.3.7. START RHR PUMP A(B)P202 AND Operator presses the AP202 START

IMMEDIATELY THROTTLE OPEN pb.

BC-HV-F015A(8) RHR LOOP A(8)

RET TO RECIRC LOOP UNTIL FI R603A(B) OR FR-R60BA(B) - CRIDS A3137(A3139), LOOP A(B) FLOW indicates:::: 3000 gpm.

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:

Rev: 04 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation Examiner Note: F015A will fail Operator observes the FI-R603A OR closed and not establish flow. FR-R60BA - CRIDS A3137, LOOP A Operator must secure the pump lAW FLOW indicates 0 gpm.

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.

Operator determines CAUTION applies.

Operator presses AP202 STOP pb.

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 16 of 22

TQ-AA-106-0303 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

TQ-AA-106-0303 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 NCO.

Transfer RHR Shutdown Cooling to the A RHR loop.

The required shutdown cooling flow for the 'A' RHR pump is between 9500 -10,000 gpm.

Page 18 of 22

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

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 open.

ENSURE associated Schedule File is loaded.

OPEN BC-HV-F007A breaker using ET-1.

OPEN BC-HV-F027A breaker using ET-2.

PLACE red bezel covers on the BC-HV-F007B AND the BC-HV-F027B.

PLACE red bezel covers on the BC-HV-F007A AND the BC-HV-F027A.

Page 19 of 22

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

RH30 HV-F007B RHR Pump A Min Flow None None Insert remote RH30B to TAGGED Valve ET006 GROUP 3B HV-F027B RHR None None Insert remote ET006 to RACK_CLOSE Supp. Pool Spray Insert remote RH30A to TAGGED on RH30 HV-F007A RHR Pump A Min Flow None None event 1 Valve Insert remote ET005 to RACK_CLOSE ET005 GROUP 3B HV-F027A RHR None None on event 2 Supp. Pool Spray RH29 GROUP 3E HV-F015A RHR SOC None None Insert remote RH29A to FAIL_CLOSE Return Isol BC-HV-F015 B increase PB none none depressed Causes event 4 to insert zxxxxx.x Inserts XXXX after 120 seconds on none none Trips "A" RHR pump event 4 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 [KJ STA SRO ~

DEVELOPED BY: Steve Dennis DATE: 2/16/12 Instructor REVIEWED BY: DATE: .2~,JIL APPROVED BY: °ntCJ1L--

Training Department DATE: ;J/J)~2

TQ-AA-106-0303 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: RO SRO EO D RO [K] STA D SRO [K]

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:

1. The plant is operating at 100% power.

2. Main Condenser vacuum is degrading due to fluctuations in 3rd Stage SJAE flow.

3. Troubleshooting has determined that PIC-1964B, AIR EJECTOR B EXH PRESS, has an electronics problem and failure of the valve is imminent.

4. HC.OP-AB.BOP-0006, Main Condenser Vacuum, is being implemented.

5. Radwaste Operator has been notified.

6. Offgas is in service.

INITIATING CUE:

Place SJAE A in service on Main Steam accordance with HC.OP-AB.ZZ-0001.

Page 3 of 18

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

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # eval**...,j.:~~\

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

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

Operator obtains procedure Operator obtains the correct procedure. HC.OP-AB.ZZ-0001 Attachment 11.

Operator determines beginning step of Operator determines correct beginning step the procedure. to be 1.0.

1.0 OPEN HV-1957A Operator presses the HV-1957A OPEN

Y N Flagging pushbutton.

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

Page 4 of 18

TQ-J-\A-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 2.0 Operator presses the HV-1955A OPEN

Y N Flagging OPEN HV-1955A. pushbutton.

r-~ ~---~ ~-~

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

~-~

3.0 OPEN HV-2016A (HV-2020A if the Y N Flagging SJAE's are being supplied by Aux. Stm)

THEN OBSERVE 145-150 psig (with #

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

2022A.

- ~~

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

Tc.t-AA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) 4.0 Operator presses the PIC-1964A AUTO

Y N Flagging ENSURE PIC-1964A is in AUTO at 11 pushbutton.

psig. #

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

Operator presses the PIC-1964A

Y N Flagging UP/DOWN Arrows as necessary to place the setpoint indicator on 11 psig.

5.0 Operator presses the HV-1959A OPEN

Y N Flagging OPEN HV-1959A. pushbutton.

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

6.0 Operator presses the HV-1956A OPEN

Y N Flagging OPEN HV-1956A. pushbutton.

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

_L Page 6 of 18

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

Rev: 02 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) r-----..

7.0 OBSERVE the following 3rd stage indications:

Operator observes the FR-2021A SJAE 3 rd I II FR-2021 A increasing stage flow increasing.

r*_*

rd Operator observes the PIC-1954A SJAE 3 PI-1954A lowering. stage pressure lowering.

8.0 Operator presses the HV-1963A OPEN

Y N Flagging OPEN HV-1963A. pushbutton.

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

i*

9.0 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.

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

lowering.

~. -- --

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

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

Page 7 of 18

TQ-I-\A-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 J08 PERFORMANCE MEASURE DATE: _________________

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 11.0 Operator presses the HV-1967A OPEN

YN Flagging OPEN HV-1967A. pushbutton.

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

12.0 Operator presses the HV-1968 A 1, A2, A3,

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

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

13.0 Operator observes all "A "SJAE valves VERIFY valve operated in Steps 1.0 thru open.

12.0 have successfully repositioned.

14.0 Operator presses the HV-1968 81,82,83,

Y N Flagging CLOSE HV-1968 81,82,83. 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:

Rev: 02 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eval 15.0 MONITOR PIC-1964A for the following indications:

Operator observes the PIC-1964A SJAE 3rd stage outlet pressure at approximately 11 SJAE 3rd stage outlet < 11 psig.

psig.

Operator observes the Gaseous Radwaste Gaseous Radwaste Flow < 75 scfm Flow <75 scfm.

(1900 #/hr).

CUE Examiner Note: Operator should check CRIDS points A3431 or A9343 for indication of Offgas Treatment Flow.

IF asked as Radwaste Operator, for Operator may request Radwaste to Offgas Flow, THEN REPORT that provide flow indication from 1HAFI Offgas flow is approximately 35 scfm. 5665. It will take a few minutes for flow to lower to < 75 scfm.

16.0 Five minutes AFTER closing HV-1968 B1, B2, B3, CLOSE the following valves:

CUE "Five minutes have elapsed."

Page 9 of 18

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

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

Operator presses the HV-1967B CLOSE Y N Flagging

HV-1967B pushbutton.

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

Operator presses the HV-1963B CLOSE Y N Flagging

HV-1963B pushbutton.

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

r-- -----~~

Operator presses the HV-1962B CLOSE Y N Flagging

HV-1962B pushbutton.

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

c--------

Operator presses the HV-1955B CLOSE Y N Flagging

HV-1955B pushbutton.

Page 10 of 18

TQ-rlA-106-0303 JPM: CG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) I Operator observes the HV-1955B CLOSE light illuminates and the OPEN light extinguishes.

Operator presses the HV-1956B CLOSE Y N Flagging

HV-1956B pushbutton.

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

Operator presses the HV-1957B CLOSE YN Flagging

HV-1957B pushbutton.

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

Operator presses the HV-1959B CLOSE Y N Flagging

HV-1959B pushbutton.

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 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Condenser Air Removal TASK: Respond To A Main Condenser Low Vacuum

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eval Operator presses the HV-2016B CLOSE Y N Flagging

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

Aux Steam)

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.

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

STOP TIME:

Page 12 of 18

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

DATE:

JPM Number: CG003 TASK: Respond To A Main Condenser Low Vacuum TASK NUMBER: 4000580401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 13 of 18

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

1. The plant is operating at 100% power.

2. Main Condenser vacuum is degrading due to fluctuations in 3rd Stage SJAE flow.

3. Troubleshooting has determined that PIC-1964B, AIR EJECTOR B EXH PRESS, has an electronics problem and failure of the valve is imminent.

4. HC.OP-AB.BOP-0006, Main Condenser Vacuum, is being implemented.

5. Radwaste Operator has been notified.

6. 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

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

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 alarm.

IMPLEMENT AB.BOP-0005. Markup procedure to step B.1 ENSURE a copy of HC.OP-AB.BOP-0005 is available.

ENSURE a copy of HC.OP-AB.zZ-0001 Attachment 11 is available.

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

Event code: ZLMC1968(1) >=1.0 & MONVAR(31) <=5.8 2

Description:

Removes malfunction MC01 when SJAE swap complete.

Event code:

Description:

Event code:

Descri ption:

Page 15 of 18

TQ-AA-106-0303 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

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: CG003 Rev# ! Date Description Validation Required?

01 1/3/12 Converted JPM CG003 to new JPM format. Since Critical JPM y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial Validation is required to establish completion times. Validated with 2 ROs on 1/3/12. Avg completion time was 13 minutes.

i 02 2/16/12

Step 14.0 revised to a critical step. Revalidated by an RO and Y

.SRO I

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501

..IPM NUMBER: 305H-JPM.GS005 REV#: 04 SAP BET: NOH05JPGS05E ALTERNATE PATH: 00 APPLICABILITY:

EOD RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 1/14/12 Instructor REVIEWED BY: 1<t2-cef-z.-vtc DATE: Ikdlt~

APPROVED BY: CWCflL Training Department DATE: }//r)/l I

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: GS005 REV: 04 SYSTEM: Containment Atmosphere Control TASK NUMBER: 2000950501 TASK: 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 SIGNATURE: DATE:

Page 2 of 21

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 INITIAL CONDITIONS:

1. The 'B' RHR pump suction was isolated due to a leak.

2. The Plant experienced a large break LOCA.

3. HC.OP-EO.ZZ-0102, Primary Containment Control has been implemented.

4. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising.

5. Suppression Pool Level indicates approximately 83 inches.

6. The Emergency Instrument Air Compressor has been restored lAW HC.OP-EO.ZZ-0319.

7. The Control Room Emergency Filtration System is operating in the Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001 (Q).

8. FRVS is in operation in accordance with HC.OP-SO.GU-0001(Q).

9. 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 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

(*Denotes a Critical Step) I

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

STANDARD # StU 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 Operator obtains the correct procedure.

HC.OP-EO.ZZ-0318.

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

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

Operator determines beginning step Operator determines correct beginning of the procedure 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

(*Denotes a Critical Step) I

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

STANDARD # S/U evaluation) 5.1.1 VENT the containment via the Hard Operator reviews Prerequisites and Torus Vent as follows: ensures Prerequisites complete.

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

performed.

CUE Acknowledge the communication to the EDO.

5.1.1 C. In the Lower Relay Room, Elev Operator directs the field operator to

102'atpanel1YF404(see install fuse F22 at panel 1YF404.

Attachment 2), INSTALL F22 (6 #

amp fuse).

Page 5 of 21

TQ-I"\A-106-0303 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation)

~l'.!li~l, t\ ~;~;,: :1 CUE WHEN directed to install 1YF404 lit~*i*'*h' fuse F22, THEN TRIGGER ET-3 AND REPORT the fuse is installed.

~

5.1.1 D. DEPRESS ISLN OVRD and Operator depresses the ISLN OVRD ---*

OPEN GS-HV-4964 SUPP pushbutton for the HV-4964.

CHMBR TO CPCS DMP. #

I Operator observes the amber OVER RIDDEN indicator illuminates.

I Operator depresses the HV4964 OPEN

PB.

I Operator observes the red OPEN indicator illuminates and the green CLSD indicator extinguishes.

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

Page 6 of21

TQ-MA-106-0303 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.1.1 F. When HV-4964 SUPP CHMBR TO Operator observes that the HV4964 CPCS DMP is full open, then OPEN indicator is illuminated.

OPEN GS-HV-11541 TORUS Operator observes that the HV4964 VENT ISOLATION VALVE.

CLSD indicator is extinguished.

Operator rotates HV11541 keylock

switch to the OPEN position.

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

Operator informs CRS.

"'!:,"'I!:\il~

CUE Repeat back report from Operator Examiner Note: Based on the Initial .';':;

It\1!~{: .

and direct Operator to continue to Conditions, the Reactor Building is NOT implement the procedure until a accessible. Manually opening the ;>..

vent path is established. HV-11541 is not an option. ilillill"

, . .111 Ii! 111:

1 Page 7 of 21

TQ-AA-106-0303 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) 5.1.1 G. When drywell pressure can be Operator determines drywell pressure maintained below 60 psig, then is not being maintained below 60 psig, CLOSE GS-HV-11541 TORUS continues on in the procedure.

VENT ISOLATION VALVE.

---- i 5.1.1 H. REPEAT steps 5.1.1.E thru Operator determines repeating these 5.1.1.G as necessary to reduce steps will not establish a vent path.

and maintain drywell pressure below 65 psig.

-- I 5.1.1 I. If actions taken to reduce Operator determined actions taken thus containment pressure have been far have not been successful, continues unsuccessful, then continue in this in the procedure.

procedure.

I 5.1.2 VENT the containment via the Operator determines this path is not Suppression Chamber supply and available since it requires access to the ILRT piping as follows: Reactor Building and the reactor Building is not accessible.

'-------- I Page 8 of 21

TQ-AA-106-0303 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

(*Denotes a Critical Step) I

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

CUE IF the Operator requests the status of the "angled piping downstream of 1-GS-V058",

THEN INFORM the Operator the piping has NOT been rotated to align the vent path and the Reactor Building is NOT accessible.

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

5.1.4 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 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

(*Denotes a Critical Step) I

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

STANDARD # S/U evaluation) 5.1.4 A. ENSURE that all prerequisites Operator reviews Prerequisites and have been satisfied in accordance ensures Prerequisites complete.

with Section 2.0 of this procedure.

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

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

performed.

CUE Acknowledge the communication to the EDO.

5.1.4 C. DEPRESS ISLN OVRD and Operator presses the DRYWELL

OPEN GT-HD-9372A Drwl Purge PURGE SHUT OFF DMPRS ISLN Vent Exh Dmpr. OVRD pushbutton. #

Operator observes the pushbutton backlights.

Page 10 of 21

TQ*I"\A*106*0303 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

(*Denotes a Critical Step) COMMENTS STEP

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.

5.1.4 D. DEPRESS ISLN OVRD and Operator observes the amber OVER OPEN GS-HV-4964 SUPP RIDDEN light for the HV-4964 ISLN CHMBR TO CPCS DMP. OVRD is already illuminated.

Operator observes red HV4964 OPEN light is already illuminated and green CLSD light is already extinguished.

Examiner Note: It is only critical the HV-4964 is open. It is not critical whether it was left open from step 5.1.1.C, or closed and then re-opened at this step.

5.1.4 E. ANNOUNCE containment venting Operator announces containment

of the Suppression Chamber to venting of the Suppression Chamber to the Reactor Building. the Reactor Building over the plant #

page.

Page 11 of 21

TQ-",A-106-0303 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.1.4 F. When GS-HV-4964 SUPP Operator observes red HV4964 OPEN CHMBR TO CPCS DMP is full light is illuminated and green CLSD open, then DEPRESS ISLN light is extinguished.

OVRD and OPEN GS-HV-4963 SUPP CHMBR N2 M/U EXH.

Operator presses ISLN OVRD for the

HV4963.

Operator observes the amber OVER RIDDEN light illuminates.

1----- -

Operator presses the HV4963 OPEN

pushbutton.

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

CUE WHEN Vent path has been established, TRIGGER ET-6 to reduce Drywell Pressure.

Page 12 of 21

TQ-I"'\A-106-0303 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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.1.4 G. When drywell pressure can be Operator informs CRS that drywell maintained below 60 psig, then venting has commenced and monitors CLOSE GS-HV-4963 SUPP drywell pressure.

CHMBR N2 M/U EXH and GS HV-4964 SUPP CHMBR TO CPCS DMP.

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:

I I Page 13 of 21

TQ-AA-106-0303 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

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

1. The 'B' RHR pump suction was isolated due to a leak.

2. The Plant experienced a large break LOCA.

3. HC.OP-EO.zZ-0102, Primary Containment Control has been implemented.

4. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising.

5. Suppression Pool Level indicates approximately 83 inches.

6. The Emergency Instrument Air Compressor has been restored lAW HC.OP-EO.ZZ-0319.

7. The Control Room Emergency Filtration System is operating in the Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001 (0).

8. FRVS is in operation in accordance with HC.OP-SO.GU-0001 (0).

9. The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

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

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

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

INITIATING CUE:

Vent the Containment via the Hard Torus Vent lAW HC.OP-EO.ZZ-0318. Notify the CRS when venting has commenced.

Page 15 of 21

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIALIZE the simulator to 100% power, MOL, EPU.

CLOSE the BC-HV-F004B RHR pump suction valve.

ISOLATE drywell cooling by closing the inboard and outboard drywell chilled water isolation valves.

TRIGGER ET-1 and ESTABLISH post large break LOCA conditions with a downcomer break and drywell pressure approximately 60 psig. Malfunctions may be modified as necessary.

CLOSE the MSIVs and drains.

IMPLEMENT EOP-101 AND EOP-102 AFTER drywell pressure is raised to approximately 60 psig.

