Text

Hope Creek - Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML15100A042
Person / Time
Site:	Hope Creek
Issue date:	03/06/2015
From:	Suzanne Dennis; Public Service Enterprise Group
To:	Brian Fuller; Operations Branch I
Shared Package
ML14254A267	List: IR 05000354/2015301; ML15048A126; ML15100A040; ML15100A041; ML15100A042; ML15163A241; ML15163A242; ML15163A243; ML15163A244; ML15163A245; ML15163A246; ML16145A244;
References
	TAC U01904
	Download: ML15100A042 (360)
	v • d • e

' STATION:

Hope Creek SYSTEM: Administrative JOB PERFORMANCE MEASURE TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs COPY OF JPM NUMBER: 305H-JPM.ZZ016

[RO A1-1] REVISION:

03 SAP BET: NOH05JPZZ16E K/ANUMBER:

2.1.18 IMPORTANCE FACTOR: RO: 3.6 SRO: 3.8 ALTERNATE PATH: D APPLICABILITY:

EO D RO (8J STAD sRoD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-DL.ZZ-0026, Rev. 144 TOOLS, AND EQUIPMENT:

Black pen and Red Pen ESTIMATED COMPLETION TIME: __ 1_9 __ Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: _ ___:_Nc:.:..:/A'--'----

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

Minutes REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-8-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of13 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs INITIAL CONDllTONS:

1. A Plant Startup is in progress following a Forced Outage. 2. HC.OP-IO.ZZ-0003, Startup from Cold Shutdown to Rated Power, is being implemented.

3. Current power is 95%. 4. Power ascension has been on hold for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months while Reactor Engineers evaluate core conditions.

INITIATING CUE: COMPLETE the Day Shift daily Surveillance Logs for 10C609, 10C611, AND MSL Radiation (Items 61-74 of Attachment 1 a) in accordance with HC.OP-DL.ZZ-0026.

Page 2of13

, JPM NUMBER: REV NUMBER: STEP NUMBER 305H-JPM.ZZ016 03 ELEMENT NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD CUE: PROVIDE the operator the initiating cue. START TIME: Operator obtains the correct Operator obtains HC.OP-DL.ZZ-procedure.

0026. 3.1 COMPLETE Attachment 1 (all *operator records readings for subsections) daily. Items 61-74 of Attachment 1a, Day Shift. Examiner Note: IAW the Initiating Cue, only Items 61-74 of Attachment 1 a are required.

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

Examiner Note: Completion of Note 54 calculation is not appropriate due to transient plant conditions.

3.2 lE in OP CON 4 or 5, THEN Operator determines this step is COMPLETE Attachment 2 ... N/A. 3.3 COMPLETE Attachment 4 to Operator determines this step is perform surveillances

... N/A. 3.4 ENTER the Operational

operator enters the Operational Condition and date on each Condition and date in the page of the log in the blanks appropriate blanks. provided.

3.5 COMPLETE the applicable Operator determines this step is subsections of Attachment 3 ... N/A. 3.6 COMPLETE all surveillances Examiner Note: The Operator may as indicated in each log. IF a not perform this step until Technical Specification completion of Step 3.7. Operator Surveillance cannot be may perform Step 3.6.3 and successfully completed OR is include the T/S references.

out-of-spec, THEN *operator determines that the IMMEDIATELY NOTIFY the deviation for Item 63 exceeds the SM/CRS AND the Duty RO MAX DEVIATION, AND corrective action initiated shall be noted in the comments THEN IMMEDIATELY NOTIFIES section.

the SM/CRS AND the Duty RO, AND notes corrective action in the comments section.

Page 3of13 SAT/ COMMENTS UNSAT (Required for UNSAT)

JPM NUMBER: 305H-JPM.ZZ016 NAME: REV NUMBER: 03 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fa STANDARD UNSAT) CUE: Repeat back message from Operator on Item 63 deviation.

operator determines that the deviation for Item 65 exceeds the MAX DEVIATION, THEN IMMEDIATELY NOTIFIES the SM/CRS AND the Duty RO, AND notes corrective action in the comments section.

Examiner Note: Operator may perform Step 3.6.3 and include the TIS references.

CUE: Repeat back message from Operator on Item 65 deviation.

3.6.1 !E a work order is issued to Operator determines this step is repair an abnormal

reading, N/A. THEN NOTE the work order number in the comment section.

3.6.2 !E an Action Statement Log Operator determines this step is Sheet is issued ... N/A. 3.6.3 IF a surveillance item is out-of-Operator refers to Step 3.11 AND spec or not successfully determines applicable TIS completed, THEN REFER to reference numbers and notes for Step 3.11 for T JS reference items 63 and 65. numbers and notes. CUE: Repeat back message from Operator on T/S numbers and notes. 3.7 !E performing a channel check *operator performs channel that requires a comparison checks and records the between channels, THEN differences between the high RECORD the difference and low values and trip status. between the high and low value and trip status. Examiner Note: IAW the Initiating Cue, only Items 61-74 of Attachment 1 a Day Shift is required.

Refer to Exhibit 1 for expected values. Values may not exactly match due to differences in the observed values. MAX DEVIATION readings are SAT if they are mathematically correct.

-Page 4of13

, JPM NUMBER: 305H-JPM.ZZ016 NAME: ---REV NUMBER: 03 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN: REPEAT BACK any message from the operator on the status of the JPM; then state "This JPM is complete";

AND RECORD the STOP TIME. STOP TIME: Task Standard:

Operator completes required Daily Surveillance Log entries in accordance with HC.OP-DL.ZZ-0026. Page 5of13 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION 305H-JPM.ZZ016 NAME: ------------

03 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 6of13 ,

, JOB PERFORMANCE MEASURE JPM NUMBER: 305H-JPM.ZZ016 REVISION HISTORY Rev# Date Description Validation Required?

1 1/14/12 Reference procedure change only. No changes to operator actions.

No N validation required.

2 7/1/2013 Revised due to Reference procedure revision.

Added additional action y item. Added to lnitiatinQ Cue due to simulator equipment out of service.

3 10/31/2014 Revised format. Changed initial conditions.

Modified Malfunctions to y change OOS items. Validated with 2 ROs. Validation time 19 minutes.

Added place screen prints over XR11497 due to equipment unavailability.

3 1/22/2015 Modified Malfunction and Remote severities to obtain desired N indications.

Added simulator setup information to adjust severities as necessary during setup. Corrected typographical error in expected response.

Page 7of13 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 305H-JPM.ZZ016 REV#: 03 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Complete The Daily Surveillance Logs Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO J. KOSKEY RO ON FILE 10/31/2014 Name Qua I Signature Date R. KEFER RO ON FILE 10/31/2014 Name Qua I Signature Date Page 8of13 ,

, JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 305H-JPM.ZZ016 REV#: 03 ---------------INITIALIZE the simulator to 100% power, MOL. LOWER power to 95% using TCF. STABILIZE Xenon concentration.

TAKE Cross-Flow to Not Applied and Blocked.

INSERT Malfunctions and Overrides

(i.e.,

. PLACE pictures of Main Screen and RWCU Delta-Flow on NUMAC 1 SKXR-11497.

ENSURE meter indications support expected values. Modification of Malfunctions and Remotes may be necessary.

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

Initial ET Event code:

Description:

Initial @Time Event Action Description None None Insert malfunction RP18C to 41.20000 RPS LT-N080 C failure None None Insert malfunction RM9509 to 37.00000 9RX509, MSL 'A' -Main Steam Line Chan A None None Insert malfunction RM9510 to 38.00000 9RX510, MSL 'B' -Main Steam Line Chan B None None Insert malfunction RM9511 to 35.80000 9RX511, MSL 'C' -Main Steam Line Chan C None None Insert malfunction RM9512 to 36.80000 9RX512, MSL 'D' -Main Steam Line Chan D Page 9of13 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

/

/' < c; ' ,,,< .:$©riEOUL:E:

,

.. /, , Initial @Time Event Action Description None None Insert override 12A6 A AO to 0.21000 MASTER TRIP UNIT B21-N675A METER (COND VAC LO) -C71A-Z2A (AO) Initial @Time Event Action Description Page 10of13

... ' HC.OJ-_ .... ZZ-0026(Q)

[ EXAMINER'S COPY I Surveillance Log -Control Room -Day Shift Page 13of18 Operational Condition 1 Date Today 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@ RPV PRESSURE 1,2 N678A 1010 N678C 1000 N678B 980 N678D 980 30 100 ---1037 No 62@ DRYWELL PRESSURE 1,2,3 N650A 0.6 N650C 0.5 N650B 0.5 N650D 0.7 0.2 1 ------1.68 No NOTE29. -63@ CONDENSER VACUUM 1,2,3 N675A 24.5 N675C 27.5 N675B 27.0 N675D 27.5 l 3J 1 2.5 8.5 ------No 64@ MSL PRESSURE 1 N676A 950 N676C 950 N676B 950 N676D 960 10_ 80 756 ------No 65@ RPVLEVEL3 1,2,3 N680A 38 N680C 40 N680B 34 N680D 35 4 12.5 ------No 66@ NORTH SDV LEVEL 1,2,5 N/A N/A N601C 0 N/A N/A N601D 0 u 10 ------72 No (NOTE 61) 67@ SOUTH SDV LEVEL 1,2,5 N601A 0 N/A N/A N601B 0 N/A N/A 0 10 -----72 No CNOTE 61) 68@ MSLAFLOW 1,2,3 N686A 70 N686C 70 N686B 70 N686D 55 15 18 -----162.8 No 69@ MSL B FLOW 1,2,3 N687A 65 N687C 70 N687B 60 N687D 70 10 18 ------162.8 No 70@ MSLCFLOW 1,2,3 N688A 60 N688C 70 N688B 60 N688D 65 10 18 ------162.8 No 71@ MSLD FLOW 1,2,3 N689A 70 N689C 65 N689B 60 N689D 65 10 18 ------162.8 No 72@ RPV LEVEL 2 (NOTE 27.) 1,2,3,* N681A 36 N681C 35 N681B 40 N681D 41 6 15 -----No NOTE29. @ RPV LEVEL 1 1,2,3 N684A N/A N684C NIA N684B NIA N684D NIA N/A N/A -129 -----No 73@ RWCU dF (NOTE 56,57) 1,2,3 XR11497 0 N/A N/A N/A N/A XR11499 0 0 20 ------56 No RM-11 74@ MSL RADIATION 1.2.3 9RX509 37 9RX510 38 9RX511 36 9RX512 37 2 (NOTE 53) -----3X No (NOTES 53, 54) NOTE 55 15.0 NORM NOTE: FOR ANY INSTRUMENT FOUND TRIPPED, PLACE AT 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

!N RED AND RECORD "YES' IN THE INST TRIPPED COLUMN_ NOTE 61: WHEN IN OPER COND 5 -WITH ANY CONTROL ROD WITHDRAWN.

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

NOTE 27.: (")-WHEN HANDLING RECENTLY IRRADIATED FUEL IN THE SECONDARY CONTAINMENT AND DURING OPERATIONS WITH A POTENTIAL FOR DRAINING THE REACTOR VESSEL NOTE 29.: ALSO REQUIRED WHEN SECONDARY CONTAINMENT IS REQUIRED TO BE IN EFFECT JAW TIS. [10021778]

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 DEVlATION CALCULATED BY ADDING OPERABLE CHANNEL VALUES. DMDING RESULT BY NUMBER 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.

NUMAC READINGS SHOULD BE TAKEN 3-4 SECONDS INTO THE CPU SELF-TEST (PRESS ANY .... KEY; PRESS "ETC"

KEY; PRESS "DISPLAY TEST STATUS" ... KEY) VVHEN 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: SEE NEXT PAGE NOTE 55: DURING OPERATIONAL CONDITIONS 1 AND 2 WITH MECHANICAL VACUUM PUMP(S) IN-SERVICE AND ANY MAIN STEAM LINE NOT ISOLA TED, THE MSL RADIATION CHANNEL CHECK BETWEEN THE ALPHA AND BRA VO CHANNELS (9RX509/9RX5*to, K61 OAIK610B)

ALSO SATISFIES A MECHANICAL VACUUM PUMP TRIP INSTRUMENTATION CHANNEL CHECK !AW TIS 4.3. 10.a. NOTE 56: INITIATE NOTIFICATION WHEN DEVIATION BETWEEN CHANNELS A AND D REACHES 9 GPM TO ENSURE THAT THE PROBLEM CAUSING THE DEVIATION IS CORRECTED.

NOTE 57: IF LEAK DETECTION MONITOR INDICATES"<<<"

FOR FLOW. ADD FOUR FLOW VALUES UNDER "NORM"' COLUMN TO OBTAIN READING_

(MAY RESULT IN NEGATNE VALUE) Hope Creek Page 31 of 105 Page 11of13 Rev.144

.. I EXAMINER'S COPY =1 HC.OP-DL.ZZ-0026(Q)

ATTACHMENT 1a Page 14of18 Surveillance Log -Control Room -Day Shift Operational Condition 1 Date Today 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 c IS< 0.85 OR> 1.2 (.:!: 20%) THEN A RE-EVALUATION OF THE 3X NORMAL SETPOINT MAY BE DESIRED USING HC.SE-GP.SP-0001(0).

NOTIFY RMS SYSTEM ENGINEER FOR SUPPORT IN RE-EVALUATION.

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

MSL AVERAGE FULL POWER BACKGROUND CHECK a RM-11 LAST HOURLY AVERAGE b RM-11 HI SETPOINT c c =a I bx 3 (RATIO OF ACTUAL TO BASELINE AFPB) [JJ Item 63, Condenser Vacuum exceeds max deviation.

[I] Item 65, RPV Level 3 exceeds max deviation.

Hope Creek MIN MSLRMSA 37 105 0.850 1.057 Page 32 of 105 Page 12of13 MSLRMS B MSLRMS C MSLRMS D 38 36 37 114 112 114 1.000 0.964 0.974 Rev.144

' JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A Plant Startup is in progress following a Forced Outage. 2. HC.OP-IO.ZZ-0003, Startup from Cold Shutdown to Rated Power, is being implemented.

3. Current power is 95%. 4. Power ascension has been on hold for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months while Reactor Engineers evaluate core conditions.

INITIATING CUE: COMPLETE the Day Shift daily Surveillance Logs for 1 OC609, 1 OC611, AND MSL Radiation (Items 61-74 of Attachment 1a) in accordance with HC.OP-DL.ZZ-0026.

Page 13of13

> JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Reactor Recirculation TASK NUMBER: 3000260101 TASK: Perform Power Changes During Operation COPY OF JPM NUMBER: 305H-JPM.ZZ047

[RO A1-2] REVISION:

0 SAP BET: NOH05JPZZ47E K/A NUMBER: 2.1.23 IMPORTANCE FACTOR: RO: 4.3 SRO: 4.4 ALTERNATE PATH: D APPLICABILITY:

EO D STAD sRoD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-ST.BB-0007 Rev. 16 TOOLS, AND EQUIPMENT:

Black Pen and Red Pen, Calculator, Straight-Edge, HC.OP-ST.BB-0007 ESTIMATED COMPLETION TIME: 27 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-8-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of16 JOB PERFORMANCE MEASURE SYSTEM: Reactor Recirculation TASK NUMBER: 3000260101 TASK: Perform Power Changes During Operation INITIAL CONDllTONS:

1. Plant is operating in OPCON 1. 2. Entered Single Loop Operations in accordance with HC.OP-IO.ZZ-0006, Power Changes During Operation, to remove Reactor Recirculation Pump AP201 from service due to seal degradation.

3. HC.OP-IO.ZZ-0006 is completed through Step 5.3.9. 4. This is the second entry into single loop operation this cycle with Reactor Recirculation Pump BP201 in operation.

5. No other testing or maintenance is in progress that will adversely affect the performance of this test. 6. The 3D Monicore Computer display is out of service.

Use CRIDS OD3 for Thermal Power data. INITIATING CUE: In accordance with Step 5.3.10 of HC.OP-IO.ZZ-0006, PERFORM Section 5.1, Jet Pump Operability Verification, of HC.OP-ST.BB-0007.

An Equipment Operator is standing by at Panel 1 OC619, Aux Bldg Control Area El. 102', to obtain individual Jet Pump dp's. Another operator will perform the rest of the procedure.

Page 2of16

, JPM NUMBER: ZZ047 NAME: --------**-*------

REV NUMBER: 0 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: 5.1.1 IF this is the first subsection of Operator requests that the the procedure to be performed procedure be logged in the Control THEN LOG test start time in Room logs. the Control Room log(s). CUE: Respond that "The procedure is logged in the Control Room logs." 5.1.2 ENSURE that all prerequisites Operator ensures that all have been satisfied IA W Prerequisites have been satisfied Section 2.1 of this procedure.

(completes Attachment 1, Section 3.0) and INITIALS each prerequisite.

5.1.3 ENSURE Attachment 1, Operator ensures Attachment 1 , Section 1 .0 of the SM/CRS Section1

.0 has been completed Data and Signature Sheet has AND INITIALS Step. been completed AND Regular Surveillance OR Retest is indicated.

EXAMINER'S NOTE: Refer to the attached Examiner's Copy during the performance of the following Steps. 5.1.4 RECORD the following information in the appropriate spaces on Attachment 2: A. ENTER Recirculation Operator marks Step as N/A. Pump "A" speed IF operating, OTHERWISE N/A. B. ENTER Recirculation

operator determines Pump "B" speed !E Recirculation Pump "B" speed operating, OTHERWISE as indicated by 1-BB-SIC-R621A N/A. and enters this value on Attachment

2. %] C. ENTER Recirculation Operator marks Step as N/A. Pump "A" flow !E operating, OTHERWISE N/A. Page 3of16

' JPM NUMBER: ZZ047 NAME: -----------REV NUMBER: 0 DATE: -------(*Critical Step) SAT/ COMMENTS STEP ELEMENT (#Sequential Step) UNSAT (Required fc NUMBER STANDARD UNSAT) D. ENTER Recirculation

operator determines Pump "B" flow IF operating, Recirculation Pump "B" flow as OTHERWISE N/A. indicated by 1-BB-Fl-R613-B31 or 1-BB-FR-R614-B31 (blue), enters this value and circles the indicator used on Attachment

2. [+/-.4 KGPM] E. !E Recirculation Pump "A" Operator marks Step as N/A. is operating, ENTER SAT IF Recirculation Pump "A" flow is within +/- 10% of the established curve (at given speed) on Attachment 4, (otherwise, UNSAT). [T/S 4.4.1.2.b.1]

F. IF Recirculation Pump "B" *operator refers to Attachment 5 is operating, ENTER SAT and determines that flow is IF Recirculation Pump "B" within +/-10% of the established flow is within +/-10% of the curve (at given speed), and established curve (at given enters SAT on Attachment

2. speed) on Attachment 5, [+/-0.5 MLB/HR] (otherwise, UNSAT). [T/S 4.4.1.2.b.1]

NOTE If the operating loop drive flow Operator reads and initials the is 23 kgpm (== 48% Recirc Note. Pump speed) then the flow in the idle loop is negative (reverse) flow. If the operating loop drive flow is < 23 kgpm (== 48% Recirc Pump speed) then the flow in the idle loop is positive (forward) flow. G. CALCULATE Total Core *operator determines Jet Pump Flow as follows:

Loop Total Flow A as indicated

1. ENTER Jet Pump Loop by Fl-R611A-B21 or A3189, and Total Flow A. enters this value on Attachment

2. [+/-0.5 MLB/HR] 2. ENTER Jet Pump Loop *operator determines Jet Pump Total Flow B. Loop Total Flow A as indicated by Fl-R611B-B21 or A3190, and enters this value on Attachment

2. [+/-0.5 MLB/HR] -Page 4of16

, JPM NUMBER: ZZ047 NAME: REV NUMBER: 0 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) 3. IF the operating loop Operator determines that the drive flow is <:: 23 kgpm operating loop drive flow is <::23 (===48% Recirc Pump kgpm (===48% Recirc Pump speed) speed) PERFORM the and determines that this step is following:

applicable.

a. IF Recirculation Operator marks Step as N/A. Pump A is operating,

... b. IF Recirculation

operator multiplies the value Pump Bis obtained in Step 1 by 0.85, then operating, subtracts the resultant value MULTIPLY the from the value obtained in Step value obtained in 2, and enters calculated Total Step 1 by 0.85, Core Flow on Attachment

2. THEN SUBTRACT

[+/-0.5 MLB/HR] the resultant value Operator then initials Step and from the value obtained in Step 2 proceeds to Step 5.1.4.H.

AND ENTER calculated Total Core Flow. PROCEED to Step 5.1.4.H.

H. ENTER SAT IF calculated

operator refers to Attachment 7 Total Core Flow is within and determines that Total Core +/-10% of the established Flow is NOT within +/-10% of the curve (at given operating established curve (at given Recirc Pump flow) on operating Recirc Pump flow) and Attachment 6, Recirculation enters UNSAT on Attachment

2. Pump Flow "A" vs Total Core Flow Curve, OR on Attachment 7, Recirculation Pump Flow "B" vs Total Core Flow Curve, (otherwise, UNSAT). [T/S 4.4.1.2.b.2]

Page 5of16 JPM NUMBER: ZZ047 NAME: REV NUMBER: 0 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fc STANDARD UNSAT) NOTE The constant motion of the Operator reads and initials the individual jet pump d/p Note. indicators makes data acquisition difficult.

The recommended method is to take a high and a low reading and use their average.

Noise is the most positive indication that the jet pump is operating.

Jet Pump d/p indication accuracy and readability are marginal during periods of low Core flow. Attempt to maximize Recirc Pump speeds before performing the following steps. Jet pump data is only required for jet pumps 1 -10 when "B" Recirc. Loop is in operation, and jet pumps 11 -20 WHEN "A" Recirc. Loop is in operation.

5.1.5 COMPLETE Attachment 3 for

individual Jet Pumps in the Operator contacts the Equipment Operator to operating Recirc. Loop ONLY. perform/provide the individual Jet Pump data for Jet Pumps 1-10. Examiner Note: Data sheets provided for Jet Pumps 11-20 and 1-20. CUE: Respond as the Equipment Operator and provide the operator with the requested data on Attachment

3. 5.1.6 DETERMINE on Attachment 3 Operator determines that all% dp whether the% dp is within are within +/-20% of the established

+/-20% of the established curve curves for the appropriate for the appropriate operating operating Recirc Pump (at a given Recirc Pump (at a given speed) speed) on Attachment

8. on Attachment 8 or 9. 5.1.7 RECORD SAT OR UNSAT on *operator enters SAT for each Attachment

3. Jet Pump on Attachment

3. 5.1.8 On Attachment 2 ENTER SAT Operator enters SAT on IF all individual Jet Pumps are Attachment

2. recorded as SAT on Attachment 3 (otherwise, UNSAT). [T/S 4.4.1.2.b.3]

Page 6of16 JPM NUMBER: ZZ047 NAME: REV NUMBER: 0 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) 5.1.9 ENTER THERMAL POWER Operator obtains Thermal Power from the 3D Monicore P1 as indicated on CRIDS OD3 and Report OR OD3 on Attachment enters value on Attachment

2. 2. 5.1.10 IF this is the final subsection of Operator determines that this is the procedure THEN LOG test NOT the final subsection and end time in the Control Room marks Step as N/A. log(s). 5.1.11 IF this is the final subsection of Operator determines that this is the procedure to be performed NOT the final subsection and THEN SUBMIT this procedure marks Step as N/A. to the SM/CRS for review AND completion of Attachment

1. 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: Task Standard:

Operator performs Section 5.1, Jet Pump Operability Verification, of HC.OP-ST.BB-0007.

Page 7of16 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ZZ047 NAME: ------------

0 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 8of16 JOB PERFORMANCE MEASURE JPM NUMBER: ZZ047 REVISION HISTORY Rev# Date Description Validation Required?

0 10/31/2014 Initial issue. Significantly modified ZZ013. Validated with 2 ROs. y Validation time 27 minutes.

0 1/22/2015 Added Examiner Note to Standard for clarification of data N provided with JPM. Completed Task Standard statement.

Corrected typographical error in expected response.

Page 9of16 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ047 REV#: 0 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Perform Power Changes During Operation Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO R. KEFER RO ON FILE 10/31/2014 Name Qua I Signature Date J. KOSKEY RO ON FILE 10/31/2014 Name Qua I Signature Date Page 10of16 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: ZZ047 INITIALIZE to 100% power MOL. ---INSERT 1 OC, 1 OB, and 1 OA Control Rods. ---LOWER Reactor Recirculation Pump Demands to 74.5%. ---REV#: 0 REMOVE AP201 from service, and isolate, in accordance with HC.OP-IO.ZZ-0006 and HC.OP-SO.BB-0002, Sections 5.3 and 5.6. Initial Descri tion MARKUP HC.OP-ST.BB-0007, Attachment 3, Jet Pump data. ---MARKUP HC.OP-ST.BB-0007 for completion of Regular Surveillance.

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

Initial ET Event code:

Description:

Initial @Time Event Action Description

'* CCC',., ' , !'REl\.:ltrr:Et©'CHEDULE:::;,i\.

" '*i Initial @Time Event Action Description

< \.

'E SCHEDULE:

"c ';' F ' Initial @Time Event Action Description Page 11of16 EXAMINER'S COPY HC.OP-ST.BB-0007(Q)

ATTACHMENT 2 CONTROL ROOM DATA SHEET RECIRCULATION JET PUMP OPERABILITY-SINGLE LOOP -DAILY Page 1 of 1 1.0 Jet Pump Operability Verification STEP NOMENCLATURE 5.1.4.A RECIRCULATION PUMP "A" SPEED (1-BB-SIC-R621A) 5.1.4.B RECIRCULATrON PUMP "B"' SPEED f1-BB-SIC-R6218) 5.1.4.C RECIRCULATION PUMP "A"' FLOW 1-BB-Fl-R617-B31 or *t-BB-FR-R614-B31 (red) (Circle indicator used) 5.1.4.D RECIRCULATION PUMP "B" or 1-BB-FR-R614-B31 (blue) (C1rc1e 11 rult;.dtor used) 5.1.4.E "'A" PUMP SPEED/FLOW DEVIATION CHECK 5.1.4.F "'B'. PUMP SPEED/FLOW DEVIATION CHECK 5.1.4.G.1 JET PUMP LOOP TOTAL FLOW "A'" Fl-R611A-821 or A3189 5.1.4.G2 JET PUMP LOOP TOTAL FLOW "B" Fl-R611B-B21 or A3190 5.1.4.G-3 OR TOTAL (CALCULATED)

CORE FLOW 5.1.4.G.5 5.1.4.H RECIRC PUMP FLOW vs TOTAL CORE FLOW CHECK 5.1.8 JET PUMP DIFFERENTIAL PRESSURE CHECK 5.1.9 CORE THERMAL POWER (P1OR003)

"' Acceptance Criterion

-At least two of three blocks must be marked SAT (REFER to Tech Spec 4.4.12.b).

!E. Thermal Power is 5: 38% (14592 MWTH) of Rated Thermal Power OR Recirculation loop flow in the operating loop is 22.6 KGPM, SEE Precaution 3.1.2. VALUE N/A % 74.25 % N/A KGPM 39.030 KGPM N/A SAT 18.15 MLBJHR 67.98 MLBJHR 52.55 MLBJHR CuNsAf) SAT 2030.9 MWTH # # # Hope Creek Page 14 of 42 Rev.16 Page 12of16 1* TRAINING ONLY ATTACHMENT 3 INPLANT DATA SHEET HC.OP-ST.BB-0007(Q)

RECIRCULATION JET PUMP OPERABILITY-SINGLE LOOP -DAILY 1.0 Jet Pump Operability Verification (LOCATED ON PANEL 10C619) Step Error! COLUMN A Reference source not found. COLUMN A WITHIN+/- 20% OF JET PUMP INDIVIDUAL JET ESTABLISHED

% dp on PUMP% dp ATTACHMENT 8 or9 ENTER SAT OR UNSAT JP-1 55 JP-2 57 JP-3 51 JP-4 63 JP-5 58 JP-6 53 JP-7 60 JP-8 60 JP-9 56 JP-10 54 JP-11 9 JP-12 10 JP-13 9 JP-14 11 JP-15 7 JP-16 10 JP-17 7 JP-18 12 JP-19 9 JP-20 7 Hope Creek Page 16 of 42 Rev.16 Page 13of16 TRAINING ONLY ATTACHMENT 3 INPLANT DATA SHEET HC.OP-ST.BB-0007(Q)

RECIRCULATION JET PUMP OPERABILITY-SINGLE LOOP -DAILY 2.0 JET PUMP OPERABILITY VERIFICATION (LOCATED ON PANEL 10C619) Step Error! COLUMN A Reference source not found. COLUMN A WITHIN+/- 20% OF JET PUMP INDIVIDUAL JET ESTABLISHED

% dp on PUMP% dp ATTACHMENT 8 or 9 ENTER SAT OR UNSAT JP-1 JP-2 JP-3 JP-4 JP-5 JP-6 JP-7 JP-8 JP-9 JP-10 JP-11 9 JP-12 10 JP-13 9 JP-14 11 JP-15 7 JP-16 10 JP-17 7 JP-18 12 JP-19 9 JP-20 7 Hope Creek Page 16 of 42 Rev.16 Page 14of16 I( TRAINING ONL y ATTACHMENT 3 INPLANT DATA SHEET HC.OP-ST.BB-0007(Q)

RECIRCULATION JET PUMP OPERABILITY-SINGLE LOOP -DAILY 3.0 JET PUMP OPERABILITY VERIFICATION (LOCATED ON PANEL 10C619) Step Error! COLUMN A Reference source not found. COLUMN A WITHIN+/- 20% OF JET PUMP INDIVIDUAL JET ESTABLISHED

% dp on PUMP% dp ATTACHMENT 8 or 9 ENTER SAT OR UNSAT JP-1 55 JP-2 57 JP-3 51 JP-4 63 JP-5 58 JP-6 53 JP-7 60 JP-8 60 JP-9 56 JP-10 54 JP-11 JP-12 JP-13 JP-14 JP-15 JP-16 JP-17 JP-18 JP-19 JP-20 Hope Creek Page 16 of 42 Rev.16 Page 15of16 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: 1 . Plant is operating in OPCON 1 . 2. Entered Single Loop Operations in accordance with HC.OP-IO.ZZ-0006, Power Changes During Operation, to remove Reactor Recirculation Pump AP201 from service due to seal degradation.

3. HC.OP-IO.ZZ-0006 is completed through Step 5.3.9. ) 4. This is the second entry into single loop operation this cycle with Reactor Recirculation Pump BP201 in operation.

5. No other testing or maintenance is in progress that will adversely affect the performance of this test. 6. The 3D Monicore Computer display is out of service.

Use GRIDS OD3 for Thermal Power data. INITIATING CUE: In accordance with Step 5.3.10 of HC.OP-IO.ZZ-0006, PERFORM Section 5.1, Jet Pump Operability Verification, of HC.OP-ST.88-0007.

An Equipment Operator is standing by at Panel 1 OC619, Aux Bldg Control Area El. 102', to obtain individual Jet Pump dp's. Another operator will perform the rest of the procedure.

Page 16of16 STATION:

Hope Creek SYSTEM: Administrative JOB PERFORMANCE MEASURE TASK NUMBER: 2990090301 TASK: Generate An SAP System Valve/Breaker Alignment COPY OF JPM NUMBER: 305H-JPM.ZZ048

[RO A2] REVISION:

00 SAP BET: NOH05JPZZ48E K/A NUMBER: 2.2.41 IMPORTANCE FACTOR: RO: 3.5 SRO: 3.9 ALTERNATE PATH: D APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

M-51-1 Sheet 2, Rev. 42 OP-AA-109-115, Rev. 7 TOOLS, AND EQUIPMENT:

Mechanical P&IDs, M-00-0 through M-104-0 ESTIMATED COMPLETION TIME: __ 1_6'----_

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

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014

---'-=-"---'=-=-..c-'---

Training Department Page 1of8 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2990090301 TASK: Generate An SAP System Valve/Breaker Alignment INITIAL CONDllTONS:

1. The plant is operating at 100% power. 2. The Residual Heat Removal (RHR) System is in its normal standby lineup. 3. A small leak (approximately 1 gallon per hour) has developed on the suction piping to RHR Pump AP202 between HV-F004A, RHR PMP A SUP POOL SUCT, and the pump. INITIATING CUE: The affected pipe needs to be ISOLATED, VENTED, AND DRAINED to perform repairs.

Using controlled station Mechanical Drawings:

1. IDENTIFY the Mechanical components that are required to be tagged, and their required positions.

2. IDENTIFY the Electrical components that are required to be tagged. Identification of Electrical breaker number(s) is(are) NOT required.

Page 2 of 8 JPM NUMBER: ZZ048 NAME:

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: OP-AA-109-115 4.1.2 Determine Blocking Points and Tag Types (Initiator)

1. Review the following:

Operator obtains M-51-1, Sheet 2. -Controlled Documents and Drawings from the TOR or DCRMS. If ... -Select blocking points Operator determines the blocking and tag types. points AND required positions by reviewing the controlled drawings.

Applicant identifies the following mechanical isolation valves: * *HV-F004A, RHR PMP A SUP POOL SUCT, SHUT * *v10s, RHR PMP A DSCH VLV, SHUT * *V129, RHR PMP A MIN FL VLV ISLN VLV, OR HV-F007A, RHR PUMP A MIN FLOW MOV, SHUT * *HV-F006A(V104),

RHR PMP A(B) SUCT FROM RECIRC, SHUT(normally closed)

V142(V141),

RHR PMP A SUCT HOR TO RW SUP V, SHUT(normally locked closed) Applicant identifies the following mechanical VENT paths (valves in the OPEN position):

*V143 AND V144 Page 3 of 8 JPM NUMBER: REV NUMBER: STEP NUMBER ZZ048 00 ELEMENT NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD Applicant identifies the following mechanical DRAIN valves in the OPEN position:

*V293 AND V294

V145 AND V146 Applicant identifies the following ELECTRICAL components required to ISOLATE the leak: * *HV-F004A

[MCC 1 OB212 Breaker 52-212031] * *AP202 [1 OA401, Breaker 52-40106

] Examiner Note: Breaker numbers are not critical.

SAT/ UNSAT COMMENTS (Required fa UNSAT) 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 JPfl.. complete".

STOP TIME: Task Standard:

Operator IDENTIFIES the mechanical and electrical components, and their required positions, to ISOLATE, VENT, AND DRAIN the affected pipe using controlled station Mechanical Drawings as noted. Page 4 of 8 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ZZ048 NAME: --------------

00 DATE: SAT D UNSAT D SAT D UNSAT D Page 5 of 8 JOB PERFORMANCE MEASURE JPM NUMBER: ZZ048 REVISION HISTORY Rev# Date Description Validation Required?

00 11/7/2014 Modified ZZ046. Validated with 2 ROs. Validation Time was 16 y minutes.

00 1/22/2015 Added non-Critical Standard as possible response.

N Page 6 of 8 r x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ048 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Generate An SAP System Valve/Breaker Alignment Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date J. NERE RO ON FILE 11/7/2014 Name Qua I Signature Date Page 7 of 8 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is operating at 100% power. 2. The Residual Heat Removal (RHR) System is in its normal standby lineup. 3. A small leak (approximately 1 gallon per hour) has developed on the suction piping to RHR Pump AP202 between HV-F004A, RHR PMP A SUP POOL SUCT, and the pump. INITIATING CUE: The affected pipe needs to be ISOLATED, VENTED, AND DRAINED to perform repairs.

Using controlled station Mechanical Drawings:

1. IDENTIFY the Mechanical components that are required to be tagged, and their required positions.

2. IDENTIFY the Electrical components that are required to be tagged. Identification of Electrical breaker number(s) is(are) NOT required.

Page 8 of 8 ,

JOB PERFORMANCE MEASURE STATION:

Hope Creek COPY OF SYSTEM: Emergency/ECG/E-Plan/Fire

& Medical TASK NUMBER: TASK: Perform the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form JPM NUMBER: 305H-JPM.ZZ014

[RO A4] REVISION:

02 SAP BET: NOH05JPZZ14E KIA NUMBER: 2.4.30 IMPORTANCE FACTOR: RO: 2.7 SRO: 4.1 ALTERNATE PATH: D APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

EP-HC-111-F8, Rev. 8 TOOLS, AND EQUIPMENT:

Black pen SRO cgj ESTIMATED COMPLETION TIME: 7 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes -----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-8-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-8-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of11 JOB PERFORMANCE MEASURE SYSTEM: Emergency/ECG/E-Plan/Fire

& Medical TASK NUMBER: TASK: Perform the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form INITIAL CONDllTONS:

1. You are the On-Shift Reactor Operator.

2. The plant has experienced a LOCA followed by a LOP. 3. An Alert has been declared.

4. The Secondary Communicator has submitted the Major Equipment and Electrical Status (MEES) Form for your review. INITIATING CUE: PERFORM the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form. Page 2of11 JPM NUMBER: 305H-JPM.ZZ014 NAME: REV NUMBER: 02 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: B.1.a. OBTAIN Licensed Operator Examiner Note: See attached review. completed form. Examiner Note: PCIG compressors may be marked as OUT OF SERVICE(N) or as IN SERVICE(Y).

Operator reviews the provided Major Equipment and Electrical Status (MEES) Form, while walking-down the control room boards. *operator observes that CRD Pump B is not available due to breaker clearance and corrects the Form. CUE: IF the operator asks for the status of BC663, B Hydrogen Recombiner, state that "it is not in service, but is available."

[Equipment is Not available in the simulator.]

operator observes that RHR Pump A is Out of Service (or not available) based on indications of pump not running and/or inoperable

breaker, and corrects the form [N or X]. *operator initials the Major Equipment and Electrical Status (MEES) Form. 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: Task Standard:

Operator performs the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form. Page 3of11 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION 305H-JPM.ZZ014 NAME: ------------

02 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 4of11 JOB PERFORMANCE MEASURE JPM NUMBER: 305H-JPM.ZZ014 REVISION HISTORY Rev# Date Description Validation Required?

02 10/31/2014 Revised format. Updated Simulator Initial Conditions.

Validated y with 2 ROs. Validation Time 7 minutes.

Incorporated comments on RHR pump and CRD pump status. Page 5of11 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 305H-JPM.ZZ014 REV#: 02 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Perform the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO R. KEFER RO ON FILE 10/31/2014 Name Qua I Signature Date J. KOSKEY RO ON FILE 10/31/2014 Name Qua I Signature Date Page 6of11 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 305H-JPM.ZZ014 RESET to 100% power IC. REV#: 02

\ initial \ Description PLACE bezel covers over CRD Pump BP207 ---PLACE INFO Cover over breaker 52-44014 INSERT Override INSERT Malfunctions PLACE Simulator in RUN TAKE Scram Actions RESTORE 1 E Breakers, EXCEPT 52-44014

---RESTORE PCIG ALLOW conditions to stabilize PLACE Simulator in FREEZE ---MARKUP MEES with CRD Pump Bas "N", and RHR Pump A as "Y" Initial ET Event code:

Description:

Initial @Time Event Action None None Insert malfunction RR31 A2 to 100.00000 None None Insert malfunction QQ20 to SHORT None None Insert malfunction EG12 after 120 Page 7of11 Description Recirc loop A large break [V] (10%-6000 gpm, 100%-60000 gpm) RHR pump AP202 Malfunctions Loss of all off site power --: <tV JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

<SCHEDOLE:

Initial @Time Event Action Initial @Time Event Action Description Description None None Insert override 3A83_F _LO to Off BP207 STOP (LO) Page 8of11

1 MEES JOB PERFORMANCE MEASURE I EXAMINER'S COPY I EP-HC-111-FS ATT8 Page 7of13 HOPE CREEK DATE: Today MAJOR EQUIPMENT AND ELECTRICAL STATUS (MEES) UPDATE TIME: Now REACTIVITY ELECT. CONTAINMENT ELECT. CONTROL FEED YIN CONTROL FEED YIN Instructions:

SLCPUMPS A B2I2 N FRVS RECIRC A B410 y Y = IN SERVICE B B222 N FANS E B450 y N =OUT OF SERVICE RWCUPUMPS A B254 x 11 B B420 y ("X" OUT UNAVAILABLE EQUIPMENT)

B B264 x F B460 y REACTOR A AilO c B430 y RECIRC PUMPS B AI20 D B440 y WATER COOLING ELECT. CRDPUMPS A B430 SVENT A B2I2 y YIN SYSTEMS FEED B BA A(i v 1'.T II FANS B B222 y SW PUMPS A A401 y ELECTRICAL STATUS H2 A B410 N c A403 y YIN RECOMBINERS B B480 N B A402 y OFFSITE AC POWER AVAILABLE x PCIG A B232 y D A404 y EMERGENCY DIESELS RUN LOADED COMPRESSORS B B242 y SACS PUMPS A A401 y EDG A y y SERVICE AIR ELECT. c A403 y B y y COMPRESSORS FEED YIN B A402 y c y y OOK107 AI20 x D A404 y D y y IOK107 AIIO x RACSPUMPS A B4I5 N HVAC ELECT. EMER. INST. AIR ELECT. B B426 N FEED YIN COMPRESSOR FEED YIN c B250 ,, x TURBINE BLDG A Al IO x IOKIOO B450 x CIRC WATER A A50I x CHILLED WATER B AI20 x ECCS ELECT. PUMPS B A502 x CHILLERS c AIOI x FEED YIN c A50I x D AIIO x RHRPUMPS A A401 . lf. ,., ... A D A502 x TURBINE BLDG A Bl30 x c A403 y CONDENSATE/

ELECT. CHILLED WATER B BI20 x B A402 y FEEDWATER FEED YIN CIRCPUMPS c BIIO x D A404 y PRIMARY A Al IO x CONTROL AREA A B43I y RCICPUMPS STEAM x CONDENSATE B A120 x CHILLED WATER HPCIPUMPS STEAM x PUMPS c Al02 x CIRCPUMPS B B44I y CORE SPRAY A A40I y SECONDARY A AllO x CONTROL AREA A A403 y PUMPS c A403 y CONDENSATE B Al20 x CHILLED WATER B A402 y PUMPS c Al04 x CHILLERS B A404 y D A404 y FEED A STEAM x TSC A B45I y WATER B STEAM x CHILLED WATER PUMPS c STEAM x CIRCPUMPS B B46I y TSC A A40I y CHILLED WATER CHILLERS B A402 y LICENSED OPERATOR REVIEW: Initials INITIALS Page 9of11 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. You are the On-Shift Reactor Operator.

