Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML16295A057
Person / Time
Site:	Hope Creek
Issue date:	10/01/2016
From:	Fish T H; Operations Branch I
To:	; Public Service Enterprise Group
Shared Package
ML15308A608	List: IR 05000354/2016301; ML16053A103; ML16224A303; ML16295A055; ML16295A056; ML16295A057; ML17186A121; ML17186A145; ML17186A237; ML17186A244;
References
	TAC U01925
	Download: ML16295A057 (157)
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JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: 2990010101 2016 NRC EXAM RO-JPM A1 Copy __ of __ TASK: Perform The Watchstanding Duties Of The Nuclear Control Room Operator JPM NUMBER: 305H-JPM.ZZXXX REVISION:

00 SAP BET: NOH05JPZZXXE KIA NUMBER: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (CFR: 41.10 I 43.5 I 45.12) IMPORTANCE FACTOR: RO: 2.9 SRO: 3.9 ALTERNATE PATH: D APPLICABILITY:

RO IZJ EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-AA-105-102, Rev. 11 TOOLS, AND EQUIPMENT:

None SRoD 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 Page 1of12 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2990010101 TASK: Perform The Watchstanding Duties Of The Nuclear Control Room Operator INITIAL CONDllTONS:

1. You were issued a Reactor Operator (RO) License on May 15, 2016, and assigned as the Tagging NCO in Work Control. 2. The computer system is down and the status of your active license must be verified.

3. All shifts stood have been confirmed to be part of the Narrative Log. 4. All shifts included turnovers.

INITIATING CUE: 1. Fill out OP-AA-105-102 Attachment 1 for the third quarter of 2016. 2. Assume no other watchstanding will occur for the remainder of the third quarter of 2016. 3. REVIEW AND DETERMINE lE you will meet the requirements to maintain an active license into the fourth quarter of 2016. 4. Document how you did, or did not, meet the requirements on the following page. Examiner's Note: Provide past work schedule and a copy of OP-AA-105-102.

Page 2of12 JPM NUMBER: zzxxx NAME:

REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: OP-AA-105-102

4. MAIN BODY NOTE: The quarterly shift watch Operator reads NOTE. requirement may be completed with a combination of complete 8 and 12-hour shifts (in a position appropriately credited for watch-standing proficiency as discussed below) at sites having a mixed shift schedule, and watches shall not be truncated when the minimum quarterly requirement (56 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months ) is satisfied. (NUREG I 1021, Revision 9) 4.1 Active License Maintenance Page 3of12 JPM NUMBER: zzxxx NAME: REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS ELEMENT (*Critical Step) (Required for NUMBER (#Sequential Step) UNSAT UNSAT)!a>

NOTE: As specified in 10 CFR 55.4, Operator reads NOTE. "Definitions," "Actively performing the functions of an operator or senior operator," means that "the individual carries out and is responsible for the duties covered by that position".

For RO and SRO watches being credited for license maintenance, administrative tasks not related to the licensed position should be minimized.

Non-position related administrative tasks performed outside the control room, e.g., NRC physicals, all hands meetings, etc., shall not be scheduled during a credited shift. Non-position related administrative tasks performed inside the control room are allowed during'a credited shift provided the activities do not impact the individual's ability to perform assigned licensed responsibilities; i.e., the individual is in a position to provide prompt assistance to or oversight of the RO at the controls.

4.1.1. MAINTAIN

an active license by Operator reads Step. actively performing the functions of RO, SRO or LSRO. 1. RO licenses by performing the duties of the Unit RO and/or Unit PO for a minimum of seven 8-hour or five 12-hour shifts per calendar quarter, including turnover to the next shift. 4.1.2 DOCUMENT the required *operator documents the shifts number of shifts on Attachment on 7/10, 7/31, and 8/6 as the 1, Active License Tracking Log required shifts on Attachment

1. or similar computer-based tracking method. Examiner Note: Refer to Examiner's Copy of Attachment

1. The order of shifts is not critical.

Page 4of12 JPM NUMBER: ZZXXX NAME:

REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT}@ *operator documents that the requirements to maintain an active license into the fourth quarter have NOT been met. Examiner Note: Operator is considered current for the third quarter. *operator documents that additional watches need to be completed by September 30, 2016 to maintain proficiency.

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 determines license maintenance requirements have not been met. Specifically only 4 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts were worked in the second quarter. @Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.

[IER L 1-11-3 Rec. 3b] Page 5of12 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: 4010260201 TASK: Complete A Sunday Shift Routine Log JPM NUMBER: 305H-JPM.ZZOXX SAP BET: NOH05JPZZXXE 2016 NRC EXAM RO-JPM A2 Copy __ of __ REVISION:

00 KIA NUMBER: 2.1 .. 25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 I 43.5 I 45.12) ALTERNATE PATH: D APPLICABILITY: IMPORTANCE FACTOR: RO: 3.9 SRO: 4.2 sRoD EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-HC-108-116-1001 Rev. 3 HC.OP-DL.ZZ-0020, Rev. 38 TOOLS, AND EQUIPMENT:

OP-HC-108-116-1001; Straight-edge, Calculator ESTIMATED COMPLETION Tll)llE: 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 Page 1of7 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 4010260201 TASK: Complete A Sunday Shift Routine Log INITIAL CONDllTONS:

1. Plant is operating at 100% power fifteen (15) days following a refueling outage. 2. HC.OP-DL.ZZ-0020, Sunday Shift Routine Log, is in progress at Step 3.6.7. 3. GRIDS A3175, FUEL POOL HX COMMON INLET TEMP, indicates 83F. 4. The Reactor Engineer is not available.

INITIATING CUE: DETERMINE the time for the Hope Creek Spent Fuel Pool (SFP) to reach 200 degrees Fahrenheit

{bulk temperature) in the event that normal cooling is lost IAW OP-HC-108-116-1001.

ENTER your determination on Attachment

3. Page 2 of 7 JPM NUMBER: zzoxx NAME:

REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue, modified OP-HC-108-116-1001, AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: 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 9.5 ;t0.1 MBtu/hr. rate for the current date. 4.2 Select the series of curves from *#operator selects Page 4 of Attachment 2 for loss of ATTACHMENT

2. cooling, with the initial pool 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 to be 44 ;t2 hours, normal cooling is lost. IF necessary, interpolate the heat and enters this time on Attachment load between lines. 3. ,, 4.4 Submit the completed time to Operator submits the completed CRS for review. time to CRS for review. 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 determines the Spent Fuel Pool decay heat load IAW OP-HC-108-116-1001.

@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.

[IER L 1-11-3 Rec. 3b] Page 3of7 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: 2990020301 2016 NRC EXAM RO-JPM A3 Copy __ of __ TASK: Perform A Manual Tagout With SAP System Inoperable JPM NUMBER: 305H-JPM.ZZXXX REVISION:

00 SAP BET: NOH05JPZZXXE KIA NUMBER: 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (CFR: 41.10 / 45.12 / 45.13) ALTERNATE PATH: D APPLICABILITY: IMPORTANCE FACTOR: RO: 3.5 SRO: 3.9 sRoD EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

M-51-1 Sheets 1 and 2, Rev. 50/44 OP-AA-109-115, Rev. 7 TOOLS, AND EQUIPMENT:

Highlighters; M-51-1 Sheets 1 and 2 [Large Size] ESTIMATED COMPLETION T'ME: __ 1_7 __ Minutes TIME PERIOD IDENTIF.IED 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 Page 1of11 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2990020301 TASK: Perform A Manual Tagout With SAP System Inoperable INITIAL CONDllTONS:

1. The plant is operating at 100% power. 2. The Residual Heat Removal (RHR) System is in its normal standby lineup. 3. HV-F007C, RHR Pump C Min Flow Valve, is scheduled for in-body repair work. INITIATING CUE: HV-F007C, RHR Pump C Min Flow Valve, and its associated piping and electrical components need to be ISOLATED, VENTED, AND DRAINED to perform the repairs. Using controlled station drawing M-51-1, sheets 1 and 2 (provided):

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, and their required positions, NOTE: The following are NOT required to be identified:

Electrical Breaker number(s)

Control switches

Type of tag (Red blocking Tag, Worker Blocking Tag, etc)

Current position

Tag Sequence Page 2of11 JPM NUMBER: zzxxx NAME:

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

the initiating cue; M-51-1, Sheets 1 and 2; AND ENTER ST ART 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:

-Controlled Documents and Drawings from the Operator reviews provided M-51-1, TOR or DCRMS. If ... Sheets 1 and 2. 2. Perform the following:

Operator determines the blocking Select blocking points points AND required positions by -reviewing the controlled drawing. and tag types. Applicant identifies the following mechanical isolation valves: Applicant identifies the following mechanical isolation valves AND the required positions:

*V132, SHUT * *V317, S.HUT * *HV-F024A (V124), SHUT * *HV-F010A (V125), SHUT * *HV-F011A (V126), SHUT * *v20s, SHUT * *HV-F007A (V128), SHUT Applicant identifies the following mechanical VENT AND the required positions:

*V372, OPEN * *V373, OPEN Examiner Note: V338 and V339 would satisfy this vent path. Page 3of11 JPM NUMBER: ZZXXX NAME:

REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS ELEMENT (*Critical Step) (Required for NUMBER (#Sequential Step) UNSAT UNSAT)@ Applicant identifies the following mechanical DRAIN valves AND the required positions:

*V554, OPEN * *V555, OPEN Applicant identifies the following ELECTRICAL components AND the required positions:

*HV-F007C (V131) MOV breaker, OPEN * *HV-F024A (V124) MOV breaker, OPEN * *HV-F010A (V125) MOV breaker, OPEN *HV-F007A (V128) MOV '

breaker, OPEN Examiner Note: Breaker numbers are not required.

Examiner Note: The Applicant may identify the following additional components as part of the tagout for equipment protection or safety precaution (not considered critical):

HV-F007C (V131 ), OPEN (to allow proper draining on both upstream/downstream sides of valve)

CP202 RHR Pump 4kV Breaker, OPEN/PTL

AP202 RHR Pump 4kV Breaker, OPEN/PTL

V338 AND/OR V339, CLOSED (test connection).

Unless opened as vent path.

V9988 AND V9989, CLOSED (flow ports for FE4436C)

AP202 and CP202 control room hand switches Page 4of11 JPM NUMBER: ZZXXX NAME:

REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) 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 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. @Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.

[IER L 1-11-3 Rec. 3b] Page 5of11 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK NUMBER: 4010010201 TASK: Complete the Daily Surveillance Logs JPM NUMBER: 305H-JPM.ZZ017 SAP BET: NOH05JPZZ17E 2016 NRC EXAM SRO-JPM A1 Copy __ of __ REVISION:

04 K/A NUMBER: 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, I and reports. (CFR: 41.10 I 45.12 I 45.13) ALTERNATE PATH: D APPLICABILITY:

IMPORTANCE FACTOR: RO: 3.6 SRO: 3.8 EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0026 Rev. 153 TOOLS, AND EQUIPMENT:

HC.OP-DL.ZZ-0026; HC.OP-IS.BD-0001 ESTIMATED COMPLETION TIME: 13 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes ----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:

EVALUATOR:

DATE: Signature Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: Conduct of Operations TASK NUMBER: 4010010201 TASK: Complete the Daily Surveillance Logs INITIAL CONDllTONS: 1 . The Plant is in OPCON 1 at 35% power 2. A plant startup from a forced outage is in progress IAW HC.OP-IO.ZZ-0003.

3. RCIC IST is in progress and being turned over. 4. River level is at 96.1 feet due to recent heavy rains. 5. River temperature is 83 degF but is NOT expected to exceed 85 degF. 6. All EDGs, SACS, and SSW pumps are operable.

7. The SPV Effluent RMS Skid (all components) is inoperable and has been CIT for repairs. INITIATING CUE: You are the Control Room Supervisor.

IMPLEMENT the log at the beginning of today by completing Attachment 1, Section A; Log Initiation, IDENTIFYING those Attachments that require performance due to the present conditions.

Page 2of10 JPM NUMBER: ZZ017 NAME:

REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue; a paper copy of HC.OP-DL.ZZ-0026; Attachment 1 of HG.OP-DL.ZZ-0026; AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: If requested, provide copy of HC.OP-IS.BD-0001.

Operator determines beginning Operator determines correct step of the procedure.

beginning step to be 2.1. 2.1 Shift Manager/Control Room Supervisor

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

2.1.1 The SM/CRS shall Examiner Note: Examiner Copy implement the log at the Exhibit 1 is provided for reference.

' beginning of each day by completing Attachment 1, Operator determines Attachment 1 Section A; Log Initiation, is required due to current listing those Attachments Operational Condition.

that require performance due to present conditions.

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

Operator determined Attachment 3m is required due to RCIC IST adding heat to the Suppression Pool. *operator checks Attachment 3m on Attachment 1 Section A Log Initiation.

Operator determines Attachment 3k is required IAW Item 1 and T/S 4.7.3 due to current River Water level. *operator checks Attachment 3k on Attachment 1 Section A Log Initiation.

Page 3of10 JPM NUMBER: REV NUMBER: STEP NUMBER ZZ017 04 ELEMENT NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD Operator determines Attachment 3h is required IAW Item 1 and T/S 4.7.1.3.b.1 due to current River Water temperature.

operator checks Attachment 3h on Attachment 1 Section A Log Initiation.

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

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

Operator places a "1" in the Operational Condition blank. Operator determines Attachment 3z is required for tracking purposes.

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

Operator checks Attachment 5 on Attachment 1 Section A Log Initiation.

Examiner Note: Although not specifically required by the current conditions, Attachment 5 is typically used each day to track surveillance procedures and would be needed the first time a surveillance procedure with an action time is actually logged on. SAT/ UNSAT COMMENTS (Required for UNSAT) CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: Task Standard:

Operator implements the log at the beginning of the day by completing Attachment 1, Section A, of HC. OP-DL.ZZ-0026.

@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.

[IER L 1-11-3 Rec. 3b] Page 4of10 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: 2990750302 2016 NRC EXAM SRO-JPM A2 TASK: Ensure The Operating Shift Is Adequately Manned JPM NUMBER: 305H-JPM.ZZXXX SAP BET: NOH05JPZZXXE

Copy __ of __ REVISION:

00 KIA NUMBER: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (CFR: 41.10 I 43.5 I 45.12) IMPORTANCE FACTOR: RO: 2.9 SRO: 3.9 ALTERNATE PATH: D APPLICABILITY:

EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-AA-105-102, Rev. 11 TOOLS, AND EQUIPMENT:

OP-AA-105-102 ESTIMATED COMPLETION TIME: 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 Page 1of8 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 2990750302 TASK: Ensure The Operating Shift Is Adequately Manned INITIAL CONDllTONS:

1. John Smith is in the process of license re-activation for the Control Room Supervisor position in accordance with OP-AA-105-102, NRC Active License Maintenance.

Refer to the provided OP-AA-105-102, Attachment

2. 2. The Operations Training Manager has signified that the license holder is current in the Requal Program and Completion of plant-specific activation guide. 3. The License Coordinator has verified that medical/respiratory protection qualifications are current. 4. SRO John Smith and the Operations Support Manager have verified that the license holder is compliant with & concurs with restrictions on current NRC license. 5. SRO John Smith has completed the following:

Main Control Room Tour: Completed with a current CRS on July 3, 2016

Turbine Building Tour: Completed with the on watch SM on July 14, 2016

Reactor Building Tour: Completed with a current NCO on July 15, 2016

Station Service Water and Yard Tour: Completed with the on watch Yard Equipment Operator on July 20, 2016

Auxiliary Building Tour: Completed with a Current CRS on August 4, 2016.

Reviewed Shift Turnover responsibilities I procedure.

6. SRO John Smith completed the Hours on Shift as shown. INITIATING CUE: Today is August 23, 2016. PERFORM the Shift Manager review of the OP-AA-105-102, Attachment 2, for John Smith's SRO license renewal for the Control Room Supervisor position.

COMPLETE the review AND SIGN the attachment, IF appropriate, OR LIST all gaps that require resolution before the form can be signed. Page 2 of 8 JPM NUMBER: ZZXXX NAME:

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

the initiating cue, a copy of OP-AA-105-102; the marked up Attachment 2 of OP-AA-105-102; AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: OP-AA-105-102

4.2.3. DOCUMENT

the reactivation on Attachment 2, Reactivation of License Log . *operator reviews the 1. The Shift Manager shall Attachment 2 and the Initial signify that the required Conditions.

The operator OJT hours were identifies that not all tours were completed.

completed with an ACTIVE SRO license holder. *operator reviews the Attachment 2 and the Initial ' Conditions.

The operator identifies that the watch hours stood as the CRS ONLY [20 hours total] could be used towards the 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of watchstanding requirements.

Operator does NOT sign as the Shift Manager. 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 determines license reactivation requirements have not been met in accordance with OP-AA-105-102.

@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.

[IER L 1-11-3 Rec. 3b] Page 3 of 8 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: WCD_CRS_001 TASK: Perform WCD Review and Pre-Approval JPM NUMBER: 305H-JPM.ZZXXX SAP BET: NOH05JPZZXXE 2016 NRC EXAM SRO-JPM A3 Copy __ of __ REVISION:

00 K/A NUMBER: 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (CFR: 41.10 I 45.12 I 45.13) ALTERNATE PATH: D APPLICABILITY:

ROD IMPORTANCE FACTOR: RO: 3.5 SRO: 3.9 EVALUATION SETTING/METHOD:

Classroom/Perform

REFERENCES:

OP-AA-109-115, Rev. 9 M-51-1 Sheet 2, Rev. 44 TOOLS, AND EQUIPMENT:

M-51-1Sheet1and2, Rev. 50/44 [Large size]; OP-AA-109-115, Rev. 9; Technical Specifications,.Amendment 199 ' ESTIMATED COMPLETION TIME: 16 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 Page 1of11 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: WCD_CRS_001 TASK: Perform WCD Review and Pre-Approval INITIAL CONDllTONS:

1. The plant is operating at OPERATIONAL CONDITION

1. 2. The Core Spray, ADS, HPCI and RCIC systems are OPERABLE.

3. BC-HV-FOO?C, OP/V131 RHR PMP C MIN FL VLV, requires internal repair work. 4. SAP is unavailable.

INITIATING CUE: You are the licensed Authorizing Supervisor designated to review and approve Work Clearance Documents (WCDs). You have been presented with the WCD for Independent Review and Pre-Approval in accordance with OP-AA-109-115, Safety Tagging Operations.

PERFORM the following:

1. Independently check that the WCD adequately isolates the equipment to be worked. NOTE: Electrical breaker numbers are NOT required to be identified.

Additionally, the type of tag (Red blocking Tag, Worker Blocking Tag, etc.), and the sequence of blocking points, are NOT required to be identified.

2. REVIEW Technical Specifications for applicable Limiting Conditions for Operation (LCOs):

IDENTIFY AND ENTER ON THE WCD ONLY those Technical Specifications required to be entered (ACTIVE) when the system is to be placed in this configuration.

Of the LCOs entered, IDENTIFY the most limiting.

3. PRE-APPROVE the WCD; ORJE changes are required, THEN IDENTIFY/ENTER the changes on theWCD. Page 2of11 JPM NUMBER: zzxxx NAME: REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)@ CUE: PROVIDE the operator the initiating cue; M-52-1, sheets 1 and 2; OP-AA-109-115; marked up OP-AA-109-115 FORMS 1 AND 4; AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator determines beginning Operator determines correct step of the procedure.

beginning step to be 4.2.3. 4.2.3. Perform WCD Independent Operator reads Step. Review and Pre-Approval (Approving Supervisor)

1. The Approving Supervisor shall be designated by the Operations Director to approve WCDs. NOTE: Independence is maintained as Operator reads NOTE. follows:

Do not discuss the clearance with the clearance writer until the approving supervisor has developed his or her own idea of the clearance boundary

Use appropriate references (procedures, drawings, manuals, planning documents, etc.) *Separately assess an.d understand the work scope

Separately assess and understand the hazards

Separately walk down the work area, if needed

Mark up prints from a clean copy, especially for clearances on complex equipment where no historical/archived clearance is referenced

Do not read the draft boundary tag list until the above is complete 2. The Initiator and Approving Operator reads Step. Supervisor shall be different individuals and independent.

At least one individual must be a currently licensed SRO. [CD-538E]

Page 3of11 JPM NUMBER: zzxxx NAME:

REV NUMBER: 00 DATE: STEP NUMBER ELEMENT 3. Perform the following:

-Review applicable documents and drawings.

-Independently check that the WCD adequately isolates the equipment to be worked. STANDARD (*Critical Step) (#Sequential Step) Examiner Note: Only specific portions of 4.2.3.3 are being performed.

operator:

Reviews M-52-1 and the WCD; Determines that H1 BC BC-V205 in the closed position needs to be added to the WCD; Adds this information to the WCD. Examiner Note: Tagging Point Description is NOT critical.

SAT/ UNSAT COMMENTS (Required for UNSAT)@ CUE: !f operator requests additional information to complete the Tagging Point Description, STATE exact description is not required at this time. Review applicable

operator lists the following Technical Specification on the WCD: Limiting Conditions for Operation (LCO) and ensure that potential Technical Specification

Action Statements are identified.

