ML15100A042
| 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: |
| References | |
| TAC U01904 | |
| Download: ML15100A042 (360) | |
Text
' COPY OF STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: 4010010201 TASK: Complete The Daily Surveillance Logs 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 1a) in accordance with HC.OP-DL.ZZ-0026.
Page 2of13
, JPM NUMBER: 305H-JPM.ZZ016 NAME:
REV NUMBER: 03 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD UNSAT)
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 1a are required. Refer to Exhibit 1 for expected values.
Values are typical and may not exactly match observed values.
Readings are SAT if they are within
+/-1 meter division of actual reading.
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
JPM NUMBER: 305H-JPM.ZZ016 NAME:
REV NUMBER: 03 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fa NUMBER UNSAT 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 1a 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: 305H-JPM.ZZ016 NAME:
REV NUMBER: 03 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 6of13
JOB PERFORMANCE MEASURE JPM NUMBER: 305H-JPM.ZZ016 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 305H-JPM.ZZ016 REV#: 03 TASK: Complete The Daily Surveillance Logs x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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., RM~1 *.
PLACE pictures of Main Screen and RWCU Delta-Flow on NUMAC 1SKXR-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:,
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Initial @Time Event Action Description MASTER TRIP UNIT B21-N675A METER None None Insert override 12A6 A AO to 0.21000 (COND VAC LO) - C71A-Z2A (AO)
Initial @Time Event Action Description Page 10of13
HC.OJ- _ .... ZZ-0026(Q)
[ EXAMINER'S COPY I Page 13of18 Surveillance Log - Control Room -Day Shift 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 (6~J 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 CNOTE 61) 1,2,5 N601A 0 N/A N/A N601B 0 N/A N/A 0 10 --- -- 72 No 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 -38 --- --- 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 (NOTES 53, 54) 1.2.3 9RX509 37 9RX510 38 9RX511 36 9RX512 37 2 (NOTE 53) --- -- 3X NORM No NOTE 55 15.0 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 ISOLATED, THE MSL RADIATION CHANNEL CHECK BETWEEN THE ALPHA AND BRAVO 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 Rev.144 Page 11of13
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 MIN MSLRMSA MSLRMS B MSLRMS C MSLRMS D a RM-11 LAST HOURLY AVERAGE 37 38 36 37 b RM-11 HI SETPOINT 105 114 112 114 c c =a I bx 3 (RATIO OF ACTUAL TO BASELINE AFPB) 0.850 1.057 1.000 0.964 0.974
[JJ Item 63, Condenser Vacuum exceeds max deviation.
[I] Item 65, RPV Level 3 exceeds max deviation.
Hope Creek Page 32 of 105 Rev.144 Page 12of13
' 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> while Reactor Engineers evaluate core conditions.
INITIATING CUE:
COMPLETE the Day Shift daily Surveillance Logs for 1OC609, 1OC611, 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 COPY OF SYSTEM: Reactor Recirculation TASK NUMBER: 3000260101 TASK: Perform Power Changes During Operation 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 RO~ 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: - - 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 1OC619, 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 IAW 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. ~1 %]
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) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 from the value Operator then initials Step and 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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 *Operator contacts the individual Jet Pumps in 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: ZZ047 NAME:
REV NUMBER: 0 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 8of16
JOB PERFORMANCE MEASURE JPM NUMBER: ZZ047 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ047 REV#: 0 TASK: Perform Power Changes During Operation x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 0 INITIALIZE to 100% power MOL.
INSERT 1OC, 1OB, and 1OA Control Rods.
LOWER Reactor Recirculation Pump Demands to 74.5%.
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
<\. -.::~:L-.-~<>:,itft%l:'.if:::/2F"'.1:>
'E SCHEDULE: *
'-~,:~}{1.>fb>~<<>. "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 VALUE 5.1.4.A RECIRCULATION PUMP "A" SPEED (1-BB-SIC-R621A) N/A %
5.1.4.B RECIRCULATrON PUMP "B"' SPEED f1-BB-SIC-R6218) 74.25 %
RECIRCULATION PUMP "A"' FLOW 1-BB-Fl-R617-B31 5.1.4.C N/A KGPM #
or *t-BB-FR-R614-B31 (red) (Circle indicator used)
RECIRCULATION PUMP "B" FLOv@B-Fl-R613-~
5.1.4.D 39.030 KGPM #
or 1-BB-FR-R614-B31 (blue) (C1rc1e 11 rult;.dtor used) 5.1.4.E "'A" PUMP SPEED/FLOW DEVIATION CHECK N/A 5.1.4.F "'B'. PUMP SPEED/FLOW DEVIATION CHECK SAT JET PUMP LOOP TOTAL FLOW "A'" Fl-R611A-821 5.1.4.G.1 18.15 MLBJHR or A3189 JET PUMP LOOP TOTAL FLOW "B" Fl-R611B-B21 5.1.4.G2 67.98 MLBJHR or A3190 5.1.4.G-3 OR TOTAL (CALCULATED) CORE FLOW 52.55 MLBJHR 5.1.4.G.5 5.1.4.H RECIRC PUMP FLOW vs TOTAL CORE FLOW CHECK CuNsAf) 5.1.8 JET PUMP DIFFERENTIAL PRESSURE CHECK SAT 5.1.9 CORE THERMAL POWER (P1OR003) 2030.9 MWTH #
"' 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.
Hope Creek Page 14 of 42 Rev.16 Page 12of16
1* TRAINING ONLY HC.OP-ST.BB-0007(Q)
ATTACHMENT 3 INPLANT DATA SHEET 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 INDIVIDUAL JET ESTABLISHED % dp on JET PUMP 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 HC.OP-ST.BB-0007(Q)
ATTACHMENT 3 INPLANT DATA SHEET 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 INDIVIDUAL JET ESTABLISHED % dp on JET PUMP 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 HC.OP-ST.BB-0007(Q)
ATTACHMENT 3 INPLANT DATA SHEET 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 INDIVIDUAL JET ESTABLISHED % dp on JET PUMP 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 1OC619, Aux Bldg Control Area El. 102', to obtain individual Jet Pump dp's.
Another operator will perform the rest of the procedure.
Page 16of16
JOB PERFORMANCE MEASURE STATION: Hope Creek COPY OF SYSTEM: Administrative TASK NUMBER: 2990090301 TASK: Generate An SAP System Valve/Breaker Alignment 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 RO~ STAD SRO~
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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
Applicant identifies the following mechanical VENT paths (valves in the OPEN position):
- *V143 AND V144 Page 3 of 8
JPM NUMBER: ZZ048 NAME:
REV NUMBER: 00 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fa NUMBER UNSAT STANDARD UNSAT)
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 1OB212 Breaker 52-212031]
- *AP202
[1 OA401, Breaker 52-40106 ]
Examiner Note: Breaker numbers are not critical.
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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: ZZ048 NAME:
REV NUMBER: 00 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 5 of 8
JOB PERFORMANCE MEASURE JPM NUMBER: ZZ048 REVISION HISTORY Validation Rev# Date Description 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 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ048 REV#: 00 TASK: Generate An SAP System Valve/Breaker Alignment x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 SRO cgj EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
EP-HC-111-F8, Rev. 8 TOOLS, AND EQUIPMENT: Black pen 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.
- 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: 305H-JPM.ZZ014 NAME:
REV NUMBER: 02 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 4of11
JOB PERFORMANCE MEASURE JPM NUMBER: 305H-JPM.ZZ014 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 305H-JPM.ZZ014 REV#: 02 TASK: Perform the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 02 RESET to 100% power IC.
';:~}~;,'~
--: <tV
\ 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 1E 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 Description Recirc loop A large break [V] (10%-6000 None None Insert malfunction RR31 A2 to 100.00000 gpm, 100%-60000 gpm)
None None Insert malfunction QQ20 to SHORT RHR pump AP202 Malfunctions None None Insert malfunction EG12 after 120 Loss of all off site power Page 7of11
JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
<SCHEDOLE:
Initial @Time Event Action Description Initial @Time Event Action Description None None Insert override 3A83_F_LO to Off BP207 STOP (LO)
Page 8of11
- 1 MEES 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 y RWCUPUMPS A B254 x 11 B B420
("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 SYSTEMS FEED YIN v B B A A(i 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
,., ... A. lf.
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.
- 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
JOB PERFORMANCE MEASURE MEES I TRAINING ONLy I EP-HC-111-FS ATT8
- HOPE CREEK MAJOR EQUIPMENT AND ELECTRICAL STATUS (MEES)
DATE:
UPDATE TIME:
Toda~
Page 7of13 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 COPY OF SYSTEM: Equipment Control 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 SRO: 3.8 ALTERNATE PATH: D APPLICABILITY: EO D STA~ SRO~
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 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 NAME:
~
REV NUMBER: 05 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD UNSAT)
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 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 Operator determines correct step of the procedure. beginning step to be 5.3.1 .
5.3.1 Any time it is determined that a Operator determines a TIS LCO 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.
5.3.2 DETERMINE if the T/S LCO/Tech Spec Implementation Action N/A N/A N/A Statement is ACTIVE or TRACKING based on the following criteria:
Page 3of19
JPM NUMBER: ZZ029 NAME:
-------*-----*----~
REV NUMBER: 05 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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-Spec Implementation ACTION 001 from Attachment 3-1.
(CONT) 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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:
Operator records YY-001 in LCO RECORD the LCO Index INDEX NUMBER. [YY=Year]
Number (from Attachment 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in DATE/TIME ACTION REQUIRED.
Page 6of19
JPM NUMBER: ZZ029 NAME:
REV NUMBER: 05 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD UNSAT)
- RECORD the Date/Time Operator records a Date/Time of Action Required. When *failure time plus 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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:
----~--------
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 STA, then the following step requires concurrence review from an actively licensed and proficient SRO, and/or a qualified and proficient STA. The actively licensed and proficient SRO, and/or the qualified and proficient STA completing the concurrence review shall not be the same person who authorizes entry into the TECH SPECS/Tech Spec Implementation Action Statement in 5.3.4.B.5.
Page 9of19
JPM NUMBER: ZZ029 NAME:
REV NUMBER: 05 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT STANDARD UNSAT)
E. OBTAIN CONCURRENCE Operator submits for REVIEW from an actively CONCURRENCE REVIEW.
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]
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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: ZZ029 NAME:
~~~~~~~~~~--~~
REV NUMBER: 05 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 11 of 19
JOB PERFORMANCE MEASURE JPM NUMBER: ZZ029 REVISION HISTORY Validation Rev# Date Description 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 TASK: Complete an Action Statement Log Sheet x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x-
-- 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x
--- 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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
JOB PERFORMANCE MEASURE OP-HC-108-115-1001 EXAMINER'S COPY I Revision r Page 33 of& ...
ATTACHMENT 3-1 TECHNICAL SPECIFICATION ACTION STATEMENT LOG INDEX TECH MODE ENTRY EXPIRATIOI ACTIVE/ PLANNED
( SPEC RESTRAINT
SUMMARY
DESCRIPTION DATE/ DATE/TIME TRACKING Y/N
- R NUMBER Y/N ** TIME CONDITIOI' y DATE/
1 3.6.4.2 ACTIVE GSV-PSV-5032 N (Date+ 72H)/T TIME
- !E unit mode changes, RE-EVALUATE and REVISE mode column as necessary.
Page 14of19
JOB PERFORMANCE MEASURE OP-HC-108-115-1001 EXAMINER'S COPY *Revision 27 Page 95of98 FORM 1 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 Summar~ of Actions Reguired}
3.6.4.2-Restore the VAC Breaker assembly to o~erable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least Hot Shutdown Within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
GS-PSV-5032 failed to open RESPONSIBLE DEPARTMENT NOTIFICATION{S}
SPECIAL REPORT REQUIRED YES 0 NO~ 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 Initials Entry has been logged in the Control Room Narrative logs (SM/CRS Initial)
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 OP-HC-108-115-1001 EXAMINER'S COPY Revision 27 Page 96of98 FORM 1 TECHNICAL SPECIFICATION ACTION STATEMENT LOG Page 2 of 4 1.0 ORDER AND WCD ADDENDUM DR I NOTF I RESP.
ORDER TASK/
DESCRIPTION SYSTEM 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 OP-HC-108-115-1001 EXAMINER'S COPY Revision 27 Page 97 of 98 FORM 1 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_ o f _
DR/ NOTF I RESP.
ORDER TASK/
DESCRIPTION SYSTEM DEPT/ STATUS WCD TYPE GROUP NUMBER Page 17of19
JOB PERFORMANCE MEASURE OP-HC-108-115-1001 EXAMINER'S COPY Revision 27 Page 98of98 FORM 1 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 COPY OF SYSTEM: Administrative TASK NUMBER: 2992320302 TASK: Review All Operations Logs In Use During A Shift Including Computer Logs 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 SRO~
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:
TASK NUMBER:
Administrative 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION '
JPM NUMBER: ZZ049 NAME:
REV NUMBER: 00 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 4 of 8
JOB PERFORMANCE MEASURE JPM NUMBER: ZZ049 REVISION HISTORY Validation Rev# Date Description 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
VALIDATION CHECKLIST JPM NUMBER: ZZ049 REV#: 00 TASK: Review All Operations Logs In Use During A Shift Including Computer Logs x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 OP-HC-108-116-1001 Revjsion 2 Page -13 of 13 ATTACHMENTl 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
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative 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: RO: 3.4 SRO: 4.7 ALTERNATE PATH: ~
APPLICABILITY: EO D STA~ SRO~
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 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. (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: ZZ022 NAME:
REV NUMBER: 01 DATE:
*------~
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD 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.