RESTORE Instrument Air lAW EOP-319.

PLACE Temporary Air Compressor in service.

Trend OW pressure using Insight Item MONVAR(19)

OPEN BCHV-F016A OVERRIDE and close BCHV-F017 A PLACE 'A' RHR pump in drywell spray with the exception of opening the HV-F021 A.

FAIL OPEN an ADS SRV.

USE Insight Item rhv021(1 ) (set to -0.00 to 0.2) to crack open the F021A as necessary to establish drywell pressure at 60 psig and rising slowly.

Trigger ET -5 to stabilize OW pressure indications at 62 psig.

USE Insight Item rhv017(1) (set to -0.00 to 0.1) to crack open the F017 A as necessary to establish slowly rising RPV level.

ENSLIRE CREF is in service in the ISOLATE/RECIRC Mode lAW SO.GK-0001.

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

COMPLETE "SimUlator Ready-for-Training/Examination Checklist".

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Event code: pcpdw >= 16.2 1/ Drywell Pressure in psia 2

Description:

Inserts Feedwater line break and LOCA after drywell preheated Event code: ZLHVDPDO(1) >= 1.0 & ZLPCBLO(2) >= 1.0 & ZLPCISVO(2) >= 1.0 6

Description:

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 Description Insert malfunction FW32 to Feedwater line break inside None None 100.00000 on event 2 containment Insert malfunction FW04A after 60 on Secondary condensate pump APi37 None None event 2 trip Insert malfunction FW04B after 60 on Secondary condensate pump BP137 None None event 2 trip Insert malfunction FW04C after 60 on Secondary condensate pump CP137 None None event 2 trip Insert malfunction MS01 after 90 to None None Steam line break in drywell 4.00000 on event 2 None None Insert malfunction PC04 on event 4 Downcomer break None None Insert remote RH23B to TAGGED RH23 RHR Pump B None None Insert remote RH20A to RACK_OUT RH20 HV-F021A RHR CTMT SPRAY Insert remote ET067 to INSTALLED None None ET067 HV-11541 Torus vent on event 3 None None Insert remote IAi0 to RUN IA10 T em porary station air com pressor EP38 EOP-319, Restoring Instrument None None Insert remote EP38 to Emergency 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 (AO)

Insert override 6AR11_R-.AO to PRESSURECHAMBER PR-4960A1 I None None 28.00000 on event 5

WIDE RANGE (AO)

Insert override 6AR13_B_AO to PRESSURE DRYWELL PR-4960B2 None None 26.00000 on event 5 WIDE RANGE (AO)

Insert override 6AR13_R_AO to PRESSURE CHAMBER PR-4960B1 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 (AO)

Insert override 6AR11_R_AO after 1 PRESSURECHAMBER PR-4960A1 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 EOP 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.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod TASK NUMBER: 4000040401 JPM NUMBER: 305H-JPM.BF011 REV #: 01 SAP BET: NOH05..IPBF11 E ALTERNATE PATH: [ [ ]

APPLICABILITY:

EO RO OC STA D SRO [K]

DEVELOPED BY: Archie E. Faulkner DATE: 9/14/11 Instructor REVIEWED BY: . DATE: ///y/;/

I I Operations Representative APPROVED BY:

3U~

Training Department DATE: l}/111(

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod TASK NUMBER: 4000040401 JPM NUMBER: 305H-JPM.BF011 REV #: 01 SAP BET: NOH05JPBF11 E ALTERNATE PATH: 0 APPLICABILITY:

EOD RO [K] STA D SRO [K]

DEVELOPED BY: Archie E. Faulkner DATE: 9/14/11 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 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: RO SRO EO D RO [KJ STA D SRO [KJ 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:

1. The Plant is operating at 100% power.

2. Maintenance was performed on the position indication circuit of rod 38-03

3. The maintenance is complete.

4. 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.

5. The "ON DUTY" Reactor Engineer has been notified that control rod 38-03 will be exercised lAW HC.OP-ST.BF-0001.

6. The Reactor Engineer has approved exercising rod 38-03 at 100% power.

7. Stall flows are NOT required.

INITIATING CUE:

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

Page 3 of 21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

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

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

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

HC.OP-ST .BF-0001.

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

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

Page 4 of 21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eva I Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.

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

CUE The start time for HC.OP-ST.BF 0001 for retest of rod 38-03 only, Examiner Note: It is not critical to initial has been logged in the Control the procedure steps.

Room log.

5.2 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.0 are satisfied. have been satisfied.

CUE If excessive time is taken reviewing prerequisites, inform operator that N/A all are satisfied.

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

OR Retest is indicated.

Page 5 of 21

TQ-/"\A-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.4 OBTAIN a computer printout (00-7) Operator prints 00-7 from PPC of the current Control Rod positions. computer terminal.

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

operator to use PPC terminal.

5.5 OBSERVE proper response of the Operator reviews the requirement to Nuclear Instrumentation while observe proper response of the Nuclear withdrawing Instrumentation while withdrawing OR inserting all Control Rods. OR inserting all Control Rods.

5.6 SELECT a withdrawn Control Rod Operator presses ROD SELECT

Y N Flagging AND RECORD the initial Control Rod MODULE 38-03 pushbutton. Y N Barriers position on Attachment 2. #

Operator records the initial rod position of 48 on Attachment 2.

5.7 IF Control Rod is at position 00, RECORD final Control Rod position on Attachment 2. All other blocks are N/A for this rod.

Page 6 of 21

Ttt-AA-106-0303 BF011 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.8 OBSERVE approximately 6 gpm total Operator observes approximately 6 flow through both the insert AND gpm total flow through both the insert withdraw Stabilizing Valves as AND withdraw Stabilizing Valves as indicated on CRID's point B2117. indicated on CRID's point 82117.

NOTE The following two steps will exercise Operator reads NOTE.

the 1-BF-V138, Cooling Water Header Check Valve, as required by 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.

5.9 INSERT the selected Control Rod one Operator momentarily presses the ROD

Y N Flagging notch (or as directed by Reactor MOTION CONTROLS INSERT Y N Barriers Engineering) AND PERFORM the pushbutton. #

following: [TIS 4.1.3.1.2, TIS 4.1.3.7]

Page 7 of21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.9.1 ENSURE proper operation of the Operator observes the CONTROL ROD RPIS. POSITION FOUR ROD DISPLAY, RWM, or CRIDS indicates control rod movement to position 46.

5.9.2 IF the Control Rod was inserted Examiner Note: IF the Operator inserts beyond its intended position, the Control Rod beyond position 46, THEN IMMEDIATELY WITHDRAW THEN the Operator IMMEDIATELY the Control Rod to its intended withdraws the Control Rod to position position AND CONTACT Reactor 46 AND contacts Reactor Engineering.

Engineering .

5.9.3 IF the control rod does not insert to Operator recognizes this step is not the next notch after one attempt, applicable and continues at step 5.9.4 PERFORM the following:

5.9.4 INDICATE the condition of RPIS Operator then indicates the RPIS indication on Attachment 2. indication is SAT on Attachment 2.

5.10 IF the position recorded in Step 5.7 is Operator determines the position an intermediate position, recorded in Step 5.7 is NOT an THEN PERFORM Step 5.10.1, intermediate position, continues at step otherwise, GO TO Step 5.10.2 to 5.10.2 to return the control rod to its return the control rod to its original original position.

position:

~--.-

Page 80f21

TQ-AA*106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation)

NOTE IF drive water pressure was increased Operator reads NOTE and determines to withdraw a control rod from position the NOTE is not applicable.

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.

5.10.2 WITHDRAW the control rod to Operator simultaneously presses AND

Y N Barriers position 48 AND PERFORM the holds both the WITHDRAW pushbutton following while giving the selected AND the CONTINUOUS WITHDRAW #

Control Rod a continuous withdraw pushbutton.

signal: [TIS 4.1.3.6, TIS 4.1.3.7]

A. OBSERVE the following as indication of the Control Rod being coupled: N/A

1. ROD OVERTRAVEL alarm does Operator observes OHA C6-F3 ROD NOT annunciate. OVERTRAVEL DOES annunciate.

Page 9 of 21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step)

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

STANDARD StU evaluation)

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

2. Red Full Out light illuminates on Operator observes the red FULL OUT the Full Core Display. light on the Fu" Core Display EXTINGUISHES.

. . ~ ---

3. RPIS indicates the Control Rod is Operator observes RPIS does NOT full out (48). indicate position 48.

4. Proper response of the Nuclear Operator recognizes the expected Instrumentation while response of the Nuclear withdrawing the Control Rod. Instrumentation while withdrawing the Control Rod.

Examiner Note: The expected response for a rod from 46 to 48 is negligible.

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

i Page 10 of 21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE OATE: ___________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # I S/U STANDARD evaluation C. PERFORM the following for stall Based on the Initial Conditions, flow: 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.

D. IF the CRD over travels, Operator informs the CRS of uncoupled THEN IMPLEMENT control rod and entry condition into HC.OP-AB.IC-0001 (Q), HC.OP-AB.IC-0001.

Control Rod.

CUE Acknowledge the report and DIRECT the Operator to implement N/A Condition D of HC.OP-AB.lC-0001.

HC.OP-AB.lC-0001 Condition D Uncoupled Rod and Movement Permitted by RWM 0.1 OBTAIN Reactor Engineering Operator requests Reactor Engineering guidance to recouple the Control Rod. guidance to recouple the Control Rod.

Page 11 of 21

TQ-A.A-106*0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD # stu evaluation CUE INFORM the Operator that Reactor Engineer's guidance in NOT N/A available.

0.2 IF Reactor Engineering guidance Operator determines step 0.2 is CANNOT be obtained, applicable.

THEN RECOUPLE the Control Rod as follows:

0.2.a INSERT the CRO no more than 2 Operator single notch inserts rod 38-03 notches from the point of discovery. 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.

D.2.b Single Notch WITHDRAW the Control Operator single notch withdraws rod

Rod to its original position AND VERIFY 38-03 to position 48. Y N Flagging expected response. # N Barrier~s~_ _ _-i

~r_r_~-

Operator observes correct response of the control rod.

Page 12 of 21

TQ*""A*106*0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD # I S/~1!,:"'oo_ooJ-f_ _.:..:.::.:.=.;;;;.;;.;..;.,;...:.-_--,

evalu D.2.c PERFORM a coupling check on the NIA associated control rod lAW ST.BF 0001.

CUE Provide operator 2 nd marked up NIA copy of HC.OP-ST.BF-0001.

HC.OP*ST .BF-0001 5.10.2 WITHDRAW the control rod to Operator simultaneously presses AND

position 48 holds both the WITHDRAW pushbutton Y N Barriers AND PERFORM the following while AND the CONTINUOUS WITHDRAW #

giving the selected Control pushbutton.

Rod a continuous withdraw signal:

[TIS 4.1.3.6, TIS 4.1.3.7]

A. OBSERVE the following as Operator observes OHA C6-F3 ROD indication of the Control Rod OVERTRAVEL does NOT annunciate.

being coupled:

1. ROD OVERTRAVEL alarm does NOT annunciate.

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

Page 13 of 21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

3. RPIS indicates the Control Rod is Operator observes RPIS indicates the full out (48). Control Rod is full out (48).

I

4. Proper response of the Nuclear Operator recognizes the expected Instrumentation while response of the Nuclear withdrawing the Control Rod. Instrumentation while withdrawing the Control Rod.

Examiner Note: The expected response for a rod at 48 is negligible.

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

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

Page 14 of 21

TQ-AA-106-0303 JPM: BF011 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 01 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Control Rod and Drive Mechanism TASK: Respond To An Uncoupled Control rod

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluati HC.OP-AB.lC-0001 Condition D Uncoupled Rod and Movement Permitted by RWM D.3 RESTRICT all further withdrawals of Operator informs the CRS that all this rod to Single Notch movement further withdrawals of this rod should be Y N Barriers until repairs have been completed. restricted to Single Notch movement until repairs have been completed.

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 I NtA operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 15 of21

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

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

DATE:

JPM Number: BF011 TASK: Respond To An Uncoupled Control rod TASK NUMBER: 4000040401 QUESTION:

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

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 16 of 21

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

1. The Plant is operating at 100% power.

2. Maintenance was performed on the position indication circuit of rod 38-03

3. The maintenance is complete.

4. 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.

5. The "ON DUTY" Reactor Engineer has been notified that control rod 38-03 will be exercised lAW HC.OP-ST.BF-0001.

6. The Reactor Engineer has approved exercising rod 38-03 at 100% power.

7. Stall flows are NOT required.

INITIATING CUE:

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

Page 17 of21

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

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 48.

Event code:

et_array(1) >= 1.0 & Icvposx(6) < 740 2

Description:

Rod 38-03 Overtravel and inserted II Deletes uncoupled rod after it has been inserted more than one notch lAW AB Event code:

Description:

Page 18 of 21

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

None None Insert malfunction CD043803 Control Rod 38-03 uncoupled Insert malfunction CD043803 on event None 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 Description 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

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 JPM NUMBER: 305H-JPM.ED002 REV #: 06 SAP BET: NOH05JPED02E ALTERNATE PATH: 0 APPLICABILITY:

EO 0 RO [KJ STA ~ _._' SRO [KJ DEVELOPED BY: Steve Dennis DATE: 2/16/12 Instructor REVIEWED BY: /<1<. -cf't,VL DATE: o/~

APPROVED BY: 9ttCf'JJ---

Training Department DATE: Q/}2/J~

TQ-AA-106-0303 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 ~ANUMBER: ____2_12_0_0_0_A_2_.0_1___

IMPORTANCE FACTOR: 3.7 3.9 APPLICABILITY: RO SRO EO D RO [ ] ] STA D 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:

P~ge 2 of 14

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction TASK NUMBER: 4000110401 INITIAL CONDITIONS:

1. The plant was operating at 100% power when the "N RPS MG set tripped due to a bearing problem.

2. Restoration of the "A' RPS MG set is not possible at this time.

3. There is no damage to the 'A' RPS bus.

INITIATING CUE:

Perform Condition A of HC.OP-AB.IC-0003.

Restoration of isolated equipment is not necessary at this time.

Page 3 of 14

TCt-r\A-106-0303 JPM: S8010 OPERATOR TRAINING PROGRAM NAME: _________________

Rev: 05 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation)

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

CUE ENTER START TIME AFTER ' .JiLl!ll OPERATOR REPEATS BACK INITIATING CUE: N/A T'i I"~ . H

.3"

".i1' iN": f:

START TIME:

'0:~il it .*":f!~;

Operator obtains procedure Operator obtains the correct procedure.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be A.1.

A.1 RESTORE Normal Power to the Operator determines restoration of Normal affected Bus. Power to the bus is not possible lAW Initial (if possible) Conditions provided.

Page 4 of 14

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

Rev: 05 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

CAUT Operator reviews Caution 1.

1 1. The RPS MG Set Transfer Switch is a "Break before Make" type switch.

Positioning it to the wrong position will result in a full scram.

A2 IF Normal Power cannot be restored: Operator verifies Alternate Power is available by observing the ALTERNATE A

a. VERIFY Alternate Power is FEED liaht on 10C610 is illuminated.

available.

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

b. TRANSFER Power to the Operator turns the RPS MG SET

Alternate Power Supply by TRANSFER SWITCH to the ALT A POSITIONING the RPS MG SET position. #

TRANSFER SWITCH to the Alternate position.

[CD324X]

Page 5 of 14

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

Rev: 05 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation) ~

A.3 RESET the 1/2 Scram as follows: Operator turns the key for the RPS A 1 Trip

Logic to RESET and back to NORMAL.

a. TURN the key for the Affected #

RPS channel(s) to the RESET position.

b. TURN the key BACK to NORMAL.

Operator turns the key for the RPS A2 Trip

Logic to RESET and back to NORMAL.

c. VERIFY the Scram is reset. Operator verifies the scram is reset by observing the following:

RPS TRIP LOGIC A 1 and A2 NORMAL/RESET lights are illuminated

All four PILOT SCRAM VALVE SOLENOID LOGIC A NORMAL lights are illuminated

REACTOR SCRAM TRIP LOGIC A 1 and A2 OHAs are no longer illuminated Page 6 of 14

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

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation)

A.4 IF the MSIV's are OPEN Operator presses the NUCLEAR STEAM

THEN RESET the tripped NSSSS SUPPLY SHUTOFF SYSTEM TRIP Logic as follows: LOGIC A pushbutton. #

a. PRESS the NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC A(B,C,D) RESET Pb.

~,

~-

Operator presses the NUCLEAR STEAM

SUPPLY SHUTOFF SYSTEM TRIP LOGIC C RESET pushbutton. #

I 1-----

b. VERIFY MSIV TRIP LOGIC Operator verifies the MSIV TRIP LOGIC TRI PPED goes off. TRIPPED light for LOGIC A is extinguished.

Operator verifies the MSIV TRIP LOGIC TRIPPED light for LOGIC C is extinguished.