TS 3.6.2.3 Action a.-One suppression pool cooling loop inoperable

-72 hr. LCO 4. !E changes are required, THEN return the tagging package to the Initiator.

Examiner Note: The following Technical Specifications may be listed by are NOT critical:

3.5.1.b; 3.6.2.2; 3.6.2.3; 3.6.3; 3.3.7.4; and 3.3.7.5. Operator does NOT sign for approval, and returns the package. 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 the required portions of the Approving Supervisor's Independent Review of the WCD in accordance with OP-AA-109-115.

@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.

[IER L 1-11-3 Rec. 3b] Page 4of11 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK NUMBER: 4000270401 2016 NRC EXAM RO/SRO-JPM A4 Copy __ of __ TASK: Respond To An Abnormal Release Of Gaseous Radioactivity JPM NUMBER: 305H-JPM.ZZ019 REVISION:

04 SAP BET: NOH05JPZZ19E K/A NUMBER: 2.3.11 Ability to control radiation releases. (CFR: 41.11 I 43.4 I 45.10) ALTERNATE PATH: D APPLICABILITY: IMPORTANCE FACTOR: RO: 3.8 SRO: 4.3 EVALUATION SETTING/METHOD:

Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0004, Rev. 6 HC.OP-DL.ZZ-0026, Rev. 152 TOOLS, AND EQUIPMENT:

Calculator ESTIMATED COMPLETION TIME: 10

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 Page 1 of 10 JOB PERFORMANCE MEASURE SYSTEM: Administrative TASK NUMBER: 4000270401 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity INITIAL CONDllTONS:

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590. 2. SPDS is unavailable.

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

4. NPV Exh Flow instrumentation channel 9AX300 is inoperable.

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

5. Monitor Item 136 display is 001. INITIATING CUE: DETERMINE the Release Rate of NOBLE GAS from the NPV in accordance with HC.OP-AB.CONT-0004, Action A.4. Page 2of10 JPM NUMBER: ZZ019 NAME:

REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue; HC.OP-DL.ZZ-0026(0), Attachment 3u; AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains the correct Operator obtains procedure procedure.

HC.OP-AB.CONT-0004.

Operator determines beginning Operator determines correct step of the procedure.

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

USE the SPDS Noble Gas Total. OR

USE one of the Formulas in Table "A". I IF the emuent (µCi/see) channel on the RM-11 is NOT operatmg for a specJfJc plant vent, THEN CALCULATE the Noble Gas release rate for that vent usin 0.1g. 3. The earthquake was felt inside the Main Control Room. 4. Control Room Annunciator C6-C4 (SEISMIC MON PNL C673) is in alarm. 5. ON Panel 1 OC673:

The SMA-3 Event Indicator is White.
The Strong Motion Accelerograph Tape Machines have advanced but are not currently running.
The AMBER alarm light on the Seismic Switch Power Supply Drawer is lit. 6. Numerous amber lights and 3 red lights are lit on the response Seismic Response Spectrum Annunciator.
7. A LOCA results. The Reactor is successfully scrammed, with RPV level dropping rapidly to -250"; then stabilizing between -225" and -205, and being maintained using all available ECCS (2 LPCI Loops only). 8. Drywell Pressure peaked at 44 psig, then dropped to < 2 psig over the next 90 seconds, and continues to slowly drop. 9. The current 33 ft. elevation wind direction is from 163° at 11 mph. 10. Plant Effluent activity is:
1.17E+01 µCi/sec Noble Gas
1.1 ?E-02 µCi/sec 1-131 11. DAPA monitors indicate:
2.000E+OO DAPA A
1.500E+OO 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 2of16 JPM NUMBER: ECG006 NAME:
REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER ST ART 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 hot OPCONs apply to this classification.
2. REVIEW EAL categories Operator assesses the initial and subcategories on the conditions, and determines that H, appropriate and R, are appropriate ECG flowcharts/wallcharts.
categories; and H1, and R1 are appropriate subcategories.
Page 3of16 JPM NUMBER: ECG006 NAME: REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for 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 H1, and R1. REVIEW EALs in the Operator determines that HA 1 .1 , subcategory beginning with the lowest emergency and HU1 .1 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 examines the FPB categories in the left categories in the left column of the column of the table. table. b. SELECT the category Operator selects categories RPV that most likely Level; and RPV/Drywell Pressure coincides with event /Temperature/H2
& 02 Levels most conditions.
likely coincide with event conditions.
c. REVIEW all thresholds Operator reviews all thresholds in in this category for each of the categories identified in each fission product 5.b for each fission product barrier, barrier. and determines FB1 .L, RB1 .L, RB2.L, and CB1 .L apply to this event. Page 4of16 JPM NUMBER: ECG006 NAME:
REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ d. For each threshold that Operator proceeds to the FPB is exceeded, IDENTIFY Table to determine the point values its point value and and classification level. DETERMINE the classification level in accordance with the instructions on the Fission Product Barrier Table (or in EAL Technical Bases, Attachment 1 ). Hope Creek-Fission Product Barrier Table NOTE1 The Primary Containment Operator reads NOTE. Barrier should not be declared lost or potentially lost based on exceeding Technical Specification action statement criteria, unless there is an event in progress requiring
' mitigation by the Primary Containment barrier. When no event is in progress (Loss or Potential Loss of either Fuel Clad and/or RCS barrier) the Primary Containment Barrier status is addressed by Technical Specifications.
Page 5of16 JPM NUMBER: ECG006 REV NUMBER: 10 STEP NUMBER ELEMENT Use of Fjssion Product Barrier Table A point system is used lo dotennine the Emergency Classification Level based on the Fission Product Barrier Table. Each Fission Product Barrier Loss and Poteotial loss threshold is assigned a point value as noted below. Perform the IOllowing
1. Review all columns of the Fission Product Barrier Table and identify which need further review. 2. For each of the three barriers, detem1ine the EAL with the highest point value. No more than one EAL should be selected for each barrier 3. Add the point values for the three barriers.
4. Classify based on the point value sum as follows. Ms:um ... ::. 3 Emergency Acbon levels {EAls) $l7E AREA \...oss or lass EMERGENCY c' ANY -barn"" 1--0SS r:l ANY two C-ENE?.A:..
EME?GENCY AliQ Loss ECG ATT# NAME: DATE: (*Critical Step) (#Sequential Step) STANDARD Operator identifies the point values FB1 .L = 5 points, RB1 .L(OR RB2.L) = 5 points, and CB1 .L = 3 points. *operator adds the values, for a total of: 13 points -General Emergency.
Examiners Note: Determining this value for future use is critical; marking it on the FPB Table is not. Page 6of16 SAT/ UNSAT COMMENTS (Required for UNSAT JPM NUMBER: ECG006 NAME:
REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ EP-HC-111-101
6. REVIEW the associated Operator reviews the EALs EALs as com pared to the identified in Step 8.4.3 and 4, and event and SELECT the selects EAL HA 1.1 as the highest highest appropriate emergency action level met or emergency.
If identification exceeded (ALERT). However, the of an EAL is questionable classification determined by the refer to paragraph 8.1 FPB Table (GENERAL above. EMERGENCY) is the highest. 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 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 seperately reported as long as the applicable N/A information is communicated to the NRG using ECG Attachment 5, EP-HC-111-F5, NRC Data Sheet & Completion Reference.
Page 7of16 JPM NUMBER: ECG006 NAME: REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 8. When the Shift Manager Operator requests STA/IA (SM) is the Emergency verification of classification.
Coordinator, the Shift Examiner Note: Due to time spent Technical Advisor (STA} is responsible to perform an assessing and/or nature of JPM independent verification of administration, Operator may not the EAL classification.
The request verification.
ST A verification does not alleviate the requirement of the SM to make a timely classification.
Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on-shift SRO, the Independent Assessor.
CUE: IF the Operator requests the STA/IA to independently verify the EAL Classification, THEN INFORM the Operator the STA/IA is not available.
' 9. IDENTIFY and Operator identifies and implements IMPLEMENT the EP-HC-111-F4, and refers to EP-referenced ECG form HC-111-102 as a guide for correct based on the Emergency description wording for entry on the Classification Level. ICMF for all EALs.
Un:..1sual Event lmpletn*'nt EP*+IC 111 .f 1
Alert lmp!ernent EP*tiC, l l 1-F2
site Area Emergency lmplemenl EP-HC-l 11-F3
General E:.mergency lmpfen1ent
unusual Event (Common Site) Implement EP-HC-111-F24 REFER to EP-HC-111-102, Hope Creek Emergency Classification Description Table, as a guide for correct description wording for entry on the Initial Contact Message Form (ICMF) for all EALs. EP-HC-111-F4 ATTACHMENT 4 GENERAL 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 Primary and Secondary Communicators.
Page 8of16 JPM NUMBER: ECG006 NAME:
REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 2. IF a Security Event is in Operator determines Step is not progress, THEN applicable and marks Step 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 ST A/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 commences filling out Independent Verification ICMF and initials Step. is obtained:
DECLARE the *operator declares a General
Emergency, places time and GENERAL date in the appropriate spots in the EMERGENCY (enter ICMF, time and date on ICMF) and initials the step as the EC. Examiners Note: NOTE the declaration time that the operator entered on the ICMF. The difference between the ST ART TIME and the "DECLARED AT" TIME is the first critical time (15 min). Time: Page 9of16 JPM NUMBER: ECG006 NAME:
REV NUMBER: 10 DATE: I (*Critical Step) COMMENTS STEP SAT/ NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@
COMPLETE I *operator places the EAL #(s): APPROVE the ICMF FB1.L, RB1.L(OR RB2.L) and CB1 .L, a description of the event, checks NO Release in progress, enters the wind direction and speed, determines PAR, 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 EALs FB1 .L, RB1 .L(OR RB2.L), and CB1 .L. 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 ST A/IA perform accuracy peer check of the an accuracy peer check of the completed ICMF completed ICMF. CUE: IF the Operator requests the STA/IA to perform an. accuracy peer check of the completed ICMF, THEN INFORM the Operator the STA/IA is not available.
6. Continue with NOTIFICATION AND ACTIVATION as follows: Operator activates the ERO per posted instructions titled Training
If not previously Use Emergency Callout Activation performed, ACTIVATE and initials Step. I DIRECT Examiner Note: ENSURE the ACTIVATION of ERO Emergency Callout operator is using the Simulator (EP 96-003) Training Activation instructions.
CUE: If asked/requested to activate the ERO Emergency Callout, ST ATE "The ERO Callout is complete." Page 10of16 JPM NUMBER: ECG006 NAME:
REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@
DIRECT the Primary *operator provides the ICMF to Communicator to Primary Communicator and implement ECG directs implementation of Att.6 Attachment 6 and initials Step. Examiner Note: The difference between the "DECLARED AT" TIME and this LOG TIME is the second critical time (13 min.). Time: CUE: Role-play as Primary Communicator and repeat back the directions given.
DIRECT the Secondary
operator directs CM2 to Communicator to implement Att. 8 for a GENERAL implement ECG EMERGENCY Attachment 8 for a GENERAL and initials Step. EMERGENCY CUE: Role-play as Secondary Communicator 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 General Emergency in accordance with EALs FB1 .L, RB1 .L(OR RB2.L), and CB1 .L; initiates a PAR; and makes notifications within identified Critical Times in accordance with EP-HC-111-101.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 11of16 '
JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod and Drive Mechanism TASK NUMBER: 4000040401 TASK: Respond To An Uncoupled Control Rod JPM NUMBER: 305H-JPM.BF011 SAP BET: NOH05JPBF11 E 2016 NRC EXAM JPMA Copy __ of __ REVISION:
04 KIA NUMBER: 201003 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: (CFR: 41.5 I 45.6) ALTERNATE PATH: C8J APPLICABILITY:
A2.02 Uncoupled rod RO C8J IMPORTANCE FACTOR: RO: 3.7 SRO: 3.8 SRO C8J EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-ST.BF-0001 Rev. 31 HC.OP-AB.IC-0001 Rev. 16 TOOLS, AND EQUIPMENT:
None ESTIMATED COMPLETION TIME: 33 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 Page 1of14 JOB PERFORMANCE MEASURE SYSTEM: Control Rod and Drive Mechanism TASK NUMBER: 4000040401 TASK: Respond To An Uncoupled Control Rod INITIAL CONDllTONS: 1 . The Plant is operating at 100% power. 2. Maintenance was performed on the position indication circuit of rod 38-03 3. The maintenance is complete.
4. As part of the retest requirements, performance of HC.OP-ST.BF-0001 Control Rod Drive Exercise -Weekly is required for control rod 38-03 only. 5. The "ON DUTY" Reactor Engineer has been notified that control rod 38-03 will be exercised IAW HC.OP-ST.BF-0001.
6. Use CRIDS for OD-7 control rod positions.
7. The Reactor Engineer has approved exercising rod 38-03 at 100% power. 8. Stall flows are NOT required.
9. HC.OP-ST.BF-0001, retest for control rod 38-03, has been entered in the Control Room log. INITIATING CUE: EXERCISE control rod 38-03 IAW HC.OP-ST.BF-0001.
Page 2of14 JPM NUMBER: BF011 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue, marked-up copy of HC.OP-ST.BF-0001, AND ENTER ST ART 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, THEN INFORM operator that all are satisfied.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 5.1. 5.1 LOG test start time in the Operator requests the procedure Control Room log(s). be logged in the Control Room log and initials Step. CUE: The start time for HC.OP-ST.BF-0001 for retest of rod 38-03 only, has been logged in the Control Room log. ' 5.2 ENSURE all prerequisites of Operator ensures that all Section 2.0 are satisfied.
prerequisites have been satisfied and initials Step. CUE: If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.
5.3 ENSURE
Attachment 1, Operator observes Attachment 1 , Section 1.0 has been Section 1.0 has been completed completed AND Regular AND Retest is indicated and initials Surveillance OR Retest is Step. indicated.
5.4 OBTAIN
a computer printout of Operator displays OD-7 from the current Control Rod GRIDS terminal and initials Step. positions. (e.g. OD-7) CUE: Provide operator printout of OD-7 from CRIDS. 5.5 OBSERVE proper response of Operator reviews the requirement the Nuclear Instrumentation to observe proper response of the while withdrawing OR inserting Nuclear Instrumentation while all Control Rods. withdrawing OR inserting all Control Rods and initials Step. 5.6 SELECT the next Control Rod *#Operator presses ROD AND RECORD or verify the SELECT MODULE 38-03 initial Control Rod position on pushbutton Attachment
2. and initials Step. Page 3of14 JPM NUMBER: BF011 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 5.7 lE Control Rod is at position 00, Operator determines that this step RECORD final Control Rod is N/A and marks Step N/A. position on Attachment
2. All other blocks are N/A for this rod. 5.8 OBSERVE approximately 6 Operators observes approximately gpm total flow through both the 6 gpm total flow through both the insert AND withdraw Stabilizing insert AND withdraw Stabilizing Valves as indicated on CRID's Valves as indicated on CRID's point 82117. [70044199]
point B2117 and initials Step. NOTE The following two steps will Operator reads NOTE and initials exercise the 1-BF-V138, Note. Cooling Water Header Check Valve, as required by TIS 4.0.5. If a "failed position" is encountered when a single notch insertion is attempted, an alternate position may be selected to insert the rod, provided that guidance is obtained from Reactor Engineering.
In this situation the remarks section of Attachment 3 should document the alternate position utilized.
5.9 INSERT
the selected Control *#operator momentarily Rod one notch (or as directed presses the ROD MOTION by Reactor Engineering)
AND CONTROLS INSERT pushbutton PERFORM the following:
[T/S 4.1.3.1.2, TIS 4.1.3.7] and initials Step. 5.9.1 ENSURE proper operation of Operator observes the CONTROL the RPIS. ROD POSITION FOUR ROD DISPLAY, RWM, or GRIDS indicates control rod movement to position 46 and initials Step. 5.9.2 lE a Control rod is inadvertently Operator determines that this step positioned at other than the is N/A and marks Step N/A. desired position, THEN IMPLEMENT the associated guidance contained in the Reactor Engineering Weekly Guidance AND CONTACT Reactor Engineering.
Page 4of14 JPM NUMBER: BF011 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)(@ 5.9.3 lE the control rod does not Operator determines that this step insert to the next notch after is N/A and marks Step N/A. one attempt, PERFORM the following:
... 5.9.4 INDICATE the condition of Operator then indicates the RPIS RPIS indication on Attachment indication is SAT on Attachment 2 2. and initials Step. 5.10 IF the position recorded in Step Operator determines the position 5.6 is an intermediate position, recorded in Step 5. 7 is NOT an THEN PERFORM Step 5.10.1, intermediate position, continues at OTHERWISE, GO TO Step step 5.10.2 and initials Step. 5.10.2 to return the control rod to its original position:
... NOTE IF drive water pressure was Operator reads NOTE and increased to withdraw a control determines the NOTE is not rod from position 46, the same applicable and initials NOTE. or slightly higher pressure should be used to perform the ' uncoupling check. [80009340]
Control Rods experiencing coupling problems should be single-notched to 48 (with settle) prior to using continuous withdraw to verify coupling.
5.10.2 WITHDRAW the control rod to *#Operator simultaneously . , position 48 AND PERFORM presses AND holds both the the following while giving the WITHDRAW pushbutton AND the selected Control Rod a CONTINUOUS WITHDRAW continuous withdraw signal: pushbutton
[T/S 4.1.3.6, T/S 4.1.3.7] and initials Step. A. OBSERVE the following as indication of the Control Rod being coupled: 1. ROD OVERTRAVEL alarm Operator observes OHA C6-F3 does NOT annunciate.
ROD OVERTRAVEL DOES annunciate.
CRIDS C071, ROD OVERTRAVEL, in alarm. Operator releases both the WITHDRAW pushbutton AND the CONTINUOUS WITHDRAW pushbutton.
2. Red Full Out light Operator observes the red FULL illuminates on the Full Core OUT light on the Full Core Display Display. EXTINGUISHES.
Page 5of14 JPM NUMBER: BF011 NAME: REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 3. RPIS indicates the Control Operator observes RPIS does Rod is full out (48). indicate position 48 on OD-7. However, indicates 49, in alarm, on CRIDS page 249. 4. Proper response of the Operator recognizes the expected Nuclear Instrumentation response of the Nuclear while withdrawing the Instrumentation while withdrawing Control Rod. the Control Rod. Examiner Note: The expected response for a rod from 46 to 48 is negligible.
B. INDICATE on Attachment 2 the Operator indicates the coupling condition of Coupling Check. check is UNSAT on Attachment
2. NOTE Stall flows need to be taken at Operator reads NOTE and initials least each month. Stall flows NOTE. should be recorded the first ' time this test is performed each month OR as requested by System Engineer.
C. PERFORM the following for Based on the Initial Conditions, stall flow: ... Operator determines Stall Flow is NOT required.
Operator marks the step N/A. D. lE the CRD over travels, THEN Operator informs the CRS of IMPLEMENT HC.OP-AB.IC-uncoupled control rod and entry 0001(0), Control Rod. condition into HC.OP-AB.IC-0001 and initials Step. CUE: Acknowledge the report, and DIRECT the Operator to implement Condition D of HC.OP-AB.IC-0001. HC.OP-AB.IC-0001 CONDITION D, Uncoupled Rod AND Movement Permitted by the RWM NOTE 1 1. Tech Spec 3.1.3.6 has a 2 Operator reads NOTE 1. hour time limit associated with it. D.1 OBTAIN Reactor Engineering Operator requests Reactor guidance to recouple the Engineering guidance to recouple Control Rod. the Control Rod and initials Step. CUE: INFORM the Operator that Reactor Engineer's guidance in NOT available.
Page 6of14 JPM NUMBER: BF011 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ D.2 lE Reactor Engineering Operator determines step D.2 is guidance CANNOT be applicable and initials Step. obtained, THEN RECOUPLE the Control Rod as follows: a. INSERT the CRD no more Operator single notch inserts rod than 2 notches from the 38-03 to position 46 (no more than point of discovery.
position 44) using INSERT PB and initials Step. Examiner Note: Due to the rod being at Overtravel, it will take two single notch insertions to insert the rod to 46. The first insertion will settle the rod at 48 and may bring in OHA C6 E3 ROD DRIFT. IF ROD DRIFT alarm comes in, THEN operator will respond using OHA C6-E3 Alarm Response Procedure and determine rod 38-03 caused the alarm. b. Single Notch WITHDRAW single notch the Control Rod to its withdraws rod 38-03 to position original position AND 48. VERIFY expected response.
Operator observes correct response of the control rod and initials Step. c. PERFORM a coupling Operator requests copy of HG.OP-check on the associated ST.BF-0001.
control rod IAW ST.BF-0001. CUE: Provide operator 2nd marked up copy of HC.OP-ST.BF-0001 IF requested.
HC.OP-ST .BF-0001 5.10.2 WITHDRAW the control rod to *#Operator simultaneously position 48 AND PERFORM presses AND holds both the the following while giving the WITHDRAW pushbutton AND the selected Control Rod a CONTINUOUS WITHDRAW continuous withdraw signal: pushbutton.
[T/S 4.1.3.6, T/S 4.1.3.7) A. OBSERVE the following as indication of the Control Rod Operator observes OHA C6 F3 being coupled: ROD OVERTRAVEL does NOT 1. ROD OVERT RAVEL alarm annunciate and initials Step. does NOT annunciate.
Page 7of14 JPM NUMBER: BF011 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 2. Red Full Out light Operator observes the red FULL illuminates on the Full Core OUT light on the Full Core Display Display. illuminates and initials Step. 3. RPIS indicates the Control Operator observes RPIS indicates Rod is full out (48). the Control Rod is full out (48) and initials Step. 4. Proper response of the Operator recognizes the expected Nuclear Instrumentation response of the Nuclear while withdrawing the Instrumentation while withdrawing Control Rod. the Control Rod and initials Step. Examiner Note: The expected response for a rod at 48 is negligible.
B. INDICATE on Attachment 2 the Operator indicates the coupling condition of Coupling Check. check is SAT on Attachment 2 and initials Step. Examiner Note: Operator may ' initial D.2.c or HC.OP-AB.IC-0001 at this time. HC.OP-AB.IC-0001 CONDITION D, Uncoupled Rod AND Movement Permitted by the RWM D.3 RESTRICT all further Operator informs the CRS that all withdrawals of this rod to further withdrawals of this rod Single Notch movement until should be restricted to Single repairs have been completed.
Notch movement until repairs have been completed.
CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".
STOP TIME: Task Standard:
Operator exercises, and re-couples, control rod 38-03 IAW HC.OP-ST.BF-0001.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 8of14 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Feedwater TASK NUMBER: 2590120101 TASK: Place The First RFPT In Service JPM NUMBER: 305H-JPM.AE005 SAP BET: NOH05JPAE05E 2016 NRC EXAM JPM B Copy __ of __ REVISION:
10 KIA NUMBER: 259001 A4. Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 TO 45.8) A4.02 Manually start/control a RFP/TDRFP IMPORTANCE FACTOR: RO: 3.9 SRO: 3.7 ALTERNATE PATH: D APPLICABILITY: EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-SO.AE-0001 Rev. 72 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 Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: Feedwater TASK NUMBER: 2590120101 TASK: Place The First RFPT In Service INITIAL CONDllTONS:
1. A plant startup from cold shutdown is in progress IAW HC.OP-IO.ZZ-0003.
2. Reactor Pressure is approximately 500 psig. 3. AP101 and BP101 RFPs are on Recirc IAW Section 5.3 of HC.OP-SO.AE-0001.
4. Startup level control is in AUTO Reactor Vessel level control. 5. Chemistry is ready to place Condensate Polisher Vessels in service as required.
INITIATING CUE: PLACE Reactor Feed Pump AP101 in service in Manual control in accordance with 5.4 of HC.OP-SO.AE-0001. Page 2of10 JPM NUMBER: AE005 NAME:
REV NUMBER: 10 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT) CUE: PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains and locates Operator obtains the correct procedure HC.OP-SO.AE-procedure.
0001. Operator reviews precautions Operator reviews precautions and and limitations.
limitations.
CUE: IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 5.4. 5.4.1 ENSURE all prerequisites of Operator ensures that all ' Section 2.4 are satisfied.
prerequisites have been satisfied, and initials Step. ' CAUTION Opening the HV-1769A{B,C)
Operator reads and initials REACTOR FEED PUMP CAUTION. A(B,C) DISCH STOP CHK VLV MOT OPER completes the RFP start logic. IF adequate SCP(s) are NOT in service, a RFP trip will occur. (REFER to Attachment 1.) 5.4.2 ENSURE HV-1769A(B,C), *#Operator opens HV-1769A, REACTOR FEED PUMP A(B,C) DISCH STOP CHK VLV and initials Step. MOT OPER, is open. NOTE Placing the initial Reactor Feed Operator reads and initials NOTE. Pump in service will cause a transient on the pump rotating assembly.
Vibration and/or axial displacement alarms are possible immediately after placing the pump in service, and are expected to clear after the pump is in service and the discharge pressure is stable. Page 3of10 JPM NUMBER: AE005 REV NUMBER: 10
(*Critical Step) SAT/ COMMENTS STEP ELEMENT (#Sequential Step) (Required for NUMBER STANDARD UNSAT UNSAT) CAUTION Reactor Feed Pump Turbine Operator reads and initials Critical Speed is approximately CAUTION. 3400 rpm. Operation in the range of 3250 rpm to 3550 rpm should be minimized.
5.4.3 PRESS
RFPT A(B,C) SPEED *#operator presses RFPT A CTRLR SPD DEMAND INC i SPEED CTRLR SPD DEMAND pushbutton as required to INC i pushbutton as required to establish approximately 150 to establish approximately 150 to 450 psid across the Startup 450 psid across the Startup Valves to achieve positive Valve, response on the startup valves. and initials Step. 5.4.4 CLOSE HV-1772A(B,C), RFPT *operator closes HV-1772A, A(B,C) STEAM LOW PRESSURE SUPPLY STOP and initials Step. VLV BELOW SEAT DRAIN MOV. 5.4.5 CLOSE HV-1786, RFP *#Operator closes HV-1786, BYPASS STOP VLV. and initials Step. NOTE For RFP Turbine speed ;::: 5000 Operator reads and initials NOTE. rpm increase the RFPT RECIRC FLOW CTRL A{B,C) setpoint to 4500 gpm. If possible, maintain RFP DISCH Press such that level control is accomplished via LV-1785. Valve differential pressure of < 450 psid should be attempted to be maintained.
CAUTION Carefully monitor for vessel Operator reads and initials level swings AND RFPT CAUTION. hunting when controlling differential pressure across the S/U valves in AUTO AND below 900 psig RX Pressure.
Page 4of10 JPM NUMBER: AE005 NAME:
REV NUMBER: 10 DATE: STEP NUMBER 5.4.6 ELEMENT CONTROL the differential pressure across the startup valves automatically or manually by performing the following:
A. MANUAL 1. Intermittently PRESS RFPT A(B,C) SPEED CONTROLLER SPD DEMAND INC I OR DEC ! pushbutton as necessary to maintain RFP discharge press above Reactor pressure to allow Startup Valve to Control Reactor Vessel level. (*Critical Step) (#Sequential Step) STANDARD Examiner Note: Operator may adjust A RFP speed again to ensure dp in the range of 150 to 450 psid. Operator reads and initials Step. SAT/ UNSAT COMMENTS (Required for UNSAT) CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".
STOP TIME: -------Task Standard:
Operator places AP101 Reactor Feed Pump in service in Manual control in accordance with HC.OP-SO.AE-0001.
Page 5of10 JOB PERFORMANCE MEASURE STATION: Hope Creek 2016 NRC EXAM JPMC Copy __ of __ SYSTEM: Integrated Operating Procedures TASK NUMBER: 30002090101 TASK: Perform a Cooldown Using Bypass Valves JPM NUMBER: 305H-JPM.AC008 SAP BET: NOH05JPAC08E REVISION:
01 K/A NUMBER: 241000 A4. Ability to manually operate and/or monitor in the control room: (CFR: 41. 7 I 45.5 TO 45.8) A4.02 Reactor pressure IMPORTANCE FACTOR: RO: 4.1 ALTERNATE PATH: D APPLICABILITY: EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-IO.ZZ-0004, Rev. 100 TOOLS, AND EQUIPMENT:
None SRO: 4.1 ESTIMATED COMPLETION TIME: 16 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 Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: Integrated Operating Procedures TASK NUMBER: 30002090101 TASK: Perform a Cool down Using Bypass Valves INITIAL CONDllTONS:
1. A plant shut down is in progress for a refueling outage. 2. HC.OP-IO.ZZ-0004 has been implemented through Step 5.1.48. INITIATING CUE: COMMENCE a Reactor Cooldown and Depressurization to 530 psig in accordance with Step 5.2.1.B of HC.OP-IO.ZZ-0004:
Another operator will plot cooldown rate. Page 2of10 JPM NUMBER: AC008 NAME:
REV NUMBER: 01 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains procedure Operator obtains the correct HC.OP-IO.ZZ-0004.
procedure.
Operator reviews precautions Operator reviews precautions and and limitations.
limitations, and initials each one. CUE: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
2.0 PREREQUISITES
ENSURE all personnel who are Operator completes Attachment 1, to perform any step(s) in this Section 1.0, prior to performing any procedure have completed part of this procedure, and initials Attachment 1, Section 1.0, prior Step. to performing any part of this ' procedure.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 5.2.1.B. NOTE Steam Loads, Decay Heat, and Operator reads and initials NOTE. Feed will directly affect Cooldown I Depressurization.
Impact of these variables, ,, regardless of DEHC Control mode selected, MUST be continuously evaluated for impact on the cooldown.
The cooldown rate should be limited to 60°F per hour when above 200 psig to preclude RWCU flashing.
At approximately 200 psig reactor pressure, the cooldown rate should be limited to approximately 30° F/hr to prevent excessive cavitation of the RWCU pump. Page 3of10 JPM NUMBER: AC008 NAME: REV NUMBER: 01 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)(a) 5.2.1. CONTINUE/MAINTAIN a cooldown rate of::; 60°F/hr using Rx Cooldown mode, Pressure Control mode OR Bypass Valve Manual Jack as follows: A. Establish PRESSURE Operator determines and marks CONTROL as ... this Step as N/A. NOTE When Rx Cooldown mode is Operator reads and initials NOTE. initiated with a bypass valve open, a minor Pressure Rise will occur. This pressure rise should be anticipated when placing Rx Cooldown controller in service. Any cooldown that has occurred since the shutdown must be considered prior to ' establishing Rx Cooldown mode in determining initial cooldown so as NOT to exceed 60°F/hr. Once Rx Cooldown mode is established, the INTENT is to remain on the Rx Cooldown controller for the duration of the Cooldown I Depressurization.
An In-Progress Cooldown can be interrupted to support plant manipulations without exiting the Rx Cooldown mode by establishing the temperature Setpoint at the desired hold point on the Cooldown Controller.
5.2.1.B. B. IF desired, Establish
operator selects !control! , REACTOR COOLDOWN and IRX Cooldown I. as follows: 1. SELECT IControll , and initials Step. IRX Cooldownl
2. SELECT jRamp
operator selects !Ramp AND ENTER desired and enters a desired rate that rate not to exceed 60 does not exceed 60 deg F/hr, deg F/hr. and initials Step. Page 4of10 JPM NUMBER: AC008 NAME:
REV NUMBER: 01 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 3. SELECT
operator selects AND ENTER desired and enters a value for the temperature.
desired temperature, and initials Step. Examiner Note: Desired temperature is approximately 470F :t20F. 4. SELECT Reactor *#operator selects Reactor Cooldown /ON/ AND Cooldown /ON/, VERIFY Rx Cooldown Controlling indication is verifies Rx Cooldown Controlling observed.
indication is observed, and initials Step. 5. MAINTAIN Throttle Operator maintains Throttle Pressure Set, Pressure Pressure Set, Pressure Setpoint Setpoint approximately approximately 50-100 psig above 50-100 psig above Throttle Pre?"sure not to exceed Throttle Pressure not to 905 psig, and initials Step. exceed 905 psig. Examiner Note: Pressure Setpoint is currently 905 psig. 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 establishes a cooldown in accordance with Step 5.2.1.B of HC.OP-10.ZZ-0004.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 5of10 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: High Pressure Coolant Injection TASK NUMBER: 2060180201 TASK: Place HPCI in Full Flow Test Operation JPM NUMBER: 305H-JPM.BJ014 SAP BET: NOH05JPBJ14E 2016 NRC EXAM JPM D Copy __ of __ REVISION:
04 KIA NUMBER: 206000 A4. Ability to manually operate and/or monitor in the control room: (CFR: 41. 7 I 45.5 TO 45.8) A4.06 Reactor pressure:
BWR-2,3,4 ALTERNATE PATH: [8J APPLICABILITY:
RO [8J IMPORTANCE FACTOR: RO: 4.3 SRO: 4.3 SRO [8J EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-AB.ZZ-0001, Rev 31 TOOLS, AND EQUIPMENT:
None ESTIMATED COMPLETION TIME: 13 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes ----JPM PERFORMED BY: GRADE: SAT D UNSAT D ACTUAL COMPLETION TIME: Minutes ----ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes ----REASON IF UNSATISFACTORY:
EVALUATOR:
DATE: Signature Page 1of13 JOB PERFORMANCE MEASURE SYSTEM: High Pressure Coolant Injection TASK NUMBER: 2060180201 TASK: Place HPCI in Full Flow Test Operation INITIAL CONDllTONS:
1. The Reactor has scrammed due to a spurious Group 1 isolation.
2. All control rods are full in. 3. RCIC has automatically initiated on low reactor water level and is injecting to the RPV. 4. HPCI has automatically initiated on low reactor water level. 5. Reactor water level is currently approximately-10 inches and slowly rising. 6. RHR Loop Bis in Suppression Pool Cooling. 7. Another operator is controlling RPV level and pressure.
INITIATING CUE: PLACE HPCI into the Full Flow Test Mode in order to commence a plant cooldown in accordance with HC.OP-AB.ZZ-0001 (Q), Attachment
6. The simulator will remain in FREEZE until you are ready to start the task. Page 2of13 JPM NUMBER: BJ014 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue, ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue AND states ready to begin. START TIME: CUE: PLACE the simulator in RUN, and inform the Operator that the simulator is in RUN. Operator obtains and locates Operator obtains the correct procedure.
procedure.
NOTE Loss of 1AD481, 1CD481, Operator reads and initials NOTE. 1AD482, or 1CD482 may affect controls and indication.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 2.0 on page 6 of 6. 2.0 lE HPCI is in the Injection Mode of Operati,an, THEN PERFORM the following:
A. IF necessary, RESET HPCI *operator depresses the RESET INITIATION LOGIC. HPCI INITIATION LOGIC pushbutton, and initials Step. B. ADJUST FIC R600 HPCI Operator observes zero % FLOW (STPT) to indication is reached on FIC-R600, zero% and initials Step. Examiner Note: Setpoint is already at zero%. C. WHEN FLOW indicates
operator observes zero gpm is zero gpm THEN CLOSE reached, and depresses the HV-F006. CLOSE pushbutton for HV-F006, and initials Step. Examiner Note: HPCI flow is currently zero gpm. D. CLOSE HV-8278. *operator depresses the CLOSE pushbutton for HV-8278, E. ENSURE HPCI AND RCIC Operator observes HPCI AND Suctions are lined up to the RCIC Suctions are lined up to the CST. CST. (OPEN lights for BJ-HV-F004 and BD-HV-F010 are illuminated) and initials Step. Page 3of13 JPM NUMBER: BJ014 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ F. PRESS HV-F008 INCR PB *operator depresses the INCR for == 20 seconds pushbutton for approximately 20 seconds and observes the OPEN light illuminate, resulting in dual indication for the FOOS, and initials Step. Examiner Note: Any timing method is acceptable, as the time requirement is "approximately" 20 seconds. G. OPEN AP-HV-F011.
operator depresses the AP-HV-F011 OPEN pushbutton, and initials Step. Examiner Note: Pressing the AP-HV-F011 pushbutton will activate ET-1, starting a slow rise in Suppression Pool water level. I H. ADJUST FIC-R600 *operator depresses the Raise setpoint to achieve 3000 and/or Lower Setpoint gpm flow. Pushbutton(s) until HPCI flow indicates approximately 3000 gpm on FIC-R600, and initials Step. Examiner Note: WHEN Suppression Pool Water Level reaches 78.5 inches, Overhead Annunciator B1-C3 SUPPRESSION POOL LEVEL HI/LO alarm and HPCI suction transfer occur. Performance of the next Step may/may not be observed.
J. THROTTLE HV-F008 AND Operator throttles and adjusts FIC-ADJUST FIC-R600 R600 setpoint, as necessary, up to setpoint, as necessary, up and including full flow rate, to to and including full flow control HPCI pump parameters/
rate, to control HPCI pump reactor pressure.
parameters/reactor pressure.
Page 4of13 JPM NUMBER: REV NUMBER: STEP NUMBER BJ014 04 ELEMENT NAME:
DATE: (*Critical Step) (#Sequential Step) STANDARD Operator identifies HPCI Suction Swap is occurring based on OHA B1-C3 and HPCI Pump suction auto-transferring from the CST (HV-F004) to the Torus (HV-F042).
Operator announces
'Suppression Pool Level Hi(/Lo)', and informs CRS. Examiner Note: The following actions may be performed by the Operator using the guidance from HC.OP-AB.ZZ-0001, Attachment 6 section for HPCI Suction Transfer to CST without/prior to direction from the CRS based on the direction in step 1.0 of that section. SAT/ UNSAT COMMENTS (Required for UNSAT)@ Operator identifies the need to perform HC.OP-AB.ZZ-0001, Attachment 6 section for HPCI Suction Transfer to CST and take the required actions from that section. I CUE: IF necessary, DIRECT the Operator to transfer HPCI suction back to the CST and place HPCI in Full Flow Test mode to continue plant cooldown in accordance with HC.OP-AB.ZZ-0001.
1.0 Loss of 1AD481 may affect controls and indication.
lE a HPCI Suction Transfer has occurred while in Full Flow Test, OR HPCI is in Full Flow Test AND a Suction Swap is anticipated, THEN PERFORM the following:
A. ADJUST FIC R600 Flow Setpoint to zero gpm. B. lE required, CLOSE HV-F011. C. WHEN Suction Swap to Suppression Pool is completed, (HV-F042 OPEN, HV-F004 and HV-F011 are CLOSED) THEN PROCEED in this Attachment.
Operator reads and initials NOTE. *operator depresses the Lower Setpoint Pushbutton until zero gpm flow indication is reached on FIC-R600, and initials Step. Operator may depress the CLOSE Pb for AP-HV-F011, and initials Step. Examiner Note: Valve will auto close when BJ-HV-F042 is full open. Operator observes position indication and when the CST Suction valve HV-F004 indicates CLSD and the Torus Suction valve HV-F042 indicates open, and initials Step. Page 5of13 JPM NUMBER: BJ014 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@, 2.0 PRESS HV-F042 AUTO OPEN *operator depresses the OVRD OVRD Pushbutton AND Pb for HV-F042, VERIFY the HV-F042 OVRD Light is LIT. and initials Step. 3.0 IF a HPCI Initiation Signal is Operator identifies that the HPCI present, THEN PERFORM the Initiation Signal is NOT present, following:
marks Step as N/A, and proceeds to Step 4.0. Examiner Note: The initiation signal was reset during the initial actions to place HPCI in Full Flow Test. 4.0 IF a HPCI Initiation Signal is NOT present, THEN PERFORM the following:
operator depresses the HV-A. PRESS the HV-F042 F042 CLOSE Pb, CLOSE Pushbutton and initials Step. ' B. WHEN HV-F042 indicates Operator observes both the OPEN dual position, THEN OPEN and CLSD lights are illuminated for HV-F004. HV-F042, *operator depresses the HV-F004 OPEN Pb, and initials Step. CUE: IF the CRS is asked about restoring HPCI to full flow test, DIRECT the Operator to restore HPCI to the Full Flow Test mode to continue plant cooldown.
5.0 !E required, RESTORE HPCI to *operator depresses the Raise Full Flow Test as follows: and/or Lower Setpoint A. ADJUST FIC-R600 HPCI Pushbutton(s) until HPCI flow FLOW setpoint to 1000 setpoint indicates approximately gpm. 1000 gpm on FIC-R600, and initials Step. B. IMMEDIATELY OPEN AP-*operator depresses the AP-HV-HV-F011. F011 OPEN pushbutton, and initials Step. Page 6of13 JPM NUMBER: BJ014 NAME:
REV NUMBER: 04 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ C. WHEN Discharge Pressure WHEN HPCI discharge pressure turns ADJUST FIC-R600 begins to lower, Operator setpoint to 3000 gpm. depresses the Raise and/or Lower Setpoint Pushbutton(s) until HPCI flow setpoint indicates approximately 3000 gpm on FIG-R600, and initials Step. Examiner note: The termination statement by the Operator may be a report to the CRS that HPCI is in Full Flow Test mode of operation.
At that time it is acceptable to terminate the JPM. D. THROTTLE HV-F008 AND Operator throttles and adjusts FIG-ADJUST FIC-R600 R600 setpoint, as necessary, up to setpoint, as necessary, to and including full flow rate, to control HPCI pump control HPCI pump parameters/
parameters/reactor reactor pressure.
pressure.
' 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 HPCI in Full Flow Test mode and returns to Full Flow Test mode after HPCI Suction Transfer to CST in accordance with HC.OP-AB.ZZ-0001.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 7of13 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK NUMBER: 4000400401 2016 NRC EXAM JPM E Copy __ of __ TASK: Respond To A Loss Of Shutdown Cooling JPM NUMBER: 305H-JPM.BC003 REVISION:
09 SAP BET: NOH05JPBC03E K/A NUMBER: 205000 A2. Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 I 45.6) A2.06 SDC/RHR pump trips IMPORTANCE FACTOR: RO: 3.4 SRO: 3.5 ALTERNATE PATH: D APPLICABILITY: EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-AB.RPV-0009, Rev. 11 ' TOOLS, AND EQUIPMENT:
None 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 Page 1of9 JOB PERFORMANCE MEASURE SYSTEM: Residual Heat Removal TASK NUMBER: 4000400401 TASK: Respond To A Loss Of Shutdown Cooling INITIAL CONDllTONS:
1. The plant was is OPCON 4. 2. The reactor has been shut down for 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months . 3. RHR Pump B was in shutdown cooling at 10,000 gpm for several days. 4. RCS temperature was 120F. 5. A worker inadvertently tripped the RHR Pump B breaker locally. 6. The breaker has been inspected and is undamaged.
7. The Shutdown Cooling suction line did NOT isolate. 8. NSSSS and PCIS are reset. 9. The pump has been tripped for 5 minutes. 10. HC.OP-AB.RPV-0009 Shutdown Cooling is being implemented.
INITIATING CUE: PERFORM Condition A, Steps A.5 and A.6, of HC.OP-AB.RPV-0009.
The required shutdown cooling flow for the 'B' RHR pump is between 9500 -10,000 gpm. Page 2of9 JPM NUMBER: BC003 NAME:
REV NUMBER: 09 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains and locates Operator obtains the correct . procedure HG.OP AB.RPV-procedure.
0009. Operator determines beginning Operator determines correct step of the procedure.
beginning step to be A.5. A.5 ENSURE the following:
HV-F008, HV-F009 and Operator determines the HV-F008, HV-F006A(B) are OPEN. (If HV-F009, and HV-F006B are open necessary, dispatch by observing the red OPEN lights operators to operate are illuminated and green CLSD manually).
lights are extinguished, and initials [CD-065X]
Step. '
HV-F006B(A) and HV-Operator determines the HV-FOO? A(B) are CLOSED. F006A is closed by observing the red OPEN lights are extinguished and green CLSD lights are illuminated, and initials Step. A.6 RESTORE tripped RHR pump *#operator presses the HV-as follows: F015B DECR pushbutton until a. CLOSE F015A(B).
the OPEN light extinguishes, and initials Step. b. RESTART RHR Pump *#operator presses the BP202 A(B). START push button, observes the RUNNING indicator illuminates and the STOPPED indicator extinguishes, and initials Step. c. IMMEDIATELY
operator presses HV-F015B THROTTLE OPEN INCR pushbutton until Shutdown F015A(B) to establish Cooling flow is between 9500 Shutdown Cooling flow gpm and 10,000 gpm, between 3000 gpm and 10,000 gpm. and initials Step. Page 3 of 9 JPM NUMBER: BC003 NAME:
REV NUMBER: 09 0 ATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN 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 Steps A.5 and A.6 of HC.OP-AB.RPV-0009.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 4of9 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: System TASK NUMBER: 3620190101 2016 NRC EXAM JPM F Copy __ of __ TASK: Shift A 4160 V 1 E Bus To Alternate Feeder JPM NUMBER: 305H-JPM.PB001 SAP BET: NOH05JPPB01 E K/A NUMBER: 262001 A4.01 ALTERNATE PATH: APPLICABILITY: REVISION:
00 IMPORTANCE FACTOR: RO: 3.4 SRO: 3.7 EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-SO.PB-0001, Rev. 29 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 Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: System TASK NUMBER: 3620190101 TASK: Shift A 4160 V 1 E Bus To Alternate Feeder INITIAL CONDllTONS:
1. Maintenance is required on the 40201 breaker. INITIATING CUE: SHIFT 10A402 supply to the Alternate Feeder Breaker in accordance with Section 5.6 of . 0001. Page 2of10 JPM NUMBER: PB001 NAME:
REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) 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.
procedure.
Operator reviews precautions Operator reviews precautions and and limitations.
limitations.
CUE: IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 5.6.1 . NOTE The Normal (Alternate)
Feeder Operator reads and initials NOTE. Breaker should have the AUTO CLOSE BLOCK PB set ' (illuminated) when the breaker ... 5.6.1. ENSURE that the prerequisites Operator completes Attachment 1 of Section 2.6 have been Section 2.0 and ensures that all satisfied.
prerequisites have been satisfied, and initials each prerequisite.
CAUTION When transferring the A vital Operator reads NOTE, determines bus, the CRS should it is not applicable, and initials determine
... NOTE. 5.6.2. IF desired, OPEN breakers 52-Operator determines that the Step 212071 and 52-212072 for is not applicable, and marks Step RAGS valves 1 EDHV-2598 and as N/A. 1 EDHV-2599.
5.6.3. ENSURE
Bus Voltage is Operator refers to HC.OP-DL.ZZ-adjusted to the higher band 0003 and determines Bus Voltage required for the Bus alignment adjustment is required, prior to transfer AND if *#places 1AX501 Tap Changer necessary, PLACE 1 AX501 (1 BX501) Tap Changer in in Manual and adjusts Bus Manual. (REFER TO HG.OP-Voltage to 4.276 KV -4.370 KV DL.ZZ-0002(3)(0), Control (CRIDS A7066), Console Log(s)) and initials Step. Examiner Note: Operator may also place the 1 BX501 Tap Changer in Manual in anticipation of future adjustments.
Page 3of10 JPM NUMBER: PB001 REV NUMBER: 00 STANDARD SAT/ COMMENTS STEP ELEMENT (*Critical Step) (Required for NUMBER (#Sequential Step) UNSAT UNSAT) 5.6.4. SHIFT breaker alignment on the desired Class 1 E 4160V busses (listed in Table PB-002, Section 5.4) as follows: A. lE the Alternate (Normal) Operator observes the Alternate AUTO CLOSE BLOCK PB AUTO CLOSE BLOCK PB backlight is OFF, and initials Step. backlight is ON, THEN PRESS the Alternate (Normal) AUTO CLOSE BLOCK AND VERIFY that the PB backlight is OFF. [CD-056H]
B. PRESS Normal (Alternate)
operator presses the 40201 AUTO CLOSE BLOCK AUTO CLOSE BLOCK PB and AND VERIFY that the PB verifies that the PB backlight is backlight is OFF. [CD-OFF, 056H] AND INITIAL Attachment
1. and initials Step. ' C. PRESS CLOSE PB on *#operator presses CLOSE PB Alternate (Normal) FEED on Alternate Feed Breaker BRKR. 40208, and initials Step. D. ENSURE that the Alternate Operator observes the 40208 (Normal) FEED BRKR CLOSE PB backlight is lit, and the closes AND that the TRIP PB is extinguished, and the Normal (Alternate)
FEED 40201 CLOSE PB backlight is BRKR trips. AND INITIAL extinguished and the TRIP PB is lit, Attachment
1. and initials Attachment
1. E. PRESS the AUTO CLOSE *#operator presses the AUTO BLOCK PB for the CLOSE BLOCK PB for the Alternate (Normal) Feed Alternate Feed Breaker 40208, Breaker AND VERIFY that the AUTO CLOSE BLOCK verifies that the AUTO CLOSE PB is illuminated.
[CD-BLOCK PB is illuminated, and 056H] AND INITIAL initials Step. Attachment
1. 5.6.5. ENSURE Bus Voltage is Operator refers to HC.OP-DL.ZZ-adjusted, as necessary, within 0003 and determines Bus Voltage required range. (REFER TO to be within the required range. HC.OP-DL.ZZ-0002(3)(0), Control Console Log( s)) Page 4of10 JPM NUMBER: PB001 NAME:
REV NUMBER: 00 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT {*Critical Step) UNSAT (Required for {#Sequential Step) UNSAT)@ 5.6.6. lE opened in Step 5.6.2, Operator determines that this Step CLOSE breakers 52-212071 is not applicable and marks N/A. and 52-212072 for RAGS isolation valves 1 EDHV-2598 and 1 EDHV-2599 AND INITIAL Attachment
1. 5.6.7. PERFORM independent Operator provides the procedure verification that the system is for an independent review. aligned IAW 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 shifts 10A402 supply to the Alternate Feeder in accordance with HC.OP-SO.PB-0001.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 5of10 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Area Ventilation System TASK NUMBER: 4880060101 TASK: Isolate the Control Room HVAC System JPM NUMBER: 305H-JPM.GK002 SAP BET: NOH05JPGK02E 2016 NRC EXAM JPMG Copy __ of __ REVISION:
04 K/A NUMBER: 290003 A4. Ability to manually operate and/or monitor in the control room: (CFR: 41. 7 I 45.5 TO 45.8) A4.01 Initiate/reset system ALTERNATE APPLICABILITY:
EVALUATION SETTING/METHOD:
REFERENCES:
HC.OP-AB.HVAC-0002 Rev.10 HC.OP-SO.GK-0001 Rev. 22 TOOLS, AND EQUIPMENT:
None IMPORTANCE FACTOR: RO: 3.2 SRO: 3.2 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 Page 1 of 11 JOB PERFORMANCE MEASURE SYSTEM: Control Area Ventilation System TASK NUMBER: 4880060101 TASK: Isolate the Control Room HVAC System INITIAL CONDllTONS:
1. The plant is at 100% power. 2. Control Room Ventilation Train A is in service. 3. The Aux Building Operator has been briefed and is standing by on location.
4. Chiller BK400 is ready for a start. INITIATING CUE: SWAP Control Room Ventilation Trains IAW Section 5.4 of HC.OP-SO.GK-0001.
Page 2of11 JPM NUMBER: GK002 NAME:
REV NUMBER: 04 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains and locates Operator obtains the correct procedure.
procedure.
Operator reviews precautions Operator reviews precautions and and limitations.
limitations.
CUE: IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 5.4.1. 5.4.1 ENSURE that all prerequisites Operator ensures that all have been satisfied IAW prerequisites have been satisfied Section 2.4. ' and initials each. NOTE All operations are performed Operator reads and initials NOTE. from 1 OC651 E unless otherwise noted. Procedure describes transfer from A Control Chilled Water Loop in service to the B Loop in service, values in parentheses used to transfer back to A in service. SACS Pump Room Unit Coolers 1AVH214 AND 1 BVH214 are interlocked to operate in AUTO only IF Chilled Water Pump AP400 is in service. SACS Pump Room Unit Coolers 1CVH214 and 1 DVH214 are interlocked to operate in AUTO only IF Chilled Water Pump BP400 is in service. Page 3of11 JPM NUMBER: GK002 NAME:
REV NUMBER: 04 DATE: STEP NUMBER 5.4.2 ELEMENT PRESS CH W CIRC PUMP B(A)P400 MAN PB. VERIFY MAN comes on. STANDARD (*Critical Step) (#Sequential Step) *operator presses the BP400 MAN PB, and observes the MAN push button illuminated and the AUTO push button extinguished.
Examiner Note: Operator may place BP400 in AUTO when proceeding to respond to smoke. SAT/ UNSAT COMMENTS (Required for UNSAT)@ CUE: "REPORT as Yard Operator that there is a large fire north of the HC Million Gallon Fuel Oil Storage Tank and smoke is headed towards the power block." "Light smoke is coming out of the Control Room ventilation supply ductwork into the Main Control Room. [SRO] Take any required actions. [SRO] If requested state, "Implement HC.OP-AB.HVAC-0002 and take any required actions." CUE: ENSURE ET-1 TRIGGERS; advance Fire Computer, OR PROVIDE Fire Computer Alarm Summary. HC.OP-AB.HVAC-0002
' Operator reviews AB.HVAC-0002 CONTROL ROOM ENVIRONMENT.
EXAMINER NOTE: The directions to HC.OP-AB.HVAC-0002 are contained within HC.OP-AR.QK-0001 (2). The operator may respond to the fire alarm and not go directly to HC.OP-AB.HVAC-0002. CUE: If operator responds to OHA A2-A5 in accordance with HC.OP-AR.ZZ-0002, and HC.OP-AR.QK-0001 /2, respond as appropriate to implement HC.OP-AB.HVAC-0002 and take any required actions. I. Smoke OR Toxic Gases are ENTERING the Control Room from an Outside source. Date/Time:

Operator determines Retainment Override Condition I. applies. Page 4of11 JPM NUMBER: GK002 NAME:

REV NUMBER: 04 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)@ I.a. PRESS the ISOLATE PB *#operator presses the for the 1/S Control Room ISOLATE PB for the A Control Ventilation Train. Room Ventilation Train. Operator observes the HD9598A ISOLATE PB for the A Control Room Ventilation Train illuminates.
Operator observes the HD9588M and HD9588BA NORMAL ISOLATED lights are illuminated.
Operator observes the AV400 START PB illuminates, and the STOP PB extinguish.
l.b. PRESS the RECIRC PB for *#Operator presses the RECIRC the l/S CREF Unit. PB for AV400. Operator observes the OA DMPR HD9593A OPEN PB extinguish and HD9593A CLOSED PB I illuminate.
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 Isolates the Control Room HVAC System in accordance with HC.OP-AB.HVAC-0002.
@Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 5of11 JOB PERFORMANCE MEASURE STATION: Hope Creek 2016 NRC EXAM JPM H Copy __ of __ SYSTEM: Safety & Turbine Auxiliaries Cooling TASK NUMBER: 3080050101 TASK: Transfer TACS to the Standby SACS Loop JPM NUMBER: 305H-JPM.EG002 SAP BET: NOH05JPEG02E REVISION:
13 400000 A.4.Ability to manually operate and I or monitor in the control room: KIA NUMBER: (CFR: 41.7 I 45.5 TO 45.8) A4.01 CCW indications and control IMPORTANCE FACTOR: RO: 3.1 SRO: 3.0 ALTERNATE PATH: D APPLICABILITY: EVALUATION SETTING/METHOD:
Simulator/Perform
REFERENCES:
HC.OP-AB.ZZ-0001, Rev. 31 TOOLS, AND EQUIPMENT:
None ESTIMATED COMPLETION TIME: 9 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 Page 1of11 JOB PERFORMANCE MEASURE SYSTEM: Safety & Turbine Auxiliaries Cooling TASK NUMBER: 3080050101 TASK: Transfer T ACS to the Standby SACS Loop INITIAL CONDllTONS:
1. The plant is at 100% power. 2. TAGS is being supplied by SACS Loop A. 3. SACS Pump AP210 has developed an oil leak on the inboard pump bearing and there is no oil level in the bubbler. 4. There is no line break in the system. 5. SACS Pump DP210 has been checked for a start. INITIATING CUE: TRANSFER TAGS to the B SACS loop IAW HC.OP-AB.ZZ-0001Attachment10 (Hard Card). STOP SACS Pump AP201. ENSURE SACS cooling is aligned to the A RHR Heat Exchanger AND secured to the B RHR Heat Exchanger.
There are no additional operators available to assist in the swap. Page 2of11 JPM NUMBER: EG002 NAME:
REV NUMBER: 13 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)@ CUE: PROVIDE thia 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.ZZ-0001 procedure.
Attachment 10, Page 2 of 2, T ACS TRANSFER TO B LOOP. Operator determines beginning Operator enters the Date and step of the procedure.
Time, and determines correct beginning step to be 1.0. 1.0 IF 'A' Loop TAGS is isolating, Operator determines this step is THEN LOCKOUT: not applicable and marks the Steps N/A.
HV-2522 I 2496A
HV-2522 I 2496C 2.0 VERIFY no Line Break in the Operator reviews Initiating Cue T ACS System. and/or observes normal SACS Head Tank Levels, and determines no line break exists, and initials Step 3.0 ENSURE B and D SACS Pumps in service, lE required, THEN START the B(D) Pump as follows: Operator observes the SAFETY A. ENSURE REMOTE PB is AUXILIARIES COOLING LOOP B OFF. PUMPS PUMP D REMOTE light is extinguished, and initials Step. B. PLACE the B(D) Pump in *#operator presses the SAFETY MAN. AUXILIARIES COOLING LOOP B PUMPS PUMP D MAN pushbutton, observes the MAN light illuminates and the AUTO light extinguishes, and initials Step. Page 3of11 JPM NUMBER: EG002 NAME:
REV NUMBER: 13 DATE: STEP STANDARD SAT/ COMMENTS ELEMENT (*Critical Step) (Required for NUMBER (#Sequential Step) UNSAT UNSAT)@ C. START the B(D) SACS *#Operator presses the SAFETY Pump. AUXILIARIES COOLING LOOP B I PUMPS PUMP D DP210 START Date/Time pushbutton, observes the PUMP D DP210 START light illuminates and the STOP light extinguishes, enters the Date and Time, and initials Step. CUE: IF asked for status of 'D' SACS pump after the start, REPORT post start checks are satisfactory.
D. OBSERVE LOW DIFF Operator observes the SAFETY PRESS light extinguishes.
AUXILIARIES COOLING LOOP B PUMPS PUMP D LOW DIFF PRESS light is not illuminated, and initials Step. 4.0 ENSURE the following valves *#operator presses the LOOP B are OPEN/OPENING:
ISLN TACS CLG/HYDR PNEU
HV-2522/24968 ACCUM AIR TACS INBD SPLY/RTN HV 2522B HV 2496B OPEN pushbutton, observes the HV 25228 HV 24968 OPEN light illuminates, and the CLOSE light extinguishes, and initials Step.
HV-2522/2496D
operator presses the LOOP B ISLN TACS CLG/HYDR PNEU ACCUM AIR TACS OUTBD SPL Y/RTN HV-25220/HV-24960 OPEN pushbutton, observes the HV 2522D HV 2496D OPEN light illuminates, and the CLOSE light extinguishes, and initials Step. 5.0 WHEN a positive indication is *#operator presses the LOOP A observed that valves in Step ISLN TACS CLG/HYDR PNEU 4.0 are OPEN/OPENING, ACCUM AIR TACS INBD THEN ENSURE the following SPL Y/RTN CLOSE pushbutton valves are CLOSED/CLOSING:
for HV 2522 HV 2496A,
HV-2522 I 2496A observes the CLOSE lights illuminate and the HV 2522A HV 2496A OPEN light extinguishes, and initials Step. Page 4of11 JPM NUMBER: EG002 NAME:
REV NUMBER: 13 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)(a)
HV-2522 I 2496C *#Operator presses the LOOP A ISLN TACS CLG/HYDR PNEU ACCUM AIR TACS OUTBD SPL Y/RTN CLOSE pushbutton for HV 2522 HV 2496C, observes the CLOSE lights illuminate and the HV 2522C HV 2496C OPEN light extinguishes, and initials Step. 6.0 ENSURE the B AND D SACS Operator observes the SAFETY Pumps are in AUTO. AUXILIARIES COOLING LOOP B PUMPS PUMP B AUTO light is illuminated and MAN light is extinguished, *#operator presses the SAFETY AUXILIARIES COOLING LOOP B PUMPS PUMP D AUTO pushbutton, I observes the AUTO light illuminates and the MAN light extinguishes, and initials Step. 7.0 PERFORM the following lE required:
operator presses the A. ADJUST OPEN HV-2512A HV2512A INCR pushbutton until to ==4500 gpm SACS flow flow on Fl-2511A (CRIDS, or to "A" RHR Hx. ,, equivalent) indicates
==4500 gpm, and initials Step. B. CLOSE HV-25128 *#operator presses the HV2512B DECR pushbutton until the HV2512B OPEN light extinguishes and initials Step. CUE: DIRECT the operator to secure SACS Pump AP210. C. PLACE the A(C) SACS Operator presses the SAFETY Pump in MAN. AUXILIARIES COOLING LOOP A PUMPS PUMP A MAN pushbutton, and/or observes the MAN light illuminates and the AUTO light extinguishes(d), and initials Step. EXAMINER NOTE: The pump should have already swapped to MAN. Page 5of11 JPM NUMBER: EG002 REV NUMBER: 13 STEP STANDARD SAT/ COMMENTS ELEMENT (*Critical Step) (Required for NUMBER (#Sequential Step) UNSAT UNSAT)@ D. STOP the A(C) SACS *#operator presses the SAFETY Pump. AUXILIARIES COOLING LOOP A PUMPS PUMP A STOP pushbutton, observes the PUMP A STOP light illuminates and the AP210 START light extinguishes, and initials Step. 8.0 ENSURE proper Service Water Operator observes that a SSW pump alignment IAW HC.OP-pump is operating in each loop, SO.EA-0001 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 transfers TACS to SACS Loop Bin accordance with HC.OP-AB.ZZ-0001 Attachment
10. @Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 6of11 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Protection 2016 NRC EXAM JPM I Copy __ of __ TASK NUMBER: 2120050101 TASK: Transfer RPS Bus A/B Power From Alternate Source To RPS MG Set JPM NUMBER: 305H-JPM.SB015 REVISION:
06 SAP BET: NOH05JPSB1 SE K/A NUMBER: 212000 A2. Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 I 45.6) A2.01 RPS Motor-Generator Set Failure IMPORTANCE FACTOR: RO: 3.7 SRO: 3.9 ALTERNATE PATH: APPLICABILITY: EVALUATION SETTING/METHOD:
Plant/Simulate
REFERENCES:
HC.OP-SO.SB-0001, Rev 34 TOOLS, AND EQUIPMENT:
None ESTIMATED COMPLETION TIME: 12 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 Page 1of10 JOB PERFORMANCE MEASURE SYSTEM: Reactor Protection TASK NUMBER: 2120050101 TASK: Transfer RPS Bus A/B Power From Alternate Source To RPS MG Set INITIAL CONDllTONS:
1. The plant is at 100% power. 2. RPS A is being powered from the ALTERNATE A FEED. 3. Maintenance has been completed on 1A-G-401, RPS MG set. 4. Once the MG Set is running, Maintenance needs to check/adjust MG Set output voltage in accordance with Step 5.5.2.D. INITIATING CUE: START the 1 A-G-401, RPS MG SET A, in preparation to transfer RPS Bus A power from RPS Alternate Transformer A to RPS MG SET A in accordance with Section 5.5 of HG.OP SO.SB 0001. CONT ACT Maintenance when ready for MG set output voltage check/adjust.
Page 2of10 JPM NUMBER: SB015 NAME:
REV NUMBER: 06 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains procedure Operator obtains the correct HC.OP-SO.SB-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 5.5.1 5.5.1 ENSURE all prerequisites of Operator ensures that all Section 2.5 are satisfied.
prerequisites have been satisfied.
' CUE: If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.
CUE: IF asked about the current status/indications, state: The Red MOTOR ON lamp is extinguished, and the Green MOTOR OFF lamp is illuminated.
The output breaker is open. 5.5.2 lE start of 1A(B)G401, RPS MG Operator determines that this Step Set, is necessary, THEN applies and initials Step. PERFORM the following (A[B] MG Set Local Panel): NOTE IF the MOTOR ON push-button Operator reads and initials NOTE. is NOT held in for long enough, THEN the starting sequence will NOT be completed.
This may result in an undervoltage condition in the generator, which may result in generator damage. A. PRESS AND HOLD the *#operator presses and holds MOTOR ON push-button the AG401 MOTOR ON push-(Red MOTOR ON lamp button, illuminates).
and initials Step. CUE: The Red MOTOR ON lamp is illuminated, and the Green MOTOR OFF lamp is extinguished.
Page 3of10 JPM NUMBER: SB015 NAME:
REV NUMBER: 06 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ B. VERIFY A-C VOL TS Operator observes A-C VOL TS Generator Output Voltage Generator Output Voltage and AND PERFORM the EXPECTS a voltage increase to following:
115-125 volts which stabilizes for 1. IF voltage increases to approximately 5 seconds. 115 -125 volts AND has Following the next Cue, the been stabilized for Operator determines need to approximately 5 seconds, proceed to Step 5.5.2.B.2.
THEN RELEASE the MOTOR ON push-button.
CUE: The meter identified has risen from 0 volts, and has stabilized at approximately 100 volts. 2. IF voltage does NOT increase to 115 -125 volts, THEN PERFORM *#Operator releases the AG401 the following:
MOTOR ON push-button, a. RELEASE the and initials Step. MOTOR ON push-button. ' b. PRESS AND HOLD *#Operator presses and holds MOTOR OFF push-the AG401 MOTOR OFF push-button. button, and initials Step. c. WHEN the MOTOR When the AG401 MOTOR ON light ON light extinguishes, extinguishes, the operator releases THEN RELEASE the the AG401 MOTOR OFF push-MOTOR OFF push-button. button. Following the next Cue, the *operator releases the MOTOR OFF push-button, and initials Step. CUE: The Red MOTOR ON lamp is extinguished, and the Green MOTOR OFF lamp is illuminated.
d. REPEAT Step Operator returns to Step 5.5.2.A. 5.5.2.A. CUE: If asked about restarting the MG Set, inform the operator that one restart attempt is allowed and restart can be attempted while the MG Set is spinning.
Page 4of10 JPM NUMBER: SB015 NAME:
REV NUMBER: 06 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ 5.5.2 A. PRESS AND HOLD the *#operator presses and holds MOTOR ON push-button the AG401 MOTOR ON push-(Red MOTOR ON lamp button, illuminates).
and initials Step. CUE: The Red MOTOR ON lamp is illuminated, and the Green MOTOR OFF lamp is extinguished.
B. VERIFY A-C VOL TS Operator observes A-C VOL TS Generator Output Voltage Generator Output Voltage and AND PERFORM the EXPECTS a voltage increase to following:
115-125 volts which stabilizes for 1. !E voltage increases to approximately 5 seconds. 115 -125 volts AND has Following the next Cue, the been stabilized for approximately 5 seconds, *#Operator releases the AG401 THEN RELEASE the MOTOR ON push-button, MOTOR ON push-button.
and initials Step. CUE: The meter identified has risen from 0 volts, and has stabilized at approximately 120 volts for I approximately 5 seconds. 2. !E voltage does NOT Operator determines this step no increase to 115 -125 longer applies. volts, THEN PERFORM the following:
C. WHEN 1 minute of MG Set Operator waits one minute, and operation has elapsed, *#places the RPS MG Set THEN PLACE RPS MG Set 1A(B)G401 GENERATOR 1AG401 GENERATOR OUTPUT OUTPUT breaker to ON breaker to ON, AND INITIAL Attachment
1. initials Attachment 1, and initials the Step. CUE: The breaker identified is in the stated position.
NOTE The RPS MG Set output voltage shall NOT be set using the local panel meter. Use of the local panel meter ... Page 5of10 JPM NUMBER: SB015 NAME:
REV NUMBER: 06 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ D. REQUEST Maintenance Operator requests maintenance to Department to CHECK AND check and adjust if necessary RPS ADJUST (as necessary), the MG Set A output voltage at the RPS MG Set(s) output input to Electrical Protection voltage at the input to Assembly (EPA) Circuit Breaker Electrical Protection 1AN410 (unloaded)
IAW HG.MD-Assembly (EPA) Circuit PM.SB-0001 (Q). Breaker 1 AN410 ( 1 AN411) (unloaded)
IAW HG.MD-PM.SB-0001 (Q), OTHERWISE, VERIFY A-C VOL TS at local panel meter is 115 to 125 volts. 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 starts the 1 A-G-401, RPS MG SET A, in accordance with Section 5.5 of HG.OP SO.SB-0001. @Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 6of10 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod Drive Hydraulic TASK NUMBER: 2010090104 TASK: Shift In-Service CRD Stabilizing Valves JPM NUMBER: 305H-JPM.BF002 SAP BET: NOH05JPBF02E 2016 NRC EXAM JPM J Copy __ of __ REVISION:
12 K/A NUMBER: 201001 A2. Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 I 45.6) ALTERNATE PATH: D APPLICABILITY:
A2.02 Valve closures RO l:8J IMPORTANCE FACTOR: RO: 3.2 SRO: 3.3 SRO l:8J EVALUATION SETTING/METHOD:
Reactor Building/Simulate
REFERENCES:
HC.OP-SO.BF-0001 Rev. 34 TOOLS, AND 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 Page 1of9 JOB PERFORMANCE MEASURE SYSTEM: Control Rod Drive Hydraulic TASK NUMBER: 2010090104 TASK: Shift In-Service CRD Stabilizing Valves INITIAL CONDllTONS:
1. The plant is operating at 80% power. 2. Stabilizing Valves A(B) is in service. 3. Stabilizing Valves A(B) has failed closed due to a malfunction in the Reactor Manual Control System. INITIATING CUE: PLACE Stabilizing Valves B(A) in service; SECURE Stabilizing Valves A(B) in accordance with SO.BF-0001, Section 5.2. * [Evaluator:
DETERMINE the in service and standbys Stabilizing Valves based on current plant conditions, AND MODIFY the Initial Conditions and STANDARDS appropriately.]
Page 2of9 JPM NUMBER: BF002 NAME:
REV NUMBER: 12 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)@ CUE: PROVIDE the operator the initiating cue, a marked up copy of HC.OP-SO.BF-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, THEN INFORM operator that all are satisfied.
Operator determines beginning Operator determines correct step of the procedure.
beginning step to be 5.2.1. 5.2.1 ENSURE all prerequisites of Operator ensures all prerequisites Section 2.2 are satisfied.
are satisfied; completes Attachment 1 and initials each prerequisite.
' 5.2.5 lE Stabilizing Valve B(A) is to *operator simulates rotating the be alternated, THEN 1-BF-V054(1-BF-V071)
PERFORM the following:
handwheel in the A. Slowly OPEN 1-BF-counterclockwise direction until V054(1-BF-V071
), CRD the handwheel reaches full open, Drive Wtr Stabilizing Vlvs and initials Step. "B(A)" Inlet Viv. CUE: The handwheel of the valve indicated rotates in the direction indicated and comes to a hard stop. B. Slowly OPEN 1-BF-*operator simulates rotating the V060(1-BF-V059), CRD 1-BF-V060(1-BF-V059)
Drive Wtr Stabilizing Vlvs handwheel in the "B(A)" Outlet Viv. counterclockwise direction until the handwheel reaches full open, and initials Step. CUE: The handwheel of the valve indicated rotates in the direction indicated and comes to a hard stop. C. PRESS (STABILIZER Operator requests that the Control VALVES) VALVE Room press the VAL VE SELECTOR AND VERIFY SELECTOR push button and verify that B(A) VAL VE B(A) VAL VE SELECTED is SELECTED is illuminated.
illuminated.
(10C651C)
CUE: Respond as the Control Room, B(A) Valve Selected is illuminated.
Page 3 of 9 JPM NUMBER: BF002 NAME: REV NUMBER: 12 DATE: STEP STANDARD SAT/ COMMENTS NUMBER ELEMENT (*Critical Step) UNSAT (Required for (#Sequential Step) UNSAT)(@, D. CLOSE 1-BF-V059(1-BF-
operator simulates rotating V060},CRD Drive Wtr the 1-BF-V059(1-BF-V060)
Stabilizing Vlvs "A(B)" handwheel in the clockwise Outlet Viv. direction until valve handwheel reaches a hard stop, and initials Step. CUE: The handwheel of the valve indicated rotates in the direction indicated and comes to a hard stop. E. CLOSE 1-BF-V071 (1-BF-*#operator simulates rotating V054 ), CRD Drive Wtr the 1-BF-V071(1-BF-V054)
Stabilizing Vlvs "A(B)" Inlet handwheel in the clockwise Viv. direction until valve handwheel reaches a hard stop, and initials Step. CUE: The handwheel of the valve indicated rotates in the direction indicated and comes to a hard stop. F.' OBSERVE that Operator observes approximately 6 approximately 6 gpm total gpm total flow through both the flow through both the Insert Insert AND Withdraw Stabilizing AND Withdraw Stabilizing valves is indicated on 1 BF-Fl-R004 valves is indicated on 1 BF-C11, Stabilizing Header Flow Fl-R004 C11, Stabilizing Indicator, and initials Step. Header Flow Indicator.
CUE: The meter indicates as seen. ' G. PERFORM valve lineup Operator completes valve lineup in IAW Attachment
1. accordance with Attachment 1 and requests verification.
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 CRD Hydraulic System Stabilizing Valves in accordance with HC.OP-SO.BF-0001. @Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 4 of 9 JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: 120 VAC Electrical Distribution TASK NUMBER: 4000020404 TASK: Respond To A Station Blackout 2016 NRC EXAM JPM K Copy __ of __ JPM NUMBER: 305H-JPM.PN005 REVISION:
00 SAP BET: NOH05JPPN05E K/A NUMBER: 295003AA1.
Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :(CFR: 41.7 I 45.6) AA 1.01 A.C. Electrical Distribution System IMPORTANCE FACTOR: RO: 3.7 SRO: 3.8 ALTERNATE PATH: D APPLICABILITY:
EVALUATION SETTING/METHOD:
Auxiliary Building/Simulate
REFERENCES:
HC.OP-AB.ZZ-0135 Rev. 41 SRO (8J TOOLS, AND EQUIPMENT:
HC.OP-AB.ZZ-0135 Equipment stored in the EOP locker in the shift clerks office in the Main Control Room ESTIMATED COMPLETION TIME: 15 Minutes ----TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 30 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 Page 1of11 JOB PERFORMANCE MEASURE SYSTEM: 120 VAC Electrical Distribution TASK NUMBER: 4000020404 TASK: Respond To A Station Blackout INITIAL CONDllTONS:
1. The plant is in OPCON 3. 2. A loss of all offsite and onsite AC power has occurred.
3. HC.OP-AB.ZZ-0135, STATION BLACKOUT //LOSS OF OFFSITE POWER//DIESEL GENERATOR MALFUNCTION is being implemented.
INITIATING CUE: PERFORM the 30 MINUTE SBO Actions of HC.OP-AB.ZZ-0135, Attachment 1 OA, Auxiliary Building Actions For SBO -Operator #1. This is a Time Critical JPM. Page 2of11 JPM NUMBER: PN005 NAME:
REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER Operator repeats back the Initiating Cue. START TIME: Operator obtains and locates Operator obtains HG.OP AB.ZZ-procedure.
0135. Operator determines beginning Operator obtains copy of step of the procedure.
Attachment 1 OA. ATTACHMENT 10A, AUXILIARY BUILDING ACTIONS FOR SBO-OPERATOR #1 EQUIPMENT REQUIRED:
operator obtains equipment (Equipment below is stored in required by Attachment 10A, the EOP locker in the shift (stored in the EOP locker in the clerk's office) shift clerks office) 7 Door Stops and initials Attachment 1 OA. 4 Keys, all #172 (PA 2235) in I Note: It is critical that the Work Control Key Cabinet equipment is obtained before the performance of the following actions. However, the following actions can be completed in any order. CUE: After the operator has obtained the equipment, inform the operator to return equipment to storage, and to assume that the Equipment Required has been obtained.
1. BYPASS HPCI and RCIC high *operator inserts one #172 (PA temperature isolation trips at 2235) key into switch B21 B-S6A the following (Key 172, and rotates to the BYPASS PA2235, for all switches):
position,
HPCI panel 1 O-C-620, Switch 821 B-S6A and initials Attachment 1 OA. CUE: The switch you have indicated is in the stated position.
HPCI panel 1 O-C-641, *operator inserts one #172 (PA Switch 821 B-S6C 2235) key into switch B21 B-S6C and rotates to the BYPASS position, and initials Attachment 1 OA. CUE: The switch you have indicated is in the stated position.
Page 3of11 JPM NUMBER: PN005 NAME:
REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@
RCIC panel 1 O-C-621, *operator inserts one #172 (PA Switch 821 B-S5B 2235) key into switch B21 B-S5B and rotates to the BYPASS position, and initials Attachment 1 OA. CUE: The switch you have indicated is in the stated position.
RCIC panel 1 O-C-640, *operator inserts one #172 (PA Switch 821 B-S5D 2235) key into switch B21 B-S5D and rotates to the BYPASS position, and initials Attachment 1 OA. CUE: The switch you have indicated is in the stated position.
2. BLOCK OPEN the following doors in the Lower Relay Room. ' *operator opens and blocks 5335A,5302A,5302C,5316B, open door 5335A using a Door 5318C Stop, Note: The doors may be blocked open in any order. CUE: The door you have id.entified is blocked open. *operator opens and blocks open door 5302A using a Door Stop, CUE: The door you have identified is blocked open. *operator opens and blocks open door 5302C using a Door Stop, CUE: The door you have identified is blocked open. *operator opens and blocks open door 5316B using a Door Stop, CUE: The door you have identified is blocked open. Page 4of11 JPM NUMBER: PN005 NAME:
REV NUMBER: 00 DATE: STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ *operator opens and blocks open door 5318C using a Door Stop, and initials Attachment 1 OA. CUE: The door you have identified is blocked open. 3. OPEN the circuit breakers in Operator reads and initials Step the following tables to shed when complete.
non-essential loads. Note: All of the following actions are located in 54' CONTROL DIESEL, RM 5102A. I LOCATION PANEL# 54* *operator locates 1 BJ483, CONTROL 1BJ483 DIESEL and simulates opening circuit RM 5102A breaker #6, CIRCUIT#6 and initials block. FUSE PANEL 1YF406 I CUE: The breaker you have indicated is open. CIRCUIT#10
operator simulates opening ELECTRICAL PROTECTION circuit breaker #10, ASSEMBLY 1 AN414 and initials block. CUE: The breaker you have indicated is open. CIRCUIT#22
operator simulates opening FEEDWATER
& RECIRC circuit breaker #22, INSTR. CAB. 10C612 and initials block. CUE: The breaker you have indicated is open. LOCATION PANEL# 54* *operator locates 1AJ483, CONTROL 1AJ483 DIESEL and simulates opening circuit RM 5102A breaker #7, CIRCUIT#?
and initials block. FUSE PANEL 1 YF405 CUE: The breaker you have indicated is open. Page 5of11 JPM NUMBER: PN005 REV NUMBER: 00 STEP (*Critical Step) SAT/ COMMENTS NUMBER ELEMENT (#Sequential Step) UNSAT (Required for STANDARD UNSAT)@ CIRCUIT#9
operator simulates opening ELECTRICAL PROTECTION circuit breaker #9, ASSEMBLY 1 AN413 and initials block. CUE: The breaker you have indicated is open. CIRCUIT#15
operator simulates opening ROD POSITION INFO CAB circuit breaker #15, 10C615 and initials block. CUE: The breaker you have indicated is open. CIRCUIT#21
operator simulates opening PROCESS INSTR. VERT. circuit breaker #21, BOARD 10C613 and initials block. CUE:
you have indicated is open. LOCATION PANEL# 54' *operator locates 1CJ483, CONTROL 1CJ483 DIESEL and simulates opening circuit RM 5102A breaker #6, CIRCUIT#6 ROD SEQUENCE CONTROL and initials block. CAB 10C659 CUE: The. breaker you have indicated is open. 4. NOTIFY CONTROL ROOM Operator notifies the control room, THAT 30 MINUTE SBO and initials Step. ACTIONS FOR ATTACHMENT 10A ARE COMPLETE and that you are continuing on with the remainder of the Attachment.
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 30 MINUTE SBO Actions of HC.OP-AB.ZZ-0135 Attachment 1 OA, Auxiliary Building Actions For SBO -Operator #1. @Comments regarding any identified trainee failure to adhere to Operator Fundamentals of SER 3-05, Weaknesses in Operator Fundamentals, shall be noted in the comments.
[IER L 1-11-3 Rec. 3b] Page 6of11 SIMULATOR COPY __ OF __ EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 2016 NRC EXAM SCENARI0-1 SCENARIO NUMBER: ESG-2016 NRC-1 EFFECTIVE DATE: Effective When Approved EXPECTED DURATION:
1 Hour REVISION NUMBER: 1 PROGRAM: 0 LICENSED OPERATOR REQUALIFICATION cg] INITIAL LICENSE OOTHER: REVISION
SUMMARY
1. Minor editorial comments made from validation.
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. Remove EOG From Service 8. EOG Trip C. Raise Reactor power using Control Rods. D. Stuck Control Rod E. Seismic Event (>OBE) I EHC Filter Clogging F. Safety Relief Valve Stuck Open G.ATWS H. SBLC Failure to Auto Start I SBLC Pump B Failure on Start I. RWCU Failure to Automatically Isolate J. Loss of EHC K. RHR Pump Trip Ill. SCENARIO
SUMMARY
The scenario begins with the plant at approximately 88% power; with power ascension in progress following maintenance on RFPT AP101, and an Emergency Diesel Generator test in progress.
The EOG will trip during its removal from testing, making the EOG inoperable.
After Technical Specifications are addressed, the crew will continue with the power ascension.
A stuck rod will require actions to raise drive pressure to move the rod. EHC Filter clogging will occur during a seismic event. Actions will be successful in preventing a loss of EHC pressure.
A SRV will open requiring a Reactor Scram to comply with Technical Specifications.
An ATWS occurs on the scram. The Standby Liquid Control System will fail to automatically initiate, and one pump will fail after the system is manually placed in service. Reactor Water Cleanup System will need to be manually isolated following SLC initiation.
A loss of EHC will remove the Main Turbine and Bypass Valves from the pressure control strategy.
The first RHR pump to be placed in service will trip requiring another pump be placed in service for containment control. ESG-2016 NRC-1 Page 2 of 28 Rev. 1 IV. INITIAL CONDITIONS:
I l.C. lnftial I INITIALIZE the simulator to 100% power, MOL, T ACS on SACS A. ---REDUCE Reactor Power to 88% with Recirculation Pumps, and inserting Groups 1 OA and 1 OB rods. ___ ENSURE Recirculation Pump A speed is NOT 68-71% AND Pump B speed is NOT 67-73%. STABILIZE Xenon concentration.

ENSURE SACS Pump BP210 is in service, AND SACS Pump DP210 is in standby. ENSURE RACS Pumps Band Care in service. ---___ ENSURE EHC Pump AP116 is in service. START AG400 and load IAW HC.OP-ST.KJ-0001to1000 kw and 50-200 KvAR. ---PREP FOR TRAINING (i.e., RM-11 set points, procedures, bezel covers) Initial I ___ INITIAL IO.ZZ-0006;for the power ascension.