START TIME: _ _ __
5.9 SUBMIT this procedure to the Operator completes Attachment 3, SM/CRS for review AND Step 3.1, and reviews the completion of Attachment 1. 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.
The data acquired during the *operator signs and dates the performance of this test has UNSATISFACTORY line of been reviewed for Attachment 1.
completeness and compliance with Technical Specification *operator identifies that 4.8.3.1, 4.8.3.2, or 4.8.1.1.1.a Technical Specification 3.8.1.1.c.
and the test is considered: applies.
2.1.2 UNSATISFACTORY AND IF necessary the TIS ACTION statement has been implemented.
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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: ZZ022 NAME:
REV NUMBER: 01 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 4of24
JOB PERFORMANCE MEASURE JPM NUMBER: ZZ022 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ022 REV#: 01 TASK: Ensure Plant Operations Are In Accordance With Technical Specifications x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 HC.OP-ST.ZZ-0001(Q)
EXAMINER'S COPY 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.
Signature Current Date-Time SM/CRS Date-Time 1.1.3. Order No.
Unsatisfactory due to 20X supplying both Station Service Transformers AX501 and BX501.
Technical Specification 3.8.1.1, ACTION c applies.
Hope Creek Page 10 of 46 Rev.36 Page 7of24
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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. (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 PSEG NUCLEAR L.L.C. Page 1 of 1 HOPE CREEK GENERATING STATION HC.OP-ST.ZZ-0001(Q) - Rev. 36 POWER DISTRIBUTION LINEUP - WEEKLY USE CATEGORY: I
- Packages and Affected Document Numbers incorporated into this revision:
CP No. CP Rev. AD No. Rev No. None ../
- The following OPEX were incorporated into this revision: None
- The following OTSCs were incorporated into this revision: None REVISION
SUMMARY
20596049
- 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
HC.OP-ST.ZZ-0001 (Qt TRAINING ONLY 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 ONLy HC.OP-ST.ZZ-0001 (Q) 1.0 PURPOSE The purpose of this procedure is to ensure the Class 1E 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
HC.OP-ST.ZZ-0001 (Q}
TRAINING ONLY 5.0 PROCEDURE 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 1E Bus voltages) may be checked by local or remote indication, GRIDS, and/or proper equipment operation. 4.16KV 1E 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 1E Bus voltages as defined in note associated with 4.16KV 1E 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 1OA401
- 4.16KV SWITCHGEAR 1OA402
- 4.16KV SWITCHGEAR 1OA403
- 4.16KV SWITCHGEAR 1OA404
- OFFSITE TO ONSITE DISTRIBUTION (continued on next page)
Hope Creek Page 7 of 46 Rev.36
- 1 TRAINING ONLy 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
HC.OP-ST.ZZ-0001 (Q)-
TRAINING ONLY The line-up provided in Attachment 2 verifies that the Class 1E 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 NIA R 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 Rev.36
j I TRAINING ONLy HC.OP-ST.ZZ-0001 (Q) 6.0 RECORDS 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, 1Oa, 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
- CM-HC-2011-0818, HC License Amendment 188, EOG A and B Allowed Outage Time Extension Hope Creek Page 7 of 46 Rev.36
HC.OP-ST.ZZ-0001 (Q}
TRAINING ONLY 7.3 Other Documents
- 80054115
- 80058456
- 70038194, Non conservative 4.16 KV 1E bus voltage values Engineering Evaluation H-1-PB- EEE-1832, Revision 3 (Associated with 70038194)
- 70038770, Excessive Voltage on 1E buses
- 70040516, Attachment 2 readings and clarifying notes associated with 1OA401
( 1OA402, 1OA403, 1OA404) 4KV 1E 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 1BX501 Load Tap Changer (LTC) Setpoints Adjusted IAW 20240642 and 20240460 Hope Creek Page 7 of 46 Rev.36
HC.OP-ST.ZZ-0001 (Q)
- 1 TRAINING ONLY 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 Initials NOTE For an extended outage on A or B EDG, refer to Step 5.4.1. J 1.1.2. 4.8.1.1.1.a ONLY J (SEE Step 5.4) Initials 1.1.3. Retest/Other Initials 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
HC.OP-ST.ZZ-0001 (Q)
TRAINING ONLY 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
HC.OP-ST.ZZ-0001 (Q)
- 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) 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 T~-NC',11 Hope Creek Page 10 of 46 Rev.36
HC.OP-ST.ZZ-0001 (Q)
TRAINING ONLY 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
- EOG AG400 OUTPUT BKR 40107 TO 10A401 OPEN CIT) (uNSAT R 40108 NORMAL FEEDER BKR CLOSED TO BUS 1OA401 x SAT R 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)
-~~~~rc1RCLEONE:-~f]?f~~1----~;,~-rs~~-T~
- 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)
--~6~:~?-~~;~:~-~r C_l_R_CiE-ONE~----~;~~~s~-~~~~fi~-;--T----~-~~~£~~~v~~------r *
- 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, 1BX501) 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
HC.OP-ST.ZZ-0001 (Q)
TRAINING ONLY ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY Page 9 of 33 1.0 Power Distribution Lineup (Continued)
SAT/
EQUIPMENT NOMENCLATURE REQUIRED ACTUAL PERF UNSAT CHANNEL C 4.16KV SWGR 1OA403 40301 ALTERNATE FEEDER BKR OPEN 0 SAT R TO 10A403 40303 1OA403 FEED TO 108470 CLOSED x SAT R
- 40307 EOG CG400 OUTPUT BKR OPEN 0 SAT R TO 10A403 40308 NORMAL FEEDER BKR TO CLOSED 10A403 x SAT R 40310 1OA403 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) -
--~ ~:~~-~~~:~-~r--------ciRCL-E--ON_E_=----~l~~~s~~~=~~) ---r--~-~-~~~~~~~3; ~-~----r-----~;~~-------r-----~~~------r----~-----
6 5 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)
--~6~:~~-~~~:~-:r----------ciRCL-E--ON_E_: ~l~~~s;~~~~~~~;---l---~-~-F~~-~~~3;~-~----~ - *
- 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 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, 1BX501) 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 1BX501: A3210, A3487, A7076, A7071)
Hope Creek Page 19 of 46 Rev.36
HC.OP-ST.ZZ-0001 (Q)
TRAINING ONLY ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY Page 12 of 33 1.0 Power Distribution Lineup (Continued)
SAT/
EQUIPMENT NOMENCLATURE REQUIRED ACTUAL PERF UN SAT CHANNEL B 4.16KV SWGR 1OA402 40201 NORMALFEEDERBKRTO CLOSED 10A402 x SAT R 40203 1OA402 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 1OA402 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)
~6~:~10- CiRCLEONE;---~1~~~s~--~~~?f~::~~I.:*1~;;~1~~~--~-
- 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)
--~6~:~y~~;i:::r----------ciRCLE--ON_E_~---~l~~~s~~~~~r-~~~---T---~~-~~i~~~~3;1-~-----~-----~ *
- 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 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, 1BX501) 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 ONLy 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)
SAT/
EQUIPMENT NOMENCLATURE REQUIRED ACTUAL PERF UN SAT CHANNEL D 4.16KV SWGR 1OA404 40401 NORMAL FEEDER 8KR CLOSED TO 10A404 x SAT R 40403 1OA404 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 1OA404 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)
--~6~:~?-~~;f:-~:r----------ClRCL-E--ON_E_;---~~~~s~=-r---~~~~j~~~~3jf.-~----r-----~~~-~------T-----~-~~------r----;-----
- 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)
--~-6~:~?-~~~:::r----------ClRCL-E--ON_E_;---~l~~~s:2~~~~i~~----r--~-~~~i~-~~~3;5~-~----- *
- 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 adjusted~ MAX, GENERATE notification to Hope Creek Electrical/ l&C, System Engineering documenting each voltage operating limit violation (start & stop times), so that 4.16 KV System Engineer can track and analyze voltage levels, IAW Notification 20184742. [70038770]
(6) 4.16 KV Buses supplied from a common Station Service Transformer (1AX501, 1BX501) have the same voltage and associated CRIDS points should read the same discounting instrument loop inaccuracies. If in normal 2 bus (or less) alignment, any of the following CRIDS points are considered equivalent and may be substituted for any other if one or more is a failed indicator: (For 1AX501: A3209, A3484, A7061, A7066) (For 1 BX501: A3210, A3487, A7076, A7071)
Hope Creek Page 25 of 46 Rev.36
HC.OP-ST.ZZ-0001 (Q)
TRAINING ONLY ATTACHMENT 2 INPLANT DATA SHEET POWER DISTRIBUTION LINEUP - WEEKLY Page 24 of 33 1.0 Power Distribution Lineup (Continued)
SAT/
EQUIP NOMENCLATURE REQUIRED ACTUAL PERF I UN SAT OFFSITE TO ONSITE DISTRIBUTION +
BS4-5 13KV BUS SECTION 4-5 BKR CLOSED x SAT R
- BS6-7 13KV BUS SECTION 6-7 BKR CLOSED x SAT R
- 2T60 STAXFMR T2 CIRCUIT SWITCHER CLOSED x SAT R
- BS3-4 500KV BUS SECTION 3-4 BKR CLOSED x SAT R
- BS6-5 500KV BUS SECTION 6-5 BKR CLOSED x SAT R
- BS7-8 13KV BUS SECTION 7-8 BKR OPEN 0 SAT R
- f BS2-3 13KV BUS SECTION 2-3 BKR OPEN '-... x ) :_uNsAi) R
- r ::---,
BS1-2 13KV BUS SECTION 1-2 BKR CLOSED IC 0 ) ,UNSAT,.., R
- BS9-0 13KV BUS SECTION 9-10 BKR CLOSED x SAT R *
~
1T60 STA XFMR T1 CIRCUIT SWITCHER CLOSED
\.
0 ) rUNSAT""'
'- ./
R
- 3T60 STA XFMR T3 CIRCUIT SWITCHER CLOSED I'
\...._ 0 ) ~UNSAT) R
- BS1-3 500KV BUS SECTION 1-3 BKR CLOSED IC 0 ) : UNSAV R
- BS5-1 500KV BUS SECTION 5-1 BKR CLOSED x SAT R
- BS2-6 500KV BUS SECTION 2-6 BKR CLOSED x SAT R
- BS2-4 500KV BUS SECTION 2-4 BKR CLOSED x SAT R
- Step Salem Unit 3 Gas Turbine Generator SAT#
- N/A N/A N/A 5.4.1.B
+ 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 1E 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
JOB PERFORMANCE MEASURE STATION: Hope Creek COPY OF SYSTEM: Administrative TASK NUMBER: 2992470102 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 SRO~
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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 1a 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 RM-11 (9AX327) Operator observes Fl (Failed 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 FLOW), FOR EVAPORATIVE *operator determines correct 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: ZZ050 NAME:
~~~~~~~~~~~~-
REV NUMBER: 01 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 6of12
JOB PERFORMANCE MEASURE JPM NUMBER: ZZ050 REVISION HISTORY Validation Rev# Date Description Required?
01 10/31/2014 Revised format. Updated procedure reference. Validated with 2 y*
SROs. Validation Time 10 minutes.
Page 7of12
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ZZ050 REV#: 01 TASK: Ensure Plant Operations are in Compliance with ODCM (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow) x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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
JOB PERFORI\. .NCE MEASURE 1- - EXAMINER'S COPY I HC. OP-OLZZ-0026(Q)
ATTACHMENT 3y P§9e1 of1 Radioactive Liquid Effluent Monitoring Instrumentation TIS 6.8.4.Q OOCM Table 3.3.7.10-1Item3b, ACTION 112 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to ensure that the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Tech Spec Action limit is NOT exceeded per 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 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} I 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* = TOTAl WEIR FLOW NOW 13560 .. 21345 = 34905 - 4-6700 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 Rev.141 Page 9of12
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 1a, ITEM 47, Day Shift reading, AND Attachment 3y for the inoperable RMS Cooling Tower Slowdown Weir Flow Rate Monitor.
Page 10of12
HC.OP-DLZZ-G026(Q)
I- TRAINING ONLy I ATTACHMENT 1a Page 10of18 Surveillance Log - Control Room Operational Condition 1 Date TODAY ITEM SURVEILLANCE OPER ACCEPTABLE LIMITS INSTRUMENT {PANEL) DAY EVE MID COMMENTS MIN NORM MAX COND 47 CHANNEL CHECK: COOLING TOWER BLOWDOYm WEIR FLOW RATE MONITOR AT ALL TIMES ITEM 002 <40K 70K OSP-Rl486t ITEM029 RM-11 {QAX327)
(tOC604)
(NOTE 45.j 0J "'
.1JTSAS 2015-001 See Attachment 3Y
- NO - INST TRIPPED ( Fl ~ {NOTE 33 .* 35~ 46.* 47 .)
43 CHANNEL CHECK: COOLING AT ALL - - ITEM SP-Rl88H \10C604) 'iilTA' WA {NOTE 30~ 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 WA NIA (NOTE30.)
TBCW RADIATION MONITOR TIMES OR RM-11 {9RX5D5) 1.1E-6 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) {NOTE30.)
LOOP A RADIATION MONITOR TIMES RM-11 {!GRX501) 3.2E-7 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.