2. The plant has experienced a LOCA followed by a LOP. 3. An Alert has been declared.

4. The Secondary Communicator has submitted the Major Equipment and Electrical Status (MEES) Form for your review. INITIATING CUE: PERFORM the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form. Page 10of11

, MEES -JOB PERFORMANCE MEASURE I TRAINING ONL y I EP-HC-111-FS ATT8 Page 7of13 HOPE CREEK DATE:

MAJOR EQUIPMENT AND ELECTRICAL STATUS (MEES) UPDATE TIME: Now REACTIVITY ELECT. CONTAINMENT ELECT. CONTROL FEED YIN CONTROL FEED YIN Instructions:

SLCPUMPS A B212 N FRVS RECIRC A B410 y Y = IN SERVICE B B222 N FANS E B450 y N =OUT OF SERVICE RWCUPUMPS A B254 x B B420 y ("X" OUT UNAVAILABLE EQUIPMENT)

B B264 x F B460 y REACTOR A AllO x c B430 y RECIRC PUMPS B A120 x D B440 y WATER COOLING ELECT. CRDPUMPS A B430 N FRVS VENT A B212 y SYSTEMS FEED YIN B B440 N FANS B B222 y SW PUMPS A A401 y ELECTRICAL STATUS 2 A B410 N c A403 y YIN .fNFR<;:

B B480 N B A402 y OFFSITE AC POWER AVAILABLE x CIG A B232 y D A404 y EMERGENCY DIESELS RUN LOADED SORS B B242 y SACS PUMPS A A401 y EDG A y y SERVICE AIR ELECT. c A403 y B y y COMPRESSORS FEED YIN B A402 y c y y OOK107 A120 x D A404 y D y y 10K107 A110 x R 'PUMPS A B415 N HVAC ELECT. EMER. INST. AIR ELECT. B B426 N FEED YIN COMPRESSOR FEED YIN c B250 x TURBINE BLDG A AllO x lOKlOO B450 x CIRC WATER A A501 x CHILLED WATER B A120 x ECCS ELECT. PUMPS B A502 x CHILLERS c AIOI x FEED YIN c A501 x D AllO x RHRPUMPS A A401 y D A502 x TURBINE BLDG A Bl30 x c A403 y CONDENSATE/

ELECT. CHILLED WATER B B120 x B A402 y FEEDWATER FEED YIN CIRCPUMPS c BllO x D A404 y PRIMARY A A110 x CONTROL AREA A B431 y RCICPUMPS STEAM x CONDENSATE B A120 x CHILLED WATER HPCIPUMPS STEAM x PUMPS c A102 x CIRCPUMPS B B441 y CORE SPRAY A A401 y SECONDARY A A110 x CONTROL AREA A A403 y PUMPS c A403 y CONDENSATE B A120 x CHILLED WATER B A402 y PUMPS c A104 x CHILLERS B A404 y D A404 y FEED A STEAM x TSC A B451 y WATER B STEAM x CHILLED WATER PUMPS c STEAM x CIRCPUMPS B B461 y TSC A A401 y CHILLED WATER CHILLERS B A402 y LICENSED OPERATOR REVIEW:

INITIALS Page 11 of 11 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Equipment Control COPY TASK NUMBER: 4010590202/2990640305 TASK: Complete an Action Statement Log Sheet JPM NUMBER: 305H-JPM.ZZ029

[SRO A1-1] REVISION:

05 SAP BET: NOH05JP29E K/ANUMBER:

2.1.18 IMPORTANCE FACTOR: RO: 3.6 ALTERNATE PATH: D APPLICABILITY:

EO D EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-HC-108-115-1001 Rev 27 HC.OP-ST.GS-0003 Rev 8 Tech Spec 3.6.4.2 Amendment 194 HG Technical Specifications TOOLS, AND EQUIPMENT:

OP-HC-108-115-1001 Attachment 3-1, OP-HC-108-115-1001, Form 1; Blank HC.OP-ST.GS-0003 ESTIMATED COMPLETION TIME: 11 OF SRO: 3.8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes -----JPM PERFORMED BY: GRADE: SATO UNSATD ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1 of 19 JOB PERFORMANCE MEASURE SYSTEM: Equipment Control TASK NUMBER: 4010590202/2990640305 TASK: Complete an Action Statement Log Sheet INITIAL CONDllTONS:

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

(Last performed Satisfactorily 20 days ago.) 2. The GS-PSV-5032 failed to stroke open when tested. 3. Local observation confirms the valve is failing to stroke and the valve fully closed. 4. All other valves passed the surveillance.

5. The failure occurred one hour ago at . (NOTE: ENTER Current Time minus one hour here AND on the Trainee's Cue Sheet.) 6. SAP is currently unavailable, and no NOTF has been written.

7. SAP LCO Tracking is NOT available.

INITIATING CUE: You are the CRS. COMPLETE a manual Action Statement log entry for the failure of GS-PSV-5032, AND SUBMIT for CONCURRENCE REVIEW in accordance with OP-HC-108-115-1001.

Determination of retests is NOT required at this time. NOTE: A blank copy of HC.OP-ST.GS-0003 is provided for reference.

Page 2of19 JPM NUMBER: ZZ029 REV NUMBER: 05 STEP NUMBER ELEMENT NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD CUE: PROVIDE the operator the initiating cue AND:

A blank OP-HC-108-115-1001 Attachment 3-1

Copy of OP-HC-108-115-1001

A blank OP-HC-108-115-1001 Form 1

Copy of HC.OP-ST.GS-0003

Technical Specifications SAT/ UNSAT CUE: PROVIDE the operator the Initiating Cue [ENTER Current Time minus one hour] AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: ----Operator determines beginning step of the procedure.

Operator determines correct beginning step to be 5.3.1 . 5.3.1 Any time it is determined that a Operator determines a TIS LCO 5.3.2 TECH SPECS/Tech Spec must be entered.

Implementation SSC is or will be INOPERABLE either due to a Condition Adverse to Quality identified via the NOTF process (Section 5.1 ), a planned activity (Section 5.2), or following a Plant Transient, the appropriate TIS LCO/Tech Spec Implementation Action Statement is entered.

DETERMINE if the T/S LCO/Tech Spec Implementation Action Statement is ACTIVE or TRACKING based on the following criteria:

N/A Page 3of19 N/A COMMENTS (Required for UNSAT) N/A JPM NUMBER: ZZ029 NAME: ----

REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fc STANDARD UNSAT) ACTIVE: An Active TIS Operator determines failure LCO/T ech Spec requires ACTIVE LCO due to Implementation Action INOPERABLE SSC and the SSC Statement is entered for those design function is specifically conditions where the SSC is required to be OPERABLE in the INOPERABLE and the SSC current Operational Condition by design function is specifically Technical Specification 3.6.4.2.

required to be OPERABLE in the current Operational Condition by Technical Specifications/Tech Spec Implementation.

An example of an Active TIS LCO/Tech Spec Implementation Action Statement is a failure of an Emergency Diesel Generator to satisfy its surveillance requirements in Operational Condition

1. TRACKING:

A Tracking T/S Operator determines failure LCO/Tech Spec requires ACTIVE LCO due to Implementation Action absence of 100% redundant Statement is entered whenever equipment IAW T/S 3.6.4.2.

any of the following conditions exists: ... 5.3.3 lE the cause of the SSC being Operator determines the cause INOPERABLE is a planned was NOT planned and this step Operations, Maintenance, does NOT apply. Radiation Protection, or Chemistry Evolution that satisfies the following criteria:

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

5.3.4 For short duration entry into a Operator determines that this step Tech Spec Action statement for does not apply. unplanned transient conditions (i.e. less than one shift), the Control Room Narrative Log may be used to track the LCO entry and exit time. The entry should contain the following information:

... 5.3.5 For activities that cause a Operator determines the cause TECH SPECS/Tech Spec does NOT meet the criteria of Implementation SSC to be Section 5.3.3 and the following INOPERABLE that do not meet steps apply to document the the criteria of Section 5.3.3, condition.

DOCUMENT the condition as follows:

... Page 4of19 JPM NUMBER: ZZ029 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) NOTE: TS LCO/Tech Spec Implementation Action Statement Tracking may be accomplished using either the Operator reads NOTE. computerized SAP LCO Tracking System or Attachment 3-1 and Form

1. 5.3.5.1 For SAP LCO tracking, REFER Based on Initial Conditions TO guidance provided in OP-(Electronic LCO Tracking NOT AA-108-115-1001, SAP LCO available),

operator recognizes this Entry. step does NOT apply. NOTE: Preparation of Form 1 is not limited to the SM/CRS. Form 1 may be prepared by appropriate personnel in advance to support planned activities or, after the fact during plant transients.

During normal operations, the Operator reads NOTE. SM/CRS remains responsible for the accuracy of the information provided and authorizing entry into T/S LCO/Tech Spec Implementation Action Statements.

5.3.5.2 For LCO tracking using Based on Initial Conditions Attachment 3-1 and Form 1, (Electronic LCO Tracking NOT PEFORM the following:

available) and Initiating Cue, operator recognizes the following steps apply. A. ASSIGN the next consecutive Operator determines that this is the LCO Index Number obtained first entry for the current year from the Action Statement Log (CUE) and .. Index (Attachment 3-1) ... CUE: "This is the first LCO of the new year." A. ... and LOG the T/S LCO/Tech Operator assigns log number YY-(CONT) Spec Implementation ACTION 001 from Attachment 3-1. Statement on the Index. J.E this is the first LCO of the new year, I ENSURE the first two digits I reflect the proper year (i.e.12-001). Page 5of19 JPM NUMBER: ZZ029 NAME: ----

REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fc STANDARD UNSAT) B. IF the unit is shutdown, Operator determines the unit is not COMPLETE the Mode shutdown and leaves field blank. Restraint column by indicating Yes or No AND the restricted mode number, OTHERWISE leave blank. C. COMPLETE Sections 1 and 2 of Form 1 by performing the following:

-RECORD the LCO Index Operator records YY-001 in LCO Number (from Attachment INDEX NUMBER. [YY=Year]

3-1) -RECORD the LCO Status Operator records *ACTIVE in LCO (Active I Tracking)

STATUS. -RECORD the applicable Operator records *3.6.4.2 in TECH Technical Specification/

SPEC NUMBER. Tech Spec Implementation LCO number. When an INOPERABLE TECH SPECS/Tech Spec Implementation SSC affects multiple LCO Action Statements, RECORD the LCO number with the most limiting Action Time. -RECORD the Date/Time Operator records *current date Entered.

and *failure time from Initial Conditions in DATE/TIME ENTERED.

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

the LCO. -RECORD the expiration Operator records a Date/Time of Date/Time.

failure time plus 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in DATE/TIME ACTION REQUIRED.

Page 6of19 JPM NUMBER: ZZ029 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) -RECORD the Date/Time Operator records a Date/Time of Action Required.

When *failure time plus 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in recording the date and time DATE/TIME ACTION REQUIRED.

that Action is required for an LCO Action Statement that has multiple

actions, use the most limiting Action time. For Tracking Action Statements, record 'N/A'. -RECORD Other Applicable Operator recognizes no other TIS TIS. List only active LCOs. apply and leaves blank. Applicable tracking LCOs should be listed separately in the Summary Description of the Log Sheet. -RECORD the Equipment Operator records GS-PSV-5032, or description.

similar in EQUIPMENT.

-Briefly STATE the reason Operator enters verbiage from TIS for the SSC condition in the 3.6.4.2 Action a. or similar.

Summary Description section and include a brief summary of actions required, including submittal of any special reports to the NRC. NOTIFY the Shift Operations Superintendent of any reporting requirements.

Page 7of19 JPM NUMBER: ZZ029 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fc STANDARD UNSAT) -For unavailable conditions Due to absence of compensatory associated with Fire in actions, operator determines these (A)(4) systems or Steps do not apply. components (refer to Exhibit 9) INITIATE Fire Department Notifications for required

... -The individual being notified will come to the Control Room and sign the NOTIF# box next to ... -For unavailable conditions associated with Fire in (A)(4) systems or components

... -For recurring

samples, analysis, hook-up of sample equipment, etc., the departmental

... -When actions are no longer required or an instrument is to be restored to the ... C. -ENSURE all applicable Operator leaves ORDER AND Non-Conforming WCD ADDENDUM blank, since Component/

Material none is available and (NCCM) Evaluations, determination of retests is NOT Notifications/

Orders, Work required IAW Initiating Cue. Clearance Documents (WCD) etc., are entered on the Order and WCD Addendum.

INCLUDE any surveillances required to restore the equipment to operability as part of the Addendum.

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

-RECORD Redundant Operator enters Y in REDUNDANT Equipment Operable (Y/N). EQUIPMENT OPERABLE.

D. IF the INOPERABLE SSC will Based on Initial Conditions impact Secondary Containment (OPCON 1 ), and absence of effect Integrity per TIS 3.6.5.1 -on Secondary Containment, during Fuel ... operator recognizes this step does not apply. Page 8of19 JPM NUMBER: ZZ029 NAME: REV NUMBER: 05 DATE: -------

STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) NOTE: For a planned entry into an action statement, SRO/STA concurrence is required,

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

If the person who completed Sections 1 and 2 of Form 1 (Step 5.3.5.2.B) was not an actively licensed and proficient SRO, or a qualified and Operator reads NOTE. proficient ST A, then the following step requires concurrence review from an actively licensed and proficient SRO, and/or a qualified and proficient ST A. The actively licensed and proficient SRO, and/or the qualified and proficient STA completing the concurrence review shall not be the same person who authorizes entry into the TECH SPECS/Tech Spec Implementation Action Statement in 5.3.4.B.5.

Page 9of19 JPM NUMBER: ZZ029 REV NUMBER: 05 STEP NUMBER E. ELEMENT OBTAIN CONCURRENCE REVIEW from an actively licensed and proficient SRO and/or a qualified and proficient STA of plant conditions, T/S, existing active and tracking action statements, and, the TIS Action Statement Log, to ensure the equipment can be, or, is properly removed from service (for unplanned entry into a TIS LCO/ Tech Spec Implementation Action Statement) and, that redundant equipment is operable.

For planned entry into a TIS LCO/ Tech Spec Implementation Action Statement, this review should be performed within a reasonable time prior to removal of the equipment from service to ensure plant conditions are reflective of conditions when the SSC will be removed form service.

[CD-079A] NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD Operator submits for CONCURRENCE REVIEW. SAT/ UNSAT COMMENTS (Required fc UNSAT) 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: Task Standard:

Operator COMPLETES a manual Action Statement log entry for the failure of GS-PSV-5032, AND SUBMITS for CONCURRENCE REVIEW in accordance with OP-HC-108-115-1001.

Page 10of19 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ZZ029 NAME:

05 DATE: SAT D UNSAT D SAT D UNSAT D Page 11 of 19 JOB PERFORMANCE MEASURE JPM NUMBER: ZZ029 REVISION HISTORY Rev# Date Description Validation Required?

01 12/6/2008 Converted JPM ZZ029 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.

Incorporation of significant governing procedure change requires validation.

02 6/1/2010 Updates all reference procedure revisions.

Validated with 2 y SROs. Avq validation time was 9 minutes.

03 12/30/2011 Updates all reference procedure revisions.

Editorial changes N only. No change to operator actions.

04 7/2/2013 Updates all reference procedure revisions.

Editorial changes N only. No chanqe to operator actions.

05 10/31/2014 Revised format and revision numbers.

Validated with 2 SROs. y Validation Time 11 minutes.

Incorporated comments.

05 1/22/2015 Added procedure identified in body of JPM to Tools and N Equipment.

Added Last Performed information to Initial Conditions.

Made editorial changes to Initial Conditions.

Page 12of19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ029 REV#: 05 x 1. x 2. x 3. x 4. x 5. x 6. ---x 7. x 8. x 9. x 10. x 11. x 12. x 13. ---x 14. x 15. TASK: Complete an Action Statement Log Sheet Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

SRO L. MYERS SRO ON FILE 10/31/2014 Name Qua I Signature Date M. CHARLES SRO ON FILE 10/31/2014 Name Qua I Signature Date Page 13of19

( :R 1 TECH SPEC NUMBER 3.6.4.2 JOB PERFORMANCE MEASURE EXAMINER'S COPY I ATTACHMENT 3-1 OP-HC-108-115-1001 Revision r Page 33 of& ... TECHNICAL SPECIFICATION ACTION STATEMENT LOG INDEX ACTIVE/ MODE PLANNED ENTRY EXPIRATIOI TRACKING RESTRAINT SUMMARY DESCRIPTION Y/N DATE/ DATE/TIME Y/N ** TIME CONDITIOI' ACTIVE y GSV-PSV-5032 N DATE/ (Date+ 72H)/T TIME -** !E unit mode changes, RE-EVALUATE and REVISE mode column as necessary.

Page 14of19 JOB PERFORMANCE MEASURE EXAMINER'S COPY FORM 1 OP-HC-108-115-1001

Revision 27 Page 95of98 TECHNICAL SPECIFICATION ACTION STATEMENT LOG Page 1of4 1.0 ACTION STATEMENT LOG SHEET LCO INDEX NUMBER: YY-001 LCO STATUS (ACTIVE/TRACKING):

Active TECH SPEC NUMBER: 3.6.4.2 DATE/TIME ENTERED:

Date/Time APPLICABILITY:

1, 2, 3 DATE/TIME EXPIRATION:

(Date+ 72H)/Time OTHER APPLICABLE T/S: DATE/TIME ACTION REQUIRED:

(Date+ 72H)/Time EQUIPMENT:

GS-PSV-5032, REACTOR BLDG TO SUPP CHAMBER VAC BRKR SUMMARY DESCRIPTION

{Include of Actions Reguired}

3.6.4.2-Restore the VAC Breaker assembly to status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least Hot Shutdown Within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . GS-PSV-5032 failed to open RESPONSIBLE DEPARTMENT NOTIFICATION{S}

SPECIAL REPORT REQUIRED YES 0 REPORT INITIATION DUE DATE N/A I NOTIFICATIONS FOR COMPENSATORY ACTIONS OR SURVEILLANCES*

NAME of DEPARTMENT NOTIFICATION NAME of PERSON NOTIF# and PERSON NOTIFIED (DATE/TIME)

MAKING NOTIFICATION (If applicable)

ENTRY I EXIT . NIA ::..

lE entry into an Action Statement or failure to meet an Action Statement time limitation requires the submittal of a special report to the NRG, THEN: ENSURE the responsible department is notified of the reporting requirements, AND, NOTIFY the SOS or other Operations Management within one hour, AND, ENSURE Station Regulatory Assurance is notified of the reporting requirements, AND, INITIATE a Notification IAW LS-AA-120, Notification Process.

REDUNDANT EQUIPMENT OPERABLE (Y/N) : y Entry has been logged in the Control Room Narrative logs (SM/CRS Initial)

Initials APPROVAL TO REMOVE FROM SERVICE, VERIFICATION OF REDUNDANT EQUIPMENT CONCURRENCE AUTHORIZATION Printed Name SRO/STA (print name) SM/CRS (print name) Signature Current Date/Time I SRO/STA (signature)

DATE/TIME SM/CRS (signature)

DATE/TIME Page 15of19 JOB PERFORMANCE MEASURE EXAMINER'S COPY FORM 1 OP-HC-108-115-1001 Revision 27 Page 96of98 TECHNICAL SPECIFICATION ACTION STATEMENT LOG Page 2 of 4 1.0 ORDER AND WCD ADDENDUM DR I NOTF I RESP. ORDER DESCRIPTION SYSTEM TASK/ DEPT/ STATUS WCD TYPE GROUP NUMBER PSV-5032 Failed to open GS NOTF H-0 HC.OP-ST.GS-0003 GS ST H-0 (Continue on Paqe 3) RETURN TO SERVICE (SM/CRS INITIAL OR N/A ALL BOXES) TAGS RELEASED, SYSTEM/EQUIPMENT FILLED & VENTED, RESTORED FOR OPERATION SURVEILLANCE RETESTS & SPECIAL TEST/ACTIONS COMPLETE RESPONSIBLE DEPARTMENTS

-INFORMED DCP TURNOVER CHECKLIST COMPLETED ACTION STATEMENT LOG INDEX UPDATED EXIT HAS BEEN LOGGED IN THE CONTROL ROOM NARRATIVE LOGS VERIFICATION OF OPERABILITY REQUIREMENTS AND SYSTEM RESTORATION CONCURRENCE AUTHORIZATION SRO/STA (print name) SM/CRS (print name) SRO/STA (signature)

DATE/TIME SM/CRS (signature)

DATE/TIME Page 16of19 JOB PERFORMANCE MEASURE EXAMINER'S COPY FORM 1 OP-HC-108-115-1001 Revision 27 Page 97 of 98 TECHNICAL SPECIFICATION ACTION STATEMENT LOG Page 3 of 4 1.0 ORDER AND WCD ADDENDUM(Continued)

INDEX NUMBER ___ YY_-0_0_1

__ _ Page Number_2_

of_ DR/ NOTF I RESP. ORDER DESCRIPTION SYSTEM TASK/ DEPT/ STATUS WCD TYPE GROUP NUMBER Page 17of19 JOB PERFORMANCE MEASURE EXAMINER'S COPY FORM 1 OP-HC-108-115-1001 Revision 27 Page 98of98 TECHNICAL SPECIFICATION ACTION STATEMENT LOG SHEET Page 4 of 4 3.0 DESCRIPTION ADDENDUM INDEX NUMBER ___ vv_-_00_1

__ _ Page Number_1 of_ DATE/TIME-Entered Unplanned Active LCO YY-001 for GS-PSV-5032 failure to open durinq performance of HC.OP-ST.GS-0003.

Page 18of19 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

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

(Last performed Satisfactorily 20 days ago.) 2. The GS-PSV-5032 failed to stroke open when tested. 3. Local observation confirms the valve is failing to stroke and the valve is fully closed. 4. All other valves passed the surveillance.

5. The failure occurred one hour ago at __ _ 6. SAP is currently unavailable, and no NOTF has been written.

7. SAP LCO Tracking is NOT available.

INITIATING CUE: You are the CRS. COMPLETE a manual Action Statement log entry for the failure of GS-PSV-5032, AND SUBMIT for CONCURRENCE REVIEW in accordance with OP-HC-108-115-1001.

Determination of retests is NOT required at this time. NOTE: A blank copy of HG.OP ST.GS-0003 is provided for reference.

Page 19of19 f JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Administrative TASK NUMBER: 2992320302 TASK: Review All Operations Logs In Use During A Shift Including Computer Logs COPY OF JPM NUMBER: 305H-JPM.ZZ049

[SRO A1-2] REVISION:

00 SAP BET: NOH05JPZZ49E K/A NUMBER: 2.1 .. 25 IMPORTANCE FACTOR: RO: 3.9 SRO: 4.2 ALTERNATE PATH: D APPLICABILITY:

EO D ROD STAD EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-HC-108-116-1001, Rev. 2 HC.OP-DL.ZZ-0020, Rev. 38 TOOLS, AND EQUIPMENT:

MODIFIED OP-HC-108-116-1001(Attachment1 Dates Modified);

Straight-edge ESTIMATED COMPLETION TIME: 8 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of8 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2992320302 TASK: Review All Operations Logs In Use During A Shift Including Computer Logs INITIAL CONDllTONS:

1. Plant is operating at 100% power fifteen (15) days following the last refueling outage ending on 2/10/2015.

2. Fuel Pool Cooling Heat Exchanger AE202 is isolated for maintenance.

3. GRIDS A3175, FUEL POOL HX COMMON INLET TEMP, indicated 93F. 4. The Reactor Operator is performing Step 3.6.7 of HC.OP-DL.ZZ-0020, SUNDAY SHIFT ROUTINE LOG. 5. The Reactor Operator has provided a completed Attachment 3 of OP-HC-108-116-1001, Spent Fuel Pool Decay Heat Load Determination.

INITIATING CUE: PERFORM the CRS review of Attachment 3 of OP-HC-108-116-1001, Spent Fuel Pool Decay Heat Load Determination.

Page 2 of 8 '

f JPM NUMBER: ZZ049 NAME: REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator:

the initiating cue; completed copy of OP-HC-108-116-1001 Attachment 3; a modified copy of OP-HC-108-116-1001(Attachment1 Date Modified and marked NOT FOR PLANT USE); AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: OP-HC-108-116-1001 4.4 Submit the completed time to N/A N/A N/A CRS for review. OP-HC-108-116-1001

4. MAIN BODY 4.1 Utilizing Attachment 1, Spent *#operator determines that the Fuel Pool Decay Heat Load approximate SFP decay heat rate Determination, determine the for the current date is approximate SFP decay heat approximately 8.5 [+/-0.3) MBtu/hr.

rate for the current date. 4.2 Select the series of curves from *# Operator selects Page 6 of Attachment 2 for loss of ATTACHMENT 2 (rounding up 93 cooling, with the initial pool to 95). temperature that most closely matches current pool temperature, (round up to the next highest Fuel Pool Temperature curve). 4.3 Utilizing the decay heat rate *# Operator determines the time determined in 4.1, determine in hours for the SFP to reach the time in hours for the SFP to 200°F in the event normal reach 200 °F in the event cooling is lost is approximately normal cooling is lost. IF 45 [+/-3] hours. Therefore, necessary, interpolate the heat Attachment 3 is NOT properly load between lines. completed in accordance with OP-HC-108-116-1001.

CUE: If the operator does NOT correct the calculation, ask "What would be the correct number of hours to reach 200°F?" 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: Task Standard:

Operator performs the CRS review of Attachment 3 of OP-HC-108-116-1001, Spent Fuel Pool Decay Heat Load Determination.

Page 3 of 8 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ZZ049 NAME: ------------

00 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 4 of 8 '

, JOB PERFORMANCE MEASURE JPM NUMBER: ZZ049 REVISION HISTORY Rev# Date Description Validation Required?

00 10/31/2014 New JPM. Validated with 2 SROs. Validation Time 8 minutes.

y 00 1/22/2015 Added that referenced procedure needs to have the chart dates N modified to support the date in the Initial Conditions provided in the JPM. Mark the modified procedure as Not for Plant Use. Moved provide copy of procedure to a previous Cue. Page 5 of 8 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ049 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Review All Operations Logs In Use During A Shift Including Computer Logs Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

SRO L. MYERS SRO ON FILE 10/31/2014 Name Qua I Signature Date M. CHARLES SRO ON FILE 10/31/2014 Name Qua I Signature Date Page 6 of 8 '

f TRAINING ONLY ATTACHMENTl OP-HC-108-116-1001 Revjsion 2 Page -13 of 13 Spent Fuel Pool Time to 200 °F 54 Hrs Page 7 of 8 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Plant is operating at 100% power fifteen (15) days following the last refueling outage ending on 2/10/2015.

2. Fuel Pool Cooling Heat Exchanger AE202 is isolated for maintenance.

3. GRIDS A3175, FUEL POOL HX COMMON INLET TEMP, indicated 93F. 4. The Reactor Operator is performing Step 3.6.7 of HC.OP-DL.ZZ-0020, SUNDAY SHIFT ROUTINE LOG. 5. The Reactor Operator has provided a completed Attachment 3 of OP-HC-108-116-1001, Spent Fuel Pool Decay Heat Load Determination.

INITIATING CUE: PERFORM the CRS review of Attachment 3 of OP-HC-108-116-1001, Spent Fuel Pool Decay Heat Load Determination.

Page 8 of 8 STATION:

Hope Creek SYSTEM: Administrative JOB PERFORMANCE MEASURE TASK NUMBER: 2990400102 TASK: Ensure Plant Operations Are In Accordance With Technical Specifications JPM NUMBER: 305H-JPM.ZZ022

[SRO A2] REVISION:

01 SAP BET: NOH05JPZZ22E KJA NUMBER: 2.2.40 IMPORTANCE FACTOR: ALTERNATE PATH: APPLICABILITY:

EO D EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

HC.OP-ST.ZZ-0001, Rev. 36 TOOLS, AND EQUIPMENT:

Completed copy of HC.OP-ST.ZZ-0001.

E-0001-0 RO: 3.4 SRO: 4.7 ESTIMATED COMPLETION TIME: 11 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of24 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2990400102 TASK: Ensure Plant Operations Are In Accordance With Technical Specifications INITIAL CONDllTONS:

1. Emergency Diesel Generator AG400 was cleared and tagged due to scheduled maintenance and declared inoperable at 0700 yesterday.

It is expected to return in the next 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . (Not an extended outage.)

2. All previous performances of HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, have been completed satisfactorily and within the required Technical Specification time periods.

3. BS1-3, 500KV BUS SECTION 1-3 BKR, AND Station Power Transformer T1 were just cleared and tagged for maintenance.

The switchyards were re-aligned to support all tagging operations IAW the ESO instructions.

4. Salem Unit 3 Gas Turbine Generator is available.

5. Current River Temperature is 75F. Current River Level is 93 feet. 6. HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, is due. This procedure is being performed to satisfy Technical Specification Surveillance requirement 4.8.1 .1.1.a. INITIATING CUE: PERFORM the SM/CRS review of the HC.OP-ST.ZZ-0001.

RECORD any remarks on this Cue Sheet. Page 2 of 24 JPM NUMBER: REV NUMBER: STEP NUMBER ZZ022 01 ELEMENT NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD SAT/ UNSAT CUE: PROVIDE the operator the initiating cue, the copy of HC.OP-ST.ZZ-0001, AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. 5.9 START TIME: ___ _ SUBMIT this procedure to the SM/CRS for review AND completion of Attachment

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:

2.1.2 UNSATISFACTORY AND IF necessary the TIS ACTION statement has been implemented.

Operator completes Attachment 3, Step 3.1, and reviews the surveillance for completion and satisfactory performance.

operator determines (using E-0001 or equivalent) that the lineup is unsatisfactory based on the guidance in the note below the table, and includes this determination in section 2.1.4 of attachment

1. Examiner Note: The remarks made in 2.1.4 need to reflect the operator's decision to determine that the Surveillance is UNSATISFACTORY.

operator signs and dates the UNSATISFACTORY line of Attachment

1. *operator identifies that Technical Specification 3.8.1.1.c.

applies.

COMMENTS (Required for UNSAT) CUE: If the operator identifies and asks if T/S action statement(s) is(are) being implemented, inform the operator that "actions are being implanted in accordance with Technical Specifications."

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: ___ _ Task Standard:

Operator performs the SM/CRS review of a completed Surveillance Test. Page 3 of 24 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ZZ022 NAME: ------------

01 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 4of24 JOB PERFORMANCE MEASURE JPM NUMBER: ZZ022 REVISION HISTORY Rev# Date Description Validation Required?

00 Initial creation.

01 12/11/2014 Revised format. Updated procedure reference.

Significantly y modified the initial condition and outcome.

Revised based on validation comments.

Validated with 2 SROs. 01 12/11/2014 Added clarifying information to Initial Conditions.

Added print N noted in procedure to Tools and Equipment.

--Page 5of24 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ022 REV#: 01 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Ensure Plant Operations Are In Accordance With Technical Specifications Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

SRO M. DAVIS SRO ON FILE 12/10/2014 Name Qua I Signature Date G. MCKEOWN SRO ON FILE 12/11/2014 Name Qua I Signature Date Page 6of24 JOB PERFORMANCE MEASURE EXAMINER'S COPY HC.OP-ST.ZZ-0001(Q)

ATTACHMENT 1 SM/CRS DATA AND SIGNATURE SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 1of3 1.0 POST TEST INFORMATION 1.1 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:

1.1.1. SATISFACTORY (All acceptance criteria is marked SAT) SM/CRS Date-Time 1.1.2. UNSATISFACTORY AND !E necessary the T/S ACTION statement has been implemented.

Hope Creek Signature SM/CRS 1.1.3. Order No. Current Date-Time Date-Time Unsatisfactory due to 20X supplying both Station Service Transformers AX501 and BX501. Technical Specification 3.8.1.1, ACTION c applies.

Page 10 of 46 Page 7of24 Rev.36 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Emergency Diesel Generator AG400 was cleared and tagged due to scheduled maintenance and declared inoperable at 0700 yesterday.

It is expected to return in the next 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . (Not an extended outage.)

2. All previous performances of HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, have been completed satisfactorily and within the required Technical Specification time periods.

3. BS1-3, 500KV BUS SECTION 1-3 BKR, AND Station Power Transformer T1 were just cleared and tagged for maintenance.

The switchyards were re-aligned to support all tagging operations IAW the ESQ instructions.

4. Salem Unit 3 Gas Turbine Generator is available.

5. Current River Temperature is 75F. Current River Level is 93 feet. 6. HC.OP-ST.ZZ-0001, Power Distribution Lineup-Weekly, is due. This procedure is being performed to satisfy Technical Specification Surveillance requirement 4.8.1.1.1.a.

INITIATING CUE: PERFORM the SM/CRS review of the HC.OP-ST.ZZ-0001.

RECORD any remarks on this Cue Sheet. Page 8 of 24 PSEG Internal Use Only USE CATEGORY:

I PSEG NUCLEAR L.L.C. HOPE CREEK GENERATING STATION HC.OP-ST.ZZ-0001(Q)

-Rev. 36 POWER DISTRIBUTION LINEUP -WEEKLY

Packages and Affected Document Numbers incorporated into this revision:

CP No. CP Rev. AD No. Rev No.

The following OPEX were incorporated into this revision:

None

The following OTSCs were incorporated into this revision:

None REVISION SUMMARY 20596049 Page 1 of 1 None ../

Reformats Step 5.4.1 and substeps to make it more clear. HC was added to positively identify Hope Creek breakers.

The distribution table on Attachment 2 was updated.

This is an editorial change. TRAINING ONLY IMPLEMENTATION REQUIREMENTS Effective Date 3/1 /13 ------None TRAINING ONLY HC.OP-ST.ZZ-0001 (Qt POWER DISTRIBUTION LINEUP -WEEKLY TABLE OF CONTENTS Section 1.0 PURPOSE ........................................................................................................................................

2 2.0 PREREQUISITES

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

2 3.0 PRECAUTIONS AND LIMITATIONS

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

2 4.0 EQUIPMENT REQUIRED

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

2 5.0 PROCEDURE

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

3 6.0 RECORDS ........................................................................................................................................

6

7.0 REFERENCES

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

6 ATTACHMENTS Attachment 1, SM/CRS Data and Signature Sheet...

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

8 Attachment 2, In plant Data Sheet ............................................................................................................................

11 Attachment 3, Measuring and Test Equipment Data Sheet.. ...................................................................................

44 Attachment 4, Component Information Sheet .........................................................................................................

.45 Hope Creek Page 7 of 46 Rev.36 I TRAINING ONL y 1.0 PURPOSE HC.OP-ST.ZZ-0001 (Q) The purpose of this procedure is to ensure the Class 1 E electrical distribution is aligned pursuant to Technical Specification 4.8.3.1, 4.8.3.2, or 4.8.1.1.1.a.

2.0 PREREQUISITES 2.1 ENSURE permission to perform this test has been obtained from the SM/CRS as indicated by the completion of Attachment 1, Section 1.0. 2.2 ENSURE all personnel involved in the performance of this procedure, should complete Attachment 1, Section 3.0, prior to performing any part of this procedure.

2.3 ENSURE no other testing OR maintenance is in progress that will adversely affect the performance of this test. 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1. IF at any time during the performance of this test, a step cannot be completed or is observed to be unsatisfactory; immediately NOTIFY the NCO and the SM/CRS. [CD-927E]

3.2 Limitations None 4.0 EQUIPMENT REQUIRED

Fluke -Model 45 Hope Creek Page 7 of 46 Rev.36 TRAINING ONLY 5.0 PROCEDURE HC.OP-ST.ZZ-0001 (Q} 5.1 LOG test start time in the Control Room log(s). 5.2 ENSURE that all prerequisites have been satisfied IAW Section 2.0 of this procedure.

5.3 ENSURE Attachment 1, Section 1.0 of the SM/CRS Data and Signature Sheet has been completed and Regular Surveillance or Retest is indicated.

Correct voltages (not including 4.16KV 1 E Bus voltages) may be checked by local or remote indication, GRIDS, and/or proper equipment operation.

4.16KV 1 E Bus voltages may only be checked with GRIDS or FLUKE measurements IAW HC.OP-SO.MC-0001.

Alternate GRIDS point(s) may be used for 4.16KV 1 E Bus voltages as defined in note associated with 4.16KV 1 E Bus Voltage Readings.

250 VDC need not be performed when HPCI and/or RCIC are not required to be operable (i.e., condition 4 and 5). Only 2 channels may be required in Condition 4 or 5 (T/S 3.8.2.2 and 3.8.3.2) 5.4 !E performing this procedure to satisfy TIS Surveillance 4.8.1.1.1.a ONLY, PERFORM the following sections:

[T/S 4.8.1.1.1.a]

4.16KV SWITCHGEAR 1 OA401

4.16KV SWITCHGEAR 1 OA402

4.16KV SWITCHGEAR 1 OA403

4.16KV SWITCHGEAR 1 OA404

OFFSITE TO ONSITE DISTRIBUTION (continued on next page) Hope Creek Page 7 of 46 Rev.36

1 TRAINING ONL y HC.OP-ST.ZZ-0001(Q) 5.4.1. When in an extended outage for A or B EOG, PERFORM the following:

A. VERIFY, the following are available to supply Hope Creek #2 Station Power Transformer:

S3, Salem Gas Turbine Generator (Engine A, Engine Band not protected for Salem use, defense in depth) NIA J

Salem T-2, #2 Station Power transformer

Salem 20X, 500 KV BREAKER 1-8

Salem 21X, 500 KV BREAKER 2-8

Salem 31X, 500 KV BREAKER 2-10

HC T-2, #2 Station Power transformer

HC 2T60 STA XFMR T2 CIRCUIT SWITCHER

HC BS4-5, 13.8 KV 4-5 BKR

HC BS2-3, 13.8 KV 2-3 BKR

HC BX501, Station Service Transformer B. !E all of the required equipment is available for an extended outage for A or B EOG, THEN ENTER SAT on Attachment 2 for Salem Unit 3 under OFFSITE TO ONSITE DISTRIBUTION, OTHERWISE ENTER UNSAT. NIA J 5.5 RECORD M& TE identification numbers and calibration due dates for test equipment utilized for this test on Attachment 3 and the PSEG Nuclear Home Page. NIA J Hope Creek Page 7 of 46 Rev.36 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q)-The line-up provided in Attachment 2 verifies that the Class 1 E electrical distribution is aligned IAW Technical Specification requirements.

Indications other than those provided in Attachment 2 may be utilized to verify the required line-up.

This may be necessary due to maintenance, abnormal line-ups, etc. 5.6 PERFORM Power Distribution Lineup by completing Attachment

2. 5.7 IF any indication not specified in Attachment 2 was used to satisfy this surveillance THEN DOCUMENT AND JUSTIFY its use in Section 2.1.4 of Attachment

1. 5.8 LOG test end time in Control Room log(s). 5.9 SUBMIT this procedure to the SM/CRS for review AND completion of Attachment

1. Hope Creek Page 7 of 46 NIA R Rev.36 j I TRAINING ONL y 6.0 RECORDS HC.OP-ST.ZZ-0001 (Q) 6.1 RETAIN the following in accordance with RM-AA-101; Records Management Program:

Procedure cover page

Attachment 1 -SM/CRS Data and Signature Sheet

Attachment 2 -Power Distribution Lineup (include applicable pages)

Attachment 3 -Measuring and Test Equipment Data Sheet

7.0 REFERENCES

7.1 Drawings:

E-0001-0

E-0002-1, Shts. 1 & 2

E-0003-1

E-0004-1

E-0005-1, Shts. 1 & 2

E-0006-1, Shts. 1 & 2

E-0009-1, Shts. 1 -5

E-0011-1, Shts. 1 & 2

E-0012-1, Shts. 1 -5

E-0014-0

E-0015-0, Shts. 1 -3

E-0016-0

E-0018-1, Shts. 1 -3

E-0019-1, Shts. 1 & 2

E-0020-1, Shts. 1 & 2

E-0021-1, Shts. 1 -6

E-0022-1, Shts. 1 & 2

E-0023-1, Shts. 1 -4

E-1405-1, Shts. 9a, 1 Oa, 11 a, 12a 7.2 Commitment Document

CD-927E, (NRC INFO 87-25)

CM-HC-2011-0816, HC License Amendment 188, EOG A and B Allowed Outage Time Extension Hope Creek

CM-HC-2011-0818, HC License Amendment 188, EOG A and B Allowed Outage Time Extension Page 7 of 46 Rev.36 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q} 7.3 Other Documents

80054115

80058456

70038194, Non conservative 4.16 KV 1 E bus voltage values Engineering Evaluation H-1-PB-EEE-1832, Revision 3 (Associated with 70038194)

70038770, Excessive Voltage on 1 E buses

70040516, Attachment 2 readings and clarifying notes associated with 1 OA401 ( 1 OA402, 1 OA403, 1 OA404) 4KV 1 E Buses voltages

80075651, Engineering Evaluation H-1-PB-EEE-1832

70045071, Enter T/S 3.8.1.1.a versus T/S 3.8.3 7.4 New ABB-SSV-T Relays Installed IAW NUCP 80081967.

7.5 Main Power Transformer 1AX501 and 1 BX501 Load Tap Changer (L TC) Setpoints Adjusted IAW 20240642 and 20240460 Hope Creek Page 7 of 46 Rev.36

1 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 1 SM/CRS DATA AND SIGNATURE SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 2 of 3 1.0 PRETEST INFORMATION 1.1 Reason for the Test 1.1.1. Regular Surveillance NOTE For an extended outage on A or B EDG, refer to Step 5.4.1. 1.1.2. 4.8.1.1.1.a ONLY (SEE Step 5.4) 1.1.3. Retest/Other Initials J Initials Initials J 1.1.4. IF not performing the complete test, THEN LIST subsection(s) to be performed, as well as marking N/A on the applicable subsection(s) on the Attachment(s) that will not be performed, OR that do not require an independent verification IAW OP-AA-108-101-1002, Component Configuration Control.

SUBSECTION(S) 1 .2 Plant Conditions 1.2.1. Operational Condition 1 1.2.2. Reactor Power Level 100 1.2.3. MWe 1260 1.3 Permission to Perform the Test 1.3.1. Permission granted to perform this test. SM/CRS Date-Time Hope Creek Page 10 of 46 Rev.36 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 1 SM/CRS DATA AND SIGNATURE SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 3 of 3 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 criteria is marked SAT) SM/CRS Date-Time 2.1.2. UNSATISFACTORY AND IF necessary the T/S ACTION statement has been implemented.

SM/CRS Date-Time 2.1.3. Order No. Hope Creek Page 10 of 46 Rev.36

1 TRAINING ONLY ATTACHMENT 1 SM/CRS DATA AND SIGNATURE SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 4 of 3 3.0 PROCEDURE PERFORMER(S)

AND VERIFIER(S)

HC.OP-ST.ZZ-0001 (Q) 3.1 I have read and understand the steps of this procedure that I am required to perform.

(All Departments)

PRINT NAME SIGNATURE INITIALS DATE/TIME Jon Smith J Today-Now Tom Roberts Hope Creek Page 10 of 46 Rev.36 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 6 of 33 1.0 Power Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SAT/ PERF UN SAT CHANNEL A 4.16KV SWGR 10A401 40101 ALTERNATE FEEDER BKR OPEN 0 SAT R TO 10A401 40103 10A401 FEED TO 108450 CLOSED x SAT R 40107 EOG AG400 OUTPUT BKR OPEN CIT) (uNSAT R TO 10A401 40108 NORMAL FEEDER BKR CLOSED x SAT R TO BUS 1 OA401 40110 10A401 FEED TO 108410 CLOSED x SAT R IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON EACH STATION SERVICE TRANSFORMER (SST) (1AX5<>1, 1BX501)]

WITH TAP CHANGER IN AUTO, RECORD THE FOLLOWING READING (USE CRIDS AS PRIMARY INDICATION (FLUKE SECONDARY))

(NOTES 2,3,4,&6)

IF IN AN ABNORMAL BUS ALIGNMENT

[(3) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON (1) SST; OR, (4) 4.16 KV CLASS 1E BUSES AND (2) 4.16 KV NON-1E BUS ON (1) SST] (NOTES 2, 3, 4, & 6)

______

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 MIN/MAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage.

!E Bus Voltage is outside the MIN/MAX take Manual control of Load Tap Changer and ADJUST until voltage is within range. Voltage>

MAX with Load Tap Changer on 1 position is normal during certain conditions (i.e., HI grid voltage and/or no loads on bus.) (NOTE: If in a normal 2 bus alignment with tap changer in manual and voltage remains within established limits, tap changer should be returned to AUTO. (Refer to the appropriate GRIDS 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 T/S 3.8.1.1.a Action Statement.

!E Bus Voltage cannot be adjusted_:::

MAX, GENERATE notification to Hope Creek Electrical I 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, IAW Notification 20184742.

[70038770]

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

If in normal 2 bus (or less) alignment, any of the following GRIDS 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: A3210, A3487, A7076, A7071) Hope Creek Page 16 of 46 Rev.36 * * *

TRAINING ONLY HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 9 of 33 1.0 Power Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SAT/ PERF UNSAT CHANNEL C 4.16KV SWGR 1 OA403 40301 ALTERNATE FEEDER BKR OPEN 0 SAT R TO 10A403 40303 1 OA403 FEED TO 108470 CLOSED x SAT R 40307 EOG CG400 OUTPUT BKR OPEN 0 SAT R TO 10A403 40308 NORMAL FEEDER BKR TO CLOSED x SAT R 10A403 40310 1 OA403 FEED TO 108430 CLOSED x SAT R IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON EACH STATION SERVICE TRANSFORMER (SST) (1AX501, 1BX501)]

WITH TAP CHANGER IN AUTO, RECORD THE FOLLOWING READING (USE CRIDS AS PRIMARY INDICATION (FLUKE SECONDARY))

(NOTES 2,3,4,&6)

-

IF IN AN ABNORMAL BUS ALIGNMENT

[(3) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON (1) SST; OR, (4) 4.16 KV CLASS 1E BUSES AND (2) 4.16 KV NON-1E BUS ON (1) SST] (NOTES 2, 3, 4, & 6)

____

-* 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 MIN/MAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage.