Page 7 of 14

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

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Respond To A Reactor Protection System Malfunction

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

EVAL (Required for UNSAT NO. #

STANDARD StU evaluation)

WHEN operator informs you the task is N/A 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 14

TQ-AA-106-0303 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

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

1. The plant was operating at 100% power when the 'A' RPS MG set tripped due to a bearing problem.

2. Restoration of the 'A' RPS MG set is not possible at this time.

3. There is no damage to the 'A' RPS bus.

INITIATING CUE:

Perform Condition A of HC.OP-AB.IC-0003.

Restoration of isolated equipment is not necessary at this time.

Page 10 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE i Initial INITIALIZE the simulator to 100% power, MOL.

INSERT malfunction RP02A.

AFTER RWCU trips and conditions stabilize, ACKNOWLEDGE all overhead and RM11 alarms.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

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.,

TQ-AA-106-0303 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: W KIA NUMBER: 295018 AA2.02 1M PORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO EO D RO [ ] ] STA D 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

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction TASK NUMBER: 4000230401 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 Operator.

Place the BP209 RACS pump in service and secure the AP209 RACS pump.

Page 3 of 19

TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step)

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

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

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-SO.EO-0001.

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

CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. N/A Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.3.1.

Page 4 of 19

TQ-",A-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step)

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

STANDARD # I S/U eva I 5.3.1 ENSURE all prerequisites have been Operator ensures that all prerequisites satisfied lAW Section 2.3. have been satisfied.

Operator then initials the appropriate Reactor Auxiliaries Cooling Water procedure step.

System is in service.

CUE If excessive time is taken reviewing prerequisites, inform operator that all are satisfied. N/A 5.3.2 ENSURE that one of the following On 10C651A operator observes the HX valves are OPEN (10C651A): INLET VALVES:

ED-HV-2537A(B) HX INLET VLVS.

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 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 06 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step)

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

STANDARD S/U evaluation) 5.3.3 OBSERVE the following lights are off for the RACS Pumps Operator observes the REACTOR going in service: AUXILIARIES COOLING PUMPS

OVLD/PWR FAIL PUMP Bamber OVLD/PWR FAIL, INOP, and white REMOTE lights are

INOP extinguished.

REMOTE 5.3.4 For the 1AP209 and/or 1BP209, as

applicable, ENSURE RACS PMP 1AP209 BKR On 10C650E operator observes the 52-41011, RACS PMP BP209 BRKR 52-42011 and/or 1BP209 BKR 52-42011 red CLOSED light is illuminated and CLOSED is on. (10C650E) green TRIPPED light is extinguished.

5.3.5 IF returning a pump to service that has been isolated and drained, PERFORM the following steps as necessary to correct/prevent air Operator determines to proceed to Step binding, otherwise, PROCEED to 5.3.6, since the Initiating Cue states Step 5.3.6 for a normal start of a that the pump was not isolated.

standby pump:

Page 6 of 19

TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation) 5.3.6 PRESS REACTOR AUXILIARIES

COOLING PUMP A(B)(C) Operator presses the REACTOR #

START PB (10C651A). START AUXILIARIES COOLING PUMPS comes on. PUMP B BP209 START pushbutton.

OBSERVE AI-6460 (AI-6461)

REACTOR AUXILIARIES COOLING Operator observes:

PUMP A(B)(C) MOT AMPS settles at

The red BP209 START light

< 180 amps illuminates and the green STOP AND is approximately the same as light extinguishes.

the other lIS RACS pumps' motor

AI-6461 is < 180 amps and settles amps. at approximately the same value as the "AI! and "C" RACS pumps' amps.

I 5.3.7 PRESS REACTOR AUXILIARIES

COOLING PUMP B(A)(C) Operator presses the REACTOR AUXILIARIES COOLING PUMPS #

STOP PB. STOP comes on.

PUMP A STOP pushbutton.

Operator observes the green STOP light illuminates and the red AP209 START light extinguishes.

Page 7 of 19

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

Rev: 06 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step)

COMMENTS STEP 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 has been secured, the Operator observes Control Board Awareness the following:

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 HC.OP-AR.ZZ-0002 N/A ATT OPERATOR ACTION:

E2 1. REFER to HC.OP-AB.COOL-0003(Q); Reactor Auxiliary Cooling System.

2. ENSURE compliance with Technical Specifications 3.6.3 Operator refers to HC.OP-AB.COOL-0003.

Containment Isolation Valves.

3. ENSURE compliance with I Technical Specifications 3.6.5 Secondary Containment Integrity.

Page 8 of 19

TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 06 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. # evaluation STANDARD S/U eelOCI<X!If~-----"':"-----f CUE Direct the Operator to perform Condition 'A' of HC.OP-AB.COOL-0003 Reactor N/A Auxiliary Cooling System.

N/A HC.OP-AB.COOL-0003 N/A COND Date/Time Operator enters the current Date/Time in the spaces provided.

A A.1 PRESS the START P.B. for any Operator presses the REACTOR available RACS pump in standby. AUXILIARIES COOLING PUMPS PUMP A AP209 START pushbutton.

Operator observes:

The red AP209 START light remains extinguished and the green STOP light remains illuminated.

Motor amps continue to indicate O.

Page 9 of 19

TQ-AA-106-0303 JPM: ED002 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

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

EVAL {Required for UNSAT NO.

STANDARD # I StU eval CUE Respond to any reports of the 'A' RACS pump failure to start by directing the operator to continue implementing Condition 'A' of N/A HC.OP~AB.COOL-0003.

A.2 IF a second RACS Pump CANNOT be placed in service, THEN ISOLATE RACS to the out of Operator observes the OFF GAS service Off-Gas Train as follows: RECOMB TRAIN SELECT:

IF the Common Off-Gas Train

COM TRAIN red OPEN light is in service, illuminated and green CLOSE light THEN CLOSE HV-2S77. extinguished.

IF Unit 1 Off-Gas Train is in

TRAIN 1 red OPEN light service, extinguished and green CLOSE light THEN CLOSE HV-7712A1. 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: ED002 OPERATOR TRAINING PROGRAM NAME:

Rev: 06 JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Reactor Auxiliaries Cooling System TASK: Respond To A Reactor Auxiliary Cooling Malfunction

(*Denotes a Critical Step)

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

STANDARD S/U 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.

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

STOP TIME:

Page 11 of 19

TQ-AA-106-0303 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

TQ*AA*106-0303 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 Operator.

Place the BP209 RACS pump in service and secure the AP209 RACS pump.

Page 13 of 19

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

INITIALIZE the simulator to any IC with the Main Generator loaded.

ENSURE the 'A' & 'C' RACS pumps are in service and the 'B' RACS pump is in STBY.

ENSURE the Common Offgas Train is in service and HV-2577 is open.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

ENSURE NON -1 E BKR 52-42011 is OPEN Initial 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

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

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

TQ*AA*106*0303 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

TQ-AA-106-0303 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 Operator.

Place the BP209 RACS pump in service and secure the AP209 RACS pump.

ERFORMANC MEASURE STATION: Hope Creek SYSTEM: Main Steam TASK: Install Jumpers To Bypass MSIV Low Level Isolation Interlock TASK NUMBER: 2000010501/200059054

...'PM NUMBER: 305H-JPM.AB001 REV#: 07 SAP BET: NOH05JPAB01 E ALTERNATE PATH: D APPLICABILITY:

EO RO [KJ STA '------' SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 9/4/08 Instructor REVIEWED BY:

i2/ElL~

Operations Representative DATE: 9-/~-o8 APPROVED BY: gztg:JJ--

Training Department DATE: ~LJ6/or

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

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:

1. The Reactor is at 32% power following a full core ATWS.

2. The Main Turbine is tripped.

3. The MSIVs are open.

4. The Main Condenser is available.

5. HC.OP-EO.ZZ-0101A, ATWS - RPV Control, is being executed.

6. 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.

7. 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

l~

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

STANDARD # StU evaluation)

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

I I~

ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains and locates Operator obtains the correct procedure.

procedure HC.OP-EO.zZ-0301.

~--~-~~-

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

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

Page 4 of 13

AB001 OPERATOR TRAINING PROGRAM Rev: 07 JOB PERFORMANCE MEASURE DATE: __________~.......

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

STANDARD # S/U evaluation) 4.0 EQUIPMENT REQUIRED Operator obtains the following required equipment:

4.1 EOP-301 Implementation Kit (OS Office EOP Drawer) EOP-301 Implementation Kit from NSS Contents: 4 Banana Plug Jumpers Office EOP drawer OR 1 Flashlight Key #9 from OS Office or key from OR break glass key holder in OSC for OSC 4.2 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 OSC.

EOP-301 Implementation Kit (EOP Locker in OSC). Examiner Note: After operator has Contents: 4 Banana Plug Jumpers demonstrated ability to obtain 1 Flashlight required equipment, ensure that the equipment is returned to its appropriate storage location.

Operator determines beginning step Operator determines the correct of the procedure. beginning step to be 5.2.

5.2.1 ENSl1REthat allprerequisiteshave Operator ensures that all prerequisites been satisfied JAW Section 2.0 of this have been satisfied.

procedure.

__ T~*_' ___

CUE 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 STEP (*Denotes a Critical Step) COMMENTS NO.

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # StU evaluation) 5.2.2 At panel 10C609 Div. 1 (front) Operator installs jumper between the

INSTALL a jumper in the red and red and black jacks labeled B21 H-black jacks labeled: K212A T1-M1 HC.OP-EO.zZ-0301 B21H-K212A T1-M1 OP-EO.ZZ-301 (10C609)

(fourth column, first row)

"cuE the jumper has been installed as you have indicated. /:';'., .

.:2 ........*

r 5.2.3 At panel 10C609 Div 3 (front) Operator installs jumper between the INSTALL a jumper in the red and red and black jacks labeled 821 H-

black jacks labeled: K212C T1-M1 HC.OP-EO.ZZ-0301 B21H-K212C T1-M1 OP-EO.ZZ-301 (10C609)

(fourth column, first row)

CUE The jumper has been installed as I* .

I*. .'

you have indicated.

N i.

..... I; '.

. :. I, ........ ,

--~--~-.

5.2.4 At panel 1OC611 Div. 2 (front) Operator installs jumper between the INSTALL a jumper in the red and red and black jacks labeled 821 H-

black jacks labeled: K212B T1-M1 HC.OP-EO.zZ-0301 B21H-K212B T1-M1 OP-EO.ZZ-301 (10C611 ).

(fourth column, first row)

CUE The jumper has been installed as I',* .' I**** *.:>

you have indicated.

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

STANDARD # S/U evaluation) 5.2.5 At panel 10C611 Div. 4 (front) Operator installs jumper between the INSTALL a jumper in the red and red and black jacks labeled 821 H

black jacks labeled: K212D T1-M1 HC.OP-EOZZ-0301 B21H-K212D T1-M1 OP-EO.ZZ-301 (10C611).

(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:

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 0303 a

JOB PERFORMANCE MEASURE INITIAL COND!TIONS:

1. The Reactor is at 32% power following a full core ATWS.

2. The Main Turbine is tripped.

3. The MSIVs are open.

4. The Main Condenser is available.

5. HC.OP-EO.ZZ-0101A, ATWS - RPV Control, is being executed.

6. 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.

7. 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 0303 m

JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

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 Description COMPLETE "Simulator Ready-for-TrainingfExamination Checklist".

EVENT ACTION: I COMMAND: .

PURPOSE:

EVENT ACTION:

2 COMMAND:

PURPOSE:

Page 10 of 13

TQ*AA*106*0303 JOB PERFORMANCE SIMULATOR SETUP INSTRJCTIONS (OPTIONAL) 07 Half Core ATWS - Right Side 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 # Date Description Validation 1

Required?

07 9/4/2008 This revision converts to HC LOR format, documents validation, Y and generates estimated completion time.

Since Critical ~IPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

Revised power level from 48% to 32% based on IC and current core model.

Added Remote functions for EOP 311 and 319 implementation.

Updated Reference procedure revision number. No change to operator actions.

I

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction TASK NUMBER: 400780401 JPM NUMBER: 305H-JPM.EG003 REV #: 17 SAP BET: NOH05JPEG03E ALTERNATE PATH: D APPLICABILITY:

EO RO [KJ STA D SRO [KJ DEVELOPED BY: Archie E. Faulkner DATE: 12/30/11 Instructor REVIEWED BY: ~R ~rt.JVL DATE: I;; c/;z APPROVED BY: qu~ DATE: 1/1 t/(<

Training Department

TQ-AA-106-0303 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__

IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO EOD ROCK] STAD SROCK]

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:

1. SACS Loop B has been declared inoperable.

2. HC.OP-AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System, is being implemented.

3. Components are being realigned lAW Section 5.12 of HC.OP-SO.EG-0001.

4. 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 presented in HC.OP-SO.EG-0001 Attachment 3 Part B.

WCM update and tagging will be performed by another operator.

Page 3 of 12

TQ-~ ,.-\-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 17 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction

(*Denotes a Critical Step)

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

STANDARD Stu eval CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains/locates procedure Operator locates the proper procedure.

HC.OP-SO.EG-0001.

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

CUE If excessive time is taken reviewing Examiner Note: The sequence critical Precautions and Limitations, portion of the following steps is to close inform operator that all are the 1-EG-V689 AND 1-EG-V692 satisfied. BEFORE opening the 1-EG-V703 OR 1-EG-V702.

ATI.3 FRVS CLG COIL DVH-213 LP B SUP Operator unlocks 1-EG-V689.

10 1-EG-V689 Examiner Note: Support operator's requests for Verifier.

LOCKED CLOSED Page 4 of 12

TO-*..--\-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME:

Rev: 17 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction

(*Denotes a Critical Step)

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

STANDARD StU evaluatio CUE The lock has been removed from N/A the valve indicated.

Operator closes 1-EG-V689.

CUE The valve indicated has been N/A rotated in the direction stated and has come to hard stop.

Operator reinstalls a locking device on valve 1-EG-V689.

CUE The lock is installed on the valve N/A indicated.

ATT.3 FRVS CLG COIL DVH-213 LP B RTN Operator unlocks 1-EG-V692.

11 1-EG-V692 Examiner Note: Support operators requests for Verifier.

LOCKED CLOSED CUE The lock has been removed from N/A the valve indicated.

Page 5 of 12

TQ-",A-106-0303 JPM: EG003 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 17 JOB PERFORMANCE MEASURE SYSTEM: Safety Auxiliaries Cooling Water TASK: Respond To A SACS Malfunction

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U Operator closes 1-EG-V692.

CUE The valve indicated has been N/A rotated in the direction stated and has come to hard stop.

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

CUE The lock is installed on the valve N/A indicated.

ATT.3 FRVS CLG COIL DVH-213 LP A SUP Operator unlocks 1-EG-V703.

12 1-EG-V703 Examiner Note: Support operator's requests for Verifier.

LOCKED OPEN CUE The lock has been removed from N/A the valve indicated.

Operator opens 1-EG-V703.

Page 6 of 12

TQ-h,",~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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD ~S/U evaluation CUE The valve indicated has been N/A rotated in the direction stated and has come to hard stop.

Operator reinstalls a locking device on valve 1-EG-V703.

CUE The lock is installed on the valve N/A indicated.

ATT.3 FRVS CLG COIL DVH-213 LP A RET Operator unlocks 1-EG-V702.

13 1-EG-V702 Examiner Note: Support operator's requests for Verifier.

LOCKED OPEN CUE The lock has been removed from N/A the valve indicated.

Operator opens 1-EG-V702.

CUE The valve indicated has been rotated in the direction stated and has come to hard stop. N/A Page 7 of 12

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

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U 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

TQ-AA-106-0303 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

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

1. SACS Loop B has been declared inoperable.

2. HC.OP-AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System, is being implemented.

3. Components are being realigned lAW Section 5.12 of HC.OP-SO.EG-0001.

4. 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 in HC.OP-SO.EG-0001 Attachment 3 Part B.

WCM update and tagging will be performed by another operator.

Page 10 of 12

TQ*AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: EG003 I Rev#

Date Description Validation Required?

13 8/28/2008 Revised to new JPM format. Revalidated .JPM time. y 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.

TQ-AA-106-0303 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 IMPORTANCE FACTOR: 4.1 4.2 APPLICABILITY: RO SRO EO D RO [KJ STA D SRO [KJ 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.

2. HC.OP-AB.RPV-0006 Safety Relief Valve, is being executed.

3. 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 HC.OP-AB.RPV-0006.

Page 3 of 12

TQ-AA-106-0303 JPM: AB00302 OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve

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

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

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

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

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.RPV-0006 f------+~~~~~~ ......

Operator reviews Immediate Operator Operator reviews Immediate Operator Actions, Retainment Overrides, Actions, Retainment Overrides, applicable Cautions and Notes. applicable Cautions and Notes.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be A.3 A.3 IF the SRV solenoid cannot be de Operator determines this step applies energized from the Control Room, and reviews Attachment 2.

THEN REMOVE SRV fuses associated with the energized logic lAW 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

TQ-MA-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 (e Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD e ELEMENT S/U evah Att 2 At panel 10C628 (ADS DIV 2) the

Y N STAR 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).

CUE The fuse that you have indicated is N/A pulled.

Att 2 At panel 10C628 (ADS DIV 2) the Operator simulates pulling fuse I

I I Y N STAR operator pulls fuse 821 C F4D F10.