- 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 {HOURlY) 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 DATE AND TIME UNDER 'ENTER START TIME" TO AT LEAST 12 HOURS AGO (ONtY 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 DATA. [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 Rev. 141 Page 11of12
HC.OP-OLZZ-0026(Q)
I TRAINING ONLY I Page 1of1 ATTACHMENT 3y Radioactive Liquid Effiuent Mooitoring Instrumentation T/S 6.8.4.Q ODCM Table 3.3.7.10-1Item3b. ACTION 112 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to ensure that the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Tech Spec Action 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 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) I TIME A) - CRIDS POINT A9327 (CTB BLOWDOWN DtSCH FLOW)
B) - RM-11, 9RX599 (PROCESS FLOWN)
C} - 1OC604 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 * = TOTAL 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 FLOW~ 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 GAUMIN~ ON THE MONITOR DISPLAY.
Hope Creek Page 100of105 Rev.141 Page 12of12
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 STA~ SRO~
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 1OC673:
- 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 subcategory beginning with Operator determines that HA 1.1, 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT STANDARD UNSAT)
- 8. When the Shift Manager Operator requests STA/IA (SM) is the Emergency verification of classification.
Coordinator, the Shift Technical Advisor (STA) is Examiner Note: Due to time spent responsible to perform an assessing and/or nature of JPM independent verification of administration, Operator may not the EAL classification. The request verification.
STA verification does not alleviate the requirement of the SM to make a timely classification. Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO, 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.
Implement EP-
- Unusual Event HC-111-F1 Implement EP-
- Alert 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 ICMF,
- DECLARE the SITE 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 START TIME and the "DECLARED AT" TIME is the first critical time (15 min).
Time:
Page 7of14
JPM NUMBER: ECG007 NAME: ~~~~~~~~~--~~~~~*
REV NUMBER: 10 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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 Emergency Callout Activation and
- If not previously 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:
~---- ------
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: ECG007 NAME:
~~~~~~~~~~~~-
REV NUMBER: 10 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 10of14
JOB PERFORMANCE MEASURE JPM NUMBER: ECG007 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: ECG007 REV#: 10 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 EP-HC-111-F3 EXAMINER'S ATT3 COPY 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_)__ -----(D_A_T-E)---~
EAL# CS
3.1 DESCRIPTION
OF EVENT:
~-----------------
LOSS OF REACTOR PRESSURE VESSEL INVENTORY AFFECTING CORE DECAY Arly release llL 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 INITIALS EC Initials (Approval to Transmit ICMF)
HCGS Rev_0:3 EXAMINER'S COPY Page 13of14
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 1OC673:
- 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.
-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 COPY OF SYSTEM: Reactor Protection System TASK NUMBER: 2120030101 TASK: Reset A Reactor Scram JPM NUMBER: 305H-JPM.SB013 [JPM A] REVISION: 05 SAP BET: NOH05JPSB13E K/A NUMBER: 212000 A4.14 IMPORTANCE FACTOR: RO: 3.8 SRO: 3.8 ALTERNATE PATH: ~
APPLICABILITY: EO D RO~ STAD SRO~
EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
HC.OP-SO.SB-0001 Rev. 34 TOOLS, AND EQUIPMENT: None ESTIMATED COMPLETION TIME: - - - 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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.
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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 have settled into notch *operator attempts to verify all 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: SB013 NAME:
~~~~~~~~~~-
REV NUMBER: 05 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 8of13
JOB PERFORMANCE MEASURE JPM NUMBER: SB013 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: SB013 REV#: 05 TASK: Reset A Reactor Scram x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 05 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 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 Event code: (rp_k14a & rp_k14c) I (rp_k14b & rp_k14d)
Description:
Y2 RPS Reset Event code: lcvposb( 154) >= 16 2
Description:
Rod 38-47@ position 01 Initial @Time Event Action Description None None Insert malfunction CD023847 on event 1 Control Rod 38-4 7 drift out Insert malfunction CD023847 on event 2 None None Control Rod 38-4 7 drift out delete in 1 Page 11of13
JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Initial @Time Event Action Description Initial @Time Event Action Description Insert override 3A81_Q_LO after 1 to Off on ROD SELECT - ROD MOTION - INSERT None None event 1 delete in 3 (LO}
ROD SELECT - ROD MOTION - INSERT None None Insert override 3A81_Q_LO to Off (LO)
Insert override 3A81 I DI to On on event 1 ROD SELECT - CONTINUOUS INSERT None None delete in 1 (DI)
ROD SELECT - ROD MOTION CONTROL -
None None Insert override 3A81_R_LO to Off WITHDRAW (LO}
Insert override 3A81_R_LO to Off on event ROD SELECT - ROD MOTION CONTROL -
None None 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 COPY OF SYSTEM: Reactor Water Cleanup System TASK NUMBER: 4000760401 TASK: Respond To A Containment Isolation JPM NUMBER: BG003 [JPM B] REVISION: 00 SAP BET: NOH05JPBG03E K/A NUMBER: 204000 A2.13 IMPORTANCE FACTOR: RO: 3.4 SRO: 3.4 ALTERNATE PATH: D APPLICABILITY: EO D RO~ STAD SRO~
EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
HC.OP-AB.CONT-0002 Rev. 12 TOOLS, EQUIPMENT: None 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.
- 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT UNSAT)
STANDARD
- 2. ENSURE HV-F044, Filter Operator ensures HV-F044, Filter Demin Bypass valve is Demin Bypass valve is CLOSED.
CLOSED.
- 4. ENSURE at least one RACS Operator ensures at least one Pump is in service. RACS Pump is in service.
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.
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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 5 of 9
JOB PERFORMANCE MEASURE JPM NUMBER: BG003 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BG003 REV#: 00 TASK: Respond To A Containment Isolation x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 Final Initial Malfunction Description Event Delay Ramp Value Value REMOTE
SUMMARY
Initial Final Initial Remote Description Event Delay Ramp Value Value 1/0 OVERRIDE
SUMMARY
Initial Final Initial Override Description Event Delay Ramp Value Value EVENT
SUMMARY
Initial Event Override
Description:
Event Code:
Page 8of9
JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- 1. RPS Bus B power was lost.
- 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 COPY OF SYSTEM: Control Rod Drive TASK NUMBER: 4000060401 TASK: Respond to a Loss of CRD Regulating Function 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 RO~ STAD SRO~
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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 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:
- Operator presses the PB for A. Selected rod PB comes ON 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 OBSERVE the following: AND initials Step.
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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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.
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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 is applicable and takes Corrective
- 3. Complete loss of Drive Actions.
Water Pumps A and B CORRECTIVE ACTION Operator refers to HC.OP-AB.IC-3A.REFER to HC.OP-AB.IC- 0001 (Q); Control Rod.
0001(0); 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: BF012 NAME: ~~~~~~~~~~-
REV NUMBER: 08 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD UNSAT)
CUE: Acknowledge report of CRD Accumulator Trouble alarms.
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
- operator locks the Mode INOPERABLE.
Switch in SHUTDOWN ACTION AND implements HC.OP-AB.ZZ-IA. LOCK Mode Switch in 0001, Attachment 1.
SHUTDOWN. [T/S 3.1.3.5.a.3] [CM-HC-1982- Examiner Note: If the Mode 108] 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."
HC.OP-AB.ZZ-0001 Att. 1 N/A N/A N/A 1.0 ANNOUNCE "Crew - Standby Operator announces "Crew -
for Scram Report". Standby for Scram Report".
Examiner Note: If the Mode Switch is already in SHUTDOWN, provide the Terminating Cue.
2.0 LOCK the Mode Switch in Operator locks the Mode Switch in Shutdown. SHUTDOWN.
Examiner Note: If the Mode Switch is now in SHUTDOWN, provide the Terminating Cue.
Page 7 of 7
JPM NUMBER: BF012 NAME:
------~--
REVNUMBER: 08 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: BF012 NAME:
REV NUMBER: 08 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 9of9
JOB PERFORMANCE MEASURE JPM NUMBER: BF012 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BF012 REV#: 08 TASK: Respond to a Loss of CRD Regulating Function x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk(*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 lfJITIAltt~ONDfTIONS: -
- ~\~1,ift*'
- tr>
"'";:~;. }:$:;,:~fif) "" . . ' *:t"!°?:\), \<_ ., _ :.s~**
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 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?">"'"' ' ., *~*
Initial @Time Event Action Description Insert malfunction CD1 OA after 15 on event None None CRD hydraulic pump A trip 1
Insert malfunction CD054223 after 25 on None None Control Rod 18-43 accumulator trouble event1 Insert malfunction CD053059 after 35 on None None Control Rod 02-39 accumulator trouble event 1 Insert malfunction CD050239 after 45 on None None Control Rod 42-23 accumulator trouble event1 None None Insert malfunction CD10B on event 2 CRD hydraulic pump B trip Page 12of12
JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Initial @Time Event Action Description Initial @Time Event Action Description Page 13of13
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
JOB PERFORMANCE MEASURE OP-AB-300-1003 J!JlopeCreek)
. .GENERATING STATION./
TRAININIG ONLY Revision 11 Page 15of15 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1of2 TITLE OF MANEUVER: STARTUP REMA 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: """"Jo""""h-'-'-n"'--S~m=it"""'"h_ _--=-T..::;...od=.;a~y Reviewed by: Pete Jones Today Reactor Engineer Date Qualified Nuclear Engineer Date Approved by: Rick Thompson Today Authorized by: _B_ill_W_il_lia~m_s_ _ _ _ _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_ _ _ _ _ _T_o_d_a~y 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
JOB PERFORMANCE MEASURE OP-AB-300-1003 TRAININIG ONLY Revision 11 Page 16of16 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 2of2 Maneuver Steps
- 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
JOB PERFORMANCE MEASURE OP-AB-300-1003 TRAININIG ONLY Revision 11 Page 17of17 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 1of3 Reactivity Maneuver Plan # 0005 Description of Maneuver Step: Raise CTP to 9% RTP.
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:
- 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: RO: 3.4 SRO: 3.6 ALTERNATE PATH: D APPLICABILITY: EO D RO~ STAD SRO~
EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
HC.OP-SO.GK-0001, Rev. 22 TOOLS, AND EQUIPMENT: None 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:
~--~-------
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 1AVH403 and 1BVH403 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:
REV NUMBER:
GK003 00 NAME:
DATE:
~
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 BV415 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 SUPPLY FAN *#Operator presses the BVH403 A(B)VH403 START PB START PB, (A(B)VH403 START is observes that START 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:
REV NUMBER:
GK003 00 NAME:
DATE:
{*Critical Step) COMMENTS STEP SAT/
ELEMENT {#Sequential Step) (Required for NUMBER UNSAT 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.
1EC485):
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 1BVH407 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 FAN AVH407, initials Attachment
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:
REV NUMBER:
GK003 00 NAME:
DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fa' NUMBER UNSAT STANDARD UNSAT)
B. PERFORM the following: *#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 START 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 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: GK003 NAME:
~~~~~~~~~~~~~
REV NUMBER: 00 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 7of11
JPM NUMBER: GK003 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: GK003 REV#: 00 TASK: Place The Control Equipment Room Supply System In-Service x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 00 Initial INITIALIZE the simulator to 100% power MOL.
Initial Descri tion 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 COPY OF SYSTEM: Containment Atmosphere Control TASK NUMBER: 4000510401 TASK: Respond To Rising Drywell Pressure JPM NUMBER: 305H-JPM.GS011 [JPM E] REVISION: 00 SAP BET: NOH05JPGS11 E K/A NUMBER: 295010AA1.05 IMPORTANCE FACTOR: RO: 3.1 SRO: 3.4 ALTERNATE PATH: D APPLICABILITY: EO D STAD SRO C8J EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
HC.OP-AB.CONT-0001, Rev. 3 TOOLS, AND EQUIPMENT: None ESTIMATED COMPLETION TIME: - - 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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.
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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:
- operator closes HV-4951,
- a. CLOSE the following:
and initials Step.
- 1. HV-4951
- 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.
and initials Step.
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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: GS011 NAME:
~~~~~~~~~~~~~
REV NUMBER: 00 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 5of9
JOB PERFORMANCE MEASURE JPM NUMBER: GS011 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: GS011 REV#: 00 TASK: Respond To Rising Drywell Pressure x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: _:::3.0 (LOR); or _:::2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk(*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 00
- 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 Description
. REMOTE sc~~BOLB.
Initial @Time Event Action Description Initial @Time Event Action Description Page 8of9
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 COPY OF SYSTEM: Safety Auxiliaries Cooling Water TASK NUMBER: 4000780401 TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 follows:
A.1 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:
REV NUMBER:
~~~
EG008 09
~~~~
NAME:
DATE: '
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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:
Operator presses the
- a. PRESS GEN VR 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 NAME:
REV NUMBER: 09 DATE:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD UNSAT)
- d. STOP the EOG. *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.
- ENSURE Control Room Operator observes the Control Chilled Water is aligned to Room Ventilation and Chilled the unaffected loop.(GJ) Water Train A is in service, and initials Step.
- ENSURE TSC Chilled Operator observes the TSC Water is aligned to the Ventilation and Chilled Water Train unaffected loop.(GJ) A is in service, and initials Step.
- DECLARE the loop Operator informs CRS SACS Loop inoperable, AND B should be declared inoperable, IMPLEMENT Condition K and Condition K should be implemented, and initials Step.
Examiner Note: It is not necessary for the Operator to perform any Condition K actions.