---ENSURE REMA is provided to support power ascension.
Withdrawing 1 OA rods then TCF adjustment.
MARKUP HC.OP-ST.KJ-0001to Step 5.4.13.D.
---REVIEW the Scenario Reference section and CLEAN the balded EOPs, ABs and SOPs listed (at a ---minimum).
(80091396 0270) ---COMPLETE the Simulator Ready for Training/Examination Checklist.
ESG-2016 NRC-1 Page 3 of 28 Rev. 1 EVENT FILE: Initial Event 4 Event Code: ET _ARRAY(2)
& ZL TUEHSB
Description:
ET-2 ACTIVE & EHC B STARTED 5 Event Code: lcvposx(1)
<= 700
Description:
Rod 18-03 Position 6 Event Code: sl_pmbrn
Description:
SLC Pump B Running 13 Event Code: rh_bkr(1)
& !et_array(14)
==
Description:==
RHR A Running First 14 Event Code: rh_bkr(2)
& !et_array(13)
==
Description:==
RHR B Running First 15 Event Code: ZLLCWHIT(123)
& (A3015_V >=308)
Description:
Rod 30-39 Selected AND Drive Pressure >=308 psid 16 Event Code: MONVAR(18)
==
Description:==
RPV Pressure psig ESG-2016 NRC-1 Page 4 of 28 Rev. 1 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction CU11A RWCU isolation valve F001 failure to auto close None None Insert malfunction CU11 B RWCU isolation valve F004 failure to auto close None None Insert malfunction SL04A SBLC pump A failure of auto start signal None None Insert malfunction SL04B SBLC pump B failure of auto start signal None None Insert malfunction RP06 Half-core A TWS -left side None None Insert malfunction CD033039 Control Rod 30-39 stuck None None Insert malfunction PC07 A on event 2 Seismic Event I None None Insert malfunction TC16 to 30.00000 in 120 on EHC pump discharge filter plugging event2 None None Insert malfunction AD02DO on event 3 ADS/Relief valve F013D (MS LINE D) I sticks open None None Insert malfunction TC16 to 0 on event 4 delete EHC pump discharge filter plugging in 1 None None Insert malfunction RPO? after 2 on event 5 Half-core ATWS -right side None None Insert malfunction SL01 B after 5 on event 6 SBLC injection pump BP208 failure .None None Insert malfunction TCO?A after 300 on event 6 EHC pump A trip None None Insert malfunction TCO?B after 300 on event 6 EHC pump B trip None None Insert malfunction TC01-10 after 420 on event All turbine bypass valves fail closed 6 None None Insert malfunction QQ20 to SHORT on event RHR pump AP202 Malfunctions 13 None None Insert malfunction QQ21 to SHORT on event RHR pump BP202 Malfunctions 14 None None Insert malfunction CD033039 on event 15 Control Rod 30-39 stuck delete in 1 None None Insert malfunction AD02DO on event 16 delete ADS/Relief valve F013D (MS LINE D) in 1 sticks open None None Insert malfunction DG02A on event 17 Diesel generator A failure ESG-2016 NRC-1 Page 5 of 28 Rev. 1 REMOTE SCHEDULE:
Initial @Time Event Action Description None None Insert remote EP01 after 360 to BYPASS on EP01 EOP-301, bypass MSIV (-129") events isolation interlock None None Insert remote EP02 after 480 to BYPASS on EP02 EOP-311, bypass PCIG (-129") event 9 isolation interlock None None Insert remote EP38 after 180 to Emergency on EP38 EOP-319, Restoring Instrument event 10 Air in an Emergency None None Insert remote EP09 after 240 to REMOVED on EP09 EOP-320 (step 5.1.2), ARI valve event 11 fuses F6A/F5A None None Insert remote EP1 O after 240 to REMOVED on EP10 EOP-320 (step 5.1.4), ARI valve event 11 fuses F6B/F5B None None Insert remote EP11 after 360 to INSTALLED EP11 EOP-320 (step 5.2.2), RPS on event 11 division 1 jumper None None Insert remote EP12 after 360 to INSTALLED EP12 EOP-320 (step 5.2.4), RPS on event 11 division 2 jumper None None Insert remote EP13 after 360 to INSTALLED EP13 EOP-320 (step 5.2.3), RPS on event 11 division 3 jumper None None Insert remote EP14 after 360 to INSTALLED EP14 EOP-320 (step 5.2.5), RPS on event 11 division 4 jumper None None Insert remote EP35 after 180 to FAIL_CLOSE EP35 EOP-322 HV-F006 HPCI to CS on event 12 OVERRIDE SCHEDULE:
Initial @Time Event Action Description ESG-2016 NRC-1 Page 6 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response
CRS directs unloading and Removing AG400 From Service: securing 1 AG400 in accordance with HG.OP-ST.KJ-0001.
PO unloads and secures 1AG400 IAW HC.OP-ST.KJ-0001: => Presses DIESEL ENG GOV DECR PB and lowers load to 50-200 kw => Presses TRIP for EOG AG400 40107 Gen Brkr. => Uses GEN VR RAISE OR LOWER PBs CYCLE Generator terminal voltage between 4056V and 4394V I (one complete cycle) then returns voltage to approximately 4160V. => Presses GEN VR MAN PB and ensures the MAN light is on. => Uses GEN VR RAISE OR LOWER PBs, CYCLE ,, Generator terminal voltage between 4056V and 4394V (one complete cycle), then returns voltage to approximately 4160V. => Presses GEN VR AUTO PB and ensures the AUTO light is on. ESG-2016 NRC-1 Page 7 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response EOG Trip
Crew recognizes EOG BEFORE the operator stops the problem by: => OHA E4-A3 DIESEL ENG EOG, or at the discretion of the PNL A/B/C/D C423 Lead Examiner, TRIGGER ET-17 => OHA E4-A2 DIESEL GEN PNL A/B/C/D C422 REPORT as ABEO that there is a => GRIDS 03776 DG A large oil leak from EOG A. REGULAR LOCKOUT RELAY Report as EO that the oil leak is
CRS declares EOG A Perform Surveillance stopped. Cleanup is in progress.
inoperable and enters Tech Requirement 4.8.1.1.1.a Spec 3.8.1.1. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.
If notified as SM/Work Control state Restore the inoperable that ST.ZZ-0001 will be performed
diesel generator to by another operator.
Continue with OPERABLE status power ascension.
within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR Verify the Salem Unit 3 gas turbine generator (GTG) is available within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter*, and restore the inoperable diesel generator to OPERABLE status within 14 days. Power Ascension:
CRS directs power ascension IAW 10-6. As RE, PROVIDE the following
CRS directs withdrawing guidance:
control rods IAW RE guidance.
Withdraw Control Rods IAW REMA.
Emergency Load reductions will be performed using SPRG. ESG-2016 NRC-1 Page 8 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response
RO withdraws control rods IAW REMA guidance and HC.OP-SO.SF-0001.
=:. Presses the desired Control Rod Select PB =:. Momentarily presses the WITHDRAW PB =:. After the withdrawal cycle is completed, ENSURE that the rod position indicates that the rod is in the correct, even numbered position and initials REMA. Rod 30-39 Stuck:
RO determines rod 30-39 is stuck and informs the CRS. Rod 30-39 Stuck is pre-inserted.
CRS Implements AB.IC 0001 CRS refers to TIS Condition F 3.1.3.1 if rod is =:. determined to be non-moveable.
,,
RO performs actions of Condition F of AB.IC-0001:
=:. Verifies NO Rod Blocks are present. =:. Attempts to operate the drive in both directions to determine the exact condition of the Control Rod. =:. Vent Control Rod using Continuous Insert PB. =:. Attempts to withdraw Control Rod using Withdraw PB (including Continuous Withdraw PB). ESG-2016 NRC-1 Page 9 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response ::::;. Simultaneously presses and holds both the Withdraw PB and the Continuous Withdraw PB. ::::;. Momentarily presses and then releases the CONTINUOUS INSERT PB(this step may be repeated).
. Releases both the Withdraw PB and the Continuous Withdraw PB.

:::;. Raises the drive water pressure in approximately I 50 psid increments, not to exceed 500 psid (to approximately 315 psig) by throttling closed HV-F003 ::::;. Attempts to notch in OR notch out the control rod at each new pressure increment.
RO determines that the control rod is freed and returns the drive water pressure to the normal operating range (260-270 psid on A3015).
RO ensures that rod 30-39 is at the desired position and initials REMA. ESG-2016 NRC-1 Page 10 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response Earthquake:
Crew recognizes Seismic After CRD is returned to normal Event by: and at the discretion of the Lead OHA C6-C4 "SEISMIC Examiner, MON PNL C673"
PLAY the Earthquake Sound GRIDS D3977 "SEISMIC Effect (if available}
at medium TROUBLE ALARM TRBL" volume for about 15 seconds Response Spectrum OR Analyzer indications on ANNOUNCE "You feel motion 10C650C then it stops", AND TRIGGER Loud rumbling noise ET-2 (if available)
Crew monitors critical parameters to determine if plant is stable. I !E Crew calls National Earthquake
CRS implements Center, AB.MISC-0001:
THEN REPORT a seismic event of Condition E 6.0 on Richter scale centered 12 Condition F miles east of Wilmington, DE. !E Crew calls Security,
RO/PO implements THEN REPORT the Security AR.ZZ-0011 Attachment C4. system is intact. !E dispatched to 1 OC673,
Crew dispatches ABEO to THEN REPORT: 10C673.
The Event Indicator is WHITE
Crew recognizes a seismic
The tape machines have event >0.1 g has occurred advanced but are not running
The Amber Alarm light on the Seismic Switch Power Supply drawer is lit. IF directed to reset 1 OC673,
RO/PO directs ABEO to reset THEN DELETE Malfunction 1 OC673 IAW SO.SG-0001.
PC07A.
RO/PO record Seismic Response Spectrum Analyzer lights on AR.ZZ-0011 Att. C4-1. ESG-2016 NRC-1 Page 11 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response
RO/PO reset Seismic Response Spectrum Analyzer IAW SO.SG-0001.
IF directed to investigate EOG
RO/PO investigates A EOG alarms, THEN REPORT alarms LO and HI Priority Alarms. were Fuel Oil Day Tank Hi/Lo alarms. EHC Filter Clogging:
Crew recognizes clogging of EHC Filter Clogging is automatically AP116 EHC pump discharge filter by: inserted on ET-2. => OHA D3-F5 "TURB HYDR PUMP TROUBLE" => GRIDS 03627 "MAIN ' TURB EHC PUMP A FILTER DP" lnSight Item:
RO/PO responds to OHA IAW CRS may refer to
EHC Header Pressure HC.OP-AR.ZZ-0014 and AB.BOP-0003.
tupehchd HC.OP-AR.ZZ-0024.
EHC Pump Disch Pressure tup.ehc(1-2)
EHC Pump Filter D/P tupehcdp(1-2)
IF dispatched to the EHC pump,
RO/PO directs EO to the EHC THEN REPORT AP116 discharge skid to investigate the problem filter dp is very high.
RO/PO presses HYDR FLUID PUMP B MAN Pb. ENSURE ET-4 actuates when RO/PO presses BP116 BP116 is started.
START Pb and ensures HDYR FLUID PUMP BLOW DISCH PRESS is OFF. IF dispatched to swap EHC filters,
RO/PO directs EO to SWAP THEN REPORT EHC Pump AP116 the AP116 HYDR FLUID filters have been swapped. PUMP in service Discharge Filter IAW HG.OP-SO.CH-0001 (Q). ESG-2016 NRC-1 Page 12 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response
RO/PO presses HYDR FLUID PUMP A STOP Pb.
RO/PO presses HYDR FLUID PUMP A AUTO Pb. Stuck Open SRV:
Crew recognizes SRV open At the discretion of the Lead by: =:> OHA C1-A3 "ADS/SAFETY Examiner, TRIGGER ET-3 (PSV RELIEF VALVE NOT F013D Inadvertent Opening).
CLOSED" =:> Acoustic Monitor Indication on 10C650C =:> Tailpipe temperature on TR-R614 =:> L:.owering MWe =:> Steam Flow to Feed Flow mismatch =:> RPV level swell lnSight Items:
PO cycles SRV control switch
PSV-F013D Position in attempt to close the SRV . advpos(4)
F013D B Channel Switch ,, zdads1(4)
F013D D Channel Switch zdads2(4)
CRS implements AB. RPV-0006.
CRS recognizes SRV will not Action taken to comply close within two minutes, with T/S 3.4.2.1.b.
directs: =:> Reducing recirc pumps to minimum speed =:> Locking the Mode Switch in SHUTDOWN ESG-2016 NRC-1 Page 13 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response
RO performs the following:
. Reduces Recirc Pumps A & B to minimum speed

::;. Locks the Mode Switch in SHUTDOWN :::;. Performs scram actions IAW AB.ZZ-0001 Att. 1. ATWS >4%:
Crew recognizes Scram Condition and Reactor Power The half core A TWS is already Above 4% EOP entry inserted on the right side of the condition:
core. :::;. Rod FULL IN lights on Full Core Display Not lit as I expected :::;. APRM indications show higher than expected power levels
CRS enters EOP-101A.
Crew recognizes RPV Level Below 12.5" EOP entry ,, condition by: :::;. OHA C5-A4 "RPV WATER LEVEL LO" :::;. OHA A7-D5 "RPV LEVEL 3" :::;. Various water level indicators
CRS directs: :::;. Initiating SLC :::;. Verifying RWCU Isolates
Crew starts AP208 SLC ENTER Suppression pump before Suppression Pool temp when AP208 Pool temperature reaches SLC pump is started: 110 degrees. Temp: ESG-2016 NRC-1 Page 14 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response RWCU Failure to Isolate:
RO/PO manually initiates SLC identifies that RWCU FAILS to RWCU failure is pre-inserted.
isolate, isolates RWCU by closing HV-F001 and HV-F004, and notifies CRS of responses and actions taken. Failure of SLC to Auto-Start/Trip
Crew recognizes trip of BP208 of SLC Pump: SLC pump by: => OHA C1-B1 "SLC The BP208 SLC pump will trip 5 PUMPNALVE O/PF" seconds after starting.
=> OHA C1-F1 "SLC/RRCS INITIATION FAILURE" => CRIDS D3023 "SLC INJ I PMP BP208 TROUBLE TRBL" => Flashing STOP light for BP208 IF dispatched to investigate trip of
Crew dispatches NEO and BP208, Maintenance to investigate trip THEN REPORT the motor is hot to of BP208 SLC pump. the touch and the breaker will not reset. (52-222101)
CRS directs: => Verifying Recirc runback to minimum => Tripping reactor recirc pumps
RO/PO: => Verifies Recirc runback to minimum => Trips reactor Recirc Pumps
CRS directs inhibiting ADS .
RO/PO inhibits ADS IAW AB.ZZ-0001 Att. 13. ESG-2016 NRC-1 Page 15 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response
CREW prevents an This Critical Task is not uncontrolled applicable if RPV level depressurization during never reaches -129". A TWS conditions by See justification for preventing ADS failure criteria.
ACTUATION.
REFER to the appropriate EOP and
CRS directs performance of The timing, order, and SUPPORT Crew requests for EOPs the following EOPs: priority of the EOP IAW with the following.
Validated
=;. EO.ZZ-0320 "Defeating performance may vary. execution time delays are built-in:
ARI and RPS Interlocks" EOP-301: ET-8 =;. EO.ZZ-0301 "Bypassing EOP-311: ET-9 MSIV Isolation Interlocks" EOP-319: ET-10 =;. EO.ZZ-0311 "Bypassing EOP-320: ET-11 Primary Containment EOP-322: ET-12 Instrument Gas Isolation 1 Interlocks" STRATEGIES FOR SUCESSFUL
=;. EO.ZZ-0319 "Restoring TRANSIENT MITIGATION Instrument Air in an Promptly initiate actions IAW the 300 Emergency" series EOPs to shutdown 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.
CRS directs terminating and preventing injection to the RPV with the exception of: =;. SLC =;. CRD =;. RCIC ESG-2016 NRC-1 Page 16 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response
RO/PO terminate and prevent injection IAW AB.ZZ-0001:
=> Attachment 16 (1 OC651) => Attachment 17 (1 OC650)
CRS directs maintaining RPV The first RHR pump to water level between -50" be started will trip. Refer and -185". to RHR Pump Trip event description on page 19.
RO/PO control level as directed by CRS with: => Feedwater IAW AB.ZZ-0001 Att. 14 => RCIC IAW AB.ZZ-0001 Att. I 6 => HPCI IAW EOP-322
Crew maintains or restores adequate core cooling by maintaining or restoring RPV level above-185" /AW EOP-101A without ,, Emergency Depressurizing.
CRS directs bypassing the RWM and commencing manual rod insertion.
RO/PO aligns CRD for A TWS operation IAW AB.ZZ-0001 Attachment
18.
RO/PO bypasses RWM and inserts control rods IAW RE-AB.ZZ-0001 Attachment
1. ESG-2016 NRC-1 Page 17 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response Total Loss of EHC:
RO/PO recognizes loss of both EHC Pumps and informs Ensure ET-is active following the CRS. trip of SLC Pump 8. The bypass valves will fail shut about 2 minutes later.
RO/PO aligns CRD for A TWS operation IAW AB.ZZ-0001 Attachment
18.
Crew recognizes turbine bypass valves failing shut by: ==> OHA D3-D5 "EHC UNIT PANEL 1 OC363" ==> DEHC Bypass Valve Positioning Error alarms ==> Reactor pressure rising above Pressure Setpoint STRATEGIES FOR SUCESSFUL
CRS directs stabilizing When pressure control TRANSIENT MITIGATION pressure below 1037 psig swaps to SRVs, Pressure Leg with: maintaining RPV water Direct initial pressure control as Stabilize
==> Main Stearn. Line Drains level between -50" and pressure 800 psig to 1000 psig. The lower SRVs -129" will be very limit of 800 psig will not complicate RPV ==> level maintenance and will prevent an ==> RPFT challenging due to unwanted cooldown.
The upper limit of shrink and swell and 1000 psig is a round number below 1047 changing reactor psig. pressure with the RFPTs in MAN.
RO/PO control pressure as directed by CRS with: ==> Main Steam Line Drains IAW AB.ZZ-0001 Att. 15 ==> SRVs IAW AB.ZZ-0001 Att. 13 ==> RFPTs ESG-2016 NRC-1 Page 18 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Comments Response
Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by: :::;. OHA C8-F1 "SUPPR POOL TEMP HIGH" :::;. Flashing 95 degree status light on 1 OC650C :::;. RM11 9AX833/834 alarm :::;. Various Suppression Pool temperature indicators Strategies For Successful Transient
CRS implements EOP-102 . Mitigation Torus Temperature Leg Start all available Torus cooling as soon as possible to remove heat from containment.
CRS directs placing RHR in I Suppression Pool Cooling.
RO/PO place RHR in Suppression Pool Cooling IAW AB.ZZ-0001 Att. 2 or 3. TriQ of RHR PumQ:
RO/PO recognizes RHR RHR Pump will trip after placing it Pump trip. in service, or it starting automatically.
CRS directs placing remaining A/B RHR pump in Suppression Pool Cooling.
RO/PO place remaining A/B RHR pump in Suppression Pool Cooling IAW AB.ZZ-0001 Att. 2 or 3. ESG-2016 NRC-1 Page 19 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response IF dispatched to investigate the trip
Crew dispatches operator and of the A/B RHR pump, Maintenance to the tripped THEN REPORT: RHR pump and breaker.
The breaker has target flags dropped on the 51A and 518 Time Overcurrent relays (401/402 bkr 06)
The pump motor is hot to the touch and bearing oil levels are normal
IF Suppression Pool temperature is >110 degrees, AND Reactor power is >4%, AND SRVs are open or ; cycling, THEN Crew terminates and prevents injection to the RPV with the exception of SLC, CRD, and RCIC, UNTIL Reactor power is <4%, OR RPV level reaches -129", OR SRVs remain closed. * : !E RPV level reaches -129", *THEN RO/PO terminate and prevents injection from Core Spray IAW AB.ZZ-0001 Attachment
16. WHEN the Crew has reset RPS,
WHEN EOP-320 Section 5.1 THEN DELETE Malfunctions RP06 and 5.2 are complete, AND RP07 to allow full rod THEN the Crew implements insertion on the next scram. EOP-320 Section 5.3 and reset RPS. At the Lead Examiners discretion,
WHEN OHA C5-B4 clears, MODIFY lnSight Item lclsdv to THEN the Crew initiates a accelerate draining of the SDV. manual scram IAW EOP-320 Section 5.3. ESG-2016 NRC-1 Page 20 of 28 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Comments Response
CREW fully inserts all control rods via RMCS and/or manual scram(s) IAW HC.OP-EO.ZZ-0320.
CREW fully inserts all control rods via RMCS and/or manual scram(s) /AW HC.OP-EO.ZZ-0320; OR inserts Cold Shutdown Boron Weight.
Crew recognizes the reactor is shutdown by: ::::::> SPDS ALL RODS IN I ::::::> RWM Confirm Shutdown ::::::> GRIDS Rod positions
CRS directs terminating SLC injection.
RO/PO terminates SLC injection.
Termination Reguirement:
CRS exits EOP-101A, enters The scenario may be terminated at EOP-101. the discretion of the Lead Examiner when:
RPV Level is being maintained above-185" AND
All rods are fully inserted ESG-2016 NRC-1 Page 21 of 28 Rev. 1 SIMULATOR COPY OF ----EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 2016 NRC EXAM SCENARIO SCENARIO NUMBER: ESG-2016NRC-2 EFFECTIVE DATE: Effective When Approved EXPECTED DURATION:
60 Minutes REVISION NUMBER: 0 PROGRAM: 0 LICENSED OPERATOR REQUALIFICATION INITIAL LICENSE OOTHER: REVISION
SUMMARY