Logic 821 C F4D F10 at panel 10C628 (ADS 8 (Panel labeled H11-P628) DIV2}.

CUE The fuse that you have indicated is N/A pulled.

Att 2 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 H11-P631 ) DIV 4).

CUE The fuse that you have indicated is N/A pulled.

Att 2 At panel10C631 (ADS DIV 4) the Y N STAR 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).

CUE The fuse that you have indicated is N/A pulled.

Page 5 of 12

TQ-rlA-106-0303 AB00302 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Steam TASK: Respond to a Failed Open Safety Relief Valve (e Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

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

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

STOP TIME:

Page 6 of 12

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

DATE:

JPM Number: AB00302 TASK: Respond to a Failed Open Safety Relief Valve TASK NUMBER: 4000210401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 7 of 12

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

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

EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 8 of 12

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

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

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: AB00302 Rev # Date Description Il .... _~: __

Re~~ir;d?

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

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

1. The Reactor is shutdown due to the "0" SRV being electrically held open with both Logic Train Band 0 solenoids.

2. HC.OP-AB.RPV-0006 Safety Relief Valve, is being executed.

3. 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 HC.OP AB.RPV-0006.

Page 12 of 12

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout TASK NUMBER: 4000020404 JPM NUMBER: 305H-JPM.PK001 REV #: 02 SAP BET: NOH05JPPK01E ALTERNATE PATH: D APPLICABILITY:

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

APPROVED BY: WCW-Training Department DATE: ///t//?

TQ~AA~106-0303 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:

i Page 2 of 14

TQ-AA-106-0303 NAIVI E:

DATE:

SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout TASK NUMBER: 4000020404 INITIAL CONDITIONS:

1. The plant is in OPCON 3.

2. A loss of all offsite and onsite AC power occurred 15 minutes ago.

3. HC.OP-AB.ZZ-0135, STATION BLACKOUT IILOSS OF OFFSITE POWERI/OIESEL GENERATOR MALFUNCTION has been completed through step 4.5.4.

INITIATING CLlE:

IMPLEMENT Attachment 3, Radwaste Building Actions of HC.OP-AB.ZZ-0135(Q).

Page 3 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU evaluation)

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

cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating m

Cue: N/A START TIME: _

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.ZZ-0135(Q).

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 4.5.5.

I Operator locates Attachment 3. I I Page 4 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eval Attach OPEN the circuit breakers in the 3 following tables when plant has entered an S80.

Step

1. CLOSE the circuit breakers in the Examiner Note: A map showing panel following tables when restoring offsite locations is provided on the bottom of power. Attachment 3.

All are ARC Flash Category O.

18D318 Operator locates panel 1B0318 in Room 3449.

0 Circuit 12 Operator simulates opening breaker 12 I

on 80318.

CUE The breaker you have indicated is open. N/A o Circuit 19 Operator simulates opening breaker 19

on 80318.

Page 5 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluation)

CUE The breaker you have indicated is open. N/A o Circuit 24 Operator simulates opening breaker 24 on 80318.

CUE The breaker you have indicated is open. N/A o Circuit 27 Operator simulates opening breaker 27 on 80318.

CUE The breaker you have indicated is open. N/A 1AD318 Operator locates panel1A0318 in Room 3449.

o Circuit 12 Operator simulates opening breaker 12

on A0318.

Page 6 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluatio CUE The breaker you have indicated is open. N/A o Circuit Operator simulates opening breaker 27 on AD318.

CUE The breaker you have indicated is open. N/A o Circuit 28 Operator simulates opening breaker 28 on AD318.

CUE The breaker you have indicated is open. N/A 1DD318 Operator locates panel 100318 in Room 3432.

o Circuit 11 Operator simulates opening breaker 11

on 00318.

Page 7 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U eval

-oo-oo~,----~~~~~---;

CUE The breaker you have indicated is open. N/A o Circuit 12 Operator simulates opening breaker 12 on 00318.

CUE The breaker you have indicated is open. N/A o Circuit 14 Operator simulates opening breaker 14

on 00318.

CUE The breaker you have indicated is open. N/A o Circuit 27 Operator simulates opening breaker 27

on 00318.

CUE The breaker you have indicated is open. N/A Page 8 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD S/U evaluatio 1CD318 Operator locates panel 1CD318 in Room 3432.

o Circuit 11 Operator simulates opening breaker 11

on CD318.

CUE The breaker you have indicated is open. N/A o Circuit 12 Operator simulates opening breaker 12 on CD318.

CUE The breaker you have indicated is open. N/A o Circuit 14 Operator simulates opening breaker 14 on CD318.

CUE The breaker you have indicated is open. N/A Page 9 of 14

JPM: PK001 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 02 JOB PERFORMANCE MEASURE SYSTEM: DC Electrical Distribution TASK: Respond To A Station Blackout

(*Denotes a Critical Step) COMMENTS STEP

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

STANDARD StU 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.

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

STOP TIME:

Page 10 of 14

TQ-AA-106-0303 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

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

1. The plant is in OPCON 3.

2. A loss of all offsite and onsite AC power occurred 15 minutes ago.

3. HC.OP-AB.ZZ-0135, STATION BLACKOUT IILOSS OF OFFSITE POWERI/DIESEL GENERATOR MALFUNCTION has been completed through step 4.5.4.

INITIATING CUE:

IMPLEMENT Attachment 3, Radwaste Building Actions of HC.OP-AB.ZZ-0135(Q).

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 2007JPM 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: NRC SCENARIO 1 SCENARIO NUMBER: ESG-NRC-S1 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 80 minutes REVISION NUMBER: 01 PROGRAM: '---_-----' L. O. REQUAL X I INITIAL LICENSE

'---_-----' OTH ER REVISION

SUMMARY

1. NOTE added to delay ET-5 until RPV level has recovered to ..:..12.5 inches.

PREPARED BY: Steve Dennis 2/15/12 Instructor DATE APPROVED BY:

LORT Group t6ad or Designee . r DATE APPROVED BY:

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an " *.")

A. Raise Power with Recirc B. PT-N076A MSL Pressure Fails Upscale C. A CRD Pump Trip D. Seismic Event with 10A403 Bus Lockout E. Small Break LOCA ! Manual scram F. LOP! with A, B, and D EDG Malfunctions G. HPCI Oil Line Break H. 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 24 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 pump.

At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

(800913960270)

ENSURE Data Collection is trending the following datapool variables:

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

i*t,f~t><~i7; Initial @Time Event Action Description None None Insert malfunction TC07B EHC pump B trip None None Insert malfunction DGO 1A 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 1OA 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 0%~60 gpm, None None 600 on event 4 100%~600 gpm)

Seismic Event II None None Insert malfunction PC07B on event 5 None I None Insert malfunction EG 12 on event 5 Loss of all off site power 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 0%~6000 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 None RCIC turbine overspeed in!

Insert malfunction DGOIA after 1 on event None None Diesel generator A failure to start 12 delete in 1 I

ESG-NRC-S1 Page 4 of 24 Rev: 01

Insert remote Re02 after 5 to RESET on None event 8 RC02 RCIC overspeed trip reset Insert remote HP08 to TAGGED on event None None HP08 HPCI Aux Oil Pump Insert remote eXIl after 60 to OPEN on eXIl ex valve AP-V041 to Core Spray None None event 11 header A Insert remote eX15 after 120 to OPEN on None None eXI5 ex valve AP-V044 to RHR header A event 11 I11.'lert remote eXl? after 180 to OPEN on None None eXl? ex valve AP-V04? to RHR headerC event 11

Raise Power with Recirc:

CRS directs the RO to raise After the Crew assumes the Reactor power with Reactor watch. Recirc in accordance with RE guidance.

RO increases Reactor Recirc pump speeds in accordance with HC.OP-SO.BB-0002 and CRS directions.

PT~N076A Failure:

Crew recognizes 'A' NSSSS After.the Crew assumes the instrument failure by:

watch and at the discretion of =:> OHA C8-A5 "NSSSS INBD the Lead Examiner,TRIGGER ISLN SYS OUT OF SVCE" ET-1 ('A' NSSSS MSL =:> Amber NSSSS CH A 'TRIP Pressure Transmitter Fails UNIT IN CAL OR GROSS High). 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 This will prevent the 'A' units and finds B21-N676A is NSSSS Channel from failed upscale with a Gross Fail generating an MSIV Trip in. isolation signal on Low Main Steam Line pressure.

Transmitter is located in TB

Crew contacts Maintenance to Electrical Mezzanine. troubleshoot.

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

ESG-NRC-S1 Page 6 of 24 Rev: 01

CRS recognize the following TIS TIS Table 3.3.2-1 Trip applies Function 3c.

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 HC.OP appropriate delay, support GP.ZZ-0011 to place trip units actions of placing trip units in into tripped condition tripped condition by changing MALF 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 52 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 24 Rev: 01

~ 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.

Earthquake/10A403 Bus

Crew recognizes Seismic Event Loss: by:

After the Crew restores CRD ~ OHA C6-C4 "SEISMIC MON and at the discretion of the PNL C673" Lead Examiner: ~ CRIDS D3977 "SEISMIC

PLAY the Earthquake TROUBLE ALARM TRBL" Sound Effect (if available) at Response Spectrum Analyzer

.rTIedium volume for about indications on 1OC650C 20 seconds ~ Loud rumbling noise OR (if available)

ANNOUNCE "You feel motion then. it stops"

TRIGGER"ETw3 (Seismic Eventl10A403 Bus Loss)

Crew monitors critical parameters to determine if plant is stable.

IE Crew calls l\Jational

CRS implements AB.MISC-0001 : AB.MISC-0001 actions Earthquake Center, ~ Condition E provided for reference THEN REPORT a seismic Condition F only. Due to the pace event of 6.0 on Richter scale of the scenario, it is centered 12 miles east of unlikely they will be Wilmington, DE. implemented.

IF Crew calls Security, THEN REPORT the Security system is intact.

ESG-NRC-S1 Page 8 of 24 Rev: 01

RO/PO implement AR.ZZ-0011 Attachment C4.

IF dispatched to 10C673,

Crew dispatches ABEO to THEN REPORT: 10C673.

The Event Indicator is

Crew recognizes a seismic event WHITE

>0.1 g has occurred

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,

RO/PO direct ABEO to reset THEN DELETE Malfunction 10C673 lAW SO.SG-0001.

PC07A.

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 24 Rev: 01

CRS directs PO to complete AB.ZZ-0172 Subsequent Actions.

PO ensures A SACS pump is in service.

PO ensures B TACS Loop is in service.

PO ensures A SSW pump is in service.

PO determines A SSW Pump has failed to auto-start.

PO starts A SSW pump as follows:

=> PO places A SSW Pump in MAN.

=> PO presses A SSW Pump START pb.

PO ensures B Control Room HVAC Train is in service.

IE dispatched to align AP to 'A'

PO directs RBEO to align keepfill Core Spray and A & C RHR to "A" Core Spray Loop and "A" THEN: and "C" RHR Loops.

TRIGGER ET*11 to open AP-V044N047N041

CRS recognize the following TIS TIS 3.B.3.1.

applies

> 3.B.3.1.a.3. a)

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

=> 3.B.1.1 Perform Power Distribution lineup within one hour.

ESG-NRC-S1 Page 10 of 24 Rev: 01

Small Break LOCA:

Crew recognizes LOCA 20 minutes after the condition:

earthquake ~ OHA C6-B1 "DLD SYSTEM OR, ALARMITRBL"

~ RM11 9AX314 DLD FLOOR at the discretion of the Lead Examiner, TRIGGER ET-4. 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 AB.CONT Based on the rate of 0006: drywell pressure rise

~ Condition A (==10 minutes to 1.68#)

~ Condition B some or all of these

~ Condition C Conditions may not be entered.

CRS implements AB.CONT 0001:

~ Condition A

RO/PO ensures drywell cooling maximized.

Crew checks

~ Recirc pump seal parameters

~ SRV temperatures ESG-I'JRC-S1 Page 11 of 24 Rev: 01

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 Aftershock/LOP/LOCA:

Crew recognizes Loss of Offsite Power by:

NOTE: Ensure RPV level has => aHA "STA SERVICE recovered to +12.5 before TRANSFORMER TROUBLE" ET-5 is triggered. for all transformers

=> TRIP indication for all 500 KV At the Lead Examiners breakers discretion, => Flashing TRIP lights for all

PLAY the E~rthquake previously closed bus infeeds.

Sound Effect (if available) at => Numerous OVLD/PWR FAIL medium v()lumefor about lights.

20 seconds OR ANNOUNCE "You Jeel moti.on then it stops"

TRIGGER ET-5 (LOP/LOCA)

ESG-NRC-S1 Page 12 of 24 Rev: 01

.' ? '. .. .

. V/~'<.: SCENARIO G

Crew recognizes failure of the Only 'B' EOG will start A/B/O EOGs to start and load by: from the Control Room.

~ Engine STOP lights

'C' EOG is not available

~ Output breaker TRIP lights due to the 10A403 bus

~ OVLO/PWR lights on lockout.

associated Channel components IF directed to start the 'B' EOG

RO/PO attempt to start the A/B/O Immediate Operator locally, EOGs. Action lAW AB.ZZ-0135 THEN TRIGGER ET-7 and REPORT 'B' EOG running.

RO/PO close 'B' EOG output Immediate Operator breaker. Action lAW AB.ZZ-0135.

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.

IE dispatched to investigate the

Crew dispatches NEO and/or failure of '0' EOGs to start, Maintenance to investigate THEN REPORT '0' EOG has failure of 0 EOG to start.

Lube Oil Low Pressure Shutdown alarm. There is oil on '0' EOG room floor.

ESG-NRC-S1 Page 13 of 24 Rev: 01

IE dispatched to investigate the

Crew dispatches NEO and/or failure of the "A' EDG to start, Maintenance to investigate THEN REPORT there is a failure of 'A' EDG to start.

blown fuse on DC Circuit 3 on the AC421 panel.

IF directed to start the EDG using either local control

switch, THEN REPORT it did not work.

(AR.KJ-0001 Att. 37A)

IE dispatched to check 86, SFR, and SDR relays for "A'

EDG, THEN REPORT:

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

Crew recognizes HPCI Oil line status of HPCI, break problem by:

THEN REPORT

HPCI is idle :::} HPCI Aux Oil Pump running

HPCI Aux oil pump is :::} HV- F001 open running.

} "HPCI INIT AND SEALED IN"

HV-F001 is open light on

Oil in the floor surrounding :::} HPCI Governor valve closed the pump skid

} HPCI Turbine Speed 0 rpm IF directed to open the breaker for the HPCI Aux Oil pump, (72-251042)

THEN TRIGGER ET-10.

IF dispatched to investigate

Crew dispatches NEO to RCIC trip, investigate RCIC trip.

THEN REPORT the Overspeed device is tripped.

ESG-NRC-S1 Page 14 of 24 Rev: 01

IF directed to reset the RCIC

Crew resets Overspeed trip lAW Overspeed device, SO.BD-0001.

THEN TRIGGER ET*8.

CRS directs injecting with 'B' Only available injection SLC pump. source.

RO/PO start the 'B' SLC pump.

Crew recognizes Supp Pool Given the lowering RPV Temp Above 95°F EOP entry water level, and 'B' condition by: RHR being the only

=> OHA C8-F1 "SUPPR POOL available RHR pump, TEMP HIGH" the Crew may not place

=> Flashing 95 degree status 'B' RHR in Suppression light on 10C650C Pool cooling at this RM11 9AX833/834 alarm time.

=> Various Suppression Pool temperature indicators

Crew recognizes Supp Pool Given the LOP and the Level Above 78.5 In EOP entry unavailability of HPCI condition by: and RCIC, there is

=> OHA B1-C3 "SUPPRESSION nothing the Crew can POOL LEVEL HIILO" do to lower

=> Various Suppression Pool Suppression Pool water level indicators level at this time.

CRS recognize RPV level continues to lower and Emergency Depressurization is required.

WHEN RPV water level reaches

-129",

THEN CRS directs inhibiting ADS.

ESG-NRC-S1 Page 15 of 24 Rev: 01

RO/PO inhibit ADS lAW AB.ZZ-0001 Att. 13.

BEFORE RPV water level reaches -185",

THEN CRS directs opening five ADS SRVs.

RO/PO open five ADS SRVs lAW AB.ZZ-0001 Att. 13.

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".

IF directed to restore the 'A'

Crew recognizes start of the 'A' The restoration of the EDG to service, AND after level EDG by: 'A' EDG makes the 'A' has been restored with 'B' => Diesel engine START light Core Spray Loop EDG, => Generator breaker CLOSE available for RPV water THEN TRIGGER ET-12 AI\ID light level control.

REPORT the 'A' EDG has => OVLD/PWR FAIL lights been successfully restarted. 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.

ESG-NRC-S1 Page 16 of 24 Rev: 01

Termination Requirement:

RO/PO places 'A' RHR pump in The scenario should be Drywell Spray lAW AB.ZZ-0001.

terminated at the discretion of the Lead Examiner when:

The reactor has been depressurized

RPV water level is being maintained above -129"

Drywell Spray is initiated.

ESG-NRC-S1 Page 17 of 24 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

.IJ; ESG-NRC-S1/01 1.

