ML14119A392

From kanterella
Jump to navigation Jump to search

Final Operating Exam (Sections a, B, and C) (Folder 3)
ML14119A392
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/31/2014
From: Hooper G
Entergy Corp
To: David Silk
Operations Branch I
Jackson D
Shared Package
ML13330B159 List:
References
TAC U01887
Download: ML14119A392 (243)
v • d • e


Text

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

...,.\ S/RO 14-1 NRC S/RO TASK TITLE: Core Thermal Heat Balance Verification Using C001 Turbine Steam Pressure APPL. TO JPM NUMBER REV: DATE:---- NRC KIA SYSTEM NUMBER: 2.1.19 {3.9/3.8)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 12/20 Minutes j/ L SUBMITTED: -~.....-:z::::-:_...::;...__.fl"--:b:=~-t:~-- OPERATIONS REVIEW: -1{\ p(<<il(/~

APPROVED:

~

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom TIME TO COMPLETE:

  • "'f?ATE PERFORMED:

- - - Minutes

~hERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC S/RO TASK TITLE: Core Thermal Heat Balance Verification Using C001 Turbine Steam Pressure APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required cgj None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC S/RO TASK TITLE: Core Thermal Heat Balance Verification Using C001 Turbine Steam Pressure APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-65, Startup and Shutdown Procedure B. RAP-7.3.03, Core Thermal Power Evaluation Ill. TOOLS AND EQUIPMENT A. Calculator B. Steam Tables IV. SET UP REQUIREMENTS A. Provide a copy of RAP-7.3.03 ready to perform section 9.3 and Attachment 2.

B. Obtain a 30 Monicore Power-Flow report at approximately 100% power.

C. Obtain an EPIC screen shot for point 1299 at approximately 712 psig.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. A plant startup has just been completed.

B. Verification of Core Thermal Power is required.

C. The required plant data is given in the provided handouts.

-3 of 10-

SIRO 14-1 NRC SIRO C001 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "Verify Core Thermal Power per RAP-7.3.03 Section 9.3."

EVALUATION I STEP STANDARD COMMENT

1. Obtain and review procedure. Candidate obtains and reviews RAP- SAT I UNSAT 7.3.03. Candidate determines that the start point is step 9.3.

EVALUATOR:

Hand candidate a copy of RAP-7 .3.03 ready to perform Section 9.3 and Attachment 2. Provide the EPIC screenshot and 3D Monicore case.

  • 2. Obtain and record Turbine first stage Obtains a value of -711.8 psig for CRITICAL STEP pressure from EPIC 1299. EPIC point 1299 and records on SAT I UNSAT Attachment 2.
  • 3. Calculate and record Reactor power Calculates -106% power and CRITICAL STEP calculated from Turbine first stage records on Attachment 2. SAT I UNSAT pressure.
  • 4. Obtain and record Reactor power Obtains a value of -99.9% for CRITICAL STEP calculated from heat balance. Reactor power and records on SAT I UNSAT Attachment 2.
  • 5. Determine if the two methods are Determines the two methods differ CRITICAL STEP within 5% of rated power of each by more than 5%. SAT I UNSAT other.
  • 6. Determine need to initiate Indicates that an investigation must CRITICAL STEP investigation. be initiated. SAT I UNSAT NOTE: This step may be satisfied by direct report, notification to Shift Manager, notification to Reactor Engineering, initiating a Condition I Report, or similar.

-4 of 10-

S/RO 14-1 NRC S/RO C001 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure I

EVALUATION I STEP STANDARD COMMENT

7. Determine need to notify General Indicates that the General Manager SAT/UNSAT Manager Plant Operations. Plant Operations must be notified if the difference cannot be explained.

NOTE: This step may be satisfied by direct report, notification to Shift Manager, notification to Reactor Engineering, initiating a Condition Report, or similar.

EVALUATOR: Terminate the task at this point for RO candidates. For SRO candidates, provide the additional SRO Only Conditions and Cue, along with the SRO Only Worksheet.

Additional SRO Only Conditions:

Investigation has revealed the following:

  • The 30 Monicore Core Thermal Power calculation is erroneous .
  • Turbine first stage bowl pressure accurately reflects plant power level.
  • Operation at the current power level has been ongoing for three hours .

Additional SRO Only Cue:

Complete the provided SRO Only Worksheet regarding requirements associated with the Licensed Power Level.

I

-5 of 10-

SIRO 14-1 NRC SIRO C001 TASK TITLE: Core Thermal Heat Balance Verification Using Turbine Steam Pressure I

EVALUATION I STEP STANDARD COMMENT

  • 8. SROONLY SROONLY CRITICAL STEP Determine requirements for 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Determines requirement for 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> SAT I UNSAT thermal power average thermal power average is:
  • If the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds RTP, take timely action to ensure that thermal power is less than or equal to RTP (or similar).
  • 9. SROONLY SROONLY CRITICAL STEP Determine requirement for average Determines requirement for average SAT I UNSAT Reactor power level for each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Reactor power level for each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift shift is:
  • The average reactor power level for each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift shall not exceed Rated Thermal Power (or similar).
  • 10. SROONLY SRO ONLY CRITICAL STEP Determine the procedure that Determines RAP-7.3.16 contains the SAT I UNSAT contains the specific guidance on specific guidance on both 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and both 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thermal 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thermal power averages.

power averages.

EVALUATOR: Terminate the task at this point for SRO candidates.

Task Standard: Core thermal heat balance determined to be out of tolerance in relation to Turbine steam pressure. For SRO candidates, procedural requirements of RAP-7 .3.16, Plant Power Changes, for control of core thermal power determined.

-6 of 10-

SRO Only Key

1. Describe the specific requirement(s) regarding 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thermal power average, in accordance with plant procedure.

If the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds RTP, take timely action to ensure that thermal power is less than or equal to RTP (or similar).

2. Describe the specific requirement(s) regarding the average Reactor power level for each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, in accordance with plant procedure.

The average reactor power level for each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift shall not exceed Rated Thermal Power (or similar).

3. Identify the plant procedure that contains the specific guidance on both of the questions above.

RAP-7.3.16 SRO Only Key

-7 of 10-

HANDOUT

  • A plant startup has just been completed.
  • Verification of Core Thermal Power is required.

Verify Core Thermal Power per RAP-7.3.03 Section 9.3.

-8 of 10-

ADDITIONAL SRO ONLY HANDOUT Investigation has revealed the following:

  • The 30 Monicore Core Thermal Power calculation is erroneous.
  • Turbine first stage bowl pressure accurately reflects plant power level.
  • Operation at the current power level has been ongoing for three hours.

Complete the provided SRO Only Worksheet regarding requirements associated with the Licensed Power Level.

-9 of 10-

SRO Only Worksheet

1. Describe the specific requirement(s) regarding 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thermal power average, in accordance with plant procedure.
2. Describe the specific requirement(s) regarding the average Reactor power level for each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, in accordance with plant procedure.
3. Identify the plant procedure that contains the specific guidance on both of the questions above.

-10 of 10-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

""\ RO 14-1 NRC RO TASK TITLE: Perform RHR Lineup Verification Per ST-2AN C002 APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: _..;;2~.1~.3;;...1;_:(~._;..4;_.:;..6'-)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes ~

SUBMITTED: .z=-:,a. :7< _,---- OPERATIONS REVIEW: /1i_, (~

APPROVED:

~~

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Simulator DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes

~ERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 8-

ENTERGYNUCLEARNORTHEAST JOB PERFORMANCE MEASURE RO 14-1 NRC RO TASK TITLE: Perform RHR Lineup Verification Per ST-2AN C002 APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 8-

ENTERGYNUCLEARNORTHEAST JOB PERFORMANCE MEASURE RO 14-1 NRC RO TASK TITLE: Perform RHR Lineup Verification Per ST-2AN C002 APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ST-2AN, RHR Loop A Monthly Operability Test Ill. TOOLS AND EQUIPMENT

  • None IV. SET UP REQUIREMENTS A. Provide a copy of ST-2AN completed up to step 8.1.

B. Reset the simulator to an IC (IC-68) with RHR in a normal standby lineup, except for the following:

a. 10MOV-16A, MIN FLOWVLV, is closed.
b. 1OMOV-66A, HX A BYP VLV, is closed.
c. 10MOV-57, RHR DISCH TO RADW, is open.
d. 10MOV-18, SHUTDOWN CLG SUCT, is open.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

D. Should Candidate inform CRS that ST cannot be continued due to the out of position valve or out of spec readings, etc ... , inform Candidate the deviation has been noted and for them to continue with the ST.

VI. TASK CONDITIONS A. ST-2AN, RHR Loop A Monthly Operability Test, is in progress.

B. Other operators have prepared ST-2AN up to Section 8.1.

C. RHR Loop A level switches are operable.

VII. INITIATING CUE Inform the candidate, "Complete ST-2AN Sections 8.1 and 8.2."

-3 of 8-

RO 14-1 NRC RO C002 TASK TITLE: Perform RHR Lineup Verification

  • - CRITICAL STEP EVALUATION I STEP STANDARD COMMENT
1. IF 10LS-100 (RHR loop A Contacts Operator in Relay Room to SAT I UNSAT containment spray line level switch) verify lights for 1OLS-1 00 and 1OLS-and 10LS-101 (RHR loop' A LPCI 101 are OFF on alarm module 10-keep-full level switch) are operable, 74-1-44 inside panel AR-8 THEN perform the following:

EVALUTOR ROLE PLAY:

Verify RHR Loop A keep-full level Inform the Candidate that the lights switch alarms are clear by one of the for 10LS-100 and 10LS-101 are following methods: OFF.

  • Verify lights for 10LS-100 and -OR-10LS-101 are off on alarm module 10-74-1-44 inside panel AR-8 in relay room Utilizes any EPIC station and verifies points EPIC-D-129 and EPIC-D-130
  • Verify associated EPIC points indicate NORMAL (EPIC-D-129 and EPIC-D-130) indicate NORMAL
2. Mark Steps 8.1.2 through 8.1.1 0 NIA Marks Steps 8.1.2 through 8.1.1 0 SAT I UNSAT NIA
  • 3. IF RHR Loop A is in standby LPCI Verifies the following lineup at panel CRITICAL STEP lineup per OP-13, Section E, THEN 09-3 and documents in ST -2AN: (bolded items only) perform the following: SAT I UNSAT Verify the following lineup at panel 09-3:

-4 of 8-

RO 14-1 NRC RO C002 TASK TITLE: Perform RHR Lineup Verification r STEP STANDARD EVALUATION I COMMENT

3. Verify the following lineup at panel Verifies the following lineup at panel CRITICAL STEP (cont.) 09-3 (cont.): 09-3 and documents in ST-2AN (bolded items only)

(cont.): SAT I UNSAT

-Closed

-Closed

  • MIN FLOWVLV 10MOV-16A-Open * *MIN FLOWVLV 10MOV-16A-Closed EVALUATOR NOTE: The bolded items in this step are improperly aligned. Should the Candidate inform the CRS that the ST cannot be continued due to the improperly aligned item, inform the Candidate the deviation has been noted, continue with the ST, and the deviation will be corrected by another Operator later.
  • OW SPRAY OUTBO VLV
  • OW SPRAY INBO VLV 10MOV-

-Open

-Open

  • RHR TEST TORUS CLG &
  • RHR TEST TORUS CLG &

SPRAY 1OMOV-39A- Closed SPRAY 1OMOV-39A- Closed

  • TORUS SPRAY INBO VLV

-5 of 8-

RO 14-1 NRC RO C002 TASK TITLE p e rform RHRL"meup ven"fi1caf1on I STEP STANDARD EVALUATION I COMMENT

3. Verify the following lineup at panel Verifies the following lineup at panel CRITICAL STEP (cont.) 09-3 (cont.): 09-3 and documents in ST-2AN (bolded items only)

(cont.): SAT I UNSAT

-Closed

-Closed

-Open

-Open

-Open

-Open

-Closed

-Closed

  • RHR DISCH TO RADW 1OMOV Closed
  • RHR DISCH TO RADW 10MOV Closed
  • SHUTDOWN CLG SUCT 10MOV Closed
  • SHUTDOWN CLG SUCT 10MOV Closed l

-6 of 8-

RO 14-1 NRC RO C002 TASKTIT L E p e rform RHRL"meup vefl"fi1cat1on I EVALUATION I STEP STANDARD COMMENT

  • 4. Verify the following lineup at panel Verifies the following lineup at panel CRITICAL STEP 09-4: 09-4 and documents in ST-2AN {bolded items only)

(cont.): SAT I UNSAT

  • RHR DISCH TO RADW 1OMOV Closed * *RHR DISCH TO RADW 1OMOV Open
  • SHUTDOWN CLG SUCT 10MOV Closed * *SHUTDOWN CLG SUCT 10MOV Open EVALUATOR NOTE: The bolded items above are improperly aligned.

Should the Candidate inform the CRS that the ST cannot be continued due to the improperly aligned item, inform the Candidate the deviation has been noted, continue with the ST, and the deviation will be corrected by another Operator later.

EVALUATOR: Terminate the task at this point.

Task Standard: RHR lineup verification performed. Improper lineup of minimum flow valve, heat exchanger bypass valve, discharge valve to Radwaste, and shutdown cooling isolation valve identified.

-7 of 8-

HANDOUT

  • ST-2AN, RHR Loop A Monthly Operability Test, is in progress.
  • Other operators have prepared ST-2AN up to Section 8.1.

Complete ST-2AN Sections 8.1 and 8.2.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO TASK TITLE: Determine Reportability Requirements- Scram C002 With HPCI and RCIC Injection APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: .....;;2~.1..;..;.*...;..;18;;_(=3.;..;;.8.~.--)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 25 Minutes !7 ~

SUBMITTED: .-=--"" --=? __...,_ OPERATIONS REVIEW: t1& ~~

APPROVED: __ £~~=--.~--------

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes

~:.PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO TASK TITLE: Determine Reportability Requirements- Scram C002 With HPCI and RCIC Injection APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO TASK TITLE: Determine Reportability Requirements- Scram C002 With HPCI and RCIC Injection APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. 10 CFR 50.72 B. NUREG 1022 C. EN-LI-108 Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant was operating at 100% power with no equipment out of service.

B. A failure of the Feedwater Level Control System has occurred.

C. The plant was manually scrammed in anticipation of an automatic Reactor scram.

D. Reactor water level reached a low of 120 inches during the transient.

E. All systems operated as designed.

F. HPCI did NOT inject into the Reactor because Reactor water level was recovered per EOP-2 using Feedwater.

G. Reactor water level has been restored to the normal band.

-3 of 8-

SRO/RO 14-1 NRC SRO C002 TASK TITLE: Determine Reportability Requirements- Scram With HPCI and RCIC Injection

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate of the following:

"List ALL the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category. Record your findings on the sheet provided."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a applicable reference Obtains a copy of applicable reference documents: SAT I UNSAT documents
  • EN-LI-108 EVALUATOR: Ensure sufficient copies of these documents are available.
2. Locate and identify applicability of 10 Determines no emergency classification is required SAT I UNSAT CFR 50.72(a)(1)

EVALUATOR NOTE: This step may be evaluated by the absence of a one hour emergency report.

  • 3. Locate and identify applicability of 10 Identifies reportability per 10 CFR 50.72(b)(2)(iv)(B), for CRITICAL STEP CFR 50.72(b)(2)(iv)(B) a valid RPS actuation while the Reactor is critical SAT/UNSAT
  • 4. Determine notification time requirement Determines 10 CFR 50.72(b)(2)(iv)(B) requires CRITICAL STEP for 10 CFR 50.72(b)(2)(iv)(B) notification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SAT/UNSAT

-4 of 8-

SROIRO 14-1 NRC SRO C002 TASK TITLE: Determine Reportability Requirements- Scram With HPCI and RCIC Injection STEP STANDARD EVALUATION I COMMENT

  • 5. Locate and identify applicability of 10 Identifies reportability per 10 CFR 50. 72(b)(3)(iv)(A), for CRITICAL STEP CFR 50. 72(b)(3)(iv)(A) a valid actuation of HPCI, RCIC, and containment SAT I UNSAT isolation I EVALUATOR NOTE: Candidate may alternately refer to 10CFR 50.72(b)(3)(iv)(B){2, 4, and 5) for this reportability requirement.
  • 6. Determine notification time requirement Determines 10 CFR 50. 72(b)(3)(iv)(A) requires CRITICAL STEP for 10 CFR 50.72(b)(3)(iv)(A) notification within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> SAT I UNSAT EVALUATOR NOTE: Candidate may alternately refer to 10CFR 50. 72(b)(3)(iv)(8)(2, 4, and 5) for this reportability requirement.

EVALUATOR NOTE: Candidate may report that the these notifications are due within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to coincide with the RPS actuation notification. This satisfies the requirement for notification within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

EVALUATOR: Terminate the task at this point.

Task Standard: NRC reportability requirements and associated time limits are determined.

-5 of 8-

HANDOUT

  • The plant was operating at 100% power with no equipment out of service.
  • A failure of the Feedwater Level Control System has occurred.
  • The plant was manually scrammed in anticipation of an automatic Reactor scram.
  • Reactor water level reached a low of 120 inches during the transient.
  • All systems operated as designed.
  • HPCI did NOT inject into the Reactor because Reactor water level was recovered per EOP-2 using Feedwater.
  • Reactor water level has been restored to the normal band.

List ALL the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category. Record your findings on the sheet provided.