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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: EG008 NAME:
REV NUMBER: 09 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 6of11
JOB PERFORMANCE MEASURE JPM NUMBER: EG008 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: EG008 REV#: 09 TASK: Respond To A Safety Auxiliaries Cooling Water Malfunction x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.}
x 14. Validation time is included.
x 15. 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
JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Initial @Time Event Action Description None None Insert malfunction QQ13 to short on event 1 SACS pump BP210 trip Insert malfunction QQ15 to short on event 2 None None SACS pump DP210 trip after 3 REMOTE Initial @Time Event Action Description Initial @Time Event Action Description Insert override 5A29_A1_LO to On on event BP210 OVLD/PWR FAIL-LOOP B PUMPS-None None 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 COPY OF SYSTEM: Main Turbine TASK NUMBER: 2450100101 TASK: Roll the Main Turbine to Rated Speed JPM NUMBER: 305H-JPM.AC007 [JPM G] REVISION: 03 SAP BET: NOH05JPAC07E 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 SRO 1:8:1 EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
HC.OP-SO.AC-0001, Rev. 69 TOOLS, AND EQUIPMENT: None ESTIMATED COMPLETION TIME: - - 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT STANDARD UNSAT)
B. VERIFY the following: Operator verifies that all CV's, IV's and MSV's are closed, and initials
- All CV's, IV's and 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 1OC363 is D5, EHC Panel 1OC363 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:
AND observes the following:
- MSV#2 opens 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 Validation Rev# Date Description Required?
03 11/7/2014 Complete re-write. Validated with RO and SRO. Incorporated y comments. Validation time 10 minutes.
Page 7of10
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: AC007 REV#: 03 TASK: Roll the Main Turbine to Rated Speed x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (KIA) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 03 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.
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 Insert malfunction TC02-2 from 1.00000 to None None Turbine control valve CV-2 failure 2.00000 on event 1 Insert malfunction TC02-3 from 1.00000 to None None Turbine control valve CV-3 failure 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 COPY OF SYSTEM: System Name TASK NUMBER: 4001570401 TASK: Respond to a Reactor Recirculation Pump Runback 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 SRO [8J EVALUATION SETTING/METHOD: Simulator/Perform
REFERENCES:
HC.OP-SO.BB-0002, Rev. 100 HC.OP-AB.RPV-0004, Rev. 10 TOOLS, AND EQUIPMENT: None ESTIMATED COMPLETION TIME: - - - 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 performing the following: *#Operator reduces CRIDS 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 concurrently if 5.4.2 was performed A. INTMD RUNBACK RESET for both Recirc Pumps, or can be push button performed individually.
- 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT STANDARD UNSAT) 5.4.2 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 *#operator reduces CRIDS performing the following: STR087(086), RECIRC: SPEED B. REDUCE GRIDS STATION B(A) OUTPUT, by STR086/087, RECIRC: pressing the DECREASE push SPEED STATION A(B) button on SIC-R621 B(A) 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 STR087(086) is less than OR A(B) SPD CONT until the equal to the SPEED DEMAND on SPEED STATION SIC-R621 B(A) PUMP B(A) SPD OUTPUT on GRIDS CONT, STR086/087 is less than and initials Step.
OR equal to the SPEED DEMAND on SIC-R621 Examiner Note: Approximately A(B) PUMP A(B) SPD 46%.
CONT.
5.4.3 PRESS the following for *#operator presses Reactor Reactor Recirc Pump A(B): Recirc Pump B(A) INTMD C. INTMD RUNBACK RESET RUNBACK RESET push button, push button and initials Step.
D. FULL RUNBACK RESET Operator depresses the FULL push button RUNBACK RESET push button and initials step, OR determines and marks Step as N/A.
CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.
REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".
STOP TIME: - - - - - - -
Task Standard: Operator resets the Reactor Recirculation Runbacks in accordance with HC.OP-SO.BB-0002.
Page 5of10
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: 88001 NAME:
REV NUMBER: 09 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 6of10
JOB PERFORMANCE MEASURE JPM NUMBER: 88001 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BB001 REV#: 09 TASK: Respond to a Reactor Recirculation Pump Runback x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 REV#: 09 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 Description Initial @Time Event Action Description Initial @Time Event Action Description Page 9of10
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 COPY OF SYSTEM: Control Rod Drive Hydraulic TASK NUMBER: 2010080104 TASK: Shift In-Service CRD Flow Control Valves JPM NUMBER: 305H-JPM.BF001 [JPM I] REVISION: 16 SAP BET: NOH05JPBF01 E K/A NUMBER: 201001 A2.07 IMPORTANCE FACTOR: RO: 3.2 SRO: 3.1 ALTERNATE PATH: D APPLICABILITY: EO ~ RO~ STAD SRO~
EVALUATION SETTING/METHOD: Plant/Simulate
REFERENCES:
HC.OP-SO.BF-0001, Rev. 33 TOOLS, AND EQUIPMENT: None ESTIMATED COMPLETION TIME: - - 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 1BF-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 1BF-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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: BF001 NAME:
~~~~~~~~~~~~~
REV NUMBER: 16 DATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 7of10
JOB PERFORMANCE MEASURE JPM NUMBER: BF001 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: BF001 REV#: 16 TASK: Shift In-Service CRD Flow Control Valves x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 COPY OF SYSTEM: Primary Containment Instrument Gas TASK NUMBER: 4000340401 TASK: Respond To An Instrument Gas Malfunction 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 STAD SRO 1:8:1 EVALUATION SETTING/METHOD: Plant/Simulate
REFERENCES:
HC.OP-AB.COMP-0002, Rev. 8 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 *#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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fo NUMBER UNSAT 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 from cabinet 1C-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 4-2-1-4. (Cabinet 1C-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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: KL006 NAME:
REV NUMBER: 00 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 5 of 9
r JOB PERFORMANCE MEASURE JPM NUMBER: KL006 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: KL006 REV#: 00 TASK: Respond To An Instrument Gas Malfunction x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk(*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 1DC653 FRONT FRONT I 1CC658 1CC653 DN FRONT I 1BC658 1BC653 1AC658 1AC653 FRONT FRONT I 1CC654 1EC654 1BC654 1DC654 I 1FC654
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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 COPY OF 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] REVISION: 00 SAP BET: NOH05JPPN04E K/ANUMBER: 2.1.30 IMPORTANCE FACTOR: RO: 4.4 SRO: 4.0 ALTERNATE PATH:~
APPLICABILITY: EO ~ RO~ STAD SRO~
EVALUATION SETTING/METHOD: Auxiliary Building/Simulate
REFERENCES:
HC.OP-SO.PN-0001, Rev. 24 TOOLS, AND EQUIPMENT: None ESTIMATED COMPLETION TIME: - - - 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 1DD481.
- 2. Plant conditions are satisfactory for this work.
INITIATING CUE:
REMOVE the 1DD481 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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 1BD492) 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 *#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) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fc NUMBER UNSAT 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) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required for NUMBER UNSAT 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:
(*Critical Step) COMMENTS STEP SAT/
ELEMENT (#Sequential Step) (Required fa NUMBER UNSAT 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
OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION JPM NUMBER: PN004 NAME:
REV NUMBER: 00 0 ATE:
QUESTION:
RESPONSE
RESULT: SAT D UNSAT D QUESTION:
RESPONSE
RESULT: SAT D UNSAT D Page 7of10
JOB PERFORMANCE MEASURE JPM NUMBER: PN004 REVISION HISTORY Validation Rev# Date Description 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
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: PN004 REV#: 00 TASK: Remove A 120 VAC Electrical Distribution System From Service x 1. Task description and number, JPM description and number are identified.
x 2. Knowledge and Abilities (K/A) is identified, and is: ~3.0 (LOR); or ~2.5 (IL T); or justification is provided.
x 3. License level identified. (SRO,RO,STA,NLO) x 4. Performance location specified (In-Plant, Control Room, Simulator, or Classroom).
x 5. Initial setup conditions are identified.
x 6. Initiating and terminating cues are properly identified.
x 7. Task standards for successful completion are identified.
x 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence Critical Steps are identified with a pound sign (#).
x 9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.
x 10. Procedure(s) referenced by this JPM match the most current revision of that procedure.
x 11. Cues both verbal and visual are complete and correct.
x 12. 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.
x 13. Statements describing important actions or observations that should be made by the operator are included (if required.)
x 14. Validation time is included.
x 15. 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 HC.OP-SO.PN-0001.
Page 10of10
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training SIMULATOR COPY - - OF - -
EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 2015 NRC EXAM SCENARIO SCENARIO NUMBER: ESG-1 EFFECTIVE DATE: Effective When Approved EXPECTED DURATION: 75 Minutes REVISION NUMBER: 1 PROGRAM: 0 LICENSED OPERATOR REQUALIFICATION iZ! INITIAL LICENSE D OTHER:
REVISION
SUMMARY
- 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 1E 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 1E 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 1OA 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 HC.OP-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 Event Code: zarrs621 (6) > 0.67 & zdrrs621 (6) 1
Description:
RR B speed >67% and Raise PB pressed Event Code: zcrpsudn >= 1 4
Description:
Reactor Mode Switch in Shutdown Event Code: D2015_V 5
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 RRCS Channel A - Logic A Failure to None None Insert malfunction RZ03A Auto Initiate RRCS Channel B - Logic A Failure to None None Insert malfunction RZ03C Auto Initiate None None Insert malfunction RP04 Failure of RPS to SCRAM (ATWS)
Loss of 120 VAC class 1E inst bus None None Insert malfunction E00902 on event 2 100482 Insert malfunction RR31A1 to 100.00000 Recirc loop A small break [V] (10%-60 None None in 1200 on event 4 gpm, 100%-600 gpm)
Insert malfunction RR31 A2 after 600 to Recirc loop A large break [VJ (10%-6000 None None 1.00000 in 300 on event 4 gpm, 100%-60000 gpm)
Insert malfunction FW30A after 5 on None None Heater 2A hi level switch failure event 5 Insert malfunction FW30B after 10 on None None Heater 28 hi level switch failure event 5 Insert malfunction FW30C after 3 on None None Heater 2C hi level switch failure event 5 I REMOTE SCHEDULE:
Initial @Time Event Action Description None None Insert remote HV06 to STOP on event 3 HV06 RBVS Supply fan C Insert remote HV05 after 1 to STOP on None None HV05 RBVS Supply fan B event 3 Insert remote HV04 after 1 to STOP on None None HV04 RBVS Supply fan A event 3 Insert remote HV03 after 2 to STOP on None None HV03 RBVS Exhaust fan C event 3 Insert remote HV02 after 2 to STOP on None None HV02 RBVS Exhaust fan B event 3 Insert remote HV01 after 3 to STOP on None None HV01 RBVS Exhaust fan A event 3 Insert remote AN24 after 5 to NORM on AN24 E6-C5 RBVS & Wing Area HVAC None None 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 Insert override 3A46 C DI to On on SIC-R621 B RAISE-REC IRC PUMP B None None event1 (DI)
HV-1625 OPEN-BYPASS HEATERS None None Insert override 5A159_C_DI to Off 1&2 ORN CLEAR (DI)
HV-1625 RAISE-BYPASS HEATERS None None Insert override 5A159_D_DI to Off 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 Expected Plant/Student Event / Instructor Activity Comments
Response
=> PRESS the INCREASE j PEERCHECK0 or DECREASE t push FLAGGING D button on the Pump as OP BARRIERS 0 necessary, to equalize the "DEMAND" signals, WHILE MONITORING the INPO Fundamentals:
following: D Monitoring plant
- RFPT Discharge conditions and Pressure indications closely.
- RFPT "DEMAND" D Having a solid
- RFPT "FLOW" understanding of plant
=> WHEN FLOW and SPEED design and system are approximately equal, interrelationships.
TRANSFER RFPT C SPEED CTRLR to automatic by pressing the A pushbutton AND observing "A" illuminates.
ROLE PLAY as Reactor
Engineer for the Reactivity Brief.
RE guidance for power ascension is:
- Raise reactor power to 90%
RTP with core flow.
- Withdraw 1OA control rods from 00-6. (==4%)
- Do not exceed 1% per minute.
ESG-1 Page 6 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event I Instructor Activity Comments
Response
Raise Reactor Power with the
- CRS directs raising reactor Recirculation System 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.
MAINTAIN Recirc MG Oil temps
(Monitor Variables rrtoil(1) and directs maintaining Recirc MG D Monitoring plant rrtoil(2)) as directed using oil temperatures between 110- conditions and Remotes CW15 and CW16 as 130 degF. indications closely.
appropriate.
speeds obtaining Peer STARD Checks from PO IAW HU-AA- PEERCHECK0 101. FLAGGING 0
- RO observes effect on: OP BARRIERS 0
=> Reactor Power
=> Recirc Loop Flow
=> Recirc Loop Jet Pump Flow
=> Total Core Flow
and affected plant D Monitoring plant parameters. conditions and indications closely.
D Having a solid understanding of plant design and system interrelationships.
ESG-1 Page 7 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments Response I
- RO ensures Recirculation IO.ZZ-0006 loop flow mismatch is ST.BB-0001 maintained within:
~ 5% of rated core flow with effective core flow~ 70%
of rated core flow.
speed changes do not exceed Pump B speed changes the rpm limitations of should not exceed 10-20 SO.BB-0002. rpm with a wait of 1 to 2 minutes between changes.( 3.1.14)
- IF reactor power reaches 90% SO.BB-0001:
THEN RO informs CRS In extended steady state reactor power has been raised two loop operation it is to 90%. desirable to have Jet Pump Loop Flows approximately the same (within 1 mlbm/hr)
(3.2.17)
Recirculation Pump Runaway
- Crew recognizes Reactor INPO Fundamentals:
Recirculation Pump A D Monitoring plant Runaway will occur automatically runaway by: conditions and when RR Pump B speed demand ~ OHA C1-A5 "COMPUTER indications closely.
is 67%, OR at the discretion of POINT IN ALARM" the Lead Evaluator INSERT ET- ~ Reactor power rising
- 1. ~ 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
~ 1OC650C Recirc and Jet pump indications ESG-1 Page 8 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
- RO performs the following: Immediate Operator
=> Presses SCOOP TUBE Action IAW TRIP for 'B Recirc Pump AB.RPV-0001.