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

Fluke (Model 45) Hookup and Voltage Readings at PT Secondary.

(4) IF Bus Voltage cannot be MIN, DECLARE the respective offsite circuit of the A.C. electrical power source INOP AND ENTER T/S 3.8.1.1.a Action Statement.

!E Bus Voltage cannot be adjusted_::

MAX, GENERATE notification to Hope Creek Electrical I 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, IAW Notification 20184742.

[70038770]

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

If in normal 2 bus (or less) alignment, any of the following GRIDS 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: A3210, A3487, A7076, A7071) * * *

Hope Creek Page 19 of 46 Rev.36 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 12 of 33 1.0 Power Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SAT/ PERF UN SAT CHANNEL B 4.16KV SWGR 1 OA402 40201 NORMALFEEDERBKRTO CLOSED x SAT R 10A402 40203 1 OA402 FEED TO 108460 CLOSED x SAT R 40207 EOG BG400 OUTPUT BKR TO OPEN 0 SAT R 10A402 40208 ALTERNATE FEEDER BKR TO OPEN 0 SAT R 10A402 40210 1 OA402 FEED TO 108420 CLOSED x SAT R IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON EACH STATION SERVICE TRANSFORMER (SST) (1AX501, 1BX501)]

WITH TAP CHANGER IN AUTO, RECORD THE FOLLOWING READING (USE CRIDS AS PRIMARY INDICATION (FLUKE SECONDARY))

(NOTES 2,3,4,&6)

IF IN AN ABNORMAL BUS ALIGNMENT

[(3) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON (1) SST; OR, (4) 4.16 KV CLASS 1E BUSES AND (2) 4.16 KV NON-1E BUS ON (1) SST] (NOTES 2, 3, 4, & 6)

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 MIN/MAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage.

!E Bus Voltage is outside the MIN/MAX take Manual control of Load Tap Changer and ADJUST until voltage is within range. Voltage>

MAX with Load Tap Changer on 1 position is normal during certain conditions (i.e., HI grid voltage and/or no loads on bus.) (NOTE: If in a normal 2 bus alignment with tap changer in manual and voltage remains within established limits, tap changer should be returned to AUTO. (Refer to the appropriate GRIDS 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) !E Bus Voltage cannot be adjusted.:::_

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

!E Bus Voltage cannot be MAX, GENERATE notification to Hope Creek Electrical I 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, IAW Notification 20184742.

[70038770]

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

If in normal 2 bus (or less) alignment, any of the following GRIDS 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: A3210, A3487, A7076, A7071) Hope Creek Page 22 of 46 Rev.36 * * * *

, I TRAINING ONL y HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 15 of 33 1.0 Power Distribution Lineup (Continued)

EQUIPMENT NOMENCLATURE REQUIRED ACTUAL SAT/ PERF UN SAT CHANNEL D 4.16KV SWGR 1 OA404 40401 NORMAL FEEDER 8KR CLOSED x SAT R TO 10A404 40403 1 OA404 FEED TO 108480 CLOSED x SAT R 40407 EOG DG400 OUTPUT 8KR OPEN 0 SAT R TO 10A404 40408 ALTERNATE FEEDER 8KR OPEN 0 SAT R TO 10A404 40410 1 OA404 FEED TO 108440 CLOSED x SAT R IF IN A NORMAL 2 BUS ALIGNMENT

[(2) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON EACH STATION SERVICE TRANSFORMER (SST) (1AX501, 1BX501)]

WITH TAP CHANGER IN AUTO, RECORD THE FOLLOWING READING (USE CRIDS AS PRIMARY INDICATION (FLUKE SECONDARY))

(NOTES 2,3,4,&6)

IF IN AN ABNORMAL BUS ALIGNMENT

[(3) 4.16 KV CLASS 1E BUSES AND (1) 4.16 KV NON-1E BUS ON (1) SST; OR, (4) 4.16 KV CLASS 1E BUSES AND (2) 4.16 KV NON-1E BUS ON (1) SST] (NOTES 2, 3, 4, & 6)

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 MIN/MAX may be indicative of a malfunctioning Transformer Load Tap Changer when in automatic.

COMPARE Bus Voltage with Station Service Transformer Sec. Voltage.

IF Bus Voltage is outside the MIN/MAX take Manual control of Load Tap Changer and ADJUST until voltage is within range. Voltage > MAX with Load Tap Changer on 1 position is normal during certain conditions (i.e., HI grid voltage and/or no loads on bus.) (NOTE: If in a normal 2 bus alignment 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) !E Bus Voltage cannot be adjusted.'."..

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

!E Bus Voltage cannot be 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, IAW Notification 20184742.

[70038770]

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

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

(For 1AX501: A3209, A3484, A7061, A7066) (For 1 BX501: A3210, A3487, A7076, A7071) * * *

Hope Creek Page 25 of 46 Rev.36 TRAINING ONLY HC.OP-ST.ZZ-0001 (Q) ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP -WEEKLY Page 24 of 33 1.0 Power Distribution Lineup (Continued)

EQUIP NOMENCLATURE I REQUIRED ACTUAL OFFSITE TO ONSITE DISTRIBUTION BS4-5 13KV BUS SECTION 4-5 BKR CLOSED x BS6-7 13KV BUS SECTION 6-7 BKR CLOSED x 2T60 STAXFMR T2 CIRCUIT SWITCHER CLOSED x 4T60 STA XFMR T4 CIRCUIT SWITCHER CLOSED x BS3-4 500KV BUS SECTION 3-4 BKR CLOSED x BS6-5 500KV BUS SECTION 6-5 BKR CLOSED x BS7-8 13KV BUS SECTION 7-8 BKR OPEN 0 -BS2-3 13KV BUS SECTION 2-3 BKR OPEN f x ) '-... BS1-2 13KV BUS SECTION 1-2 BKR CLOSED IC 0 ) BS9-0 13KV BUS SECTION 9-10 BKR CLOSED x 1T60 STA XFMR T1 CIRCUIT SWITCHER CLOSED \. 0 ) 3T60 STA XFMR T3 CIRCUIT SWITCHER CLOSED I' 0 ) \...._ BS1-3 500KV BUS SECTION 1-3 BKR CLOSED IC 0 ) BS5-1 500KV BUS SECTION 5-1 BKR CLOSED x BS2-6 500KV BUS SECTION 2-6 BKR CLOSED x BS2-4 500KV BUS SECTION 2-4 BKR CLOSED x Step Salem Unit 3 Gas Turbine Generator SAT# N/A 5.4.1.B SAT/ PERF UN SAT SAT R SAT R SAT R SAT R SAT R SAT R SAT R :_uNsAi)

R r ::---, ,UNSAT,..,

R SAT R rUNSAT""'

'-./ R R : UNSAV R SAT R SAT R SAT R N/A N/A + 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.

+ * * * * *

* * * * * * * * * * * !E actual alignment deviates from the above, CONSULT Electrical Drawing E-0001-0 to determine if proper separation exists, and IAW 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 !E all four of the 1 E infeed breakers are OPERABLE.

!E 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 EOG outage. REFER to Step 5.4.1 for a list of required equipment.

IF not required, THEN N/A. Hope Creek Page 34 of 46 Rev.36 STATION:

Hope Creek SYSTEM: Administrative JOB PERFORMANCE MEASURE TASK NUMBER: 2992470102 COPY OF TASK: Ensure Plant Operations are in Compliance with ODCM (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow) JPM NUMBER: 305H-JPM.ZZ050

[SRO A3] REVISION:

01 SAP BET: NOH05JPZZ50E K/A NUMBER: 2.3.11 IMPORTANCE FACTOR: RO: 3.8 SRO: 4.3 ALTERNATE PATH: D APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0026, Rev. 141 TOOLS, AND EQUIPMENT:

HC.OP-DL.ZZ-0026 ESTIMATED COMPLETION TIME: 10 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: __ N-'-/A-'---

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

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of12 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2992470102 TASK: Ensure Plant Operations are in Compliance with ODCM (Determine Liquid Radwaste Radiation Monitor; System Cooling Tower Slowdown Weir Flow) INITIAL CONDllTONS:

1. The plant is at 100% power. 2. Circulating Water Pump BP501 is tagged for motor replacement.

3. Circulating Water Pumps AP501, CP501, and DP501 are in service.

4. Service Water Pumps AP502, BP502, and DP502 are in service 5. Cooling Tower Slowdown Weir Flow Rate Monitor OSP-Rl4861 is reading blank, and is INOPERABLE.

TSAS 2015-001 was entered.

6. RM-11 point 9AX327 historical data is NOT available.

7. SSW Loop Flow GRIDS Point values as follows:

A2440 SERVICE WATER FLOW RATE DIV A= 13,560 gpm

A2441 SERVICE WATER FLOW RATE DIV B = 21,345 gpm INITIATING CUE: You are the Control Room Supervisor.

PERFORM the Control Room Supervisor review of the completed HG.OP DL.ZZ-0026, Attachment 1a, ITEM 47, Day Shift reading, AND Attachment 3y for the inoperable RMS Cooling Tower Slowdown Weir Flow Rate Monitor.

Page 2of12 JPM NUMBER: ZZ050 NAME: REV NUMBER: 01 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue, the completed copy of HG.OP DL.ZZ 0026 (both pages), AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: HC.OP-DL.ZZ-0026, Attachment 1 a ITEM SURVEILLANCE Operator reads ITEM 47. 47 CHANNEL CHECK: COOLING Operator determines the ITEM is TOWER SLOWDOWN WEIR applicable is the current Op FLOW RATE MONITOR Condition OSP-Rl4861 Operator reads the limits. ITEM 029 Operator observes Fl (Failed RM-11 (9AX327)

Instrument) is entered for the Day Shift. NOTE 45 CHANNEL CHECK SHALL Operator reads NOTE 45 and CONSIST OF VERIFYING determines that data is not INDICATION OF FLOW available from the Initial DURING PERIODS OF Conditions.

RELEASE.

CHANNELCHECK SHALL BE ... INST TRIPPED Operator observes Fl (Failed Instrument) is entered for the Day Shift. NOTE 33 TO OBTAIN VALUES 006 OR Operator reads NOTE 33 and 002, PRESS MON PB, KEY IN determines that data is not 006 OR 002, THEN ITEM PB. available from the Initial Conditions.

NOTE 35 TO OBTAIN VALUES 028, Operator reads NOTE 35 and 029, OR 073, PRESS MON determines that data is not PB, KEY IN 028, 029, OR 073, available from the Initial THEN ITEM PB. Conditions.

NOTE 46 IF INSTRUMENT IS INOP, Operator reads NOTE 46 and USE ATTACHMENT 3Y TO determines that Attachment 3Y is ESTIMATE WEIR FLOW. applicable.

THIS IS REQUIRED REGARDLESS OF WHETHER A RADIOACTIVE LIQUID RELEASE IS IN PROGRESS.

HC.OP-DL.ZZ-0026 Attachment 3Y Examiner Note: Refer to steps below and the Examiner Copy of Attachment 3Y for Standards associated with these steps. Page 3of12 JPM NUMBER: ZZ050 NAME: ----REV NUMBER: 01 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) DATE Operator verifies current date on Attachment 3Y. (Note: "TODAY" is acceptable)

METHOD 1 Operator determines data for Method 1 completion is not available and continues to METHOD 2. TIME Operator verifies current time on Attachment 3Y under Method 2 (Note: "Now" is acceptable for current time.) SSW LOOP A FLOW # Operator reads # Footnote

READ FROM FIT-2218A/B Operator determines A SSW Loop OR FR-2218-1/2 OR GRIDS Flow is 13,560 gpm from GRIDS A2440/A2441.

(B SSW point A2440 in the Initial LOOP FLOW (FIT-2218B)

IS Conditions, and that it is recorded OBTAINED LOCALLY AT correctly on Attachment 3Y under PANAMETRICS MONITOR.

'SSW LOOP A FLOW #'. FLOW VALUE IS THE AVERAGE VOLUMETRIC FLOW RATE WHICH IS DISPLAYED AS "AVG VOLUMETRIC GAL/MIN" ON THE MONITOR DISPLAY.

SSW LOOP B FLOW # Operator reads # Footnote

READ FROM FIT-2218A/B Operator determines B SSW Loop OR FR-2218-1/2 OR GRIDS Flow is 21,345 gpm from GRIDS A2440/A2441.

(B SSW point A2441 in the Initial Conditions LOOP FLOW (FIT-2218B)

IS and that it is recorded correctly on OBTAINED LOCALLY AT Attachment 3Y under 'SSW LOOP PANAMETRICS MONITOR.

B FLOW#'. FLOW VALUE IS THE AVERAGE VOLUMETRIC FLOW RATE WHICH IS DISPLAYED AS "AVG VOLUMETRIC GAL/MIN" ON THE MONITOR DISPLAY.

TOTAL SSW FLOW Operator verifies calculation of Total SSW Flow at 34,905 gpm by summing Loop A and Loop B flows. -EVAPORATIVE LOSSES*.

Operator reads* Footnote Page 4of12 JPM NUMBER: ZZ050 NAME: --------------REVNUMBER:

01 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)

REFERENCE PRINT 10855-Operator determines Evaporative M15-181-1 FOR Losses from

Footnote at bottom EVAPORATIVE LOSS of page for 3 Circ Water Pump ESTIMATES.

USE 16,700 operations is INCORRECTLY GPM FOR DEFAULT recorded as 16, 700gpm. VALUE(MIN.

DILUTION

operator determines correct FLOW), FOR EVAPORATIVE LOSS ESTIMATES IF 4 value of Evaporative Losses to CIRCULATING WATER be 12,500gpm (3 CW pumps in PUMPS ARE IN SERVICE, service) and enters the value OR 12,500 GPM IF ONLY 3 12,500 under EVAPORATIVE CIRCULATING WATER LOSSES* on ATT 3Y. PUMPS ARE IN SERVICE.

THIS BLOCK IS N/A IF THE COOLING TOWER IS OUT OF SERVICE.

CUE: If applicant asks, inform applicant that he/she is to correct any identified incorrect values. TOTAL WEIR FLOW Operator determines that recorded TOTAL WEIR FLOW of 18,205 gpm is incorrect.

Operator determines that recorded TOTAL WEIR FLOW should be 22,405gpm by subtracting Evaporative Losses (12,500 gpm) from Total SSW Loop Flow (34,905 gpm). *operator enters the correct value of 22,405 under TOTAL WEIR FLOW on ATT 3Y 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: Task Standard:

Operator performs the Control Room Supervisor review, and correction, of Surveillance Log. Page 5of12 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ZZ050 NAME:

01 DATE: SAT D UNSAT D SAT D UNSAT D Page 6of12 JOB PERFORMANCE MEASURE JPM NUMBER: ZZ050 REVISION HISTORY Rev# Date Description Validation Required?

01 10/31/2014 Revised format. Updated procedure reference.

Validated with 2 y* SROs. Validation Time 10 minutes.

Page 7of12 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ050 REV#: 01 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Ensure Plant Operations are in Compliance with ODCM (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow) Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

SRO M. CHARLES SRO ON FILE 10/31/2014 Name Qua I Signature Date L. MYERS SRO ON FILE 10/31/2014 Name Qua I Signature Date Page 8of12 1--EXAMINER'S COPY I JOB PERFORI\.

.NCE MEASURE ATTACHMENT 3y Radioactive Liquid Effluent Monitoring Instrumentation TIS 6.8.4.Q OOCM Table 3.3.7.10-1Item3b, ACTION 112 HC. OP-OLZZ-0026(Q)

P§9e1 of1 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, then effluent releases via this pathway may continue provided the How rate rs estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves (VTD 322848) should be used if using Method 3. [7-0042554]

Readings are taken regardless of whether a Liquid Release is in progress.

DATE TODAY Readings are taken every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 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.

Any one of the following Methods may be used to satisfy the requirements of Action 112. -ENTER TIME Of EACH READING IN THE T-= 0, T + 3 HRS. T + 6 HRS *.*.*.* BLOCKS METHOD 1 DIRECT READING OF WEIR FlOW I T=O T+ J HRS T+6HRS T+9HRS IT+ 12 HRS T+15HRS T+18HRS IT+21 HRS rr + 24HRS (USE ANY ONE OF THE FOLLOWING}

TIME A} -CR1DS POINT A9327 {CTB BlOWDOWN DISCH FLOW) B) -RM-11. 9RX599 (PROCESS FLOW NJ C)-1DCG04 PANEL. LIQUID R1W OSP-Rl48G1 jCTB FLOW P.B.} METHOD 2 CALCULATED WEIR FlOW TIME SSW lOOP A FLOW# + SSW LOOP B FLOW# = TOTAL SSW FLOW -EVAPORATIVE LOSSES* = TOT Al WEIR FLOW NOW 13560 .. 21345 = 34905 6700 12500 = 4820§ 22405 .. = -= + = -= + = -= + = -= + = -= + "' -= + = -= METHOD 3 ESTIMATED WEIR FLOW (VID 322848 SHOULD BE USED FOR PUMP PERFORMANCE CURVE TO SUPPORT USE Of METHOD 3) [70042554]

DATEmME A & C SSW PUMP FLOW + B & D SSW PUMP FLOW = TOTAL SSW FLOW -EVAPORATIVE LOSSES * = TOTAL WBR FLOW .. = -= .. = -= + = -:: + = -= .. = -= + = -= + = -= REFERENCE PR.INT 108564'115-181-t FOR EVAPORATIVE LOSS ESTIMATES.

USE 16,700 GPM FOR DEFAULT VALUE(MIN.

DIUJTION FLOW). FOR EVAPORATIVE LOSS ESTIMATES IF 4 CIRCULATING WATER PUMPS ARE IN SERvtCE,

.QR 12,fil!O GPM IF ONLY 3 CIRCULATING WATER PUMPS ARE IN SERVICE.

THIS BLOCK IS NIA IF THE COOLING TOWER 1S OUT OF SERVICE.

READ FROM FIT-2218AJB OR FR-22113-t/2 OR GRIDS A2440iA2441.

(B SSW LOOP FLOW {FIT-22186)

IS OBTAINED LOCALLY AT PANA.METRICS MONITOR FLOW VALUE IS THE AVERAGE VOLUMETRIC FLOW RATE WHICH .IS GISPLAYED AS "AVG VOLUMETRIC GAUMIN" ON THE MONITOR ffiSPi.AY.

Hope Creek Page 100of105 Page 9of12 Rev.141 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1 . The plant is at 100% power. 2. Circulating Water Pump BP501 is tagged for motor replacement.

3. Circulating Water Pumps AP501, CP501, and DP501 are in service.

4. Service Water Pumps AP502, BP502, and DP502 are in service 5. Cooling Tower Slowdown Weir Flow Rate Monitor OSP-Rl4861 is reading blank, and is INOPERABLE.

TSAS 2015-001 was entered.

6. RM-11 point 9AX327 historical data is NOT available.

7. SSW Loop Flow GRIDS Point values as follows:

A2440 SERVICE WATER FLOW RATE DIV A= 13,560 gpm

A2441 SERVICE WATER FLOW RATE DIV B = 21,345 gpm INITIATING CUE: You are the Control Room Supervisor.

PERFORM the Control Room Supervisor review of the completed HG.OP DL.ZZ-0026, Attachment 1 a, ITEM 47, Day Shift reading, AND Attachment 3y for the inoperable RMS Cooling Tower Slowdown Weir Flow Rate Monitor.

Page 10of12 I -TRAINING ONL y I ATTACHMENT 1a Surveillance Log -Control Room HC.OP-DLZZ-G026(Q)

Page 10of18 Operational Condition 1 ---*-Date TODAY ITEM SURVEILLANCE OPER ACCEPTABLE LIMITS INSTRUMENT

{PANEL) DAY EVE MID COMMENTS COND MIN NORM MAX -47 CHANNEL CHECK: COOLING AT ALL ITEM OSP-Rl486t (tOC604) 0J .1JTSAS 2015-001 TOWER BLOWDOYm WEIR TIMES 002 <40K 70K ITEM029 See Attachment 3Y FLOW RATE MONITOR RM-11 {QAX327)

(NOTE 45.j "' -NO -INST TRIPPED ( Fl {NOTE 33 .* 46 .* 47 .) 43 CHANNEL CHECK: COOLING AT ALL --ITEM SP-Rl88H

\10C604)

'iilTA' WA {NOTE 41.} TOWER SLOWDOWN TIMES OOQ RADIATJON MONITOR SAMPLE FLOW rn -14.a SP-Rl88U (10C604)

NIA NJ.A {NOTE35.)

ITEMOW SAMPLE LOW FLOW ALARM UJ -1.0 SP-Rl88H

{10C604)

WA WA {NOTE33.)

ITEM00:2

-0000 -SP-Rl8817 (10C604)

WA WA {NOTE41J.)

ITEM044 ANY OF ITEM 48 -NO -INST TRIPPED N!A NIA 49 CHAN'NEL CHECK: AT ALL --2.4F' SP-Rl4557 1.1E-6 WA NIA (NOTE30.)

TBCW RADIATION MONITOR TIMES OR RM-11 {9RX5D5) 5() CHAf!lNEL CHECK: AT ALL --9E.s SP-Rl2534

{NOTE 30.} RACS RADIATION MONITOR TIMES OR RM-11 (gRXft{]!J) 7.7E-7 M CHANNEL CHECK: SACS AT ALL --t1F' SP-Rl4859A 1 OR (1EC267) 3.2E-7 {NOTE30.)

LOOP A RADIATION MONITOR TIMES RM-11 {!GRX501)

NOTES: :JIJ. IF NORMAL 1NSTRUMENT IS INOP AND cruDS IS USED (FOLLOWING EOO!VALENCY REVIEW),

THEN ONLY OBTAIN CR!DS VALUE FROM 'RM-11 DATA' SCREEN OF THE 'GROUP 2 MENU' OF GROUP DISPLAYS.

[70134816]

33. TO OBTAIN VALUES 006 00 002, PRESS MON PB, KEY IN 006 OR 00:2, THEN ITEM PB. 35. TO OBTAIN VALUES 0:28, ll29. OR 073. PRESS MON PB, KEY IN 023, 029, OR 073, THEN ITEM PB. 40. TO OBTAIN VALUE 044, PRESS MON PB. KEY IN 044, THEN ITEM PB. IF VALUE IS NOT AT 0000 HAVE !&CIR.AD PRO INVESTIGATE OPERABILITY.

41. TO OBTAIN VALUE 000, PRESS LIQ PB, KEY IN 009, THEN ITEM PB. 45. CHANNEL CHECK SHALL CONSIST OF \/ERIFYING INDICATION OF FLOW DURING PERIODS OF RELEASE.

CHANNEL CHECK SHALL BE MADE AT LEAST ONCE PER 24 HOURS ON DAYS ON WHICH CONTINUOUS.

PERIODIC.

OR BATCH RELEASES ARE MADE. WHEN THREE SSWS PUMPS ARE IN-SERVICE.

ANO. THE RM-11 IS AVAILAElE.

RECORD THE lO\'VEST OF THE LAST 12 {HOURl Y) AVERAGES FOR 9AX327 (CTB FLOW) AS FOLLOWS:

CLICK ON 9AX327, THEN CUCK ON 00 MIN AVG BUTTON. [70026506]

OR FROM THE TOP LEVEL MENU THAT CAN SE ARRIVED AT BY DEPRESSING 1HE *EsC' KEY. CLICK THE "lOGSJ'REPORTS.

BUTTON, THEN THE "'DAILY LOG SETI.JP" BUTTON, (F2) OR 1YPE "ARCHIVE' IN THE YELLOW FUNCTION FIELD; CHANGE DA TE AND TIME UNDER 'ENTER START TIME" TO AT LEAST 12 HOURS AGO (ONt Y THE BACKSPACE KEY FUNCTIONS TO ERASE EXISTING TEXT}; IN THE FIELD UNDER "OR ENTER PIDS (COMMA DELIMITED}:*

ENTER "TR604861-4".

THIS IS THE 00 MINUTE AVERAGE TREND FOR THE DESIRED POINT; SELECT F3 OR CUCK THE "F3=VIEW PIO" BUTTON AT THE SCREEN BOTTOM TO DISPLAY THE DA TA. [70026506]

46. If INSTRUMENT IS !NOP, USE ATTACHMENT 3Y TO ESTIMATE WEIR FLOW. THIS IS REQUIRED REGARDLESS OF WHETHER A RADIOACTIVE LIQUID RELEASE lS IN PROGRESS.

47. REFER TO HC.OP-SO.SP-0001(0),

RADIATION MONITORING SYSTEM OPERATION.

FOR NOTES ON OPERABILITY.

Hope Creek Page 28of105 Page 11of12 Rev. 141 I TRAINING ONLY I ATTACHMENT 3y Radioactive Liquid Effiuent Mooitoring Instrumentation T/S 6.8.4.Q ODCM Table 3.3.7.10-1Item3b.

ACTION 112 HC.OP-OLZZ-0026(Q)

Page 1of1 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, then effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves {VTD 322848) shouid be used if using Method 3_ [70042554]

Readings are taken regardless of whether a Liquid Release is in progress_

DATE TODAY I Readings are taken every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to ensure that the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Tech Spec Action Hmit is NOT exceeded per administrative requirements_

Any one of the following Methods may be used to satisfy the requirements of Action 112. --ENTER TIME OF EACH READlNG 1N THE T-= O. T + 3 HRS. T + 6 HRS .. _____ BLOCKS METHOD 1 DIRECT READING OF WEIR FLOW I T=O T+3 HRS T+6HRS T+9 HRS [+12HRS IT+ 15HRS T+ 18 HRS T+21 HRS T + 24 HRS (USE ANY ONE OF THE FOLLOWING)

TIME A) -CRIDS POINT A9327 (CTB BLOWDOWN DtSCH FLOW) B) -RM-11, 9RX599 (PROCESS FLOWN) C} -1 OC604 PANEL. LIQUID RIW llSP-Rl48Gt (CTB FLOW P.B.) METHOD 2 CAI..CULATED WEIR. FLOW TIME SSW LOOP A FLOW# + SSW LOOP B FLOW I = TOTAL SSW FLOW -EVAPORATIVE LOSSES * = TOT AL WEIR FLOW NOW 13560 + 21345 = 34905 -16700 = 18205 + = -= *+ = -= + = -= + = -: + = -= + = -= + = -: METHOD 3 ESTIMATED WEIR FLOW (VTD 322848 SHOULD BE USED FOR PUMP PERFORMANCE CURVE TO SUPPORT USE OF METHOD 3} [70042554]

DATEmME A & C SSW PUMP FLOW + B & D SSW PUMP FLOW = TOTAL. SSW FLOW -EVAPORATIVE LOSSES * = TOTAL WEIR FLOW + = -= + = -= + = -= + = -= + = -= + = -= + = -= REFERENCE PRINT 10055-M 15-18 t-1 FOR EVAPORATIVE LOSS ESTIMATES.

USE 16,700 G?M FOR DEFAULT VALUE(MJN.

DIUJTION FOR EVAPORATIVE LOSS ESTIMATES IF 4 C1RCULA TING WATER PUMPS ARE IN SERVICE, QR 12,500 GPM JF ONLY 3 CIRCULATING WATER PUMPS ARE IN SERVICE.

THIS BLOCK IS NIA If THE COOLING TOWER IS OUT OF SERVICE.

READ FROM FIT-221SAJB OR FR-2218-112 OR CRIDS A2440/A2441.

(B SSW LOOP FLOW {flT-221BB}

IS OBTAINED LOCALLY AT PANA.METRICS MONITOR FLOW VALUE IS THE AVERAGE VOLUMETRIC FLOW RATE WHICH IS DISPLAYED AS "AVG VOLUMETRIC ON THE MONITOR DISPLAY.

Hope Creek Page 100of105 Page 12of12 Rev.141 JOB PERFORMANCE MEASURE STATION:

Hope Creek COPY OF SYSTEM: Emergency Procedures/Plan TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition JPM NUMBER: 305H-JPM.ECG007

[SRO A4] REVISION:

10 SAP BET: NOH05JPCL07E K/A NUMBER: 2.4.38 IMPORTANCE FACTOR: RO: 2.4 SRO: 4.4 ALTERNATE PATH: D APPLICABILITY:

EO D EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

EP-HC-111-100 Rev. 12 EP-HC-111-101Rev.0 EAL Flowcharts and EAL Wallcharts HCGS ECG -EAL Technical Basis TOOLS, AND EQUIPMENT:

EP-HC-111-F*[1-5,24];

EP-HC-111-101; EAL Flowcharts and EAL Wallcharts:

HCGS ECG -EAL Technical Basis; Phone and EP Aid-031, Simulator Only ESTIMATED COMPLETION TIME: 13 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15/13 Minutes -----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: Minutes REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: D. M. REIN/SIGNATURE ON FILE DATE: 1/28/2015 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 1/28/2015 Operations Representative APPROVED BY: M. SHAFFER/SIGNATURE ON FILE DATE: 2/5/2015 Training Department Page 1of14 JOB PERFORMANCE MEASURE SYSTEM: Emergency Procedures/Plan TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition INITIAL CONDllTONS:

1. The plant is in OPERATIONAL CONDITION 4 and has been in COLD SHUTDOWN for 10 days. 2. Offsite Release Rates on SPDS were:

1.17E+1 µCi/sec Noble Gas

1.17E-2 µCi/sec 1-131 3. 'B' RHR was in Shutdown Cooling at 10,000 gpm with an RCS temperature of 120 degF. 4. Then, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1 g. 5. Control Room Annunciator C6-C4 is in. 6. On Panel 1 OC673:

The SMA-3 Event lndictor 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 7. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer.

8. A LOCA results.

RPV level dropped to -250", then stabilizes between -225" and -205", being maintained using all available ECCS (2 LPCI Loops). 9. Secondary Containment integrity is intact with FRVS in service.

10. The current 33 ft. elevation wind direction is from 332° at 21 mph. 11. Plant Effluents:

1.17E+1 µCi/sec Noble Gas

1.17E-2 µCi/sec 1-131 12. DAPA monitors indicate:

6.942E+01 DAPA A

2.761 E+01 DAPA B 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 the event is NOW. Page 2of14 JPM NUMBER: ECG007 NAME: --------REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: EP-HC-111-101 8.4 Classification N/A N/A N/A NOTE Comparison of redundant Operator reads Note. instrumentation, indications, and/or alarms should be used to confirm actual plant conditions.

The primary tools for Operator reads text. determining the emergency classification level are the EAL flowcharts or EAL wallcharts.

The user of the EAL flowcharts or wallcharts may (but is not required to) consult the EAL Technical Basis in order to obtain additional information concerning the EALs under classification consideration.

To use the EAL flowcharts or wallcharts, follow this sequence:

1. ASSESS the event and/or Operator assesses the initial plant conditions and conditions, and determines that DETERMINE which ECG -EALs that are applicable under all EAL Group/Section is most plant Operational Conditions appropriate.

(OPCONs),

AND EALs applicable only under cold OPCONs apply to this classification.

2. REVIEW EAL categories Operator assesses the initial and subcategories on the conditions, and determines that R, appropriate H, and C are appropriate ECG flowcharts/wallcharts.

categories; and R1, H1, and C3, are appropriate subcategories.

Page 3of14 JPM NUMBER: ECG007 NAME: -----------

---REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) 3. If using the ECG -EAL Operator refers to Flowchart flowcharts, for each Diagrams and/or Wallcharts and applicable subcategory, reviews EALs in R1, H1, and C3. REVIEW EALs in the Operator determines that HA 1.1, subcategory beginning with the lowest emergency CS3.1 and apply to the event. classification level to the highest classification level (left to right). ENSURE all pages of a particular subcategory being considered are reviewed.

4. If using the ECG -EAL Wallcharts, for each applicable subcategory, REVIEW EALs in the subcategory beginning with the highest emergency classification level to the lowest classification level (left to right). 5. If in OPCON 1, 2 or 3, also REVIEW the Fission Product Barrier (FPB) Table: a. EXAMINE the FPB Operator refers to FPB Table and categories in the left identifies that the Initial Conditions column of the table. (Operational Condition

4) are not b. SELECT the category applicable.

that most likely coincides with event conditions.

c. REVIEW all thresholds in this category for each fission product barrier.

d. For each threshold that is exceeded, IDENTIFY its point value and DETERMINE the classification level in accordance with the instructions on the Fission Product Barrier Table (or in EAL Technical Bases, Attachment 1 ). -Page 4of14 JPM NUMBER: ECG007 NAME: REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) 6. REVIEW the associated Operator reviews the EALs EA Ls as com pared to the identified in Step 8.4.3 and 4, and event and SELECT the selects EAL CS3.1 as the highest highest appropriate emergency action level met or emergency.

If identification exceeded (SITE AREA of an EAL is questionable EMERGENCY).

refer to paragraph 8.1 above. If there is any doubt with regard to assessment of a particular EAL, the ECG EAL Technical Bases Document should be reviewed.

Words contained in an EAL that appear in uppercase and bold print (e.g., VALID) are defined at the end of the bases for the particular EAL or in ECG -EAL Technical Basis Document, Attachment 3, EP-HC-111-232, EAL Definitions.

Words or numbers contained in an EAL that are in bold print but not uppercase are EAL threshold values (e.g.,;::::

15 minutes).

7. If an EAL has been Examiner Note: Filling out the exceeded, equal level NRG Data Sheet is beyond the EALs or lower level EALs scope of this JPM. are not required to be separately reported as long as the applicable N/A information is communicated to the NRG using ECG Attachment 5, EP-HC-111-F5, NRG Data Sheet & Completion Reference.

Page 5of14 JPM NUMBER: ECG007 NAME: ----REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) 8. When the Shift Manager Operator requests STA/IA (SM) is the Emergency verification of classification.

Coordinator, the Shift Examiner Note: Due to time spent Technical Advisor (STA) is responsible to perform an assessing and/or nature of JPM independent verification of administration, Operator may not the EAL classification.

The request verification.

ST A verification does not alleviate the requirement of the SM to make a timely classification.

Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO, the Independent Assessor.

CUE: IF the Operator requests the STA/IA to independently verify the EAL Classification, THEN INFORM the Operator the STA/IA is not available.

9. IDENTIFY and Operator identifies and implements IMPLEMENT the EP-HC-111-F3.

referenced ECG form based on the Emergency Classification Level.

Unusual Event Implement EP-HC-111-F1

Alert Implement EP-HC-111-F2

Site Area Implement EP-Emergency HC-111-F3

General Implement EP-Emergency HC-111-F4

Unusual Event Implement EP-(Common Site) HC-111-F24 EP-HC-111-F3 ATTACHMENT 3 SITE AREA EMERGENCY A. CLASSIFICATION

1. CALL communicators to Operator calls communicators to the Control Room. the Control Room and initials Step. CUE: After 2 minutes, report as the CM1 and CM2 communicators.

-Page 6of14 JPM NUMBER: ECG007 NAME: REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) 2. IF a Security Event is in Operator determines Step is N/A progress, THEN and marks N/A. IMPLEMENT the prompt actions of NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to classification.

3. If time allows, DIRECT Operator requests STA/IA Classification Independent verification of classification and Verification to be initials Step. performed Examiner Note: Due to time spent assessing and/or nature of JPM administration, Operator may not request a verification.

CUE: IF the Operator requests the STA/IA to independently verify the EAL Classification, THEN INFORM the Operator the STA/IA is not available.

4. After Classification

Operator declares a Site Area Independent Verification Emergency, places the time and is obtained:

date in the appropriate spots on

DECLARE the SITE ICMF, AREA EMERGENCY Examiners Note: NOTE the (enter time and date on declaration time that the operator ICMF) entered on the ICMF. The difference between the ST ART TIME and the "DECLARED AT" TIME is the first critical time (15 min). Time: Page 7of14 JPM NUMBER: ECG007 10 NAME:

REV NUMBER: DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fc STANDARD UNSAT)

COMPLETE/

operator places the EAL APPROVE the ICMF #CS3.1, a description of the event, checks NO Release in progress, enters the wind direction and speed, and initials as EC in the appropriate spots in the ICMF, and initials the step as the EC. Examiners Note: See the attached ICMF for an example of what the form should look like when filled out properly.

Note that the exact words do not have to be in the "DESCRIPTION OF EVENT", but the description must convey the sense of the Initiating Condition for EAL CS3.1. The operator may place the Examiner's name as the Communicator, or tell the Examiner to place his/her name as the Communicator.

5. If time allows OBTAIN Operator requests STA/IA perform accuracy peer check of the an accuracy peer check of the completed ICMF completed ICMF. CUE: IF the Operator requests a peer check to verify the EAL Classification, THEN INFORM the Operator that no one is available.

6. Continue with Operator activates or directs the NOTIFICATION AND activation of the ERO per posted ACTIVATION as follows:

instructions titled Training Use If not previously Emergency Callout Activation and

initials Step. performed, ACTIVATE I DIRECT Examiner Note: ENSURE the ACTIVATION of ERO operator is using the Simulator Emergency Callout Training Activation instructions.

(EP 96-003) CUE: If asked/requested to activate the ERO Emergency

Callout, STATE "The ERO Callout is complete."

Page 8of14 JPM NUMBER: ECG007 NAME: REV NUMBER: 10 DATE:

STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)

DIRECT the Primary *operator provides the ICMF to Communicator to Primary Communicator and implement ECG directs implementation of Att.6 Attachment 6 and initials Step. Examiner Note: The difference between the "DECLARED AT" TIME and this LOG TIME is the second critical time (13 min.). Time: CUE: Role-play as CM1 and repeat back the directions given.

DIRECT the Secondary

operator directs CM2 to Communicator to implement Att. 8 for a SITE implement ECG AREA EMERGENCY Attachment 8 for a SITE AREA and initials Step. EMERGENCY CUE: Role-play as CM2 and repeat back the directions given. Provide Terminating Cue. CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: Task Standard:

Operator declares a Site Area Emergency

[ECG CS3.1 ], and makes notifications within identified Critical Times in accordance with EP-HC-111-101.

Page 9of14 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION ECG007 NAME:

10 DATE: SAT D UNSAT D SAT D UNSAT D Page 10of14 JOB PERFORMANCE MEASURE JPM NUMBER: ECG007 REVISION HISTORY Rev# Date Description Validation Required?

02 8/26/08 Updated Estimated Completion Time with historical average N performance time. No change in actions, validation not required.

Updated Reference procedure revision number. No change in operator actions.

This change is editorial, validation not required.

Converted JPM ECG007 to new JPM format. Since Critical JPM actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial, validation not required.

Removed references to checking off/initialing steps in procedure.

This is a generic work practice and adds unnecessary clutter to the Standard section.

This change is editorial, validation not required.

03 10/6/09 Updated procedure revision number. No change in operator N actions.

Validation not required.

04 8/12/10 Updated Reference procedure revision numbers.

Updated ICMF N key to reflect words of "Hope Creek Emergency Classification Description Table". No changes to operator actions.

No validation required.

05 9/12/11 Updated Reference procedure revision numbers.

Revised N procedure steps due to editorial changes of the procedure.

Modified wind direction and speed. No changes to operator actions.

No validation required.

06 9/26/12 Complete re-written to stay SAE under new ECG-EAL changes.

y Added Task Standard to JPM. Editorial change only. Updated Validation Checklist to current form from TQ-AA-106-0304.

Editorial change only. Validated with 2 SROs from E Shift. 07 3/27/13 Updated procedure revision number. No change in operator N actions.

Validation not required.

07 9/17/13 Validated correct reference procedure revision.

NO changes.

N 08 9/9/2014 Revised format. Updated steps due to procedure revisions.

N Revised Standards' terminoloqv.

All changes are editorial.

09 10/31/2014 Revised Typographical Errors. Validated with 2 SROs. y 10 1/19/2015 Revised based on new revision to EP-HC-111-F3.

Revised N Initiating Cue to add release activities and DAPA readings.

Revised formatting of actions to complete ICMF due to the procedure revision.

No siqnificant chanqes to operator actions.

Page 11 of 14 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ECG007 REV#: 10 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

SRO M. CHARLES SRO ON FILE 10/31/2014 Name Qua I Signature Date L. MYERS SRO ON FILE 10/31/2014 Name Qua I Signature Date Page 12of14 JOB PERFORMANCE MEASURE EXAMINER'S COPY EP-HC-111-F3 ATT3 Pg. 2 of5 INITIAL CONTACT MESSAGE FORM I. THIS IS NOT REQUIRED

, COMMUNICATOR IN THE Iii CONTROL ROOM (NAME) 0 TSC AT THE HOPE CREEK NUCLEAR GENERATING STATION_

IL THIS IS NOTIFICATION OF AN SITE AREA EMERGENCY WHICH WAS DECLARED AT TODAY'S TIME ON TODAY'S DATE --CT-im-e---24_H_R_C_L_O_CK_)__

EAL# CS3.1 DESCRIPTION OF EVENT:

LOSS OF REACTOR PRESSURE VESSEL INVENTORY AFFECTING CORE DECAY llL Arly release 0 THERE IS A RELEASE IN PROGRESS DUE TO THE EVENT } above normal. -attributable to the IXI THERE IS NO RELEASE IN PROGRESS DUE TO THE EVENT event. See Ba:sis -fur examples.

IV. 33 FT. LEVEL WIND DIRECTlON (From): 332 WIND SPEED: 21 (From MET Computer

/SPDS) (DEGREES)

(MPH) V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME HCGS EXAMINER'S COPY Page 13of14 INITIALS EC Initials (Approval to Transmit ICMF) Rev_0:3 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is in OPERATIONAL CONDITION 4 and has been in COLD SHUTDOWN for 10 days. 2. Offsite Release Rates on SPDS were:

1.17E+1 µCi/sec Noble Gas

1.17E-2 µCi/sec 1-131 3. 'B' RHR was in Shutdown Cooling at 10,000 gpm with an RCS temperature of 120 degF. 4. Then, Hope Creek experiences an earthquake which indicates a magnitude of> 0.1g. 5. Control Room Annunciator C6-C4 is in. 6. On Panel 1 OC673:

The SMA-3 Event lndictor 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 7. Numerous amber lights and 3 red lights are lit on the response spectrum analyzer.

8. A LOCA results.

RPV level dropped to -250", then stabilizes between -225" and -205", being maintained using all available ECCS (2 LPCI Loops). 9. Secondary Containment integrity is intact with FRVS in service.

10. The current 33 ft. elevation wind direction is from 332° at 21 mph. 11. Offsite Release Rates on SPDS:

1.17E+1 µCi/sec Noble Gas

1.17E-2 µCi/sec 1-131 12. DAPA monitors indicate:

6.942E+01 DAPA A

2.761 E+01 DAPA B 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 the event is NOW. Page 14of14 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Reactor Protection System TASK NUMBER: 2120030101 TASK: Reset A Reactor Scram COPY OF JPM NUMBER: 305H-JPM.SB013

[JPM A] REVISION:

05 SAP BET: NOH05JPSB13E K/A NUMBER: 212000 A4.14 IMPORTANCE FACTOR: ALTERNATE PATH: APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-SO.SB-0001 Rev. 34 TOOLS, AND EQUIPMENT:

None RO: 3.8 SRO: 3.8 ESTIMATED COMPLETION TIME: 11 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of13 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection System TASK NUMBER: 2120030101 TASK: Reset A Reactor Scram INITIAL CONDllTONS:

1. Reactor is shutdown following a scram. 2. The scram initiating signal is clear. 3. ARl/RRCS has not initiated.

4. HC.OP-AB.ZZ-0000, Reactor Scram, is being implemented.

INITIATING CUE: COMPLETE Section 5.3.3, Resetting RPS Trips, of HC.OP-SO.SB-0001.