-6 of 8-

Attachment 1 EVALUATOR'S KEY Identify ALL the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit 10 CFR 50. 72(b)(2)(iv)(B) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Valid Reactor Protection System (RPS) actuation while the Reactor is critical 10 CFR 50.72(b)(3)(iv)(A) Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) (HPCI, RCIC, isolations)

Note: Candidate may alternately refer to 10CFR Note: Candidate may report

50. 72(b)(3)(iv)(B)(2), 50. 72(b)(3)(iv)(B)(4}, that this notification is and 50.72(b)(3)(iv)(B)(5) for this due within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reportability requirement. coincide with the RPS actuation notification.

This satisfies the requirement for notification within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

EVALUATOR'S KEY

-7 of 8-

Attachment 2 JPM Scorecard for Candidate Use Identify ALL the applicable 10 CFR 50.72 reportability requirements, the reason that they apply, and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

"'** S/RO 14-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.2.41 (3.5/3.9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15/25 Minutes ~*

/( 1~

SUBMITTED: OPERATIONS REVIEW: It LA }c;2 ULt~

~~~~~\-----

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.2.41 (3.5/3.9)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15/25 Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review 0 Additional Information 0 Questions and Answers 0 Validation 0 Procedural Change Required [gl None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. Electrical Print 1.67-99 (GE 791 E456 Sheet 9)

B. Electrical Print 1.67-101 (GE 791E456 Sheet 11)

C. Technical Specification 3.3.1.1 Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. Preparations are underway to perform ST-29A, Manual Scram Functional Test.

-3 of 9-

SRO/RO 14-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate of the following:

"Using the provided station electrical prints, explain how depressing the MANUAL SCRAM A pushbutton on panel 09-5 results in an RPS half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action."

For SRO candidates, also provide the following:

"Additionally, explain the Technical Specification impact if the MANUAL SCRAM A pushbutton becomes inoperable with the plant operating at 100%

power. Include the Technical Specification impact if the Required Action is not completed within the required completion time."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of applicable Obtains a controlled copy of applicable electrical prints: SAT I UNSAT electrical prints.
  • 1.67-99 (GE 791E456 Sheet 9)
  • 1.67-101 (GE 791 E456 Sheet 11)

EVALUATOR: Provide working copy of identified prints.

  • 2. Identifies MANUAL SCRAM A Identifies MANUAL SCRAM A pushbutton (5A-S3A) on CRITICAL STEP pushbutton on electrical print 1. 67-99. electrical print 1.67-99 (near location E-1 0). SAT/UNSAT EVALUATOR NOTE: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

-4 of 9-

SROIRO 14-1 NRC SIRO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION I COMMENT

  • 3. Identifies relays 5A-K15A and 5A-K15C Identifies relays 5A-K15A and 5A-K15C on electrical CRITICAL STEP on electrical print 1.67-99. print 1.67-99 (near location F-10). SAT I UNSAT I

1 EVALUATOR NOTE: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

  • 4. Identifies contacts 5A-K 15A and SA- Identifies contacts 5A-K15A and 5A-K15C on electrical CRITICAL STEP K15C on electrical print 1.67-101. print 1.67-101 (1L-1T and 2L-2T, near locations B-3, 8- SAT I UNSAT 6, B-9, and B-11).

EVALUATOR NOTES:

  • This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
  • The candidate does not have to identify all four contacts on this sheet, as long as a representative sample is identified and some indication is given that there are multiple contacts.

-5 of 9-

SRO/RO 14-1 NRC S/RO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION I COMMENT

  • 5. Identifies relays 3-13-117 (or 03SOV- Identifies solenoids/relays 3-13-117 (or 03SOV-117) on CRITICAL STEP 117) on electrical print 1.67-101. electrical print 1.67-101 (near locations C-2/3, C-4, C-5, SAT I UNSAT C-6, C-8, C-9, C-11, and C-12).

I I I EVALUATOR NOTES:

  • This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
  • The candidate does not have to identify all eight solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays. I I
6. Describes how depressing the Describes the following: SAT I UNSAT I I

MANUAL SCRAM A pushbutton on I panel 09-5 results in an RPS half

I

causes contacts 5A-K 15A and 5A-K 15C to open.

  • Contacts 5A-K 15A and 5A-K 15C opening causes solenoid/relay 3-13-117 to de-energize at each HCU.

EVALUATOR NOTE: This is a summary of previous critical steps. The candidate does not have to match this description word-for-word, but must include all concepts in their description.

-6 of 9-

SROIRO 14-1 NRC SIRO EC TASK TITLE: Explain RPS Operation Using Electrical Drawings STEP STANDARD EVALUATION I COMMENT

  • 7. SRO Only SRO Only SRO Only Determines and reports the Technical Reports that Technical Specification Table 3. 3.1.1-1 Specification impact of MANUAL Function 11 is not met. CRITICAL STEP SCRAM A pushbutton inoperability SAT I UNSAT I Reports that Technical Specification 3.3.1.1 Condition C I

must be entered and requires restoring RPS trip capability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

EVALUATOR NOTE: The candidate may also identify the need to enter Technical Specification 3.3.1.1 Condition A, which requires initiating a trip I half scram within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This is not a critical part of this step since it is less restrictive than Condition C. RPS trip capability is not maintained for Function 11 with either one of the MANUAL SCRAM pushbuttons inoperable.

Reports that if the Required Action is not completed within the required completion time, then:

  • Technical Specification 3.3.1.1 Condition G requires being in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

EVALUATOR: Terminate the task at this point.

Task Standard: Operation of manual scram pushbutton explained using electrical prints, including identification of related electrical components.

For SRO candidates, Technical Specification 3.3.1.1 impact of inoperable manual scram pushbutton determined.

-7 of 9-

RO HANDOUT

  • The plant is operating at 100% power.

Using the provided station electrical prints, explain how depressing the MANUAL SCRAM A pushbutton on panel 09-5 results in an RPS half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

-8 of 9-

SRO HANDOUT

  • The plant is operating at 100% power.

Using the provided station electrical prints, explain how depressing the MANUAL SCRAM A pushbutton on panel 09-5 results in an RPS half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

Additionally, explain the Technical Specification impact if the MANUAL SCRAM A pushbutton becomes inoperable with the plant operating at 100% power.

Include the Technical Specification impact if the Required Action is not completed within the required completion time.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-1 NRC RO RC TASK TITLE: Determine Release Rates APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 2.3.11 (3.8)

~~---------

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 25 Minutes /,. .K-1--

SUBMITTED: --=~--P--'~+---~---- OPERATIONS REVIEW: /!{ /~

APPROVED: d-!?efr CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE:

- - - Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 14-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-1 NRC RO RC TASK TITLE: Determine Release Rates APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required r2J None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 14-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE RO 14-1 NRC RO RC TASK TITLE: Determine Release Rates APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ARPs for Panel 09-3-2 Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the references listed above are available for the number of candidates.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. A plant transient has resulted in fuel damage.

B. Radiation releases are occurring through Service Water and Off-gas.

C. Annunciator 09-3-2-27, OFF GAS RAD MON HI, has alarmed.

D. Annunciator 09-3-2-38, OFF GAS RAD MON HI-HI, has NOT alarmed.

E. Annunciator 09-3-2-30, LIQUID PROCESS RAD MONITOR HI-HI, has NOT alarmed.

F. Current indications for RBCLC, Service Water, and Off-gas radiation monitoring are provided in the attached pictures.

G. Chemistry has determined release rates I radiation levels for RBCLC, Service Water, and Off-gas as follows:

Chemistry Calculations RBCLC (800 -14) x 2.23 E-7 =4.21032 E-4 J.!Cilml Service Water (200- 4) x 2.67 E-7 =5.2866 E-5 J.!Ci/ml Off-gas (801- 4) x 88.85 =70813.45 J..tCi/sec H. Chem1stry Will determine 1f 10CFR, ODCM, Tech Spec, or TRM release rates are w1th1n limits.

-3 of 14-

RO 14-1 NRC RO RC TASK TITLE: Determine Release Rates

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate of the following:

"The CRS had directed you to:

  • Verify the Chemistry data entries and calculations for release rates I activity levels for:

o RBCLC (RM-352) o Service Water (RM-351) o Off-Gas (RM-150A/B)

  • Determine if, based upon the given radiation monitor indications, the status of annunciators 09-3-2-27, 09-3-2-30, and 09-3-2-38 are appropriate."

STEP STANDARD EVALUATION I COMMENT I

  • 1. Verify RBCLC activity. Calculates RBCLC activity to be approximately *1.66632 I CRITICAL STEP E-4 f.lCilml (acceptable range of 1.45644 E-4 to 1.8762 SAT I UNSAT E-4).

EVALUATOR NOTE: The Chemistry calculation utilized an incorrect K-factor. The correct calculation is (800 -

=

14) x 2.12 E-7 1.66632 E-4 f.lCilml. The acceptable range is based on a chart reading of 701 and 899.

-4 of 14-

RO 14-1 NRC RO RC TASK TITLE: Determine Release Rates STEP STANDARD EVALUATION I COMMENT

  • 2. Verify Service Water activity. Calculates Service Water activity to be approximately CRITICAL STEP 7.9032 E-5 j..LCilml (acceptable range of 6.5682 E-5 to SAT I UNSAT 9.2382 E-5).

I I EVALUATOR NOTE: The Chemistry calculation utilized an incorrect rad monitor reading. The correct calculation

=

is (300- 4) x 2.67 E-7 7.9032 E-5 j..LCilml. The acceptable range is based on a chart reading of 250 to 350.

  • 3. Verify Off-gas activity. Determines the Chemistry calculation for Off-gas activity CRITICAL STEP is accurate. SAT I UNSAT
4. Determine status of alarms. Determines that annunciator 09-3-2-27, OFF GAS RAD SAT I UNSAT MON HI, is operating properly.

Determines that annunciator 09-3-2-38, OFF GAS RAD MON HI-HI, is operating properly.

Determines that annunciator 09-3-2-30, LIQUID PROCESS RAD MONITOR HI-HI, should have alarmed when Service Water activity exceeded 200 cps.

EVALUATOR: Terminate the task at this point.

Task Standard: Release rates I activities are verified. Incorrect RBCLC and Service Water calculations are identified and correct values are calculated.

-5 of 14-

HANDOUT

  • A plant transient has resulted in fuel damage.
  • Radiation releases are occurring through Service Water and Off-gas.
  • Current indications for RBCLC, Service Water, and Off-gas radiation monitoring are provided in the attached pictures.
  • Chemistry has determined release rates I radiation levels for RBCLC, Service Water, and Off-gas as follows:

Chemistry Calculations RBCLC (800- 14) x 2.23 E-7 =4.21032 E-4 J.LCilml Service Water (200- 4) x 2.67 E-7 =5.2866 E-5 J.LCi/ml Off-gas (801 - 4) x 88.85 =70813.45 J.LCi/sec

  • Chemistry will determine if 10CFR, ODCM, Tech Spec, or TRM release rates are within limits.

-6 of 14-

HANDOUT (cont.)

The CRS had directed you to:

  • Verify the Chemistry data entries and calculations for release rates I activity levels for:

o RBCLC (RM-352) o Service Water (RM-351) o Off-Gas (RM-150A/B)

  • Determine if, based upon the given radiation monitor indications, the status of annunciators 09-3-2-27, 09-3-2-30, and 09-3-2-38 are appropriate.

-7 of 14-

HANDOUT

-8 of 14-

HANDOUT

{

OffGA!; K -£AC.1.QB. DATA SHEET Page 1 of l.

Q(FGAS X-fACIQB ~IA ~~~&I NO'rSI To c:alcu.lat.e the current OFFGAS release rate in uCi /sec:

uCi/s~c = I S,JAE f\ad Monitor Head.ing Bkgd l X K Factor l lmR/hr*) (mR/hr}..~ ~~

mR/hr )

K-F'ACTOR Analysis S..JA~ RAO MONITOR o;.n: 6KGr:l ~

mr!hr

.fs/;
L

... , '-1 ~~-")"

8: !i

/~/2-DATE COMPILF:D: :J../:;-(;.:J..

'I'ECHNICIAN: _ _-_ _bL1'f/c.z-APPROVED FOR C\N&ROOM P( "PI '""~~J- ~ YES . - *, _ NO SUPEHVcSOR -~  ; .r~N)j...; 'LI./,...,.~ L"':'\- *-----

C7 Prift/Sign FOR lNFORMA'l'lON. CONTACr THE CH!:;MISTRY LAB AT X-6746 OFF GAS RADIA'TTON MONITOR t.lMITS tl*lta For FfB ~01~ .. . {mont:h/yr!

NOM! NAl, .:ii.EAl2.L!i-rATE BSAL!U!I.i;  !:lHiH l}.L,e.BM SEieOJI'l:I; 17RM*J~0A - -~ rnR/hr 17RM-ISO!\ - \s.1 mR/hr l"IRM-150fl - __i.Q:l_ mR/hr 17RM-*150B - '5'.9 mH/hr CONTACT Qllili_J.al;\ fQB SAM!.'!,;; U1

/

1 IRJ~ .>50A exc:eed* I (a.'> rr.R/hr l"IRM-1 '>08 .,......,. 12 .z.. mR/hr

[ F.P!L: ALARM

__]_Q__ r.R/hr I

p
> 3 . ()"*) STEA."' ,JET AIR J':,JECTOR AND Rf:COMBTNER At.tilChmcnt 10 Rev . No. _!,! __ ErrLUEN*I' :;,\MPLTNG AND ANALYSIS I' *.1 q e _.2!i ot __.!i.i-

-9 of 14-

HANDOUT CO?Y

~!OUIQ PROCESS MONITOR CAL DATA Page 1 of 1 TO CALCULATE ACTIVITY:

Activity (uCi/~ll * !Monitor Reading (cp*l* BKO(cpell X K*Pactor (uCi/ml/cp*l MONITOR ID ID 1J CAL OATS BACKGROUND K FACTOR (BKG) uCi/ml cpa cpa RADWASTE 17RM-3SO T.TQUIO J../)/;). l'f  ;;.-;r'-7 NORMAL 17RM-351 SERVICll! WATER J../)/;). tf J.lo7/f"-7 RBCLC 17RM-352 J./s/;;. ttf )./)(.:. 7 CHEM TECHNICIAN:

( P:tint/Sign)

SP-03.07 f,IQUID PROCESS RADIATION ATTACHMENT 7 Rev. No. ~ MONITORS Page _!U_ of ~

)

-10 of 14-

HANDOUT

-11 of 14-

HANDOUT Expanded View of Service Water and RBCLC Radiation Monitor Blue

-12 of 14-

HANDOUT

-13 of 14-

HANDOUT

-14 of 14-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

  • """' SRO 14-1 NRC SRO RC TASK TITLE: Determine Release Rates and ODCM Actions APPL TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: _;;2~.3~*..;...11_(:~..,;,4~.3"-)- - - - -

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes /) ,.

SUBMITTED: .?£: A ~ _..-L OPERATIONS REVIEW: ti{, &~

APPROVED: _...:::::;.;.:...."".:....::~~~---------

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom DATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 15-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO RC TASK TITLE: Determine Release Rates and ODCM Actions APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required ~ None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 15-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO RC TASK TITLE: Determine Release Rates and ODCM Actions APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. ODCM B. ARPs for Panel 09-3-2 Ill. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the references listed above are available for the number of candidates.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

VI. TASK CONDITIONS A. A plant transient has resulted in fuel damage.

B. Radiation releases are occurring through Service Water and Off-gas.

C. Annunciator 09-3-2-27, OFF GAS RAD MON HI, has alarmed.

D. Annunciator 09-3-2-38, OFF GAS RAD MON HI-HI, has NOT alarmed.

E. Annunciator 09-3-2-30, LIQUID PROCESS RAD MONITOR HI-HI, has NOT alarmed.

F. Current indications for RBCLC, Service Water, and Off-gas radiation monitoring are provided in the attached pictures.

G. Chemistry has determined release rates I radiation levels for RBCLC, Service Water, and Off-gas as follows:

Chemistry Calculations RBCLC {800- 14) x 2.23 E-7 =4.21032 E-4 f..lCi/ml Service Water (200- 4) x 2.67 E-7 =5.2866 E-5 f..lCi/ml Off-gas (801 - 4) x 88.85 =70813.45 f..lCi/sec H. Chemistry w1ll determme 1f 10CFR, ODCM, Tech Spec, or TRM release rates are w1thm limits.

-3 of 15-

SRO 14-1 NRC SRO RC TASK TITLE: Determine Release Rates and ODCM Actions

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate of the following:

"The CRS had directed you to:

  • Verify the Chemistry data entries and calculations for release rates I activity levels for:

o RBCLC (RM-352) o Service Water (RM-351) o Off-Gas (RM-150A/B)

  • Determine if, based upon the given radiation monitor indications, the status of annunciators 09-3-2-27, 09-3-2-30, and 09-3-2-38 are appropriate.
  • Determine if there are additional actions required by Tech Specs, TRM, or ODCM (other than release rates/limits, which Chemistry will determine)."

STEP STANDARD EVALUATION I COMMENT

  • 1. Verify RBCLC activity. Calculates RBCLC activity to be approximately 1.66632 CRITICAL STEP E-4 ).I.Ci/ml (acceptable range of 1.45644 E-4 to 1.8762 SAT I UNSAT E-4).

EVALUATOR NOTE: The Chemistry calculation utilized an incorrect K-factor. The correct calculation is (800 -

=

14) x 2.12 E-7 1.66632 E-4 J.!Ci/ml. The acceptable range is based on a chart reading of 701 and 899.

-4 of 15-

SRO 14-1 NRC SRO RC TASK TITLE: Determine Release Rates and ODCM Actions STEP STANDARD EVALUATION I COMMENT

  • 2. Verify Service Water activity. Calculates Service Water activity to be approximately CRITICAL STEP 7.9032 E-5 J.!Ci/ml (acceptable range of 6.5682 E-5 to SAT I UNSAT 9.2382 E-5).

I I

EVALUATOR NOTE: The Chemistry calculation utilized an incorrect rad monitor reading. The correct calculation I

=

is (300- 4) x 2.67 E-7 7.9032 E-5 J.!Ci/ml. The acceptable range is based on a chart reading of 250 to 350.

  • 3. Verify Off-gas activity. Determines the Chemistry calculation for Off-gas activity CRITICAL STEP is accurate. SAT I UNSAT
4. Determine status of alarms. Determines that annunciator 09-3-2-27, OFF GAS RAD SAT/UNSAT MON HI, is operating properly.

Determines that annunciator 09-3-2-38, OFF GAS RAD MON HI-HI, is operating properly.

Determines that annunciator 09-3-2-30, LIQUID PROCESS RAD MONITOR HI-HI, should have alarmed when Service Water activity exceeded 200 cps.

-5 of 15-

SRO 14-1 NRC SRO RC TASK TITLE: Determine Release Rates and ODCM Actions STEP STANDARD EVALUATION I COMMENT

  • 5. Determine Technical Specification, Determines Service Water radiation monitor is CRITICAL STEP TRM, and/or ODCM required action(s). inoperable and the discharge can continue if grab SAT I UNSAT samples are taken every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I I EVALUATOR NOTE: This requirement is based on I

ODCM Table 2.1-1 Action (b). I EVALUATOR: Terminate the task at this point.

Task Standard: Release rates I activities are verified. Incorrect RBCLC and Service Water calculations are identified and correct values are calculated. Inoperable Service Water radiation monitor is identified and associated ODCM requirement is determined.

-6 of 15-

HANDOUT

  • A plant transient has resulted in fuel damage.
  • Radiation releases are occurring through Service Water and Off-gas.
  • Current indications for RBCLC, Service Water, and Off-gas radiation monitoring are provided in the attached pictures.
  • Chemistry has determined release rates I radiation levels for RBCLC, Service Water, and Off-gas as follows:

Chemistry Calculations RBCLC (800- 14) x 2.23 E-7 = 4.21032 E-4 llCilml Service (200- 4) x 2.67 E-7 = 5.2866 E-5 11Ci/ml Water Off-gas (801 - 4) x 88.85 = 70813.45 11Ci/sec

  • Chemistry will determine if 10CFR, ODCM, Tech Spec, or TRM release rates are within limits.

-7 of 15-

HANDOUT (cont.)

The CRS had directed you to:

  • Verify the Chemistry data entries and calculations for release rates I activity levels for:

o RBCLC (RM-352) o Service Water (RM-351) o Off-Gas (RM-150A/B)

  • Determine if, based upon the given radiation monitor indications, the status of annunciators 09-3-2-27, 09-3-2-30, and 09-3-2-38 are appropriate.
  • Determine if there are additional actions required by Tech Specs, TRM, or ODCM (other than release rates/limits, which Chemistry will determine).

-8 of 15-

HANDOUT r--r:llf~ ~ --Tjs;~-~i~l a., i*

--*-iif-,

-*~!ilti~--~l 4

1

, 1*g * -~u JI tiJ -1

~---- -~*-+~~ -d-l-:'t ..---*+ i*~L_J

.  ;  ! *! 'I! t ~~~

I g~,

1§1ii1

.I r*

~~

"!§ f*