=> Reduces 'A' Recirc Pump speed to reduce power to HPI USED:
pre-transient value STARD PEERCHECK0 INPO Fundamentals:
D CONTROL
=> Condition F
=> Condition B may be referenced
- 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 INPO Fundamentals:
Pretreatment AND Main D Monitoring plant Steam Line Radiation conditions and Monitors for indications of indications closely.
Fuel Damage.
Crew MAY enter HC.OP-
AB.RPV-0008 due to a small rise
=> Condition A in Offgas Pretreatment radiation
=> Condition C may be levels.
entered ESG-1 Page 9 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
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
!E called as RE to determine
- Crew determines peak maximum thermal power thermal power during the reached, transient.
THEN REPORT thermal power peaked at approximately 90%(check GRIDS to ensure)
(3460 MWth).
- CRS recognize the following Must restore recirc loop Tech Specs/actions apply: flow mismatch within tvl
~ 3.4.1.3 Recirculation Loop hours or declare the B Flow loop not in operation.
INPO Fundamentals:
0 KNOWLEDGE
- CRS contacts Operations Management to initiate Prompt Investigation and ERT callout.
ESG-1 Page 10 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
Loss of 100482
- Crew recognizes loss of NOTE: OHA D3 E3 DD482 by observing: "120VAC UPS After Technical Specifications => OHA A7-C2, SACS TROUBLE" is NOT have been addressed, OR at the SUPPLY RHR PUMP D received on a loss of a discretion of the Lead Evaluator, TROUBLE, in alarm 482 inverter. 482 INSERT ET-2. => Both RWCU Pumps trip. inverter supplies the
=> RWCU Loss OHAs C1-C2, output to this alarm for
-D2, and -F2 its channel.
=> Loss of 1E DIV 2/Channel D analog instrumentation. INPO Fundamentals:
=> Loss of control and status D Monitoring plant indication for Non-ECCS conditions and Division 2/Channel B indications closely.
components.
=> RCIC, RHR D and Core Spray D will lose status indications ONLY.
=> GRIDS page 167
=> Assess all plant systems and enter appropriate Abnormal Procedures
=> Determine failed inverter
=> Condition B
ESG-1 Page 11 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity 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
- 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 1OC650E (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"
=> Condition A
=> Condition D
- Crew dispatches RBEO to 1OC382 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 Expected Plant/Student Event/ Instructor Activity Comments
Response
IF directed to secure RBVS,
THEN TRIGGER ET-3. IAW SO.GU-0001, or AB.ZZ- STARD 0001 Attachment 20. PEERCHECK0
=> 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 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to reenergize following Tech Specs actions panel and restore apply for the loss of DD482: inverter within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
=> Distribution - Operating or Hot SD in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.8.3.1 action a AND d and Cold SD in following 24.
ESG-1 Page 13 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
- Crew recognizes coolant leak: INPO Fundamentals:
=:> OHA C6-B1 "OLD D Monitoring plant After Technical Specifications SYSTEM ALARM/TRBL" conditions and have been addressed, OR at the =:> RM11 9AX314 OLD indications closely.
discretion of the Lead Evaluator, FLOOR ORN FLOW alarm INSERT ET-4. RPS failure is pre- =:> RM11 9AX317/318/320 inserted. 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
=:> Condition A
=:> Condition B
=:> Condition C
=:> Condition A
- RO/PO ensures drywell cooling maximized.
- Crew checks:
=:> Recirc pump seal parameters
=:> SRV temperatures
- WHEN the Crew determines INPO Fundamentals:
drywell pressure cannot be 0 CONSERVATISM maintained below 1.5 psig, THEN CRS directs:
=:> Reducing recirc pump A to minimum speed
=:> Locking the Mode Switch in SHUTDOWN ESG-1 Page 14 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
- RO: RPS will NOT cause a
=> Reduces recirc pump A to scram on ANY signals.
minimum speed STRATEGIES FOR SUCESSFUL => Locks the Mode Switch in TRANSIENT MITIGATION SHUTDOWN 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 JAW HC.OP-AB. ZZ-0001.
RPS Failure
- RO recognizes RPS failure, announces condition, and RPS failure is pre-inserted. initiates ARI IAW AB.ZZ-0001.
- After placing the Mode Switch in SHUTDOWN, the Crew manually initiates ARI to shut down the reactor.
ESG-1 Page 15 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
Below 12.5" EOP entry 0TEAMWORK condition by:
~ OHA C5-A4 "RPVWATER LEVEL LO"
~ OHA A 7-05 "RPV LEVEL 3"
~ Various water level indicators
Loss of Feedwater:
The 1&2 Feedwater heaters will trip by: D Monitoring plant
~ OHAA7-E2 conditions and isolate shortly after the Main "FEEDWATER HEATER indications closely.
Turbine Trip. ENSURE ET-5 activates. The bypass around the TRIP" 1&2 Feedwater heaters is failed ~ Flashing HTR TRIP lights shut. for FWH #2A/B/C
~ Condensate Inlet and Outlet valves stroking shut for FWH 1&2A/B/C.
- PO informs CRS of inability to inject with condensate.
~ 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.
ESG-1 Page 16 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
- WHEN Drywell Pressure reaches 1.68#, THEN Crew recognizes RFPT trips by:
=> OHA B3-E1 "RFP TURBINE TRIP"
=> RFPT Control Valve indications on 1OC650C
=> TRIP status light on RFPT bezels
=> RFPT discharge pressure indications on 1OC650C
=> Feed flow indications
=> HPCI
=> RCIC
- RO/PO ensure isolations occur IAW either:
=> AB.CONT-0002 HPCI Injection Valves Fail To
HPCI Injection Valves' failure is pre-inserted.
to automatically initiate by: D Monitoring plant
=> OHA B1-E5 HPCI PUMP conditions and DISCHARGE FLOW LO indications closely.
=> High Discharge Pressure
=> High Turbine Speed
=> No injection flow ESG-1 Page 17 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event/ Instructor Activity Comments Response I
injection IAW AB.ZZ 0001 Att. D CONTROL 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 INPO Fundamentals:
Drywell Pressure EOP entry 0TEAMWORK condition by:
==> OHA A 7 04 "DRYWELL RECORD time that PRESSURE HI/HI" drywell pressure
==> OHA C5 85 "DRYWELL exceeds 1.68#
PRESSURE HI"
==> Various system initiations TIME:
and isolations
- Crew reports Torus Water temperature if it reaches 95 degrees.
ESG-1 Page 18 of 25 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Expected Plant/Student Event / Instructor Activity Comments
Response
Note: An Alert is required to be
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:
=> 1E Breakers
=> CRD
=> Instrument Air
- IF directed, THEN RO/PO HPI USED:
restore 1E 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
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 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.
2.
- 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 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.
ESG-1 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 LOCA TRANSIENTS: LOSS OF SUPPORT SYSTEMS:
Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Y Loss of Feedwater Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT KEY SYSTEMS y 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:
'---~~-O~N_Ll_N_E_R_IS_K_:_G_R_E_E_N~~~~I ~I~~-w_o_R_K_W~E_E_K_C_H_A_N_N_E_L_:B~~--'
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
- 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 Event Code: Lcvposx(1) <= nnn (See note* below) 3
Description:
Rod 18-03 position// Initiates ATWS and sets initial rod position Event Code: sl_pmarn I sl_pmbrn 4
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 1OB 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 SBLC pump A failure of auto start None None Insert malfunction SL04A signal SBLC pump B failure of auto start None None Insert malfunction SL04B signal None None Insert malfunction NM12D to 0 on event 1 Flow summer K607D failure Insert malfunction TC10-1 to 100 in 180 on None None EHC fluid leak-Stop Valve 2 event2 None None Insert malfunction RP06 after 1on event 3 Half-core ATWS - 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 Insert remote EP01 after 360 to BYPASS on EP01 EOP-301, bypass MSIV (-129")
None None event 5 isolation interlock Insert remote EP02 after 480 to BYPASS on EP02 EOP-311, bypass PCIG (-129")
None None event 6 isolation interlock Insert remote EP38 after 180 to Emergency on EP38 EOP-319, Restoring Instrument None None event 7 Air in an Emergency Insert remote EP09 after 240 to REMOVED on EP09 EOP-320 (step 5.1.2), ARI valve None None event 8 fuses F6A/F5A Insert remote EP10 after 240 to REMOVED on EP10 EOP-320 (step 5.1.4), ARI valve None None event 8 fuses F6B/F5B EP11 EOP-320 (step 5.2.2), RPS None None Insert remote EP11 to INSTALLED on event 9 division 1 jumper Insert remote EP13 after 360 to INSTALLED EP13 EOP-320 (step 5.2.3), RPS None None on event 8 division 3 jumper EP12 EOP-320 (step 5.2.4 ), RPS None None Insert remote EP12 to INSTALLED on event 8 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 EP14 EOP-320 (step 5.2.5), RPS None None Insert remote EP14 to INSTALLED on event 9 division 4 jumper Insert remote EP35 after 180 to FAIL_CLOSE None None 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 Comments Swap EHC Pumps: 1
I
~------------
~ PRESS HYDR FLUID STARD PUMP AP116 MAN push- PEERCHECK0 button FLAGGING 0
~ PRESS HYDR FLUID OP BARRIERS 0 PUMP AP116 START push-button
~ PRESS HYDR FLUID PUMP BP116 STOP push-button
~ PRESS HYDR FLUID PUMP BP116 AUTO push-button Power Reduction: 1
- CRS directs power reduction I
____________, IAW 10-6 and REMA.
- CRS directs inserting control rods and lowering Reactor Recirc IAW REMA guidance.
As RE, PROVIDE the following
guidance: Rods, and then lowers reactor STARD
- Power reduction guidance is to power to 85% with Reactor PEERCHECK0 insert Group 1OB Control Recirc. FLAGGING 0 Rods, then reduce reactor OP BARRIERS 0 power to 85% using Reactor Recirc flow IAW ReMA INPO Fundamentals:
guidance. D CONTROL
- 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 Page 6 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 Comments Flow summer K607D failure:
- Crew monitors Reactor power, INPO Fundamentals:
After the Crew lowers power, pressure, and level and D Monitoring plant OR, ensure plant conditions are conditions and at the discretion of the Lead stable. indications closely.
Examiner, TRIGGER ET-1.
-=> 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" ESG-2 Page 7 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 Comments
- Crew recognizes K607D failure Downscale by:
=> [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".
If panels are opened, state that
- RO refers to HC.OP-AR.ZZ-indications on 1OC608 indicate 0020, GRIDS C049:
K607D meter is downscale. => CHECK flow unit readings AND under the direction of Flow Unit D COMPARATOR and the SM/CRS BYPASS the Flow Unit C Comparator lights on unit having an off normal 1OC608 should be illuminated. reading.
- Crew re-enters OP-AB.IC-004 INPO Fundamentals
=> Condition F D Monitoring plant conditions and
=> Crew bypasses the indications closely.
affected Flow Unit. D Controlling plant
=> Crew refers to DD.ZZ- evolutions precisely.
0020 for a failed PPC Sensor.
=> Crew directs Reactor Engineering to evaluate the flow unit failure on the PPC.
ESG-2 Page 8 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 Comments NOTE: => Crew directs l&C to INPO Fundamentals WHEN directed by the crew to PLACE the MODE D Working effectively Switch, on the D flow as a team.
place the flow unit mode switch to unit, to the the "unlabeled" position, THEN "UNLABELED" position D Having a solid MODIFY NM12D to 100%. understanding of between STANDBY and ZERO. plant design and system interrelationships.
=> 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.
If panels are opened, state that
- PO may check indications on indications on 1OC608 indicate 1OC608 and reports K607D is K607D is INOP. 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.
ESG-2 Page 9 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 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
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 observed if scram ordered first.
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 dispatched to EHC,
level indicates greater than 6 inches LOW (bottom of indication). No indication of where EHC fluid is leaking.
- WHEN AP116 amps are >60, IAW the SPRI, Recirc THEN CRS enters Condition C Pumps are considered and directs: to be at minimum if
=> Monitoring Turbine Valve below 30% speed.
Positions Crew may not lower
=> Reducing recirc pump recirc pump speeds speed to minimum before scramming.
=> Locking the Mode Switch in SHUTDOWN
=> Tripping the Main Turbine
maintain EHC level, D CONSERVATISM THEN IAW 8.7 directs:
=> Reducing RR Pump Speed to minimum
=> Lock the MS in SD
- WHEN directed, HPI USED:
THEN the RO: STARD
=> Reduces recirc pump PEERCHECK0 speeds to minimum
=> Locks the Mode Switch in SHUTDOWN ESG-2 Page 11 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 Comments ATWS:
- Crew recognizes Scram RECORD time of Mode The A TWS is automatically Condition and Reactor Power Switch to SHUTDOWN inserted during the scram. Above 4% EOP entry for 15 min ECG condition: Classification.
=:> APRM indications
=:> Absence of rod FULL IN Time: - - - - -
lights on the right side of Full Core Display
=:> Rod position indications STRATEGIES FOR SUCESSFUL HPI USED:
TRANSIENT MITIGATION
- RO performs scram actions IAW AB.ZZ-0001 Att. 1. STARD Reactor Scram Reports HARD CARD 0 Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status IAW HC.OP- Due to ATWS, CRS AB.ZZ-0001. Crew personnel should hold may not direct tripping all other non-essential communications Main Turbine IAW until after the initial scram report is complete. The Control Room Supervisor AB. BOP-0002.