Incorporated minor Editorial comments from validation.
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. Place Remaining Circulating Water Pumps In-Service B. Raise Power with Control Rods C. Flow Unit Failure D. LossofBD481120VAC 1E Inverter E. Steam Leak in the Steam Tunnel-Scram-MSIV Isolation Failure F. LOCA G. Suppression Pool Leak II. SCENARIO
SUMMARY
A Reactor startup is in progress following a forced outage. Nitrogen Makeup to the Drywell is:* in progress following lnerting the Containment.
The crew will place remaining Circulating Water Pumps in-service.
Power will then be raised using Control Rods. During rod movement a Recirculation Flow Unit will fail initiating a % Scram and Rod Block. The crew will take action to bypass the failed Flow Unit and reset RPS in order to continue with the startup. A loss of a Class 1 E 120VAC Inverter will cause a trip of the running Fuel Pool Cooling System (FPCS) pump and cause a loss of Reactor Building Ventilation.
The crew will restore FPCS flow and cooling, and put FRVS in service. A steam leak develops in the Steam Tunnel that requires a scram and closure of the Main Steam Isolation Valves (MS IVs). Manual action will .. be required to ensure isolation of the Main Steam Lines. A small break LOCA will develop during pressure control operations which will raise Drywell Pressure to above the High-High Pressure setpoint.
A break develops on the suction line to RHR Pump D when the pump starts. The crew will be required to isolate the leak to maintain Suppression Pool level without Emergency Depressurizing the Reactor. ESG-2016NRC-2 Page 2 of 21 Rev. 1 V. INITIAL CONDITIONS:
l.C. Initial INITIALIZE to IC at approximately 9% power with Reactor Startup in progress.
---INSERT Control Rods (Reverse Pull) to stabilize power at approximately 5%. ---DE-INERT Containment.
---ENSURE HC.OP-IO.ZZ-0003 complete through Step 5.3.38, and 5.3.39A, B, and G. ---ENSURE Containment is inerted, and Drywell makeup is in progress.
---ENSURE TAGS is supplied by SACS A. ---ENSURE HV-2173, CLG TWR BYPASS VALVE is CLOSED. ---ENSURE sufficient Condensate Demineralizers are in service/standby to support startup ---PREP FOR TRAINING (i.e., RM-11 set points, procedures, bezel covers) Initial I MARKUP HC.OP-IO.ZZ-0003;through Step 5.3.38, and 5.3.39A and G; N/A E and F. ------MARKUP HC.OP-SO.DA-0001 through Step 5.1.31. MARKUP HC.OP-SO.AC-0001 through Step 5.2.7.R.5.
---MARKUP HC.OP-SO.CG-0001 through Step 5.9.3 [5.9.2 is N/A]; and Att 3 to 1.4.D for ---degraded vacuum. ---MARKUP HC.OP-SO.GS-0001 through Step 5.2.10. ---MARKUP Rod Pull List to Step 359, Rod 42-43@ 06. ENSURE REMA available for Startup ---At a minimum review the Scenario Reference section and CLEAN the balded EOPs, ABs ---and SOPs listed. (80091396 0270) ---COMPLETE "Simulator Ready-for-Training/Examination Checklist".
EVENT FILE: Initial Event 6 Event Code: rh_bkr(4)
==
Description:==
RHR Pump D Start 7 Event Code: rhv004(4)
<= 0
Description:
HV-F004D Closed ESG-2016NRC-2 Page 3 of 21 Rev. 1 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction NM12D to 0 on event 1 Flow summer K607D failure None None Insert malfunction ED09B1 on event 2 Loss of 120 VAC class 1 E inst bus 1 BD481 None None Insert malfunction MS04B to 80.00000 in Steam line B leak in tunnel 180 on event 3 None None Insert malfunction MS19B MSIV F022B fail to auto isolation None None Insert malfunction MS20B MSIV F028B fail to auto isolation None None Insert malfunction RR31A1 to 40.00000 in Recirc loop A small break [V] (10%-60 300 on event 4 gpm, 100%-600 gpm) None None Insert malfunction RH07D after 5 on event RHR Leak via Pump Suction, Loop D 6 None None Insert malfunction PC06 to 2.00000 on Suppression pool break event 6 None None Insert malfunction PC06 to 0 on event 7 Suppression pool break delete in 1 ' None None Insert malfunction HP06E HPCI aux oil pump failure to auto start REMOTE SCHEDULE:
Initial <@Time Event Action Description None None Insert remote HV011 to STOP on event 3 HV011 Steam tunnel unit cooler AVH216 None None Insert remote HV006 to STOP on event 9 HV006 RBVS Supply fan C None None Insert remote HV005 to STOP on event 9 HV005 RBVS Supply fan B None None Insert remote HV004 to STOP on event 9 HV004 RBVS Supply fan A None None Insert remote HV003 after 5 to STOP on HV003 RBVS Exhaust fan C event 9 None None Insert remote HV002 after 6 to STOP on HV002 RBVS Exhaust fan B event 9 Insert remote HV001 after 7 to STOP on \ None None event9 HV001 RBVS Exhaust fan A ESG-2016NRC-2 Page 4 of 21 Rev. 1 OVERRIDE SCHEDULE:
Initial @Time Event Action Descriotion ESG-2016NRC-2 Page 5 of 21 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity PLACE REMAINING
CIRCULATING WATER PUMPS IN-SERVICE
INSERT Remote AN-06 to NORM when necessary to acknowledge local alarm on pump start. RAISE POWER WITH CONTROL
RODS
I ESG-2016NRC-2 Expected Plant/Student Response CRS directs placing remaining Circulating Water Pumps in-service IAW HC.OP-SO.DA-0001. PO places remaining Circulating Water Pumps in-service IAW HC.OP-SO.DA-0001: => OBSERVE CIRCULATING WATER PUMP STR ENBL is illuminated
=> PRESS Pump START push-button.
=> OBSERVE DISCH VAL VE OPEN/CLOSE MID I illuminates
=> PRESS Pump START push-button.
=> OBSERVE DISCH VALVE OPEN/CLOSE MID illuminates
=> PRESS DISCH VAL VE HV-2152A(B,C,D)
OPEN FULL push-buttons to open fully each valve. CRS directs power ascension IAW 10-3 and REMA. CRS directs withdrawing control rods IAW REMA guidance.
Page 6 of 21 Comments Rev.1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity
Flow summer K607D failure:
After the Crew raises power, OR, at the discretion of the Lead Examiner, TRIGGER ET-1. * ,, If panels are opened, state that
indications on 1 OC608 indicate K607D meter is downscale.
Flow Unit D COM PARA TOR and Flow Unit C Comparator lights on 1 OC608 should be illuminated.
ESG-2016NRC-2 Expected Plant/Student Response RO withdraws control rods IAW REMA guidance and HC.OP-SO.SF-0001.
=> Presses the desired Control Rod Select PB => Momentarily presses the WITHDRAW PB => After the withdrawal cycle is completed, ENSURE that the rod position indicates that the rod is in the correct, even numbered position.
=> Initials Rod Pull Sheet Crew monitors Reactor power, pressure, and level and ensure plant conditions are stable. Crew recognizes K607D failure Downscale by: => [C6-D1] "APRM/RBM FLOW REF OFF NORMAL". => Flow Units C & D "COMPAR" status lights. => CRIDS C049 "RECIRC FLOW COMPAR". RO refers to HC.OP-AR.ZZ-0020, CRIDS C049: => CHECK flow unit readings AND under the direction of the SM/CRS BYPASS the unit having an off normal reading. Page 7 of 21 Comments Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity
NOTE: WHEN directed by the crew to place the flow unit mode switch to the "unlabeled" position, THEN MODIFY NM120 to 100%. If panels are opened, state that
indications on 1 OC608 indicate K607D is INOP. * *
ESG-2016NRC-2 Expected Plant/Student Response Crew enters OP-AB.IC-0004
=> Condition F => Crew bypasses the affected Flow Unit. => Crew refers to DD.ZZ-0020 for a failed PPG Sensor. => Crew directs Reactor Engineering to evaluate the flow unit failure on the PPG. => Crew directs l&C to PLACE the MODE Switch, on the D flow to the "UNLABELED" position between STANDBY and ZERO. => Crew verifies RPS Trip clear. PO may check indications on 1 OC608 and reports K607D is now BYPASSED.
Crew contacts Maintenance to troubleshoot K607D failure. Crew contacts Operations Management.
CRS enters Tracking LCOs for Tech Spec 3.3.6 [since Mode 2], and may enter a Tracking LCO for 3.1.4.3 [since Mode 2]. Page 8 of 21 Comments Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student
Response Comments LOSS OF BD481120 VAC 1E
Crew identifies the loss of INVERTER BD481 by: AFTER actions are completed for OHA D3-E3 120VAC UPS the stuck control rod, OR at the TROUBLE discretion of the Lead Examiner, GRIDS Page 167 TRIGGER ET-2. GRIDS D4971 in alarm
CRS enters AB.ZZ-0136 and directs actions IAW Note: M/U to the drywell AB.ZZ-0136:
will isolate on the Assess all plant systems inverter loss. RCIC is inoperable due to no and enter appropriate power to the Flow Abnormal Procedures Controller. Determine failed inverter
CRS implements AB.COOL-I 0004 for the loss of FPC Flow: Condition I
PO restores Fuel Pool Cooling System flow IAW AB.COOL-0004 by restarting at least one Fuel Pool Cooling Pump as follows: ,, Ensures Skimmer Surge Tank> 22". Opens 1-EC-HV-4689A(B), FILTER DEMIN BYPASS VALVE. Closes 1-EC-HV-4689B(A), FILTER DEMIN BYPASS VALVE. Closes either 1-EC-HV-4676A OR 1-EC-HV-4676B, F/D INL ISLN. Starts one Fuel Pool Cooling Pump A(B)P211.
CRS implements AB.COMP-0002 for the Inadvertent B Channel Isolation.: Condition E ESG-2016NRC-2 Page 9 of 21 Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity * * ' ,, *
IF directed to secure RBVS,
THEN TRIGGER ET-9. ESG-2016NRC-2 Expected Plant/Student Response PO ensures Isolations per Attachment 5 for B Channel. => KL-HV5126B
=> KL-HV5172B Crew recognizes Loss of RBVS by: => RB D/P indication on 10C650E => 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" => GRIDS D3960 "RBVS EXH RMT PNL C382 TRBL" => GRIDS D3961 "RBVS SUPPLY RMT PNL C382 TRBL" CRS implements AB.CONT-003:
=> Condition A => Condition D CRS recognize the following Tech Specs actions apply for the loss of Secondary Containment Integrity.
=> 3.6.5.1, IF unable to draw down the secondary containment to greater than or equal to 0.25" vac wg RO/PO places FRVS in service IAW SO.GU-0001, or AB.ZZ-0001 Attachment
20. Page 10 of 21 Comments Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity If sent to investigate Inverter
problem, report Blown Main Fuse indicated on the Inverter Section. STEAM LEAK IN THE STEAM
TUNNEL-SCRAM AFTER FPCCU System flow has . been restored, OR at the discretion of the Lead Examiner, TRIGGER ET-3. IF dispatched to check the status
of Steam Tunnel Unit Coolers, THEN REPORT both Steam Tunnel Unit Coolers are in service (Do NOT actually place the coolers in service).
At the Lead Examiners discretion,
RAISE Steam Tunnel temperature to 165 degrees in 2 degree increments using Insight Item mstunl. ESG-2016NRC-2 Expected Plant/Student Response CRS recognize the following Tech Specs actions apply for the loss of BD481: => Distribution
-Operating 3.8.3.1 action a AND d Crew recognizes rising temperature in the Steam Tunnel by: => CRIDS A2541 "ST TUNNEL 10 VH216 INLET AIR" => OHA D3-A3 "MN STM/RWCU AREA LEAK TEMP HI" => CRI DS D5866 "RWCU/MAIN ST LEAK DETTMPCHW" CRS implements AB.BOP 0005: => Condition A WHEN the Crew determines Steam Tunnel temperature cannot be maintained below 145 degrees THEN CRS DIRECTS: => Lock the Mode Switch in Shutdown Page 11 of 21 Comments 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to reenergize panel and restore inverter within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or Hot SD in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold SD in following
24. ' .. Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Reports Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status IAW 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.
MSIV ISOLATION FAILURE MSIV isolation failure is pre-inserted.
ESG-2016NRC-2
* * *
Expected Plant/Student Response RO observes Recirc pump speeds at minimum and locks the Mode Switch in SHUTDOWN and performs scram actions IAW AB.ZZ-0001 Att. 1. CRS implements AB-000 . CRS may direct placing FRVS in service. Crew recognizes isolation signal has been generated by: OHAsC8-A14,NSSSS MSIV LOGIC A(B,C,D) INITIATED OHA C8-C4, NSSSS ISLN SIG-STM TNL TEMP HI RO recognizes all MSIVs are NOT closed, closes at least one valve in the failed line, and informs CRS. Page 12 of 21 Comments Crew may isolate the MSLs before isolation signal is received.
Immediate Operator Actions AB-CONT-0002. Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity LOCA AFTER the MSIVs have been closed, OR at the discretion of the Lead Examiner, TRIGGER ET-4. ESG-2016NRC-2 Expected Plant/Student Response *Crew prevents an uncontrolled leak of steam outside of secondary containment by closing at least one MSIV in each Main Steam Line.
Crew recognizes LOCA condition:
=> OHA C6 81 "OLD SYSTEM ALARM/TRBL" => RM11 9AX314 OLD FLOOR ORN FLOW alarm => Rising Drywell Pressure
CRS implements AB.CONT-001: => Condition A
RO/PO ensures drywell cooling maximized.
Crew checks => Recirc pump seal parameters
=> SRV temperatures
Crew recognizes High Drywell Pressure EOP-101 and 102 entry condition:
=> OHA A 7-04 "DRYWELL PRESSURE HI/HI" => OHA C5-B5 "DRYWELL PRESSURE HI" => Various system initiations and isolations Page 13 of 21 Comments Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity * *
I SUPPRESSION POOL LEAK
ENSURE ET-6 activates when RHR D pump starts. * ,,
NOTE: Entry into EOP-103 may
not be made until reports of high water levels or Room Flood Alarm is received.
ESG-2016NRC-2 Expected Plant/Student Response Crew recognizes High Drywell Temperature EOP-102 entry condition:
=> CRIDS 85070 SPDS DRYWELL AVG TEMP in alarm. CRS enters EOP-102, and EOP-101. Crew recognizes LOCA Sequencer failure and starts/imitates various system initiations and isolations as necessary Crew recognizes lowering torus water level. Crew recognizes Supp Pool Level Below 7 4.5 In EOP entry condition by: => OHA B1-C3 "SUPPRESSION POOL LEVEL HI/LO" => Various Suppression Pool level indicators CRS re-enters EOP-102 . CRS implements EOP 103/104. Page 14 of 21 Comments Rev. 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity IF dispatched to 'D' RHR pump room, THEN REPORT there is about three inches of water on the floor. Water is coming from a cracked weld on an elbow of the 'D' RHR pump suction line. Expected Plant/Student Response
Crew dispatches NEO and Maintenance to 'D' RHR pump room. IF directed to place the DP202
RO/PO close 'D' RHR suction RHR pump breaker in PTL, valve. THEN INSERT REMOTE ET109T TO TAGGED. IF directed to implement EOP-315, THEN REPORT operators will be briefed and sent into the field. Do NOT open makeup valves until after leak is isolated.
TERMINATION REQUIREMENT:
The scenario should be terminated at the discretion of the Lead Examiner when:
RPV Level and Pressure Control is established and
The RHR leak has been isolated.
ESG-2016NRC-2
Crew isolates Suppression Pool leak and prevents a required Emergency Depressurization.
RO/PO coordinates implementation of EOP-315 with NEO. Page 15 of 21 Comments Rev. 1 SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION:
REVISION NUMBER: PROGRAM: REVISION
SUMMARY
SIMULATOR EXAMINATION SCENARIO GUIDE COPY OF ----PCIG Leak/Loss of 10A110/Loss of Feedwater/HPCI Trip/LOCA ESG-2016 NRC-3 Effective When Approved 1.0 Hour 1 x I LO. REQUAL X I INITIAL LICENSE .___ _ __.I OTHER 1. Incorporated Editorial comments from validation.
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. Recirculation Pump Runaway B. Primary Containment Instrument Gas Leak C. Loss of 10A110 D. Loss of Feedwater with Automatic Scram Failure E. Trip of HPCI F. LOCA G. Failure of 'A' Channel Core Spray and RHR Logics Ill. SCENARIO
SUMMARY
The scenario begins with the plant at 95% power with power ascension in progress.
A Recirculation Pump runaway will occur during power ascension.
The crew will need to lower power to less than the license maximum power level. After actions have been taken' for the power excursion a Primary Containment Instrument Gas Leak will develop and require the crew to isolate a portion of the PCIG System to stop the leak. After the leak has been isolated, the 1OA110 7 .2 KV bus is lost. The plant stabilizes in the OPRM Enable Region and power will rise to Region 1 due to the loss of Feedwater heating from the load reduction.
The Crew must insert control rods to maintain the plant outside of Region 1. After exiting Region 1, 'C' PCP and all SCPs trip causing a complete loss of Feedwater.
RPS fails to actuate on L VL 3 or the Mode Switch, and RPS or ARI must be manually initiated to shutdown the Reactor. Shortly after the reactor is scrammed, HPCI will trip due to a failed turbine exhaust pressure transmitter.
A LOCA will occur which will be beyond the capacity of available high pressure injection.
The 'A' Channels of Core Spray and RHR will fail to automatically initiate, but can be manually initiated.
The Crew must Emergency Depressurize and restore level with low pressure ECCS. ESG-2016 NRC-3 Page 2 of 28 Rev.: 1 IV. INITIAL CONDITIONS:
l.C. Initial ---INITIALIZE the simulator to 100% power, MOL, TACS on SACS Loop A ---ENSURE 'D' SACS pump is in service and 'B' SACS pump in STBY. LOWER power to 95% with Recirculation Pumps. ---EQUALIZE Xenon concentration.
---ENSURE CROSSFLOW is BLOCKED and NOT APPLIED. ------ENSURE associated Schedule file open and running. ENSURE associated Events file open. ---PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers) I initial I Description

ENSURE Data Collection is trending the following variables:

Instrument Air Header Pressure:
iapiarca/iapiarcb or equivalent
'
W/R Reactor Water Level: rrln091a or equivalent
Fuel Zone Reactor Water Level: rrlfzcha or equivalent At a minimum review the Scenario Reference section and CLEAN the balded EOPs, ABs and SOPs listed. (80091396 0270) COMPLETE the Simulator Ready for Training/Examination Checklist.
ESG-2016 NRC-3 Page 3 of 28 Rev.: 1 EVENT FILE: Initial ET# 3 Event code: crqnmi <= 10
Description:
Reactor Power <= 10% 4 Event code: hpnt >= 2500 & monvar{174)
>= -50
Description:
HPCI running and RPV Water Level >= -50" 7 Event code: zcrpsudn
Description:
Mode Switch in SHUTDOWN 8 Event code: zcrpsudn
Description:
Mode Switch in SHUTDOWN 10 Event code: crqnmi <= 7.0
Description:
Reactor Power <= 7% 11 Event code: crqnmi <= 7.0
Description:
Reactor Power <= 7% 12 Event code: rrprv <= 765
Description:
Reactor Pressure <750 psig 13 Event code: ZDRRS621{5)
& !et_array{14)
==
Description:==
RR A raise pb first 14 Event code: ZDRRS621{6)
& !et_array{13)
==
Description:==
RR B raise pb first ESG-2016 NRC-3 Page 4 of 28 Rev.: 1 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction AD01 Failure of ADS valves to open None None Insert malfunction PC03E from Drywell pressure transmitter N094E 0.40000 to 0.40000 failure None None Insert malfunction RR20E from ECCS level transmitter N091 E failure 30.00000 to 30.00000 None None Insert malfunction RZ01 E to 31 RRCS Level Transmitter L T-N402E Failure None None Insert malfunction RZ01 F to 31 RRCS Level Transmitter LT-N402F Failure None None Insert malfunction IA03 from 0.00000 Loss of drywell instrument gas to 25.00000 in 600 on event 1 None None Insert malfunction ED03 on event 2 Loss of 7.2 KV bus E 10A110 None None Insert malfunction QQ02 to SEIZE on Condensate pump BP102 trip event 3 None None Insert malfunction QQ03 to SEIZE on Condensate pump CP102 trip event 3 None None Insert malfunction FW04B after 3 on Secondary condensate pump BP137 trip event 3 ;None None Insert malfunction FW04C after 3 on Secondary condensate pump CP137 trip event 3 None None Insert malfunction HP03 on event 4 HPCI turbine trip None None Insert malfunction AN-81 C4 on event 4 CRYWOLF ANN B1C4 HPCI TURBINE TROUBLE None None Insert malfunction CD08A on event 4 CRD suction filter AF201 clogging None None Insert malfunction CD08B on event 4 CRD suction filter BF201 clogging None None Insert malfunction RR31 A2 after 120 to Recirc loop A large break [V] (10%-6000 5.00000 in 600 on event 4 gpm, 100%-60000 gpm) None None Insert malfunction TC01-10 on event All turbine bypass valves fail closed 12 None None Insert malfunction RZ01 E to 31 on RRCS Level Transmitter L T-N402E event 10 delete in 1 Failure None None Insert malfunction RZ01 F to 31 on RRCS Level Transmitter L T-N402F event 11 delete in 1 Failure None 7 SET rp_k14b = 0.0 Allows Mode Sw to trip 81 RPS None 8 SET rp_k14d = 0.0 Allows Mode Sw to trip 82 RPS ESG-2016 NRC-3 Page 5 of 28 Rev.: 1 REMOTE SCHEDULE:
Initial @Time Event Action Description None None Insert remote EP11 to INSTALLED EP11 EOP-320 (step 5.2.2), RPS division 1 jumper None None Insert remote EP13 to INSTALLED EP13 EOP-320 (step 5.2.3), RPS division 3 jumper None None Insert remote CD04 to OPEN on event CD04 CRD suction filter isolation valve 5 V030 OVERRIDE SCHEDULE:
Initial @Time Event Action Description None None Insert override 3S22_D_DI to On RPS MODE SWITCH -RUN (DI) None None Insert override 10S200_A_DI to Off HV-F021 B OPEN (DI) ' None None Insert override 9DS41_A_LO to On on TRIP UNIT IN CAL OR GROSS FAIL (LO) event 4 None None Insert override 3A28_C_DI to On on SIC-R621 A RAISE-REC I RC PUMP A (DI) event 13 None None Insert override 3A46_C_DI to On on SIC-R621 B RAISE-REC I RC PUMP B (DI) event 14 ESG-2016 NRC-3 Page 6 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Recirculation
Crew recognizes Reactor Runaway: Recirculation pump runaway by: Ensure ET-13(14) (Stuck ==> OHA C1-A5 "COMPUTER RAISE push button) is POINT IN ALARM" triggered when RR Pump ==> Reaciorpower>100%
speed is increased.
==> CRIDS D2899(2900) "RECIRC MG A(B) SPEED CONTROL SIG FAIL" ==> CRIDS D2930(1) "RECIRC MG A(B) DRIVE TUBE LOCK TRBL" ==> SIC-R621A(B)
SPEED DEMND and SPEED Upscale ==> 1 OC650C Recirc and Jet pump indications
RO performs the following:
I ==> Presses SCOOP TUBE TRIP Immediate Operator for 'A' Recirc Pump Action IAW ==> Reduces A(B) Recirc Pump AB.RPV-0001.
speed to reduce power to Note: RR lockup may pre-transient value occur before pressing SCOOP TUBE TRIP ob.
CRS implements AB.RPV-001:
==> Condition F
Crew reduces power to ::; 3840 RECORD the time that MWt as indicated by the PPC 5 power was above 3840 minute average following the MWt. Recirc Pump runaway. TIME:
Crew checks Recirc Loop Flow mismatch IAW ST.BB-0001.
SUPPORT requests for local
Crew ensures Recirc MG Oil control of Recirc MG Oil Temperatures are maintained in Temperatures.
ADJUST the normal band. REMOTES CW15 and CW16 as necessary.
Crew Monitors Offgas Pretreatment AND Main Steam Line Radiation Monitors for indications of Fuel Damage. ESG-2016 NRC-3 Page 7 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments IF called as RE to determine
Crew determines peak thermal maximum thermal power power during the transient.
reached, THEN REPORT APRM power peaked at 103.6%.
CRS recognize the following IF mismatch is Tech Specs/actions apply: observed, then must 2.C(1) Maximum Power Level restore recirc loop flow 3.4.1.3 Recirculation Loop mismatch within two Flow hours or declare the A(B) loop inoperable.
PCIG Leak:
Crew recognizes PCIG leak by: With no operator action, After the Crew has taken GRIDS A3460 "PCIG PCIG receiver actions for the runaway RECEIVER AT201 PRESS" pressures will reach 50 Recirculation Pump, and at the lowering psig in about 10 discretion of the Lead GRIDS A3461 "PCIG minutes. Examiner, TRIGGER ET-1 ' RECEIVER BT201 PRESS" (PCIG Leak on Supply Line to lowering Torus). OHA A 1-A3 "INST GAS RECEIVER A PRESSURE LO" OHA A1-A4 "INST GAS RECEIVER B PRESSURE LO" :* GRIDS D4480 "INSTRUMENT GAS PNL AC213 ALARM" GRIDS D4481 "PCIG RECEIVER AT201 PRESSURE" GRIDS D4482 INSTRUMENT GAS PANEL BC213" GRIDS D4483 "PCIG RECEIVER BT201 PRESSURE" Both PCIG compressors running Insight Items:
CRS implements AB.COMP-002:
'A' PCIG Receiver press Condition A iapigrca * 'B' PCIG Receiver press iapigrcb ESG-2016 NRC-3 Page 8 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments
Crew announces lowering PCIG pressure on plant page.
RO/PO closes: => HV-5156A => HV-51568
Crew recognizes leak isolated by rising PCIG receiver pressures.
IF dispatched as Site
Crew dispatches Site Protection Protection to check 02 levels, to conduct 02 samples in THEN REPORT all samples Reactor Building.
are normal. !E dispatched to look for PCIG
Crew dispatches RBEO and leak, Maintenance to investigate loss THEN REPORT no evidence of of PCIG. leak in PCIG rooms. You will begin walking down the lines I isolated by the 5156A/B. IF directed to reset local panel alarms, THEN TOGGLE Remote AN-01A and AN-018 to NORMAL. REPORT alarm was "Low Low Pressure".
,, Loss of 10A110 Bus:
Crew recognizes:
After the Crew takes actions for => Reactor power lowering the PCIG Leak, => Reactor level swell OR at the discretion of the Lead Examiner, TRIGGER ET-2.
Crew monitors Reactor power, pressure, and level until plant conditions are stable.
PO ensures Feedwater restores and maintains RPV level between L VL 4 and L VL 7. ESG-2016 NRC-3 Page 9 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments
Crew recognizes trip of 'A' Recirc pump by: => OHA C1-D4 "REACTOR RECIRC A TROUBLE" => OHA B3-F2 CROSSFLOW ALARM/TRBL
=> 1 OC651 C pump d/p and flow indications
=> Flashing Reactor Recirculation PUMP A MOTOR GENERATOR TRIP light
RO ensures at least one Reactor Recirc pump remains running. *Only if INST AIR HOR PRESS
Crew recognizes loss of 10K107 reaches the LO Pressure by: alarm. ' OHA A2-B2 "COMPRESSED
=> AIR PANEL OOC188" => 10K107 CPRSR MOT OVLD/PWR FAIL light => *OHA A2-A1/A2 "INST AIR HEADER A/B PRESS LO" => *GRIDS 04601 "INSTR AIR SPL Y HOR A PRESS LO" ,, => *GRIDS 04602 "INSTR AIR SPL Y HOR B PRESS" LO => Lowering Service and Instrument Air pressures
PO places OOK107 in service Immediate Operator IAW AB.ZZ-0001 Attachment
7. Action IAW AB.COMP-0001.
CRS enters AB.COMP-0001 and May enter Condition A, verifies immediate operator but success path actions complete.
remains starting of OOK107.
Crew recognizes trip of AP102 The trips of AP102 and PCP and AP137 SCP by: AP137 are silent and => OVLD/PWR FAIL lights may not be immediately
=> STOP lights lit recognized by the => Motor amps zero Crew. ESG-2016 NRC-3 Page 10 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments
Crew validates automatic actions: => Feedwater PCP Speed Limiter on => Feedwater SCP Speed Limiter on => Recirc pump Intermediate Run back
Crew recognizes loss of AK111 The trip of AK111 is TB chiller by: silent and may not be => Solid OVLD/PWR FAIL lights immediately recognized
=> STOP lights lit by the Crew. => Motor amps zero
Crew recognizes loss of 1OA110 bus from: => OHA E3-E1 7.2 KV S.YS INCOMING BRKR MALF => OVLD/PWR FAIL lights on loads lost => Flashing TRIP light for infeed bkr52-11001
=> CRIDS D3677 "SWGR BUS A110 DIFF LOCKOUT" => CRIDS D3679 "SWGR BUS A110 UNDERVOL TAGE" => GRIDS D5447 "SWGR BUS A 110 OVERCURRENT LKOUT"
Crew announces loss of 1OA110 The order of the AOP on the plant page. implementation may vary.
Crew recognizes entry into the OPRM Enable Region by: => OHA C3-F1 "OPRM TRIP ENABLED" => GRIDS D5941-5948 "OPRM TRIP ENABLED" ESG-2016 NRC-3 Page 11 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity I Expected Plant/Student Response Comments IF directed to monitor/control
CRS implements AB.RPV-0003:
Rx Power ::::::56%
recirc MG oil temps, Condition B Core Flow ::::::43 Mlbm/hr THEN INSERT CW15 and Condition A on recorder CW16 and MONITOR: Core Flow ::::::44 Mlbm/hr
rrtoila(1) for 'A' MG by adding JP loop flows
rrtoila(2) for 'B' MG The pace of the scenario will not allow the Crew to fully address single loop requirements.
lE the Crew manually scrams,
IF in Region 1 of the Pwr/Flow THEN the Loss of Feedwater map, and LOCA will be automatically THEN RO inserts rods IAW ESG inserted.
guidance as necessary to exit Region 1.
RO/PO close HV-F031A Recirc pump discharge valve for 5 minutes, then re-open.
RO/PO implements DL.ZZ-0026 Att. 3v.
CRS implements AB.RPV-0001: Condition B
CRS implements AB.RPV-0004:
May not enter if RPV Condition D level alarms not Condition G reached.
PO closes HV-1680A PCP discharge valve.
PO closes HV-1651A SCP discharge valve.
PO bypasses Feedwater Run backs.
CRS references AB.CONT-0001:
Due to pace of scenario Condition A and relatively small Condition E effect of AK 111 loss on drywell pressure, may NOT enter at this time. ESG-2016 NRC-3 Page 12 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity I Expected Plant/Student Response Comments WHEN dispatched,
Crew dispatches TBEO and THEN REPORT the 10A110 Maintenance to investigate loss Bus Differential Overcurrent of 10A110 bus. Relays are tripped. There is no visible indication of damage to the bus.
CRS recognize the following actions apply: => Recirculation Loops 3.4.1 .1 action a 4.4.1.1.1
=> Reactor Coolant System Specific Activity TIS Table 4.4.5-1 Item 4(b) => ODCM Table 4.11.2.1.2-1 Items (c) & (f)
CRS notifies Shift Rad Pro and Shift Chem Tech to take samples IAW: => TIS Table 4.4.5-1 Item 4(b) => ODCM Table 4.11.2.1.2-1 Items (c) & (f)
CRS implements IO.ZZ-0006 . IF asked as RE,
Crew contacts RE for guidance . THEN REPORT that inserting the first 12 steps of the CRAM rods can be used to achieve an 80% rod line. ACKNOWLEDGE any direction to evaluate single loop operation IAW SE-PR.ZZ-0003.
ESG-2016 NRC-3 Page 13 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments
Crew contacts ESOC and Trading Floor, gives estimate of MWe output limitations and duration of limitation.
Loss of Feedwater I ATWS:
Crew recognizes loss of 20 minutes after the Loss of Feedwater by: 10A110 bus, => OHA A6-F2 "CONDENSATE OR TRAIN B TROUBLE I at the discretion of the Lead => OHA A6-F3 "CONDENSATE Examiner, TRAIN C TROUBLE TRIGGER ET-3. => OHA B3-E1 "RFP TURBINE TRIP" => Flashing SCP TRIP lights => RFPT Governor Valve I Positions
=> Feed flow indications
=> Lowering RPV level
RO locks the Mode Switch in SHUTDOWN when RPV level drops to 15" IAW AB.RPV-0004 Retainment Override. (May scram earlier if the loss of RFPT's is recognized.}
Crew recognizes Scram Condition and Reactor Power Above 4% EOP entry condition.
ESG-2016 NRC-3 Page 14 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL
RO performs scram actions IAW The Mode Switch will TRANSIENT MITIGATION AB .ZZ-0001 Att. 1 . not actuate A1/A2 RPS, Reactor Scram Reports but the Arm & Depress Following a Reactor scram, the NCO should make an initial scram Pushbuttons will. report by announcing reactor ARI will not status IAW HC.OP-AB.ZZ-0001.
automatically initiate, Crew personnel should hold all but can be manually other non-essential initiated.
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.
Before Reactor Water Level RECORD the RPV level reaches L VL 1, the Crew at which RPS or ARI is manually actuates RPS and/or actuated.
,, ARI to shutdown the reactor. RPV Level:
Crew recognizes RPV LVL 3 RPS A1/A2 will not EOP entry condition:
actuate on ANY =:> OHA C5-A4 "RPVWATER automatic scram LEVEL LO" signals. =:> OHA A7-D5 "RPV LEVEL 3" =:> Various water level indicators
CRS enters EOP-101A.
AFTER the reactor is verified to be shutdown, THEN CRS exits EOP-101 A, implements EOP-101. ESG-2016 NRC-3 Page 15 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response I Comments I STRATEGIES FOR SUCESSFUL
Crew recognizes RPV L VL 2 by: TRANSIENT MITIGATION OHA A7-E5 "RPV LEVEL 2" EOP 101 RPV Control. => Level Leg => OHA C8-C3 "NSSSS ISLN SIG -RPV LEVEL LO" Direct an initial band of +12.5" to +54" OHA C1-D3 "REACTOR Rx level. This gives a manageable
=> band with level control still in the RECIRC PUMPS TRIP" indicating range. If controlling
=> OHA E3-E3 "USS FEEDER Reactor Pressure with SRVs and the BRKRTRBL" 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.
PO verifies HPCl/RCIC initiation . HPCI will NOT initiate until the reactor is scrammed.
LOCA with Tri12 of HPCI:
PO recognizes trip of HPCI by: After HPCI recovers RPV water => OHA B1-A4 "HPCI TURBINE level to -50", ENSURE ET-4 TRIP" triggers to insert the LOCA with => OHA B1-B5 "HPCI OUT OF trip of HPCI, SERVICE" OR, => OHA B1-C4 "HPCI TURBINE at the discretion of the Lead TROUBLE" Examiner, => OHA B1-E5 "HPCI PUMP TRIGGER ET-4 manually.
DISCHARGE FLOW LO" (The LOCA will start two => HPCI Stop Valve & Control minutes after HPCI trips) Valve failure to open => HPCI speed and flow indications
PO informs CRS of HPCI trip . ESG-2016 NRC-3 Page 16 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF dispatched to investigate
Crew dispatches ABEO and HPCI trip units, Maintenance to investigate trip of THEN REPORT: HPCI.
E41-N656E Turb Exhaust Pressure is reading upscale with trip and gross fail lights lit.
E41-N656A Turb Exhaust Pressure is reading 0 IF dispatched to 'C' PCP,
Crew may dispatch TBEO and THEN REPORT the 51A and Maintenance to investigate trip of 51 C Time Overcurrent relays 'C' PCP. are tripped on the breaker (52-10208) and the motor is hot to the touch. IF dispatched to 'B/C' SCP's, THEN REPORT there are no apparent problems with the pumps or their breakers.
Crew recognizes LOCA condition:
=> OHA C6-B 1 "OLD SYSTEM ALARM/TRBL" => RM11 9AX314 OLD FLOOR ,, ORN FLOW alarm => RM 11 9AX317 /318/320 OLD CCM alarms => OHA D3-C3 "DRYWELL SUMP LEVEL HI/LO" => OHA A4-F5 "COMPUTER PT IN ALARM" => OHA A 7-E4 "DRYWELL PRESSURE HI/LO" => Rising Drywell Pressure on various indicators
CRS references AB.CONT-0006
CRS references AB.CONT-0001
=> Condition A
RO/PO ensures drywell cooling is maximized.
ESG-2016 NRC-3 Page 17 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE I Event / Instructor Activity I Expected Plant/Student Response Comments
Crew checks =:> Recirc pump seal parameters
=:> SRV temperatures
Crew recognizes High Drywell Pressure EOP entry condition:
=:> OHA A7-D4 "DRYWELL PRESSURE HI/HI" =:> OHA C5-B5 "DRYWELL PRESSURE HI" =:> Various system initiations and isolations.
CRS implements EOP-102, re-enters EOP-101.
RO/PO verifies automatic actions. I Failure of 'A' Channel
Crew recognizes failure of the A PCIS LOCA L VL 2 Initiations:
Core Spray logics to initiate by: initiations WILL occur. The failure of 'A' Core Spray =:> A INIT AND SEALED IN light and RHR logics to auto initiate extinguished is already inserted.
=:> Pump STOPPED indication
=:> A channel breaker status on 1 OC650E NON CLASS 1 E LOAD ISLN CIRCUIT BREAKER STATUS AND CONTROL =:> A EDGs not running =:> Various valve failures to isolate
RO/PO manually initiates Core Spray 'A' logic.
Crew recognizes failure of the 'A' RHR logic to initiate by: =:> A INIT AND SEALED IN light extinguished
=:> Pump STOPPED indication
RO/PO manually initiates
'A' RHR logic.
RO/PO trips 'B' recirc pump if not already tripped by RPV Level 2. ESG-2016 NRC-3 Page 18 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments
CRS directs restoring PCIG to SRVs and Rx Bldg to Torus Vac Bkrs.
RO/PO restores PCIG to SRVs and Rx Bldg to Torus Vac Bkrs IAW AB.ZZ-0001 Att. 9. * !Ethe Crew attempts to reduce pressure with the bypass valves, THEN Crew recognizes the bypass valves fail shut at 750# by: => OHA E1-F4 "COMPUTER PT RETURN TO NORMAL" => OHA D3-D5 "EHC UNIT PANEL 1 OC363" => Bypass valve indication BPV Positioning Error alarms ' => IF directed to align for two CRD
CRS orders injection with two CRD pumps will trip on pump injection, CRD pumps. low suction pressure THEN PERFORM the
CRS orders injection with SLC due to suction filter following:
pumps. clogging.
REFER to SO.BF-0001 Sect
WHEN RPV water level drops 5.4. to -129", TRIGGER ET-5 (Suction filter). THEN the Crew inhibits ADS. SET Remote Function for Stby CRD pump discharge valve to 0% (CD01/CD02).
REPORT Stby CRD pump ready for start. WHEN Stby CRD is running, THEN RAMP discharge valve to 100% open. Due to suction filter clogging, the CRD pumps will trip before the remainder of the lineup can be completed.
ESG-2016 NRC-3 Page 19 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event/ Instructor Activity Expected Plant/Student Response Comments
WHEN the Crew determines RECORD compensated RPV water level cannot be RPV water level when maintained above -185", the Crew determines THEN the CRS implements EOP that Emergency 202. Depressurization is
Crew determines that required.
Emergency Depressurization is required before LEVEL: compensated RPV water level reaches -185"; AND subsequently restores and maintains RPV water level to above -161 ". STRATEGIES FOR SUCESSFUL
WHEN directed, TRANSIENT MITIGATION THEN RO/PO open five ADS Emergency Depressurization Level Response And Control SRVs IAW AB.ZZ-0001 Att. 13. The Control Room Supervisor should I 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.
RO/PO restore RPV level IAW IF the 'A' Core Spray AB.ZZ-0001:
logic was NOT .Att. 4 for RHR manually initiated, Att. 5 for Core Spray THEN the 'A' Core Spray loop will need to be manually aligned for injection during the blowdown.
ESG-2016 NRC-3 Page 20 of 28 Rev.: 1 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE I Event / Instructor Activity J Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL
AFTER adequate core cooling is TRANSIENT MITIGATION restored, Emergency Depressurization THEN CRS directs placing RHR Level Response And Control For non-ATWS emergency in Suppression Pool Cooling and depressurizations, the Control Room Spray. Supervisor should establish and maintain an RPV level band between -38" to +54" on Wide Range indication.
This transient level band will prevent adverse hydraulic effects caused by high outside shroud reactor level while maintaining adequate core submergence based on Fuel Zone indication.
Following the emergency depressurization, level will be restored and maintained to the preferred EOP reactor level band by using a suggested Wide Range compensated level band of +12.5" to +54" if possible using I Condensate and Startup Level Control or the Control Room Supervisor can maintain an RPV level band of -38" to +54" if still batch feeding with low pressure ECCS to maintain RPV level.
RO/PO place RHR in Suppression Pool Cooling and Spray as directed by CRS IAW AB.ZZ-0001 Attachment
3.
AFTER adequate core cooling is restored, THEN CRS directs placing one loop of RHR in Drywell Spray. Termination Reguirement:
RO/PO place RHR in Drywell The HV-F021 B will The scenario may be Spray as directed by CRS IAW NOT open. terminated at the discretion of AB.ZZ-0001 Attachment
2. The 'A' RHR pump the Lead Examiner when the CANNOT be placed in RPV has been depressurized drywell spray UNLESS and level is being maintained the 'A' RHR logic has above -129". been manually initiated.
ESG-2016 NRC-3 Page 21 of 28 Rev.: 1

v t e Letter Sequence Other
TAC:U01925, (Open)
Initiation Acceptance Administration Questions Answers Results Approval... Other: ML16295A055, ML16295A057, ML17186A121, ML17186A145
MONTHYEAR2016-10-11 [Table View]

ML16295A057

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