~~~

  • ~i a *

-l S

~

I. :,,..

I -1 I

~~ai '. :ail
  • 'ilt a1z .

cI 1... il a1:

g :S

.. ~

. ir1 In

~ I *~ Q; ~ i~ 9

  • ~~! ~~ I ~~il "d 1 I '

f-

~~

  • I

! e 1 I

---n*,.~=

  • *I
  • r-*-;~ ---r--

t

  • I i§;

EI 1

,v,, I r.

i *~.

I t~ I~~a:]--G~~-~t ~~t~::t l ~tJ ~

-9 of 15-

HANDOUT

{

QffGA!:i K-FAC'fOR DATA SHEET P,lge 1 of Qff~S K-EACIQS DATA SH~~I NO'l'll:l To calculate the <:urr~nt OFFC.AS release rate in uCi/sec:

~Ci/sec = [ S,JA£ Rad Monitor Reading Bkgd 1X K ~*actor tmR/hr*) (mR/hrl.,. ~~

mR/hr )

K-FACTOR Analysis s.;Ar; RAO MON t'rOR DIITE Bi<GiJ ~

mr/hr J../5/; ~ A: '-1 '?) ~." S"'

B: 'I

J../5// ;J..

DATE COMPLLF:D:

-~kAt£-.. /l!J4/Z-

Itt!-

TECHNIC.' IAN:

APPROVED FOR C'N&ROOM'"'~~.:.:l P "ri YES . * *, _ NO SUPEtWrSOR -c<:.C?; .iA<NAd....> Pri;{t/Sign

'(..V*~-"' t&<.- *-----

FOR lNFORMATION, CONTACT 1'HE CH!::MISTRY LAB AT X-6746 OFF GAS RADIATION MONITOR t.lMITS Dr3til F*)r Ff8 ).Of~

.. . (month/yr)

NOMINAL.SI~TATE BE:AI.m!\.i;  !:liCH llJ.,ARM SE;IfQINI; 1"1RM*l50A - -~ mR/hr l7RM-I '>OA - \S. 1 mR/hr PRM-150B - .J...Q:l_ rnR/hr 17RM-150B - ..!2:.9_ mR/hr CQtlTi\.CI Cillili.. LAJ;l fQB S8M!.'!,t; Ill

/

1/RM :soA axcaada I fa*') rr.R/hr l?RM-J)UB axcaeda l2 .z.. mR/hr I F:PtC AI.ARM I

iP ,) 3. O'i STEA.'1 ,JE'l' AIH t':Jt:CTOR AND Rf:COMBTNI';R Attachment 10 l'..ll) *~ ..:;& () t ..lii-6 R=e=*.",;.'.:,*..,;,N;.;c.;.';,*::_.:i;;;;'*o;*-=====.,;!,;,'f;..'=P=L=:U;;E;:N:.*:;.,.,*;;,:,*;

1\MPL I NG /\ND ANALYSIS

-10 of 15-

HANDOUT CO?'f LIQUID PROCESS MQNIIQR CAL DATA Page l of 1 TO CALCULATE ACTIVITY:

Activity (uCi/~11 * !Monitor Reading lcp*l* BKO(cpell X K*Pactor luCi/ml/cpe)

MONITOR ID ID It CAL OATS BACKGROUND K FACTOR (BKQ) uCi /ml cp* cpa RADWASTE

!.TQUIO 17RM-350 J./>/;). I~ :J.?-rE-7 NORMAL 17RM-351 SERVICE WATER  ;./>/;;. tf J.to?e-7 RBCLC 17RM-352 J../>/t;.. ttf ~./)(.:. 7 CHEM TECHNICIAN:

jCc {1./~ru /CCttL-___

(Print/Sign)

, SP-03.07 Rev. No. ~

LIQUID PROCESS RADIATTON MONITORS Page ATTACHMENT 7

.......5.1._ of ~

-11 of 15-

HANDOUT

-12 of 15-

HANDOUT Expanded View of Service Water and RBCLC Radiation Monitor

-13 of 15-

HANDOUT

-14 of 15-

HANDOUT

-15 of 15-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE

  • ., SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate

, APPL. TO JPM NUMBER Event Notification DATE: NRC KIA SYSTEM NUMBER: _2_.4_.4_0......,(4_.5-.~..)_ _ _ __

REV:

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes (/ Ar:--

SUBMITTED: ___;;;~--'-~____,~fl'--~~'---- OPERATIONS REVIEW: ~~ ~~~.

APPROVED:

~

CANDIDATE NAME: LOGIN ID:

JPM Completion Perform Location: Classroom TIME TO COMPLETE:

DATE PERFORMED:

- - - Minutes fERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

-1 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update By:

Date lnt Previous Revision Date:

-2 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. IAP-1 B. IAP-2 C. EAP-1.1 Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure sufficient copies of the referenced documents are available, including extra copies of the Part 1 notification form.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, placekeeping and three-point communication.

-3 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate APPL. TO JPM NUMBER Event Notification VI. TASK CONDITIONS A. The plant was initially operating at 100% power with no equipment out of service.

B. An earthquake was felt in the Control Room and confirmed with both JAF and Nine Mile Point Unit 2 seismic instrumentation.

C. JAF seismic instrumentation indicates >0.1g for both horizontal and vertical acceleration.

D. The earthquake resulted in a loss of DC power system A.

E. The earthquake also caused a coolant leak in the Drywell.

F. The Reactor was manually scrammed five minutes ago.

G. The following conditions exist now:

  • Reactor pressure is 200 psig and lowering.
  • Reactor water level is 0 inches and rising.
  • Drywell pressure is 15 psig and slowly rising.
  • Torus pressure is 12 psig and slowly rising.
  • Torus water temperature is 105°F and slowly rising.
  • Reactor Building differential pressure is -0.25" H2 0.
  • Chemistry reports that Reactor coolant activity is 400 f.!Ci/gm 1-131 dose equivalent.
  • 200' elevation wind speed is 10 mph from 190°.
  • 30' elevation wind speed is 5 mph from 190°.
  • Stability class is E.

-4 of 9-

SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification VII. INITIATING CUE Inform the candidate of the following:

"Classify the event and complete the Part 1 Notification per EAP-1.1, Offsite Notifications. This is a time critical JPM. Your time clock starts once you acknowledge this task."

  • - CRITICAL STEP STEP STANDARD EVALUATION I COMMENT
1. Obtain applicable reference documents Obtains a copy of applicable reference documents, as SAT I UNSAT needed:
  • EAP-1.1 EVALUATOR: Ensuie sufficient copies of these documents are available.
  • 2. Classify the event Classifies the event as Site Area Emergency FS 1.1 CRITICAL STEP based on loss of Fuel Clad and RCS barriers within 15 SAT I UNSAT minutes of JPM start time.

JPM start time:

Time of classification:

Time difference:

-5 of 9-

SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification STEP STANDARD EVALUATION I COMMENT

  • 3. Implement EAP-1.1, Offsite Completes EAP-1.1 Attachment 1, Part 1 notification CRITICAL STEP I I Notific~tions, in order to notify offsite form per attached key within 15 minutes of classification SAT I UNSAT agenc1es I time Time of classification:

I Time of offsite notification:

Time difference:

EVALUATOR NOTE: Only item 3, 4, 5, 6, and 7 of EAP-1.1 Attachment 1 are deemed critical for this JPM.

These items are individually graded in the JPM steps below. All other items are non-critical. See attached key.

  • 4. Completes Part 1 Notification step 3 Indicates "SITE AREA EMERGENCY" in Part 1 CRITICAL STEP Notification step 3 (see attached key) SAT I UNSAT
  • 5. Completes Part 1 Notification step 4 Records today's date and time of declaration in Part 1 CRITICAL STEP Notification step 4 (see attached key) SAT I UNSAT
  • 6. Completes Part 1 Notification step 5 Indicates "No Release" in Part 1 Notification step 5 (see CRITICAL STEP attached key) SAT I UNSAT

-6 of 9-

SRO 14-1 NRC SRO EP TASK TITLE: Determine Emergency Classification and Initiate Event Notification STEP STANDARD EVALUATION I COMMENT

  • 6. Completes Part 1 Notification step 6 Indicates "NO NEED for PROTECTIVE ACTIONS CRITICAL STEP outside the site boundary" in Part 1 Notification step 6 SAT I UNSAT I I (see attached key)

I

  • ~
  • 7. I Completes Part 1 Notification step 7 I Indicates EAL # "FS1.1" in Part 1 Notification step 7 (see I CRITICAL STEP attached key) SAT I UNSAT EVALUATOR: Terminate the task at this point.

Task Standard: The emergency event is classified and the Part 1 Notification form is filled out.

-7 of 9-

EVALUATOR'S KEY PART ONE GENERAL INFORMATION Paqe 1 of 1 NEW YORK STATE

!JP5TATE RADIOLOGICAL EMERGENCY DATA fORM Ullll Nocifil:llioft If

.,.hllla to rlpCIIt 111 ir1clclenl til lhe J - A. FllzPIIIrlcl! P - Plant. Sllldly for CIOiiltnn.UClft." (Candul:l ral QIIID Include lie fcllooMing tllltlona:) 0 N1w Vtllll..... 0 a.-.. Countr 0 Nine ........... Uftll 11 0 11M M.. l'olnl """a FROM: (gL m. mEa OTHER) ED Approval: CS!gnaturel

.1. In.......,

GI;,NERAL INFORMATION (Note: 0 When c'**td 1nc1Ata c:Mnge MIM~~ge *.wnfttecl 011: ( , _ *cr,_,_ ~MourCtooll a ,., ..... :s1a.m-2200 lll..2201 NOT for 1Mce VIe: A. IEC8

. ~

0 o.w.aoeo.: set..et50ar_ttt 0 , . , It: 34M201 IlL~ Room Hollne 0 NMP

  • a: 349-5202 QLConlrol R<<n ......
02. This is: A. An ~* Elrlerpney (!}Ant:un:ise The Eme~ Clauification ir.:

03.

A. UNUSUAL EVllNT

8. 1\1..£1\T cpsiTE AREA EMERGENCY GENERAl. EMER.GI:NCY E. EMERGENCY 'n:RMINAT£0
f. Other
04. This EmcrJef'CY Classitkllion dcc:larccl on: __Jig_Qy~ .O~~L*--*-****

(dille) -... -* *-(~~t!, clock)

Os. ~:of RadiDKtive Murial' ciae to die clast~ lied cvtn~:

No !tel-Rele.sc BILOW fedenllimil5 Technia.l Speciliaition oToM~ oToW~

C. ltd- ABOVE fedmtllimits Tcc:hnital Specilkation aToA~ cToWiltf D. Uamonil<ll'ed rcleue reQIIiriU evaliiAtiOft

06. The rollowina Protective Aetionlarcl'4llliiiDIMJid 10 be i""'lcrncnled a10011 es pnic:licable:

G)No Nt:t:D rw PROT£CTI\'£ ACTIONS oubide 1he lite bounUry

8. t:VACliAIt: 11141MPLEMJ:I"CT llle KJ PLAN f<< !he fol~q t:RPA11114 All m~~~ininB ERPAs MONITOR die f.Mt:RGlNCY ALERT SYSTtM I 2 3 4 s 6 7 8 9 10 II 12 13 14 IS 16 17 18 19 20 21 22 23 24 l$ 26 27 lJ Z9

~rE.; oFFSITE dflliJQMil~;S. SiQL!J.D. COll~flu. SH'Lru.-~-e~a. ... u.u. u. lf ltd~TION cs. NDI.WSJ.Il.l.~

C. SHELTt:R-IN-PLAC£ aad IMPLEMENT tiM Kl PLAN lOr lhe foiiCMina ERPAs and All re-inina ERPAs MONITOR llle EMERGENCY ALERT SYSTEM 1 2 3 4 s 6 7 8 9 10 II 12 ll 14 15 \6 \7 18 19 20 21 22 23 24 l$ 26 27 28 29

07. EALIESl.l (Optional description here - not critical)

Briel' F.vent ...

Description A Odicr S~ificant -- - *-**** ......,....,.h__ --.~-*-----*-----

lnformeOOrl

+---*

Os.

09.

Rllllc:t<< SLitlus; Wind Speed: A. Hl

.\. Operational (8. l 1 oaay s_u_ate1 Miks'Huur at ckwti011 200 (dille)

.,~;:,_taf1 11me- o m1nutesJ (time 24 hr elude)

Feet (Eitvalled) 8.5 Mileti'Huur at ekmbon 30 Feet (Ground) 010. Wind llilmion: A. (from) lJI!J J:le&rce$ a1 clcvllion ~W. Feet (EienMd)

a. (From>. , go Delrees 8l elewlion 30 feel (Groundl Q_ll. Stability CIIISS EJevatcd: 1lDilll!!c - A B c ~-D .S!II!k -(E~ F G 012. Rc:ponocl Py- Communk:aroR name: Tdcplionc
  • ill..Sl "INIM18 ,Ooyoun-.ny~'7' 0 New York 1t1i11e 0 Oewtgo ~ 0 Nine llle Plllnl Unltl1 0 Nine .... Point UnlliZ "Jamee A. Filzhlllclc Nuc:leer PoMir PWlllXIIal (!ltfl! ljrrw)"

EVALUATOR'S KEY

-8 of 9-

HANDOUT

  • The plant was initially operating at 100% power with no equipment out of service.
  • An earthquake was felt in the Control Room and confirmed with both JAF and Nine Mile Point Unit 2 seismic instrumentation.
  • JAF seismic instrumentation indicates >0.1g for both horizontal and vertical acceleration.
  • The earthquake also caused a coolant leak in the Drywell.
  • The Reactor was manually scrammed five minutes ago.
  • The following conditions exist now:

o Reactor pressure is 200 psig and lowering.

o Reactor water level is 0 inches and rising.

o Drywell pressure is 15 psig and slowly rising.

o Torus pressure is 12 psig and slowly rising.

o Torus water temperature is 105°F and slowly rising.

o Reactor Building differential pressure is -0.25" H20.

o Stack and Reactor Building ventilation radiation monitors are stable at the pre-transient values.

o Chemistry reports that Reactor coolant activity is 400 J.1Ci/gm 1-131 dose equivalent.

o 200' elevation wind speed is 10 mph from 190°.

o 30' elevation wind speed is 5 mph from 190°.

o Stability class is E.