Crew starts the tB' EDG by EITHER:

Pressing the 'B' EDG START pushbutton in the Control Room, 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 3.6 KIA 295003 Partial or Complete Loss of A.C. Power AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER AA 1.02 Emergency generators RO 4.2 SRO 4.3 AA 1.03 Systems necessary to assure safe plant shutdown RO 4.4 SRO 4.4 The '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 1OA401, 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 Level EA 1. 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 EA1.06 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 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 24 Rev: 01

ESG-NRC-S1 101 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT Y Loss Of Offsite Power/SBO Internal Flooding Y LOCA Loss of 1E 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 UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN KEY EQUIPMENT KEY EQUIPMENT

-- Y - 1 E 4.16KV Bus --- 120VAC 481 Inverter Hard Torus Vent _ _ _ Switchgear Room Cooler 1E 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 YIN OPERATOR ACTION Y Emergency Depressurize RPV WIO High Pressure Injection

_ _ _ Emergency Venting of Primary Containment Y Aligning RHR for Suppression Pool Cooling

_ _ _ Restore Switchgear Cooling

- - - Control Plant via Remote Shutdown Panel

_ _ _ Manually Start SW Pump

_ _ _ Cross-tie DC Charger to Portable Supply

- - - Isolate SW Pipe Rupture in RACS Room Y 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-S1 Page 20 of 24 Rev: 01

Rx Power: 100%

WorkWeek: B Risk Color: Green Activities Completed Last Shift:

Tagged BP116 EHC pump for discharge line leak repair.

Major Activities Next 12 Hours:

Release BP116 after leak repaired.

Protected Equipment:

AP116 EHC pump Tagged Equipment:

BP116 EHC pump ESG-NRC-S1 Page 21 of 24 Rev: 01

EXAMINATION SCENARIO GUIDE (ESG) REVIEWNALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of tllis form to each scenario reviewed.

SELF CHECK ESG- NRC-S1 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

___ 4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

5. The events are valid with regard to physics and thermodynamics.

6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

--- 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

___ 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 24 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 (E~(i) VALIDATIO~ (con't)

Crew Validation Rev: 00 Date Validated: 1/3/12 Validated with a 3 man crew from B Shift. Runtime 80 minutes.

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 Validated: - - - -

Validation Comments Disposition W////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////////,

ESG-NRC-S1 Page 24 of 24 Rev.: 01

SCENARIO TITLE: NRC SCENARIO 2 SCENARIO NUMBER: ESG-NRC-S2 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 75 minutes REVISION NUMBER: 01 PROGRAM: x I L.O. REQUAL

'----~

INITIAL LICENSE OTHER REVISION

SUMMARY

1. Added a malfunction to trip the RFPT operating for level control following the ATWS

2. Minor Typo changes PREPARED BY: Steven Dennis 2/15/12 Instructor APPROVED BY:

'DATE APPROVED BY:

DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS. which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an " *.")

A. Raise Power 84.5% to 90% using Control Rodsl Place C RFPT in service B. Stuck Rod (TS)

C. Flow Unit Fails Downscale wi Half Scram (TS)

D. A EHC Pump Trip E. Loss of EHC due to Filter Clogging wi Manual Scram F. ATWS G. Failure of RWCU to Auto Isolate H. Failure of HPCI Components to Auto-Initiate I. 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 ATWS. 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 29 Rev.: 01

INITIALIZE the simulator to 100% power, 3840 MWt EPU.

REDUCE Reactor power to 84.5% using reactor recirc pumps and control rods.

Stick control rod 46-47 at position 00 using ET-1.

Remove C RFPT from service and place recirc at 1000 rpm lAW HC.OP-SO.AE-0001.

Remove Crossflow from service and clear Overhead Alarm.

ENSURE A EHC Pump is in service.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

INITIAL 10-6 for Power Ascension.

APPLY Protected Equipment bezel covers to A and B RFPTs.

MARKUP HC.OP-SO.AE-0001 Section 5.7 for C RFPT.

ENSURE Move Sheets are available for Control Rods:

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 listed.

(80091396 0270)

ENSURE Data Collection is trending the following parameters as a minimum:

W/R Reactor Water Level

W/R RPV Pressure

Fuel Zone Reactor Water Level

Suppression Pool temperature COMPLETE "Simulator Ready-for-Training/Examination Checklist".

ESG-NRC-S2 Page 3 of 29 Rev.: 01

Initial

ET #

Event code: LCPNEP01 >= 300 2

Description:

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 Insert malfunction RP07 Half-core ATWS - right side RWCU isolation valve FOOl failure to auto None None Insert malfunction CUIIA close RWCU isolation valve F004 failure to auto None None Insert malfunction CUIIB close N one Insert malfunction HP 14 HPCI HV-F006 failure to auto open None None Insert malfunction HP 15 HPCI HV-8278 failure to auto open None None Insert malfunction HP 16 HPCI HV-F059 failure to auto open None None Insert malfunction HP06E HPCI aux oil pump failure to auto start None ne Insert malfunction CD034647 Control Rod 46-47 stuck Insert malfunction CD034647 after I on None ne Control Rod 46-47 stuck event 2 delete in 1 No ne Insert malfunction NM 12B to 0 on event 3 Flow summer K607B failure None None Insert malfunction TC07 A on event 4 EHC pump A trip Insert malfunction TC16 to 100.000 on None None EHC pump discharge filter plugging event 4 Insert malfunction EG 11 after 360 on None None Main generator trip event 4 Insert malfunction TCOI-to after 380 on N All turbine bypass valves fail closed event 4 N None Insert malfunction FW26Aon event 24 Trips "A" RFPT None None Insert malfunction FW26B on event 25 Trips "B" RFPT None None Insert malfunction FW29C on event 26 Trips "C" RFPT ESG-NRC-S2 Page 5 of 29 Rev.: 01

Initial @Time Event Action Description None None Insert remote PP04 to NO PP04 OD-3 Crossflow Applied None None Insert remote AN28 to NORM AN28 CROSSFLOW ALARM/TRBL Insert remote EPOI after 360 to BYPASS EPOl EOP-30I, bypass MSIV (-129")

None None on event 5 isolation interlock Insert remote EP02 after 480 to BYPASS EP02 EOP-311, bypass PCIG (-129")

None None on event 6 isolation interlock Insert remote EP38 after 180 to EP38 EOP -319, Restoring Instrument Air in None None Emergency on event 7 an Emergency Insert remote EP09 after 240 to EP09 EOP-320 (step 5.1.2), AR1 valve fuses None None REMOVED on event 8 F6A1F5A Insert remote EPlO after 240 to EPlO EOP-320 (step 5.1.4), ARl valve fuses None None REMOVED on event 8 F6BiF5B Insert remote EPI1 after 360 to EOP-320 (step 5.2.2), RPS division 1 None None INSTALLED on event 8 Insert remote EP 13 after 360 to 3 EOP-320 (step 5.2.3), RPS division 3 None None INSTALLED on event 8 jumper Insert remote EP 12 after 720 to EP12 EOP-320 (step 5.2.4), RPS division None None ALLED on event 8 jumper Insert remote EP14 after 720 to EP14 EOP-320 (step 5.2.5), RPS division 4 None None INSTALLED on event 8 jumper Insert remote EP35 after 180 to FAIL None None EP35 EOP-322 HV-F006 HPCI to CS CLOSE on event 9 ESG-NRC-S2 Page 6 of 29 Rev.: 01

Place C RFPT in service:

CRS directs BOP Operator to After the Crew assumes the place C RFPT in service feeding watch. the RPV lAW HC.OP-SO.AE 0001.

BOP Operator places C RFPT in service feeding the RPV lAW HC.OP-SO.AE-0001.

Raise Reactor Power with

CRS directs the RO to raise Control Rods: Reactor power with Control Rods After the Crew assumes the in accordance with RE guidance.

watch.

RO withdraws Control Rods in accordance with HC.OP-SO.SF 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).

NOTE: Operator may single

At the ROD SELECT MODULE, notch withdraw the rods, as simultaneously press and hold necessary, in which case the both the WITHDRAW PB CONTINUOUS WITHDRAW AND the CONTINUOUS PB is NOT used. WITHDRAW PB and observe the following:

=> The INSERT (white) light comes 01\1 momentarily.

=> The WITHDRAW (white) light comes ON and the CONTINUOUS WITHDRAW (white) light comes ON.

ESG-NRC-S2 Page 7 of 29 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 HC.OP 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 29 Rev.: 01

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

3. RPIS indicates the Control Rod is full out (48).

4. 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 HC.OP-AB.IC 0001:

~ Condition F.

RO performs actions in accordance with CRS directions:

~ Verifies no Rod Blocks are present.

NOTE: Crew may request RE Attempts to operate the drive guidance. Respond that a in both directions to withdraw signal then an insert determine the exact condition signal may be attempted. of the Control Rod.

~ Verifies drive water flow fluctuates normally.

ESG-NRC-S2 Page 9 of 29 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

Performs the following:

drive water pressure dp >300 => Raises the drive water psid. This deletes stuck rod pressure in approximately 50 malfunction. 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

RO returns the drive water pressure to the normal operating range (260-270 psid on A3015).

Flow Unit Failure:

Crew monitors Reactor power, Atthe Lead Examiners pressure, and level and ensure discretion, plant conditions are stable.

TRIGGER EJ-3 (8 APRM Flow Ensures no scram setpoints have Unit FailureDownscale). 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 29 Rev.: 01

Crew recognizes 'B', 'D', and 'F' APRMs Upscale by:

=> OHA C3-C5 "APRM SYS B UPSCALE TRIP/INOP"

> C3-D4 "APRM UPSCALE"

> APRMs B, D, and F "UPSC TR OR INOP" status lights

=> APRM B, D, and F "UPSC ALARM" status lights

> CRIDS D4305 "APRIVI CH B UPSCALE THERMAL. TRIP"

> CRIDS D4307 "APRIVI CH D UPSCALE THERMAL TRIP"

> CRIDS D4309 "APRM CH F UPSCALE THERMAL. TRIP"

Crew recognizes 'B' RECIRC LOOP FLOW SUMMER FAILURE Downscale by:

=> FLOW UNIT Band B "COMPAR" status lights

> APRM B, D, and F "UPSC ALARM" status lights

> CRIDS C026 "EITHER RBM CHANNEL UPSCALE"

> CRIDS C049 "RECIRC FLOW COMPR OUT LIMITS"

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.

ESG-I\JRC-S2 Page 12 of 29 Rev.: 01

IF directed to place the Flow

RO directs I&C to place the Unit B MODE Switch in the MODE Switch, on the applicable unlabeled position, THEN flow unit, to the "UNLABELED" CHANGE Malfunction NM12B position between STANDBY and Final value to 100%. 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 Trip of 'A' EHC Pump:

Crew recognizes trip of AP116 If left in AUTO, the After the Crew resets RPS and EHC pump by: BP116 EHC pump will addresses Tech Spec, => OHAD~F5~URBHYDR auto-start in about 50 OR, PUMP TROUBLE" seconds.

at the discretion of the Lead => OHA D3-E5 "TURB HYDR Examiner, RESERVOIR TROUBLE" TRIGGER ET*4 (Loss of EHC). => CRIDS D5542 "HYDRAULIC FLUID PUMP A TRBL" CRIDS D5575 "TURBINE HYDRAULIC FLUID PRESS LO"

=> HYDR FLUID PUMP A flashing LOW DISCH PRESS light IF dispatched to the EHC

RO/PO start the BP116 EHC Immediate Operator pump, THEN REPORT AP116 pump. action lAW motor is very hot to the touch. AB.BOP-0003.

ESG-NRC-S2 Page 13 of 29 Rev.: 01

InSight Item:

CRS implements AB.BOP-0003. There are no

EHC Header Pressure subsequent actions in tupehchd AB.BOP-0003 for a trip of a pump.

EHC Pump Disch Pressure tupehc(2) - 15

EHC Pump Filter DIP tupehcdp(2)

EHC Filter Plugging:

Crew recognizes BP116 With NO discharge filter The BP116 discharge filter will discharge filter clogging by: swap, EHC pressure begin clogging after the pump OHA D3-F5 "TURB HYDR will reach 1100# in starts. PUMP TROUBLE" about 6 minutes after CRIDS D3629 "MAIN TURB the pump trip.

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 IF directed to swap BP116

Crew directs TBEO to swap EHC header pressure discharge filters, BP116 pump discharge filters. will continue to decay.

REFER to SO.CH-0001 Section 5.20, THEN REPORT the duplex filter transfer handle will not move.

WHEN EHC pressure lowers to May direct earlier, 1200 psig, based on rate of THEN CRS directs locking the pressure drop and Mode Switch in SHUTDOWN. absence of any remaining compensatory actions.

RO locks the Mode switch in SHUTDOWN.

ESG-NRC-S2 Page 14 of 29 Rev.: 01

ATWS:

Crew recognizes Scram The half core ATWS is already Condition and Reactor Power inserted. Above 4% EOP entry condition:

=> 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 1OC651 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 29 Rev.: 01

CRS directs: Recirc RPT breakers

=> Verifying Recirc runback to may already be tripped minimum due to Main Turbine Tripping reactor recirc pumps Trip.

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 This Critical Task is not uncontrolled depressurization applicable if RPV level during A TWS conditions by never reaches -129".

preventing ADS ACTUATION. See justification for failure criteria.

REFER to the appropriate EOP

CRS directs performance of the The timing, order, and and SUPPORT Crew requests following EOPs: priority of the EOP for EOPs lAW with the EO.zZ-0320 "Defeating ARI performance may vary.

following. Validated execution and RPS Interlocks" time delays are built-in: => EO.zZ-0301 "Bypassing EOP-301: ET-5 MSIV Isolation Interlocks" EOP-311: ET-6 => EO.ZZ-0311 "Bypassing EOP-319: ET-7 Primary Containment EOP-320: ET-8 Instrument Gas Isolation EOP-322: ET-9 Interlocks"

=> EO.ZZ-0319 "Restoring Instrument Air in an Emergency" EO.ZZ-0322 "Core Spray Injection Valve Override" ESG-NRC-S2 Page 16 of 29 Rev.: 01

CRS directs terminating and preventing injection to the RPV with the exception of:

> SLC

> CRD RCIC

RO/PO terminate and prevent injection from HPCI, RHR and feedwater/condensate lAW AB.ZZ-0001 :

> Attachment 16 (1 OC650)

> Attachment 17 (1 OC651)

Trip of RFPT

CRS directs maintaining RPV Typically, the lower end water level between -50" and of the level band is set Once the crew has re -185" with feedwater and/or above -129".

established level control with RCIC.

feedwater, observe which RFPT is in service and then trip

Crew recognizes trip of operating it as follows: RFPT and establishes flow with a RFPT in standby or RCIC ET* 24 - Trips "A" RFPT ET Trips "6" RFPT ET Trips "C" RFPT

CRS directs bypassing the RWM and commencing manual rod insertion.

RO/PO bypass RWM and insert control rods lAW RE.AB.ZZ-0001 Att.2.

IF EOP-322 is complete before Typically, the lower end RPV water level reaches -129", of the level band is set THEN CRS directs maintaining above -129",

RPV water level between -50" and -185" with HPCI and RCIC.

ESG-NRC-S2 Page 17 of 29 Rev.: 01

IF EOP-322 is NOT complete EOP-322 states:

before RPV water level reaches "HPCI injection flow

-129", should be limited (or THEN CRS directs maintaining secured, if not required water level between -129" and to maintain RPV level

-185" with HPCI and RCIC. above T AF) while this (After EOP-322 is complete, and procedure is in injection through the Core Spray line progress."

has been terminated, the CRS may Hope Creek has use the full level band allowed by defined the intent of EOP-101A. In this case, with "above TAF" in this Suppression Pool temperature statement to mean no below 110°, the upper RPV level higher than -129".

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 Pump

~ HPCI HV-F006

~ HPCI HV-8278

~ HPCI HV-F059

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 EOP 322 in Control Room as follows:

ESG-NRC-S2 Page 18 of 29 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 CRD

~ PCIG to SRVs

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 29 Rev.: 01

IF directed, Restoring PCIG to THEN RO/PO restore PCIG to the SRVs lAW SRVs lAW AB.ZZ-0001 Att. 9 AB.ZZ-0001 Att. 9 is also equivalent to the Control Room actions in EOP-311.

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 the Crew has reset

WHEN EOP-320 Section 5.1 and RPS, 5.2 are complete, THEN DELETE Malfunction THEN the Crew implements RP07 to allow full rod insertion EOP-320 Section 5.3 and reset on the next scram. RPS.

At the Lead Examiners

WHEN OHA C6-E4 clears, discretion, MODIFY Insight THEN the Crew initiates a Item Iclsdv to accelerate manual scram lAW EOP-320 draining of the SDV. Section 5.3.

ESG-NRC-S2 Page 20 of 29 Rev.: 01

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.

Termination Requirement:

CRS exits EOP-101A, enters The scenario may be . EOP-101.

terminated at the discretion of the Lead Examiner when:

RPV Level is being maintained above--161" AND

All rods are fully inserted ESG-NRC-S2 Page 21 of 29 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-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 01 1.

CREW prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUATION.