Page 2of13

, JPM NUMBER: SB013 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue, a marked-up copy of HC.OP-SO.SB-0001, AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator reviews precautions Operator reviews precautions and and limitations.

limitations.

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

Operator reviews prerequisites.

Operator ensures all prerequisites are met, and completes Attachment 1, Section 2.0. Operator determines beginning Operator determines correct step of the procedure.

beginning step to be 5.3.1. 5.3.1 ENSURE all prerequisites of Operator ensures that all Section 2.3 are satisfied.

prerequisites of Section 2.3 are satisfied, including completing Attachment 1, Section 2.0, and initials Step. 5.3.2 lE a Half Scram condition Operator observes that this Step is N/A N/A exists ... marked as N/A. 5.3.3 IF a Full Scram has occurred, THEN PERFORM the following:

A. IF initiated, THEN RESET Operator determines ARI is reset, ARI prior to resetting the and initials or N/As Step. scram. B. ENSURE the RPS MODE Operator observes that the Mode SWITCH is in SHUT-DOWN Switch is in SHUT-DOWN, and OR REFUEL. initials Step. C. INSERT Key AND PLACE HI *#operator places SCRAM LEVEL SCRAM BYPASS in DISCHARGE VOLUME HIGH BYPASS AND OBSERVE the LEVEL SCRAM BYPASS switch DISCH VOL HI WTR LVL (10C651C) in BYPASS, TRIP BYP annunciator is illuminated.

observes and acknowledges annunciator C5-C4, DISCH VOL HI WTR LVL TRIP BYP, and initials Step Page 3of13 JPM NUMBER: SB013 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) D. PERFORM the following to reset the Scram Reset Switches:

1. INSERT Key AND TURN *operator places RPS TRIP RPS TRIP SYSTEM A SYSTEM A, TRIP LOGIC A1 TRIP LOGIC A1 to RESET SWITCH to RESET; then RESET AND RETURN to releases switch (Spring Return NORM. INITIAL to NORM), Attachment 1 . initials Attachment 1 and Step. 2. INSERT Key AND TURN *operator places RPS TRIP RPS TRIP SYSTEM A SYSTEM A, TRIP LOGIC A2 TRIP LOGIC A2 to RESET SWITCH to RESET; then RESET AND RETURN to releases switch (Spring Return NORM. INITIAL to NORM), Attachment

1. initials Attachment 1 and Step. 3. INSERT Key AND TURN *operator places RPS TRIP RPS TRIP SYSTEM B SYSTEM B, TRIP LOGIC 81 TRIP LOGIC 81 to RESET SWITCH to RESET; then RESET AND RETURN to releases switch (Spring Return NORM. INITIAL to NORM), Attachment

1. initials Attachment 1 and Step. 4. INSERT Key AND TURN *operator places RPS TRIP RPS TRIP SYSTEM B SYSTEM B, TRIP LOGIC 82 TRIP LOGIC 82 to RESET SWITCH to RESET; then RESET AND RETURN to releases switch (Spring Return NORM. INITIAL to NORM), Attachment

1. initials Attachment 1 and Step. E. ENSURE the TRIP LOGIC Operator verifies the TRIP LOGIC A1, A2, 81, AND 82 A1, A2, 81, and 82 NORMAL/RESET lights are NORMAL/RESET indicators illuminated.

illuminated, and initials Step. F. ENSURE the PILOT SCRAM Operator verifies the PILOT VALVE SOLENOID TRIP SCRAM VALVE SOLENOID TRIP ACTUATOR LOGICS A ACTUATOR LOGICS "LOGIC A NORMAL AND B NORMAL NORMAL" and "LOGIC B lights are illuminated (Four NORMAL" indicators are Control Rod Groups).

illuminated for group 1, 2, 3, and 4 solenoids, and initials Step. NOTE The ROD DRIFT alarm is reset Operator reads and initials Note. to detect rods moving beyond notch position "00" once the reactor scram is reset. Page 4of13 JPM NUMBER: SB013 NAME: ---------------------

REVNUMBER:

05 0 ATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) G. RESET the ROD DRIFT Operator depresses the Rod Drift alarm. Alarm reset push-button, verifies the Rod Drift overhead alarm is clear, and initials Step. Examiner Note: The Rod Drift alarm may not clear at this time. H. ENSURE HV-F01O/HV-F180 Operator verifies SCRAM SCRAM DISCHARGE DISCHARGE VOLUME VOLUME PIPING INBD/OUTBD VENT VALVES INBD/OUTBD VENT VALVE HVF01O/HVF180 and AND HV-F011/HV-F181 INBD/OUTBD DRAIN VALVES INBD/OUTBD DRAIN VALVE HVF011/HVF181 OPEN indicators OPEN indication is are illuminated and initials Step. illuminated.

I. ENSURE blue SCRAM lights Operator verifies blue SCRAM are extinguished for all 185 lights on the FULL CORE Control Rods on FULL CORE DISPLAY (10C650C)

ARE DISPLAY.

(10C650C)

EXTINGUISHED (185 CONTROL RODS) and initials Step. J. ENSURE the following Operator verifies the following annunciators are de-annunciators are not in alarm: energized:

REACTOR SCRAM TRIP *

REACTOR SCRAM TRIP LOGICA1 LOGICA1

REACTOR SCRAM TRIP

REACTOR SCRAM TRIP LOGICA2 LOGIC A2

REACTOR SCRAM TRIP

REACTOR SCRAM TRIP LOGIC 81 LOGIC 81

REACTOR SCRAM TRIP

REACTOR SCRAM TRIP LOGIC 82 LOGIC 82 and initials Steps. NOTE The Reactor Protection System Operator reads and initials Note. is now reset. Page 5of13 JPM NUMBER: SB013 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) K. WHEN CRD SCRAM DISCH Operator observes that the CRD VOL LVL HI annunciator is SCRAM DISCH VOL LVL HI de-energized, THEN INSERT annunciator is de-energized, and Key AND PLACE HI LEVEL places CRD DISCH VOLUME BYP SCRAM BYPASS in in NORMAL, observes that the NORMAL (DISCH VOL HI DISCH VOL HI WTR LEVEL TRIP WTR LVL TRIP BYP BYP annunciator is de-energized, annunciator is de-energized) initials Attachment 1, and the Step. AND INITIAL Attachment

1. Examiner Note: May have the simulator operator reduce the SDV level such that the time until draining is complete is shortened.

L. AFTER resetting the Scram THEN PERFORM the following as soon as possible:

1. VERIFY all control rods *operator attempts to verify all have settled into notch position "00" using one of control rods have settled into the following:

notch "00", and identifies that all rods have NOT reseated,

FOUR ROD DISPLAY and informs the CRS that rod 38-* Process Plant 47 is at position 02 . Computer (PPG)

RWM Shutdown Confirmation Screen.

SPDS ALL RODS INSERTED reads "YES" CUE: Acknowledge the report from the operator, and direct the operator to reseat the Control Rod. NOTE IF Control Rods at overtravel in Operator reads and initials Note. position DO NOT re-seat after applying an insert signal, then a single notch withdrawal may be applied.

2. RE-SEAT Control Rods *operator applies an insert to "00" by applying a rod signal to Control Rod 38-47, insert signal. Observes that it seats to position "00", informs the CRS that all rods are seated, and initials Step. CUE: Acknowledge the report from the operator.

-Page 6of13 I JPM NUMBER: SB013 NAME: REV NUMBER: 05 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) 3. lE seating at "00" is NOT Operator determines Step is not possible, THEN applicable and initials or marks ISOLATE the affected Step N/A. HCU JAW HC.OP-SO.BF-0002(0),

to prevent inadvertent rod motion. 4. Following the resetting of Operator notifies Radiation a Full Scram, NOTIFY Protection to survey the Scram Radiation Protection to Discharge Volumes.

survey the Scram Discharge Volumes.

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: Task Standard:

Operator resets RPS, identifies rod 38-47 is at position 02, and reseats rod 38-47, in accordance with HC.OP-SO.SB-0001.

Page 7of13 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION SB013 NAME:

05 DATE: SAT D UNSAT D SAT D UNSAT D Page 8of13 JOB PERFORMANCE MEASURE JPM NUMBER: SB013 REVISION HISTORY Rev# Date Description Validation Required?

02 9/14/11 Converted JPM SB013 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 validation times needed. Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. Updated Reference procedure revision numbers only. Validated with 2 operators from "C" Shift. Avg completion time 27 minutes.

03 9/20/12 Added Task Standard to JPM. Updated Reference procedure N revision only. Editorial change only. No validation required.

Updated Validation Checklist to current form from TQ-AA-106-0304. Editorial chanqe only. 04 9/11/2014 Updated Reference procedure revisions.

Revised format and N standards.

Added to provide marked-up copy of procedure.

Added the last two non-critical Steps to complete task as stated. Editorial change only. No validation required.

05 11/7/2014 Modified to have different Control Rod settle to 02 vice the y overtravel position.

Validated with 2 ROs. Validation time 11 minutes.

05 1/22/2015 Added guidance for procedure markup into Preparation for N Training Setup, and revised Standard to reflect this change. Identified durinq NRC review Page 9of13 x x x x x x x x x x x x x

x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: SB013 REV#: 05 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13.

14. 15. TASK: Reset A Reactor Scram Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date J. NERE RO ON FILE 11/7/2014 Name Qua I Signature Date Page 10of13 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: SB013 INITIALIZE the simulator to 100% power, MOL. ------SCRAM the reactor AND TAKE Immediate Operator Actions.

ENSURE associated Schedule file open and running.

---ENSURE associated Events file open. ---ENSURE Control Rod 38-47 is selected.

---Initial Descri tion REV#: 05 MARKUP HC.OP-SO.SB-0001 for completion on Section 5.3 (ENSURE 5.3.2 is marked as N/A.) ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Initial ET 2 Event code: (rp_k14a

& rp_k14c)

I (rp_k14b

& rp_k14d)

==

Description:==

Y2 RPS Reset Event code: lcvposb(

154) >= 16

Description:

Rod 38-47@ position 01 Initial @Time Event Action None None None None Insert malfunction CD023847 on event 1 Insert malfunction CD023847 on event 2 delete in 1 Page 11of13 Description Control Rod 38-4 7 drift out Control Rod 38-4 7 drift out Initial @Time Event Initial @Time Event None None None None None None None None None None JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Action Description Action Description Insert override 3A81_Q_LO after 1 to Off on ROD SELECT -ROD MOTION -INSERT event 1 delete in 3 (LO} Insert override 3A81_Q_LO to Off ROD SELECT -ROD MOTION -INSERT (LO) Insert override 3A81 I DI to On on event 1 ROD SELECT -CONTINUOUS INSERT delete in 1 (DI) Insert override 3A81_R_LO to Off ROD SELECT -ROD MOTION CONTROL -WITHDRAW (LO} Insert override 3A81_R_LO to Off on event ROD SELECT -ROD MOTION CONTROL -2 delete in 1 WITHDRAW (LO) Page 12of13 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Reactor is shutdown following a scram. 2. The scram initiating signal is clear. 3. ARl/RRCS has not initiated.

4. HC.OP-AB.ZZ-0000, Reactor Scram, is being implemented.

INITIATING CUE: COMPLETE Section 5.3.3, Resetting RPS Trips, of HC.OP-SO.SB-0001.

Page 13of13 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Reactor Water Cleanup System TASK NUMBER: 4000760401 TASK: Respond To A Containment Isolation JPM NUMBER: BG003 [JPM B] SAP BET: NOH05JPBG03E COPY REVISION:

00 K/A NUMBER: 204000 A2.13 IMPORTANCE FACTOR: RO: 3.4 ALTERNATE PATH: D APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0002 Rev. 12 TOOLS, EQUIPMENT:

None OF SRO: 3.4 ESTIMATED COMPLETION TIME: 10 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of9 JOB PERFORMANCE MEASURE SYSTEM: Reactor Water Cleanup System TASK NUMBER: 4000760401 TASK: Respond To A Containment Isolation INITIAL CONDllTONS: 1 . RPS Bus B power was lost. 2. Power to RPS Bus B was restored IAW HC.OP-AB.IC-0003, Actions A.1-A.4.

3. It has been decided that for the RWCU isolation, HC.OP-AB.CONT-0002(0),

Condition B may be used for a faster restoration instead of the SOP. INITIATING CUE: PERFORM Action B.1 of HC.OP-AB.CONT-0002.

Page 2of9 JPM NUMBER: BG003 NAME:

REV NUMBER: 0 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT} CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains and locates Operator obtains the correct procedure HG.OP-AB.CONT-procedure.

0002. Operator determines beginning Operator determines the correct step of the procedure.

beginning step to be B.1. B.1 IF RWCU isolated, THEN Operator proceeds to Attachment RESTORE RWCU IAW 3. Attachment

3. ATT3 lE necessary, RESET NSSSS 1. as follows:

Operator determines that the a. ENSURE conditions cause of the isolation has been causing the Isolation have corrected.

been corrected.

b. PRESS the following PBs Operator depresses the NUCLEAR to reset NSSSS: STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC A RESET

NUCLEAR STEAM push button. SUPPLY SHUTOFF SYSTEM TRIP LOGIC Examiner Note: Actions in 1.b need A RESET. not be performed, since; these were completed as part of the actions performed in the Initiating Cue.

NUCLEAR STEAM Operator depresses the NUCLEAR SUPPLY SHUTOFF STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC SYSTEM TRIP LOGIC B RESET B RESET. push button.

NUCLEAR STEAM Operator depresses the NUCLEAR SUPPLY SHUTOFF STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC SYSTEM TRIP LOGIC C RESET C RESET. push button.

NUCLEAR STEAM Operator depresses the NUCLEAR SUPPLY SHUTOFF STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC SYSTEM TRIP LOGIC D RESET D RESET. push button. c. OPEN HV-F001 and HV-*#Operator opens HV-F004.

F004, RWCU suction valves. Operator ensures HV-F001 is already open. Page 3 of 9 JPM NUMBER: BG003 NAME:

REV NUMBER: 0 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) -2. ENSURE HV-F044, Filter Operator ensures HV-F044, Filter Demin Bypass valve is Demin Bypass valve is CLOSED. CLOSED. 3. ENSURE HV-F104 HX Bypass Operator ensures HV-F104 HX valve is CLOSED. Bypass valve is CLOSED. 4. ENSURE at least one RACS Operator ensures at least one Pump is in service.

RACS Pump is in service.

5. START A(B) P221, RWCU *#Operator starts AP221, OR pump. BP221, RWCU pump. Examiner Note: Operator must press STOP before START IF the STOP PB is flashing.

6. THROTTLE OPEN HV-F044,

operator throttles HV-F044, Filter Demin Bypass valve until Filter Demin Bypass valve until computer point A2856, RWCU computer point A2856, RWCU Outlet Flow indicates Outlet Flow indicates approximately 150 gpm. approximately 150 gpm. Examiner's Note: Critical to establish flow greater than 70 gpm. 7. START B(A) P221, RWCU *operator starts BP221, OR pump. AP221, RWCU pump. Examiner Note: Operator must press STOP before ST ART lE the STOP PB is flashing.

8. THROTTLE OPEN HV-F044,

operator throttles HV-F044, Filter Demin Bypass valve until Filter Demin Bypass valve until computer point A2856, RWCU computer point A2856, RWCU Outlet Flow indicates Outlet Flow, indicates approximately 300 gpm. approximately 300 gpm. Examiner's Note: Critical to establish/maintain flow greater than 70 gpm. 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: -Task Standard:

Operator responds to a containment isolation and restores RWCU IAW HC.OP-AB.CONT-0002.

Page 4of9 QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION SAT D UNSAT D SAT D UNSAT D Page 5 of 9 JOB PERFORMANCE MEASURE JPM NUMBER: BG003 REVISION HISTORY Rev# Date Description Validation Required?

0 11/7/2014 New JPM. Validated with 2 ROs. Validation time 10 minutes.

y 0 1/21/2015 Added Examiner Note per NRC request.

Added clarifying N information to an Examiner Note. Page 6 of 9 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BG003 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Respond To A Containment Isolation Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date J. NERE RO ON FILE 11/7/2014 Name Qua I Signature Date Page 7 of 9 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: BG003 REV#: 0 INITIAL CONDITIONS:

IC Initial Description INITIALIZE to any 100% power IC. PLACE RPS MG SET TRANSFER SWITCH B to the Alternate position.

ALLOW conditions to stabilize.

PERFORM Actions A.1, A.2, A.3, and A.4 of HC.OP-AB.IC-0003.

PREPARATION FOR TRAINING (E.G., PROCEDURES, BEZEL COVERS) Initial Description COMPLETE "Simulator Ready-for-Traininq/Examination Checklist".

MALFUNCTION SUMMARY:

Initial Malfunction Description Event Delay REMOTE SUMMARY:

Initial Remote Description Event Delay 1/0 OVERRIDE SUMMARY:

Initial Override Description Event Delay EVENT SUMMARY:

Initial Event Override

==

Description:==

Event Code: Page 8of9

Ramp Initial Final Value Value -Ramp Initial Final Value Value Ramp Initial Final Value Value JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1 . RPS Bus B power was lost. 2. Power to RPS Bus B was restored IAW HC.OP-AB.IC-0003, Actions A.1-A.4.

3. It has been decided that for the RWCU isolation, HC.OP-AB.CONT-0002(Q),

Condition B may be used for a faster restoration instead of the SOP. INITIATING CUE: PERFORM Action B.1 of HC.OP-AB.CONT-0002.

Page 9of9 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Control Rod Drive TASK NUMBER: 4000060401 TASK: Respond to a Loss of CRD Regulating Function COPY OF JPM NUMBER: 305H-JPM.BF012

[JPM C] REVISION:

08 SAP BET: NOH05JPBF12E K/A NUMBER: 295022 AA1 .02 IMPORTANCE FACTOR: RO: 3.6 SRO: 3.6 ALTERNATE PATH: APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.IC-0001, Rev. 16; HC.OP-IO.ZZ-0003, Rev 104; HC.OP-AR.ZZ-0020, Rev. 19; HC.OP-SO.SF-0001, Rev. 32; HC.OP-AR.ZZ-0011, Rev. 59 TOOLS, AND EQUIPMENT:

None ESTIMATED COMPLETION TIME: 11 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes ----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1 of 1 JOB PERFORMANCE MEASURE SYSTEM: Control Rod Drive TASK NUMBER: 4000060401 TASK: Respond to a Loss of CRD Regulating Function INITIAL CONDllTONS:

1. Reactor pressure is approximately 500 psig. 2. A Reactor startup is in progress in accordance with HC.OP-IO.ZZ-0003.

Completed up to step 5.3.34.C.

3. Currently completed Step 320 of the Rod Pull Listing (Rod 10-19 @04). INITIATING CUE: WITHDRAW control rods to attain 11,000 gpm through the Condensate Demineralizers in preparation to place the first RFP in service.

Page 2 of 2 JPM NUMBER: BF012 NAME: REV NUMBER: 08 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains procedure Operator obtains correct HC.OP-SO.SF-0001.

procedure.

Operator reviews precautions Operator reviews precautions and and limitations.

limitations.

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

Operator determines beginning Operator determines correct step of the procedure beginning step to be 5.3.1. 5.3.1 ENSURE that all prerequisites Operator reviews prerequisites and have been satisfied IAW initials each prerequisite in the Section 2.3. space provided in the procedure.

NOTE For a specified control rod, Operator reads and initials NOTE. Reactor Engineering may request a range for Drive Water Differential Pressure below the normal range of 260-270 psid to compensate for double-notching pending Corrective Maintenance.

A lower differential pressure will slow down the control rod. 5.3.2 IF desired, LOWER Drive Operator determines that this Step Water Differential Pressure to is N/A and marks Step as N/A. the desired range. 5.3.3 To select the desired control rod, PRESS the desired Control Rod Select PB on the ROD SELECT MODULE AND OBSERVE the following:

A. Selected rod PB comes ON *#Operator presses the PB for rod 26-35 (bright white). and observes rod 26-35 PB illuminates AND initials Step. B. CONTROL ROD Operator observes the CONTROL POSITION FOUR ROD ROD POSITION FOUR ROD DISPLAY indicates the DISPLAY indicates the control rod control rod position position (04) AND initials Step. (10C650C).

Page 3 of 3 JPM NUMBER: BF012 NAME: ---------------------

REV NUMBER: 08 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) C. The associated Full Core Operator observes rod 26-35 Full Display (white) numbered Core Display (white) numbered rod rod identification light identification light is ON AND comes ON (10C650C).

initials Step. D. Approximately 6 gpm total Operator determines that flow through both the Insert approximately 6 gpm total flow AND Withdraw Stabilizing through both the Insert AND valves is indicated on Withdraw Stabilizing valves is CRID's point B2117. indicated on CRID's point B2117 [70044199]

AND initials Step. NOTE WHEN a single notch motion is Operator reads and initials NOTE. required, the WITHDRAW PB must be held until the INSERT lamp illuminates.

This is to ensure the Rod Motion Timer cycle is sealed in. [80013510]

The leading indicator of excessive channel distortion is slow settle times. A normal settle time is about 2 seconds from the time that the settle light illuminates until the even notch appears on the Four Rod Display.

Settle times should be monitored and Reactor Engineering promptly notified of slow times. 5.3.4 At the ROD SELECT *#The operator momentarily MODULE, momentarily PRESS presses the WITHDRAW PB the WITHDRAW PB AND AND initials Step. OBSERVE the following:

A. The INSERT (white) light Operator observes the INSERT comes ON momentarily.

(white) light comes ON momentarily AND initials Step. B. The WITHDRAW (white) Operator observes the light comes ON for == 1 WITHDRAW (white) light comes second. ON for== 1 second AND initials Step. C. CONTROL ROD Operator observes CONTROL POSITION FOUR ROD ROD POSITION FOUR ROD DISPLAY indicates control DISPLAY indicates control rod rod movement.

movement AND initials Step. -D. The Full Core Display Operator determines that this Step FULL IN (green) light goes is N/A and marks Step N/A. OUT, as applicable.

Page 4 of 4 JPM NUMBER: BF012 NAME: REV NUMBER: 08 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) E. The WITHDRAW (white) Operator observes the light goes OUT. WITHDRAW (white) light goes OUT AND initials Step. F. The SETTLE (white) light Operator observes the SETTLE comes ON for ::::: 6 seconds, (white) light comes ON for:::::

6 THEN goes out. seconds, then goes out AND initials Step. G. CONTROL ROD Operator observes CONTROL POSITION FOUR ROD ROD POSITION FOUR ROD DISPLAY indicates the DISPLAY indicates the control rod control rod has settled to has settled to the desired the desired position.

position(06)

AND initials Step. H. For control rods withdrawn Operator determines that this Step to position 48 (full out), the is N/A and marks Step N/A. applicable Full Core Display FULL OUT (red) light comes ON. I. After the withdrawal cycle Operator ensures that the rod is completed, ENSURE position indicates that the rod is in that the rod position the correct, even numbered indicates that the rod is in position(06)

AND initials Step. the correct, even numbered position.

Operator observes that the The operator reports the status of operating CRD Pump has the CRD System. tripped by observing the following alarms and indications:

Annunciator CRD SYSTEM TROUBLE, C6-F2 is energized.

Lowering CRD Drive Water Flow

Lowering Charging Water Header Pressure

Flashing STOP PB for the operating CRD pump.

D2244 CRD WTR PMP A MOT MALF GRIDS in alarm. CUE: Acknowledge the report of the status of the CRD Pump. State "Start the standby CRD pump in accordance with the Annunciator Response Procedure."

Page 5 of 5 JPM NUMBER: BF012 NAME: ---------REV NUMBER: 08 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) The operator attempts to place Examiner Note: It may be the B CRD pump in service in necessary to have the simulator accordance with D2244, operator support placing the CRD HC.OP-AR.ZZ-0011, and pump in service JAW HC.OP-HC.OP-AR.ZZ-0020, HC.OP-AB.ZZ-0001.

AB.ZZ-0001, OR Section 5.2.8 of HC.OP-SO.BF-0001.

HC.OP-AR.ZZ-0020(Q)

N/A N/A N/A D2244 OPERATOR ACTION: 1. DETERMINE cause of A CRD Pump trip. CAUSE Operator determines that Cause CRD Pump trip due to 1A is applicable and takes overcurrent OR undervoltage.

Corrective Actions.

(OVLD/PWR FAILURE amber light on (HS4011A).

CORRECTIVE ACTION 1A. PLACE DRIVE WTR *#Operator places DRIVE WTR FLOW controller in FLOW controller (FIC-R600) in MANUAL AND SET to 0. MANUAL AND sets it to 0. 1B. START B CRD Pump AND *#Operator starts B CRD Pump RESTORE system flow to by pressing the START PB, 63 gpm. and observes that it trips after start. CUE: Acknowledge the report of the status of the CRD Pump. CAUSE Operator determines that Cause 3 3. Complete loss of Drive is applicable and takes Corrective Water Pumps A and B Actions.

CORRECTIVE ACTION 3A.REFER to HC.OP-AB.IC-Operator refers to HC.OP-AB.IC-0001(0);

Control Rod. 0001 (Q); Control Rod. CUE: Acknowledge the report of the status of the CRD system. CUE: Announce "Crew Update" after acknowledged state "Entering HC.OP-AB.IC-0001, Control Rod, end of update."

HC.OP-AB.IC-0001 (Q) N/A N/A N/A -Operator responds to CRD Operator acknowledges OHA and Accumulator alarm C6-D4, reports status of accumulators.

CRD ACCUM TROUBLE Page 6 of 6 JPM NUMBER: REV NUMBER: STEP NUMBER BF012 08 ELEMENT NAME:

DATE: (*Critical Step) (#Sequential Step) STANDARD SAT/ UNSAT CUE: Acknowledge report of CRD Accumulator Trouble alarms. COMMENTS (Required for UNSAT) CUE: IF the operator requests that the Reactor Building Equipment Operator report the local Accumulator pressures for the associated rods, THEN REPORT that indicated pressure for all three is approximately 600 psig. CUE: IF the operator requested that the Reactor Building Equipment Operator report the local Accumulator pressures for the associated rods, and that indicated pressure for all three is approximately 600 psig, THEN STATE that the Accumulators for those rods are declared INOPERABLE.

Operator determines that the Retainment Override applies.

CONDITION I. Reactor Pressure<

900 psig AND Charging Water Header Pressure<

940 psig AND ANY WITHDRAWN Control Rod Scram Accumulator INOPERABLE.

ACTION IA. LOCK Mode Switch in SHUTDOWN.

[T/S 3.1.3.5.a.3]

[CM-HC-1982-108] *operator locks the Mode Switch in SHUTDOWN AND implements HC.OP-AB.ZZ-0001, Attachment

1. Examiner Note: If the Mode Switch is in SHUTDOWN, provide the Terminating Cue. CUE: IF the operator requests permission to lock the reactor mode switch in Shutdown, THEN STATE "Lock the Mode Switch in Shutdown."

1.0 2.0 HC.OP-AB.ZZ-0001 Att. 1 ANNOUNCE "Crew -Standby for Scram Report".

LOCK the Mode Switch in Shutdown.

N/A Operator announces "Crew -Standby for Scram Report".

Examiner Note: If the Mode Switch is already in SHUTDOWN, provide the Terminating Cue. Operator locks the Mode Switch in SHUTDOWN.

Examiner Note: If the Mode Switch is now in SHUTDOWN, provide the Terminating Cue. Page 7 of 7 N/A N/A JPM NUMBER: BF012 NAME: -----

REVNUMBER:

08 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) 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: Task Standard:

Operator responds to a loss of CRD regulating function in accordance with HC.OP-AB.IC-0001

.

Page 8 of 8 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION BF012 NAME: -------------

08 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 9of9 JOB PERFORMANCE MEASURE JPM NUMBER: BF012 REVISION HISTORY Rev# Date Description Validation Required?

02 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 numbers.

Replaced 3 rod accumulator malfunctions with 3 active malfunctions for rods currently not at 00. Revised pull sheet step to 257 due to change in rod pattern.

Revised 10-3 step to 5.3.29.C due to procedure revs. Changed event trigger to lcvposx(

137) >=64 to trigger off actual rod movement of rod 26-43 vs. rod selection.

03 9/9/09 Updated procedure revision numbers.

Updated referenced N procedure step numbers.

Changed pump trip trigger from rod number 26-43 position 04 to rod 26-27 position 06 due to changes in rod pattern with new core model. No change in operator actions.

No validation required.

04 5/6/10 Updated reference procedure revisions.

Changed Control rod N and position to equivalent step due to core model changes.

No validation required.

05 9/12/11 Modified Malfunction, Remote, Override, and Event list sections N for TREX event syntax. Updated Reference procedure revision numbers only. Rod position changed from notch 08 to 06 due to core model change No changes to operator actions.

No validation required.

06 9/4/12 Added Task Standard to JPM. Updated Validation Checklist to N current form from TQ-AA-106-0304.

Editorial change only. No validation required.

Updated Reference procedure revisions only. No changes to operator actions.

No validation required.

07 3/17/13 Updated Reference procedure revision numbers only. Changed N pump trip trigger from rod number 34-11 position 06 to rod 14-35 position 18 due to changes in rod pattern with new core model. Revised pull sheet step to 245 due to change in rod pattern.

No changes to operator actions.

No validation required.

08 11/7/2014 Revised format. Deleted second rod movement steps. Revised y K&A to reflect RPS actions.

Changed rod movement due to change in Simulator Load. Incorporated comments from validation.

08 1/21/2015 Added information to the Initiating Cue. Corrected typographical N error in Standard.

Added controller designation per NRC request.

Added Reactivity Management Approval paqes (REMA). I Page 10of10 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BF012 REV#: 08 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Respond to a Loss of CRD Regulating Function Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO C. MINARICH SRO ON FILE 11/7/2014 Name Qua I Signature Date T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date Page 11 of 11 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: BF012 REV#: 08

"" . . ' *:t"!°?:\),

-:

t*' *tr> \< __ ., __

RESET simulator to an IC snapped during a startup and at approximately 500 psig. ---SELECT the rod associated with the previous step. Initial the Rod Pull Listing up through Step 320. ---INSERT Malfunctions and Event Triggers

---ENSURE Condensate Demineralizer Flow is less than 11,000 gpm. ---ENSURE associated Schedule and/or Event file(s) is/are open and running (as required).

Initial I Description MARKUP HC.OP-IO.ZZ-0003 up to and including 5.3.33.A with this step 5.3.33.A circled.

---MARKUP Rod Pull List through Step 320. ---ENSURE REMA for startup prepared.

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

' : ' ' "EVENTi'FILE:

Initial ET Initial Event code: LCVPOSX(107)>=90

==

Description:==

Rod 26-35 at 06 Event code: ZLLCPBSS 2

Description:

B CRD Pump START PB Light ON Cn; c,,,-. 1MALFUNCTIO

.. ?:tf?">"'"'

' ., @Time Event None None None None None None None None None None Action Insert malfunction CD1 OA after 15 on event 1 Insert malfunction CD054223 after 25 on event1 Insert malfunction CD053059 after 35 on event 1 Insert malfunction CD050239 after 45 on event1 Insert malfunction CD10B on event 2 Page 12of12 Description CRD hydraulic pump A trip Control Rod 18-43 accumulator trouble Control Rod 02-39 accumulator trouble Control Rod 42-23 accumulator trouble CRD hydraulic pump B trip Initial @Time Event Initial @Time Event JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Action Action Page 13of13 Description Description JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Reactor pressure is approximately 500 psig. 2. A Reactor startup is in progress in accordance with HC.OP-IO.ZZ-0003.

Completed up to step 5.3.34.C.

3. Currently completed Step 320 of the Rod Pull Listing (Rod 10-19 @ 04 ). INITIATING CUE: WITHDRAW control rods to attain 11,000 gpm through the Condensate Demineralizers in preparation to place the first RFP in service.

Page 14of14 J!JlopeCreek)

.. GENERATING STATION./

JOB PERFORMANCE MEASURE TRAININIG ONLY ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1of2 TITLE OF MANEUVER:

STARTUP REMA OP-AB-300-1003 Revision 11 Page 15of15 Reactivity Maneuver Plan #: HRE: 0005 Revision:

Q Valid Date(s):

TODAY Multiple Activations Allowed:

Yes D No C8J (If yes, SM/CRS may make additional copies) Complex ReMA: Yes cgj No D (If yes, Attachments 1 -9 are required)

(If no, Attachments 1, 2, 3, and 9 are required)

Prepared by:

__

Reviewed by: Pete Jones Today Reactor Engineer Date Qualified Nuclear Engineer Date Approved by: Rick Thompson Today Authorized by:

_____ T __ o'-'d"""'a-'J..y RE Manager Date Senior Reactor Operator Date NF Review Requested:

Yes C8J No D Performed/Declined by _B_ill_W_il_lia_m_s

______

NF Individual Contacted Date ReMA Activated:

Sam West Today ReMA Terminated:

_________

_ Control Room Supervisor Date Control Room Supervisor Date Purpose/Overview of Evolution The purpose of this document is to provide guidance on managing reactivity during the startup and placing the first Reactor Feed Pump in service.

General Issues

All Control Rod motion is documented IAW HC.RE-FM.ZZ-0001 (Q)

Power changes outlined in this plan should be limited to an average rate of 1 % RTP/min IAW HC.OP-10.ZZ-0003(0),

unless otherwise noted.

Power changes are not planned to exceed 15% per hour during this maneuver.

This maneuver is planned to start Today. Page 15of15 Maneuver Steps JOB PERFORMANCE MEASURE TRAININIG ONLY ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 2of2 OP-AB-300-1003 Revision 11 Page 16of16 1. WITHDRAW Control Rods IAW the Startup Sequence or MRPLs provided by Reactor Engineer to achieve conditions required to place the first Reactor Feed Pump in service.

2. This REMA is complete when the first Reactor Feed Pump is in service.

Additional Attachments None Page 16of16

STEP 1of3 JOB PERFORMANCE MEASURE TRAININIG ONLY ATTACHMENT 2 Reactivity Maneuver Guidance Sheet Reactivity Maneuver Plan # 0005 Description of Maneuver Step: Raise CTP to 9% RTP. OP-AB-300-1003 Revision 11 Page 17of17 This step is scheduled to begin today. This step ends after the first Reactor Feed Pump is in service.

ONE presence required in the Control Room: Yes D No [8J Onsite Only? Yes [8J No D Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range lnit. Parameter Value or Range lnit. FLLLP <0.100 N/A N/A N/A Critical Parameters to be Verified During the Step Description including frequency, method of monitoring, and High Low contingency actions (if needed) None N/A N/A Performance Steps: 1. RAISE CTP to 9% RTP using Rods per the Rod Pull Listing.

Currently at Step 320, Rod 10-19@ 04. 2. STOP power ascension when conditions are met to place the first Reactor Feed Pump in service.

ReMA Step Complete:

Verified by: __________

_ Reactor Operator Date Control Room Supervisor Date Page 17of17 JOB PERFORMANCE MEASURE STATION:

Hope Creek COPY OF SYSTEM: Control Area Ventilation TASK NUMBER: 4880030101 TASK: Place The Control Equipment Room Supply System In-Service JPM NUMBER: 305H-JPM.GK003

[JPM D] REVISION:

00 SAP BET: NOH05JPGK03E K/A NUMBER: 290003 A2.03 IMPORTANCE FACTOR: ALTERNATE PATH: D APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-SO.GK-0001, Rev. 22 TOOLS, AND EQUIPMENT:

None RO: 3.4 SRO: 3.6 ESTIMATED COMPLETION TIME: 15 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1 of 11 JOB PERFORMANCE MEASURE SYSTEM: Control Area Ventilation TASK NUMBER: 4880030101 TASK: Place The Control Equipment Room Supply System In-Service INITIAL CONDllTONS:

1. Maintenance is being performed on Chilled Water Pump AP400 and Chiller AK400. 2. Chilled Water Pump BP400 AND Chiller BK400 have just tripped.

INITIATING CUE: PLACE Control Area Ventilation Train B in-service without cooling, including the BVH407 fan, in accordance with Steps 5.8.1 through 5.8.5 of HC.OP-SO.GK-0001.

An Equipment Operator is standing by to assist. Page 2of11 '

JPM NUMBER: GK003 NAME: REV NUMBER: 00 DATE:

STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue, a marked-up copy of HC.OP-SO.GK-0001, AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator reviews precautions Operator reviews precautions and and limitations.

limitations.

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

Operator determines beginning Operator determines correct step of the procedure.

beginning step to be 5.8.1. 5.8.1 ENSURE that all prerequisites Operator ensures all prerequisites have been satisfied IAW are met, and completes Section 2.8. Attachment 1, Section 2.0, and initials Step. NOTE Normal lineup is to have one Operator reads and initials NOTE. supply unit in service and the other one in AUTO. Control Room Supply System Fans 1 AVH403 and 1 BVH403 are interlocked to operate in AUTO mode with Chilled Water Pump AP400 and BP400 respectively.

T.S. 3.7.2.1 and 3.7.2.2 Amendment No. 191 allows CREF operability without chilled water cooling.

5.8.2 IF available, SWAP to the Operator determines and initials Control Room Ventilation train Step as N/A. with an operable Chilled Water system IAW Section 5.4 AND EXIT this section.

5.8.3 PLACE Control Room Supply System in service as follows:

A. PRESS the flashing STOP *#operator presses the STOP PB's for any tripped Fan in PB's for 1BVH403,

1BVH407, the loop to be restarted AND BV415 fans, And initials Step. B. PRESS following CONTROL AREA ISOLATION DAMPERS OP MODE PBs: Operator presses the HD-9598A

1. HD-9598A NORMAL NORMAL PB, and initials Step. Page 3of11 JPM NUMBER: GK003 NAME: '

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT} 2. HD-9598B NORMAL Operator presses the HD-9598B NORMAL PB, and initials Step. C. PRESS the following CONTROL RM EMER FILTER UNIT RTN AIR FAN PBs AND INITIAL Operator presses the AV415 AUTO Attachment 1 : PB, initials Attachment 1, and 1. AUTO AV415. initials Step. 2. AUTO BV415. Operator presses the BV 415 AUTO PB, initials Attachment 1, and initials Step. D. ENSURE the following Control Room Supply Fan LOCKOUT/AUTO PBs in AUTO AND INITIAL Operator ensures that AUTO is Attachment 1: illuminated for CONT RM SPL Y 1. CONT RM SPL Y FAN FAN AVH403, initials Attachment AVH403 1, and initials Step. -2. CONT RM SPL Y FAN Operator ensures that AUTO is BVH403 illuminated for CONT RM SPL Y FAN BVH403, initials Attachment 1, and initials Step. E. PERFORM the following:

1. PRESS CONT ROOM *#Operator presses the BVH403 SUPPLY FAN A(B)VH403 START PB START PB, (A(B)VH403 ST ART is observes that ST ART is illuminated)

AND illuminated, and observes BVH415, OBSERVE A(B)VH415, CONTROL RM EMER FILTER CONTROL RM EMER UNIT RTN AIR FAN, Auto Start, FILTER UNIT RTN AIR and initials Step. FAN, Auto Start. 2. VERIFY Fl-9589A (B) Operator verifies that Fl-9589B CONTROL ROOM CONTROL ROOM SUPPLY SUPPLY SYSTEM SYSTEM B SPL Y FLOW indicates A(B) SPL Y FLOW approximately 17,500 cfm, and indicates approximately initials Step. 17,500 cfm. NOTE Normal lineup is to have one Operator reads and initials NOTE. Control Area Exhaust Fan in RUN AND the other in AUTO. Page 4of11

' JPM NUMBER: GK003 NAME: ----REV NUMBER: 00 DATE: STEP {*Critical Step) SAT/ COMMENTS NUMBER ELEMENT {#Sequential Step) UNSAT (Required for STANDARD UNSAT) 5.8.4 PLACE the Control Area Operator contacts the Equipment Exhaust System in service as Operator to perform Step 5.8.4, follows AND INITIAL and following the report, initials the Attachment 1 (Local Panel Step. 1 EC485): A. TURN HS-9599A(B),

CONTROL AREA EXHAUST FAN A(B)V402 to STOP AND THEN to RUN. B. TURN HS-9599B(A),

CONTROL AREA EXHAUST FAN B(A)V402 to STOP AND THEN to AUTO. CUE: Respond as Equipment Operator that Step 5.8.4 is complete.

NOTE It may be desired to place Operator reads and initials NOTE. A(B)VH407 fans in-service based on outside air temperatures.

IF not, refer to HC.OP-AB.HVAC-0001.

Normal lineup is to have one Supply Fan in service AND the other in AUTO. Control Equipment Room Supply Fans 1AVH407 AND 1 BVH407 are interlocked to operate in AUTO mode with Chilled Water Pumps AP400 AND BP400 respectively.

5.8.5 IF desired, PLACE the Control Equipment Room Supply System in service as follows:

A. ENSURE CONT EQ RM SPLY FAN LOCKOUT/AUTO PBs in AUTO AND INITIAL Operator ensures that AUTO is Attachment 1 : illuminated for CONT EQ RM SPL Y CONT EQ RM SPL Y FAN AVH407, initials Attachment

1. 1, and initials Step. FAN AVH407. 2. CONT EQ RM SPL Y Operator ensures that AUTO is FAN BVH407. illuminated for CONT EQ RM SPL Y FAN BVH407, initials Attachment 1, and initials Step. Page 5of11 JPM NUMBER: GK003 NAME: ' REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fa' STANDARD UNSAT) B. PERFORM the following:

1. operator presses the CONT 1. PRESS CONT EQ RM EQ RM SPLY FAN BVH407 SPL Y FAN A(B)VH407 START PB, START PB AND observes START is illuminated, OBSERVE ST ART is and initials Step. illuminated.

2. VERIFY FIC-9603A (B) Operator contacts the Equipment CONTROL EQ RM Operator to verify FIC-9603B FAN A(B)VH407 FAN indicates approximately 59,500 cfm AIR FLOW indicates (Local Panel DC483), and following approximately 59,500 report, initials the Step. cfm (Local Panel C(D)C483).

CUE: Respond as Equipment Operator that FIC-9603B indicates approximately 59,500 cfm. 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: -Task Standard:

Operator places Control Area Ventilation Train B in-service without cooling, including the BVH407 fan, in accordance with Steps 5.8.1 through 5.8.5 of HC.OP-SO.GK-0001.

Page 6of11 t JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION GK003 NAME:

00 DATE: SAT D UNSAT D SAT D UNSAT D Page 7of11

' JOB PERFORMANCE MEASURE JPM NUMBER: GK003 REVISION HISTORY Rev# Date Description Validation Required?

00 11/3/2014 Initial issue. Validated with RO and SRO. Incorporated y comments.

Validation time 15 minutes.

00 1/21/2015 Corrected typographical errors in Initial Conditions.

N Page 8of11 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: GK003 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Place The Control Equipment Room Supply System In-Service Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required}.

VALIDATED BY: Qualification Level Required:

RO T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date C. MINARICH SRO ON FILE 11/7/2014 Name Qua I Signature Date Page 9of11 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: GK003 Initial INITIALIZE the simulator to 100% power MOL. Initial Descri tion REV#: 00 MARKUP HC.OP-SO.GK-0001 Prerequisites and Attachment 1, Section 1.0 and 2.0 ---PLACE AP400 in MAN, AND PRESS AK403 STOP push button. ---PLACE BP400 in MAN, AND TRIP BP400. ENSURE BK403 trips. ---ACKNOWLEDGE Overhead Annunciators.

PLACE tagging bezel covers over AP400 and AK400. ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Initial ET Event code:

Description:

Initial @Time Event Action Description Initial @Time Event Action Description Initial @Time Event Action Description Page 10of11 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Maintenance is being performed on Chilled Water Pump AP400 and Chiller AK400. 2. Chilled Water Pump BP400 AND Chiller BK400 have just tripped.

INITIATING CUE: PLACE Control Area Ventilation Train B in-service without cooling, including the BVH407 fan, in accordance with Steps 5.8.1 through 5.8.5 of HC.OP-SO.GK-0001.