Classify the event and complete the Part 1 Notification per EAP-1.1, Offsite Notifications. This is a time critical JPM. Your time clock starts once you acknowledge this task.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 A TASK TITLE: Reset an RPS Scram with Scram Valve Failure to Close (Faulted)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 212000 A4.14 (3.8/3.8)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- Minutes SUBMITIED: OPERATIONS REVIEW:

APPROVED:

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

CANDIDATE NAME:

JPM Completion 0 Simulated IZI Performed Location:

",TE PERFORMED:

D Plant 1Zl Simulator TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory

~----------------------------------*~------------------------------------------

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE.

REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 A TASK TITLE: Reset an RPS Scram with Scram Valve Failure to Close (Faulted)

APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review 0 Additional Information 0 Questions and Answers 0 Validation 0 Procedural Change Required 1Z1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 A TASK TITLE: Reset an RPS Scram with Scram Valve Failure to Close (Faulted)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A None II. REFERENCES A AOP-1, Reactor Scram, Current Revision Ill. TOOLS AND EQUIPMENT A None IV. SET UP REQUIREMENTS A Initialize the simulator to any full power IC (IC--66).

B. Insert a manual scram by placing the Mode Switch to SHUTDOWN.

C. Ensure ARI is reset.

D. Stabilize RPV level above 177 inches.

E. Manually override the blue scram lights "ON" for control rods 14-43, 30-19, 06-19, 42-07.

F. Verify the blue scram lights for control rods 14-43, 30-19, 06-19, 42-07 are visibly lit.

V. EVALUATOR NOTES A The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A The reactor was scrammed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to a Feedwater malfunction.

B. The scram condition has been identified and cleared.

C. All Reactor scram signals are now clear with the exception of the scram discharge volume high level signal.

-3 of 7-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS has directed that you reset the scram per AOP-1."

NOTE: All actions performed at Panel 09-5

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

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SAT I UNSAT AOP-1, Reactor Scram. of AOP-1. (Control Room, Merlin)

EVALUATOR: Provide candidate a current copy of AOP-1

2. Select the correct section to The candidate selects Section F .1 of AOP-1. SAT I UNSAT perform the task.

EVALUATOR: Provide candidate a copy of section F.1

3. IF ARI actuated, THEN reset Observes that ARI is reset. SAT I UNSAT ARI.
4. Verify annunciator 09-5-1-33 Observes that the annunciator window for annunciator 09 SAT I UNSAT MODE SW IN SHUTDOWN 1-33 is in alarm.

TRIP BYPASSED is in alarm.

  • 5. Place the SDIV HI LVL TRIP Places the SDIV HI LVL TRIP switch in BYPASS. (09-5 CRITICAL STEP keylock switch in BYPASS. 11 Alarm) SAT/UNSAT

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

  • 6. Place RX SCRAM RESET Places the REACTOR SCRAM RESET selector switch, (5A- CRITICAL STEP switch to Group 2 & 3, then to S5), momentarily to the GP2 and GP3 position then back SAT I UNSAT 1 & 4, spring return to NORM. thru "NORM" to the GP1 and GP4 position then back to "NORM".
7. Verify RPS A and B SCRAM Verifies the scram has been reset by ensuring that the SAT I UNSAT GROUPS 1, 2, 3 and 4 lights following lights are lit:

are on.

A RPS A Scram Groups 1, 2, 3 and 4 on Panel 09-5 B. RPS B Scram Groups 1, 2, 3 and 4 on Panel 09-5

8. Verify closed all scram inlet Recognizes/reports that several control rod scram inlet and SAT I UNSAT and outlet valves using one or outlet valves have failed to close by observing that blue a combination of the following scram lights are lit.

methods: Blue scram lights or local indication.

EVALUATOR: If Candidate asks about local indication, ask Candidate, "which HCU's"?

The Candidate should reply: 14-43, 30-19, 06-19, 42-07 Inform Candidate that local indication is consistent with the blue lights, the valves are open.

  • 9. IF any scram inlet or outlet Depresses the both manual scram pushbuttons. CRITICAL STEP valve fails to close, then SAT I UNSAT perform the following:

A Depress the following push buttons:

-5 of 7-

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

STEP STANDARD EVALUATION I COMMENT B. Investigate cause States that they would initiate action (condition report, work SAT I UNSAT order request or discussion with supervision) to identify the cause of the scram valves failing to close.

EVALUATOR: Terminate the task at this point.

Task Standard: The Reactor scram is reset. Then, failure of scram valves to close is detected and the Reactor is re-scrammed.

-6 of 7-

HANDOUT

  • The reactor was scrammed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago due to a Feedwater malfunction.
  • The scram condition has been identified and cleared.

The CRS has directed that you reset the scram per AOP-1

-7 of 7-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 B TASK TITLE: Initiate RCIC in Pressure Control with Speed Failure (Ait Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 217000 A4.01 (3.7/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes . ;2_ _L:.

SUBMITIED: _:::z-/Z -:) .---- OPERATIONS REVIEW: f; /(f!/i!XJJ~

APPROVED: ~ ~S

~~------------~~--------------------*-~-~-------------------------------~-------

CANDIDATE NAME:

JPM Completion D Simulated 1:8J Performed Location: D Plant I:8J Simulator

~f>ATE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 B TASK TITLE: Initiate RCIC in Pressure Control with Speed Failure (Ait Path)

APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items 0 Technical Review D Additional Information 0 Questions and Answers 0 Validation 0 Procedural Change Required 0 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 B TASK TITLE: Initiate RCIC in Pressure Control with Speed Failure (Ait Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-19, Reactor Core Isolation Cooling System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Plant in a shutdown condition with RPV level between 177" and 222.5" (IC-66).

B. Reactor pressure between 700 psig and 1000 psig and rising slowly.

C. Main Steam Isolation Valves closed.

D. Insert malfunction RC07A (RCIC Governor Fails High).

E. HPCI is not available.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS

1. A plant shutdown and cooldown is in progress.
2. Main Steam Isolation valves have been closed due to a Condenser tube rupture.
3. Reactor pressure is between 700 psig and 1000 psig and rising slowly.
4. Another Operator may cycle an SRV to assist in pressure control during this evolution.
5. HPCI is not available.

-3 of 8-

  • - CRITICAL STEP INITIATING CUE Inform the candidate, "The CRS directs you to start the RCIC System for RPV pressure control.

Maximize heat removal with RCIC to minimize SRV operations per OP-19."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Posted Obtains a controlled copy of OP-19. SAT I UNSAT Attachment, RCIC MANUAL START UP FOR RPV PRESSURE CONTROL or OP-19, 0.2.
2. Caution: Operating RCIC in Reviews Caution and Note. SAT I UNSAT pressure control mode with suction from the CST and CST level below 79.5 inches could cause vortexing. Verifies that CST level is greater than 79.5 inches.

Note: When RCIC flow is below 300 gpm in automatic, the system can become unstable and cause flow oscillations.

3. Verify HPCI auto-initiation condition Verifies that there is no HPCI SAT I UNSAT is clear. automatic initiating condition present of high drywell pressure or low RPV water level.
4. Verify Annunciator 09-4-0-32 RCIC Verifies Annunciator 09-4-0-32 RCIC SATIUNSAT LOGIC RX LVL HI is clear. LOGIC RX LVL HI is clear.
5. Align RCIC to CSTs as follows: Ensures: SAT I UNSAT
a. Ensure open CST SUCT VLV 13MOV-18
  • CST SUCT VLV 13MOV b. Ensure closed the following open
  • INBD TORUS SUCT 13MOV-

I

-4 of 8-

STEP STANDARD EVALUATION I I COMMENT

  • 7. Start VAC PMP 13P-3. At Panel 09-4, starts pump 13P-3 by CRITICAL STEP placing its control switch to the SAT I UNSAT START position.
  • 8. Open OIL CLR WTR SUPP 13MOV- At Panel 09-4, opens 13MOV-132 by CRITICAL STEP 132. placing its control switch to the SAT I UNSAT OPEN position.
  • 9. Throttle open TEST VLV TO CST At Panel 09-4, throttles open CRITICAL STEP 13MOV-30 approximately 10 13MOV-30, by placing its control SAT I UNSAT seconds. switch to the OPEN position and releasing after 10 seconds.
11. Verify RCIC Flow rate is Observes RCIC flow rate is high. SAT I UNSAT approximately 400 gpm. May attempt to adjust auto setpoint.

Informs the CRS of the failure of SAT I UNSAT automatic speed control of the RCIC turbine; follow guidance of EN-OP-115 to place the RCIC turbine speed controller in manual.

EVALUATOR NOTE:

Applicant should recognize RCIC speed has failed high.

EVALUATOR ROLE PLAY:

Role play as CRS to direct the Candidate to take manual control and establish pressure control with RCIC. Direct RCIC flow maintained approximately 400 gpm while in manual during the remainder of the evolution.

I

-5 of 8-

STEP STANDARD EVALUATION I I COMMENT

  • 12. Place RCIC flow controller in manual Places RCIC flow controller in CRITICAL STEP to control speed manual to control speed. SAT I UNSAT
13. Ensure closed the following valves: Observes that the green- closed SAT I UNSAT indicating light is on for:
14. NOTE: As RPV pressure lowers, Reviews Note. SAT I UNSAT indicated level on 02-3LI-283A may rise and result in an undesired trip at the red line high level trip value.

Posted Attachment 3 will give an equivalent trip level for 06LI-941AIBIC indicators on panel 09-5.

15. CAUTION: Operating RCIC at less Reviews Caution. SAT I UNSAT than 2200 rpm could cause improper oil system operation and insufficient exhaust flow resulting in check valve banging or steam flow reversals.

Failure to closely monitor RCIC pump discharge pressure could result in exceeding RCIC piping design pressure of 1320 psig.

EVALUATOR NOTE: RCIC flow control manual adjustment knob will need to be adjusted in tandem with 13MOV-30 to maintain RCIC flow near 400 gpm.

I

-6 of 8-

STEP STANDARD EVALUATION I I COMMENT

  • 17. Throttle TEST VLV TO CST 13MOV- At Panel 09-4, throttles closed CRITICAL STEP 30, to obtain the desired RPV 13MOV-30 to begin the RPV SAT I UNSAT pressure control. depressurization to minimize SRV operation.

EVALUATOR NOTE: RPV pressure may be approaching 1000 psig and Candidate may suggest opening an SRV. Inform Candidate that another Operator is assigned to SRVs.

18. Startup RHR Torus cooling per EVALUATOR CUE: Inform the SAT I UNSAT Section D of OP-138, as soon as applicant that another operator has practicable. been tasked with initiating Torus cooling and monitoring T crus parameters.
19. WHEN time permits, verify the Dispatches an Operator to verify the SAT I UNSAT following RCIC parameters: following RCIC parameters:
  • Oil pump discharge pressure:
  • Oil pump discharge pressure:

12 to 15 psig. 12 to 15 psig.

  • Oil temperature from cooler:
  • Oil temperature from cooler:

GREATER THAN 60°F. GREATER THAN 60°F.

  • Oil temperature from the
  • Oil temperature from the turbine bearings: LESS turbine bearings: LESS THAN 160°F THAN 160oF EVALUATOR CUE: Acknowledge direction and report that these parameters have been verified SAT.

EVALUATOR: Terminate the task at this point.

Task Standard: RCIC is placed in pressure control mode. RCIC speed is controlled manually due to a failure of the governor to respond properly to automatic control.

-7 of 8-

HANDOUT

  • A plant shutdown and cooldown is in progress.
  • Reactor pressure is between 700 psig and 1000 psig and rising slowly.
  • Another Operator may cycle an SRV to assist in pressure control during this evolution.
  • HPCI is not available.

The CRS directs you to start the RCIC System for RPV pressure control. Maximize heat removal with RCIC to minimize SRV operations per OP-19.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 C TASK TITLE: Restore CRD to Normal Alignment Following ATWS (Ait Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 201001 A2.07 (3.2/3.1)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes /) ~

SUBMITIED: ~ k :="7 ~ OPERATIONS REVIEW: /d-L ~

APPROVED:

d~

CANDIDATE NAME:

JPM Completion D Simulated [8:1 Performetd Location: D Plant [8:1 Simulator 1.

~:

~TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 C TASK TITLE: Restore CRD to Normal Alignment Following ATWS (Ait Path)

APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 C TASK TITLE: Restore CRD to Normal Alignment Following A TWS (Ait Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-3, Backup Control Rod Insertion B. OP-25, Control Rod Drive Hydraulic System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset to an appropriate IC (IC-67).

B. Ensure the Reactor is scrammed.

C. Ensure both CRD pumps are running.

D. Ensure full open CRD Drive Water Pressure Control Valve 03MOV-20.

E. Ensure full closed CRD Cooling Water Pressure Control Valve 03MOV-22.

F. Ensure CRD Flow Control tapeset is run to maximum.

G. Ensure override RD ZAI3FC301 (2), CRD FLOW CONTROLLER -AUTO, is preset at a high value

(>95).

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. An ATWS has occurred.

B. Control rods were inserted by raising CRD drive water and cooling water differential pressure.

-3 of 8-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to perform EP-3 Section 5.15, CRD Hydraulic System Restoration. Secure CRD pump Band leave CRD pump A running."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-3. SAT I UNSAT EP-3.
2. Select the correct section to Selects Section 5.15. SAT I UNSAT perform the task.
3. Ensure open 03CRD-56 (CRD Dispatches operator to ensure open 03CRD-56. SAT I UNSAT charging water supply header isol valve).

EVALUATOR CUE: 03CRD-56 is open.

4. Ensure open 03CRD-91 Dispatches operator to ensure open 03CRD-91. SAT I UNSAT (stabilizing valves A & B outlet header isol valve).

EVALUATOR CUE: 03CRD-91 is open.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

5. Ensure open the following Dispatches operator to ensure open 03CRD-177A and SAT I UNSAT valves: 03CRD-1778.
  • 6. IF both CRD pumps are Stops CRD pump 8 by rotating control switch CRITICAL STEP running, THEN shut down one counterclockwise. SAT I UNSAT of the CRD pumps.
7. Establish normal CRD Obtains a controlled copy of OP-25 Section E. SAT I UNSAT Hydraulic System operating values per Section E of OP-25.
  • 8. Establish normal CRD system Attempts to adjust tapeset on CRD FLOW CNTRL 03FIC- CRITICAL STEP flow. 301 to lower CRD system flow. SAT I UNSAT EVALUATOR NOTE: The tapeset on 03FIC-301 is failed, such that the controller will not respond to the operator's adjustments while in AUTO. EN-OP-115 provides guidance for the operator to take manual control of a controller that has failed in automatic.

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

9. Recognize I report CRD Flow Reports CRD Flow Control Valve failure. SAT I UNSAT Control Valve failure.

EVALUATOR NOTE: If candidate asks how to proceed, direct them to make a recommendation and then carry out that recommendation.

  • 11. Establish normal CRD system Adjusts knob on CRD FLOW CNTRL 03FIC-301 to establish CRITICAL STEP flow. between 59 and 61 gpm. SAT I UNSAT EVALUATOR NOTE: JPM steps 11-13 may be performed in any order, but have the potential to affect CRD parameters established in ether steps. JPM steps 11 and 12 should only be graded SAT if the associated parameter is ensured in band at the completion of the JPM. This may require the candidate to re-adjust the associated controls.
  • 12. Establish normal CRD drive Throttles closed CRD Drive Water Motor Operated Pressure CRITICAL STEP water differential pressure. Control Valve 03MOV-20 by rotating control switch SAT I UNSAT counterclockwise.

Adjusts 03MOV-20 as required to establish 260 to 270 psid drive water differential pressure.

  • 13. Establish normal CRD cooling Fully opens CRD Cooling Water Motor Operated Pressure CRITICAL STEP water valve alignment. Control Valve 03MOV-22 by rotating control switch SAT I UNSAT clockwise.

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

14. Ensure reference leg backfill is Dispatches operator to ensure reference leg backfill is SAT I UNSAT restored by performing one of restored.

the following:

  • Slowly open 03CRD-300 EVALUATOR CUE: Report that backfill has been restored (reactor vessel wtr lvl as requested.

backfill sys CRD charging header tie in valve)

  • Place all Reference Leg Backfill Systems in service per Section D of OP-27 A.

EVALUATOR: Terminate the task at this point.

Task Standard: The CRD system is restored to a normal alignment. The CRD flow controller is operated in manual due to failure of the automatic setpoint tape to respond to changes in operator demand.

-7 of 8-

HANDOUT

  • An ATWS has occurred.
  • Control rods were inserted by raising CRD drive water and cooling water differential pressure.

The CRS directs you to perform EP-3 Section 5.15, CRD Hydraulic System Restoration. Secure CRD pump B and leave CRD pump A running.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 D TASK TITLE: Feedwater Pump Restoration Following High Level Trip APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 259001 A4.02 (3.9/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes o-/r-SUBMITTED: ~ ? ~--- OPERATIONS REVIEW: d1J ~

APPROVED: __ &......_~=~'---7i"----------

CANDIDATE NAME:

JPM Completion 0 Simulated C8J Performed Location: 0 Plant C8J Simulator

~"'**. t. TE

.........,,, PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER I

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 D TASK TITLE: Feedwater Pump Restoration Following High Level Trip APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required [8:1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 D TASK TITLE: Feedwater Pump Restoration Following High Level Trip APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-2A, Feedwater System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Plant in a startup condition near 500 psig (IC-68).

B. Ensure Feedwater pump B is secured.

C. Ensure Feedwater pump A is tripped on high level with the high level trips NOT reset.

D. Ensure 34MOV-100A and 34MOV-100B are closed E. Ensure Reactor water level restored less than 215 inches and being controlled with 34FCV-137 in AUTO.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A plant startup is in progress.