KIA 218000 Automatic Depressurization System A4 Ability to manually operate and/or monitor in the control room:

A4.04 ADS inhibit RO 4.1 SRO 4.1 Given the current ATWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor. EOPs direct this action under the current conditions.

This critical task is only applicable if RPV water level goes below -129". Failure to satisfactorily complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure to less than 100 psig.

2.

RO/PO isolate RWCU HV-F001 OR HV-F004 following SBLC pump start.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. 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 Unknown EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA2.02 Reactor water level RO 4.1 SRO 4.2 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 29 Rev.: 01

4.

CREW fully inserts all control rods via RMCS and/or manual scram(s) lAW HC.OP-EO.ZZ-0320.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. 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 29 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 1E 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 UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN KEY EQUIPMENT YIN KEY EQUIPMENT 1E 4.16KV Bus 120VAC 481 Inverter Hard Torus Vent Switchgear Room Cooler 1E 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 Injection

_ _ _ Emergency Venting of Primary Containment Y Aligning RHR for Suppression Pool Cooling

_ _ _ Restore Switchgear Cooling Control Plant via Remote Shutdown Panel

_ _ _ 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-S2 Page 25 of 29 Rev.: 01

Rx Power: 84.5%

WorkWeek: A Risk Color: Green Activities Completed Last Shift:

Reduced power to 84.5% for C RFPT vibration troubleshooting.

Commenced Power ascension lAW 10-6 C RFPT is in Recirc at -1000 rpm.

Major Activities Next 12 Hours:

Return to 100% power.

Protected Equipment:

Aand B RFPTs Tagged Equipment:

None ESG-NRC-S2 Page 26 of 29 Rev.: 01

EXAMINATION SCENARIO GUIDE REVIEW N ALiDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF CHECK ESG- NRC-S2 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

4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding

--- event has occurred.

5. The events are valid with regard to physics and thermodynamics.

___ 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

___ 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-S2 Page 27 of 29 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 (con't)

Crew Validation Rev: 00 Date Validated: 1/14/12 Validated with one 3 man crew from B Shift. Runtime was 75 minutes.

Validation Comments Disposition IW//////&//$///////$/////$////////////////////////////////////////////////////~///// ////&/////////////$////////$///&///////$//$$/////////$////////~

ft RPV level control by operators kept level above - 129 Added MT trip and TBV fail closed after 6 minutes on ET-4 to drive pressure control to SRVs.

Crew Validation Rev: Date Validated: ----

Validation Comments Disposition

'//7///////////////////////////////////$/////////////////$////////////////$/////////$/////////////////$///$//////////////////////

/////////////////////////////////////h ESG-NRC-S2 Page 29 of 29 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}([ ~:V-----

LORT Group Lead or Designee Jdr/Jz DATE APPROVED BY: ~~ Ij~c2 DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Critical tasks within this examination scenario guide are identified with an " *.")

A. Raise reactor power with control rods B. IRM "0" fails upscale C. MSL Drain HV-F019 Failure D. RFPT "A" trips E. Main Steam Tunnel leak with Fuel Leak F. 2 Control Rods stick at position 48 G. Failure of MSIVs and MSL Drains to auto close H. 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 25 Rev: 01

INITIALIZE the simulator to 3% power IIC, BOL. Pull step 409 INSERT control rods through step 409.

ENSURE both MS Tunnel Coolers in service.

INITIAL IO.zZ-0003 Section 5.3 up to and including step 5.3.43.

ENSURE Insight is trending the following parameters:

Reactor power

W/R Reactor Water Level

W /R Reactor Pressure COMPLETE the Simulator Ready for Training/Examination Checklist.

ZCRPSUDN >= 1.0 6

Reactor Mode Switch in Shutdown.

Event code: LCPNEP01>=200&ZCRPSUDN>=1 12

Description:

Deletes malfunction when drive pressure is 200 psig with MS in SO.

Event code: LUIVI.;:II.;:lOv >= 1.0 14

Description:

ABHVF016 CLOSE PB pressed Event code:

15

Description:

Event code:

16 cription: Main Steam Tunnel Temp> 160 F and MS in SO fails TBV #1 Event code: *

Description:

ESG-NRC-S3 Page 3 of 25 Rev: 01

ne Insert malfunction CD032259 Control Rod 22-59 stuck None Insert malfunction CD032655 Control Rod 26-55 stuck None None Insert malfunction MS 19D MSIV F022D fail to auto isolation None None Insert malfunction MS20D MSIV F028D fail to auto isolation 9RX621, OG RMS Offgas Pretreatment None None Insert malfunction RM9621 to 1.04000 ChanA 9RX622, OG RMS - Offgas Pretreatment None None Insert malfunction RM9622 to 1.25000 ChanB Insert malfunction NM06D to 100.00000 None None IRM channel D reads high or low on event 1 None None Insert malfunction FW26A on event 3 105 trip Insert malfunction MS04D to 100.00000 None None Steam line D leak in tunnel on event 5 Insert malfunction CR01 to 100.00000 on None None Fuel cladding leak event 5 Insert malfunction CD09 A after 60 to None None Drive water flow control valve F002A failure 0.00000 on event 12 Insert malfunction CD09A after 5 delete in None None Drive water flow control valve F002A failure Ion event 11 Insert malfunction CD032259 after 1 None None Control Rod 22-59 stuck delete in 1 on event 6 Insert malfunction CD032655 after 1 None None Control Rod 26-55 stuck delete in 1 on event 6 None None Insert malfunction TCOl-l on event 16 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 Action Description None None Insert remote HV12 to RUN on event 5 Steam Tunnel Unit Cooler BV216 Insert remote CD 10 after 5 to ON on event None None COl 0 CRD FCV B 11 Insert remote CD09 after 5 to OFF on None None CD09 CRD FCV A event 11 MS11 Main Steam Line Drain Valve, AB None None Insert remote MS 11 to TAGGED HV-F016 MS11 Main Steam Line Drain Valve, AB None 14 Insert remote MS11 to UNTAGGED HV-F016 Insert remote MS12 to TAGGED on event MS12 Main Steam Line Drain Valve, AB None None 15 HV-F019

OP*HC*1 03*1 05 Revision 0 Page 6 of 25 None None Insert override 3A107 A LO to Orf HV-F016 OPEN-CTMT INBD STEAMLINE None None Insert override 3A107 E LO to On DRAIN HEADER ISLN-INBD (LO)

HV-F016 CLOSE-CTMT INBD STEAMLINE None None Insert override 3A107 F LO to Off DRAIN HEADER ISLN-INBD (LO)

HV-F016 OPEN-CONTAINMENT None None Insert override 7DS 11 A LO to On ISOLATION VALVES-MAIN STEAM DRAIN LINE HV-FO 16 CLOSED-CONTAINMENT None None Insert override 7DS 11 B LO to Off ISOLATION VALVES-MAIN STEAM DRAIN LINE OUTBD-CONT AINMENT ISOLATION None None Insert override 7DS 1 B LO to Off V ALVES-MOV OVLDlPWR FAIL (LO)

None 14 Remove override lOS 111 C LO to On HV-F016A OPEN (LO)

None 14 Remove override lOS 111 B LO to Ofr HV-F016A CLOSED (LO)

HV-F016 OVLD/PWRFAIL-CTMT INBD None 14 Remove override 3AlO7 A LO to Off STEAMLINE DRAIN HEADER ISLN-INBD HV-F016 OPEN-CTMT INBD STEAMLINE None 14 Remove override 3AI07 E LO to On DRAIN HEADER ISLN-INBD (LO)

HV-F016 CLOSE-CTMT INBD STEAMLINE None 14 Remove override 3AI07 F LO to orr DRAIN HEADER ISLN-INBD (LO)

HV-FOI6 OPEN-CONTAINMENT None 14 Remove override 7DS 1 to On ISOLATION VALVES-MAIN STEAM DRAIN LINE HV-F016 CLOSED-CONTAINMENT None 14 Remove override 7DS 11 B LO to Orf ISOLATION V ALVES-MAIN STEAM DRAIN LINE

Raise Reactor Power with

CRS directs the RO to raise Control Rods: Reactor power with Control Rods After the Crew assumes the in accordance with RE guidance.

watch.

NOTE: LPRM downscale

RO withdraws Control Rods in alarms can be expected. As accordance with HC.OP-SO.SF RE, inform crew alarms are 0001 and CRS directions.

expected for this rod pattern. => 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).

NOTE: Operator may single

At the ROD SELECT MODULE, notch withdraw the rods, as simultaneously press and hold necessary, in which case the both the WITHDRAW PB CONTINUOUS WITHDRAW AND the CONTINUOUS PB is NOT used. 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 25 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 HC.OP 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.

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

ESG-NRC-S3 Page 8 of 25 Rev: 01

3. RPIS indicates the Control Rod is full out (48).

4. Proper response of the Nuclear Instrumentation while withdrawing the Control Rod.

Indicates the completion of the movement on the Pull Listing.

'0' IRM Fails Upscale:

Crew recognizes IRM failure by:

Afterreactor power has been OHA C3-A5 "REACTOR raised, SCRAM TRIP LOGIC B2" OR, "'> OHA C3-C3 "IRM C/D/G/H at the discretion of the Lead UPSCALE INOPITRIP" Examiner, TRIGGER ET-1. OHA C3-D3 "IRM UPSCALE" NOTE: Trigger when there is OHA C5-A1 "NEUTRON NO rod motion to prevent Rod MONITORING SYSTEM Drift alarm and actiOns. 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.

ESG-NRC-S3 Page 9 of 25 Rev: 01

Crew contacts Operations Management.

Note: This AB covers the same

CRS implements AB.IC-0003:

actions as AB-IC-0004 and ==> Condition B may not be performed.

CRS recognize the following For both TIS, still meet Tech Specs apply: the Minimum Operable

==> Reactor Protection System Channels per Trip Instrumentation Function. Tracking 3.3.1 Action statement only.

==> Control Rod Block Instrumentation 3.3.6 MSL Drain AB*HV-F019

Crew recognizes AB-HV-F019 Failure: failure by:

After reactor power has been ==> OHA C8-E5 "MAIN STEAM raised, STP/ORN VALVE O/PF "

OR, ==> 02285 MS DR OUTBO ISO V at the discretion of the Lead HV-F0190PF Examiner, TRIGGER ET*15. ==> CONTAINMENT ISOLATION (HV-F019 Breaker trips). VALVE O/PF

==> 04675 CONT ISLN MOV VLV OPF

RO implements HC.OP-AR.ZZ CRS may refer to 0011: AB.CONT-0002 but no

==> C8-E5 actions are applicable.

RO implements HC.OP-AR.ZZ 0012:

==> 01-B3

CRS recognize the following Tech Specs apply:

==> Primary Containment Isolation Valves 3.6.3 ESG-NRC-S3 Page 10 of 25 Rev: 01

'A'RFPT Trip:

Crew recognizes AP1 01 RFPT TRIGGER ET-3 at the trip by:

discretion of the Lead => OHA B3-E1 "RFP TURBINE Examiner. TRIP"

=> RFP "A" TURB MODE TRIP IF the reactor scrams, THEN TRIGGER ET*5 Main Steam light

=> OHA B3-F1 DFCS TROUBLE Tunnel Leak.

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.

IF dispatched to investigate the

Crew dispatches TBEO and trip of AP1 01, Maintenance to investigate the THEN REPORT: trip of the AP101 RFPT.

The RFPT is slowing down.

There is nothing else obviously wrong at the RFPT.

ESG-NRC-S3 Page 11 of 25 Rev: 01

Steam I~ak in the steam

Crew recognizes Steam Tunnel tunnel/Fuel Leak: temp rising:

=> A2541 Stm Tunnel Clr Inlet TRIGGER EI;~~(~t~arh lea~i'in temp in alarm.

the Steam Tunnel) when th~ . => OHA D3-A3 MN STIVl/RWCU crewCbmplet~sactions for the AREA TEMP HI trip of'A' R.FPTor at the Lead Examiner's discretion. .

CRS directs PO to implement HC.OP-AB.BOP-0005, Condition A:

PO implements HC.OP-AB.BOP 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 25 Rev: 01

~ Ensure proper positioning of IF dispatched to perform BOP-0005 actions, THEN Steam Tunnel Supply Ar-.,ID REPORT: Return Backdraft dampers

~ Ensure both Steam Tunnel Action A3: Steam Tunnel cooling Fans in-service at supply and return back draft panel 1EC281.

dampers - both sets are open. ~ Ensure GU-HD9395A AND Action A5: Place Both Steam GU-HD9395B are closed.

Tunnel cooling fans in service by placing REMOTE FUNCTION HV11 and HV12 in RUN.

Action A6: GU-HD9395A and 9395B are closed.

CRS assigns a crewmember to monitor Steam Tunnel temperature.

CRS implements HC.OP 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 HC.OP AB.CONT-0004, Condition C.

~ Monitor for indications of a steam leak NOTE:

Crew responds to RM-11 "High Alarm" for 9RX620 for the Tech This alarm may not be Support Center ARM.

received.

High alarm is 2.5 mRlhr.

ESG-NRC-S3 Page 13 of 25 Rev: 01

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 HC.OP AB.BOP-0005 Retainment Override.

The CRS may take

CRS directs a manual Scram conservative action and scram when Steam Tunnel temperature before 145 degrees. 2:145 degrees lAW the Retainment Override.

RO takes actions to manually scram the reactor lAW HC.OP AB.ZZ-0001.

PO takes action to control, restore and maintain RPV level with Feedwater.

CRS implements HC.OP-EO.ZZ 0101A based on entry condition of ~12.5" 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 25 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 25 Rev: 01

RO determines that two Control Rods are not fully inserted, and reactor NOT shutdown under all Can use "List Rods" conditions without boron and on RWM CONFIRM informs CRS: SHUTDOWN

=> RWM "CONFIRM screen to identify SHUTDOWN" screen rod not inserted.

=> 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.

IE directed to manually scram

CRS directs RO to attempt to the rods locally from the SRI insert the stuck rods.

Test switches, THEN REPORT that high radiation at those 2 HCUs prevents access to the test switches at this time.

RO determines CRD drive water pressure is too low to drive the stuck control rods and informs CRS:

ESG-NRC-S3 Page 16 of 25 Rev: 01

RO determines CRD FCV failed closed by observing:

~ HV-F002A green light illuminated and red light extinguished.

~ Drive Water Pressure not responding to operator action.

IF dispatched to investigate the

Crew dispatches RBEO and CRD FCV, THEN REPORT the Maintenance to investigate the A A FCV is closed. CRD FCV.

IF directed to swap the CRD

RO directs RBEO to swap FCV FCV, THEN TRIGGER ET-11 to standby FCV.

and REPORT the B FCV is in service.

RO establishes Drive Water DP approximately 260-450 psid lAW HC.OP-AB-ZZ-0001 Attachment 18.

NOTE: WHEN Drive Water

RO selects and drives both pressure is > 200 psid, THEN control rods in to 00.

ENSURE Malfunctions CD032259 and CD032655 are deleted.

CREW fully inserts all control rods via RMCS.

RO reports the Reactor is shutdown.

CRS exits EOP-101A and re enters EOP-101.

RO/PO coordinate transfer of Reactor Pressure and RPV level control.

ESG-NRC-S3 Page 17 of 25 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 25 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! 01 1.

Crew closes at least one MSIV in each steam line and MSL drain valve F016 before reactor pressure drops below 345 psig.

K/Al239001 Main and Reheat Steam System A4 Ability to manually operate and/or monitor in the control room:

A4.01 MSIVs R0:4.2 SRO: 4.0 Tech Spec 3.4.6.1, Reactor Coolant System 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:

AA1.01 CRD Hydraulics RO 3.8 SRO 3.9 AA1.03 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 25 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 1E 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 UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY EQUIPMENT 120VAC 481 Inverter

- - - 1E 4.16KV Bus ---

Hard Torus Vent _ _ _ Switchgear Room Cooler 1E 125VDC Bus RCIC

_ _ _ SACS Loop

- - - SSW Ventilation

_ _ _ SSW Loop SSW Pump

_ _ _ AlBRHR _ _ _ 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

_ _ _ 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-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 25 Rev: 01

EXAMINATION SCENARIO GUIDE (ESG) REVIEWNALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF CHECK ESG- NRC-S3 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

___ 4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

5. The events are valid with regard to physics and thermodynamics.

--- 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

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-S3 Page 23 of 25 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-53 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-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////////////////// /////.I/0"///////hW///////////////////////

Add status of Feedwater to Turnover Sheet -cA-"g>L.r-'..e..::..e.c...:E:::..:d:..:..it:..:..o:....ria=I'-;;:.; r - - - - - - - - - - - - - - - - - - -

nd Slow MS Tunnel temp rise. Too fast. Agree. Placed 2 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 PROGRAM: x I L.O. REQUAL X I INITIAL LICENSE

'---_-----" OTH ER REVISION

SUMMARY

1. Removed Recirc PP runaway and high vibration malfunction and replaced with multiple seal failure on'S' Recirc PP.

2. Added malfunction for an ADS valve failure to open malfunction during the Emergency Depressurization.

PREPARED BY: Steven Dennis 2/15/12 Instructor APPROVED BY: 9JJCJ1L-.