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 Page 12 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 Comments STRATEGIES FOR SUCESSFUL INPO Fundamentals:
TRANSIENT MITIGATION
- Prioritize the Power Leg to establish 0TEAMWORK 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 Page 13 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 Comments STRATEGIES FOR SUCESSFUL
- PO stabilizes and maintains HPI USED:
TRANSIENT MITIGATION For ATWS conditions where reactor RPV level as directed by CRS. STARD power remains >4% RTP, the CRS HARD CARD 0 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.
- CRS directs:
~ Initiating SLC
~ Verifying RWCU Isolates
STARD PEERCHECK0
- Crew starts AP208 and/or ENTER Supp Pool temp BP208 SLC pumps before when A/BP208 SLC Suppression Pool pump is started:
temperature reaches 110 degrees. Temp: _ _ _ __
- CRS directs tripping reactor recirc pumps.
ESG-2 Page 14 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 Comments
- RO/PO trip reactor recirc HPI USED:
pumps. STARD PEERCHECK0 May already be tripped on EOC-RPT.
Note: A SAE is required to be INPO Fundamentals:
declared IAW ECG Section SS3.1 0 KNOWLEDGE (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%)
AB.ZZ-0001 Att. 13. STARD HARD CARD D INPO Fundamentals:
0 CONTROL
- CREW prevents an This Critical Task only uncontrolled applies if conditions for depressurization during automatic ADS initiation A TWS conditions by are met. See preventing ADS justification for failure ACTUATION. criteria.
ESG-2 Page 15 of 30 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
- Crew recognizes bypass Turbine Bypass valves valves are not opening to are failed shut.
control pressure by:
=> OHA D3-D5 "EHC UNIT PANEL 10C363"
=> DEHC "BYPASS VALVE POSITIONING ERROR" alarms
=> Bypass valve position indication
=> Rising reactor pressure STRATEGIES FOR SUCESSFUL
Direct initial pressure control as Stabilize
=> Main Steam Line Drains pressure 800 psig to 1000 psig. The lower limit of 800 psig will not complicate => SRVs RPV level maintenance and will prevent => RPFT an unwanted cooldown. The upper limit of 1000 psig is a round number below 1047 psig.
- RO/PO control pressure as HPI USED:
directed by CRS with: STARD
=> Main Steam Line Drains HARD CARD 0 IAW AB.ZZ-0001 Att. 15
=> SRVs IAW AB.ZZ-0001 INPO Fundamentals:
Att. 13 D CONTROL
=> RFPTs ESG-2 Page 16 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 Comments Trip of SLC Pump;
pumps(will trip 1O minutes after => OHA C1-B1 "SLC starting). 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 IF dispatched to investigate trip of
- Crew dispatches NEO and AP208 and BP208, Maintenance to investigate trip THEN REPORT unable to of SLC pumps.
determine cause of the trips.
ESG-2 Page 17 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 Comments REFER to the appropriate EOP CRS directs performance of the The timing, order, and and SUPPORT Crew requests for following EOPs: priority of the EOP EOPs IAW with the following. =:. EO.ZZ-0320 "Defeating performance may vary.
Validated execution time delays ARI and RPS Interlocks" are built-in: =:. EO.ZZ-0301 "Bypassing EOP-301 : ET-5 MSIV Isolation Interlocks" EOP-311: ET-6 =:. EO.ZZ-0311 "Bypassing EOP-319: ET-7 Primary Containment EOP-320: ET-8 Instrument Gas Isolation EOP-322: ET-10 Interlocks" STRATEGIES FOR SUCESSFUL =:. EO.ZZ-0319 "Restoring TRANSIENT MITIGATION Instrument Air in an Promptly initiate actions IAW the 300 Emergency" series EOPs to shut down the reactor.
=:. EO.ZZ-0322 "Core Spray Timely actions will reduce the potential continued challenges to containment. In Injection Valve Override" 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 ATWS CRD operation hard card and CRAM move sheets. When control room portions of EOP-320 have been completed and the NCO is ready to re-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.
=:. SLC
=:. CRD
=:. RCIC ESG-2 Page 18 of 30 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
- RO/PO terminate and prevent HPI USED:
injection from HPCI, RHR and STARD feedwater/condensate IAW HARD CARD D AB.ZZ-0001:
=> Att. 16 for 1OC650 INPO Fundamentals:
=> Att. 17 for 1OC651 0 CONTROL
- CRS directs maintaining RPV Typically, the lower end water level between -50" and of the level band is set
-185". above -129".
- RO/PO control level as HPI USED:
directed by CRS with: STARD
=> Feedwater IAW HARD CARD 0 AB.ZZ-0001 Att. 14
INPO Fundamentals:
6
- Crew ensures adequate core cooling by maintaining, or restoring, RPV level above
-185" without Emergency Depressurizing.
- RO/PO establishes drive water HPI USED:
d/p IAW AB.ZZ-0001 Att. 18. STARD HARD CARD 0 INPO Fundamentals:
D CONTROL ESG-2 Page 19 of 30 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
inserts control rods IAW STARD RE.AB.ZZ-0001 Att. 1.
Trip of CRD Pump:
minute after ATWS. => Flashing STOP light for AP207
=> OVLD/PWR FAIL light for AP207 IF dispatched to investigate trip of
- Crew dispatches NEO and AP207, Maintenance to investigate trip THEN REPORT the motor is hot of AP207 CRD pump.
to the touch and the breaker (52-437011 )is tripped. Report that the breaker will not reset (if required).
Turbine Trip:
- Crew recognizes Turbine Trip The turbine will trip 8 minutes after by:
the EHC leak if not previously => OHA A1-D3 "TURBINE tripped. 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 1OC651 D ESG-2 Page 20 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 Comments
- 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 1OC650C
=> RM11 9AX833/834 alarm
=> Various Suppression Pool temperature indicators Strategies For Successful Transient
Mitigation Torus Temperature Leg DTEAMWORK Start all available Torus cooling as soon as possible to remove heat from containment.
- STA/IA monitors EOP-102 implementation.
Pool Cooling IAW AB.ZZ-0001 STARD Att. 3. HARD CARD 0 PEERCHECK0
- RO/PO aligns SACS to Depending on resource support second RHR Hx IAW management, this may SO.EG-0001 Section 5.9. not occur until the reactor is shutdown under all conditions without boron.
ESG-2 Page 21 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 Comments
- !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%,
- !E RPV level reaches -129",
THEN Crew terminates and prevents injection from Core Spray.
- WHEN EOP-320 Section 5.1 HPI USEl and 5.2 are complete, STARD THEN the Crew implements PEERCHECK0 EOP-320 Section 5.3 and reset RPS.
=> OHA C3-A2-A5 fail to clear
=> RPS A and B Fail to reset WHEN the Crew has requested
THEN INSERT TRIGGER-9.
WHEN the Crew has reset RPS,
- WHEN EOP-320 Section 5.1 THEN DELETE Malfunctions and 5.2 are complete, RP06 to allow full rod insertion on THEN the Crew implements the next scram. EOP-320 Section 5.3 and reset RPS.
ESG-2 Page 22 of 30 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 At the Lead Examiners discretion,
- WHEN OHA C6-E4 clears, HPI USED:
MODIFY Variable lclsdv to THEN the Crew initiates a STARD accelerate draining of the SDV. manual scram IAW EOP-320 PEER CHECK0 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 INPO Fundamentals:
shut down by: 0 MONITORING
~ SPDS ALL RODS IN
~ RWM Confirm Shutdown
~ GRIDS Rod positions Termination Requirement:
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 Page 23 of 30 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. HC.OP-EO.ZZ-0101A ATWS-RPV Control AA. HC.OP-EO.ZZ-0102 Primary Containment Control BB. HC.OP-EO.ZZ-0301 Bypassing MSIV Isolation Interlocks HC.OP-EO.ZZ-0311 Bypassing Primary Containment Instrument Gas Isolation CC.
Interlocks DD. HC.OP-EO.ZZ-0319 Restoring Instrument Air in an Emergency EE. HC.OP-EO.ZZ-0320 Defeating ARI and RPS Interlocks FF. 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 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".
2.
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 Given the current ATWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor. EOPs direct this action under the current conditions.
This critical task is only applicable if RPV water level goes below -129". Failure to satisfactorily complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure to less than 700 psig.
ESG-2 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
-185 11 without Emergency Depressurizing.
KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:
EA2.02 Reactor water level RO 4.1 SRO 4.2 Lowering 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.
4.
- 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 Manually inserting all control rods, OR, implementing HC.OP-EO.ZZ-0320, provides the only methods for control rod insertion and substantial negative reactivity addition. It is critical for the crew to implement one of these methods to insert control rods and shut the reactor down. Failure to initiate these actions may result in requiring RPV level to be lowered to or below TAF to reduce power to <4%. This represents a significant challenge to maintaining adequate core cooling.
ESG-2 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 TRANSIENTS: LOSS OF SUPPORT SYSTEMS:
y Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Manual Scram 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:
'--~~-O~NL_l_N_E_R_IS_K_:_G_R_E_E_N~~~~I l~~~w_o_R_K_W~E_E_K_C_H_A_N_N_E_L_:c~~~
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
- 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) 11 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. 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 entered/tracked. II ESG-2 Page 30 of 30 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training SIMULATOR COPY - - OF - -
EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 2015 NRG EXAM SCENARIO SCENARIO NUMBER: ESG-3 EFFECTIVE DATE: Effective When Approved EXPECTED DURATION: 75 Minutes REVISION NUMBER: 1 PROGRAM: 0 LICENSED OPERATOR REQUALIFICATION
~ INITIAL LICENSE D OTHER:
REVISION
SUMMARY
- 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 1E 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 Event Code: et_array(4) & zlcwzpds 6
Description:
LOP Inserted AND SACS Pump D Running Event Code: rrlnr <= -129 7
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 Diesel Generator B emergency start None None Insert malfunction DGO?B 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 Insert malfunction FW12B to 80.00000 in None None High pressure heater BE106 tube leak 240 on event 1 Insert malfunction SL03A on event 2 None None Inadvertent SBLC system A initiation delete in 3 LOSS OF 125 voe CLASS 1E BUS None None Insert malfunction ED11 A on event 3 100410 None None Insert malfunction EG12 on event 4 Loss of all off site power Insert malfunction 0015 after 10 to None None SACS pump DP210 trip SEIZE on event 6 Insert malfunction CD09A to 0 on event Drive water flow control valve F002A None None 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 Insert malfunction AN-A2A5 after 10 on CRYWOLF ANN A2A5-FIRE PROT None None 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 Expected Plant/Student Response Comments 68 FWH Tube Rupture:
- Crew recognizes trip of 68 The 68 FWH dump FWH and loss of Feedwater valve will not open until After the Crew assumes the shift, heating by: after the Feedwater OR, at the discretion of the Lead
=> OHA A 7-E2 "FEEDWATER heater trip setpoint is Examiner, TRIGGER ET-1 (68 HEATER TRIP" reached.
FWH Tube Rupture).
=> 68 FWH Flashing HTR TRIP light INPO Fundamentals:
=> CRIDS 02997 "Feedwater 0 MONITORING 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.
Insight Items: The tube leak will caw~
- Crew recognizes leak in 68 a small vessel level
=> RFPTs speed increasing transient (:==:2 inches).
c91a1744
=> RFP discharge flows rising
- FW Line Temp 8 with lowering feed flow to c91a1746 reactor vessel
=> Total Condensate flow rising
=> 3/4/58 FWH drain flow rising
=> 68 FWH level rising HPI USED:
- RO reduces and maintains STARD reactor power to Pre-Feedwater Heater Trip or PEERCHECK0 Isolation Value IAW the SPRI. FLAGGING 0 Immediate Operator Action IAW A8.80P-0001.
INPO Fundamentals:
D CONTROL ESG-3 Page 6 of 29 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
- Crew restores/maintains the Core Thermal Power 5 Minute Average to <3848 MWth.
IF dispatched to 8C102,
- Crew dispatched T8EO to THEN REPORT: 8C102 panel.
- 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
- 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 HPI USED:
isolate the heater per Condition STARD 8: PEERCHECK0
~ Closes HV-17538
~ Closes HV-17688
~ Ensures extraction steam isolated to 68 FWH IAW SO.AF-0001 Section 5.6 Power should be lowered to 5%
below the pre-trip value within 5 reactor power to IAW A8.80P- D CONTROL minutes.(8ased on Note 4.) 0001 Retainment Override and 0 MONITORING the SPRI.
ESG-3 Page 7 of 29 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
- IF directed, HPI USED:
THEN RO reduces reactor STARD power. PEERCHECK0
=> 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 ~15%, 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.
ESG-3 Page 8 of 29 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 Inadvertent SLC Initiation:
- Crew recognizes Inadvertent INPO Fundamentals:
After actions for the loss of FW SLC Initiation by: 0 MONITORING Heating are complete, or at the => OHA C1-C1 SLC SQUIB discretion of the Lead Examiner, VLV LOSS OF TRIGGER ET-2. 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
0001: D CONTROL
=> 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.
If requested to open breaker,
- Crew directs opening SLC INSERT Remote ET72 to Pump A breaker 52-212063.
TAGGED and report that the breaker is open.
ESG-3 Page 9 of 29 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 SLC Tank level can be observed
- CRS determines SLC on CRI DS Page A097 point operability based on SLC A7052. Pump AP208 breaker open (Per Note 3, <15 gallon change and Storage Tank level using indicates no injection reached the HC.OP-DL.ZZ-0026, and vessel.) declares inoperable SLC Pump AP208.
- Crew determines if SLC solution entered the Reactor.