B. Feedwater pump A was started and then tripped due to a high Reactor water level.

C. The Reactor water level control issue has been fixed and 34FCV-137 is controlling in AUTO.

-3 of 8-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to verify the trip of Feedwater pump A and restart the pump per OP-2A Section G.1."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-2A. SAT I UNSAT OP-2A.
2. Select the correct section to Selects Section G.1 of OP-2A. SAT I UNSAT perform the task.
3. Dispatch an operator to RFP Dispatches operator to RFP A. SAT I UNSAT A.

EVALUATOR CUE: An operator is on-station at RFP A.

4. Verify the following: Observes RFPT A LP Stop Valve green light on, red light SAT I UNSAT off.
  • RFPT ALP AND HP Stop Valves are closed. Observes RFPT A HP Stop Valve green light on, red light off.
5.

-4 of 8-

- - - ~--

- - -~--

- - -~--

STEP STANDARD EVALUATION I COMMENT

6.
  • RFPT A speed has Observes RFPT A speed has lowered. SAT I UNSAT lowered.
7. Ensure running RFPT A AC Observes RFPT A AC OIL PMP 31 P-9A green light off, red SAT I UNSAT OIL PMP 31P-9A OR RFPT A light on.

DC OIL PMP 31P-7A.

8. Ensure closed RFP A DISCH Observes RFP A DISCH 34MOV-1 OOA green light on, red SAT I UNSAT 34MOV-100A. light off.
9. Ensure RFP A FLOW CNTRL Observes RFP A FLOW CNTRL 06-84A is in MAN. SAT I UNSAT 06-84A is in MAN AND RFPT A MGU is on low speed stop.

Observes RFPT A MGU green light on, red light off.

  • 10. Ensure RFPT A MTR SPEED Places RFPT A MTR SPEED CHANGER on low speed stop CRITICAL STEP CHANGER is on low speed by rotating control switch counterclockwise to either SLOW SAT I UNSAT I stop. LOWER or FAST LOWER until green light is on and red light is off.

I

11. IF RFP A must be immediately Observes RFP A MIN FLOW 34FCV-135A green light off, SAT I UNSAT '

returned to service, THEN red light on.

perform the following:

Ensure open RFP A MIN FLOW 34FCV-135A.

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

12. Verify RPV water level is Observes Reactor water level is less than 222.5 inches. SAT I UNSAT LESS THAN 222.5 inches.
  • 13. Ensure RX WTR LVL HI Depresses RX WTR LVL HI CHNL A RESET pushbutton. CRITICAL STEP CHNL A, B, and C are reset. SAT I UNSAT Depresses RX WTR LVL HI CHNL B RESET pushbutton.

Depresses RX WTR LVL HI CHNL C RESET pushbutton.

14. IF RFPT A HYD CPLG Observes RFPT A HYD CPLG green light off, red light on. SAT I UNSAT indicates disengaged, THEN perform the following ...
  • 15. Depress AND hold A MAN Depresses A MAN TR!P RESET pushbutton. CRITICAL STEP TRIP RESET pushbutton. SATIUNSAT
16. Verify the following: Observes RFPT A LP Stop Valve green light off, red light SAT I UNSAT on.
  • RFPT A LP AND HP Stop Valves are open Observes RFPT A HP Stop Valve green light off, red light I

on.

I I

17.

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

  • 18. Release A MAN TRIP RESET Releases A MAN TRIP RESET pushbutton. CRITICAL STEP pushbutton. SAT I UNSAT
  • 19. Slowly raise RFPT A MTR Raises RFPT A MTR SPEED CHANGER to high speed CRITICAL STEP SPEED CHANGER to high stop by rotating and holding control switch clockwise until SAT I UNSAT speed stop, and continue to green light is off and red light is on, plus at least 5 seconds.

raise MSC for at least 5 seconds after reaching high speed stop to ensure MSC is fully on high speed stop.

20. Establish injection to RPV. Determines injection to RPV is established with 34FCV-137 SATIUNSAT in AUTO.

EVALUATOR: Terminate the task at this point.

II I Task Standard: Feedwater pump A is restored to service following a high level trip.

-7 of 8-

HANDOUT

  • A plant startup is in progress.
  • Feedwater pump A was started and then tripped due to a high Reactor water level.
  • The Reactor water level control issue has been fixed and 34FCV-137 is controlling in AUTO.

The CRS directs you to verify the trip of Feedwater pump A and restart the pump per OP-2A Section G.1.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 E TASK TITLE: Perform Area Radiation Monitor Functional Test APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 272000 A4.02 (3.0/3.0)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes /)~

SUBMITTED:  :?-;- ""'- --:5 ~ OPERATIONS REVIEW: !l t_ ~

APPROVED: li!if! "

CANDIDATE NAME:

JPM Completion 0 Simulated ~ Performed Location: 0 Plant ~ Simulator

"!;_c.

~},TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory

~w--------------------------------------

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 E TASK TITLE: Perform Area Radiation Monitor Functional Test APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Zl None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 9-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 E TASK TITLE: Perform Area Radiation Monitor Functional Test APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-32, Area Radiation Monitoring Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset simulator to any IC (IC-69 for 14-1 NRC exam).

EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. The TIP Cubicle area radiation monitor (ARM), 18RIA-051-24, has just been returned to service following repairs.

-3 of 9-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to perform a functional trip test of the TIP Cubicle ARM per OP-32 section G.1."

STEP STANDARD EVALUATION I COMMENT '

1. Obtain a controlled copy of Obtains a controlled copy of OP-32. SATIUNSAT OP-32.
2. Select the correct section to Selects Section G.1. SAT I UNSAT '

perform the task. I EVALUATOR CUE: Direct the candidate to make any notifications or announcements directly to the examiner (this '

is in order to reduce interference with the other JPM in progress).

3. Notify radiation protection of Notifies RP that the TIP Cubicle ARM is to be tested. SAT I UNSAT ARM testing. '

I ROLE PLAY: Acknowledge communication to RP.

4. Test each ARM to be tested Refers to Attachment 2 and determines the ARM has a local SAT I UNSAT  !

as follows: alarm unit. I IF the ARM to be tested has a local alarm unit (Refer to Attachment 2), THEN perform the following:

-4 of 9-

STEP STANDARD EVALUATION I COMMENT

5. Station an observer at the Directs an operator to station at the TIP Cubicle ARM. SAT I UNSAT ARM in the plant to verify local alarms function.

ROLE PLAY: Acknowledge communication and report that the observer is on station at the TIP Cubicle ARM.

6. Announce the following at Announces at least twice: SAT I UNSAT least twice over plant page:

"Attention, attention all "Attention, attention all personnel. Now testing area personnel. Now testing area radiation monitor at the TIP Cubicle (or similar)."

radiation monitor at (state location)."

7. IF white LOW OR amber Observes TIP Cubicle ARM white LOW alarm light is off. SATIUNSAT HIGH alarm light is on, THEN perform the following ...

i

8. Ensure power supply TRIP Rotates TIP Cubicle ARM power supply TRIP CHECK SATIUNSAT CHECK ADJUST ADJUST potentiometer fully counterclockwise, as potentiometer is full necessary.

counterclockwise.

  • 9. Place mode switch in TRIP Places TIP Cubicle ARM mode switch in TRIP TEST. CRITICAL STEP TEST. SAT I UNSAT
10. Verify white LOW light is on. Observes TIP Cubicle ARM white LOW light is on. SAT I UNSAT

-5 of 9-

- - ~--*-**~*-- - - *-- - - - - - - * - - - ---

STEP STANDARD EVALUATION I COMMENT

  • 11. Adjust power supply TRIP Rotates TIP Cubicle ARM power supply TRIP CHECK CRITICAL STEP CHECK ADJUST ADJUST potentiometer clockwise until amber HIGH alarm SAT/UNSAT potentiometer until amber light comes on.

HIGH alarm light comes on.

12. Verify white LOW light is off. Observes TIP Cubicle ARM white LOW light is on. SAT I UNSAT EVALUATOR NOTE: If Candidate recognizes white light is ON, Role Play as Shift Manager and inform Candidate that discrepancy is noted and for them to depress the Reset pushbutton to clear the white light. Continue with the Functional Test.
13. Adjust power supply TRIP Rotates TIP Cubicle ARM power supply TRIP CHECK SAT I UNSAT I CHECK ADJUST ADJUST potentiometer counterclockwise until white LOVV potentiometer until white LOW alarm light comes on.

alarm light comes on.

  • 14. Depress red RESET Depresses red RESET pushbutton on TIP Cubicle ARM. CRITICAL STEP pushbutton. SAT I UNSAT
15. Verify amber HIGH light is off. Observes TIP Cubicle ARM amber HIGH light is off. SAT/UNSAT
16. Ensure power supply TRIP Rotates TIP Cubicle ARM power supply TRIP CHECK SAT/UNSAT CHECK ADJUST ADJUST potentiometer fully counterclockwise.

potentiometer is full counterclockwise.

EVALUATOR NOTE: If the candidate rotated the potentiometer fully counterclockwise during JPM Step #15, then this step is to be graded SAT even without further manipulation.

-6 of 9-

STEP STANDARD EVALUATION I COMMENT

  • 17. Place mode switch in Places TIP Cubicle ARM mode switch in OPERATE. CRITICAL STEP OPERATE. SATIUNSAT
  • 18. Depress red RESET Depresses red RESET pushbutton on TIP Cubicle ARM. CRITICAL STEP pushbutton. SAT I UNSAT
19. Verify the following are off: Observes the following lights are off: SAT I UNSAT
  • White LOW light
  • White LOW light
  • Amber HIGH light
  • Amber HIGH light
  • Local alarm unit light
  • Local horn Contacts operator stationed at TIP Cubicle ARM for the status of the following:
  • Local alarm unit light
  • Locai horn ROLE PLAY: Report that the local alarm unit light and local horn actuated during the test and are now both off.
20. Verify local alarm unit light and Contacts operator stationed at TIP Cubicle ARM regarding SAT I UNSAT horn actuated. the performance of the local alarm unit light and horn during the test.
21. WHEN ARM testing is Notifies RP that ARM testing is complete. SAT I UNSAT completed, notify radiation protection.

ROLE PLAY: Acknowledge communication to RP.

-7 of 9-

STEP STANDARD EVALUATION I COMMENT

22. Announce the following at Announces at least twice: SAT I UNSAT least twice over plant page:

"Attention, attention all "Attention, attention all personnel. Area radiation monitor personnel. Area radiation testing is complete at the TIP Cubicle (or similar), regard all monitor testing is complete at further alarms."

(STATE LOCATION), regard all further alarms."

EVALUATOR: Terminate the task at this point.

Task Standard: A functional test of the TIP Cubicle ARM is completed and the ARM is restored to normal operation.

-8 of 9-

HANDOUT The TIP Cubicle area radiation monitor (ARM), 18RIA-051-24, has just been returned to service following repairs.

The CRS directs you to perform a functional trip test of the TIP Cubicle ARM per OP-32 section G.1.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 F TASK TITLE Initiate Alternate Containment Spray from RHRSW APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 226001 A4.08 (3.2/3.1)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes rflr.

SUBMITTED: ~ -"' -:) ---t..- OPERATIONS REVIEW: ;J*' ~~

APPROVED: --~~~~~~~-------------------

CANDIDATE NAME JPM Completion 0 Simulated C8J Performed Location: 0 Plant C8J Simulator TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 F TASK TITLE: Initiate Alternate Containment Spray from RHRSW APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review [] Additionallnformation D Questions and Answers [] Validation D Procedural Change Required ~~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 10-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 F TASK TITLE: Initiate Alternate Containment Spray from RHRSW APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-14, Alternate Containment Sprays Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Reset the simulator to an IC with the following conditions (IC-70):

  • Malfunction CS01 :B, Core Spray Pump B Trip (Preset)
  • Malfunction RH01 :A, RHR Pump A Trip (Preset)
  • Malfunction RH01 :B, RHR Pump B Trip (Preset)
  • Malfunction RH01 :C, RHR Pump C Trip (Preset)
  • Malfunction RH01 :D, RHR Pump D Trip (Preset)
  • Malfunction FW19:A, Condensate Pmp 33P-8A Trip (Preset)
  • Malfunction FW19:B, Condensate Pmp 33P-8B Trip (Preset)
  • Override CS ZL01412A(1), Core Spray lnbd Valve, OFF (Preset)
  • Override AN932:36, RHRSW Pmp 10P-1D Overcurrent, ON, Delay=4 seconds (Trigger 2)
  • Override SW ZA01 OP1 D, Service Wtr PP D Ammeter, lnitial=32, Final=44, Ramp=6 seconds (Trigger 2)
  • Event Trigger 1- Event= zdi10as48b(2)==1, Command= None
  • Event Trigger 2- Event= zdi10as13b(2)==1&zao10fi137b>0.215, Command= None
  • Event Trigger 3- Event= zdi10as13b(1)==1&zao10p1d>0.42&zao10fi137b<0.215, Command

=cor

-3 of 10-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 F TASK TITLE: Initiate Alternate Containment Spray from RHRSW APPL. TO JPM NUMBER V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

8. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A LOCA has occurred.

B. The EOPs have been entered.

C. Reactor water level is less than 0".

D. All RHR pumps have tripped.

E. RHR Loop A Drywell and Torus spray valves are unavailable.

-4 of 10-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to spray the Torus using RHRSW Loop 8 per EP-14 Section 5.2 with maximum flow to the Torus."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-14. SAT I UNSAT EP-14.

I

2. Select the correct section to Selects Section 5.2. SAT/UNSAT perform the task. I I

I

3. Verify the following RHR Observes RHR PMP 1OP-38 green light on, red light off. SAT I UNSAT pumps are stopped:
4. Ensure closed at least one of Observes 1OMOV-268 green light on, red light off. SAT I UNSAT the following valves:

-5 of 10-

STEP STANDARD EVALUATION I COMMENT

5. Ensure closed at least one of Observes 1OMOV-398 green light on, red light off. SAT/UNSAT the following valves:
  • RHR TEST TORUS CLG and/or

& SPRAY 1OMOV-398

6. Ensure closed at least one of Observes 1OMOV-398 green light on, red light off. SAT I UNSAT the following valves:
  • RHR TEST TORUS CLG and/or

& SPRAY 10MOV-398

  • 7. Ensure closed at least one of Closes 1OMOV-278 by rotating control switch CRITICAL STEP the following valves: counterclockwise and holding until green light is on, red light SAT I UNSAT is off.
  • 8. Ensure available RHRSW Starts 1OP-1 8 by rotating control switch clockwise. CRITICAL STEP pumps in RHRSW Loop 8 are SAT I UNSAT running:

Starts 1OP-1 D by rotating control switch clockwise.

-6 of 10-

STEP STANDARD EVALUATION I COMMENT

  • 9. Ensure RHRSW DISCH VLV Opens 1OMOV-89B by rotating control switch clockwise until CRITICAL STEP FROM HX B 1OMOV-89B is 2500 to 4000 gpm flow is established. SAT I UNSAT I throttled to establish 2500 to 4000 gpm per RHRSW pump.

EVALUATOR NOTE: While 10MOV-89B is being throttled, Trigger 1 will automatically activate and trip RHRSW pump B. With only one RHRSW pump running, 2500-4000 gpm will be the required flow to establish.

10. Recognize I report trip of Reports trip of RHRSW Pump B. SAT I UNSAT RHRSW Pump B.

EVALUATOR CUE: Acknowledge report. If necessary, direct candidate to continue.

11. IF drywell spray is required, Determines Drywell spray has not been directed per SAT I UNSAT THEN perform the following: initiating cue.
  • 12. IF torus spray is required, Opens 10MOV-148B by inserting key and rotating control CRITICAL STEP THEN perform the following: keylock switch clockwise. SAT I UNSAT Ensure open the following Opens 10MOV-149B by inserting key and rotating control valves: keylock switch clockwise.

-7 of 10-

STEP STANDARD EVALUATION I COMMENT

  • 13. IF RPV water level is less than Inserts key and rotates OW & TORUS SPRAY VLV CRITICAL STEP 10 inches on fuel zone water OVERRIDE OF FUEL ZONE LVL 10A-S188 keylock switch SATIUNSAT level indication, THEN place to MANUAL OVERRD.

OW & TORUS SPRAY VLV OVERRIDE OF FUEL ZONE LVL 1OA-S 188 keylock switch in MANUAL OVERRD.

  • 14. Place SPRAY CNTRL 1OA- Rotates SPRAY CNTRL 10A-S178 switch to MANUAL, then CRITICAL STEP S178 switch to MANUAL, releases to spring return to normal. SATIUNSAT spring return to normal.
15. Verify white SPRAY PERM Observes white SPRAY PERM 1OA-DS678 light is on. SAT I UNSAT 1OA-DS678 light is on.
  • 17. Ensure open RHR TEST Opens 1OMOV-398 by inserting key and rotating control CRITICAL STEP TORUS CLG & SPRAY switch clockwise. SAT I UNSAT 10MOV-398.
  • 18. Throttle TORUS SPRAY IN8D Throttles open 1OMOV-388 by rotating control switch CRITICAL STEP VLV 1OMOV-388 to establish clockwise. SAT I UNSAT desired flow while maintaining RHRSW pump motor current LESS THAN OR EQUAL TO EVALUATOR NOTE: When Torus spray flow exceeds max normal amps. -600 gpm, Trigger 2 will automatically activate to make RHRSW Pump D amps exceed the red line value.

-8 of 10-

STEP STANDARD EVALUATION I COMMENT

  • 19. Throttle TORUS SPRAY INBD Throttle closed 1OMOV-388 by rotating control switch CRITICAL STEP VLV 1OMOV-388 to establish counterclockwise until amps lower below max normal. SAT I UNSAT desired flow while maintaining RHRSW pump motor current LESS THAN OR EQUAL TO EVALUATOR NOTE: When Torus spray flow is lowered max normal amps. slightly, RHRSW Pump D amps will return to below max normal.