An Equipment Operator is standing by to assist. Page 11 of 11 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Containment Atmosphere Control TASK NUMBER: 4000510401 TASK: Respond To Rising Drywell Pressure COPY OF JPM NUMBER: 305H-JPM.GS011

[JPM E] REVISION:

00 SAP BET: NOH05JPGS11 E K/A NUMBER: 295010AA1.05 IMPORTANCE FACTOR: ALTERNATE PATH: D APPLICABILITY:

EO D STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0001, Rev. 3 TOOLS, AND EQUIPMENT:

None SRO C8J RO: 3.1 SRO: 3.4 ESTIMATED COMPLETION TIME: 10 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes -----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-10-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-10-2014 Training Department Page 1of9 JOB PERFORMANCE MEASURE SYSTEM: Containment Atmosphere Control TASK NUMBER: 4000510401 TASK: Respond To Rising Drywell Pressure INITIAL CONDllTONS:

1. HV-9531A1, A2, A3, AND A4, LOOP NB OTBD SPLY/RTN, closed due to a Bailey fault. 2. Efforts are underway to open those valves manually.

3. HC.OP-AB.CONT-0001, Drywell Pressure, is being implemented.

4. There are no indications of elevated Coolant System leakage.

INITIATING CUE: VENT the Drywell to maintain Drywell Pressure less than 0.75 psig in accordance with Condition C of HC.OP-AB.CONT-0001.

SECURE venting when Drywell Pressure is less than 0.5 psig. Page 2 of 9 JPM NUMBER: GS011 NAME: REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains and locates Operator obtains the correct procedure HG.OP-AB.CONT-procedure.

0001. Operator determines beginning Operator determines the correct step of the procedure.

beginning step to be C.1. CONDITION C. Drywell Pressure 0. 75psig AND No Evidence of Elevated Coolant System Leakage ACTION **NOTE 3** IF FRVS has NOT initiated, Operator reads and initials NOTE. periodic venting of containment is covered by the monthly SPV effluent permit and a separate gaseous effluent permit is not required.

(Refer to HC.RP-ST.ZZ-0004(0))

C.1. IF necessary, PREPARE a Operator determines and marks Gaseous Effluent Permit Step as N/A. concurrently with Step C.2 and C.3. C.2. VENT the Drywell to maintain Drywell Pressure<

0.75 psig as follows:

a. ENSURE Containment is Operator ensures Containment is aligned to vent thru aligned to vent thru RBVS/FRVS RBVS/FRVS within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start IAW prior to start IAW DL.ZZ-DL.ZZ-0026 and initials Step. 0026. b. OPEN the following:

operator opens HD-9372A,

1. HD-9372A and initials Step. 2. HV-4952 *operator opens HV-4952, and initials Step. Page 3 of9 JPM NUMBER: GS011 NAME: --------------------

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fc STANDARD UNSAT) 3. HV-4951 *operator opens HV-4951, and initials Step. C.3. SECURE Drywell venting as When Drywell pressure is <0.5 psig follows:

CLOSE the following:

operator closes HV-4951,

a. 1. HV-4951 and initials Step. 2. HV-4952 *operator closes HV-4952, and initials Step. 3. HD-9372A

operator closes HD-9372A, and initials Step. b. Visually VERIFY the Operator dispatches Equipment Blowout Panels in TABLE 1 Operator to visually verify Blowout are intact. Panels in Table 1 are intact and initials Step. -CUE: Respond as the Equipment Operator.

c. ENSURE the following Operator verifies that the following Back Draft Isolation dampers are Open as displayed on Dampers are OPEN.(GR)

GRIDS Page 105:

Dampers in table on

Dampers in table on GRIDS Page 105 GRIDS Page 105 [OPEN] and initials Step.

RB PIPECHASE CH A

RB PIPECHASE CH A ISLN DMPR ISLN DMPR [TEMP NHI] and initials Step.

RB PIPECHASE CH C

RB PIPECHASE CH C ISLN DMPR ISLN DMPR [TEMP NHI] and initials Step. 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: -Task Standard:

Operator vents the Drywell, and secures venting the Drywell when Drywell Pressure is less tha1. 0.5 psig in accordance with HC.OP-AB.CONT-0001.

Page 4 of 9 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION GS011 NAME:

00 DATE: SAT D UNSAT D SAT D UNSAT D Page 5of9 JOB PERFORMANCE MEASURE JPM NUMBER: GS011 REVISION HISTORY Rev# Date Description Validation Required?

0 11/7/2014 Initial issue. Validated with 2 ROs. Validation time 10 minutes.

y 0 1/21/2015 Corrected a typographical error in Element noted during NRC N review. Page 6of9 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: GS011 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Respond To Rising Drywell Pressure Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date J. NERE RO ON FILE 11/7/2014 Name Qua I Signature Date Page 7 of 9 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: GS011 **tc. ,;if* Initial INITIALIZE to 100% power MOL. ---CLOSE HV-9531A1, A2, A3, AND A4 ---ALLOW Drywell Pressure to rise to >1.00 psig ---PLACE the simulator in FREEZE Initial Descri tion COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Initial ET Event code:

Description:

Initial @Time Event Action . REMOTE Initial @Time Event Action Initial @Time Event Action Page 8of9 REV#: 00 Description Description Description

.. JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. HV-9531A1, A2, A3, AND A4, LOOP A/B OTBD SPLY/RTN, closed due to a Bailey fault. 2. Efforts are underway to open those valves manually.

3. HC.OP-AB.CONT-0001, Drywell Pressure, is being implemented.

4. There are no indications of elevated Coolant System leakage.

INITIATING CUE: VENT the Drywell to maintain Drywell Pressure less than 0. 75 psig in accordance with Condition C of HC.OP-AB.CONT-0001.

SECURE venting when Drywell Pressure is less than 0.5 psig. Page 9 of 9

.. ' JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Safety Auxiliaries Cooling Water TASK NUMBER: 4000780401 TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction COPY OF JPM NUMBER: 305H-JPM.EG008

[JPM F] REVISION:

09 SAP BET: NOH05JPEG08E K/A NUMBER: 295018 AA1.02 IMPORTANCE FACTOR: RO: 3.3 SRO: 3.4 ALTERNATE PATH: [8;J APPLICABILITY:

EO D RO [8;J STAD SRO [8;J EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.COOL-0002, Rev. 8 TOOLS, AND EQUIPMENT:

None ESTIMATED COMPLETION TIME: 4 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: ---"-N"""'/A-=---

Minutes JPM PERFORMED BY: GRADE: SATO UNSATD ACTUAL COMPLETION TIME: Minutes -----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-10-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-10-2014 Training Department Page 1 of 11 JOB PERFORMANCE MEASURE SYSTEM: Safety Auxiliaries Cooling Water TASK NUMBER: 4000780401 TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction INITIAL CONDllTONS:

1. The plant is operating at 100% power with TACS being supplied by SACS Loop A. 2. EOG OG400 is INOPERABLE and has been placed in service for a loaded maintenance run following work on the governor.

3. EOG OG400 has been loaded to 1000 K>N and approximately 500 KVAR in accordance with HC.OP-SO.KJ-0001. Load is being held here while governor stability at low loads is being evaluated.

4. SACS Pump BP210 just tripped and HC.OP-AB.COOL-0002 is being implemented.

INITIATING CUE: IMPLEMENT Condition A of HC.OP-AB.COOL-0002.

You are responsible for actions contained in HC.OP-AB.COOL-0002 ONLY. The Simulator is in Freeze. Inform the examiner when you are ready to begin. Page 2of11

, JPM NUMBER: EG008 NAME: ---------REV NUMBER: 09 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue; Operator obtains procedure Operator obtains the correct HC.OP AB.COOL 0002. procedure.

CUE: WHEN EITHER five minutes has elapsed, OR the Operator has indicated he/she is ready to begin, THEN ENTER START TIME, PLACE the Simulator in RUN, AND INFORM the Operator the JPM has commenced.

START TIME: CONDITION A. Trip of SACS pump in the Standby Loop. [T/S 3.7.1.1]

ACTION START the unaffected pump as A.1 follows:

Operator observes the SAFETY a. VERIFY INOP and AUXILIARIES COOLING LOOP B OVLD/PWR FAIL are not PUMPS PUMP D INOP and illuminated.

OVLD/PWR FAIL lights are not illuminated and initials Step. b. PLACE the pump in *#operator presses the SAFETY manual. AUXILIARIES COOLING LOOP B PUMPS PUMP D MAN pushbutton and observes the MAN light illuminates and the AUTO light extinguishes, and initials Step. c. START the pump. *#operator presses the SAFETY AUXILIARIES COOLING LOOP B PUMPS PUMP D, DP210 START pushbutton, and observes the PUMP D DP21 O START light illuminates and the STOP light extinguishes, and initials Step. Page 3of11 JPM NUMBER: EG008 NAME: '

REV NUMBER: 09 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) After approximately 3 seconds, the 'D' SACS pump trips and the operator observes the following:

PUMP D Al 63560 amps drop to zero

OHA A1 E5 SACS LOOP B TROUBLE reflashes

PUMP D DP210 START light extinguishes

PUMP D STOP light begins flashing CUE: IF the Operator questions who is responsible for DG400, DIRECT the Operator to perform Action A.2 of HC.OP-AB.COOL-0002.

A.2 IF flow cannot be restored to Operator determines flow cannot the affected loop, be restored to the 'B' SACS loop. THEN PERFORM the following:

UNLOAD AND SECURE all EDG's aligned to the affected loop as follows:

PRESS GEN VR Operator presses the a. EMERGENCY GENERATORS D LOWER pushbutton DIESEL GENERATOR 1DG400 until Generator KVAR GEN VR LOWER pushbutton until loading is < 200 KVAR. GEN D VARI 63950 indicates

<200 KVAR, and initials Step. b. PRESS DIESEL ENG *#operator presses the GOVDECR EMERGENCY GENERATORS D pushbutton until DIESEL GENERATOR 1DG400 Generator load < 200 DIESEL ENG GOV DECR KW. pushbutton until GEN DWI 6394D indicates

< 200 KW, and initials Step. Examiner Note: The DG400 output breaker may trip on reverse power. c. TRIP associated EOG Operator presses the GEN BRKR. EMERGENCY GENERATORS D DIESEL GENERATOR 1DG400 GEN BRKR TRIP pushbutton, observes the 40407 TRIP light illuminates and the CLOSE light extinguishes, and initials Step. Page 4of11

, JPM NUMBER: EG008 REV NUMBER: 09 STEP NUMBER ELEMENT d. STOP the EOG.

ENSURE Control Room Chilled Water is aligned to the unaffected loop.(GJ)

ENSURE TSC Chilled Water is aligned to the unaffected loop.(GJ)

DECLARE the loop inoperable, AND IMPLEMENT Condition K NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD

operator presses the EMERGENCY GENERATORS D DIESEL GENERATOR 1DG400 DIESEL ENG STOP pushbutton, observes the DG400 STOP light illuminates and the START light extinguishes BEFORE the EOG catastrophically fails and trips (==9 minutes with NO operator action),

and initials Step. Examiner Note: Successful completion of the JPM is satisfied IF the Operator secures the EOG before it catastrophically fails and trips. Operator observes the Control Room Ventilation and Chilled Water Train A is in service, and initials Step. Operator observes the TSC Ventilation and Chilled Water Train A is in service, and initials Step. Operator informs CRS SACS Loop B should be declared inoperable, and Condition K should be implemented, and initials Step. Examiner Note: It is not necessary for the Operator to perform any Condition K actions.

SAT/ UNSAT COMMENTS (Required for UNSAT) 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: Task Standard:

Operator implements Condition A of HC.OP-AB.COOL-0002, AND DG400 is: unloaded, Output Breaker is open, and stopped.

Page 5of11 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION EG008 NAME: ------------

09 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 6of11 '

, JOB PERFORMANCE MEASURE JPM NUMBER: EG008 REVISION HISTORY Rev# Date Description Validation Required?

03 914108 Revised to new JPM format. JPM Initial Cue and Start Time did not N change, therefore previously validated time did not change. No re-validation required.

Updated reference procedure revision number. Revised power level for EPU. Operator actions did not change. 04 12/7/09 Updated reference procedure revision number. Revised power level for N EPU. Operator actions did not change. Added "TIME "to step A.2.d COMMENTS field to mark time of stopping EOG. Replaced N/A with "9" minutes to "Time Period For Time Critical Steps". This time was already specified in the body of the JPM and is an editorial chanQe. 05 5/26/10 Updated reference procedure revision numbers.

Split out action steps N from observation elements.

Deleted Tap changers in manual. No longer needed for EOG operation in test. Operator actions did not change. Validated with 2 RO's. Average validation time did not change. 06 12/22/11 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.

07 9/17/13 Updated Validation Checklist to current form from TQ-AA-106-0304.

N Added Task Standard to JPM. Updated Reference procedure revision.

Editorial chanqe only. 08 3/10/2014 Added Core Work Practice information.

Modified Malfunction QQ15 to y delay for 3 seconds (consistent with expected response).

Revised Critical Steps and Completion Time based on Validation comments.

09 11/7/2014 Revised to new format. Removed Core Work Practice information N (redundant to TQ-QQ-203 and TQ-AA-106-0116).

Editorial changes.

Successfully used during 2014 LOR Annual Exam. Run for verification with RO and SRO 11/7/14.

No comments noted. 09 1/21/2015 Revised a Step A.2.b to not Critical from NRC review. N Page 7of11 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: EG008 REV#: 09 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13.

14. 15. TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.}

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO T. HENDRICKS RO ON FILE 3/13/2014 Name Qua I Signature Date S. KOZINK SRO ON FILE 3/13/2014 Name Qua I Signature Date Page 8of11 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: EG008 REV#: 09 f;*1Nrn*

,"':';,,:,;;,,:i+;;u,.'

' ' INITIALIZE the simulator to 100% power, MOL. ---ENSURE TAGS is aligned to SACS Loop A. ---ENSURE the Control Room Ventilation Train A is in service.

ENSURE TSC Ventilation Train A is in service.

---ENSURE EG-HV-2314B is closed. (SACS Loop B to Fuel Pool Cooling Heat Exchanger)

---START AND LOAD DG400 to 1000 KW AND 500 KVAR in accordance with HC.OP-SO.KJ-0001.

ACKNOWLEDGE Control Room AND Local Alarms. ---INSERT the trip of BP210 as follows:

---1. ENSURE BP210 is in service and DP210 is in standby.

---2. INSERT Malfunction QQ13 to SHORT. 3. ALLOW the pump to trip AND OHA A1-A5 to alarm, and THEN FREEZE the simulator.

---ENSURE associated Schedule and/or Event file(s) is/are open and running (as required).

Descri tion INITIAL HC.OP-SO.KJ-0001 for DG400 up through Step 5.6.13.A.9.

---UPDATE the LAST START AND BAR information for DG400. ---PLACE Robust Operational Barriers on DG400 BREAKER AND ENG Controls

---FLAG DG400 GOV AND GEN VAR pushbuttons.

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

Initial ET Event code: cw_z52pd 2

Description:

DP210 Start to trip DP210 shortly after start Page 9of11 Initial @Time Event None None None None REMOTE Initial @Time Event Initial @Time Event None None JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Action Description Insert malfunction QQ13 to short on event 1 SACS pump BP210 trip Insert malfunction QQ15 to short on event 2 after 3 Action Action SACS pump DP210 trip Description Description Insert override 5A29_A1_LO to On on event BP210 OVLD/PWR FAIL-LOOP B PUMPS-1 PUMP B (LO) Page 10of11 JOB PERFORMANCE MEASURE INITIAL CONDITIONS: 1 . The plant is operating at 100% power with T ACS being supplied by SACS Loop A. 2. EOG OG400 is INOPERABLE and has been placed in service for a loaded maintenance run following work on the governor.

3. EOG OG400 has been loaded to 1000 KW and approximately 500 KVAR in accordance with HC.OP-SO.KJ-0001.

Load is being held here while governor stability at low loads is being evaluated.

4. SACS Pump BP210 just tripped and HC.OP-AB.COOL-0002 is being implemented.

INITIATING CUE: IMPLEMENT Condition A of HC.OP-AB.COOL-0002.

You are responsible for actions contained in HC.OP-AB.COOL-0002 ONLY. The Simulator is in Freeze. Inform the examiner when you are ready to begin. Page 11of11 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Main Turbine TASK NUMBER: 2450100101 TASK: Roll the Main Turbine to Rated Speed JPM NUMBER: 305H-JPM.AC007

[JPM G] SAP BET: NOH05JPAC07E COPY OF REVISION:

03 K/A NUMBER: 241000 A3.18 IMPORTANCE FACTOR: RO: 3.0 SRO: 3.0 ALTERNATE PATH: 1:8:1 APPLICABILITY:

EO D RO 1:8:1 STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-SO.AC-0001, Rev. 69 TOOLS, AND EQUIPMENT:

None SRO 1:8:1 ESTIMATED COMPLETION TIME: 10 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes ----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-10-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-10-2014 Training Department Page 1 of 10 JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK NUMBER: 2450100101 TASK: Roll the Main Turbine to Rated Speed INITIAL CONDllTONS:

1. A Reactor Startup is in progress.

2. HC.OP-IO.ZZ-0003 is complete through Step 5.4.2. 3. Preparations to roll the Main Turbine are complete.

HC.OP-SO.AC-0001 is complete through Step 5.3.7. 4. The TBEO has been briefed and is standing by at the Front Standard.

5. No checks of the turbine are required at 800, OR 1500 rpm. INITIATING CUE: ROLL the Main Turbine IAW HC.OP-SO.AC-0001(0),

Main Turbine Operation.

Page 2of10 JPM NUMBER: AC007 NAME:

REV NUMBER: 03 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue, HC.OP-SO.AC-0001, AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator reviews Prerequisites, Operator reviews and initials Precautions, and Limitations.

Prerequisites, Precautions, and Limitations.

5.3.8. MONITOR Turbine Bearing Operator ensures CRIDS page #40 tern peratures and vibration is displayed on at least one CRT during Turbine roll by referring and initials Step. to GRIDS page display #40 TURB/GEN BRG & LUBE OIL, which should be displayed on one CRT Screen. [CD-053B]

5.3.9. WHILE rolling the Main Turbine Operator reads and initials Step. from turning gear to 1800 rpm in the following steps CLOSELY MONITOR all Main Turbine parameters in the CR AND DIRECT field operator(s) to listen for rubbing or unusual noises, and check for steam leaks and bearing oil flows. A. CYCLE HV-1065, Operator reads and initials Step. EXHAUST HOOD SUPPLY BYPASS to maintain GRIDS points A3169, A3170 and A3171 less than 140°F. CAUTION Vibration should be closely Operator reads and initials monitored as the Turbine Caution.

passes through the range where critical speeds occur (800 -1550 rpm). There is no automatic trip of the Turbine on vibration.

5.3.10. AFTER observing the parameters and operational requirements listed in Attachment 1, ROLL the Main Turbine as follows:

Operator selects lcontroll, A. SELECT IControll

, !Valve Limiters!

on DEHC HMI and !Valve Limiters!

initials Step. Page 3of10 JPM NUMBER: AC007 NAME: REV NUMBER: 03 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) B. VERIFY the following:

Operator verifies that all CV's, IV's All CV's, IV's and and MSV's are closed, and initials

Step. MSV's are CLOSED

Valves are properly Operator verifies the valves listed positioned per in Attachment 7 are positioned Attachment

7. properly for a TURB RESET, and initials Step.

Valve Position Limiter -Operator verifies Valve Position NOT LIMITING is Limiter -NOT LIMITING is displayed.

displayed, and initials Step.

Annunciator D3-D5, Operator verifies Annunciator D3-EHC Panel 1 OC363 is D5, EHC Panel 1 OC363 is extinguished.

extinguished, and initials Step. C. IF EITHER of the following Operator reads and initials Step. occur during the performance of the following step, THEN IMMEDIATELY TRIP the turbine:

Turbine speed increases rapidly beyond the 100 rpm hold point

CV's open before the IV's D. SELECT IControll

, Operator selects !Control!.

ISpeed-Loadl

!Speed-Load Ion DEHC HMI, and initials Step. E. SELECT Speed Cmd RPM *operator selects Speed Cmd Low (100), AND RPM Low (100), OBSERVE the following:

MSV#2 opens AND observes the following:

immediately AND

MSV #2 opens immediately WHEN MSV #2 is full AND WHEN MSV #2 is full open, MSV #1, #3 and open, MSV #1, #3 and #4 open #4 open slowly. slowly, and initials Step.

IV #1 , #3, and #5 open

IV #1, #3, and #5 opens slowly slowly AND WHEN IV AND WHEN IV #1, #3 and #5 #1, #3 and #5 are full are full open, IV #4, #2 and #6 open, IV #4, #2 and #6 (respectively) open, and initials (respectively}

open. Step. Page 4of10 JPM NUMBER: AC007 NAME: ----

REV NUMBER: 03 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)

Turbine Speed (RPM)

SPEED INCREASING is ON is increasing as the as the Turbine accelerates, Turbine accelerates.

and initials Step.

Turbine rolls off of

Turbine rolls off of turning gear turning gear (TURNING GEAR -(TURNING GEAR -ENGAGED is OFF), and DISENGAGED).

initials Step. CAUTION The turbine should be Operator reads and initials maintained at 90-100 rpm as Caution.

briefly as possible to achieve the desired checks. When turbine speed is maintained below 800 rpm for periods exceeding 5 minutes, turbine damage could result from non-detected rubs. CUE: If during the following the Operator requests directions, direct the operator to take any necessary actions.

F. WHEN Turbine Speed *operator observes speed indicates90-100 rpm at continue rapidly above 100 rpm Digital EHC HMI panel, hold point, and immediately CHECK for any abnormal (before the automatic trip on vibration, expansion, overspeed) trips the Main bearing temperatures, etc. Turbine, (Step 5.3.1 O.C) and informs the CRS. 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: Task Standard:

Operator responds to an abnormal Main Turbine response during Main Turbine roll in accordance with HC.OP-SO.AC-0001.

Page 5of10 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: AC007 NAME:

REV NUMBER: 03 DATE: QUESTION:

RESPONSE:

RESULT: SAT D UNSAT D QUESTION:

RESPONSE:

RESULT: SAT D UNSAT D Page 6of10 JOB PERFORMANCE MEASURE JPM NUMBER: AC007 REVISION HISTORY Rev# Date Description Validation Required?

03 11/7/2014 Complete re-write.

Validated with RO and SRO. Incorporated y comments.

Validation time 10 minutes.

Page 7of10 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: AC007 REV#: 03 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Roll the Main Turbine to Rated Speed Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

RO J. NERE RO ON FILE 11/7/2014 Name Qua I Signature Date C. MINARICH SRO ON FILE 11/7/2014 Name Qua I Signature Date Page 8of10 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: AC007 Initial RESET to IC ready to roll the Main Turbine.

---PERFORM actions required by HC.OP-SO.AC-0001, Steps 5.3.1 through 5.3.7. ---REV#: 03 ENSURE associated Schedule and/or Event file(s) is/are open and running (as required).

Initial Descri tion MARKUP HC.OP-SO.AC-0001 through Step 5.3.7. ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".

Initial ET Event code: tuns >= 40

Description:

Main Turbine >40 rpm Initial @Time Event Action Description None None Insert malfunction TC02-2 from 1.00000 to 2.00000 on event 1 Turbine control valve CV-2 failure Turbine control valve CV-3 failure None None Insert malfunction TC02-3 from 1.00000 to 2.00000 on event 1 Initial @Time Event Action Description Initial @Time Event Action Description Page 9of10 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A Reactor Startup is in progress.

2. HC.OP-IO.ZZ-0003 is complete through Step 5.4.2. 3. Preparations to roll the Main Turbine are complete.

HC.OP-SO.AC-0001 is complete through Step 5.3. 7. 4. The TBEO has been briefed and is standing by at the Front Standard.

5. No checks of the turbine are required at 800, OR 1500 rpm. INITIATING CUE: ROLL the Main Turbine IAW HC.OP-SO.AC-0001(0),

Main Turbine Operation.

Page 10of10 \

JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: System Name TASK NUMBER: 4001570401 TASK: Respond to a Reactor Recirculation Pump Runback COPY OF JPM NUMBER: 305H-JPM.BB001

[JPM H] REVISION:

09 SAP BET: NOH05JPBB01 E K/A NUMBER: 202001 A2.12 IMPORTANCE FACTOR: RO: 3.6 SRO: 3.8 ALTERNATE PATH: D APPLICABILITY:

EO D RO [8J STAD EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-SO.BB-0002, Rev. 100 HC.OP-AB.RPV-0004, Rev. 10 TOOLS, AND EQUIPMENT:

None SRO [8J ESTIMATED COMPLETION TIME: 13 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes -----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-10-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-11-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-10-2014 Training Department Page 1 of 10 JOB PERFORMANCE MEASURE SYSTEM: System Name TASK NUMBER: 4001570401 TASK: Respond to a Reactor Recirculation Pump Runback INITIAL CONDllTONS:

1. Plant was operating at 100% power. 2. Secondary Condensate Pump CP137 tripped.

3. HC.OP-AB.RPV-0004, Condition G, Action G.5 is being implemented.

INITIATING CUE: RESET the Reactor Recirculation Runbacks in accordance with HC.OP-SO.BB-0002.

Page 2of10 ,,

JPM NUMBER: BB001 NAME: REV NUMBER: 09 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator reviews precautions Operator reviews precautions and and limitations.

limitations.

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

Operator determines beginning Operator determines correct step of the procedure.

beginning step to be 5.4.1. CAUTION WHEN a scoop tube is locked Operator reads and initials up, a recirculation runback may CAUTION.

create a large flow mismatch.

Timely action must be taken to match loop flows by either resetting the runback, if possible, AND increasing the flow in the runback loop OR by unlocking the scoop tube to lower flow in the locked up loop. IF action cannot be taken in a timely manner, the Recirc Pump in the low flow (unlocked) loop should be tripped.

5.4.1 ENSURE all Prerequisites have Operator ensures that all been satisfied IAW Section 2.4. Prerequisites have been satisfied, and initials Step. CAUTION GRIDS update time should be Operator reads and initials accounted for when changing CAUTION.

Reactor Recirc Pump Output and Demand. Observe Reactor Recirc Pump speed. Stop lE actual speed is lowered.

Page 3of10 JPM NUMBER: 88001 NAME: ------------

---REV NUMBER: 09 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) 5.4.2 ENSURE GRIDS STR086/087, Examiner Note: Step 5.4.2 can be RECIRC: SPEED STATION completed for both Recirc Pumps A(B) OUTPUT, is less than OR concurrently or individually.

equal to the SPEED DEMAND indicated on SIC-R621 A(B) PUMP A(B) SPD CONT by *#Operator reduces CRIDS performing the following:

STR086(087),

RECIRC: SPEED A. REDUCE GRIDS STATION A(B) OUTPUT, by STR086/087, RECIRC: pressing the DECREASE push SPEED STATION A(B) button on SIC-R621 A(B) PUMP OUTPUT, by pressing the A(B) SPD CONT until the SPEED DECREASE push button STATION OUTPUT on CRIDS on SIC-R621 A(B) PUMP STR086(087) is less than OR A(B) SPD CONT until the equal to the SPEED DEMAND on SPEED STATION SIC-R621 A(B) PUMP A(B) SPD OUTPUT on GRIDS CONT, STR086/087 is less than OR equal to the SPEED and initials Step. DEMAND on SIC-R621 Examiner Note: Approximately A(B) PUMP A(B) SPD 46%. CONT. 5.4.3 PRESS the following for Examiner Note: Step 5.4.3 can be Reactor Recirc Pump A(B): completed for both Recirc Pumps A. INTMD RUNBACK RESET concurrently if 5.4.2 was performed for both Recirc Pumps, or can be push button performed individually.

1. Operator presses Reactor Recirc Pump A(B) INTMD RUNBACK RESET push button, and initials Step. 8. FULL RUNBACK RESET Operator depresses the FULL push button RUNBACK RESET push button and initials step, OR determines and marks Step as N/A. Page 4of10 JPM NUMBER: 88001 NAME:

REV NUMBER: 09 DATE: STEP NUMBER 5.4.2 5.4.3

-*-ELEMENT ENSURE GRIDS STR086/087, RECIRC: SPEED STATION A(B) OUTPUT, is less than OR equal to the SPEED DEMAND indicated on SIC-R621 A(B) PUMP A(B) SPD CONT by performing the following:

B. REDUCE GRIDS STR086/087, RECIRC: SPEED STATION A(B) OUTPUT, by pressing the DECREASE push button on SIC-R621 A(B) PUMP A(B) SPD CONT until the SPEED STATION OUTPUT on GRIDS STR086/087 is less than OR equal to the SPEED DEMAND on SIC-R621 A(B) PUMP A(B) SPD CONT. PRESS the following for Reactor Recirc Pump A(B): C. INTMD RUNBACK RESET push button D. FULL RUNBACK RESET push button (*Critical Step) (#Sequential Step) STANDARD

1. operator reduces CRIDS STR087(086),

RECIRC: SPEED STATION B(A) OUTPUT, by pressing the DECREASE push button on SIC-R621 B(A) PUMP A(B) SPD CONT until the SPEED STATION OUTPUT on CRIDS STR087(086) is less than OR equal to the SPEED DEMAND on SIC-R621 B(A) PUMP B(A) SPD CONT, and initials Step. Examiner Note: Approximately 46%. *#operator presses Reactor Recirc Pump B(A) INTMD RUNBACK RESET push button, and initials Step. Operator depresses the FULL RUNBACK RESET push button and initials step, OR determines and marks Step as N/A. SAT/ UNSAT COMMENTS (Required for UNSAT) 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: -------Task Standard:

Operator resets the Reactor Recirculation Runbacks in accordance with HC.OP-SO.BB-0002.

Page 5of10 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION 88001 NAME: ------------

09 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 6of10 JOB PERFORMANCE MEASURE JPM NUMBER: 88001 REVISION HISTORY Rev# Date Description Validation Required?

09 11/7/2014 Complete re-write.

Validated with RO and SRO. Incorporated y comments. Validation time 13 minutes.

09 1/21/2015 Corrected typographical errors in the Initial Conditions and N Simulator Setup. Added additional information in Standards per NRC request.

Page 7of10 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BB001 REV#: 09 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Respond to a Reactor Recirculation Pump Runback Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

.-VALIDATED BY: Qualification Level Required:

RO C. MINARICH SRO ON FILE 11/7/2014 Name Qua I Signature Date T. HENDRICKS RO ON FILE 11/7/2014 Name Qua I Signature Date Page 8of10

, JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 88001 INITIALIZE the simulator to 100% power MOL. Initial Descri tion TRIP Secondary Condensate Pump CP137. Allow conditions to stabilize.

---PERFORM AND MARKUP Actions G.1-G.4 of HC.OP-A8.RPV-0004.

---ACKNOWLEDGE Overhead Annunciators.

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

Initial ET Event code:

Description:

Initial @Time Event Action Initial @Time Event Action Initial @Time Event Action Page 9of10 REV#: 09 Description Description Description

' JOB PERFORMANCE MEASURE INITIAL CONDITIONS: 1 . Plant was operating at 100% power. 2. Secondary Condensate Pump CP137 tripped.

3. HC.OP-AB.RPV-0004, Condition G, Action G.5 is being implemented.

INITIATING CUE: RESET the Reactor Recirculation Runbacks in accordance with HC.OP-SO.BB-0002.

Page 10of10 f JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Control Rod Drive Hydraulic TASK NUMBER: 2010080104 TASK: Shift In-Service CRD Flow Control Valves COPY OF JPM NUMBER: 305H-JPM.BF001

[JPM I] REVISION:

16 SAP BET: NOH05JPBF01 E K/A NUMBER: 201001 A2.07 ALTERNATE PATH: D APPLICABILITY:

EO EVALUATION SETTING/METHOD:

Plant/Simulate

REFERENCES:

HC.OP-SO.BF-0001, Rev. 33 TOOLS, AND EQUIPMENT:

None IMPORTANCE FACTOR: RO: 3.2 SRO: 3.1 STAD ESTIMATED COMPLETION TIME: 17 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-8-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: Control Rod Drive Hydraulic TASK NUMBER: 2010080104 TASK: Shift In-Service CRD Flow Control Valves INITIAL CONDllTONS:

1 . The plant is operating at 80% power. 2. The RBEO reports that the in service CRD Hydraulic System Flow Control Valve has developed a packing leak. INITIATING CUE: ALTERNATE CRDH System Flow Control Valves from FV-F002B(A) to FV-F002A(B) in accordance with Section 5.2 of HC.OP-SO.BF-0001.

[Evaluator:

DETERMINE the in service and standbys FCV based on current plant conditions, AND MODIFY the STANDARDS appropriately.]

Page 2of10 JPM NUMBER: BF001 NAME: REV NUMBER: 16 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains locates Operator obtains the correct procedure HG.OP-SO.BF-procedure.

0001. Operator reviews precautions Operator reviews precautions and and limitations.

limitations.

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

Operator determines beginning Operator determines the correct step of the procedure.

beginning step to be 5.2.1, and then proceeds to 5.2.6. 5.2.1 ENSURE all prerequisites of Operator ensures prerequisites Section 2.2 are satisfied.

have been satisfied, completes Attachment 1, and initials each prerequisite in the space provided in the procedure.

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

5.2.6 IF FV-F002B(A),

B(A) Flow Operator determines that F002A(B)

Control Valve, is to be is to be alternated.

alternated, THEN PERFORM the following:

A. Slowly OPEN 1-BF-V014(1-

operator rotates the 1-BF-BF-V013),

CRD Drive Wtr V014(1-BF-V013)

T-hand wheel in FV-F002B(A)

Inlet Viv. the counterclockwise direction until the handwheel reaches full open, and initials Step. CUE: The valve indicated is open. B. Slowly OPEN 1-BF-V018(1-

operator rotates the 1-BF-BF-V017),

CRD Drive Wtr V018(1-BF-V017)

T-handwheel in FV-F002B(A)

Outlet Viv. the counterclockwise direction until the handwheel reaches full open, and initials Step. CUE: The valve indicated is open. Page 3of10 JPM NUMBER: BF001 NAME:

REV NUMBER: 16 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) NOTE The AUTO demand signal read Operator reads and initials NOTE. at 1-BF-Pl-D009B(A)C11, B(A) Flow Control Valve AIM Station is common to both FCVs and is indicated by the BLACK indicator regardless of AUTO/ MANUAL switch position.

As the FCV (in MANUAL) is opened at 1-BF-PI-D009B(A)C11, B(A) Flow Control Valve AIM Station, total CRD flow will momentarily increase causing the Auto signal (Black indicator) to the A AND B valves to be reduced.

The FCV in AUTO should throttle to maintain desired CRD system flow. After Steps 5.2.6.C AND 5.2.6. D are complete, all four signals (Auto AND Manual for both valves) should be approximately the same. -C. Slowly ADJUST the Operator rotates the 1 BF-Pl-INCREASE knob on valve D009B(A) controller increase knob B(A) UNTIL the Manual in the clockwise direction until the signal indicator (Red), is at red needle matches the position of the same position as the the black needle, and initials Step. Auto signal indicator (Black).

(B(A) Flow Control Valve AIM Station)

CUE: As operator motions rotating knob, provide the following information:

"The red needle is rising; the red needle position matches the black needle. D. As necessary, ADJUST the Operator rotates the 1 BF-Pl-INCREASE knob for valve D009A(B) controller increase knob A(B) UNTIL the Manual until the red needle matches the signal indicator (Red) is at position of the black needle, and the same position as the initials Step. Auto signal indicator (Black).

(A(B) Flow Control Valve AIM Station)

CUE: As operator motions rotating knob, provide the following information:

"The red needle position matches the black needle."

Page 4of10 JPM NUMBER: BF001 NAME: --------REV NUMBER: 16 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) E. POSITION valve B(A) to *operator rotates the 1-BF-PI-AUTO (B(A} Flow Control D009B(A)

AUTO/MAN knob in Valve AIM Station) the counterclockwise direction to the AUTO position, and initials Step. CUE: The switch you indicated is in the position stated. F. POSITION valve A(B) to Operator rotates the 1-BF-MAN (A(B) Flow Control D009A(B)

AUTO/MAN knob in the Valve AIM Station) clockwise direction to the MAN position, and initials Step. CUE: The switch you indicated is in the position stated. G. ADJUST the INCREASE Operator rotates the 1-BF-PI-knob on VALVE A(B) UNTIL D009A(B) controller increase knob Manual signal indicator in the counterclockwise direction (Red) indicates 0 (A(B) Flow until the red needle indicates 0, Control Valve AIM Station) and initials Step. CUE: As operator motions rotating knob, provide the following information:

"The red needle is lowering, the red needle indicates O." H. CLOSE the following valves: *operator rotates the 1-BF-1. 1-BF-V017(1-BF-V018),

V017(1-BF-V018)

T-handwheel in CRD Drive Wtr FV-the clockwise direction until F002A(B)

Outlet Viv valve handwheel reaches a hard stop, and initials Step. Examiner Note: It is NOT critical that both 1-BF-V017(18) and V013(14) be closed. CUE: The valve indicated is closed. 2. 1-BF-V013(1-BF-V014),

operator rotates the 1-BF-CRD Drive Wtr FV-V013(1-BF-V014)

T-handwheel in F002A(B)

Inlet Viv the clockwise direction until valve handwheel reaches a hard stop, and initials Step. CUE: The valve indicated is closed. I. PERFORM valve lineup IAW Operator performs lineup on Attachment 1 . Attachment 1, and initials Step. Page 5of10 JPM NUMBER: BF001 NAME:

REV NUMBER: 16 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) 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: Task Standard:

Operator alternates CRDH System Flow Control Valves in accordance with Section 5.2 of HC.OP-SO.BF-0001.

Page 6of10 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION BF001 NAME:

16 DATE: SAT D UNSAT D SAT D UNSAT D Page 7of10 JOB PERFORMANCE MEASURE JPM NUMBER: BF001 REVISION HISTORY Rev# Date Description Validation Required?

12 8/28/2008 Revised to new JPM format. Revalidated JPM time. y Updated reference procedure revision number. Operator actions did not change. 13 9/9/09 Revised due to procedure step numbers and added Note N from editorial changes to HC.OP-SO.BF-0001.

No validation required.

14 5/4/11 Updated reference procedure revision number. Operator N actions did not change. 15 3/19/13 Added Task Standard to JPM. Updated Validation Checklist N to current form from TQ-AA-106-0304.

Editorial change only. No validation required.

Updated reference procedure revision number. Deleted "and initials Attachment 1" from each step. Editorial change only. No validation required.

Revised to have the current in service FCV alternated.

No validation required.

16 12/4/2014 Revised to new JPM format. Minor revisions to CUEs. N Editorial changes only. Validated with 2 ROs. Average Validation Time was 17 minutes.

16 1/21/2015 Revised Initiating Cue with valve numbers and letter N desiqnations per NRC comments.

Page 8of10 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BF001 REV#: 16 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Shift In-Service CRD Flow Control Valves Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

EO J. KOSKEY RO ON FILE 12/4/2014 Name Qua I Signature Date D. WHITE RO ON FILE 12/4/2014 Name Qua I Signature Date Page 9of10 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is operating at 80% power. 2. The RBEO reports that the in-service CRD Hydraulic System Flow Control Valve has developed a packing leak. INITIATING CUE: ALTERNATE CRD Hydraulic System Flow Control Valves from FV-F002B(A) to FV-F002A(B) in accordance with Section 5.2 of HC.OP-SO.BF-0001.

Page 10of10

' JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: Primary Containment Instrument Gas TASK NUMBER: 4000340401 TASK: Respond To An Instrument Gas Malfunction COPY OF JPM NUMBER: 305H-JPM.KL006

[JPM J] REVISION:

00 SAP BET: NOH05JPKL06 K/A NUMBER: 295020 AA1 .01 IMPORTANCE FACTOR: RO: 3.6 SRO: 3.6 ALTERNATE PATH: D APPLICABILITY:

EO 1:8:1 RO 1:8:1 EVALUATION SETTING/METHOD:

Plant/Simulate

REFERENCES:

HC.OP-AB.COMP-0002, Rev. 8 STAD SRO 1:8:1 TOOLS, AND EQUIPMENT:

HC.OP-AB.COMP-0002 Implementation Kit ESTIMATED COMPLETION TIME: 24 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes -----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-9-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-8-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of9 JOB PERFORMANCE MEASURE SYSTEM: Primary Containment Instrument Gas TASK NUMBER: 4000340401 TASK: Respond To An Instrument Gas Malfunction INITIAL CONDllTONS:

1. A sealed in inadvertent isolation of ALL PCIG Primary Containment Valves has occurred.

2. HC.OP-AB.COMP-0002, Condition H is being implemented.

3. SACS is aligned to both PCIG compressors.

4. Technical Specification 3.6.3 and 4.6.1.1.b are being complied with. 5. Currently at Step 5.1 of Attachment

2. INITIATING CUE: PERFORM Attachment 3 of HC.OP-AB.COMP-0002 to override the isolation signal to HV-5124A.

Page 2of9 ,.

JPM NUMBER: KL006 NAME:

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains procedure Operator obtains the correct HC.OP-AB.COMP-0002.

procedure Operator determines beginning Operator determines correct step of the procedure.

beginning step to be 5.0 of Attachment

2. Operator ensures that all Operator reviews precaution and precautions have been initials the precaution in the space satisfied IAW Section 3.0. provided in the procedure.

4.0 EQUIPMENT REQUIRED

1. operator obtains the AB.COMP-0002 equipment required.

Implementation Kit Containing:

(Located in SM Office AB/EOP Locker)

1 Banana plug jumper

1 Lugged jumper (if banana jacks are unavailable)

1 Screwdriver

1 Flashlight

1 Bag for relay

Key #177 for cabinets in lower relay room CUE: Once the operator has obtained the equipment

required, inform the operator that the equipment is obtained and to return the equipment to its storage location.

NOTE The following steps bypass all Operator reads and initials NOTE. PCIS isolation signals to HV-5124A A INST GAS HOR SHUTOFF MOV. This will provide Instrument Gas to the Inboard MSIVs. The following steps are performed in the Lower Relay Examiner Note: Relay number is Room, Elev. 102'. extremely difficult to see due to Relay group number is in the cabinet configuration.

upper left hand corner of the baseplate.

Relay number is to the left of the relay. Page 3of9 r " JPM NUMBER: KL006 NAME:

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fo STANDARD UNSAT) 5.0 PROCEDURE 5.1. ENSURE all prerequisites Operator ensures all prerequisites have been satisfied IAW have been satisfied IAW Section Section 2.0 of this 2.0 of this attachment.

attachment.

5.2.REMOVE relay 11-14-1 *#operator removes relay 11-14-from cabinet 1 C-C 652 Bay 1 from cabinet 1C-C 652 Bay 11, 11, Front. (Relay group 14, Front, relay 1 -see Figure 1) and initials Step. NOTE Installation of the following Operator reads and initials NOTE. jumper will cause HV-5124A, INST GAS HOR SHUTOFF MOVto OPEN. 5.3. INSTALL jumper from *# Operator installs jumper from terminal 4-2-1-5 to terminal terminal 4-2-1-5 to terminal 4-2-1-4-2-1-4.

(Cabinet 1 C-C 657 4, Bay 4, Front, second group of terminal blocks from the and initials Step. top, terminal block 1, terminals 4 and 5 -see Figure 2). 5.4. VERIFY with the Control Operator contacts the Control Room HV-5124A, INST Room to verify HV-5124A, INST GASHDRSHUTOFFMOV GAS HOR SHUTOFF MOV is is OPEN. OPEN, and initials Step. CUE: WHEN operator requests status of HV-5124A, OR 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: Task Standard:

Operator overrides the isolation signal to HV-5124A in accordance with HC.OP-AB.COMP-0002.

Page 4of9 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION KL006 NAME: -------------

00 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 5 of 9 r JOB PERFORMANCE MEASURE JPM NUMBER: KL006 REVISION HISTORY Rev# Date Description Validation Required?

0 11/5/2014 Initial issue. Validated with RO and SRO. Validated time of 24 y minutes.

0 1/21/2015 Added map of Lower Relay Room per NRC comment.