- CRS/STA/IA recognize the Need to restore the following Tech Specs actions subsystem in 7 days, or apply: be in Hot S/D in next 12
=> SBLC - Operating hours.
3.1.5, Action A.1 INPO Fundamentals:
0 KNOWLEDGE
- If SLC entered the Reactor, the CRS initiates action within 15 minutes to reduce power to less than 24% within six hours.
Loss of 10D410:
- Crew monitors Reactor power, INPO Fundamentals:
After the SBLC pump is secured, pressure, and level and 0 MONITORING OR at the discretion of the Lead ensures plant conditions are Examiner, TRIGGER ET-3 stable.
(Loss of 100410 bus).
ESG-3 Page 10 of 29 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
- Crew recognizes loss of 100410 by:
=> Flashing INOP lights on all 1OA401 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 1OC6500
=> OHA 03-F2 "125VOC SYSTEM TROUBLE"
=> CRIOS Page 166
!E dispatched to investigate loss
- Crew dispatches ABEO and E-0009-1 Sheet 2 of 100410, Maintenance to investigate loss THEN REPORT: of 100410 bus.
- 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
- Crew contacts Operations Management to initiate ERT callout.
ESG-3 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 Expected Plant/Student Response Comments
- CRS/STA/IA recognize the Need to restore the following Tech Specs actions 1AD411 battery, apply: 1OD410 bus, and one
=> D.C. Sources - Operating charger in two hours, or 3.8.2.1 Action a be in Hot S/D in next 12
=> Distribution - Operating hours.
3.8.3.1 Action b INPO Fundamentals:
0 KNOWLEDGE Loss of Offsite Power:
- Crew recognizes Loss of 15 minutes after the loss of Offsite Power by:
10D410 bus, => OHA "STA SERVICE OR at the discretion of the Lead TRANSFORMER Examiner, TROUBLE" for all TRIGGER ET-4 (Loss of Offsite transformers Power). => TRIP indication for all 500 KV breakers
=> Flashing TRIP lights for all previously closed bus infeeds.
=> Numerous OVLD/PWR FAIL lights.
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 Page 12 of 29 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 STRATEGIES FOR SUCESSFUL
TRANSIENT MITIGATION IAW AB.ZZ-0001 Att. 1. STARD Reactor Scram Reports Following a Reactor scram, the HARD CARDO 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.
- Crew recognizes RPV Level RECORD time LOP Below 12.5" EOP entry occurred for 15 minute condition by: ECG Classification.
=> OHA C5-A4 "RPV WATER Time: - - - -
LEVEL LO"
=> OHA A 7-D5 "RPV LEVEL 3"
=> Various water level indicators
- Crew recognizes Reactor Due to the loss of both Pressure Above 1037# EOP RPS buses, the C5-A5 entry condition by: OHA will not be useful
=> OHA C1-E5 "SRV LO-LO in diagnosing peak SET ARMED" pressure during the
=> Various RPV pressure transient.
indicators ESG-3 Page 13 of 29 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 STRATEGIES FOR SUCESSFUL INPO Fundamentals:
TRANSIENT MITIGATION
0 TEAMWORK 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.
- Crew recognizes failure of the INPO Fundamentals:
'B' EOG to start and load by: MONITORING D
~ Engine STOP light
~ Output breaker TRIP light
~ OVLO/PWR lights on 'B' Channel components
- RO/PO starts the 'B' EOG and HPI USED:
ensures it loads auto start. STARD Immediate Operator Action IAW AB.ZZ-0135 ESG-3 Page 14 of 29 Rev. 1
'lo PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments IF directed to locally start the 'B'
- Crew starts the 'B' EDG by EOG, EITHER:
THEN REMOVE Malfunction Pressing the 'B' EDG START DG07B. pushbutton in the Control Room, OR Directing an operator to locally start the 'B' EDG.
- Crew recognizes failure of Failure: ChannelBloadsto automatically start.
Pre-inserted
- 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 HPI USED:
pressure as directed by CRS. STARD HARD CARD 0 INPO Fundamentals:
D CONTROL Note: AUE is required IAW ECG Section: SU1 .1 Loss of all Offsite AC power to all 4.16 KV Vital Buses AND ~15 minutes have elapsed ESG-3 Page 15 of 29 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: LVL 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 LVL 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 LVL 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 decision to Emergency
- RO/PO may direct an 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.
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 Expected Plant/Student Response Comments
pressure as directed by the STARD CRS IAW AB.ZZ-0001 Att. 13. HARD CARD 0 FLAGGING 0 INPO Fundamentals:
D CONTROL As ESOC, REPORT it will take at
- Crew contacts ESOC for least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to restore Offsite estimated time to restoration of power to Artificial Island. Offsite power.
- 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 1OC650C
=? RM 11 9AX833 alarm
=? Various Suppression Pool temperature indicators
- WHEN Suppression Pool Due to RPV water level temperature reaches 95 concerns, may not degrees, immediately place 'A' THEN the CRS implements RHR in Supp Pool Clg.
THEN RO/PO place 'B' RHR in STARD Suppression Pool Clg IAW HARD CARD 0 AB.ZZ-0001 Att. 3.
ESG-3 Page 17 of 29 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
- 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
ESG-3 Page 18 of 29 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: power.
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
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 indications on 1OC650D 0 MONITORING
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 Expected Plant/Student Response Comments
- Crew recognizes loss of Fuel Crew may enter Pool Cooling by: AB.COOL-0004, but no
=;> OHA D1-D5 "FUEL POOL conditions apply.
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' Due to the continuing FPC pump l/S bypassing the loss of RPV water level, filter demins IAW SO.EC-0001. this action may not be complete by the end of the scenario.
STRATEGIES FOR SUCESSFUL
- Crew ensures available TRANSIENT MITIGATION EOP-101 Table 1 systems are Emergency Depressurization running and aligned for Level Response And Control injection.
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.
- Crew recognizes RPV LVL 1 by:
=;> A7-F5 "RPV LEVEL 1"
=;> C1-F3 "ADS DRYWELL PRESS BYP TIMER INIT"
=;> A/CID ECCS initiations
=;> Various RPV level indicators ESG-3 Page 20 of 29 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
AB.ZZ-0001 Att. 13. STARD HARD CARDO
'B' Channel ADS logic has no power.
- RO/PO ensures available ECCS pumps start.
Emergency Depressurization
due to Low RPV Level: below-129", but before-185", DTEAMWORK THEN the CRS implements EOP-202 to Emergency Depressurize.
IAW AB.ZZ-0001 Att. 13. STARD HARD CARD 0 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 Page 21 of 29 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
- BEFORE Compensated RPV RECORD RPV water level at which five SRVs water level lowers below are opened.
-185": Crew enters EOP-202 and initiates actions to Emergency Depressurize the RPV Level: - - -
reactor. Then restores RPV water level to above -185".
- RO/PO injects with low HPI USED:
pressure ECCS IAW STARD AB.ZZ-0001 Att. 4 and/or 5 to HARD CARD 0 restore level as directed by the CRS. 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 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 Page 22 of 29 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-AB.ZZ-0001 Transient Plant Conditions Q. HC.OP-AB.CONT-0002 Primary Containment R. HC.OP-AB.COOL-0002 Safety/Turbine Auxiliaries Cooling System HC.OP-AB.ZZ-0135 Station Blackout/Loss of Offsite Power/Diesel Generator S.
Malfunction T. HC.OP-AB.ZZ-0136 Loss of 120 VAC Inverter
- u. HC.OP-AB.ZZ-0150 125 VDC Malfunction V. HC.OP-AB.ZZ-0170 Loss of 4.16 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 ~3848 MWth.
KIA 295001 Reactor Feedwater System A2 Ability to (a) predict the impacts of the following on the Reactor Feedwater System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions of operations:
A2.04 Loss of Extraction Steam RO 3.3 SRO 3.4 KIA 2.2 Equipment Control 2.2.22 Knowledge of limiting conditions for operations and safety limits R0.3.4 SRO 4.1 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.
2.
- 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 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.
ESG-3 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 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.
4.
- 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 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.
ESG-3 Page 25 of 29 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training ESG-3 / 1 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT Y Loss Of Offsite Power/SBO Internal Flooding LOCA TRANSIENTS: LOSS OF SUPPORT SYSTEMS:
Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT KEY SYSTEMS y HPCI SRVs y RCIC - - - Condensate/Feedwater B/D EOG y SSW A/B RHR Pump RPS y A/B SACS Loop 1E4.16KVBus 1E480 VAC Bus 120VAC 481 Inverter y 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:
[~~~-O~NL_l_N_E_R_IS_K_:_G_R_E_E_N~~~~I l~~~-w_o_R_K_W~E_E_K_C_H_A_N_N_E_L_:A~~~
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
- 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 SIMULATOR COPY _ _ OF _ _
EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 2015 NRC EXAM SCENARIO SCENARIO NUMBER: ESG-4 EFFECTIVE DATE: Effective When Approved EXPECTED DURATION: 75 Minutes REVISION NUMBER: 1 PROGRAM: 0 LICENSED OPERATOR REQUALIFICATION
~ INITIAL LICENSE D OTHER:
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. 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 Event Code: zdads1 (1) I zdads2(1) 2
Description:
Either F013A Control Switch to OPEN Event Code: iapiarca <= 82 6
Description:
Instrument Air Pressure <=82 psi Event Code: rh_bkr(1) 12
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 RWCU isolation valve F001 failure to None None Insert malfunction CU11A auto close RWCU isolation valve F004 failure to None None Insert malfunction CU11 B auto close None None Insert malfunction DG02B Diesel generator B failure None None Insert malfunction DG02D Diesel generator D failure RHR System C auto injection failed to None None Insert malfunction RH08C energized Insert malfunction RC06 after 240 on event None None RCIC system isolation 7
ADS/Relief valve F013A (MS LINE A)
None None Insert malfunction AD02AO on event 1 sticks open Insert malfunction AD02AO on event 2 ADS/Relief valve F013A (MS LINE A)
None None 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 Insert malfunction CU03 from 10.00000 to None None RWCU system leak 35.00000 in 600 on event 4 Insert malfunction IA02 to 60.00000 on None None Gradual loss of instrument air event 5 None None Insert malfunction EG12 on event 7 Loss of all off site power Insert malfunction RR31 A2 after 180 to Recirc loop A large break [V] (10%-6000 None None 3.00000 in 300 on event 7 gpm, 100%-60000 gpm)
Insert malfunction DG02A after 3 on event None None Diesel generator A failure 12 None None Insert malfunction PC07 A after 1 on event 7 Seismic Event II Insert malfunction DG02A on event 8 delete None None 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 Insert malfunction CD011427 after 1 on None None Control Rod 14-27 drift in event 6 Insert malfunction CD011827 after 1 on None None Control Rod 18-27 drift in event6 Insert malfunction CD012227 after 1 on None None Control Rod 22-27 drift in event6 Insert malfunction CD012627 after 1 on None None Control Rod 26-27 drift in event 6 REMOTE SCHEDULE:
Initial @Time Event Action Description Insert remote DG05 after 5 to RESET on None None DG05 Diesel generator A shutdown relay event 8 Insert remote DG01 after 20 to RESET on None None 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 Expected Plant/Student Response Comments Containment 02 Weekly
- CRS directs commencing Surveillance Test: 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 1AC200 in SAMPLE
=:> Places the Mode Switch for H2/02 Analyzer 1AC200 in Analyze
=:> Ensures the Control At This Pnl light is on. IF not, press Remote Selector PB ESG-4 Page 6 of 32 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 SRV Open/Closes:
After 1AC200 is aligned to sample ~ OHA C1-A3 "ADS/SAFETY STARD the Drywell Or Suppression RELIEF VLV NOT HARD CARDO Chamber for Oxygen, TRIGGER CLOSED" ET-1. ~ Acoustic Monitor indication
~ CRIDS D5005 "SAFETY RELIEF VALVE F013A"
~ Total steam flow lowering
~ Main Gen MWe lowering
~ RPV level swell
~ Elevated SRV tailpipe temperature
F013A lnSight Items:
- PO cycles SRV control Immediate Operator
- CH B AUTO/OPEN Switch zdads1(1)
- CH D AUTO/OPEN Switch zdads2(1)
- Before more than two RECORD elapsed time minutes has elapsed from SRV was open:
SRV opening, CREW closes F013A by cycling EITHER TIME: - - -
F013A AUTO/OPEN control switches to OPEN and back to AUTO.
ESG-4 Page 7 of 32 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
by: 0 MONITORING
=} Acoustic Monitor indication
=} Total steam flow rising
=} Main Gen MWe rising
=} RPV level shrink
=} Lowering SRV tailpipe temperature
- CRS recognize the following Must perform functional Tech Spec actions apply: test of vacuum breakers
=} Suppression Chamber- within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Drywell Vacuum Breakers 4.6.4.1.b.1 INPO Fundamentals:
0 KNOWLEDGE
- CRS refers to the following Tracking LCOs:
Tech Spec statements to 3.4.2.1 and 3.4.2.2 determine SRV operability:
=} 3.4.2.1 Active LCO:
=} 3.4.2.2 3.5.1.d
=} 3.5.1.d
=} Condition B
- SM contacts Operations Management.