EVALUATOR: Terminate the task at this point.

Task Standard: Torus spray is initiated using RHRSW loop B. The trip of RHRSW pump B is detected and proper RHRSW flow is established for single pump operation. High current is detected on RHRSW pump D and pump flow is lowered to establish acceptable pump current.

-9 of 10-

HANDOUT

  • A LOCA has occurred.
  • The EOPs have been entered.
  • Reactor water level is less than 0".
  • All RHR pumps have tripped.
  • RHR Loop A Drywell and Torus spray valves are unavailable.

The CRS directs you to spray the Torus using RHRSW Loop B per EP-14 Section 5.2 with maximum flow to the Torus.

-10 of 10*-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 G TASK TITLE: Transfer Buses 10100 and 10200 from Normal to Reserve (Ait Path)

APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 262001 A4.04 (3.6/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes ;l___;../

SUBMITTED: ~ ,c.  :"?;;? ----- OPERATIONS REVIEW: Ji1 ~D'?J APPROVED:

~

CANDIDATE NAME:

JPM Completion 0 Simulated [8] Performed Location: 0 Plant [8] Simulator

...,," . ~ TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: 0 Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 G TASK TITLE: Transfer Bus 10100 from Reserve to Normal (Ait Path)

APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required C8J None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 11-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 G TASK TITLE: Transfer Bus 10100 from Reserve to Normal (Ait Path)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A None II. REFERENCES A OP-46A, 4160 V and 600 V Normal AC Power Distribution Ill. TOOLS AND EQUIPMENT A Synch Key IV. SET UP REQUIREMENTS A Plant in a startup/shutdown situation with Main Generator load -100 MWe (IC-69).

B. Ensure Buses 10300 and 10400 are aligned to Reserve.

C. Ensure Buses 10100 and 10200 are aligned to Reserve.

D. Ensure T-4 position is adjusted such that 10100 will need to be adjusted to facilitate transfer.

E. Ensure the following simulator programming:

  • Override meter ED ZA0098SYNC17A, 0%, Delay Time= 1 second, Trigger 1 (fails RUNNING voltage meter downscale)
  • Event Trigger 1, event = ZDI251 HONA03(2)==1, command = none (activates when 10100 sync key is taken to NORM)

V. EVALUATOR NOTES A The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A A plant startup is in progress.

B. Another operator is stationed to adjust T-4 load tap changer, if required.

C. Nine Mile Point Unit 1 Control Room and Power Control have been notified of all impending bus transfers and tap changer operations.

-3 of 11-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to transfer Bus 10100 from Reserve to Normal per OP-46A Section 0.20."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of OP-46A. SAT I UNSAT OP-46A.
2. Select the correct section to Selects section 0.20. SAT I UNSAT perform the task.
3. WHILE performing the Acknowledges step. SATIUNSAT remainder of this subsection maintain 4KV and 600V bus voltage per Section E.
4. IF a degraded or undervoltage Acknowledges step. SAT I UNSAT condition occurs while transferring bus, THEN immediately establish GREATER THAN 3.9 KV using T-4 LTC CONTROL.
5. IF Main Generator is Observes Main Generator load is greater than 70 MWe and SAT I UNSAT synchronized to 345 KV stable.

System, THEN verify Main Generator has a stable load of at least 70 MWe.

-4 of 11-

STEP STANDARD EVALUATION I COMMENT

6. Ensure Nine Mile Point 1 Determines Nine Mile Point 1 has been notified per initial SAT I UNSAT Control Room (due to effect conditions.

on 115 KV line loading) has I been notified that 10100 Bus will be transferred from reserve to normal service.

7. Perform the following: Determines Power Control has been notified per initial SAT I UNSAT conditions.
  • Notify Syracuse Power Control that 71T-3 tap changer will be taken to manual.
8.
  • Ensure AUTO MANUAL T- Rotates AUTO MANUAL T-3 LTC CONTROL switch to SAT I UNSAT 3 LTC CONTROL switch is MAN.

in MAN.

9. Station operators as follows: Determines another operator has been stationed for T -4 SATIUNSAT load tap changer operation per initial conditions.
  • One to adjust bus voltage at T-4 LTC CONTROL
  • One to operate breaker control switches
  • 10. Place BUS 10100 FOR Inserts synch key and rotates clockwise to NORM for Bus CRITICAL STEP SYNCH SW switch in NORM. 10100. SAT I UNSAT

-5 of 11-

STEP STANDARD EVALUATION I COMMENT

11. IF voltages on NON-EMERG Acknowledges step. SAT/UNSAT BKRS INCOMING and RUNNING volt meters cannot be matched in following step, EVALUATOR NOTE: This step forms the basis of the THEN perform Subsection alternate path in this JPM. In the next steps, the candidate G.14, Single Meter Voltage will determine volt meters cannot be adequately matched Match Method. and will transition to OP-46A section G.14 to complete the task using an alternate method of matching voltages.
12. Match voltages on NON- Observes that the RUNNING volt meter fails downscale. SAT I UNSAT EMERG BKRS INCOMING and RUNNING volt meters using T-4 LTC CONTROL Determines that INCOMING and RUNNING volt meters switch. CANNOT be matched within 1.5 meter increments.

Transitions to OP-46A section G.14.

EVALUATOR CUE: If the candidate reports the malfunction and asks for direction, direct the candidate to make a recommendation and then carry out that recommendation. If the candidate states the volt meter mismatch exceeds that normally allowed for use of single meter match method, then give the Design Engineering cue in JPM step 13.

-6 of 11-

STEP STANDARD EVALUATION I COMMENT EVALUATOR NOTE: The steps below are from OP-46A section G.14.

13. IF voltage mismatch is Determines that voltage mismatch is greater than 6 meter SAT/UNSAT GREATER THAN 6 meter increments.

increments, THEN obtain guidance for performing bus transfer from Design Notifies CRS and/or contacts Design Engineering for Engineering. guidance.

EVALUATOR CUE: Inform the candidate that Design Engineering has determined that OP-46A section G.14.2 should be used to match voltages and transfer the 10100 bus.

  • 14. IF transferring 4.16 KV bus Rotates synch key counterclockwise to RES for Bus 10100. CRITICAL STEP from reserve to normal, THEN SAT I UNSAT perform the following:

Place 4. 16 KV bus FDR SYNCH SW switch in RES.

15. Note voltage on incoming Observes voltage on incoming volt meter. SAT I UNSAT meter.

EVALUATOR NOTE: The candidate may either write down this value or remember it for use in subsequent steps.

-7 of 11-

STEP STANDARD EVALUATION I COMMENT

  • 16. Place 4.16 KV FOR SYNCH Rotates synch key clockwise to NORM for Bus 10100. CRITICAL STEP SW switch in NORM. SAT I UNSAT
  • 17. Match voltage on NON- Rotates T-4 LTC CONTROL switch as required to set CRITICAL STEP EMERG BRKS INCOMING voltage on INCOMING volt meter within 1.5 meter SAT I UNSAT volt meter with voltage taken increments of voltage observed in JPM step 15.

in Step busing T-4 LTC CONTROL switch.

EVALUATOR CUE: If the candidate asks for another operator to adjust T-4 LTC, direct the candidate to perform the T-4 LTC manipulation for the other operator.

EVALUATOR NOTE: The candidate will now transition back to OP-46A section 0.20 at step 0.20.10.

18. IF phase angle is GREATER Observes phase angle on NON-EMERG BKRS SAT/UNSAT THAN 17 degrees on NON- SYNCHROSCOPE is less than 17 degrees.

EMERG BKRS SYNCHROSCOPE,THEN perform the following ...

-8 of 11-

1 STEP STANDARD EVALUATION I COMMENT

  • 19. WHEN incoming and running Closes breaker 10102 by rotating control switch clockwise. CRITICAL STEP I voltages are matched, AND SAT I UNSAT synchroscope is at approximately 12 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, to perform each breaker operation:
  • Close NSS TO BUS 10100 BKR 10102.
  • 20.
  • Open RSS TO BUS 10100 Opens breaker 10112 by rotating control switch CRITICAL STEP BKR 10112. counterclockwise. SAT I UNSAT L.l. Place BUS 10100 FOR Rotates synch key ciockwise to OFF and removes. SATiUNSAT SYNCH SW switch in OFF and remove handle.
22. Verify all white lights for RPS Observes all RPS A and B white lights are lit. SAT I UNSAT A and RPS B power source selectors are on at panel 09-16.

EVALUATOR CUE: If asked about further bus transfers involving T-3, report no further bus transfers are immediately planned involving T-3.

-9 of 11-

STEP STANDARD EVALUATION I COMMENT

23. Perform the following: Determines Power Control has been notified per initial SAT I UNSAT conditions.
  • Notify Syracuse Power Control that 71T-3 tap EVALUATOR NOTE: The candidate may make a changer will be taken to notification for this step. If so, acknowledge notification.

auto.

24.
  • Place AUTO MANUAL T-3 Rotates AUTO MANUAL T-3 LTC CONTROL switch to SAT I UNSAT LTC CONTROL switch in AUTO.

AUTO.

EVALUATOR: Terminate the task at this point.

Task Standard: Bus 10100 is transferred from Reserve to Normal using the Single Meter Voltage Match Method.

-10 of 11-

HANDOUT

  • A plant startup is in progress.
  • Another operator is stationed to adjust T-4 load tap changer, if required.
  • Nine Mile Point Unit 1 Control Room and Power Control have been notified of all impending bus transfers and tap changer operations.

The CRS directs you to transfer Bus 10100 from Reserve to Normal per OP-46A Section 0.20.

-11 of 111-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO NRC 14-1 H TASK TITLE: Isolate RBCLC Supply to the Drywell APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 400000 A4.01 (3.113.0)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 10 Minutes /} %-

SUBMITTED: ~ .AC- '7----- ;?: OPERATIONS REVIEW: ab</l:...w('~'__,_k_(~-~--lillc/,..f.~~-

S APPROVED:

,£!~

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

CANDIDATE NAME:

JPM Completion D Simulated rgj Performed Location: D Plant rgj Simulator

~.

..., ~iTE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory 0 Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO NRC 14-1 H TASK TITLE: Isolate RBCLC Supply to the Drywell APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review D Additional Information D Questions and Answers D Validation D Procedural Change Required rgj None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO NRC 14-1 H TASK TITLE: Isolate RBCLC Supply to the Drywell APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. EP-12, Isolating RBCLC Supply to the Drywell Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Ensure the plant is scrammed with a steam leak causing high Drywell temperature (IC-71).

* EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A small break LOCA has occurred in the Drywell.

B. Drywell temperature has exceeded 260°F.

C. The Reactor Building is accessible.

-3 of 8-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS directs you to isolate the RBCLC supply to the Drywell per EP-12."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a controlled copy of EP-12. SAT I UNSAT EP-12.
2. Select the correct section to Selects Section 5.0. SAT I UNSAT perform the task.
  • 3. Ensure RWR Pumps are Trips RWR pump A by rotating control switch CRITICAL STEP tripped. counterclockwise. SAT I UNSAT Trips RWR pump 8 by rotating control switch CRITICAL STEP counterclockwise. SAT I UNSAT

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

  • 4. Perform the following at panel Inserts key and rotates key lock switch 1-1 RBCA 10 CRITICAL STEP 09-75: counterclockwise to CLOSE. SAT I UNSAT Place the following keylock switches in CLOSE:
  • 1-1RBCA10
  • 5.
  • 1-1 RBCA13 Inserts key and rotates keylock switch 1-1 RBCA 13 CRITICAL STEP counterclockwise to CLOSE. SAT I UNSAT
  • 6.
  • 1-1RBCB10 Inserts key and rotates keylock switch 1-1 RBCB 10 CRITICAL STEP counterclockwise to CLOSE. SAT I UNSAT
  • 7.
  • 1-1 RBCB12 Inserts key and rotates key lock switch 1-1 RBCB 12 CRITICAL STEP counterclockwise to CLOSE. SAT/UNSAT

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

8. Verify closed the following Observes 15AOV-130A green light on, red light off. SAT I UNSAT valves:
9.
10.
11.
12.
13.
  • OW CLR B INLET 15AOV- Observes 15AOV-130B green light on, red light off. SAT I UNSAT 1308
14.
15.
16.

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

17. IF the Reactor Building is Dispatches operator to slowly close the following valves: SAT I UNSAT accessible, THEN slowly close the following valves:
  • 02-2RWR-398 (RWR pump 8 seal purge upstr isol pump A seal purge upstr valve) isol valve)

pump 8 seal purge upstr isol valve)

  • 18. Ensure closed the following Closes 02MOV-43A by rotating control switch CRITICAL STEP valves at panel 09-4: counterclockwise. SATIUNSAT
  • 19.
  • 20.
  • 21.
  • RWR PMP 8 DISCH Closes 02MOV-53B by rotating control switch CRITICAL STEP 02MOV-538 counterclockwise. SATIUNSAT EVALUATOR: Terminate the task at this point.

Task Standard: The RBCLC supply to the Drywell is isolated.

-7 of 8-

HANDOUT

  • A small break LOCA has occurred in the Drywall.
  • Drywall temperature has exceeded 260°F.
  • The Reactor Building is accessible.

The CRS directs you to isolate the RBCLC supply to the Drywall per EP-12.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC I TASK TITLE: Startup Main Steam Leakage Collection System APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 239003 A4.01 (3.2/3.2)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 15 Minutes /Jr-h SUBMITTED: _?:.= /0 2;v j-- OPERATIONS REVIEW: /()i ~~;,Ji2; ~_.,

APPROVED:

11~

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

CANDIDATE NAME:

JPM Completion ~ Simulated D Performed Location: ~ Plant D Simulator

,TE PERFORMED
TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 14-1 NRC I TASK TITLE: Startup Main Steam Leakage Collection System APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review [] Additionallnformation D Questions and Answers [] Validation D Procedural Change Required I~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 8-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO 14-1 NRC I TASK TITLE: Startup Main Steam Leakage Collection System APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. AOP-39, Loss of Coolant Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Provide a working copy of AOP-39 marked up to step F.1.

". EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A loss of coolant accident has occurred.

B. AOP-39, Loss of Coolant, has been completed up to step F.1.

C. All MSIVs are closed.

D. Standby Gas Treatment train A is in operation.

-3 of B-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS has directed that you place Main Steam Leakage Collection System train A in service per AOP-39 Section F.1."

NOTE: All actions performed in the relay room at panel 29MSLCS.

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of The candidate determines where to obtain a controlled copy SAT I UNSAT AOP-39, Loss of Coolant. of AOP-39. (Control Room, Merlin)

EVALUATOR: Provide candidate a current copy of AOP-39.

2. Select the correct section to The candidate selects Section F.1 of AOP-39. SAT I UNSAT perform the task.
3. (AOP-39 Step F.1} IF main Determines one train of Standby Gas Treatment is in SAT I UNSAT steam lines are isolated due to service per initial conditions.

a LOCA, THEN place Main Steam Leakage Collection System in service within approximately 20 minutes per the following:

(AOP-39 Step F.1.1} Ensure at least one standby gas treatment train is in service per OP-20.

-4 of 8-

STEP STANDARD EVALUATION I COMMENT

  • 4. (AOP-39 Step F .1.2) Perform Simulates opening 29MOV-203A by rotating control switch CRITICAL STEP one of the following steps to clockwise.

SAT I UNSAT line up MSLCS Train A or B to collect outboard MSIV stem packing leakage: EVALUATOR CUE: 29MOV-203A green light is extinguished and red light is lit.

(AOP-39 Step F.1.2.a) To line up MSLCS Train A, open 29MOV-203A MST OUTBD MSIV STEM LEAKOFF LINE A ISOL VLV.

  • 5. (AOP-39 Step F.1.3) At panel Simulates closing 29MOV-204A by rotating control switch CRITICAL STEP 29MSLCS, line up a train of counterclockwise. SAT I UNSAT MSLCS to collect leakage downstream of outboard MSIVs per Step a. or b.: EVALUATOR CUE: 29MOV-204A green light is lit and red light is extinguished.

(AOP-39 Step F.1.3.a) To line up MSLCS Train A, perform the following:

(AOP-39 Step F.1.3.a.1)

Close 29MOV-204A MSLC LINE A BYPASS DRN VLV.

-5 of 8-

STEP STANDARD EVALUATION I COMMENT

EVALUATOR CUE: 29MOV-200A green light is extinguished and red light is lit.

EVALUATOR CUE: 29MOV-201A control switch is in OPEN position.

EVALUATOR NOTE: The following cue is necessary to allow the candidate to perform the next step in the procedure. When Annunciator 09-5-2-49 clears, 29MOV-201A opens.

EVALUATOR CUE: Annunciator 09-5-2-49 is clear.

8. (AOP-39 Step F.1.3.a.4) Observes 29MOV-201A green light is extinguished and red SAT I UNSAT WHEN annunciator 09-5-2-49 light is lit.  !

MSLCS A PRESS HI is clear, verify open 29MOV-201A MSLC LINE A TO SGT EVALUATOR CUE: 29MOV-201A green light is UPSTR ISOL VLV. extinguished and red light is lit.

-6 of 8-

STEP STANDARD EVALUATION I COMMENT

9. (AOP-39 Step F.1.3.a.5) Observes 29MOV-202A green light is extinguished and red SAT I UNSAT Ensure open 29MOV-202A light is lit.

MSLC LINE A TO SGT DNSTR ISOL VLV.

EVALUATOR CUE: 29MOV-202A green light is extinguished and red light is lit.

EVALUATOR: Terminate the task at this point.