LORT Group Lead or Designee r;) /J~/J),

DATE APPROVED BY: :,v1;Ur ~Z DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an "*.")

A. Raise reactor power with control rods B. Control rod 26-03 drifts out (TS SRO)

C. Swap SSW Pumps D. SSW Pump Malfunction (TS SRO)

E. Single Reactor Recirc Pump Dual Seal Failure F. Fuel Failure with Scram G. Torus Leak I Emergency Depressurization H. RHR HX Inlet Valve F047B fails closed I. 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 27 Rev.: 05

INITIALIZE the simulator to 3% power, MOL.

INITIALIZE the simulator to 3% power IIC, BOL. Pull step 409 INSERT control rods through step 409.

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 pump.

INITIAL IO.ZZ-0003 Section 5.3 up to and including step 5.3.43.

INITIAL HC.OP-SO.EA-0001 for pump swap.

At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

(800913960270)

ENSURE Data Collection is trending the following parameters as a minimum:

W 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) <= 0.0 12

Description:

Detects 'B' MSL isolation

. Event code: ! msvf022(3) <= 0.0 I msvf028(3) <= 0.0 13

Description:

Detects 'C' MSL isolation Event code: msvf022(4) <= 0.0 I msvf028(4) <= 0.0 14

Description:

Detects 'D' MSL isolation Event code: msvfdrn1(1) <= 0.0 I msvfdrn1(2) <= 0.0 15

Description:

F016 or F019 shut II Detects MSL drain isolation Event code: 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' MSL Event code: et_array(12) >= 1.0 & et_array(15) >= 1.0 18 *

Description:

Removes high radiation from 'B' MSL Event code: eCarray(13) >= 1.0 & eCarray(15) >= 1.0 19

Description:

Removes high radiation from 'C' MSL Event code: et_array(14) >= 1.0 & eCarray(15) >= 1.0 20

Description:

Removes high radiation from 'D' MSL

Event code: *Pclsp <= 119

Description:

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 I None Insert malfunction RR05B on event 2 Recirc pump BP201 inboard seal failure None I None Insert malfunction RR06B in 60 on event 2 Recirc pump BP201 ouboard seal failure 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 on None 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

T Insert malfunction RM9511 after 1 to None 9RX51 1, MSL 'C' - Main Steam Line Chan C 119.00000 in 300 on event 16 Insert malfunction RM9512 after 1 to None '" 122.00000 in 300 on event 16 9RX512, MSL 'D' - Main Steam Line Chan D 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 I None None 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 None None event 27 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-YARD DUMP None None Insert override 5A8 E LO to Off VALVE (LO)

B-YARDDUMP i None None Insert override 5A8 F LO to On VALVE (LO)

HV -2256A OPEN-LOOP A-YARD DUMP None None i Insert override 5A3 E LO to Off VALVE (LO)

HV-2256A CLOSE-LOOP A-YARD DUMP None None Insert override 5A3 F LO to On VALVE (LO)

ESG-NRC-S4 Page 6 of 27 Rev.: 05

Raise Reactor Power with

CRS directs the RO to raise Control Rods: Reactor power with Control Rods After the Crew assumes the in accordance with RE guidance.

watch.

NOTE: LPRM downscale

RO withdraws Control Rods in alarms can be expected. As accordance with HC.OP-SO.SF RE, inform crew alarms are 0001 and CRS directions.

expected for this rod pattern. => 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).

NOTE: Operator may single

At the ROD SELECT MODULE, notch withdraw the rods, as simultaneously press and hold necessary, in which case the both the WITHDRAW PB CONTINUOUS WITHDRAW AND the CONTINUOUS PB is NOT used. 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 27 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 HC.OP 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.

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

3. RPIS indicates the Control Rod is full out (48).

ESG-NRC-S4 Page 8 of 27 Rev.: 05

4. Proper response of the Nuclear Instrumentation while withdrawing the Control Rod.

Indicates the completion of the movement on the Pull Listing.

Rod Drift:

Crew recognizes 26-03 rod drift Will occur after rod 26-03 is by:

selected and withdrawn. => OHA C6-E3 "ROD DRIFT"

=> Amber DRIFT light for 26-03 Pre.ln~serted (Control Rod 26*

on Full Core Display

=> RWM Drifting Rod display 03 Drifts Out).

"DR 26-03"

=> CRIDS C078 "ROD DRIFT ALARM"

=> Slight rise in reactor power

=> Various rod position indications

CRS implements AB.IC-0001: CRS may refer to

=> Condition C AB.RPV-0001 but no actions are applicable.

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" IF asked, THEN as Reactor => RO applies a continuous Engineer, provide guidance to control rod insert signal under CRS to continuously insert rod the direction of the Reactor 26-03 to 00 if possible. Engineer AND SM/CRS.

=> RO releases insert signal.

=> IF the control rod continues to drift out or does not respond to the insert signal THEN, ESG-NRC-S4 Page 9 of 27 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 26-03 HCU, HCU.

THEN REPORT the HCU appears normal.

ESG-NRC-S4 Page 10 of 27 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:

1. DELETE malfunction

CRS directs disarming the 26-03 directional control valves within CD022603 (drifting rod) and one hour.

allow 26-03 to settle back to 00.

2. TRIGGER ET-26 (stuck rod)

3. TRIGGER ET-27 (accum trouble)

4. !E isolating Scram pilot Air BF-V116 (as in Isolating for Maintenance section),

THEN TRIGGER ET-28.

5. AFTER OHA C6-C3 (CRD TEMP HI) is received, THEN DELETE Malfunction AN-C6C3

6. 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 HC.OP 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 27 Rev.: 05

As Yard operator, report field

PO removes "G" SSW from actions are complete for service using HC.OP-SO.EA starting "An SSW pump. 0001 section 5.6.5.

SSW Pump "Au Malfunction:

Crew recognizes "An SSW At the discretion of the lead strainer Hi OP to the strainer by:

Examiner, => A1-B1 SSWS INTAKE A TRIGGER ET-1 (Service water TROUBLE pump A marsh grass intrusion => 03857 SSW STRAINER A to 50%). OIFF HI HI STRAINER PRESSURE DIP

=> 05507 SSW STRAINER A DRIVE OPF WHEN requested as Yard

CRS implements Operator, REPORT "A" SSW AB.COOL-0001 :

pump strainer is not rotating => Condition A and the screen is covered with

=> Condition 0 grass.

The breaker for the strainer is tripped and will not reset.

!E the crew does not remove

Crew removes "A" SSW pump the "A" SSW pump from from service lAW:

service, THEN TRIGGER ET*6 => AB.ZZ-0001 AU 19 to trip the pump.

Crew places "C" SSW pump in service lAW:

=> AB.ZZ-0001 Att 19

CRS recognize the following 30 day LCO Tech Spec applies:

=> Station Service Water 3.7.1.2 Action a

Crew contacts maintenance.

ESG-NRC-S4 Page 12 of 27 Rev.: 05

"B" Reactor Recirc Pump

Crew recognizes first stage seal Inboard Seal Failure: failure on 'B' Recirc pump by:

TRIGGER ET-2, five minutes => OHA C1-F5 COMPUTER PT after Tech Specs have been IN ALARM addressed OR at the discretion => CRIDS 02927 "RECIRC of the Lead Examiner. PUMP B SEAL STAGE FLOW"

=> Rising second stage seal Reactor Recirculation Pump pressure "B"Outboard Seal Failure:

60 seconds after Inboard Seal fails

CRS implements AB.RPV-0003:

Condition 0 IF dispatched to report local seal pressures on 77' Rx Bldg, THEN REPORT readings consistent with CRIDS (Page 85),

OR the following Monitor Items:

(Monitor Items are psia)

'B' Recirc Inbd (#1) Seal rrpsI1(2) - 15 = psig

'B' Recirc Outbd (#2) Seal rrpsI2(2) - 15 = psig

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 27 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 and temperatures

~ 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 27 Rev.: 05

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.

Fuel Cladding* Failure:

Crew recognizes fuel clad IF the Crew scrams 10 minutes after the Recirc damage by: during the Recirc Pump Runaway, ~ RM11 9RX621/622 Offgas Runaway, OR, Pretreatment Alarms THEN the Fuel Failure at the Lead Examiners ~ OHA C6-A3 "MN STM LINE will automatically be discretion, RADIATION HI" inserted.

TRIGGER ET-8(tuel cladding ~ RM11 9RX509/510/511/512 MSL Radiation levels failure). Alert alarms and readings will reach 3xNFPB

~ CRI DS Page 37 MSL approximately 5 Radiation readings minutes after the failure begins.

CRS implements AB.RPV-0008: If the plant is shutdown,

~ Condition A Condition B actions are

~ Condition B not applicable.

~ Condition C

RO reduces power lAW RE Guidance (Reverse Pull Sequence)asnecessa~.

ESG-NRC-S4 Page 15 of 27 Rev.: 05

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 ENSURE MSL Radiation

RO/PO close MSIVs, HV-F016 Malfunctions RM9509-RM9512 and HV-F019 steam line drains.

ramp down to <20 when the Main Steam Lines AND drain lines are isolated.

ESG-NRC-S4 Page 16 of 27 Rev.: 05

The Crew inserts a manual The Critical Task is scram and closes at least one satisfied as long as all MSIV in each Main Steam Line lines are isolated. For and the HV-F016 or F019 drain instance, closing the valve before MSL radiation has HV-F016, but NOT the been above the Hi-Hi setpoint HV-F019 satisfies for three minutes. isolation of the F016/F019 drain line.

RECORD time (if any) between OHA C6-B2 and reactor scrammed with main steam and drain lines isolated:

TIME: _ _ __

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.

UnisolableTorus Leak:

Crew recognizes torus leak by: It will take The Torus Leak willbegin three => OHA D3-C2 "REACTOR approximately 12.5 minutes afteftheMSIVs are BLDG SUMP LVL HIILO" minutes for Supp Pool isolated. => OHA B1-C3 "SUPPRESSION level to reach 38.5".

POOL LEVEL HI/LO"

=> Various Suppression Pool level indicators lowering IF dispatched to the Torus

Crew dispatches personnel to Room to look for a leak, inspect Rx Bldg '54 and Torus THEN REPORT there is a Room for leak.

large, unisolable leak at on the bottom of the torus at Az. 180.

There is about one inch of water on the torus room floor.

ESG-NRC-S4 Page 17 of 27 Rev.: 05

IF asked,

Crew contacts RWEO and THEN REPORT both sump informs them of leak.

pumps are running in both the North and South RB Floor Drain sumps.

Crew recognizes Supp Pool Level Below 74.5 In EOP entry condition by:

OHA B1-C3 "SUPPRESSION POOL LEVEL HI/LO"

=> Various Suppression Pool level indicators

CRS implements EOP-102.

IF directed to implement

CRS directs MIU to the torus EOP-315 then, lAW EOP-315.

WHEN torus level reaches 45",

INSERT Remote Functions CS01-CS04 to make-up as directed.

Do NOT open more than two valves.

RO/PO coordinate implementation of EOP-315 with NEO.

RHR Pump Room Flooded:

Crew recognizes Reactor Bldg The 'A' RHRRoom flooded Room Floor Level Above Max alarm will be receivedabout4 Normal Op EOP Entry Condition minutes after the Torus.Leak by:

starts. => 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 LVITE indication ESG-NRC-S4 Page 18 of 27 Rev.: 05

IF dispatched to 'A' RHR room,

CRS implements EOP-103.

THEN, AFTER OHA A6-A5 "RHR ROOM FLOODED" is received, REPORT there is about two inches of water on the floor and it appears to be coming up through a floor drain.

WHEN it is determined that Supp Pool level cannot be maintained above 38.5",

THEN CRS determines Emergency Depressurization is required.

CRS implements EOP-202.

RO/PO opens five ADS SRVs 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 RECORD Supp Pool Suppression Pool water level level at which ADS was cannot be maintained above initiated.

38.5" and initiates opening of five SRVs before Suppression LEVEL: _ __

Pool level reaches 3~.

RO/PO maintain RPV level as directed by CRS.

LE Supp Pool level drops to 30",

THEN the Crew ensures HPCI is secured.

ESG-NRC-S4 Page 19 of 27 Rev.: 05

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.

RHR HX INLET Valve F047B

Crew recognizes RHR HV-F047B Fails closed: is failed closed.

The 'A' RHR HX InletValve HV-F047B will fail Ciosed when the Torus leak begins.

RO/PO places A RHR in Suppression Pool Clg lAW AB.ZZ-0001 Att. 3.

Termination Requirement:

The scenario mCiybe ....

terminated at the discretion of the Lead Examiner when the RPV has been degressyrized lAW EOP-202. ~ ....

ESG-NRC-S4 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 05 1.

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.

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 3~.

KIA 295030 Low Suppression Pool Water Level EA2 Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL EA2.01 Suppression Pool level RO 4.1 SRO 4.2 KlA 218000 Automatic Depressurization System A.4 Ability to manually operate and/or monitor in the control room:

A4.01 ADS Valves RO 4.4 SRO 4.4 If Suppression Pool Level drops below 38.5", the downcomer pipes are uncovered and the Pressure Suppression function of the Primary Containment is lost. EOPs direct Emergency Depressurizing if Suppression Pool level cannot be maintained above 38.5", Requiring the Emergency Depressurization to be initiated before Supp Pool Level reaches 30" allows the Crew three minutes to implement this action in this scenario.

ESG-NRC-S4 Page 22 of 27 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 Y Internal Flooding LOCA --

Loss of 1E ACIDC 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 UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY 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: 3%

WorkWeek: A Risk Color: Green Activities Completed Last Shift:

"An RFPT is in service in MAN with the SULCV in AUTO Single Element Control "8" RFPT is warmed up and available at 1000 rpm.

Major Activities Next 12 Hours:

Swap in service SSW pumps from "C" to "N'.

The "An SSW Traveling Screen has been run for >30 minutes.

SSW Chlorination has been removed from service.

Protected Equipment:

None Tagged Equipment:

'8' EHC Pump is tagged for maintenance.

ESG-NRC-S4 Page 24 of 27 Rev.: 05

EXAMINATION SCENARIO GUIDE REVIEWNALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF CHECK ESG- NRC-S4 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

4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding

--- event has occurred.

5. The events are valid with regard to physics and thermodynamics.

___ 6. Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate time frame and implements procedures and/or corrective actions).

___ 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

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 27 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: 2 Validated with 3 man crew. Runtime was 60 minutes.

Validation Comments Disposition W//////////////////////////////////////////////////////////Z0/////////////// /////////////////////////////////////////////////////////////////////////////// //////&&///////fi Sign prereqs in SSW SOP. _A,-: -,-,-cc:. .;eCLP.. :. :te=---=d;-:-.=-=--=----:-:-:----:---;---:-c:--~--;------------

Run SSW pump swap before rod movement. Accepted. ESG written to do either first.

MSL Rads came up hard on manual scram. Corrected ramp rate for ET-16 to be the same as ET-8.

Crew Validation Rev: Date Validated: - - - -

Validation Comments Disposition W//////////////////////////////////////////////////////////////////////////// /////////////////////////////////////////////////////////////////// //////////////////////////////fl:,

ESG-NRC-S4 Page 27 of 27 Rev.: 05

SCENARIO TITLE: Loss of 100410, Turbine Vibrations, LOP/LOCA, Rx Flooding SCENARIO NUMBER: ESG-01S EFFECTIVE DATE: Effective when approved EXPECTED DURATION: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8 minutes REVISION NUMBER: 19 PROGRAM: x 1 L.O. REQUAL X 1 INITIAL LICENSE

'---_-----'I OTHER REVISION

SUMMARY

1. Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax.

2.

PREPARED BY: Archie E. Faulkner 6/6/11 Instructor DATE APPROVED BY: 0lf~

LORT Group Lead or Designee

!tJ!b!l/

t DATE APPROVED BY:

Sha.ralions supe~isor or Designee

/V;?I;/I 7

DATE

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an "*.")

A. Loss of 100410 125VDC 1E Bus B. Main Turbine High Vibration C. Loss of Offsite Power D. LOCA E. Loss of RPV Level Indication The scenario begins with the plant at 100% power. The 100410 125VDC 1E 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 31 Rev: 19

INITIALIZE the simulator to 100% power, MOL.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

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 listed.

(800913960270)

COMPLETE the Simulator Ready for Training/Examination Checklist.