ESG-4 Page 8 of 32 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 Earthquake:
- Crew recognizes Seismic RECORD time C6-C4 AFTER Technical Specifications Event by: alarms for 15 minute for the SRV have been ~ OHA C6-C4 "SEISMIC ECG Classification.
addressed, OR at the discretion of MON PNL C673" the Lead Examiner: ~ GRIDS D3977 "SEISMIC TIME: - - - -
- PLAY the Earthquake Sound TROUBLE ALARM TRBL" Effect (if available) at medium ~ Response Spectrum volume for about 20 seconds Analyzer indications on OR 10C650C ANNOUNCE "You feel motion ~ Loud rumbling noise then it stops", AND TRIGGER (if available)
ET-3 (Seismic Event)
- Crew monitors critical INPO Fundamentals:
parameters to determine if 0 MONITORING plant is stable.
IF Crew calls National Earthquake
- CRS implements AB.MISC-0001 actions Center, AB.MISC-0001: provided for reference THEN REPORT a seismic event ~ Condition E only. Due to the pace of of 6.0 on Richter scale centered ~ Condition F the scenario, it is 12 miles east of Wilmington, DE. unlikely they will be
!E Crew calls Security, implemented.
THEN REPORT the Security system is intact.
- RO/PO implements AR.ZZ-0011 Attachment C4.
!E dispatched to 1OC673,
- Crew dispatches ABEO to THEN REPORT: 10C673.
- The SM-3 Event Indicator is
- Crew recognizes a seismic WHITE. event >0.1 g has occurred
- 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 Page 9 of 32 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 IF directed to reset 1OC673,
PC07B.
- RO/PO record Seismic Response Spectrum Analyzer lights on AR.ZZ-0011 Att.
C4-1.
ESG-4 Page 10 of 32 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 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 Page 11 of 32 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.
~ 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
- 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.
~ 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 Expected Plant/Student Response Comments
!E dispatched to check status of
- IF Instrument Air Header RAGS demins, Pressure reaches 85 psig, AND the EIAC is running, THEN CRS implements THEN REPORT the RAGS AB.COMP-0001:
demins are isolated. => Condition C
!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
- Crew dispatches TBEO and trip of 10K107, Maintenance to investigate trip THEN REPORT VIBRATION of 10K107.
ALARM and VIBRATION SHUTDOWN alarms were in.
RWCU Leak:
When the Station Air Compressor by: 0 MONITORING is in service, => CRI OS indication and OR at the discretion of the Lead alarm Examiner, TRIGGER ET-4.
ESG-4 Page 13 of 32 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
- Crew recognizes leak from Room temperatures will lnSight Items: RWCU by: not provide conclusive
- RWCU Diff Flow => Rising differential flows on evidence of leak.
cufdelta NUMAC and GRIDS RWCU differential flow RWCUDF page 61 will reach the alarm
=> OHA D3-83 "RWCU STM setpoint about 7.5
!E dispatched to look for the leak, THEN REPORT the unable to LK ISLN TIMER minutes after leak starts.
determine leak location. INITIATED" If RWCU is isolated
=> GRIDS D5871 "RWCU before differential flow NOTE: CREW may isolate RWCU ISLN TIMER INITIATED setpoint is reached, CH D" alarms will not be before alarm conditions exist.
=> GRIDS D5873 "RWCU received.
ISLN TIMER INITIATED CHA"
=> GRIDS RWCUDF "RWCU DIFFERENTIAL FLOW" in alarm.
lnSight Items:
- Crew recognizes failure of
- 'A' Channel Isolation RWCU to isolate by: If RWCU is isolated cu_k6a09 => OHA C1-A2 "RWCU DIFF before differential flow
- 'D' Channel Isolation FLOW HI" setpoint is reached, cu_k6d11 => GRIDS D5870 "RWCU isolation will not be DIFF FLOW CH D" received.
=> GRIDS D5872 "RWCU DIFF FLOW CH A" lnSight Items:
- HV-F001 HV-F001 and HV-F004. STARD cuvf001 Immediate Operator
- Crew initiates closure of Closing the RWCU RWCU HV-F001 OR HV-F004 HV-F001 OR HV-F004 when OHA C1-A2 "RWCU prior to receiving OHA DIFF FLOW HI" alarms. C1-A2 satisfies this Critical Task.
ESG-4 Page 14 of 32 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
SO.BG-0001 OR AB.CONT- STARD 0004 Condition C
=> Condition A
=> Condition B
- Crew validates isolation by INPO Fundamentals:
trending: 0 MONITORING
- !E the leak was not isolated Need to restore valves before the isolation signal was to OPERABLE or received, deactivate the HV-F001 THEN CRS/STA/IA recognize or HV-F004 in the next the following Tech Specs four hours.
apply: May also refer to TIS
=> Primary Containment 3.3.2, although both trip Isolation Valves systems would already 3.6.3 action a be tripped and the
=> Primary Containment valves already shut.
Integrity 3.6.1.1 INPO Fundamentals:
0 KNOWLEDGE
- Crew contacts Operations Management to initiate ERT callout.
ESG-4 Page 15 of 32 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 Multiple Rod Drifts:
- Crew recognizes lowering WHEN RWCU is isolated, Instrument Air Pressure by:
OR at the discretion of the Lead =? OHA A2-A1(A2), "INST AIR Examiner, TRIGGER ET-5 HEADER A(B) PRESSURE (Gradual Loss of Instrument Air). LO"
=? CRIDS 04601 (2), INST AIR SUPPLY HOR A(B)
The multiple rod drift is PRESS automatically inserted when =? Pl-7603A(B) on 10C650A instrument air pressure drops to 82 psig.
=? 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 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
=? Consider closing HV-7595 ESG-4 Page 16 of 32 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
- Crew recognizes multiple rods INPO Fundamentals:
drifting into the core by: 0 MONITORING
=> 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
SHUTDOWN. 0 CONTROL
- Crew scrams the reactor RECORD the time after multiple rod drifts. between OHA C6-E3 and reactor scrammed.
TIME: - - - -
IAW AB.ZZ-0001 Att 1. STARD HARD CARD 0
=> OHA C5-A4 "RPV WATER LEVEL LO"
=> OHA A7-D5 "RPV LEVEL 3"
=> Various water level indicators ESG-4 Page 17 of 32 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 STRATEGIES FOR SUCESSFUL
TRANSIENT MITIGATION 0TEAMWORK 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.
- STA/IA performs the following:
- . Verifies Rx shutdown
- . Trends critical plant parameters
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 Page 18 of 32 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 Aftershock/LOP/LOCA:
- Crew recognizes Loss of 5 minutes after the scram, Offsite Power by:
OR, at the Lead Examiners ~ OHA "STA SERVICE discretion, TRANSFORMER
- PLAY the Earthquake Sound TROUBLE" for all Effect (if available) at medium transformers volume for about 20 seconds ~ TRIP indication for all 500 OR KV breakers ANNOUNCE "You feel motion ~ Flashing TRIP lights for all then it stops" previously closed bus
- TRIGGER ET-7 infeeds.
(LOP/LOCA/Station Blackout) -=;> Numerous OVLD/PWR FAIL lights.
IF called as the ESOC,
- Crew recognizes failure of the Only 'A' EOG will start.
THEN REPORT both the Hope B/C/D EDGs to start and load 'A' EOG will trip when Creek AND Salem switchyards by: the 'A' RHR pump is are de-energized. It will take a ~ Engine STOP lights started.
minimum of 6-10 hours to restore ~ Output breaker TRIP lights power once the transient has ~ OVLD/PWR lights on been investigated. associated Channel components
- RO/PO attempt to start the HPI USED:
B/C/D EDGs. STARD PEERCHECK0 Immediate Operator Action IAW AB.ZZ-0135
0TEAMWORK
!E dispatched to investigate the
- Crew dispatches NEO and/or failure of B/D EDGs to start, Maintenance to investigate THEN REPORT both EDGs have failure of B/D EDGs to start.
Lube Oil Low Pressure Shutdown alarms. There is oil on EOG room floors.
ESG-4 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 Expected Plant/Student Response Comments
!E dispatched to investigate the
- Crew dispatches NEO and/or failure of the 'C' EOG to start, Maintenance to investigate THEN REPORT there is a blown failure of 'C' EOG to start.
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, problem by: 0 MONITORING THEN REPORT
- HPCI Aux oil pump is running. running
- HV-F001 is closed ~ HV- F001 not open
~ "HPCI INIT AND SEALED IF directed to open the breaker for IN" light on 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 Page 20 of 32 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
pump. STARD INPO Fundamentals:
0 CONTROL RCIC system isolation
- RO/PO identifies isolation of RCIC by:
RCIC isolation will occur 4 ~ OHA B1-A1 "RCIC minutes after the LOP. TURBINE TRIP
~ CRIDS 02400 in alarm
~ ISLN INIT Status Lights illuminated
~ BD-HV-FOO? AND FOOS CLOSING
- Crew recognizes Supp Pool Given the lowering RPV Temp Above 95°F EOP entry water level, and 'A' condition by: RHR being the only
~ OHA C8-F1 "SUPPR available RHR pump, POOL TEMP HIGH" the Crew may not place
~ Flashing 95 degree status 'A' RHR in Suppression light on 1OC650C Pool cooling at this
~ RM 11 9AX833/834 alarm time.
~ Various Suppression Pool temperature indicators
- Crew recognizes Supp Pool Given the LOP and the Level Above 78.5 In EOP entry unavailability of HPCI condition by: and RCIC, there is
~ OHA 81-C3 nothing the Crew can "SUPPRESSION POOL do to lower Suppression LEVEL HI/LO" Pool water level at this
~ Various Suppression Pool time.
level indicators ESG-4 Page 21 of 32 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 Station Blackout/Stm Clg:
after the 'A' RHR pump starts. => Diesel engine STOP light This will automatically occur at => Flashing generator breaker 1.68#, if the Crew doesn't start it TRIP light sooner. => OVLD/PWR FAIL lights on associated channel loads IF dispatched to investigate the
- Crew dispatches NEO and/or trip of the 'A' EDG, Maintenance to investigate THEN REPORT you heard the trips of the 'A' EDG.
EDG slow down, then speed up and trip. Alarm on local panel is ENGINE OVERSPEED.
WHEN OHA A2-A5 alarms,
advance the Fire Computer to lined up available for injection D MONITORING display LOP alarms. and Steam Cooling is required.
reaches -129", 0 CONTROL THEN CRS directs inhibiting ADS.
WHEN RPV level CANNOT be
restored and maintained above AB.ZZ-0001 Att. 13. STARD
-161 in.(FB1 .P AND RB1 .L); HARD CARD 0 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 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 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.
reaches -200", 0 MONITORING THEN CRS directs opening five ADS SRVs.
IAW AB.ZZ-0001 Att. 13. STARD HARD CARD 0 ESG-4 Page 23 of 32 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 at least five SRVs are
- Crew opens at least five open, SRVs after compensated THEN DELETE Malfunction reactor water level reaches DG01 C to restore the 'C' EOG to -200".
service, AND REPORT the 'C' EOG has been successfully started.
SUPPORT any requests to place
Remote Functions: => Diesel engine START light
- CS05C for 'C' Core Spray => Generator breaker CLOSE
- RH23C for 'C' RHR light
=> OVLD/PWR FAIL lights extinguished on associated channel loads RHR INJECTION FAILURE
The auto start of the 'C' RHR pump, opens the HV-F017C, STAR[
pump and auto opening of the and restores RPV water level HARD CARD [J F017C are failed. to above -185" IAW AB.ZZ-0001 Att. 4.
AFTER the Crew restores RPV
water level to above -185", restored, 0 CONTROL THEN REPORT you are ready to THEN the Crew injects with restore the 'A' EOG to service. the 'C' RHR pump and The governor oil level was low restores and maintains RPV and has been restored to normal. water level above -185".
SUPPORT any requests to place ECCS pumps in PTL using Remote Functions:
- CS05A for 'A' Core Spray
- RH23A for 'A' RHR ESG-4 Page 24 of 32 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 lE directed to restore the 'A' EOG
- Crew recognizes start of the The restoration of the to service, AND after level has 'A' EOG by: 'A' EOG makes the 'A' been restored with 'C' EOG, :=} Diesel engine START light Core Spray Loop THEN TRIGGER ET-8 AND :=} Generator breaker CLOSE available for RPV water REPORT the 'A' EOG has been light level control.
successfully restarted. :=} OVLD/PWR FAIL lights extinguished on associated channel loads
- CRS directs restoring PCIG to The AK202 PCIG the SRVs. compressor became available when the 'C' EOG was restored.
SRVs IAW AB.ZZ-0001 Att. 9. STAR 0 HARD CARD 0
Termination Requirement:
The scenario should be in Drywall Spray IAW STARD terminated at the discretion of the AB.ZZ-0001 Att. 2. HARD CARD D Lead Examiner when:
- The reactor has been depressurized
- RPV water level is being maintained above -129" ESG-4 Page 25 of 32 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-AB.ZZ-0001 Transient Plant Conditions Q. HC.OP-AB.CONT-0002 Primary Containment R. HC.OP-AB.CONT-0004 Radioactive Gaseous Release S. HC.OP-AB.COMP-0001 Instrument and/or Service Air T. HC.OP-AB.MISC-0001 Acts of Nature HC.OP-AB.ZZ-0135 Station Blackout/Loss of Offsite Power/Diesel Generator U.
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 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.
2.
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 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.
5.
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 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.
ESG-4 Page 28 of 32 Rev. 1
PSEG CONFIDENTIAL - Possession Requires Specific Permission From Nuclear Training ESG-4/1 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT Y Loss Of Offsite Power/SBO Internal Flooding Y LOCA TRANSIENTS: LOSS OF SUPPORT SYSTEMS:
Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N 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 1E 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:
~~~~O_N_L_IN_E~R-IS_K_:_G_R_E_E_N~~~~I ~'~~-w~o_R_K_w__EE_K~C_H_A_N_N_E_L_:_A~~__J 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
- 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.
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