N Page 6 of 9 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: KL006 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Respond To An Instrument Gas Malfunction Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

EO J. DOWER SRO ON FILE 11/5/2014 Name Qua I Signature Date D.HASSLER RO ON FILE 11/5/2014 Name Qua I Signature Date Page 7of9 JOB PERFORMANCE MEASURE 1DC658 FRONT FRONT I 1CC658 FRONT I 1BC658 1AC658 FRONT FRONT I 1CC654 1EC654 .r--10C613TP1 FRONT I> 1DC653 1CC653 1BC653 1AC653 1BC654 1 DC654 I 1 FC654 l1oc512t;J1oc614110c613110c612i I 10c615110c616i 10c659 H 1AC676 I 10Z656 10Z657 10Z658 10Z659 A B c D FRONT 10C690 FRONT E F 10C663 10 690 G 1628161416131 10-Z XXX D D DN I ELEC. RACEWAY I STEP 5.3 1DC657 BAY 4

......

STEP 5.2 1 CC657 FRONT ......_____

1 CC652 BA y 11 10C617 11oc52o I 10C622 I I . B I A . ._1_AC_6_5_7

_ __, 1CC696 1CC691 1AC694 1AC693 1AC696 Page 8 of 9 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A sealed in inadvertent isolation of ALL PCIG Primary Containment Valves has occurred.

2. HC.OP-AB.COMP-0002, Condition H is being implemented.

3. SACS is aligned to both PCIG compressors.

4. Technical Specification 3.6.3 and 4.6.1.1.b are being complied with. 5. Currently at Step 5.1 of Attachment

2. INITIATING CUE: PERFORM Attachment 3 of HC.OP-AB.COMP-0002 to override the isolation signal to HV-5124A. Page 9 of 9 JOB PERFORMANCE MEASURE STATION:

Hope Creek SYSTEM: 120 VAC Electrical Distribution TASK NUMBER: 2620070104 TASK: Remove A 120 VAC Electrical Distribution System From Service JPM NUMBER: 305H-JPM.PN004

[JPM K] SAP BET: NOH05JPPN04E COPY OF REVISION:

00 K/ANUMBER:

2.1.30 IMPORTANCE FACTOR: RO: 4.4 SRO: 4.0 ALTERNATE APPLICABILITY:

EO STAD EVALUATION SETTING/METHOD:

Auxiliary Building/Simulate

REFERENCES:

HC.OP-SO.PN-0001, Rev. 24 TOOLS, AND EQUIPMENT:

None ESTIMATED COMPLETION TIME: 20 Minutes -----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes -----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature DEVELOPED BY: S. DENNIS/SIGNATURE ON FILE DATE: 12-8-2014 Instructor REVIEWED BY: L. KOBERLEIN/SIGNATURE ON FILE DATE: 12-8-2014 Operations Representative APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE DATE: 12-9-2014 Training Department Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: 120 VAC Electrical Distribution TASK NUMBER: 2620070104 TASK: Remove A 120 VAC Electrical Distribution System From Service INITIAL CONDllTONS:

1. Maintenance is required on Inverter 1 DD481. 2. Plant conditions are satisfactory for this work. INITIATING CUE: REMOVE the 1 DD481 Inverter from service in accordance with Section 5.7 of HC.OP-SO.PN-0001.

Page 2of10 JPM NUMBER: PN004 NAME:

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains a copy of Operator obtains the correct HC.OP-SO.PN-0001.

procedure.

Operator reviews precautions Operator reviews precautions and and limitations.

limitations.

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

Operator determines beginning Operator determines the correct step of the procedure.

beginning step to be 5. 7.1. 5.7.1 ENSURE all prerequisites of Operator ensures prerequisites Section 2.7 are satisfied.

have been satisfied and initials each prerequisite in the space provided in the procedure.

NOTE The following steps apply only Operator reads and initials NOTE. to removing one of the BOP inverters (1AD492/1 BD492) from service.

These steps ... 5.7.2. !E one of the BOP inverters Operator determines and marks {1AD492 I 1 BD492) is to be Step as N/A. removed from service ... 5.7.3. VERIFY the PREFERRED Operator verifies the PREFERRED POSITION light is illuminated.

POSITION light is illuminated, and following the CUE, proceeds to Step 5.7.4. CUE: "The lamp you indicated is extinguished."

5.7.4. IF PREFERRED POSITION

1. Operator presses the light is not illuminated, THEN RETRANSFER push-button, PRESS the RETRANSFER verifies the PREFERRED push-button AND VERIFY the POSITION light is illuminated, PREFERRED POSITION light is illuminated.

and initials Step. CUE: "The lamp you indicated is illuminated."

Page 3of10 JPM NUMBER: PN004 NAME: --------REV NUMBER: 00 DATE: (*Critical Step) SAT/ COMMENTS STEP ELEMENT (#Sequential Step) UNSAT (Required fc NUMBER STANDARD UNSAT) 5.7.5. PLACE the MAN. BYPASS *#operator places the MAN. Control Switch in the extreme BYPASS Control Switch in the left preferred ISOLATE extreme left preferred ISOLATE position.

position, and initials Step. CUE: "The switch you indicated is in the position stated."

5.7.6. PLACE the VOLTAGE *operator places the VOLTAGE REGULATOR AC OUTPUT REGULATOR AC OUTPUT BKR-BKR-CB302 in the OFF CB302 in the OFF position, position.

and initials Step. CUE: "The breaker you indicated is in the position stated."

5.7.7. PLACE the VOLT AGE *operator places the VOLTAGE REGULATOR AC INPUT BKR-REGULATOR AC INPUT BKR-CB301 in the OFF position.

CB301 in the OFF position, and initials Step. -CUE: "The breaker you indicated is in the position stated."

5.7.8. PLACE the INVERTER AC *operator places the INVERTER OUTPUT BKR-CB10 in the AC OUTPUT BKR-CB10 in the OFF position.

OFF position, and initials Step. CUE: "The breaker you indicated is in the position stated."

5.7.9. PLACE the INVERTER DC *operator places the INVERTER INPUT BKR-CB101 in the OFF DC INPUT BKR-CB101 in the position.

OFF position, and initials Step. CUE: "The breaker you indicated is in the position stated."

5.7.10. PLACE the Static Inverter DC *operator places the Static FILTER CHARGE SWITCH in Inverter DC FILTER CHARGE the OFF position.

SWITCH in the OFF position, and initials Step. CUE: "The switch you indicated is in the position stated."

-Page 4of10 JPM NUMBER: PN004 NAME: REV NUMBER: 00 DATE: (*Critical Step) SAT/ COMMENTS STEP ELEMENT (#Sequential Step) UNSAT (Required for NUMBER STANDARD UNSAT) 5.7.11. PLACE the following ISOLATE

Operator places the ISOLATE Toggle Switches in the OFF UPS OUTPUT Toggle Switch in position

[left position]:

the OFF position, A. ISOLATE UPS OUTPUT and initials Step. CUE: "The switch you indicated is in the position stated."

B. ISOLATE INV OUTPUT *Operator places the ISOLATE INV OUTPUT Toggle Switch in the OFF position, and initials Step. CUE: "The switch you indicated is in the position stated."

C. ISOLATE SYNC SOURCE *Operator places the ISOLATE SYNC SOURCE Toggle Switch in the OFF position, and initials Step. CUE: "The switch you indicated is in the position stated."

5.7.12. PLACE the RECTIFIER

Operator places the ALTERNATE DC INPUT BKR-RECTIFIER ALTERNATE DC CB20 in the OFF position.

INPUT BKR-CB20 in the OFF position, and initials Step. CUE: "The breaker you indicated is in the position stated."

5.7.13. PLACE the RECTIFIER

Operator places the AUCTIONEER DC OUTPUT RECTIFIER AUCTIONEER DC BKR-CB21 in the OFF position.

OUTPUT BKR-CB21 in the OFF position, and initials Step. CUE: "The breaker you indicated is in the position stated."

5.7.14. PLACE the RECTIFIER AC

Operator places the INPUT BKR-CB201 in the OFF RECTIFIER AC INPUT BKR-position.

CB201 in the OFF position, and initials Step. CUE: "The breaker you indicated is in the position stated."

Page 5of10 JPM NUMBER: PN004 NAME: -------REV NUMBER: 00 DATE: -----*------

STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required fa STANDARD UNSAT) 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: Task Standard:

Operator removes the DD481 Inverter from service in accordance with Section 5. 7 of HG.OP-SO.PN-0001.

Page 6of10 JPM NUMBER: REV NUMBER: QUESTION:

RESPONSE:

RESULT: QUESTION:

RESPONSE:

RESULT: OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION PN004 NAME: -------------

00 0 ATE: SAT D UNSAT D SAT D UNSAT D Page 7of10 JOB PERFORMANCE MEASURE JPM NUMBER: PN004 REVISION HISTORY Rev# Date Description Validation Required?

00 12/4/2014 Initial issue. Validated with 2 ROs. Average Validation Time was y 20 minutes.

00 1/21/2015 Corrected typographical errors in the Initial Conditions and N Initiating Cue identified during NRC review. Page 8of10 x x x x x x x x x x x x x x x JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: PN004 REV#: 00 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. TASK: Remove A 120 VAC Electrical Distribution System From Service Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is:

(LOR); or (IL T); or justification is provided.

License level identified.

(SRO,RO,STA,NLO)

Performance location specified (In-Plant, Control Room, Simulator, or Classroom).

Initial setup conditions are identified.

Initiating and terminating cues are properly identified.

Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk

(*). Sequence Critical Steps are identified with a pound sign (#). JPM has multiple Critical Tasks, or justification of the basis for a single critical task. Procedure(s) referenced by this JPM match the most current revision of that procedure.

Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step. Statements describing important actions or observations that should be made by the operator are included (if required.)

Validation time is included.

JPM is identified as Time Critical and includes Critical Time (if required).

VALIDATED BY: Qualification Level Required:

EO J. KOSKEY RO ON FILE 12/4/2014 Name Qua I Signature Date D. WHITE RO ON FILE 12/4/2014 Name Qua I Signature Date Page 9of10 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Maintenance is required on Inverter 100481. 2. Plant conditions are satisfactory for this work. INITIATING CUE: REMOVE the 100481 Inverter from service in accordance with Section 5. 7 of SO.PN-0001.

Page 10of10 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM:

REVISION SUMMARY:

SIMULATOR EXAMINATION SCENARIO GUIDE 2015 NRC EXAM SCENARIO ESG-1 Effective When Approved 75 Minutes 1 COPY OF ----0 LICENSED OPERATOR REQUALIFICATION iZ! INITIAL LICENSE D OTHER:

Revised and revalidated based on comments made during validation.

PREPARED BY: D. M. REIN/SIGNATURE ON FILE 1/30/2015 INSTRUCTOR DATE APPROVED BY: M. SHAFFER/SIGNATURE ON FILE 2/5/2015 LORT GROUP LEAD OR DESIGNEE DATE APPROVED BY: L. KOBERLEIN/SIGNATURE ON FILE 2/11/2015 SHIFT OPERATIONS SUPERVISOR OR DESIGNEE DATE PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training I. OBJECTIVE(S):

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"*".) II. MAJOR EVENTS: A. Place RFP In Service B. Raise Reactor Power with Recirculation System C. Recirculation Pump Runaway 0. Loss of 100482 E. LOCA F. RPS Failure-ATWS/ARI Scram Successful G. HPCI Injection Valves' Failure-Loss of Condensate II. SCENARIO SUMMARY:

Plant is operating at approximately 84% power following Reactor Feed Pump (RFP) Maintenance.

The crew will place the RFP in service and commence power ascension.

A Recirculation Pump will run away during the power ascension.

The crew will take actions tu lower power to the pre-transient power level and enter Technical Specifications for Recirculation Loop mismatch.

Then a failure of a 1 E 120VAC Inverter will occur. This will cause an isolation of the Reactor Water Cleanup System and a loss of Reactor Building Ventilation.

Technical Specifications will be entered for the loss of a 1 E 120VAC source and Secondary Containment.

The crew will place Filtration, Recirculation, and Ventilation System (FRVS) in service to restore Secondary Containment integrity.

A Loss of Coolant Accident (LOCA) will progressively develop causing the crew to shut down the reactor.

The Reactor Protection System (RPS) will fail to initiate a Reactor Scram. The crew will manually initiate the Alternate Rod Insertion (ARI) System to shut down the reactor.

A loss of the Condensate System will occur during the scram response.

The High Pressure Coolant Injection (HPCI) System Injection Valves will fail on initiation.

Manual opening of the HPCI injection valves will be required to maintain vessel water level without requiring emergency depressurization.

ESG-1 Page 2 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. INITIAL CONDITIONS:

l.C. Initial ------

INITIALIZE to 100% power MOL. INSERT Group 1 OA Control Rods SET Cross-Flow to Not Applied and Blocked.

LOWER power with TCF to approximately 84%. STABILIZE Xenon concentration to simulate steady state conditions following maintenance.

Adjust TCF during Xenon stabilization to maintain 84% power. REMOVE RFP C from feeding the vessel, LOWER Demand to approximately 70% (discharge pressure 800-900 psig), AND make ready to feed in accordance with SO.AE-0001 through Step 5.7.2.E.

ENSURE TACS is on SACS Loop A. ENSURE Fuel Pool Cooling Pump A is in service.

ENSURE Schedule and/or Event File(s) is(are) open as required.

PREP FOR TRAINING (i.e., RM-11 set points, procedures, bezel covers) Initial I CREATE REMA to support power change to 95% power. ---MARKUP HC.OP-SO.AE-0001 through Step 5. 7.2.E. ---INITIAL 10-6 up through Step 5.1.3. ---REVIEW, at a minimum, the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed. (80091396 0270) ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".

---EVENT FILE: Initial Event 1 Event Code: zarrs621 (6) > 0.67 & zdrrs621 (6)

Description:

RR B speed >67% and Raise PB pressed 4 Event Code: zcrpsudn

>= 1

Description:

Reactor Mode Switch in Shutdown 5 Event Code: D2015_V

Description:

Main Turbine Tripped Event Code:

Description:

ESG-1 Page 3 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training MALFUNCTION SCHEDULE:

I Initial @Time Event Action Description None None Insert malfunction HP14 HPCI HV-F006 failure to auto open None None Insert malfunction HP15 HPCI HV-8278 failure to auto open None None Insert malfunction RZ03A RRCS Channel A -Logic A Failure to Auto Initiate None None Insert malfunction RZ03C RRCS Channel B -Logic A Failure to Auto Initiate None None Insert malfunction RP04 Failure of RPS to SCRAM (ATWS) None None Insert malfunction E00902 on event 2 Loss of 120 VAC class 1 E inst bus 100482 None None Insert malfunction RR31A1 to 100.00000 Recirc loop A small break [V] (10%-60 in 1200 on event 4 gpm, 100%-600 gpm) None None Insert malfunction RR31 A2 after 600 to Recirc loop A large break [VJ (10%-6000 1.00000 in 300 on event 4 gpm, 100%-60000 gpm) None None Insert malfunction FW30A after 5 on Heater 2A hi level switch failure event 5 None None Insert malfunction FW30B after 10 on Heater 28 hi level switch failure event 5 None None Insert malfunction FW30C after 3 on Heater 2C hi level switch failure I event 5 REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote HV06 to STOP on event 3 HV06 RBVS Supply fan C None None Insert remote HV05 after 1 to STOP on HV05 RBVS Supply fan B event 3 None None Insert remote HV04 after 1 to STOP on HV04 RBVS Supply fan A event 3 None None Insert remote HV03 after 2 to STOP on HV03 RBVS Exhaust fan C event 3 None None Insert remote HV02 after 2 to STOP on HV02 RBVS Exhaust fan B event 3 None None Insert remote HV01 after 3 to STOP on HV01 RBVS Exhaust fan A event 3 None None Insert remote AN24 after 5 to NORM on AN24 E6-C5 RBVS & Wing Area HVAC event 3 Pnl 10C382 ESG-1 Page 4 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training OVERRIDE SCHEDULE:

Initial <@Time Event Action Description None None Insert override 3A46 C DI to On on SIC-R621 B RAISE-REC I RC PUMP B event1 (DI) None None Insert override 5A159_C_DI to Off HV-1625 OPEN-BYPASS HEATERS 1 &2 ORN CLEAR (DI) None None Insert override 5A159_D_DI to Off HV-1625 RAISE-BYPASS HEATERS 1 &2 ORN CLEAR (DI} ESG-1 Page 5 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Place RFP In Service Expected Plant/Student Response

CRS directs placing 'C' RFPT in service.

PO places 'C' RFPT in service IAW SO.AE-0001.

=> PRESS the INCREASE j or DECREASE t push button on the Pump as necessary, to equalize the "DEMAND"

signals, WHILE MONITORING the following:

RFPT Discharge Pressure

RFPT "DEMAND"

RFPT "FLOW" => WHEN FLOW and SPEED are approximately equal, TRANSFER RFPT C SPEED CTRLR to automatic by pressing the A pushbutton AND observing "A" illuminates.

ROLE PLAY as Reactor

CRS leads Reactivity Brief. Engineer for the Reactivity Brief. RE guidance for power ascension is:

Raise reactor power to 90% RTP with core flow.

Withdraw 1 OA control rods from 00-6. (==4%)

Do not exceed 1 % per minute. ESG-1 Page 6 of 25 Comments HPI USED: STARD PEERCHECK0 FLAGGING D OP BARRIERS 0 INPO Fundamentals:

D Monitoring plant conditions and indications closely.

D Having a solid understanding of plant design and system interrelationships.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Raise Reactor Power with the Recirculation System MAINTAIN Recirc MG Oil temps (Monitor Variables rrtoil(1) and rrtoil(2))

as directed using Remotes CW15 and CW16 as appropriate.

ESG-1 Expected Plant/Student Response

CRS directs raising reactor power to 90% with reactor recirc pumps not to exceed 1 % per minute IAW IO.ZZ-0006 and REMA.

CRS informs System Operator of continued power ascension.

ROs review applicable sections of SO.BB-0002, noting vibration resonance and oscillation zones.

RO contacts TBEO and directs maintaining Recirc MG oil temperatures between 110-130 degF.

RO raises reactor recirc pump speeds obtaining Peer Checks from PO IAW HU-AA-101.

RO observes effect on: => Reactor Power => Recirc Loop Flow => Recirc Loop Jet Pump Flow => Total Core Flow

RO monitors reactor power and affected plant parameters.

Page 7 of 25 Comments INPO Fundamentals:

D Monitoring plant conditions and indications closely.

HPI USED: STARD PEERCHECK0 FLAGGING 0 OP BARRIERS 0 INPO Fundamentals:

D Monitoring plant conditions and indications closely.

D Having a solid understanding of plant design and system interrelationships.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response

RO ensures Recirculation loop flow mismatch is maintained within: 5% of rated core flow with effective core 70% of rated core flow.

RO ensures recirc pump speed changes do not exceed the rpm limitations of SO.BB-0002.

IF reactor power reaches 90% THEN RO informs CRS reactor power has been raised to 90%. Recirculation Pump Runaway

Crew recognizes Reactor Recirculation Pump A runaway by: Runaway will occur automatically when RR Pump B speed demand is 67%, OR at the discretion of the Lead Evaluator INSERT ET-1. ESG-1 OHA C1-A5 "COMPUTER POINT IN ALARM" Reactor power rising GRIDS D2900 "RECIRC MG B SPEED CONTROL SIG FAIL" GRIDS D29301 "RECIRC MG B DRIVE TUBE LOCK TRBL" SIC-R621 B SPEED DEMND and SPEED Upscale 1 OC650C Recirc and Jet pump indications Page 8 of 25 Comments IO.ZZ-0006 ST.BB-0001 SO.BB-0001:

Pump B speed changes should not exceed 10-20 rpm with a wait of 1 to 2 minutes between changes.(

3.1.14) SO.BB-0001:

In extended steady state two loop operation it is desirable to have Jet Pump Loop Flows approximately the same (within 1 mlbm/hr)

(3.2.17)

INPO Fundamentals:

D Monitoring plant conditions and indications closely.

Rev. 1 I PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Crew MAY enter AB.RPV-0008 due to a small rise in Offgas Pretreatment radiation levels. ESG-1 Expected Plant/Student Response

RO performs the following:

=> Presses SCOOP TUBE TRIP for 'B Recirc Pump => Reduces 'A' Recirc Pump speed to reduce power to pre-transient value

CRS implements AB.RPV 0001: => Condition F => Condition B may be referenced

CRS may refer to AB.RPV-0003

Crew checks Recirc Loop Flow mismatch IAW ST.BB-0001, Section 5.1.

Crew ensures Recirc MG Oil Temperatures are maintained in the normal band.

Crew Monitors Offgas Pretreatment AND Main Steam Line Radiation Monitors for indications of Fuel Damage.

CRS implements AB.RPV 0008: => Condition A => Condition C may be entered Page 9 of 25 Comments Immediate Operator Action IAW AB.RPV-0001.

HPI USED: STARD PEERCHECK0 INPO Fundamentals:

D CONTROL INPO Fundamentals:

D Monitoring plant conditions and indications closely.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity

!E called as RE to determine maximum thermal power reached, THEN REPORT thermal power peaked at approximately 90%(check GRIDS to ensure) (3460 MWth). ESG-1 Expected Plant/Student Response

Crew directs the following: Chemistry sample offgas; check HWCI, RWCU and Condensate Demineralizer operation; and Reactor coolant. Verify rod positions Rad Pro monitor rad levels; sample NPV Notify plant personnel

Crew determines peak thermal power during the transient.

CRS recognize the following Tech Specs/actions apply: 3.4.1.3 Recirculation Loop Flow

CRS contacts Operations Management to initiate Prompt Investigation and ERT callout.

Page 10 of 25 Comments Must restore recirc loop flow mismatch within tvl hours or declare the B loop not in operation.

INPO Fundamentals:

0 KNOWLEDGE Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Loss of 100482 After Technical Specifications have been addressed, OR at the discretion of the Lead Evaluator, INSERT ET-2. ESG-1

Expected Plant/Student Response Crew recognizes loss of DD482 by observing:

=> OHA A7-C2, SACS SUPPLY RHR PUMP D TROUBLE, in alarm => Both RWCU Pumps trip. => RWCU Loss OHAs C1-C2, -D2, and -F2 => Loss of 1 E DIV 2/Channel D analog instrumentation.

=> Loss of control and status indication for Non-ECCS Division 2/Channel B components.

=> RCIC, RHR D and Core Spray D will lose status indications ONLY. => GRIDS page 167

CRS enters AB.ZZ-0136 and directs actions IAW AB.ZZ-0136 including Attachment 8: => Assess all plant systems and enter appropriate Abnormal Procedures

=> Determine failed inverter

CRS enters/refers to AB.CONT-0002 for loss of RWCU: => Condition B

Crew informs Chem Tech that RWCU and Recirc Sample have been lost (AB.CONT-0002). Page 11 of 25 Comments NOTE: OHA D3 E3 "120VAC UPS TROUBLE" is NOT received on a loss of a 482 inverter.

482 inverter supplies the output to this alarm for its channel.

INPO Fundamentals:

D Monitoring plant conditions and indications closely.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response WHEN dispatched, THEN

Crew dispatches ABEO REPORT: and/or 12 Hr Maintenance to

Inverter main power fuses are investigate loss of inverter

. blown

CB302 (AC Regulator Output) and CB10 (Inverter AC Output) are tripped

There is an acrid odor coming from the static switch. Loss of RBVS due to closure of

Crew recognizes Loss of INPO Fundamentals:

HV-9370B and HV-9414B (loss of RBVS by: D Monitoring plant solenoid power). => RB D/P indication on conditions and 1 OC650E (PDR-9426NB) indications closely.

=> SPDS RB PARAMETERS D/P indication.

=> OHA E1-F5 "COMPUTER PT IN ALARM" => GRIDS B7164 "REACTOR BLDG DIFF PRESS" => OHA E6-C5 "RBVS & WING AREA HVAC PNL 10C382" => CRI OS 03960 "RBVS EXH RMT PNL C382 TRBL" => GRIDS 03961 "RBVS SUPPLY RMT PNL C382 TRBL"

CRS implements AB.CONT-003: => Condition A => Condition D

Crew dispatches RBEO to 1 OC382 to investigate.

ESG-1 Page 12 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity IF directed to secure RBVS, THEN TRIGGER ET-3. Expected Plant/Student Response

RO/PO place FRVS in service IAW SO.GU-0001, or AB.ZZ-0001 Attachment

20. => Start 1 FRVS Vent Fan => Dispatch an operator to stop RBVS fans => Close the Reactor Bldg lnbd/Outbd Supply/Exh dampers at Panel 10C651 E => Start 4 FRVS Recirculation Fans

CRS/STA/IA recognize the following Tech Specs apply: => Secondary Containment Integrity

=> 3.6.5.1 => Secondary Containment Automatic Isolation Dampers => 3.6.5.2 action a or b or c

CRS/STA/IA recognize the following Tech Specs actions apply for the loss of DD482: => Distribution

-Operating 3.8.3.1 action a AND d ESG-1 Page 13 of 25 Comments HPI USED: STARD PEERCHECK0 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to reenergize panel and restore inverter within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or Hot SD in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold SD in following

24. Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity LOCA

After Technical Specifications have been addressed, OR at the discretion of the Lead Evaluator, INSERT ET-4. RPS failure is pre-inserted.

* * *

ESG-1 Expected Plant/Student Response Crew recognizes coolant leak: =:> OHA C6-B1 "OLD SYSTEM ALARM/TRBL"

=:> RM11 9AX314 OLD FLOOR ORN FLOW alarm =:> RM11 9AX317/318/320 OLD CCM alarms =:> OHA 03-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-0006: =:> Condition A =:> Condition B =:> Condition C CRS implements AB.CONT-0001: =:> Condition A RO/PO ensures drywell cooling maximized.

Crew checks: =:> Recirc pump seal parameters

=:> SRV temperatures WHEN the Crew determines drywell pressure cannot be maintained below 1.5 psig, THEN CRS directs:

=:> Reducing recirc pump A to minimum speed =:> Locking the Mode Switch in SHUTDOWN Page 14 of 25 Comments INPO Fundamentals:

D Monitoring plant conditions and indications closely.

INPO Fundamentals:

0 CONSERVATISM Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Reports Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status IAW 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 JAW HC.OP-AB.

ZZ-0001.

RPS Failure RPS failure is pre-inserted.

ESG-1

Expected Plant/Student Response RO: => Reduces recirc pump A to minimum speed => Locks the Mode Switch in SHUTDOWN

RO recognizes RPS failure, announces condition, and initiates ARI IAW AB.ZZ-0001.

After placing the Mode Switch in SHUTDOWN, the Crew manually initiates ARI to shut down the reactor.

RO recognizes successful shutdown and continues with scram actions.

Page 15 of 25 Comments RPS will NOT cause a scram on ANY signals.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Loss of Feedwater:

The 1 &2 Feedwater heaters will isolate shortly after the Main Turbine Trip. ENSURE ET-5 activates.

The bypass around the 1 &2 Feedwater heaters is failed shut. ESG-1

Expected Plant/Student Response Crew recognizes RPV Level Below 12.5" EOP entry condition by: OHA C5-A4 "RPVWATER LEVEL LO" OHA A 7-05 "RPV LEVEL 3" Various water level indicators

CRS enters EOP-101A

briefly, then transitions to EOP-101.

Crew recognizes 1&2 FWH trip by: OHAA7-E2 "FEEDWATER HEATER TRIP" Flashing HTR TRIP lights for FWH #2A/B/C Condensate Inlet and Outlet valves stroking shut for FWH 1 &2A/B/C.

PO may attempt to bypass 1 &2 FWHs IAW AB.ZZ-0001 Att. 14.

PO informs CRS of inability to inject with condensate.

CRS implements AB.CONT-0006: Condition D

RO: Trips reactor recirc pumps within 10 minutes of loss of RACS cooling (1.68 psig OW pressure)

IF RPT breakers are not open. Page 16 of 25 Comments INPO Fundamentals:

0TEAMWORK INPO Fundamentals:

D Monitoring plant conditions and indications closely.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity HPCI Injection Valves Fail To Open: HPCI Injection Valves' failure is pre-inserted.

ESG-1 Expected Plant/Student Response

WHEN Drywell Pressure reaches 1.68#, THEN Crew recognizes RFPT trips by: => OHA B3-E1 "RFP TURBINE TRIP" => RFPT Control Valve indications on 1 OC650C => TRIP status light on RFPT bezels => RFPT discharge pressure indications on 1 OC650C => Feed flow indications

CRS directs level control with any combination of the following IAW EOP 101: => HPCI => RCIC

RO/PO ensure isolations occur IAW either: => SO.SM-0001 OR => AB.CONT-0002

PO manually initiates HPCI IAW AB.ZZ-0001 Att. 6.

PO recognizes failure of HPCI to automatically initiate by: => OHA B1-E5 HPCI PUMP DISCHARGE FLOW LO => High Discharge Pressure

=> High Turbine Speed => No injection flow Page 17 of 25 Comments INPO Fundamentals:

D Monitoring plant conditions and indications closely.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity ESG-1

Expected Plant/Student Response PO manually aligns HPCI for injection IAW AB.ZZ 0001 Att. 6 (ensures HV-F006 and HV-8278 are open and adjusts FIC-R600 as necessary) and informs CRS of injection valve failures

Before Compensated RPV water level drops below -185" AND without Emergency Depressurizing, Crew manually places HPCI in service and injects with HPCI to restore and maintain Compensated Reactor water level above -185".

Crew recognizes 1.68 psig Drywell Pressure EOP entry condition by: ==> OHA A 7 04 "DRYWELL PRESSURE HI/HI" ==> OHA C5 85 "DRYWELL PRESSURE HI" ==> Various system initiations and isolations

CRS enters EOP-102 .

Crew reports Torus Water temperature if it reaches 95 degrees.

CRS re-enters EOP-102 if applicable.

CRS directs placing A and/or B RHR pumps in Suppression Pool Cooling & Suppression Chamber Spray. Page 18 of 25 Comments INPO Fundamentals:

D CONTROL INPO Fundamentals:

0TEAMWORK RECORD time that drywell pressure exceeds 1.68# TIME: Rev. 1 I PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response Note: An Alert is required to be

RO/PO place A and/or B RHR HPI USED: declared IAW ECG RB2.L pumps in Suppression Pool STARD (Drywell Pressure

>1.68 psig due Cooling and Suppression HARD CARD D to RCS leakage),

OR ECG SA3.1 Chamber Spray IAW AB.ZZ-(An automatic scram failed to 0001 Att. 3. shutdown the reactor as indicated by reactor power> 4% AND Manual scram actions taken at the reactor control console (mode switch, manual scram pushbuttons, manual ARI actuation)

DO shutdown the reactor as indicated by reactor power:::;

4%.)

CRS directs restoring:

=> 1 E Breakers

=> CRD => PCIG to SRVs => Instrument Air

IF directed, THEN RO/PO HPI USED: restore 1 E breakers IAW STARD AB.ZZ-0001 Attachment

12. HARD CARD 0

IF directed, THEN RO/PO HPI USED: restore PCIG to SRVs IAW STARD AB.ZZ-0001 Att. 9 HARD CARD 0

IF directed, THEN RO/PO restore a CRD HPI USED: pump to service IAW either: STARD => SO.BF-0001 Sect 5.2 HARD CARD 0 OR => AR.ZZ-0011 Attachment F2 Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when:

RPV level is being maintained above -161" ESG-1 Page 19 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requalification Training Exam Development Job Aid B. NU REG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Hope Creek Event Classification Guide (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-101-111-1004 Operations Standards M. OP-AA-106-101-1001 Event Response Guidelines N. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program 0. OP-HC-108-106-1001 Equipment Operational Control P. HC.OP-SO.AE-0001 Feedwater System Operation Q. HC.OP-SO.BJ-0001 High Pressure Coolant Injection System Operation R. HC.OP-AB.ZZ-0001 Transient Plant Conditions S. HC.OP-AB.ZZ-0136 Loss Of 120 VAC Inverter T. HC.OP-AB.CONT-0001 Drywell Pressure U. HC.OP-AB.CONT-0002 Primary Containment V. HC.OP-AB.CONT-0006 Drywell Leakage W. HC.OP-AB.RPV-0001, Reactor Power X. HC.OP-AB.RPV-0003, Recirculation System/Power Oscillations Y. HC.OP-EO.ZZ-0101 RPV Control Z. HC.OP-EO.ZZ-0101A, ATWS-RPV Control AA. HC.OP-EO.ZZ-0102 Primary Containment Control ESG-1 Page 20 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VII. ESG CRITICAL TASK RATIONAL ESG-1/1 1.

After placing the Mode Switch in SHUTDOWN, the Crew manually initiates ARI to shut down the reactor.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA 1. Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

EA 1.01 Reactor Protection System RO 4.6 SRO 4.6 EA1 .03 ARl/RPT/ATWS RO 4.1 SRO 4.1 2. This action is prescribed by the Abnormal Procedures.

Under the scenario conditions, the Reactor Protection system has failed to respond to a manual scram condition.

The operator must take action to mitigate the failure associated with the RPS malfunction by initiating backup scram actions.

This action rapidly inserts control rods to shut down the reactor, preventing prolonged power operations without normal level control systems.

Before Compensated RPV water level drops below -185" AND without Emergency Depressurizing, Crew manually places HPCI in service and injects with HPCI to restore and maintain Compensated Reactor water level above -185". KIA 206000 High Pressure Coolant Injection System A3 Ability to monitor the operations of the HIGH PRESSURE COOLANT INJECTION SYSTEM including:

A3.03 System lineup RO 3.9 SRO 3.8 KIA 295031 Reactor Low Water Level EA 1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA 1.02 High Pressure Coolant Injection RO: 4.5 SRO 4.5 ESG-1 The HPCI system has failed to automatically inject into the reactor.

HPCI is the only High Pressure injection system available with adequate capacity to maintain RPV water level. If RPV water level is allowed to drop below -185", the fuel will be uncovered sufficiently to challenge the fuel cladding integrity.

This would escalate the event to a Site Area Emergency.

The rate of level drop in this scenario is very slow and provides more than adequate time to execute the guidance and restore RPV level with HPCI without Emergency Depressurization.

Page 21 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training ESG-1/1 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT Loss Of Offsite Power/SBO Internal Flooding

---Y/N y ---------------------------y LOCA TRANSIENTS:

Turbine Trip Loss of Condenser Vacuum Y Loss of Feedwater Manual Scram LOSS OF SUPPORT SYSTEMS:

Loss of SSW Loss of SACS COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY SYSTEMS HPCI SRVs ---RCIC y Condensate/Feedwater

---B/D EDG SSW ---A/B RHR Pump y RPS A/B SACS Loop 1E4.16KVBus 1E480 VAC Bus 120VAC 481 Inverter 1E 125VDC Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION Manual Depressurization of the RPV w/ no HP Injection Available

---___ Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi DW Press. Signal ---Control RPV Water Level w/ HP Injection during ATWS Sequence

___ Align Portable Power Supply to Battery Chargers

---Venting of Primary Containment

___ Restore Switchgear Cooling Restart Condensate

---Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence

---Complete this evaluation form for each ESG ESG-1 Page 22 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VIII. TURNOVER SHEET:

PROTECTED EQUIPMENT None EOOS is out of service REACTIVITY I Plant Status Commenced power ascension.

Power is approximately 84%. Place RFP C in service, then raise reactor power in accordance with 10-6 and REMA. Currently at 10-6 up through Step 5.1.3. ESF/SAFETY SYSTEMS None COOLING WATER None BOP RFP startup in progress in accordance with HC.OP-SO.AE-0001, through Step 5.7.2.E.

ELECTRICAL None ADVERSE CONDITION MONITORING None Page 23 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG-1 SELF-CHECK

1. Total malfunctions inserted:

5-8 --2. Malfunctions that occur after EOP entry: 1-4 --3. Abnormal Events: 2-3 --4. Major Transients:

1-2 --5. EOPs used beyond primary scram response EOP: 1-3 --6. EOP Contingency Procedures used: 0-3 --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

--10. Technical Specifications are exercised during the test: >1 --Comments:

ESG-1 Page 24 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

(continued)

Crew Validation Rev.: 0 Date Validated:

10/30/2014 Validated with operators from Crew A. Validation Comments Disposition

1. Minor changes to REMA and Turnover.

1. Changes made. 2. Add SA3.1 to ECG. 2. Changes made. 3. Add actions for RFPT to service.

3. Changes made. 4. Add references to additional Abs. 4. Changes made. Crew Validation Rev.: 1 Date Validated:

Validated with operators.

Validation Comments Disposition

1. Revised based on NRC validation.

1. Added recommendation to raise the standby Reactor Feed Pump discharge pressure to 800-900 psig in the setup. 2. Raised leak rate slightly.

Does not affect expected actions.

3. Reinserted automatic Event Trigger 1. 4. Added actions if crew determines rise in Offgas Radiation levels warrant entry into HC.OP-AB.RPV-0008.

5. Added reason for loss of Reactor Building Ventilation on Event 4. Added Reactor Building d/p instruments.

6. Added actions to open valves for Event 7. ESG-1 Page 25 of 25 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SIMULATOR COPY OF ----EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 2015 NRC EXAM SCENARIO SCENARIO NUMBER: ESG-2 EFFECTIVE DATE: Effective When Approved EXPECTED DURATION:

75 Minutes REVISION NUMBER: 1 PROGRAM:

0 LICENSED OPERATOR REQUALIFICATION

[gj INITIAL LICENSE OOTHER: REVISION SUMMARY:

Incorporated editorial comments from NRC validation.

PREPARED BY: S. DENNIS/SIGNATURE ON FILE 12-9-2014 INSTRUCTOR DATE APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE 12-9-2014 LORT GROUP LEAD OR DESIGNEE DATE APPROVED BY: L. KOBERLEIN/SIGNATURE ON FILE 12-11-2014 SHIFT OPERATIONS SUPERVISOR OR DESIGNEE DATE PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training I. OBJECTIVE(S):

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 "*".) II. MAJOR EVENTS: A. EHC Pump Swap B. Lower Power With Control Rods and Recirculation Flow C. Flow Unit Failure D. EHC System Leak E. A TWS-Main Turbine Trip-Bypass Valve Failure F. Failure of SBLC to Automatically Initiate G. CRD Pump Trip H. EOP Implementation Failure II. SCENARIO SUMMARY:

The scenario begins with the plant at approximately 95% power reduction for a rod pattern adjustment in progress.

EHC pumps will be swapped to support pump maintenance.

The Crew will continue the power reduction by inserting control rods and lowering Reactor Recirc flow. The A Flow Unit will fail upscale causing a half scram and rod block. After the Flow Unit is bypassed, the Half Scram is reset, and Tech Specs have been referenced, a leak in the EHC System will occur. The Crew will be unable to isolate the leak and a manual scram will be inserted, or an automatic scram (approximately 8 minutes from leak insertion) on a Main Turbine trip will occur. The scram will be unsuccessful and result in a 1/2 core ATWS. Both SLC pump will fail to automatically start, but can be started by the Crew. Both SLC pumps will trip 10 minutes after start. The Turbine Bypass valves will fail to open, resulting in SRV actuation being necessary to control reactor pressure.

Shortly after the A TWS the running CRD pump will trip. This will require the standby pump be placed in service in order to manually insert control rods and charge accumulators.

Improper implementation of an Emergency Operating Procedure in the field will require re-performance/correction of the EOP, or rods to be manually inserted to shut down the reactor.

The scenario ends when the Crew is inserting control rods with RMCS, or all rods are inserted using EOP-320.

ESG-2 Page 2 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. INITIAL CONDITIONS:

l.C. Initial INITIALIZE the simulator to 100% power MOL. ---ENSURE Control Area Ventilation loop B is in service.

---ENSURE EHC Pump BP116 is in service.

---ENSURE CRD Pump A is in service ---LOWER reactor power to 95% using Recirculation Pumps ---SET Cross Flow to NOT APPLIED AND BLOCKED.

---ENSURE Schedule and/or Event File(s) is(are) open as required.

---PREP FOR TRAINING (i.e., RM-11 set points, procedures, bezel covers) Initial j INITIAL 10-6 up through Step 5.2.9. ---ENSURE REMA is provided to support power reduction.

---REVIEW, at a minimum, the Scenario Reference section and CLEAN the balded EOPs, ABs and SOPs listed. (80091396 0270) ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".

---EVENT FILE: Initial Event 3 Event Code: Lcvposx(1)

<= nnn (See note* below)

Description:

Rod 18-03 position//

Initiates ATWS and sets initial rod position 4 Event Code: sl_pmarn I sl_pmbrn

==

Description:==

SLC Pump A or B Start// Triggers Failure of both SLC pumps Event Code:

Description:

Event Code:

Description:

nnn = 604 if rod insertion is NOT being observed, and nnn=700 if Group 1 OB rods will be inserted to 00. ESG-2 Page 3 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training MALFUNCTION SCHEDULE:

I Initial @Time Event Action Description None None Insert malfunction TC01-10 All turbine bypass valves fail closed None None Insert malfunction SL04A SBLC pump A failure of auto start signal None None Insert malfunction SL04B SBLC pump B failure of auto start signal None None Insert malfunction NM12D to 0 on event 1 Flow summer K607D failure None None Insert malfunction TC10-1 to 100 in 180 on EHC fluid leak-Stop Valve 2 event2 None None Insert malfunction RP06 after 1 on event 3 Half-core A TWS -left side None None Insert malfunction CD1 OA after 300 on event 3 CRD hydraulic pump A trip None None Insert malfunction SL01A after 600 on event 4 SBLC injection pump AP208 failure None None Insert malfunction SL01 B after 600 on event 4 SBLC injection pump BP208 failure I REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote EP01 after 360 to BYPASS on EP01 EOP-301, bypass MSIV (-129") event 5 isolation interlock None None Insert remote EP02 after 480 to BYPASS on EP02 EOP-311, bypass PCIG (-129") event 6 isolation interlock None None Insert remote EP38 after 180 to Emergency on EP38 EOP-319, Restoring Instrument event 7 Air in an Emergency None None Insert remote EP09 after 240 to REMOVED on EP09 EOP-320 (step 5.1.2), ARI valve event 8 fuses F6A/F5A None None Insert remote EP10 after 240 to REMOVED on EP10 EOP-320 (step 5.1.4), ARI valve event 8 fuses F6B/F5B None None Insert remote EP11 to INSTALLED on event 9 EP11 EOP-320 (step 5.2.2), RPS division 1 jumper None None Insert remote EP13 after 360 to INSTALLED EP13 EOP-320 (step 5.2.3), RPS on event 8 division 3 jumper None None Insert remote EP12 to INSTALLED on event 8 EP12 EOP-320 (step 5.2.4 ), RPS division 2 jumper I ESG-2 Page 4 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training REMOTE SCHEDULE:

Initial (@Time Event Action Description None None Insert remote EP14 to INSTALLED on event 9 EP14 EOP-320 (step 5.2.5), RPS division 4 jumper None None Insert remote EP35 after 180 to FAIL_CLOSE EP35 EOP-322 HV-F006 HPCI to CS on event 10 OVERRIDE SCHEDULE:

Initial @Time Event Action Description ESG-2 Page 5 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response I Swap EHC Pumps: 1

CRS directs EHC pump swap IAW HC.OP-SO.CH-0001.

RO swaps EHC pumps by: PRESS HYDR FLUID PUMP AP116 MAN button PRESS HYDR FLUID PUMP AP116 START push-button PRESS HYDR FLUID PUMP BP116 STOP button PRESS HYDR FLUID PUMP BP116 AUTO button I Power Reduction:

1

CRS directs power reduction IAW 10-6 and REMA. .____ ___________

_, As RE, PROVIDE the following guidance:

Power reduction guidance is to insert Group 1 OB Control Rods, then reduce reactor power to 85% using Reactor Recirc flow IAW ReMA guidance.

When reactor power is 85%, RE's will assess Core performance for rod pattern adjustment.

Emergency Load reductions will be performed using Standard Power Reduction Instructions.

ESG-2

CRS directs inserting control rods and lowering Reactor Recirc IAW REMA guidance.