Task Standard: Main Steam Leakage Collection system train A is placed in service.

-7 of 8-

HANDOUT

  • A loss of coolant accident has occurred.
  • AOP-39, Loss of Coolant, has been completed up to step F.1.
  • Standby Gas Treatment train A is in operation.

The CRS has directed that you place Main Steam Leakage Collection System train A in service per AOP-39 Section F.1.

-8 of 8-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC J TASK TITLE: Perform In-Plant Actions for Station Blackout (AOP-49 Attachment 3)

APPL. TO JPM NUMBER REV: DATE:---- NRC K/A SYSTEM NUMBER: 295003 AA1.04 (3.6/3.7)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 30 Minutes ;j !J-.1(;---

~Y ~ j;_u {~~

1 SUBMITTED OPERATIONS REVIEW:

APPROVED: ~

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

CANDIDATE NAME:

JPM Completion 1:8:1 Simulated D Performed Location: 1:8:1 Plant D Simulator

~~

';,TE PERFORMED: TIME TO COMPLETE: Minutes PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 14-1 NRC J TASK TITLE: Perform In-Plant Actions for Station Blackout (AOP-49 Attachment 3)

APPL. TO JPM NUMBER Current Update: By:

Date lint Outstanding Items D Technical Review D Additionallnformation D Questions and Answers D Validation D Procedural Change Required 1Z1 None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 9-*

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO 14-1 NRC J TASK TITLE: Perform In-Plant Actions for Station Blackout (AOP-49 Attachment 3)

APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. Part of this task involves simulating the operation of circuit breakers. The proper electrical PPE should be made available to the Candidate.

II. REFERENCES A. AOP-49, Station Blackout Ill. TOOLS AND EQUIPMENT A. Gloves IV. SET UP REQUIREMENTS A. Provide a working copy of AOP-49 Attachment 3 with steps 1, 2, 3, and 4 marked complete.

V. EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. A station blackout is in progress.

B. AOP-49, Station Blackout, Attachment 3 is in pro!~ress.

C. The Control Room has completed steps 1-4.

D. Other Operators have been dispatched to perform step 5 and step 9.

-3 of 9-

  • -CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS has directed that you perform the in-plant actions of AOP-49 Attachment 3 Steps 6, 7, and 8.

This is a time critical task. Your time starts now."

Note: This JPM is time critical. All steps must be completed within 30 minutes.

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains AOP-49 Attachment 3 from the evaluator. SAT I UNSAT AOP-49, Station Blackout, Attachment 3.

EVALUATOR: Provide candidate a current copy of AOP-49 Attachment 3 with Steps 1, 2, 3, and 4 marked as complete.

EVALUATOR NOTE: AOP-49 Attachment 3 allows steps to be performed in any order or concurrently.

EVALUATOR NOTE: The following steps are performed at panei94HSC on Turbine Building elevation 252.

Depressunze ma1n generator I Simulates closing 89H2S-G-05 by rotating valve operator clockwise.

CRITICAL STEP casing and secure Emergency SAT I UNSAT Seal Oil Pump 94P-13 as follows: 1 EVALUTOR CUE: 89H2S-G-05 has been rotated and has reached a stop.

(AOP-49 Att. 3 Step 6.a)

Close the following valves:

-4 of 9-

STEP STANDARD EVALUATION I COMMENT

  • 3. (AOP-49 Att. 3 Step 6.a) Simulates closing 89H2S-G-07 by rotating valve operator CRITICAL STEP

EVALUTOR CUE: 89H2S-G-07 has been rotated and has reached a stop.

  • 4. (AOP-49 Att. 3 Step 6.b) Simulates opening 89H2S-G-02 by rotating valve operator CRITICAL STEP Open the following valves: counterclockwise. SAT I UNSAT
  • 89H2S-G-02 (main generator casing gas vent EVALUTOR CUE: 89H2S-G-02 has been rotated and has isol valve) reached a stop.
  • 5. (AOP-49 Att. 3 Step 6.b) Simulates opening 89H2S-G-03 by rotating valve operator CRITICAL STEP
  • 89H2S-G-03 (main counterclockwise . SAT I UNSAT generator casing gas vent valve)

EVALUTOR CUE: 89H2S-G-03 has been rotated and has reached a stop.

EVALUTOR CUE: Main generator casing pressure indicates 0 psig.

  • 6. (AOP-49 Att. 3 Step 6.c) Contacts Control Room to place EMERG SEAL OIL PMP CRITICAL STEP WHEN main generator casing 94P-13 control switch in PULL TO LOCK. SAT I UNSAT is depressurized, place EMERG SEAL OIL PMP 94P-13 control switch in PULL TO EVALUTOR CUE: Inform Candidate that the Control Room LOCK. has placed 94P-13 control switch in PULL TO LOCK.

-5 of 9-

STEP STANDARD EVALUATION I COMMENT I EVALUATOR NOTE: The following steps are performed at 71 BCB-2A in the D.C. Equipment Room on Admin Building elevation 272.

  • 7. (AOP-49 Att. 3 Step 7) Simulates re-positioning FEED TO 71 LPERDC2 REACTOR CRITICAL STEP Place the following circuit BUILDING EMERGENCY LIGHTING DISTRIBUTION SAT I UNSAT breakers in OFF at 71 BCB-2A PANEL to OFF.

BATTERY CONTROL BOARD A in D.C. Equipment Room:

EVALUTOR CUE: The indicated circuit breaker is in OFF.

  • 8. (AOP-49 Att. 3 Step 7) Simulates re-positioning FEED TO 71 LPEADC1 ADMIN CRITICAL STEP BUILDING EMERGENCY LIGHTING DISTRIBUTION SAT/UNSAT
  • FEED TO 7iLPEADC1 PANEL to OFF.

ADMIN BUILDING EMERGENCY LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

  • 9. (AOP-49 Att. 3 Step 7) Simulates re-positioning FEED TO 71 LPESWDC1 CRITICAL STEP SCREENWELL EMERGENCY LIGHTING DISTRIBUTION
  • FEED TO 71 LPESWDC1 PANEL to OFF.

SAT I UNSAT SCREENWELL EMERGENCY LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

I

-6 of 9-

(

STEP STANDARD EVALUATION I COMMENT I

  • 10. {AOP-49 Att. 3 Step 7) Simulates re-positioning FEED TO 71 LPE1 ADMIN CRITICAL STEP BUILDING EMERGENCY LIGHTING DISTRIBUTION
  • FEED TO 71LPE1 ADMIN PANEL to OFF.

SAT I UNSAT BUILDING EMERGENCY LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

EVALUATOR NOTE: The following steps are performed at 71BCB-2B in the D.C. Equipment Room on Admin Building elevation 272.

  • 11. {AOP-49 Att. 3 Step 8) Simulates re-positioning 71 LPEHB1 FEEDWATER CRITICAL STEP Place the following circuit HEATER BAY EMERGENCY LIGHTING DISTRIBUTION SAT I UNSAT breakers in OFF at 71 BCB-2B PANEL to OFF.

BATTERY CONTROL BOARD Bin D.C. Equipment Room:

EVALUTOR CUE: The indicated circuit breaker is in OFF.

  • 12. {AOP-49 Att. 3 Step 8) Simulates re-positioning 71 LPERDC3 REACTOR CRITICAL STEP BUILDING EMERGENCY LIGHTING DISTRIBUTION
  • 71 LPERDC3 REACTOR PANEL to OFF.

SATIUNSAT BUILDING EMERGENCY LIGHTING DISTRIBUTION PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

-7 of 9-

STEP STANDARD EVALUATION I COMMENT

  • 13. (AOP-49 Att. 3 Step 8) Simulates re-positioning 71 LPERW1 & 25 ASP-4 CRITICAL STEP RADWASTE BUILDING EMERGENCY LIGHTING AUX
  • 71 LPERW1 & 25 ASP-4 SHUTDOWN PANEL to OFF.

SAT I UNSAT RADWASTE BUILDING EMERGENCY LIGHTING AUX SHUTDOWN PANEL EVALUTOR CUE: The indicated circuit breaker is in OFF.

EVALUATOR: Terminate the task at this point.

Task Standard: Station Blackout load shedding actions for Main Generator depressurization, Emergency Seal Oil pump, and Battery Control Boards A and Bare completed.

-8 of 9-

HANDOUT

  • A station blackout is in progress.
  • AOP-49, Station Blackout, Attachment 3 is in progress.
  • The Control Room has completed steps 1-4.
  • Other Operators have been dispatched to perform step 5 and step 9.

The CRS has directed that you perform the in-plant actions of AOP-49 Attachment 3 Steps 6, 7, and 8. This is a time critical task. Your time starts now.

-9 of 9-

ENTERGY NUCLEAR NORTHEAST JOB PERFORMANCE MEASURE S/RO 14-1 NRC K TASK TITLE: Swap CRD Pump Suction Filters APPL. TO JPM NUMBER REV: DATE: NRC KIA SYSTEM NUMBER: 239003 A4.01 (3.2/3.2)

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME:

- Minutes SUBMITTED: OPERATIONS REVIEW:

APPROVED:

*~--------------------------------------

CANDIDATE NAME:

JPM Completion 1Zl Simulated D Performed Location: 1Z1 Plant D Simulator

"'TE PERFORMED: TIME TO COMPLETE: Minutes

~**

PERFORMANCE EVALUATION: D Satisfactory D Unsatisfactory

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

COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

JOB PERFORMANCE MEASURE RECORD AND CHECKLIST S/RO 14-1 NRC K TASK TITLE: Swap CRD Pump Suction Filters APPL. TO JPM NUMBER Current Update: By:

Date lnt Outstanding Items D Technical Review [] Additionallnformation D Questions and Answers [] Validation 0 Procedural Change Required ~~ None Comments:

Current Update: By:

Date Int.

Previous Revision Date:

-2 of 7-

JOB PERFORMANCE MEASURE REQUIRED TASK INFORMATION S/RO 14-1 NRC K TASK TITLE: Swap CRD Pump Suction Filters APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. None II. REFERENCES A. OP-25, Control Rod Drive Hydraulic System Ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. Provide a working copy of OP-25 Section G.11 .

.; . EVALUATOR NOTES A. The candidate should, at a minimum, observe the change in equipment status light indication when equipment is operated.

B. If simulating this task, then inform the candidate that the conditions of each step need only be properly identified and not actually performed.

C. The candidate should demonstrate proper use of HU tools such as procedure use, self checking, place keeping and three-point communication.

VI. TASK CONDITIONS A. The plant is operating at 100% power.

B. The B CRD pump suction filter is in service and indicates 1 psid on 03PIS-246.

-3 of 7-

  • - CRITICAL STEP VII. INITIATING CUE Inform the candidate, "The CRS has directed that you swap CRD pump suction filters per OP-25 Section G.11."

STEP STANDARD EVALUATION I COMMENT

1. Obtain a controlled copy of Obtains a copy of OP-25 Section G.11 from the evaluator. SAT I UNSAT OP-25 Section G.11.

EVALUATOR: Provide Candidate a current copy of OP-25 Section G.11.

2. (OP-25 Step G.11.2) Notify Contacts Radiation Protection and informs them of SAT I UNSAT Radiation Protection that evolution.

potentially radioactive water will be vented from CRD pump suction filter. EVALUATOR CUE: Radiation Protection has been informed. They have given you permission to proceed.

3. (OP-25 Step G.11.3) Perform Observes inlet isolation valve 03CRD-151A open (by stem SAT I UNSAT the following for the filter to be position or by simulating rotating valve slightly in the placed in service: clockwise direction).

(OP-25 Step G.11.3.a) Verify EVALUATOR CUE: The indicated valve is open (may state open inlet isolation valve: either stem position is full up or handwheel rotates in indicated direction).

-4 of 7-

STEP STANDARD EVALUATION I COMMENT

  • 4. (OP-25 Step G.11.3.b) Crack Simulates cracking open vent valve 03CRD-400A by CRITICAL STEP open vent valve: rotating handwheel slightly counterclockwise. SAT I UNSAT
  • 03CRD-400A (CRD water pump A suet filter A vent EVALUATOR CUE: The indicated valve handwheel has valve) rotated in the indicated direction. Water is flowing from the vent and is free of air.

EVALUATOR NOTE: The vent piping drains to a location between the CRD pumps.

  • 5. (OP-25 Step G.11.3.c) WHEN Simulates closing vent valve 03CRD-400A by rotating CRITICAL STEP water flowing from vent is free handwheel fully clockwise. SAT I UNSAT of air, close vent valve.

EVALUATOR CUE: The indicated valve handwheel has rotated in the indicated direction and stopped. Water flow from the vent has stopped.

  • 6. (OP-25 Step G.11.3.d) Slowly Simulates slowly opening outlet isolation valve 03CRD- CRITICAL STEP open outlet isolation valve: 152A by rotating handwheel fully counterclockwise. SAT I UNSAT
  • 03CRD-152A (CRD water EVALUATOR CUE: The indicated valve handwheel has pump A suet filter A outlet rotated in the indicated direction and stopped.

isol valve)

-5 of7-

STEP STANDARD EVALUATION I COMMENT

  • 7. (OP-25 Step G.11.4) Close Simulates closing outlet isolation valve 03CRD-152B by CRITICAL STEP outlet isolation valve for the rotating handwheel fully clockwise. SAT I UNSAT filter to be removed from service.

EVALUATOR CUE: The indicated valve handwheel has rotated in the indicated direction and stopped.

EVALUATOR: Terminate the task at this point.

Task Standard: The A CRD pump suction filter is placed in service and the B CRD pump suction filter is removed from service.

-6 of 7-

HANDOUT

  • The plant is operating at 100% power.
  • The 8 CRD pump suction filter is in service and indicates 1 psid on 03PIS-246.

The CRS has directed that you swap CRD pump suction filters per OP-25 Section G.11.

-7 ofl-

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-1 Examiners: Operators:

Initial Conditions: Reactor power is approximately 85% during a power reduction. Service Water Pump B is out of service for maintenance. SRV J is inoperable. L44 is cross-connected to L43.

Turnover: Restore L44 to the normal power source. Then continue power reduction to 75% with Recirculation flow.

Event Malf. Event Event No. No. Type* Description N- Restore L44 to Normal Power Source 1 N/A BOP, SRO OP-46A R- Reduce Power to 75% with Recirculation Flow 2 N/A ATC, SRO OP-65, RAP-7.3.16 Remote HPCI Aux Oil Pump Power Supply Loss 3 C-SRO HP15 ARP 09-3-3-38, Technical Specifications ED21 C- L-16 Electrical Fault and Drywell Cooling Fan 4A Fails to Auto-Start 4 BOP, Override SRO ARP 09-8-3-29, Technical Specifications FW05:B Feedwater Pump B High Vibration and Pump Trip 5 C-All FW01:B ARP 09-6-4-18, AOP-41, AOP-8 FW05:A Feedwater Pump A High Vibration and Pump Trip 6 C-All FW01:A ARP-09-6-4-31, AOP-1, EOP-2 Coolant Leak in Drywell 7 RR15:A M-All EOP-2, EOP-4 C- RHR Pumps Fail to Automatically Start 8 RH14 BOP, SRO EOP-4 C- Trip of All Condensate Pumps FW19:

9 ATC, (A-C) EOP-2 SRO

  • (N)ormal (R)eactivity, (l)nstrument, (C)omponent, (M)aior

Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-1

1. Total malfunctions (5-8) 7 Events 3, 4, 5, 6, 7, 8, 9
2. Malfunctions after EOP entry (1-2) 2 Events 8, 9
3. Abnormal events (2-4) 3 Events 4, 5, 6
4. Major transients (1-2) 1 Event7
5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-4
6. EOP contingencies requiring substantive actions (0-2) 2 EOP-2 Alternate Level Control Leg EOP-2 Emergency Depressurization Leg
7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.

CT-2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization before Reactor water level lowers below -19", in accordance with EOP-2.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI-14-1 NRC EXAMINATION SCEAARIO 2 TITLE: LOI-14-1 NRC EXAMINATION SCENARIO 2 SCENARIO NUMBER: NRC2 PATH: STAND ALONE:

Validation: ~"" -:2:- ~ Training: £~ Operations: --=t_C_r_~----

r-------~---------.----~----------~--~--------------------~

CANDIDATES ATC SOP LOI-14-1 NRC Examination Scenario 2 Page 1 of 23

RECORD OF CHANGES 1*. SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 7/9/13 LOI-14-1 NRC Exam New Scenario T. Hooper ~~ t~J-1!-,/

LOI-14-1 NRC Examination Scenario 2 Page 2 of 23

A. TITLE: LOI-14-1 NRC EXAMINATION SCENARIO 2 B. SCENARIO SETUP:

1. IC-62
2. Special Instructions:
a. The Plant is operating at approximately 85% power.
b. Service Water pump B is out of service for maintenance.
c. SRV J is inoperable.
d. L44 is cross-connected to L43.
3. Preset Conditions:
a. Preset, M:SW05:B, Service Water Pump B Trip
b. Preset, M:AD07:1, Rx Press Relief Vlv (2E-RV2-71J)
c. Preset, OL:AD ZL0271J(1) (SRV J green light), OFF
d. Trigger 1, R:HP15, 23-P-150 HP Aux LO Pump Ckt Bkr, OPEN
e. Trigger 2, M:ED21 :C, 600VAC Emerg Bus 11600 Failure
f. Trigger 3, M:FW05:B, Rx Feedwtr Pmp B High Vibration
g. Trigger 4, M:FW05:A, Rx Feedwtr Pmp A High Vibration
h. Trigger 5, M:RR15:A, Coolant (A) Leakage Inside Primary Containment, ramp=12 minutes, 25%
i. Trigger 6, M:FW19:A, Condensate Pmp 33P8A Trip
j. Trigger 6, M:FW19:B, Condensate Pmp 33P8B Trip, delay=7 seconds
k. Trigger 6, M:FW19:C, Condensate Pmp 33P8C Trip, delay=12 seconds I. Preset, M:RH14, LPCI Failure to Auto Initiate
m. Trigger 14, M:FW01 :B, Rx Feedwater Pmp B Trip
n. Trigger 15, M:FW01:A, Rx Feedwater Pmp A Trip, delay=30 seconds
o. Trigger 30, OS: PC ZDI11 DWCB02, Drywell Cooling Fan, ON (may show as preset in snapped IC)
p. Trigger 30, OS:PC ZDI11 DWCC02, Drywell Cooling Fan, ON (may show as preset in snapped IC)
q. Trigger 30, OS:PC ZDI11 DWCD02, Drywell Cooling Fan, ON (may show as preset in snapped IC)
r. Event Trigger 6, Action: None, Command: mmf rr15:a (0 0) 40 1:00 25
s. Event Trigger 14, Action: fwv34vd10~~(2)>9, Command: None
t. Event Trigger 15, Action: zdi5as1 (1 )===1, Command: None
u. Event Trigger 30, Action: ic_ready_to_run==1, Command: None
4. Consumable Forms and Procedures:

+ AOP-1

+ AOP-8

+ AOP-41 LOI-14-1 NRC Examination Scenario 2 Page 3 of 23

C. SCENARIO

SUMMARY

I The scenario will begin at approximately 85% power with Service Water pump B out of service for maintenance and SRV J inoperable. The crew will begin the shift by restoring Bus L44 to the normal power source per OP-46A. The crew will then continue by lowering Reactor power to 75% with Recirculation flow.