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 Description None Insert malfunction ADO 1 Failure of ADS valves to open None None malfunction AD06 Failure of low-low set valves to Ann Diesel generator B emergency start signal None None Insert malfunction DG07B failure RHR System D auto injection failed to None None Insert malfunction RH08D energized None None Insert malfunction ED 11 A on event 1 Loss of 125 VDC class IE bus 10D41O Insert malfunction TUl208 from 75.00000 None None Turbine bearing #8 high temperature to 100.00000 in 720 on event 3 Insert malfunction TUl508 from 6.00000 None None Turbine bearing #8 vibration high to 13.00000 in 720 on event 3 Insert malfunction MCOIA after 300 on None None Complete Loss of Vacuum event 7 None None Insert malfunction EG12 on event 4 Loss of all off site power Insert malfunction RR31A2 to 3.00000 in Recite loop A large break [V] (lOo/a-6000 None None 600 on event 4 gpm, 100%~60000 gpm)

Insert malfunction CD09 A after 90 to None None Drive water flow control valve F002A failure 75.00000 on event 6 None None Insert malfunction CD09B to 0 on event 6 Drive water flow control valve F002B failure None None Insert malfunction RR39B to 0 on event 9 LT-3622B PM1S Shutdown Range Failure None None Insert malfunction RR39C to 0 on event 9 PDT-N017 Upset Range Failure None None Insert malfunction FW29 A to 0 on event 9 Feedwater level sensor N004A failure Insert malfunction FW29B after 60 to None None Feedwater level sensor N004B failure 60.00000 on event 9 Insert malfunction FW29C to 25.00000 in None None Feedwater level sensor N004C failure 60 on event 9 Insert malfunction RR20B to -150 on None None ECCS level transmitter N091B failure event 9 Insert malfunction RZO 1B to 60.00000 on None None RRCS Level Transmitter LT-N402B Failure event 9 Insert malfunction RZOIF from -150 to -32 None None CS Level Transmitter LT-N402F Failure in 15 on event 9 Insert malfunction RR24B after 120 on None None Reactor level transmitter N085B fails low event 9 Insert malfunction TUl508 to 45.00000 in None None Turbine bearing #8 vibration high 180 on event 7 Insert malfunction TU1508 to 0 in 120 on None None Turbine bearing #8 vibration high event 8 Insert malfunction RR31A2 to 50.00000 in Recire loop A large break [V] (10%-6000 None None 300 on event 9 gpm, 100%-60000 gpm)

ESG-015 Page 4 of 31 Rev: 19

i None 11 I Initial @Time Event Action i Description CD04 CRD suction filter isolation valve None None Insert remote CD04 to OPEN on event S V030 Insert remote CD06 to 100.00000 in 60 on CD06 Drive water press cont bypass valve None None event 6 V062 (0-100%)

Insert remote CDIO after 120 to ON on None None CDlO CRD FCVB event 6 Insert remote EP37 after 180 to BYFASS EP37 EOP-323, Bypass BC-HV-FOlSB None None on event 10 isolation interlocks Description None : None . Insert override 8AR27_B_AO to 0 on event REACTOR WATER LEVEL LR-3683B (AO) 9 i Insert override 8AR27 G AO to -19 on None : None i REACTOR WATER LEVEL LR-3682B (AO)

event 9 I Insert override 8M13_B_AO to 0 on event None i None . LEVEL LI-R60S-B21 (AO)

.9 i

i I I I

I I i

)

i I i

i I i i ESG-015 Page 5 of 31 Rev: 19

Loss of 10D410125VDC Bus:

Crew recognizes Loss of 1E HPI USED:

Afterthe Grew assumes the 125VDC by: FLAGGING 0 watchand at ihediscretion of => OHA D3-F2 "125VDC OP BARRIERS 0 the Lead Examiner, SYSTEM TROUBLE" (May flag/barrier 'A' TRIGGERET-1. => CRIDS D4630 "125VDC EDG to remind of SWGR 10D410 TRBL" it's unavailability,

=> CRIDS D4633 "125VDC since the START BATT 1AD411 PWR AVAIL light is lit)

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.

IE dispatched to investigate

Crew dispatches ABEO and E-0009-1 Sheet 1 loss of 10D410, Maintenance to investigate loss THEN REPORT: of 10D410 bus.

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 ESG-015 Page 6 of 31 Rev: 19

Crew recognizes closure of Loss of control power to HV-2197A Backwash valve by 'A' SSW pump motor 10C651A indication. breaker makes the pump appear stopped to the valve logic.

CRS directs opening HV-2197A.

PO opens HV-2197A. HPI USED:

STAR 0 PEER CHECK 0

CRS/STAliA recognize the Need to restore the following Tech Specs actions 1AD411 battery, apply: 1OD41 0 bus, and one

==> D.C. Sources - Operating charger in two hours, or 3.8.2.1 Action a be in Hot SID in next 12

==> Distribution - Operating hours.

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 #8 Bearing will reach 11 High Vibration by: mils in about 9.5

==> OHA D3-C5 "TURBINE minutes.

GENERATOR VIB HI"

==> CRIDS A2526 "MAIN TURB BRG 8 VIB X PROBE"

==> System 1 indication ESG-015 Page 7 of 31 Rev: 19

CRS implements AB.BOP-0002:

~ Condition B

STAliA monitors implementation of AB.BOP-0002 and applicability of Retainment Overrides.

SUPPORT requests to raise

Crew directs TBEO to raise IVITlO temperature using MTlO temperature (110 120"F)

Remote Function TU03.

As System Operator,

Crew co-ordinates with System HPI USED:

PROVIDE an acceptable band Operator to adjust Main STAR 0 of 300-425 MVARS. Generator MVAR loading. PEER CHECK 0 LE contacted as Engineering,

Crew contacts Engineering for THEN REPORT the vibration additional guidance.

readings appear valid and the limitations in the abnormal should be followed.

LE contacted as Operations

Crew contacts Operations Manager for concurrence to Manager for concurrence to commence a controlled commence a controlled shutdown lAW 10-0004, shutdown lAW 10-0004.

THEN CONCURR with SM recommendation.

LE dispatched to check bearing

WHEN bearing #8 reaches 11 HPI USED:

drains, mils, STAR 0 THEN wait until vibration THEN Crew: PEER CHECK 0 reaches 15 mils and REPORT ~ Reduces recirc pump speed the floor was vibrating and it to minimum.

did not appear safe to locks the Mode Switch in approach the Main Turbine. SHUTDOWN.

~ Immediately trips the Main Turbine.

ESG-015 Page 8 of 31 Rev: 19

STRATEGIES FOR SUCESSFUL

RO performs scram actions lAW HPI USED:

TRANSIENT MITIGATION Reactor Scram Reports AB.ZZ-0001 Attachment 1. STAR 0 Following a Reactor scram, the NCO HARD CARD 0 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.

ESG-015 Page 9 of 31 Rev: 19

STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

CRS implements EOP-101.

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.

STAIIA performs the following:

Verifies Rx shutdown

=> Trends critical plant parameters

=> Monitors EOP implementation

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 31 Rev: 19

WHEN Malfunction MC01 A

Crew recognizes evidence of RECORD time of inserts, physical damage to Main Turbine damage report for 15 THEN REPORT as TBEO you by: minute ECG heard a loud bang on 137' TB => TBEO report classification.

and now there is a loud => Rising offgas flow whistling noise. There pieces => Degrading condenser vacuum TIME: _ __

of turbine blades and other metal on the 137' TB floor.

CRS implements AB.BOP-0002:

=> Condition C

Crew performs the following: HPI USED:

=> Closes MSIVs and drains STAR 0

=> Closes SJAE suction PEER CHECK 0

=> Closes SJAE steam supply

=> Opens vacuum breakers

CRS directs RPV water level HPCI is unavailable due control with RCIC. to the loss of 100410.

PO controls RPV water level with HPI USED:

RCIC lAW AB.ZZ-0001 Att.6. STAR 0 HARD CARD 0

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.

ESG-015 Page 11 of 31 Rev: 19

STAIIA validates UE lAW ECG The STA is responsible Section 9.8.1.a OR 9.8.1.b. to perform an I.V. of the EAL Classification. The STA verification does not alleviate the requirement of the SM to make a timely classification. Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO.

SM declares UE lAW ECG RECORD time UE Section 9.8.1.a OR 9.8.1.b declared.

Time Declared: - - - -

!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 ARMED"

=:> OHA D1-A 1 "RRCS POTENTIAL ATWS"

=:> Safety lifting of F/H/KIM SRVs Various reactor pressure indicators ESG-015 Page 12 of 31 Rev: 19

STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

CRS directs maintaining reactor Pressure Leg pressure below 1037 psig with Direct initial band of 800 - 1000 psig. SRVs.

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.

RO/PO control RPV pressure HPI USED:

with SRVs as directed by CRS STAR 0 lAW AB.ZZ-0001 Att 13. HARD CARD 0 LOP/LOCA:

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 ESG-015 Page 13 of 31 Rev: 19

RO/PO start the 'B' EOG and HPI USED:

ensure it loads. STAR 0 PEER CHECK 0 Immed iateOperator Action lAW AB.ZZ-0135.

IF directed to locally start the

Crew starts the '8' EDG by

'B' EOG, EITHER:

THEN DELETE Malfunction Pressing the '8' EDG START DG07B. pushbutton in the Control Room, OR Directing an operator to locally start the '8' EDG.

As ESOC, REPORT it will take

Crew contacts ESOC for at least 10 hours0.417 days 0.0595 weeks 0.0137 months to restore estimated time to restoration of Offsite power to Artificial Island. Offsite power.

CRS implements AB.ZZ-0135.

Crew recognizes loss of HPI USED:

A0481/482 inverters by: FLAGGING 0

=> Loss of 'A' Channel PAMS (May flag 'A' channel indications indicators to remind of

=> Loss of power to 'A' Channel unavailability) electrical indications on 10C6500 Inverters are lost during LOP due to loss of 100410.

As time and resources permit, CRS implements AB.ZZ-0136 and AB.ZZ-170.

ESG-015 Page 14 of 31 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: Due to the pace of the

=.? Condition A LOCA, this may not be implemented.

STAIIA monitors AB.CONT-0001 implementation.

RO/PO ensures drywell cooling HPI USED:

maximized. STAR 0 PEER CHECK 0 There may not be time to maximize cooling before it isolates on high drywell pressure.

Crew checks Recirc pump seal parameters

=.? SRV temperatures

Crew recognizes Drywell RECORD time of High Pressure Above 1.68# EOP entry Drywell Pressure for 15 condition by: min ECG Classification.

=.? OHA A7-D4 "DRYWELL PRESSURE HI/HI"

=.? OHA C5-B5 "DRYWELL Time: - -

PRESSURE HI"

=.? Various system initiations and isolations.

ESG-015 Page 15 of 31 Rev: 19

STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

CRS enters EOP-102, re-enters EOP 101 RPV Control Level Leg EOP-101.

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.

ESG-015 Page 16 of 31 Rev: 19

A trigger point of "RPV level is -100

STAliA monitors EOP-102 inches and lowering" is recommended for evaluating the 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 < TAF.

'Crew resources may not be readily available during the Slowdown event; therefore the strategy of realigning the RHR systems for injection prior to reaching TAF 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. HPI USED:

STARD

CRS directs restoring PCIG to SRVs and Rx Bldg to Torus Vac Bkrs.

RO/PO restore PCIG to SRVs HPI USED:

and Rx Bldg to Torus Vac Bkrs STAR 0 lAW AB.ZZ-0001 Att. 9. HARD CARD 0

SM determines an Alert The LOP results in a Classification is required lAW UE lAW 7.1.1.

ECG Section 3.2.2.b (Valid High Drywell Pressure).

STAliA turns over with extra SRO or SM to independently assess ECG Classification.

STAIIA validates Alert lAW ECG The STA is responsible Section 3.2.2.b. to perform an I.V. of the EAL Classification. The STA verification does not alleviate the requirement of the SM to make a timely classification. Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO.

SM declares Alert lAW ECG RECORD time Alert Section 3.2.2.b. declared.

Time Declared: - -

ESG-01S Page 18 of 31 Rev: 19

STAliA verifies isolations and monitors containment performance.

IE directed to align for two CRD

CRS orders injection with two CRD pumps will trip on pump injection, CRD pumps. low suction pressure THEN PERFORM the due to suction filter following: clogging.

REFER to SO.BF-0001 Sect 5.4. IF RPV water level TRIGGER ET-5 (Suction filter). reaches -161",

SET Remote Function for Stby THEN RECORD the CRD pump discharge valve to time for 15 minute ECG 0% (CD01/CD02). Classification:

REPORT Stby CRD pump ready for start. TIME -161" WHEN Stby CRD is running, reached: _ __

THEN RAMP discharge valve to 100% open.

IE directed to manually open HV-F003, THE"I REPORT you have opened the valve.

(There is no function for this.)

AFTER HV-F003 is open, THEN TRIGGER ET-6.

WHEN two minutes have

elapsed, THEN MODIFY Malfunctions CD09A1B to control injection.

IE instrument air pressure is

zero, THEN REPORT the FCVs do not seem to be responding.

CRS orders injection with 'B' SLC pump.

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 31 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 HPI USED:

AB.ZZ-0001 Attachment 13. STAR 0 HARD CARD 0

Before RPV water level has RECORD the time been below -185" for two between -185" minutes, Crew opens five (compensated) and five SRVs to Emergency SRVs are opened.

Depressurize the reactor.

TIME: _ __

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.

ESG-015 Page 20 of 31 Rev: 19

IF RPV level reaches -161", The STA is responsible THEN STA validates a SAE is to perform an I.V. of the required lAW ECG Sections: EAL Classification. The

=;> 3.1.1.a(3pts) STA verification does AND not alleviate the

=;> 3.2.1.b or 3.2.2.b (4 pts) 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.

RO/PO inject with available HPI USED:

ECCS lAW AB.zZ-0001: STAR 0

=;> Att. 4 for B/C/D RHR HARD CARD 0

=;> Att. 4 for 'B' Core Spray loop PEER CHECK 0

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.

ESG-015 Page 21 of 31 Rev: 19

STRATEGIES FOR SUCESSFUL

CRS exits EOP-101 and enters RC/P leg was exited TRANSIENT MITIGATION EOP-206/EOP 206A RPV Flooding. EOP-206. when EOP-202 was "Can 5 ADS valves be opened?" implemented, RC/L leg This question should be answered is exited when strictly based on the present EOP-206 is entered.

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 EOP 206 and RF-30 in EOP-206A.

CRS directs commencing and Cannot achieve MSIV raising injection to the MSIVs are flooding without flooded. injection from the '0' RHR pump.

Available RPV pressure

Crew continues injection into the indicators: RPV until the RPV has been

PI-R605 flooded to the Main Steam Lines

PAMS PR-R3684B as indicated by:

A2802 PT-3684B :::;- At least 5 SRVs are open

A3547 RRCS Div 2 Ch A AND

A3548 RRCS Div 2 Ch 8 At least 2 of the RPV Flooded

Local gauges PI-R004A1B Indications of Table RF-2 can Available Supp Chamber be observed.

pressure indicators:

PR-496081

PI-4960B1

A2814 W/R Supp Chbr Press ESG-015 Page 22 of 31 Rev: 19

WHEN RPV water level It will take about 10 indication is lost, minutes for the RPV to THEN Crew injects into the fill above the Main RPV until at least 2 of the RPV Steam Lines.

Flooded Indications of Table RF-2 can be observed.

IF EOP-206 is successful, Bases for ECG 3.1.1 ,

THEN SM determines a SAE is 3.2.1 and 3.3.1 states:

required lAW ECG Sections: If all Reactor Level

~ 3.1.1.a (3 pts) instrumentation is lost AND and EOP 206 or EOP

~ 3.2.1.b or 3.2.2.b (4 pts) 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.

STAliA turns over with extra SRO or SM to independently assess ECG Classification.

ESG-015 Page 23 of 31 Rev: 19

IF EOP-206 is successful, The STA is responsible THEN STA validates a SAE is to perform an I.V. of the required lAW ECG Sections: EAL Classification. The

, 3.1.1.a (3pts) STA verification does AND not alleviate the

, 3.2.1.b or 3.2.2.b (4 pts) 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.

IF EOP-206 is successful, RECORD time SAE THEN SM declares a SAE lAW declared.

ECG Sections: Time

, 3.1.1.a (3pts) Declared: - -

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)

AND

, 3.3.1 (1 pt)

Termination Requirem~nt:

Thefscenariornay b,~ .. .

terminatedatthe discretion of the Lead Examinerwhen 9de(tu~tecOrec()olinghas ;

been established lAW EOp':'206.>

ESG-015 Page 24 of 31 Rev: 19

A. TO-AA-1 06-0304 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 01-111-1004 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 19 1.

Crew starts the 'B' EDG by EITHER:

Pressing the 'B' EDG START pushbutton in the Control Room, OR Directing an operator to locally start the 'B' EDG.

KIA 295003 Partial or Complete Loss of A.C. Power AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF AC.

POWER AA1.02 Emergency generators RO 4.2 SRO 4.3 AA 1.03 Systems necessary to assure safe plant shutdown RO 4.4 SRO 4.4 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 lost, THEN Crew injects into the RPV until at least 2 of the RPV Flooded Indications of Table RF-2 can be observed with 5 SRV's open.

KIA 295031 Reactor Low Water Level EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:

EA2.01 Reactor water level RO 4.6 SRO 4.6 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 31 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 Internal Flooding LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening Y Manual Scram COMPONENTfTRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT YIN KEY EQUIPMENT Hard Torus Vent Y SLC Y HPCI CRD 1E 4.16KV Bus Y 1E 125VDC SACS HxlPump EDG KEY SYSTEMS Y 120VAC 481/482 Inverter 500KV AC Power Y AlB RHR SRVs RCIC Y Condensate/F eedwater Y SSW Pump 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.

ESG-015 Page 27 of 31 Rev: 19

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

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

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