RO inserts Group 1 OB Control Rods, and then lowers reactor power to 85% with Reactor Recirc. Page 6 of 30 Comments HPI USED: STARD PEERCHECK0 FLAGGING 0 OP BARRIERS 0 HPI USED: STARD PEERCHECK0 FLAGGING 0 OP BARRIERS 0 INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Flow summer K607D failure:

After the Crew lowers power, OR, at the discretion of the Lead Examiner, TRIGGER ET-1. ESG-2 Expected Plant/Student Response

Crew monitors Reactor power, pressure, and level and ensure plant conditions are stable.

Crew recognizes RPS Y2 scram by: -=> OHA C3-A4/A5 "REACTOR SCRAM TRIP LOGIC 81/82" => RPS Trip Logic 81 and 82 NORMAL/RESET status lights extinguished

=> Pilot Scram Valve Solenoid LOGIC 8 NORMAL status lights for all four groups extinguished.

=> GRIDS D2126 "NEUTRON MONITOR SYSTEM SCRAM X" => GRIDS D2128 "NEUTRON MONITOR SYSTEM SCRAM Z" => GRIDS C022 "ANY APRM UPSCALE"

=> GRIDS C049 "RECIRC FLOW COMPAR OUT LIMITS" Page 7 of 30 Comments INPO Fundamentals:

D Monitoring plant conditions and indications closely.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity If panels are opened, state that indications on 1 OC608 indicate K607D meter is downscale.

Flow Unit D COMPARATOR and Flow Unit C Comparator lights on 1 OC608 should be illuminated.

ESG-2 Expected Plant/Student Response

Crew recognizes K607D failure Downscale by: => 1 /2 Scram on 'B' RPS. => [C5-A1] "NEUTRON MONITORING SYSTEM".

=> [C3-C5] "APRM SYS B UPSCALE TRIP/INOP".

=> B, D, F APRM "UPSC ALARM" and "UPSC TR OR INOP" status lights. => [C6-D1] "APRM/RBM FLOW REF OFF NORMAL".

=> Flow Units C & D "COMPAR" status lights. => GRIDS C049 "RECIRC FLOW COMPAR".

RO refers to HC.OP-AR.ZZ-0020, GRIDS C049: => CHECK flow unit readings AND under the direction of the SM/CRS BYPASS the unit having an off normal reading.

Crew re-enters OP-AB.IC-004

=> Condition F => Crew bypasses the affected Flow Unit. => Crew refers to DD.ZZ-0020 for a failed PPC Sensor. => Crew directs Reactor Engineering to evaluate the flow unit failure on the PPC. Page 8 of 30 Comments INPO Fundamentals D Monitoring plant conditions and indications closely.

D Controlling plant evolutions precisely.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity NOTE: WHEN directed by the crew to place the flow unit mode switch to the "unlabeled"

position, THEN MODIFY NM12D to 100%. If panels are opened, state that indications on 1 OC608 indicate K607D is INOP. ESG-2 Expected Plant/Student Response

=> Crew directs l&C to PLACE the MODE Switch, on the D flow unit, to the "UNLABELED" position between STANDBY and ZERO. => Crew verifies RPS Trip clear. => Crew resets RPS Trip as follows:

=> Turns the affected RPS Trip Logic key to RESET, AND RETURN to the NORMAL position.

=> Verifies that RPS is reset.

PO may check indications on 1 OC608 and reports K607D is now BYPASSED.

Crew contacts Maintenance to troubleshoot K607D failure.

Crew contacts Operations Management.

CRS enters LCO for Tech Spec 3.3.1, 3.3.6, and may enter a Tracking LCO for 3.1.4.3.

Page 9 of 30 Comments INPO Fundamentals D Working effectively as a team. D Having a solid understanding of plant design and system interrelationships.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments EHC System Leak:

Crew recognizes EHC Leak INPO Fundamentals After the Crew references Tech by: D Monitoring plant Specs for the K607D failure,

=> GRIDS D2133 "TB STOP conditions and OR, at the discretion of the Lead VALVE CLOSURE indications closely.

Examiner, TRIGGER ET-2. SCRAMW" => GRIDS D2136 "TB STOP NOTE: EHC loss in approximately VALVE CLOSURE 8 minutes.

SCRAM Y" => GRIDS D2574 "MAIN STOP VALVE 2 CLSD" => OHA D3-E5 "TURB HYDR RESERVOIR TROUBLE"

=> GRIDS D33355 "TURBINE EHC RESERVOIR LEVEL LO" => Lowering EHC pressure displayed on GRIDS

CRS implements INPO Fundamentals:

AB.BOP-0003:

0TEAMWORK

=> Condition B and C => Monitors Leakage => Add EHC oil => Informs Radwaste

=> Determines if leak is isolable

=> Evaluates effect of leak => Determines leak rate NOTE: AP116 Motor Amps will

RO observes and reports that INPO Fundamentals rise to >65 amps in 2 minutes.

AP116 Motor Amps indicate D Monitoring plant >50 amps and rising. conditions and indications closely.

NOTE: Actions may not be

CRS orders EHC Pump swap observed if scram ordered first. IAWC.3 ESG-2 Page 10 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response

RO performs EHC Pump swap. WHEN dispatched to EHC,

Crew dispatches TBEO to THEN REPORT indicated EHC EHC. level indicates greater than 6 inches LOW (bottom of indication).

No indication of where EHC fluid is leaking.

ESG-2

WHEN AP116 amps are >60, THEN CRS enters Condition C and directs:

=> Monitoring Turbine Valve Positions

=> Reducing recirc pump speed to minimum => Locking the Mode Switch in SHUTDOWN

=> Tripping the Main Turbine

CRS determines unable to maintain EHC level, THEN IAW 8.7 directs:

=> Reducing RR Pump Speed to minimum => Lock the MS in SD

WHEN directed, THEN the RO: => Reduces recirc pump speeds to minimum => Locks the Mode Switch in SHUTDOWN Page 11 of 30 Comments IAW the SPRI, Recirc Pumps are considered to be at minimum if below 30% speed. Crew may not lower recirc pump speeds before scramming.

INPO Fundamentals:

D CONSERVATISM HPI USED: STARD PEERCHECK0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity ATWS: The A TWS is automatically inserted during the scram. STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Reports Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status IAW 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 IAW HC.OPAB.ZZ-0001.

ESG-2 Expected Plant/Student Response

Crew recognizes Scram Condition and Reactor Power 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 IAW AB.ZZ-0001 Att. 1. Page 12 of 30 Comments RECORD time of Mode Switch to SHUTDOWN for 15 min ECG Classification.

Time: -----HPI USED: STARD HARD CARD 0 Due to ATWS, CRS may not direct tripping Main Turbine IAW AB. BOP-0002.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

Prioritize the Power Leg to establish SLC injection as soon as possible.

Terminating and Preventing HPCI in a timely manner is critical in order to reduce reactor power by establishing and maintaining a -50" to -100" RPV level band.

Maximize steam loads IAW with the post scram pressure control hard card actions when reactor power exceeds bypass valve capability.

Although Abnormal Operating Procedure HC.OPAB.

BOP-0002 guidance for tripping the turbine should still be followed, the impact of tripping the turbine on RPV pressure control should be evaluated and actions taken ahead of time to minimize the impact of the loss of the turbine (e.g., all other steam demands are maximized, turbine parameters are closely monitored to provide the longest time possible for other reactor shutdown actions to be implemented prior to tripping the turbine).

If reactor power is within the capability of the turbine bypass valves, the turbine should be tripped without any additional delay.

After Terminating and Preventing low pressure ECCS, place RHR in suppression pool cooling in order to mitigate reaching 110 degrees F in the Torus with SRVs cycling.

With limited injection

sources, if RPV level stabilizes below -185", the decision on whether reactor level can be restored above -185" will be based on the time required to insert sufficient negative reactivity to allow reactor level to stabilized above -185".

As control rods are inserted, reduce injection flow to maintain reactor level low in the assigned band to reduce reactor power. ESG-2 Expected Plant/Student Response

CRS implements EOP-101A.

Page 13 of 30 Comments INPO Fundamentals:

0TEAMWORK Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION For ATWS conditions where reactor power remains >4% RTP, the CRS should direct the PO to remain at feedwater to stabilize RPV level. Under these conditions, the Recirc pumps are already tripped and RWCU has already isolated and the PO should be assigned the action to initiate SLC. The RO, following completion of the post scram hard card ATWS mitigation actions (manual scram and ARI initiation),

should be directed to Terminate and Prevent HPCI injection prior to implementing any other EOP-101 A actions such as inhibiting ADS or inserting control rods. The basis for this direction is; 1) to facilitate PO control of RPV level; 2) mitigate the reactor power excursion due to the cold water HPCI injection inside the shroud; and 3) ensure that the main turbine remains available to facilitate RPV pressure control.

ESG-2 Expected Plant/Student Response

PO stabilizes and maintains RPV level as directed by CRS.

CRS directs: Initiating SLC Verifying RWCU Isolates

RO/PO initiate SLC.

Crew starts AP208 and/or BP208 SLC pumps before Suppression Pool temperature reaches 110 degrees.

CRS directs tripping reactor recirc pumps. Page 14 of 30 Comments HPI USED: STARD HARD CARD 0 HPI USED: STARD PEERCHECK0 ENTER Supp Pool temp when A/BP208 SLC pump is started:

Temp: ____ _ Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Note: A SAE is required to be declared IAW ECG Section SS3.1 (An automatic scram failed to shut down the reactor as indicated by reactor power >4% AND Manual scram actions taken at the reactor control console (mode switch, manual scram pushbuttons, manual ARI actuation)

DO NOT shutdown the reactor as indicated by reactor power >4%) ESG-2 Expected Plant/Student Response

RO/PO trip reactor recirc pumps.

CRS directs inhibiting ADS.

RO/PO inhibits ADS IAW AB.ZZ-0001 Att. 13.

CREW prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUATION.

Page 15 of 30 Comments HPI USED: STARD PEERCHECK0 May already be tripped on EOC-RPT.

INPO Fundamentals:

0 KNOWLEDGE HPI USED: STARD HARD CARD D INPO Fundamentals:

0 CONTROL This Critical Task only applies if conditions for automatic ADS initiation are met. See justification for failure criteria.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Pressure Leg Direct initial pressure control as Stabilize pressure 800 psig to 1000 psig. The lower limit of 800 psig will not complicate RPV level maintenance and will prevent an unwanted cooldown.

The upper limit of 1000 psig is a round number below 1047 psig. ESG-2 Expected Plant/Student Response

Crew recognizes bypass valves are not opening to control pressure by: => OHA D3-D5 "EHC UNIT PANEL 10C363" => DEHC "BYPASS VALVE POSITIONING ERROR" alarms => Bypass valve position indication

=> Rising reactor pressure

CRS directs stabilizing pressure below 1037 psig with: => Main Steam Line Drains => SRVs => RPFT

RO/PO control pressure as directed by CRS with: => Main Steam Line Drains IAW AB.ZZ-0001 Att. 15 => SRVs IAW AB.ZZ-0001 Att. 13 => RFPTs Page 16 of 30 Comments Turbine Bypass valves are failed shut. HPI USED: STARD HARD CARD 0 INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Trip of SLC Pump; The AP208 AND BP208 SLC pumps(will trip 1 O minutes after starting).

IF dispatched to investigate trip of AP208 and BP208, THEN REPORT unable to determine cause of the trips. ESG-2 Expected Plant/Student Response

Crew recognizes trip of AP208 SLC pump by: => OHA C1-B1 "SLC PUMP/VALVE O/PF" => OHA C1-F1 "SLC/RRCS INITIATION FAILURE"

=> GRIDS D3022 "SLC INJ PMP AP208 TROUBLE TRBL" => GRIDS D3023 "SLC INJ PMP BP208 TROUBLE TRBL" => Flashing STOP light for AP208 and BP208

Crew dispatches NEO and Maintenance to investigate trip of SLC pumps. Page 17 of 30 Comments Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity REFER to the appropriate EOP and SUPPORT Crew requests for EOPs IAW with the following.

Validated execution time delays are built-in:

EOP-301 : ET-5 EOP-311:

ET-6 EOP-319:

ET-7 EOP-320:

ET-8 EOP-322:

ET-10 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Promptly initiate actions IAW the 300 series EOPs to shut down the reactor.

Timely actions will reduce the potential continued challenges to containment.

In addition, once the post scram hard card actions have been completed and RPV level has stabilized in the required band, an NCO should be assigned the responsibility to insert control rods IAW the post A TWS CRD operation hard card and CRAM move sheets. When control room portions of EOP-320 have been completed and the NCO is ready to insert a manual scram, the NCO should perform a crew update and utilize the post scram hard card to implement the applicable post scram actions following the manual scram attempt.

ESG-2 Expected Plant/Student Response CRS directs performance of the following EOPs: =:. EO.ZZ-0320 "Defeating ARI and RPS Interlocks"

=:. EO.ZZ-0301 "Bypassing MSIV Isolation Interlocks"

=:. EO.ZZ-0311 "Bypassing Primary Containment Instrument Gas Isolation Interlocks"

=:. EO.ZZ-0319 "Restoring Instrument Air in an Emergency"

=:. EO.ZZ-0322 "Core Spray Injection Valve Override"

CRS directs terminating and preventing injection to the RPV with the exception of: =:. SLC =:. CRD =:. RCIC Page 18 of 30 Comments The timing, order, and priority of the EOP performance may vary. Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity ESG-2 Expected Plant/Student Response

RO/PO terminate and prevent injection from HPCI, RHR and feedwater/condensate IAW AB.ZZ-0001:

=> Att. 16 for 1 OC650 => Att. 17 for 1 OC651

CRS directs maintaining RPV water level between -50" and -185".

RO/PO control level as directed by CRS with: => Feedwater IAW AB.ZZ-0001 Att. 14 => RCIC IAW AB.ZZ-0001 Att. 6 => HPCI IAW EOP-322

Crew ensures adequate core cooling by maintaining, or restoring, RPV level above -185" without Emergency Depressurizing.

CRS directs bypassing the RWM and commencing manual rod insertion.

RO/PO establishes drive water d/p IAW AB.ZZ-0001 Att. 18. Page 19 of 30 Comments HPI USED: STARD HARD CARD D INPO Fundamentals:

0 CONTROL Typically, the lower end of the level band is set above -129". HPI USED: STARD HARD CARD 0 INPO Fundamentals:

0CONTROL HPI USED: STARD HARD CARD 0 INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Trip of CRD Pump: The AP207 CRD pump will trip 5 minute after ATWS. IF dispatched to investigate trip of AP207, THEN REPORT the motor is hot to the touch and the breaker (52-437011 )is tripped.

Report that the breaker will not reset (if required).

Turbine Trip: The turbine will trip 8 minutes after the EHC leak if not previously tripped.

ESG-2 Expected Plant/Student Response

RO/PO bypasses RWM and inserts control rods IAW RE.AB.ZZ-0001 Att. 1.

Crew recognizes trip of AP207 CRD pump by: => Flashing STOP light for AP207 => OVLD/PWR FAIL light for AP207

Crew dispatches NEO and Maintenance to investigate trip of AP207 CRD pump.

CRS directs start of CRD Pump BP207.

RO starts CRD pump BP207 IAW Attachment 18 of AB.ZZ-0001, or AR.ZZ-0020 point 02244.

Crew recognizes Turbine Trip by: => OHA A1-D3 "TURBINE GENERATOR TRIP" => OHA C5-A2 "TCV FAST CLOSURE"

=> OHA C5-B2 "MAIN STOP VALVE CLOSURE"

=> TRIPPED indication on TBWD panel => Turbine Stop, Control, and Intermediate valve closed indications on 1 OC651 D Page 20 of 30 Comments HPI USED: STARD Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Strategies For Successful Transient Mitigation Torus Temperature Leg Start all available Torus cooling as soon as possible to remove heat from containment.

ESG-2 Expected Plant/Student Response

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 1 OC650C => RM11 9AX833/834 alarm => Various Suppression Pool temperature indicators

CRS implements EOP-102.

STA/IA monitors EOP-102 implementation.

CRS directs placing RHR in Suppression Pool Cooling.

RO/PO place RHR in Supp Pool Cooling IAW AB.ZZ-0001 Att. 3.

RO/PO aligns SACS to support second RHR Hx IAW SO.EG-0001 Section 5.9. Page 21 of 30 Comments INPO Fundamentals:

DTEAMWORK HPI USED: STARD HARD CARD 0 PEERCHECK0 Depending on resource management, this may not occur until the reactor is shutdown under all conditions without boron. Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity WHEN the Crew has requested EOP-320 re-performed, THEN INSERT TRIGGER-9.

WHEN the Crew has reset RPS, THEN DELETE Malfunctions RP06 to allow full rod insertion on the next scram. ESG-2 Expected Plant/Student Response

!E Suppression Pool temperature is >110 degrees, AND Reactor power is >4%, AND SRVs are open or cycling, THEN Crew terminates and prevents injection to the RPV with the exception of SLC, CRD, and RCIC, UNTIL Reactor power is <4%, OR RPV level reaches -129", OR SRVs remain closed. * !E RPV level reaches -129", THEN Crew terminates and prevents injection from Core Spray.

WHEN EOP-320 Section 5.1 and 5.2 are complete, THEN the Crew implements EOP-320 Section 5.3 and reset RPS.

RO observes and reports improper implementation of EOP-320 by: => OHA C3-A2-A5 fail to clear => RPS A and B Fail to reset

CRS directs maintenance to re-implement of EOP-320.

WHEN EOP-320 Section 5.1 and 5.2 are complete, THEN the Crew implements EOP-320 Section 5.3 and reset RPS. Page 22 of 30 Comments HPI USEl STARD PEERCHECK0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity At the Lead Examiners discretion, MODIFY Variable lclsdv to accelerate draining of the SDV. Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when:

RPV Level is being maintained above-185" AND

All rods are fully inserted, OR manual rod insertion is in progress.

ESG-2 Expected Plant/Student Response

WHEN OHA C6-E4 clears, THEN the Crew initiates a manual scram IAW EOP-320 Section 5.3.

CREW fully inserts all control rods via RMCS and/or manual scram(s)

JAW HC.OP-EO.ZZ-0320.

Crew recognizes the reactor is shut down by: SPDS ALL RODS IN RWM Confirm Shutdown GRIDS Rod positions

CRS exits EOP-101A, enters EOP-101.

Page 23 of 30 Comments HPI USED: STARD PEER CHECK0 INPO Fundamentals:

0 MONITORING Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requalification Training Exam Development Job Aid B. NU REG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Hope Creek Event Classification Guide (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-101-111-1004 Operations Standards M. OP-AA-106-101-1001 Event Response Guidelines N. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program 0. OP-HC-108-106-1001 Equipment Operational Control P. HC.OP-SO.BF-0001 CRD Hydraulic System Operation Q. HC.OP-SO.CH-0001 Main Turbine Control Oil (EHC) System Operation R. HC.OP-SO.SF-0001 Reactor Manual Control S. HC.OP-AB.ZZ-0001 Transient Plant Conditions T. HC.RE-IO.ZZ-0006 Power Changes During Operation U. HC.RE-AB.ZZ-0001 Insertion of Control Rods in Response to an ATWS V. HC.OP-AB.BOP-0002 Main Turbine W. HC.OP-AB.BOP-0003 Turbine Hydraulic Pressure X. HC.OP-AB.ZZ-000 Reactor Scram Y. HC.OP-EO.ZZ-0101 RPV Control Z. AA. BB. CC. DD. EE. FF. HC.OP-EO.ZZ-0101A ATWS-RPV Control HC.OP-EO.ZZ-0102 Primary Containment Control HC.OP-EO.ZZ-0301 Bypassing MSIV Isolation Interlocks HC.OP-EO.ZZ-0311 Bypassing Primary Containment Instrument Gas Isolation Interlocks HC.OP-EO.ZZ-0319 Restoring Instrument Air in an Emergency HC.OP-EO.ZZ-0320 Defeating ARI and RPS Interlocks HC.OP-EO.ZZ-0322 Core Spray Injection Valve Override ESG-2 Page 24 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VII. ESG CRITICAL TASK RATIONAL ESG-2 / 1 1.

Crew starts AP208 and/or BP208 SLC pump before Suppression Pool temperature reaches 110 degrees.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA 1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA 1.04 SBLC RO 4.5 SRO 4.5 EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA2.04 Suppression Pool Temperature RO 4.0 SRO 4.1 2. The Boron Initiation Injection Temperature above about 9% power is 110°F. The post scram power level in this scenario is greater than 9%. 110°F is also one of the conditions that may require intentional lowering of RPV water level to as low as -129" to control power. Lowering RPV water level to -129" jeopardizes main condenser and RFPT availability, which could significantly complicate mitigation of the ATWS. Initiating SLC before 110°F will help reduce power and may prevent the need to lower level to below -129".

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 KIA 295031 Reactor Low Water Level EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA.06 Automatic depressurization RO 4.4 SRO 4.4 ESG-2 Given the current A TWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor.

EOPs direct this action under the current conditions.

This critical task is only applicable if RPV water level goes below -129". Failure to satisfactorily complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure to less than 700 psig. Page 25 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training

3.

Crew ensures adequate core cooling by maintaining, or restoring, RPV level above -18511 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 4. Lowering level RPV level during an ATWS with reactor power >4% is a key strategy for controlling reactor power. Maintaining adequate Core cooling under ATWS conditions is accomplished by maintaining/restoring level above -185". HPCI and RCIC are capable of maintaining level under the current conditions.

An Emergency Depressurization is not warranted and would result in a large injection of cold water and the potential displacement of boron from the core.

CREW fully inserts all control rods via RMCS and/or manual scram(s)

/AW HC. OP-EO.ZZ-0320.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA 1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA 1.01 Reactor Protection System RO 4.6 SRO 4.6 EA1 .07 RMCS RO 3.9 SRO 4.0 ESG-2 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.

Page 26 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training ESG-2/1 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT Loss Of Offsite Power/SBO Internal Flooding

---LOCA ---------------y TRANSIENTS:

Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Manual Scram LOSS OF SUPPORT SYSTEMS:

Loss of SSW Loss of SACS COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY SYSTEMS HPCI SRVs ---RCIC Condensate/Feedwater

---B/D EOG SSW ---NB RHR Pump RPS ___ NB SACS Loop 1E 4.16KV Bus ---1E480 VAC Bus ---120VAC 481 Inverter

---1E 125VDC ---Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION ---Manual Depressurization of the RPV w/ no HP Injection Available

---Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi DW Press. Signal y Control RPV Water Level w/ HP Injection during ATWS Sequence

---Align Portable Power Supply to Battery Chargers

---Venting of Primary Containment

---Restore Switchgear Cooling Restart Condensate

Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG ESG-2 Page 27 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VIII. TURNOVER SHEET:

PROTECTED EQUIPMENT None EOOS is out of service REACTIVITY I Plant Status Currently at 95% power. Power reduction for rod pattern adjustment is in progress.

Power is to be reduced to 85% in accordance with HC.OP-IO.ZZ-0006 and the REMA. Currently at Step 5.2.9 of 10-6. Swap EHC pumps, Insert Group 108 rods, and reduce power to 85% with TCF. ESF/SAFETY SYSTEMS None COOLING WATER None BOP Swap EHC pumps to support routine maintenance on BP116. ELECTRICAL None ADVERSE CONDITION MONITORING None Page 28 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG-2 SELF-CHECK

1. Total malfunctions inserted:

5-8 --2. Malfunctions that occur after EOP entry: 1-4 --3. Abnormal Events: 2-3 --4. Major Transients:

1-2 --5. EOPs used beyond primary scram response EOP: 1-3 --6. EOP Contingency Procedures used: 0-3 --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 --10. Technical Specifications are exercised during the test: >1 --Comments:

ESG-2 Page 29 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

(continued)

Crew Validation Rev.: 0 Date Validated:

11-5-2014 11 Validated with operators (1 SRO, 2 ROs). Validation Comments Disposition

1. Incorporated changes and comments from 1. Comments incorporated.

validation on 10/13/2014

2. Revise times for malfunction insertions.

2. Changes made. Add cue for local observation of Flow Unit. Revise Trigger numbers.

Insert expected power change in %. Crew Validation Rev.: 1 Date Validated:

1/20/2015 Validated with operators.

Validation Comments Disposition

1. Add Editorial Comments/Enhancements

1. Corrected typographical errors to Initial made during NRC validation.

Conditions.

2. Corrected typographical errors in actions and cues for Event 3. Provided more information for panel indications and cues Revised Technical Specification II entered/tracked.

ESG-2 Page 30 of 30 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM:

REVISION SUMMARY:

SIMULATOR EXAMINATION SCENARIO GUIDE 2015 NRG EXAM SCENARIO ESG-3 Effective When Approved 75 Minutes 1 COPY OF ----0 LICENSED OPERATOR REQUALIFICATION INITIAL LICENSE D OTHER:

Incorporated editorial comments from NRG validation.

PREPARED BY: S. DENNIS/SIGNATURE ON FILE 12-9-2014 INSTRUCTOR DATE APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE 12-9-2014 LORT GROUP LEAD OR DESIGNEE DATE APPROVED BY: L. KOBERLEIN/SIGNATURE ON FILE 12-11-2014 SHIFT OPERATIONS SUPERVISOR OR DESIGNEE DATE PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training I. OBJECTIVE($):

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"*".) II. MAJOR EVENTS: A. FWH Leak B. Inadvertent SBLC System Actuation C. Loss of 100410 D. Loss of Offsite Power E. Auto Start Failure of EDGs F. RCIC Trip on Overspeed G. SACS Pump Trip II. SCENARIO SUMMARY:

Plant is operating at 100% power. A leak in a Feedwater Heater (FWH) will require action to reduce power and isolate the FWH. After actions are complete for the FWH loss, an inadvertent SBLC System Actuation will occur and requires operator action to shut down the running SBLC pump. Based on whether SBLC was injected into the vessel, actions may be required to commence reducing power to less than 24% within six hours. After the stopping of the SBLC pump, a loss of 125 VDC Class 1 E Bus 100410 will occur. Additional Technical Specifications are required to be entered.

A loss of Offsite power and Emergency Diesel Generator (EOG) failures will require manual starting of the EDGs to restore power to the vital AC busses. Reactor Core Isolation Cooling (RCIC) will trip on overspeed upon initiation.

RCIC will not be available due to an overspeed on any subsequent operation.

During operation of the EDGs a SACS pump will trip, requiring starting a failed to auto-start SACS pump, or cross connecting of SACS to support continued EOG operation to prevent damaging the EOG. The scenario may be terminated after the reactor has been depressurized, and adequate core cooling has been restored.

ESG-3 Page 2 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. INITIAL CONDITIONS:

l.C. Initial INITIALIZE the simulator to 100% power. ---ENSURE CRD F002A is in service.

ENSURE TACS is being supplied by SACS Loop B ---ENSURE associated Schedule file is open and running IF required.

ENSURE associated Events file is open IF required.

---PREP FOR TRAINING (i.e., RM-11 set points, procedures, bezel covers) Initial I PREPARE a Fire Alarm for LOP ---At a minimum review the Scenario Reference section and CLEAN the balded EOPs, ABs and SOPs listed. (80091396 0270) ------*-COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE: Initial Event 6 Event Code: et_array(4)

& zlcwzpds

==

Description:==

LOP Inserted AND SACS Pump D Running 7 Event Code: rrlnr <= -129

Description:

RPV Water Level < Level 1-lnitiate CRD Filter Clogging ESG-3 Page 3 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training MALFUNCTION SCHEDULE:

I Initial @Time Event Action Description None None Insert malfunction DGO?B Diesel Generator B emergency start signal failure None None Insert malfunction DG03B LOCA sequencer chan B failure None None Insert malfunction DG04B LOP sequencer chan B failure None None Insert malfunction AD01 Failure of ADS valves to open None None Insert malfunction RC01 RCIC turbine overspeed None None Insert malfunction FW12B to 80.00000 in High pressure heater BE106 tube leak 240 on event 1 None None Insert malfunction SL03A on event 2 Inadvertent SBLC system A initiation delete in 3 None None Insert malfunction ED11 A on event 3 LOSS OF 125 voe CLASS 1 E BUS 100410 None None Insert malfunction EG12 on event 4 Loss of all off site power None None Insert malfunction 0015 after 10 to SACS pump DP210 trip SEIZE on event 6 None None Insert malfunction CD09A to 0 on event Drive water flow control valve F002A 7 failure None None Insert malfunction CD08A on event 7 CRD suction filter AF201 clogging None None Insert malfunction CD08B on event 7 CRD suction filter BF201 clogging None None Insert malfunction AN-A2A5 after 10 on CRYWOLF ANN A2A5-FIRE PROT event4 PANEL 10C671 ESG-3 Page 4 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description ESG-3 Page 5 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity 68 FWH Tube Rupture:

After the Crew assumes the shift, OR, at the discretion of the Lead Examiner, TRIGGER ET-1 (68 FWH Tube Rupture).

Insight Items:

FW Line Temp A c91a1744

FW Line Temp 8 c91a1746 ESG-3 Expected Plant/Student Response

Crew recognizes trip of 68 FWH and loss of Feedwater heating by: => OHA A 7-E2 "FEEDWATER HEATER TRIP" => 68 FWH Flashing HTR TRIP light => CRIDS 02997 "Feedwater Heater 8E106 => 68 FWH Extraction Steam valve HV-13658 closing => Lowering feed water line temperatures

Crew announces trip of the 68 FWH on the plant page.

Crew recognizes leak in 68 FWH by: => RFPTs speed increasing

=> RFP discharge flows rising with lowering feed flow to reactor vessel => Total Condensate flow rising => 3/4/58 FWH drain flow rising => 68 FWH level rising

RO reduces and maintains reactor power to Pre-Feedwater Heater Trip or Isolation Value IAW the SPRI. Page 6 of 29 Comments The 68 FWH dump valve will not open until after the Feedwater heater trip setpoint is reached.

INPO Fundamentals:

0 MONITORING The tube leak will a small vessel level transient

(:==:2 inches).

HPI USED: STARD PEERCHECK0 FLAGGING 0 Immediate Operator Action IAW A8.80P-0001.

INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity IF dispatched to 8C102, THEN REPORT:

68 FWH level is high on all indicators

There is a 100% air signal on the drain valve

There is a 0% air signal on the dump valve Power should be lowered to 5% below the pre-trip value within 5 minutes.(8ased on Note 4.) ESG-3 Expected Plant/Student Response

Crew restores/maintains the Core Thermal Power 5 Minute Average to <3848 MWth.

Crew dispatched T8EO to 8C102 panel.

CRS implements A8.80P-0001: Condition A Condition 8

Crew ensures automatic actions occur: HV-13658 extraction steam isolation closes HV-13668/13678/13598 drains open

PO performs the following to isolate the heater per Condition 8: Closes HV-17538 Closes HV-17688 Ensures extraction steam isolated to 68 FWH IAW SO.AF-0001 Section 5.6

CRS directs RO to reduce reactor power to IAW A8.80P-0001 Retainment Override and the SPRI. Page 7 of 29 Comments HPI USED: STARD PEERCHECK0 INPO Fundamentals:

D CONTROL 0 MONITORING Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity ESG-3 Expected Plant/Student Response

IF directed, THEN RO reduces reactor power.

CRS implements AB.RPV-0001:

=> Condition B, and directs power reduction to less than 1050 MWE per Table 1.

Crew contacts RE to inform about the heater trip and request Crossflow be taken to "Not Applied".

IF reactor power was reduced by THEN CRS/STA/IA recognize the following actions apply: => TIS Table 4.4.5-1 Item 4(b) => ODCM Table 4.11.2.1.2-1 Items (c) & (f)

Crew contacts ESOC and Trading Floor.

Crew contacts Operations Management to initiate Prompt Investigation and ERT callout.

Page 8 of 29 Comments HPI USED: STARD PEERCHECK0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Inadvertent SLC Initiation:

After actions for the loss of FW Heating are complete, or at the discretion of the Lead Examiner, TRIGGER ET-2. If requested to open breaker, INSERT Remote ET72 to TAGGED and report that the breaker is open. ESG-3 Expected Plant/Student Response

Crew recognizes Inadvertent SLC Initiation by: => OHA C1-C1 SLC SQUIB VLV LOSS OF CONTINUITY

=> OHA B3-B5 CORE SPRAY LINE BREAK => OHA C1-C2 RWCU SYSTEM TROUBLE => GRIDS D3020 SLC SQUIB XV-F004A CONTINUITY in alarm => SBLC Pump AP208 indicates running

CRS implements AB.RPV-0001: => Condition G

Crew verifies Reactor Level >-38" and Reactor Pressure remained

<1071 psig.

RO stops the running A SLC Pump by depressing Standby Liquid Control, Injection Pump A, STOP push button.

Crew verifies RWCU isolated.

Crew directs opening SLC Pump A breaker 52-212063.

Page 9 of 29 Comments INPO Fundamentals:

0 MONITORING INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity SLC Tank level can be observed on CRI DS Page A097 point A7052. (Per Note 3, <15 gallon change indicates no injection reached the vessel.)

Loss of 10D410: After the SBLC pump is secured, OR at the discretion of the Lead Examiner, TRIGGER ET-3 (Loss of 100410 bus). ESG-3 Expected Plant/Student Response

CRS determines SLC operability based on SLC Pump AP208 breaker open and Storage Tank level using HC.OP-DL.ZZ-0026, and declares inoperable SLC Pump AP208.

Crew determines if SLC solution entered the Reactor.

CRS/ST A/IA recognize the following Tech Specs actions apply: => SBLC -Operating 3.1.5, Action A.1

If SLC entered the Reactor, the CRS initiates action within 15 minutes to reduce power to less than 24% within six hours.

CRS may refer to AB.CONT-0002 for actions to restore RWCU, Attachment

3.

Crew monitors Reactor power, pressure, and level and ensures plant conditions are stable. Page 10 of 29 Comments Need to restore the subsystem in 7 days, or be in Hot S/D in next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . INPO Fundamentals:

0 KNOWLEDGE INPO Fundamentals:

0 MONITORING Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity

!E dispatched to investigate loss of 100410, THEN REPORT:

Bus indicates 0 volts

Both battery charger output breakers are tripped

There is an acrid odor and indication of flash damage at the battery transfer switch

There is no indication of fire ESG-3 Expected Plant/Student Response

Crew recognizes loss of 100410 by: => Flashing INOP lights on all 1 OA401 bus breakers

=> 'A' Channel ECCS "LOGIC PWR FAILURE" lights => Flashing "OVLO/PWR FAIL" lights on HPCI valves w/loss of position indication

=> Charger and bus voltage indication on 1 OC6500 => OHA 03-F2 "125VOC SYSTEM TROUBLE"

=> CRIOS Page 166

CRS implements AB.ZZ-0150.

Comments

Crew dispatches ABEO and E-0009-1 Sheet 2 Maintenance to investigate loss of 100410 bus.

Crew contacts Operations Management to initiate ERT callout.

Page 11 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Loss of Offsite Power: 15 minutes after the loss of 10D410 bus, OR at the discretion of the Lead Examiner, TRIGGER ET-4 (Loss of Offsite Power). WHEN Fire Protection OHA A2-A5 is received, THEN ADVANCE Fire Computer PowerPoint.

WHEN the crew has identified the fire alarms, THEN ADVANCE Fire Computer PowerPoint, AND REMOVE Malfunction AN-A2A5 .. ESG-3 Expected Plant/Student Response

CRS/STA/IA recognize the following Tech Specs actions apply: => D.C. Sources -Operating 3.8.2.1 Action a => Distribution

-Operating 3.8.3.1 Action b

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. Page 12 of 29 Comments Need to restore the 1AD411 battery, 1OD410 bus, and one charger in two hours, or be in Hot S/D in next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . INPO Fundamentals:

0 KNOWLEDGE Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response STRATEGIES FOR SUCESSFUL

TRANSIENT MITIGATION RO performs scram actions IAW AB.ZZ-0001 Att. 1. Reactor Scram Reports Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status IAW 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 IAW HC.OPAB.ZZ-0001.

ESG-3

Crew recognizes RPV Level Below 12.5" EOP entry condition by: => OHA C5-A4 "RPV WATER LEVEL LO" => OHA A 7-D5 "RPV LEVEL 3" => Various water level indicators

Crew recognizes Reactor Pressure Above 1037# EOP entry condition by: => OHA C1-E5 "SRV LO-LO SET ARMED" => Various RPV pressure indicators Page 13 of 29 Comments HPI USED: STARD HARD CARDO RECORD time LOP occurred for 15 minute ECG Classification.

Time: ----Due to the loss of both RPS buses, the C5-A5 OHA will not be useful in diagnosing peak pressure during the transient.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION EOP 101 RPV Control.

Level Leg Direct an initial band of +12.5" to +54" Rx level. This gives a manageable band with level control still in the indicating range. If controlling Reactor Pressure with SRVs and the MSIVs are closed, then the RPV level band assigned should be -30" to +30" 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 cannot 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-3 Expected Plant/Student Response

CRS implements EOP-101 .

Crew recognizes failure of the 'B' EOG to start and load by: Engine STOP light Output breaker TRIP light OVLO/PWR lights on 'B' Channel components

RO/PO starts the 'B' EOG and ensures it loads auto start. Page 14 of 29 Comments INPO Fundamentals:

0 TEAMWORK INPO Fundamentals:

MONITORING D HPI USED: STARD Immediate Operator Action IAW AB.ZZ-0135 Rev. 1

'lo PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity IF directed to locally start the 'B' EOG, THEN REMOVE Malfunction DG07B. LOP and LOCA Sequencer Failure:

Pre-inserted Note: AUE is required IAW ECG Section:

SU1 .1 Loss of all Offsite AC power to all 4.16 KV Vital Buses AND minutes have elapsed ESG-3 Expected Plant/Student Response

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.

Crew recognizes failure of ChannelBloadsto automatically start.

CRS directs the start of Channel B loads.

RO/PO manually start the following Channel B loads: => SSW Pump B => SACS Pump B

CREW starts "B" SACS Pump to provide cooling to "B" EDG, OR cross-connects to SACS Loop A, to prevent a "B" EDG emergency trip from cooling related problems.

PO maintains level and pressure as directed by CRS. Page 15 of 29 Comments HPI USED: STARD HARD CARD 0 INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

WHEN RPV water level drops Due to the LOP and below LVL 2, loss of power to both THEN Crew recognizes RPV RPS buses, the RPV LVL 2 by: L VL 2 and NSSSS ISLN =:> OHA 01-A 1 "RRCS SIG-RPV LEVEL LO POTENTIAL ATWS" are no longer valid =:> OHA C1-D3 "REACTOR indicators of LVL 2. RECIRC PUMPS TRIP" =:> E3-E3 "USS FEEDER BRKR TRBL" =:> RPV L VL 2 Load Sheds =:> Various RPV level indications WHEN RCIC initiates,

WHEN RCIC initiates, May be initiated it will overspeed.

THEN the Crew recognizes a manually before L VL 2 if the RCIC trip by: Crew scrammed

!E dispatched to RCICI Room, =:> OHA B1-A1 "RCIC promptly on loss of THEN REPORT the trip of RCIC TURBINE TRIP" Feedwater.

appears to be an overspeed trip. =:> CRI OS 02400 in alarm =:> RCIC TURB TRIP INPO Fundamentals:

SOLENOID ENRGZ light 0 MONITORING illuminated DO NOT reset RCIC until

RO/PO may direct an decision to Emergency equipment operator to reset the Depressurize has been made. overspeed trip of RCIC by: =:> Pressing the CLOSE push !E dispatched to RCICI Room to button for Turbine Trip reset RCIC, INSERT Remote Throttle Valve HV-4282 RC02 to RESET, =:> Requesting the equipment THEN REPORT the RCIC operator to reset the overspeed trip is reset. overspeed device =:> Reopen HV-4282 and attempt to inject with RCIC

RO/PO recognizes RCIC trips again on start.

CRS directs manual pressure control to maintain RPV pressure below 1037 psig. ESG-3 Page 16 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity As ESOC, REPORT it will take at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to restore Offsite power to Artificial Island. ESG-3 Expected Plant/Student Response

RO/PO cycle SRVs to maintain pressure as directed by the CRS IAW AB.ZZ-0001 Att. 13.

Crew contacts ESOC for estimated time to restoration of Offsite power.

CRS implements AB.ZZ-0135.

IF 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 1 OC650C =? RM 11 9AX833 alarm =? Various Suppression Pool temperature indicators

WHEN Suppression Pool temperature reaches 95 degrees, THEN the CRS implements EOP-102.

WHEN directed by the CRS, THEN RO/PO place 'B' RHR in Suppression Pool Clg IAW AB.ZZ-0001 Att. 3. Page 17 of 29 Comments HPI USED: STARD HARD CARD 0 FLAGGING 0 INPO Fundamentals:

D CONTROL Due to RPV water level concerns, may not immediately place 'A' RHR in Supp Pool Clg. HPI USED: STARD HARD CARD 0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity ESG-3 Expected Plant/Student Response

IF Drywell temperature reaches 135 degrees, THEN Crew recognizes Drywell Temp Above 135°F EOP entry condition by: => Flashing 135 alarm on GRIDS => Various Drywell temperature indicators

WHEN Drywell temperature reaches 135 degrees, THEN the CRS implements EOP-102.

CRS may direct actions to implement EOP-309 and 310. Page 18 of 29 Comments Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments

!E directed to align for two CRD

CRS directs injection with two The HV-F003 Pressure pump injection, CRD pumps. Control Valve has no THEN PERFORM the following:

RO/PO align CRD for power. REFER to SO.BF-0001 Sect 5.4. Emergency Two CRD pump HPI USED: After 1st pump is running, injection IAW SO.BF-0001 Sect STARD TRIGGER ET-7 (Suction filter).

5.4. PEERCHECK0 SET Remote Function for Stby

CRS directs injection with the CRD pump discharge valve to 0% 'B' SLC pump. At-129",

the CRD (CD01/CD02).

RO/PO start the 'B' SLC pump . Suction filters will clog REPORT Stby CRD pump ready and shortly thereafter for start. the CRD pumps will trip WHEN Stby CRD is running, on Low Suction THEN RAMP discharge valve to pressure.

100% open (CD01/CD02).

WHEN directed to locally open the HV-F003, THEN SET Monitor Item lcvp003 = 1.0 AFTER HV-F003 is open, THEN TRIGGER ET-8. WHEN two minutes have elapsed, THEN MODIFY Malfunctions CD09A/B to control injection.

Do NOT open valves >75%. Do NOT restore 1OD410 bus.

Crew pursues restoration of 10D410 bus.

Crew recognizes loss of Inverters are lost during AD481/482 inverters by: LOP due to loss of => Loss of 'A' Channel PAMS 10D410. indications

=> Loss of power to 'A' INPO Fundamentals:

Channel electrical 0 MONITORING indications on 1 OC650D

As time and resources permit, CRS implements AB.ZZ-0136.

ESG-3 Page 19 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Emergency Depressurization Level Response And Control The Control Room Supervisor should ensure that all ECCS is lined up for injection as required prior to initiating an emergency depressurization.

Only ECCS required to support RPV reflood needs to be lined up for injection.

ESG-3 Expected Plant/Student Response

Crew recognizes loss of Fuel Pool Cooling by: =;> OHA D1-D5 "FUEL POOL COOLING SYS TROUBLE"

=;> Loss of valve position indication on demin isolation valves HV-46768/4678

=;> Pump discharge pressure and flow on GRIDS Page 116

CRS directs placing the 'B' FPC pump l/S bypassing the filter demins IAW SO.EC-0001.

As time and resources permit, CRS implements AB.ZZ-0171.

Crew ensures available EOP-101 Table 1 systems are running and aligned for injection.

Crew recognizes RPV L VL 1 by: =;> A7-F5 "RPV LEVEL 1" =;> C1-F3 "ADS DRYWELL PRESS BYP TIMER INIT" =;> A/CID ECCS initiations

=;> Various RPV level indicators Page 20 of 29 Comments Crew may enter AB.COOL-0004, but no conditions apply. Due to the continuing loss of RPV water level, this action may not be complete by the end of the scenario.

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Emergency Depressurization due to Low RPV Level: Note: WHEN Emergency Depressurization is required, THEN an Alert is required IAW ECG Section:

RB4.L Emergency RPV Depressurization is required (5 pts) [If the scenario does not run for a full 15 minutes after ADS is required, the Alert Classification may not be declared]

ESG-3 Expected Plant/Student Response

WHEN RPV level reaches LVL 1, THEN CRS directs inhibiting ADS.

RO/PO inhibits ADS IAW AB.ZZ-0001 Att. 13.

RO/PO ensures available ECCS pumps start.

WHEN RPV water level is below-129",

but before-185",

THEN the CRS implements EOP-202 to Emergency Depressurize.

RO/PO opens five ADS valves IAW AB.ZZ-0001 Att. 13. Page 21 of 29 Comments HPI USED: STARD HARD CARDO 'B' Channel ADS logic has no power. INPO Fundamentals:

DTEAMWORK HPI USED: STARD HARD CARD 0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner after the reactor has been depressurized, and adequate core cooling has been restored.

ESG-3 Expected Plant/Student Response

BEFORE Compensated RPV water level lowers below -185": Crew enters EOP-202 and initiates actions to Emergency Depressurize the reactor.

Then restores RPV water level to above -185".

RO/PO injects with low pressure ECCS IAW AB.ZZ-0001 Att. 4 and/or 5 to restore level as directed by the CRS. Page 22 of 29 Comments RECORD RPV water level at which five SRVs are opened. RPV Level: ---HPI USED: STARD HARD CARD 0 Crew may implement EOP-206, due to only one channel of Fuel Zone level indication, or if indicated level goes below fuel zone. INPO Fundamentals:

D CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VI. SCENARIO

REFERENCES:

A. B. C. D. E. F. G. H. I. J. K. L. M. N. 0. P. Q. R. TQ-AA-106-0304 Licensed Operator Requalification Training Exam Development Job Aid NU REG 1021 Examiner Standards S. T. u. JTA Listing Probabilistic Risk Assessment Technical Specifications Hope Creek Event Classification Guide (ECG) Alarm Response Procedures (Various)

HU-AA-101 Performance Tools and Verification Practices HU-AA-104-101 Procedure Use and Adherence HU-AA-1081 Fundamentals Toolkit HU-AA-1211 Briefing OP-AA-101-111-1004 Operations Standards OP-AA-106-101-1001 Event Response Guidelines OP-HC-108-115-1001 Operability Assessment and Equipment Control Program OP-HC-108-106-1001 Equipment Operational Control HC.OP-AB.ZZ-0001 Transient Plant Conditions HC.OP-AB.CONT-0002 Primary Containment HC.OP-AB.COOL-0002 Safety/Turbine Auxiliaries Cooling System HC.OP-AB.ZZ-0135 Station Blackout/Loss of Offsite Power/Diesel Generator Malfunction HC.OP-AB.ZZ-0136 Loss of 120 VAC Inverter HC.OP-AB.ZZ-0150 125 VDC Malfunction V. HC.OP-AB.ZZ-0170 Loss of 4.16 KV Bus 10A401 A Channel W. HC.OP-AB.ZZ-000 Reactor Scram X. HC.OP-EO.ZZ-0101 RPV Control Y. HC.OP-EO.ZZ-0102 Primary Containment Control Z. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization AA. HC.OP-SO.BF-0001 CRD Hydraulic System Operation BB. Strategies For Successful Transient Mitigation ESG-3 Page 23 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VII. ESG CRITICAL TASK RATIONAL ESG-3 / 1 1.

Crew restores/maintains the Core Thermal Power 5 Minute Average to MWth. KIA 295001 Reactor Feedwater System A2 Ability to (a) predict the impacts of the following on the Reactor Feedwater System; and (b) based on those predictions, use procedures to correct,

control, or mitigate the consequences of those abnormal conditions of operations:

A2.04 Loss of Extraction Steam RO 3.3 SRO 3.4 KIA 2.2 Equipment Control 2.2.22 Knowledge of limiting conditions for operations and safety limits R0.3.4 SRO 4.1 2. The loss of Feedwater heating due to the trip of the 48 FWH will drive reactor power to above the licensed limit. Peak power in this transient with no operator action is just over 102% power. This would constitute a violation of our Operating License.

HC.OP-IO.ZZ-0006 defines a 5 minute average of 3848 MWth as exceeding the Licensed Power Limit. Taking the Immediate Operator Actions IAW either AB.BOP-0001 or AB.RPV-0001 will prevent this violation.

Crew starts the 'B' EOG by EITHER: Pressing the 'B' EOG START pushbutton in the Control Room, OR Directing an operator to locally start the 'B' EOG. KIA 295003 Partial or Complete Loss of A.C. Power AA 1 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 ESG-3 Due to the loss of 100410, the 'A' EOG 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.

Initiation of RHR for decay heat removal is one of the operator actions important to preventing core damage in our PRA. Page 24 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VII. ESG CRITICAL TASK RATIONAL

-Continued

3.

CREW starts "B" SACS Pump to provide cooling to "B" EOG, OR cross-connects to SACS Loop A, to prevent a "B" EOG emergency trip from cooling related problems.

KIA 295003 AA 1 .03 Systems necessary to assure safe plant shutdown RO 4.4 SRO 4.4 4. The continued availability of the "B" diesel generator is required to maintain the capability to place the plant in a cold shutdown condition.

If the "B" diesel becomes inoperable (with the "A" diesel currently inoperable),

both loops of shutdown cooling will be inoperable and will prevent placing and maintaining the plant in a cold shutdown condition.

BEFORE Compensated RPVwater level lowers below-185":

Crew enters EOP-202 and initiates actions to Emergency Depressurize the reactor.

Then restores RPV water level to above -185". KIA 295031 Reactor Low Water Level EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA 1.01 Low Pressure Coolant Injection RO: 4.4 SRO 4.4 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 ESG-3 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 restores level with low pressure ECCS. Page 25 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training Y/N y y y y ESG-3 / 1 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT Y Loss Of Offsite Power/SBO LOCA TRANSIENTS:

Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Manual Scram EVENT Internal Flooding LOSS OF SUPPORT SYSTEMS:

Loss of SSW Loss of SACS COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY SYSTEMS HPCI SRVs ---RCIC Condensate/Feedwater

---B/D EOG y SSW A/B RHR Pump RPS A/B SACS Loop 1E4.16KVBus 1E480 VAC Bus 120VAC 481 Inverter 1E 125VDC Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Y Manual Depressurization of the RPV w/ no HP Injection Available

___ Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi OW Press. Signal Control RPV Water Level w/ HP Injection during ATWS Sequence

---___ Align Portable Power Supply to Battery Chargers

---Venting of Primary Containment

___ Restore Switchgear Cooling Restart Condensate

---___ Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG ESG-3 Page 26 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VIII. TURNOVER SHEET:

PROTECTED EQUIPMENT None EOOS is out of service REACTIVITY I Plant Status None ESF/SAFETY SYSTEMS None COOLING WATER None BOP None ELECTRICAL None ADVERSE CONDITION MONITORING None Page 27 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG-3 SELF-CHECK

1. Total malfunctions inserted:

5-8 ----2. Malfunctions that occur after EOP entry: 1-4 3. Abnormal Events: 2-3 --4. Major Transients:

1-2 ----5. EOPs used beyond primary scram response EOP: 1-3 6. EOP Contingency Procedures used: 0-3 ----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 ----10. Technical Specifications are exercised during the test: >1 Comments:

ESG-3 Page 28 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

(continued)

Crew Validation Rev.: 0 Date Validated:

11/5/2014 Validated with operators (1 SRO, 2 ROs). Validation Comments Disposition

1. Incorporated changes and comments from 1. Changes made. validation on 10/30/2014

2. Revise Critical Task #4. Add TAGS supply 2. Changes made. to IC. Revise Tech Spec references.

Incorporate minor scenario comments.

Crew Validation Rev.: 1 Date Validated:

1/20/2015 Validated with operators.

Validation Comments Disposition

1. Revised based on NRC validation

1. Added information regarding magnitude of comments.

power reductions during Event 1 Subsequent Actions.

2. Added information regarding instrumentation and information to support actions required during Event 2. 3. Corrected typographical errors. 4. Added comments regarding time to restore equipment to support scenario objectives.

ESG-3 Page 29 of 29 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:

REVISION NUMBER: PROGRAM:

REVISION SUMMARY:

SIMULATOR EXAMINATION SCENARIO GUIDE 2015 NRC EXAM SCENARIO ESG-4 Effective When Approved 75 Minutes 1 COPY __ OF __ 0 LICENSED OPERATOR REQUALIFICATION INITIAL LICENSE D OTHER:

Incorporated editorial comments from NRC validation.

PREPARED BY: S. DENNIS/SIGNATURE ON FILE 12-9-2014 INSTRUCTOR DATE APPROVED BY: M.A. SHAFFER/SIGNATURE ON FILE 12-9-2014 LORT GROUP LEAD OR DESIGNEE DATE APPROVED BY: L. KOBERLEIN/SIGNATURE ON FILE 12-11-2014 SHIFT OPERATIONS SUPERVISOR OR DESIGNEE DATE PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training I. OBJECTIVE(S):

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"*".) II. MAJOR EVENTS: A. Containment 02 Weekly Surveillance Test B. SRV Open/Closes C. Earthquake-Trip of Service Air Compressor D. RWCU Pump Leak-Failure to Automatically Isolate E. Air Leak w/Multiple Rod Drift F. LOP/Station Blackout G. LOCA w/Steam Cooling-RCIC Isolation H. RHR Injection Failure II. SCENARIO SUMMARY:

The scenario begins with the plant at 100% power; 3840 MWt, MOL. The Weekly Containment 02 Surveillance Test must be completed.

During the test a Safety Relief Valve will open. Actions taken by the crew to close the SRV will be successful.

A seismic event greater than the OBE will occur and the 1OK107 Service Air Compressor will trip. This will require the OOK107 to be placed in service.

An aftershock will cause a leak in the Reactor Water Cleanup System. RWCU will fail to automatically

isolate, but can be isolated from the Control Room. After the RWCU leak is isolated and Technical Specifications are addressed, an air leak will develop on the scram air header. The air leak will cause multiple control rods to drift in, requiring a manual reactor scram. After the scram, another aftershock will occur. The aftershock will cause a loss of offsite power and LOCA. Only the 'A' EOG will start. The HPCI F001 will fail to open, rendering HPCI inoperable.

When the 'A' RHR pump starts, the 'A' EOG will trip. During RPV level control RCIC will inadvertently

isolate, rendering it inoperable.

This will result in a Station Blackout with no available injection.

When RPV water level reaches -200", the Crew must emergency depressurize.

After the Crew opens five SRVs, the 'C' EOG will be restored to service.

RHR Pump C will fail to automatically start and inject, and must be started and aligned for injection by the Crew. After RPV water level is restored to above -185" using the available RHR pump, the 'A' EOG will be restored to service.

This will allow containment control to be exercised.

The scenario is terminated when the RPV has been depressurized and RPV water level restored.

ESG-4 Page 2 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. INITIAL CONDITIONS:

l.C. Initial ---INITIALIZE the simulator to 100% power MOL. ---ENSURE 1OK107 Service Air Compressor is in service.

ENSURE TAGS is supplied from SACS 8. ------ENSURE Schedule and/or Event File(s) is(are) open as required.

PREP FOR TRAINING (i.e., RM-11 set points, procedures, bezel covers) Initial I ---MARKUP HC.OP-ST.GS-0001, Section 5.1 for approval to commence test. PREPARE a Fire Alarm for LOP. ---REVIEW, at a minimum, the Scenario Reference section and CLEAN the balded EOPs, ---ABs and SOPs listed. (80091396 0270) ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE: Initial Event 2 Event Code: zdads1 (1) I zdads2(1)

==

Description:==

Either F013A Control Switch to OPEN 6 Event Code: iapiarca

<= 82

Description:

Instrument Air Pressure

<=82 psi 12 Event Code: rh_bkr(1)

==

Description:==

RHR Pump A Start ESG-4 Page 3 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training MALFUNCTION SCHEDULE:

I Initial @Time Event Action Description None None Insert malfunction HP04 HPCI system fails to start None None Insert malfunction DG01 C Diesel generator C failure to start None None Insert malfunction AD01 Failure of ADS valves to open None None Insert malfunction CU11A RWCU isolation valve F001 failure to auto close None None Insert malfunction CU11 B RWCU isolation valve F004 failure to auto close None None Insert malfunction DG02B Diesel generator B failure None None Insert malfunction DG02D Diesel generator D failure None None Insert malfunction RH08C RHR System C auto injection failed to energized None None Insert malfunction RC06 after 240 on event RCIC system isolation 7 None None Insert malfunction AD02AO on event 1 ADS/Relief valve F013A (MS LINE A) sticks open None None Insert malfunction AD02AO on event 2 ADS/Relief valve F013A (MS LINE A) delete in 1 sticks open None None Insert malfunction PC07B on event 3 Seismic Event II None None Insert malfunction IA01 A after 20 on event 3 Service air compressor 10K107 failure None None Insert malfunction CU03 from 10.00000 to RWCU system leak 35.00000 in 600 on event 4 None None Insert malfunction IA02 to 60.00000 on Gradual loss of instrument air event 5 None None Insert malfunction EG12 on event 7 Loss of all off site power None None Insert malfunction RR31 A2 after 180 to Recirc loop A large break [V] (10%-6000 3.00000 in 300 on event 7 gpm, 100%-60000 gpm) None None Insert malfunction DG02A after 3 on event Diesel generator A failure 12 None None Insert malfunction PC07 A after 1 on event 7 Seismic Event II None None Insert malfunction DG02A on event 8 delete Diesel generator A failure in 1 ESG-4 Page 4 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None None Insert malfunction CD011427 after 1 on Control Rod 14-27 drift in event 6 None None Insert malfunction CD011827 after 1 on Control Rod 18-27 drift in event6 None None Insert malfunction CD012227 after 1 on Control Rod 22-27 drift in event6 None None Insert malfunction CD012627 after 1 on Control Rod 26-27 drift in event 6 REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote DG05 after 5 to RESET on DG05 Diesel generator A shutdown relay event 8 None None Insert remote DG01 after 20 to RESET on DG01 Diesel generator A lockout relay event 8 None None Insert remote HP08 to TAGGED on event 13 HP08 HPCI Aux Oil Pump OVERRIDE SCHEDULE:

Initial @Time Event Action Description ESG-4 Page 5 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Containment 02 Weekly Surveillance Test: ESG-4 Expected Plant/Student Response

CRS directs commencing Drywell and Suppression Chamber Oxygen Concentration Verification

-Weekly IAW HC.OP-ST.GS-0001.

PO aligns containment sampling IAW HC.OP-ST.GS-0001. =:> Opens one of the following suction valve combinations:

HV-4959A and HV-4965A

HV-4955A and HV-4983A

HV-5019A and HV-4984A =:> Opens HV-4966A and HV-5022A =:> Verifies HV-5741A, H2/02 ANLZR H2 SUP HOR is open =:> Verifies Function Selection Switch for H2/02 Analyzer 1 AC200 in SAMPLE =:> Places the Mode Switch for H2/02 Analyzer 1 AC200 in Analyze =:> Ensures the Control At This Pnl light is on. IF not, press Remote Selector PB Page 6 of 32 Comments Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity SRV Open/Closes:

After 1 AC200 is aligned to sample the Drywell Or Suppression Chamber for Oxygen, TRIGGER ET-1. F013A lnSight Items:

Valve Position advpos(1)

CH B AUTO/OPEN Switch zdads1(1)

CH D AUTO/OPEN Switch zdads2(1)

ESG-4 Expected Plant/Student Response

Crew recognizes open SRV by: OHA C1-A3 "ADS/SAFETY RELIEF VLV NOT CLOSED" Acoustic Monitor indication CRIDS D5005 "SAFETY RELIEF VALVE F013A" Total steam flow lowering Main Gen MWe lowering RPV level swell Elevated SRV tailpipe temperature

CRS implements AB.RPV-0006.

RO reduces reactor power to 95% using TCF. Comments HPI USED: STARD HARD CARDO Immediate Operator Action IAW AB.RPV-0006.

PO cycles SRV control Immediate Operator switches in attempt to close the Action IAW SRV. AB.RPV-0006.

Before more than two minutes has elapsed from SRV opening, CREW closes F013A by cycling EITHER F013A AUTO/OPEN control switches to OPEN and back to AUTO. Page 7 of 32 RECORD elapsed time SRV was open: TIME: ---Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity ESG-4 Expected Plant/Student Response

Crew recognizes SRV closed by: =} Acoustic Monitor indication

=} Total steam flow rising =} Main Gen MWe rising =} RPV level shrink =} Lowering SRV tailpipe temperature

CRS recognize the following Tech Spec actions apply: =} Suppression Drywell Vacuum Breakers 4.6.4.1.b.1

CRS refers to the following Tech Spec statements to determine SRV operability:

=} 3.4.2.1 =} 3.4.2.2 =} 3.5.1.d

CRS refers to AB.RPV-0001

=} Condition B

SM contacts Operations Management.

Page 8 of 32 Comments INPO Fundamentals:

0 MONITORING Must perform functional test of vacuum breakers within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . INPO Fundamentals:

0 KNOWLEDGE Tracking LCOs: 3.4.2.1 and 3.4.2.2 Active LCO: 3.5.1.d Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Earthquake:

AFTER Technical Specifications for the SRV have been addressed, OR at the discretion of the Lead Examiner:

PLAY the Earthquake Sound Effect (if available) at medium volume for about 20 seconds OR ANNOUNCE "You feel motion then it stops", AND TRIGGER ET-3 (Seismic Event) IF Crew calls National Earthquake Center, THEN REPORT a seismic event of 6.0 on Richter scale centered 12 miles east of Wilmington, DE. !E Crew calls Security, THEN REPORT the Security system is intact. !E dispatched to 1 OC673, THEN REPORT:

The SM-3 Event Indicator is WHITE.

The SMA-3 Event alarm is extinguished.

The tape machines have advanced but are not running.

The Amber Alarm light on the Seismic Switch Power Supply drawer is lit. ESG-4 Expected Plant/Student Response

Crew recognizes Seismic Event by: OHA C6-C4 "SEISMIC MON PNL C673" GRIDS D3977 "SEISMIC TROUBLE ALARM TRBL" Response Spectrum Analyzer indications on 10C650C Loud rumbling noise (if available)

Crew monitors critical parameters to determine if plant is stable.

CRS implements AB.MISC-0001: Condition E Condition F

RO/PO implements AR.ZZ-0011 Attachment C4.

Crew dispatches ABEO to 10C673.

Crew recognizes a seismic event >0.1 g has occurred Page 9 of 32 Comments RECORD time C6-C4 alarms for 15 minute ECG Classification.

TIME: ----INPO Fundamentals:

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

Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity IF directed to reset 1 OC673, THEN DELETE Malfunction PC07B. ESG-4 Expected Plant/Student Response

RO/PO direct ABEO to reset 1 OC673 IAW SO.SG-0001.

RO/PO record Seismic Response Spectrum Analyzer lights on AR.ZZ-0011 Att. C4-1.

RO/PO reset Seismic Response Spectrum Analyzer IAW SO.SG-0001.

Crew determines a shutdown IAW IO.ZZ-0004 is required.

Page 10 of 32 Comments Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity NOTE: An Alert Classification is required IAW ECG Section HA1 .1: Actuation of the OBE Seismic Switch {>0.1 g) as indicated by EITHER:

Annunciator C6-C4 (SEISMIC MON PNL C673) activated

Amber alarm light on the Seismic Switch Power Supply Drawer Panel 10C673 AND Earthquake confirmed by ANY of the following:

Earthquake felt in plant by Control Room Operators

National Earthquake Information Center (NEIC) (Note 4)

Control Room indication of DEGRADED PERFORMANCE of a Safety System within a Table H-1 structure:

Table H-1

Reactor Building Control/Auxiliary Building

Service Water Intake Structure Service/

Radwaste Building ESG-4 Expected Plant/Student Response Page 11 of 32 Comments Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments Trip of 10K107:

Crew recognizes loss of The primary purpose of 20 seconds after Seismic event 10K107 by: the air malfunctions is to occurs. OHAA2-B2 exercise the immediate "COMPRESSED AIR operator actions for trip PANEL OOC188" of the in-service Service OHA A2-A1/A2 "INST AIR Air compressor.

HEADER A/B PRESS LO" GRIDS 04601 "INSTR AIR SPL Y HOR A PRESS LO" GRIDS 04602 "INSTR AIR SPL Y HOR B PRESS" LO OVLD/PWR FAIL light Lowering Service and Instrument Air pressures

PO places OOK107 in service Immediate Operator IAW AB.ZZ-0001 Attachment Action IAW 7. AB.COMP-0001. PRESS OOK107 MAN PB. ENSURE OOK107 Cooling HPI USE ..... Water Booster Pumps STARD starts. HARD CARD 0 PRESS OOK107 AUX OIL PUMP START PB. OBSERVE OOK107 MOP starts following 20 second TD. PRESS OOK107 Auxiliary Oil Pump STOP PB. VERIFY lube oil pressure is adequate by only MOP RUNNING. PRESS OOK107 START PB.

CRS implements AB.COMP-001: Condition A

STA/IA monitors AB.COMP-0001 implementation.

ESG-4 Page 12 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity

!E dispatched to check status of RAGS demins, AND the EIAC is running, THEN REPORT the RAGS demins are isolated.

!E dispatched to check status of HV-11416, AND Remote Function IA01 status is ONLINE, THEN REPORT the HV-11416 is open. IF dispatched to investigate the trip of 10K107, THEN REPORT VIBRATION ALARM and VIBRATION SHUTDOWN alarms were in. RWCU Leak: When the Station Air Compressor is in service, OR at the discretion of the Lead Examiner, TRIGGER ET-4. ESG-4 Expected Plant/Student Response

IF Instrument Air Header Pressure reaches 85 psig, THEN CRS implements AB.COMP-0001:

=> Condition C

Crew dispatches TBEO and Maintenance to investigate trip of 10K107.

Crew recognizes RWCU leak by: => CRI OS indication and alarm Page 13 of 32 Comments INPO Fundamentals:

0 MONITORING Rev. 1 PSEG CONFIDENTIAL*

Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity lnSight Items:

RWCU Diff Flow cufdelta

!E dispatched to look for the leak, THEN REPORT the unable to determine leak location.

NOTE: CREW may isolate RWCU before alarm conditions exist. lnSight Items: * 'A' Channel Isolation cu_k6a09

'D' Channel Isolation cu_k6d11 lnSight Items:

HV-F001 cuvf001

HV-F004 cuvf004 ESG-4 Expected Plant/Student Response

Crew recognizes leak from RWCU by: => Rising differential flows on NUMAC and GRIDS RWCUDF page 61 => OHA D3-83 "RWCU STM LK ISLN TIMER INITIATED"

=> GRIDS D5871 "RWCU ISLN TIMER INITIATED CH D" => GRIDS D5873 "RWCU ISLN TIMER INITIATED CHA" => GRIDS RWCUDF "RWCU DIFFERENTIAL FLOW" in alarm.

Crew recognizes failure of RWCU to isolate by: => OHA C1-A2 "RWCU DIFF FLOW HI" => GRIDS D5870 "RWCU DIFF FLOW CH D" => GRIDS D5872 "RWCU DIFF FLOW CH A"

RO/PO closes RWCU HV-F001 and HV-F004.

Crew initiates closure of RWCU HV-F001 OR HV-F004 when OHA C1-A2 "RWCU DIFF FLOW HI" alarms. Page 14 of 32 Comments Room temperatures will not provide conclusive evidence of leak. RWCU differential flow will reach the alarm setpoint about 7.5 minutes after leak starts. If RWCU is isolated before differential flow setpoint is reached, alarms will not be received.

If RWCU is isolated before differential flow setpoint is reached, isolation will not be received.

HPI USED: STARD Immediate Operator action IAW AB.CONT-0002.

Closing the RWCU HV-F001 OR HV-F004 prior to receiving OHA C1-A2 satisfies this Critical Task. Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity ESG-4 Expected Plant/Student Response

Crew isolates RWCU IAW SO.BG-0001 OR AB.CONT-0004 Condition C

CRS implements AB.CONT-002:

=> Condition A => Condition B

Crew validates isolation by trending:

=> RWCU differential flow * !E the leak was not isolated before the isolation signal was received, THEN CRS/STA/IA recognize the following Tech Specs apply: => Primary Containment Isolation Valves 3.6.3 action a => Primary Containment Integrity 3.6.1.1

Crew contacts Operations Management to initiate ERT callout.

Page 15 of 32 Comments HPI USED: STARD Condition A applies if C1-A2 is received.

INPO Fundamentals:

0 MONITORING Need to restore valves to OPERABLE or deactivate the HV-F001 or HV-F004 in the next four hours. May also refer to TIS 3.3.2, although both trip systems would already be tripped and the valves already shut. INPO Fundamentals:

0 KNOWLEDGE Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Multiple Rod Drifts: WHEN RWCU is isolated, OR at the discretion of the Lead Examiner, TRIGGER ET-5 (Gradual Loss of Instrument Air). The multiple rod drift is automatically inserted when instrument air pressure drops to 82 psig. ESG-4 Expected Plant/Student Response

Crew recognizes lowering Instrument Air Pressure by: =? OHA A2-A1(A2),

"INST AIR HEADER A(B) PRESSURE LO" =? CRIDS 04601 (2), INST AIR SUPPLY HOR A(B) PRESS =? Pl-7603A(B) on 10C650A

CRS implements AB.COMP-001:

=? Condition A

PO implements AB.COMP-001 Condition A: =? Announce Terminate all unnecessary use of Service and Instrument Air =? Start the standby Service Air Compressor

Press OOK107 MAN PB

Ensure OOK107 Cooling Water Booster Pumps starts

Press OOK107 Aux Oil Pump ST ART PB.

Observe OOK107 MOP starts following 20 second TD

Press OOK107 Auxiliary Oil Pump STOP PB

Verify lube oil pressure is adequate by only MOP RUNNING

Press OOK107 START PB =? Consider closing HV-7595 Page 16 of 32 Comments Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity ESG-4 Expected Plant/Student Response

Crew recognizes multiple rods drifting into the core by: => OHA C6-E3 "ROD DRIFT" => Multiple "DRIFT",

lights on Full Core display => RWM drifting rods indication

=> GRIDS C078 "ROD DRIFT ALARM ALM" => Lowering reactor power and Main Generator output

RO locks the Mode Switch in SHUTDOWN.

Crew scrams the reactor after multiple rod drifts.

RO performs scram actions IAW AB.ZZ-0001 Att 1.

Crew recognizes RPV Level Below 12.5" EOP entry condition by: => OHA C5-A4 "RPV WATER LEVEL LO" => OHA A7-D5 "RPV LEVEL 3" => Various water level indicators Page 17 of 32 Comments INPO Fundamentals:

0 MONITORING INPO Fundamentals:

0 CONTROL RECORD the time between OHA C6-E3 and reactor scrammed.

TIME: ----HPI USED: STARD HARD CARD 0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Pressure Leg Direct initial pressure control as Stabilize pressure 800 psig to 1000 psig. The lower limit of 800 psig will not complicate RPV level maintenance and will prevent an unwanted cooldown.

The upper limit of 1000 psig is a round number below 104 7 psig. Do NOT allow the use of SRVs to interfere with Bypass valves. Use the main turbine when steam production exceeds the capacity of the Bypass valves should supersede concerns for turbine damage due to vibrations or other concerns.

STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Level Leg Direct an initial band of +12.5" to +54" Rx level. This gives a manageable band with level control still in the indicating range. If controlling Reactor Pressure with SRVs and the MSIVs are closed, then the RPV level band assigned should be -30" to +30" 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-4 Expected Plant/Student Response

CRS implements EOP-101.

STA/IA performs the following:

. Verifies Rx shutdown

:::;. Trends critical plant parameters

. Monitors EOP implementation PO controls RPV water level as directed by CRS IAW AB.ZZ-0001 Att 14. Page 18 of 32 Comments INPO Fundamentals

0TEAMWORK Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Aftershock/LOP/LOCA:

5 minutes after the scram, OR, at the Lead Examiners discretion,

PLAY the Earthquake Sound Effect (if available) at medium volume for about 20 seconds OR ANNOUNCE "You feel motion then it stops"

TRIGGER ET-7 (LOP/LOCA/Station Blackout)

IF called as the ESOC, THEN REPORT both the Hope Creek AND Salem switchyards are de-energized.

It will take a minimum of 6-10 hours to restore power once the transient has been investigated.

!E dispatched to investigate the failure of B/D EDGs to start, THEN REPORT both EDGs have Lube Oil Low Pressure Shutdown alarms. There is oil on EOG room floors. ESG-4 Expected Plant/Student Response

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/C/D EDGs to start and load by: Engine STOP lights Output breaker TRIP lights OVLD/PWR lights on associated Channel components

RO/PO attempt to start the B/C/D EDGs. Comments Only 'A' EOG will start. 'A' EOG will trip when the 'A' RHR pump is started.

HPI USED: STARD PEERCHECK0 Immediate Operator Action IAW AB.ZZ-0135

CRS implements AB.ZZ-0135.

INPO Fundamentals:

0TEAMWORK

Crew dispatches NEO and/or Maintenance to investigate failure of B/D EDGs to start.

Page 19 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity

!E dispatched to investigate the failure of the 'C' EOG to start, THEN REPORT there is a blown fuse on DC Circuit 3 on the CC421 panel. IF directed to start the EOG using either local control switch, THEN REPORT it did not work. (AR.KJ-0005 Att. 37 A) !E dispatched to check 86, SFR, and SOR relays for 'C' EOG, THEN REPORT:

86 lockout relays are reset (CC422, elev 137')

Blue buttons on SFR and SOR are out (de-energized)

(CC421 elev 102')

Maintenance expects to replace the fuse within 30 minutes.

!E dispatched to determine status of HPCI, THEN REPORT

HPCI is idle

HPCI Aux oil pump is running.

HV-F001 is closed IF directed to open the breaker for the HPCI Aux Oil pump, (72-251042)

THEN TRIGGER ET-13. IF directed to open HV-F001 by hand, REPORT HV-F001 will not move ESG-4 Expected Plant/Student Response

Crew dispatches NEO and/or Maintenance to investigate failure of 'C' EOG to start.

Crew recognizes HPCI F001 problem by: HPCI Aux Oil Pump running HV-F001 not open "HPCI INIT AND SEALED IN" light on

CRS directs injecting with 'A' SLC pump. Page 20 of 32 Comments INPO Fundamentals:

0 MONITORING Only available injection source. Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity RCIC system isolation RCIC isolation will occur 4 minutes after the LOP. ESG-4 Expected Plant/Student Response

RO/PO starts the 'A' SLC pump.

RO/PO identifies isolation of RCIC by: OHA B1-A1 "RCIC TURBINE TRIP CRIDS 02400 in alarm ISLN INIT Status Lights illuminated BD-HV-FOO?

AND FOOS CLOSING

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 1 OC650C RM 11 9AX833/834 alarm Various Suppression Pool temperature indicators

Crew recognizes Supp Pool Level Above 78.5 In EOP entry condition by: OHA 81-C3 "SUPPRESSION POOL LEVEL HI/LO" Various Suppression Pool level indicators Page 21 of 32 Comments HPI USED: STARD INPO Fundamentals:

0 CONTROL Given the lowering RPV water level, and 'A' RHR being the only available RHR pump, the Crew may not place 'A' RHR in Suppression Pool cooling at this time. Given the LOP and the unavailability of HPCI and RCIC, there is nothing the Crew can do to lower Suppression Pool water level at this time. Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Station Blackout/Stm Clg: The 'A' EDG will trip 3 seconds after the 'A' RHR pump starts. This will automatically occur at 1.68#, if the Crew doesn't start it sooner. IF dispatched to investigate the trip of the 'A' EDG, THEN REPORT you heard the EDG slow down, then speed up and trip. Alarm on local panel is ENGINE OVERSPEED.

Expected Plant/Student Response

Crew recognizes trip of the 'A' EDG by: => Diesel engine STOP light => Flashing generator breaker TRIP light => OVLD/PWR FAIL lights on associated channel loads

Crew dispatches NEO and/or Maintenance to investigate trips of the 'A' EDG. Comments WHEN OHA A2-A5 alarms, advance the Fire Computer to display LOP alarms.

CRS recognizes no pumps are INPO Fundamentals:

lined up available for injection D MONITORING and Steam Cooling is required.

WHEN RPV water level reaches -129", THEN CRS directs inhibiting ADS. WHEN RPV level CANNOT be

RO/PO inhibits ADS IAW restored and maintained above AB.ZZ-0001 Att. 13. -161 in.(FB1 .P AND RB1 .L); THEN an SAE is required IAW FPBT Sections FB1.P AND RB1 .L (9 points} [RB2.L, Drywell pressure

>1.68 psig due to RCS leakage may be used in place of RB1 .L IF High DW pressure condition is met.] Will NOT be declared if conditions for GE are met. ESG-4 Page 22 of 32 INPO Fundamentals:

0 CONTROL HPI USED: STARD HARD CARD 0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity WHEN the 'A' EOG trips, THEN an SAE is required IAW ECG Section SS1.1 (Loss of all Power (Onsite and Offsite) to all 4.16 KV Vital Buses AND >15 minutes have elapsed)

May NOT be declared if within 15 minutes:

power is restored to a 4.16 KV Vital Bus; or a GE is declared.

Note: WHEN Loss of all offsite and onsite AC power to all 4.16 KV Vital buses AND ANY of the following:

o Restoration of at least one Vital Bus in <4 hrs is NOT likely o RPV level CANNOT be restored and maintained above -161 in. o RPV level CANNOT be determined.

THEN a GE is required IAW ECG Section SG1 .1. ESG-4 Expected Plant/Student Response

WHEN RPV water level reaches -200", THEN CRS directs opening five ADS SRVs.

RO/PO opens five ADS SRVs IAW AB.ZZ-0001 Att. 13. Page 23 of 32 Comments INPO Fundamentals:

0 MONITORING HPI USED: STARD HARD CARD 0 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity WHEN at least five SRVs are open, THEN DELETE Malfunction DG01 C to restore the 'C' EOG to service, AND REPORT the 'C' EOG has been successfully started.

SUPPORT any requests to place ECCS pumps in PTL using Remote Functions:

CS05C for 'C' Core Spray

RH23C for 'C' RHR RHR INJECTION FAILURE The auto start of the 'C' RHR pump and auto opening of the F017C are failed. AFTER the Crew restores RPV water level to above -185", THEN REPORT you are ready to restore the 'A' EOG to service.

The governor oil level was low and has been restored to normal. SUPPORT any requests to place ECCS pumps in PTL using Remote Functions:

CS05A for 'A' Core Spray

RH23A for 'A' RHR ESG-4 Expected Plant/Student Response

Crew opens at least five SRVs after compensated reactor water level reaches -200".

Crew recognizes start of the 'C' EOG by: => Diesel engine START light => Generator breaker CLOSE light => OVLD/PWR FAIL lights extinguished on associated channel loads

RO/PO starts the 'C' RHR pump, opens the HV-F017C, and restores RPV water level to above -185" IAW AB.ZZ-0001 Att. 4.

WHEN the 'C' EDG is restored, THEN the Crew injects with the 'C' RHR pump and restores and maintains RPV water level above -185". Page 24 of 32 Comments HPI USED* STAR[ HARD CARD [J INPO Fundamentals:

0 CONTROL Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity lE directed to restore the 'A' EOG to service, AND after level has been restored with 'C' EOG, THEN TRIGGER ET-8 AND REPORT the 'A' EOG has been successfully restarted.

Termination Requirement:

The scenario should be terminated at the discretion of the Lead Examiner when:

The reactor has been depressurized

RPV water level is being maintained above -129" ESG-4 Expected Plant/Student Response

Crew recognizes start of the 'A' EOG by: :=} Diesel engine START light :=} Generator breaker CLOSE light :=} OVLD/PWR FAIL lights extinguished on associated channel loads Comments The restoration of the 'A' EOG makes the 'A' Core Spray Loop available for RPV water level control.

CRS directs restoring PCIG to The AK202 PCIG the SRVs. compressor became available when the 'C' EOG was restored.

RO/PO restores PCIG to the HPI USED: SRVs IAW AB.ZZ-0001 Att. 9. STAR 0

CRS directs placing the 'A' RHR pump in Drywall Spray.

RO/PO places 'A' RHR pump in Drywall Spray IAW AB.ZZ-0001 Att. 2. Page 25 of 32 HARD CARD 0 HPI USED: STARD HARD CARD D Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requalification Training Exam Development Job Aid B. NU REG 1021 Examiner Standards C. JT A Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Hope Creek Event Classification Guide (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-101-111-1004 Operations Standards M. OP-AA-106-101-1001 Event Response Guidelines N. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program 0. OP-HC-108-106-1001 Equipment Operational Control P. HC.OP-AB.ZZ-0001 Transient Plant Conditions Q. HC.OP-AB.CONT-0002 Primary Containment R. HC.OP-AB.CONT-0004 Radioactive Gaseous Release S. T. U. HC.OP-AB.COMP-0001 Instrument and/or Service Air HC.OP-AB.MISC-0001 Acts of Nature HC.OP-AB.ZZ-0135 Station Blackout/Loss of Offsite Power/Diesel Generator Malfunction V. HC.OP-AB.ZZ-000 Reactor Scram W. HC.OP-EO.ZZ-0101 RPV Control X. HC.OP-EO.ZZ-0102 Primary Containment Control Y. HC.OP-EO.ZZ-0103 Reactor Building Control Z. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization AA. HC.OP-EO.ZZ-0206 RPV Flooding BB. Strategies For Successful Transient Mitigation ESG-4 Page 26 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VII. ESG CRITICAL TASK RATIONAL ESG-4/1 1.

Before more than two minutes has elapsed from SRVopening, CREW closes F013A by cycling EITHER F013A AUTO/OPEN control switches to OPEN and back to AUTO. KIA 239002 Safety Relief valves A2. Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

A2.03 Stuck open SRV RO 4.1 SRO 4.2 A4 Ability to manually operate and/or monitor in the control room: A4.01 SRV's RO 4.4 SRO 4.4 2. Immediate Operator Actions in AB.RPV-0006 direct cycling the SRV control switch in an attempt to close the SRV. Cycling the control switches cycles the SRV pilot valve, and may result in clearing debris or reseating the pilot valve such that the SRV closes. Failing to perform this action would result in the SRV remaining open for more than two minutes, which would require a manual scram IAW with Tech Specs. This would result in an unnecessary scram transient.

Two minutes is adequate time to validate the SRV is open and cycle the appropriate control switch.

Crew initiates closure of RWCU HV-F001 OR HV-F004 when OHA C1-A2 "RWCU DIFF FLOW HI" alarms. KIA 223002 Primary Containment Isolation System I Nuclear Steam Supply Shut-Off A4 Ability to manually operate and/or monitor in the Control Room A4.01 Valve Closures RO 3.6 SRO 3.5 A4.06 Confirm initiation to completion RO 3.6 SRO 3.7 The RWCU System has failed to isolate automatically.

Failure of the Crew to manually isolate the system will result in a bypass of the Reactor Coolant and Primary Containment boundaries and release of radioactive materials to the Reactor Building.

3. Crew scrams the reactor after multiple rod drifts. KIA 201003 Control Rod and Drive Mechanism A2 Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct,

control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 Drifting rod RO: 3.4 SRO 3. 7 Having multiple rods inserting into the core out of sequence places the core in an unanalyzed condition.

Thermal Limits may be violated resulting in fuel damage and a potential for radiological release.

The Neutron Monitoring System is not designed to protect the core under these conditions and operator action is required.

ESG-4 Page 27 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VII. ESG CRITICAL TASK RATIONAL (CONTINUED)

4. Crew opens at least five SRVs a'fter compensated reactor water level reaches -200". KIA 295031 Reactor Low Water Level EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: EA.06 Automatic depressurization RO 4.4 SRO 4.4 5. When Reactor water level cannot be maintained above -200" without injection to the RPV, adequate core cooling cannot be assured (Minimum Zero Injection Reactor Water Level). EOPs direct action to initiate emergency depressurization when RPV water level reaches this value if there is no injection sources available.

To restore adequate core cooling, the Crew must Emergency Oepressurize and restores level with low pressure ECCS. WHEN the 'C' EDG is restored, THEN the Crew injects with the 'C' RHR pump and restores and maintains RPVwater level 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: EA 1.01 Low pressure coolant injection (RHR) RO 4.4 SRO 4.4 ESG-4 The automatic opening of the HV-F017A is failed. 'C' RHR is the only ECCS pump available for injection (although the 'C' Core Spray pump is running, there is no power to the injection valve due to the loss of the 'A' EOG). Operator action will be required to initiate injection and restore/maintain adequate core cooling.

The absence of a time limit is due to the potential variance in reactor pressure when the 'C' RHR pump becomes available.

The pump may become available before or after the permissible injection pressure for the RHR pump (IAW AB.ZZ-0001) is reached.

This action must therefore be complete before the end of the scenario.

Inherent to this critical task is the Crew dispatching personnel to investigate the failure of the 'C' EOG to start. If no one is sent to investigate, the EOG will NOT be restored to service.

Page 28 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training Y/N ESG-4/1 HOPE CREEK ESG -PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT Y Loss Of Offsite Power/SBO Y LOCA TRANSIENTS:

Turbine Trip Loss of Condenser Vacuum Loss of Feedwater Y Manual Scram EVENT Internal Flooding LOSS OF SUPPORT SYSTEMS:

Loss of SSW Loss of SACS COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY SYSTEMS Y HPCI SRVs ------y RCIC Condensate/Feedwater

y B/D EDG SSW ------A/B RHR Pump RPS ------A/B SACS Loop ---y 1E 4.16KV Bus 1 E 480 VAC Bus ---120VAC 481 Inverter

---1E 125VDC ---Hard Torus Vent ---OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Y Manual Depressurization of the RPV w/ no HP Injection Available

___ Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi DW Press. Signal ---Control RPV Water Level w/ HP Injection during ATWS Sequence

___ Align Portable Power Supply to Battery Chargers

___ Venting of Primary Containment

---Restore Switchgear Cooling Restart Condensate

Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG ESG-4 Page 29 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training VIII. TURNOVER SHEET:

__

PROTECTED EQUIPMENT None EOOS is out of service REACTIVITY I Plant Status Reactor power 100%. Perform HC.OP-ST.GS-0001 using 1AC200. ESF/SAFETY SYSTEMS None COOLING WATER None BOP None ELECTRICAL None ADVERSE CONDITION MONITORING None Page 30 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG-4 SELF-CHECK

1. Total malfunctions inserted:

5-8 ----2. Malfunctions that occur after EOP entry: 1-4 3. Abnormal Events: 2-3 ----4. Major Transients:

1-2 5. EOPs used beyond primary scram response EOP: 1-3 ----6. EOP Contingency Procedures used: 0-3 --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 --10. Technical Specifications are exercised during the test: >1 --Comments:

ESG-4 Page 31 of 32 Rev. 1 PSEG CONFIDENTIAL

-Possession Requires Specific Permission From Nuclear Training SIMULATOR ESG REVIEWNALIDATION CHECKLIST:

(continued)

II Crew Validation Rev.: 0 Date Validated:

11/5/2014 Validated with operators from Crew Validation Comments Disposition

1. Incorporated changes and comments from 1. Changes made. validation on 10/31 /2014 2. Revised based on comments during this 2. Changes made. validation.

Added Abnormal actions.

Revised Tech Spec references.

Crew Validation Rev.: 1 Date Validated:

1/20/2015 Validated with operators.

Validation Comments Disposition

1. Revised based on NRC validation

1. Added control panel manipulations in comments.

Event 1. 2. Added actions performed as part of response to initial indications for Event 5. 3. Added instructor actions on OHA A2-A5. 4. Made editorial changes to ECG classification moved to more appropriate location.

Added possible lower level ECG classification.

ESG-4 Page 32 of 32 Rev. 1

ML15100A042

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