Power will be lost to the HPCI Auxiliary Oil pump. This will render HPCI inoperable for the remainder of the scenario. The SRO will determine the Technical Specification impact.

L-16 will de-energize due to an electrical fault and Drywell Cooling fan 4A will fail to auto-start. The crew will execute AOP-19A, Loss of Switchgear L 16. The crew will start Drywell Cooling fan 4A. Multiple safety-related electrical loads will lose power, including a Core Spray B injection valve and RHR B containment spray valves. The SRO will determine the Technical Specification impact.

Feedwater pump B will develop a high vibration. The crew may lower Reactor power in anticipation of tripping the pump. When the vibration exceeds 6 mils, the crew will trip the pump. If the crew does not trip the pump by 9 mils, the pump will spuriously trip. A Recirculation run back is likely to occur following the pump trip. The crew will respond to stabilize the plant within the capacity of a single Feedwater pump.

Feedwater pump A will also develop a high vibration. Tht:! crew will scram the Reactor as the Feedwater pump vibration approaches the level requiring pump trip. If the crew has not already tripped Feedwater pump A, it will spuriously trip 30 seconds after the scram. With HPCI and both high pressure Feedwater pumps unavailable, the crew will utilize RCIC and CRD to control Reactor water level.

A coolant leak will develop in the Drywell. The crew will attempt to maintain Reactor water level with RCIC and CRD and will eventually need to lower Reactor pressure to inject with Condensate Booster pumps. The crew will place Torus spray in service. This will be complicated by the RHR pumps failing to automatically start and loss of power to RHR B containment spray valves. The crew will be able to manually start RHR pumps and spray using RHR A. When Torus pressure exceeds 15 psig, the crew will also place Drywell spray in service. Drywell spray will lower Drywell pressure such that the Pressure Suppression Pressure curve is not challenged.

All Condensate pumps will sequentially trip and the coolant leak will get worse. With no Condensate injection and the coolant leak exceeding the capacity of RCIC, CRD, and SLC, Reactor water level will lower to the top of active fuel. The crew will execute an Emergency RPV Depressurization and then control low pressure injection systems to restore Reactor water level.

The scenario will be terminated when all control rods are inserted, the Emergency RPV Depressurization is in progress, and Reactor water level is controlled above 0".

LOI-14-1 NRC Examination Scenario 2 Page 4 of 23

Shift Turnover The Plant is operating at approximately 85% power during a power reduction.

Service Water pump B is out of service for maintenance.

SRV J is inoperable.

L44 is cross-connected to L43.

When you take the shift:

1. Restore L44 to the normal power source per OP-46A Section G.12.4. The procedure is in progress up to step G.12.4.d.
2. Then, lower Reactor power to 75% using Recirculation flow.

LOI-14-1 NRC Examination Scenario 2 Page 5 of 23

Critical Tasks/Standards Critical Task #1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.

Critical Task #2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization before Reactor water level lowers below

-19", in accordance with EOP-2.

LOI-14-1 NRC Examination Scenario 2 Page 6 of 23

EVENT NO. EVENT SEQUENCE

1. Restore L44 to Normal Power Source (Normal: BOP, SRO)
2. Reduce Power to 75% with Recirculation Flow (Reactivity: ATC, SRO)

HPCI Aux Oil Pump Power Supply Loss (Component: SRO) 3.

(Tech Spec: SRO)

L-16 Electrical Fault and Drywell Cooling (Component: BOP, SRO) 4.

Fan 4A Fails to Auto-Start (Tech Spec: SRO)

5. Feedwater Pump B High Vibration and Pump Trip (Component: All)
6. Feedwater Pump A High Vibration and Pump Trip (Component: All)
7. Coolant Leak in Drywell (Major: All)
8. RHR Pumps Fail to Automatically Start (Component: BOP, SRO)
9. Trip of All Condensate Pumps (Component: ATC, SRO)

D. TERMINATION CUES:

  • Emergency RPV Depressurization is in progress
  • Reactor water level is controlled above 0" LOI-14-1 NRC Examination Scenario 2 Page 7 of 23

~abi>!MroR .Acr1o P' d '-"'-' :c- - -_,-- ~, , , ' lt-JoAAi TS/BVALUAltbN Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow I All no more than five minutes for panel walkdown

  • Walkdown the control panels and assume the watch Event 1 I SRO SAT I UNSAT INA Restore L44 to Normal Power Source
  • Perform Crew Brief
  • Direct BOP to restore L44 to the normal power source per OP-46A Section G.12.4 BOP SAT I UNSAT INA
  • Ensure closed L 14 L24 L34 L44 4KV FOR BKR 10440
  • Place L43-L44 TIE SYNCH SW switch in ON
  • WHEN incoming and running voltages are matched, AND synchroscope is at approximately 12 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, to perform each breaker operation:

o Close L44 600V FOR BKR 14402 o Open L43-L44 TIE BKR 14304 o Place L43-L44 TIE SYNCH SW switch in OFF and remove handle LOI-14-1 NRC Examination Scenario 2 Page 8 of 23

JisJSJftNQ~D Event 2 SRO SAT I UNSAT INA Reduce Power to 75% with Recirculation Flow

  • Direct ATC to lower power to 75% with Recirc flow
  • Provide oversight for reactivity manipulation ATC SAT I UNSAT INA
  • Lower Recirc flow alternately with RWR MG A(B) SPEED CNTRL
  • Monitor APRMs, CTP, Recirc flow, Reactor water level LOI-14-1 NRC Examination Scenario 2 Page 9 of23

~qcQ\~AtJIVITY I*POSITtciN Event 3 BOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 1

  • Recognize I report 09-3-3-38, HPCI AUX OIL PMP OVERLOAD OR CNTRL PWR LOSS HPCI Aux Oil Pump Power Supply Loss
  • Recognize I report loss of power to HPCI Auxiliary Oil pump SRO SAT I UNSAT INA Role Play:
  • Acknowledge report If dispatched to investigate, wait 2 minutes and then report
  • Direct ARP response that the circuit breaker for the

LOI-14-1 NRC Examination Scenario 2 Page 10 of 23

Event4 ATCIBOP SATIUNSATINA On Lead Examiner Cue:

ACTIVATE TRIGGER 2

  • Recognize I report loss of L-16 Drywell Cooling Fan 4A Fails
  • Recognize I report loss of Drywell Cooling fans and failure of to Auto-Start Drywell Cooling fan 4A to auto-start SRO SAT I UNSAT INA
  • Acknowledge reports
  • Determine most limiting Technical Specification entry is LCO 3.8.7 Condition A, which requires restoring L-16 to operable status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

LOI-14-1 NRC Examination Scenario 2 Page 11 of 23

Role Play: BOP SAT/UNSAT/NA If dispatched to investigate, wait 2 minutes, then report

  • Executes AOP-19A, Loss of Switchgear L 16 that the L-16 supply breaker o Attempt to maintain drywell pressure by controlling drywell (11602) is tripped and appears temperature as follows:

to be damaged.

  • Ensure running Drywell Cooling Fans 68FN-2A, 2C, 4A, 4C
  • Consider initiating Torus Vent per OP-37

o Ensure running, Standby Treatment System "A" per OP-20 o Depress RB VENT ISOL A pushbutton at 09-75 o Verify Reactor Building Isolation per Section G of OP-51A, refer to Attachment 1 for de-energized valves o Refer to Attachment 1 for affected loads o Refer to Attachment 2 for multiple alarms associated with L161oads o Consider shutting down the following systems:

  • Fuel Pool Cooling System o Direct Electricians to measure "B" LPCI Inverter Battery 71 BAT-3B parameters every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LOI-14-1 NRC Examination Scenario 2 Page 12 of 23

Event 5 BOP/ATC SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

  • Recognize I report rising Feedwater pump B vibrations SRO SAT I UNSAT INA Note:
  • Acknowledge report The ARP directs tripping Feedwater pump B if vibration
  • Direct ARP response reaches 6 mils. There is no
  • May direct emergency power reduction with Recirculation flow automatic trip on vibration, and/or CRAM rods however the pump will spuriously trip in this scenario
  • Direct trip of Feedwater pump B if vibration reaches -9 mils.

BOP SAT I UNSAT INA Note:

  • Execute ARP 09-6-4-18 Recirculation pumps will likely run back to the 44% limiter due o Monitor vibration level and trend to only one Feedwater pump o When vibration approaches/exceeds 6 mils, trip Feedwater operating and Reactor water pump B level lowering to 196.5".

Role Play: ATC SAT I UNSAT INA If dispatched as operator to

  • Lower Reactor power with Recirculation flow and/or CRAM investigate vibrations, wait 2 rods, as required I directed minutes, then report that Feedwater pump B is vibrating significantly, but there is no obvious cause.

LOI-14-1 NRC Examination Scenario 2 Page 13 of 23

Event& BOP/ATC SAT I UNSAT INA On Lead Examiner Cue:

  • Recognize I report EPIC alarms ACTIVATE TRIGGER 4 Feedwater Pump A High
  • Recognize I report rising Feedwater pump A vibrations SRO SAT I UNSAT INA Note:
  • Acknowledge reports The ARP directs tripping Feedwater pump A if vibration
  • Direct ARP response reaches 6 mils. There is no

The pump will trip in this

  • Enter AOP-1 (Reactor Scram) scenario 30 seconds after the
  • Enter EOP-2 (RPV Control) on low Reactor water level Mode Switch is placed in SHUTDOWN. If the crew
  • Direct Reactor water level controlled 180-220" using does not take action and Condensate, RCIC, and/or CRD directed by lead examiner, manually activate TRIGGER
  • Direct Reactor pressure controiied 800-1000# using Turbine 15 to trip Feedwater pump A. Bypass Valves
  • May direct Reactor depressurization to inject with Condensate BOP SAT I UNSAT INA Role Play:
  • Execute ARP 09-6-4-11 If dispatched as operator to investigate vibrations, wait 2 o Monitor vibration level and trend minutes, then report that o If vibration approaches/exceeds 6 mils, trip Feedwater Feedwater pump A is vibrating pump A significantly, but there is no obvious cause.
  • Control Reactor water level 180-220" using Condensate, RCIC, and/or CRD LOI-14-1 NRC Examination Scenario 2 Page 14 of 23

ATC SAT I UNSAT INA

  • Place RX MODE switch in SHUTDOWN
  • Observe Reactor power lowering
  • Ensure closed SDIV vent and drain valves
  • Verify 4KV loads transfer to reserve power
  • May begin Reactor depressurization LOI-14-1 NRC Examination Scenario 2 Page 15 of 23

Events 7, 8, & 9 BOPIATC SAT I UNSAT INA On Lead Examiner Cue:

  • Recognize I report degrading Primary Containment conditions ACTIVATE TRIGGER 5 (leakage, temperature, pressure)

Coolant Leak in Drywell, RHR Pumps Fail to Automatically

  • Recognize I report lowering Reactor water level Start, Trip of All Condensate Pumps Critical Task #1 Given a coolant leak inside the Containment, the crew will Pass I Fail spray the Drywall, in accordance with EOP-4.

Drywell spray in service Critical Task #1 Standard:

Critical Task #2 Given a coolant leak, a loss of high pressure injection Pass I Fail systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization before Reactor water level lowers below -19", in accordance with EOP-2.

7 ADS valves open.

Critical Task #2 Standard:

LOI-14-1 NRC Examination Scenario 2 Page 16 of 23

SRO SAT I UNSAT INA Booth Operator:

  • Enter AOP-39 (Loss of Coolant)

When the crew has completed placing Drywell spray in

  • Direct Control Room and Relay Room Ventilation isolated per service and directed by lead OP-558 Section G within 30 minutes examiner, activate TRIGGER
  • Direct TSC filtered ventilation started per Section D of OP-598 6 to trip Condensate pumps within 60 minutes and ramp up to the coolant leak size.
  • Re-enter EOP-2 (RPV Control) on high Drywell pressure
  • May direct Core Spray and RHR injection terminated and When directed to place prevented per EP-2 Control Room, Relay Room, and/or TSC filtered ventilation
  • When Primary Containment pressure exceeds 2. 7 psig and in service, acknowledge before Torus pressure exceeds 15 psig, direct initiation of direction. Torus Spray
  • Acknowledge failure of RHR pumps to automatically start and direct manual start
  • May direct Reactor pressure reduction to inject with Condensate Booster pumps
  • When Torus pressure exceeds 15 psig:

o Verify Recirculation pumps tripped o Direct trip of Drywell cooling fans o Direct initiation of Drywell Spray

  • Acknowledge loss of all Condensate pumps
  • Determine Reactor water level cannot be maintained above 0"
  • Enter Alternate RPV Level Control leg of EOP-2
  • Direct override of ADS
  • Direct CRD maximized and SLC injection LOI-14-1 NRC Examination Scenario 2 Page 17 of 23

SRO cont. SAT I UNSAT INA

  • When Reactor water level reaches 0, enter Emergency RPV Depressurization leg of EOP-2
  • Direct opening 7 ADS valves
  • Direct Reactor water level restored and maintained 180-220" using Core Spray and/or LPCI
  • As time allows, directs re-start of Drywell spray ATC I BOP SAT I UNSAT INA
  • Attempt to maintain Reactor water level with RCIC and CRD
  • Recognize I report leakage exceeds capacity of RCIC and CRD
  • May inject using Condensate Booster pumps
  • Initiate Torus spray:

o Place SPRAY CNTRL 10A-S17A switch to MANUAL, spring return to normal o Verify white SPRAY PERM 1OA-DS67A light is on o Ensure available RHR pumps in RHR Loop A are running (recognize/report failure to automatically start) o Open RHR TEST TORUS CLG & SPRAY 10MOV-39A o Throttle TORUS SPRAY INBD VLV 10MOV-38A to establish desired torus spray flow rate o WHEN RHR Loop A flow is GREATER THAN 1500 gpm, ensure closed MIN FLOWVLV 10MOV-16A LOI-14-1 NRC Examination Scenario 2 Page 18 of 23

N ATC I BOP SAT I UNSAT INA (cont.)

  • Initiate Torus spray (cont.):

o Throttle RHR TEST & TORUS CLG 1OMOV-34A(B) to divert excess flow to the torus to maintain > 6,500 gpm RHR Loop A(B) flow with one RHR pump operating or >

13,000 gpm RHR Loop A(B) flow with two RHR pumps operating o Establish RHRSW flow and temperature control:

o Start one of the RHRSW pumps o Throttle RHRSW DISCH VLV FROM HX A(B) 10MOV-89A(B) to establish 2500 to 4000 gpm o Start the second RHRSW pump if desired o Throttle RHRSW DISCH VLV FROM HX A( B) 1OMOV-89A(B) to establish 2500 to 4000 gpm per RHRSW pump o IF drywell or torus sprays are in service, THEN establish 4000 gpm per RHRSW pump o Close HX A( B) BYP VLV 1OMOV-66A(B)

Note:

When RPV water level lowers

  • Ensure Recirc pumps tripped below 59.5", Torus and
  • Ensure Drywell Cooling fans tripped Drywell Spray are automatically secured as LPCI
  • Initiate Drywell spray: Critical Task #1 receives an initiation signal. o Place SPRAY CNTRL 10A-S17A(B) switch to MANUAL, The SRO will direct Torus and spring return to normal Drywell Spray re-established at a later time. o Verify white SPRAY PERM 1OA-DS67 A(B) light is on o Ensure available RHR pumps in RHR Loop A(B) are running o Open OW SPRAY OUTBD VLV 1OMOV-26A(B) o Throttle OW SPRAY INBD VLV 10MOV-31A(B) to establish desired drywell spray flow rate LOI-14-1 NRC Examination Scenario 2 Page 19 of 23

SAT I UNSAT INA

  • Recognize I report loss of all Condensate pumps
  • Recognize I report lowering Reactor water level
  • Override ADS:

o Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE o Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE o Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm o Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on

  • Initiate SLC injection Note:
  • Open 7 ADS valves Critical Task #2 due to loss of L-16.
  • Restore and maintain Reactor water !eve! 180-220" using available injection systems

o Throttle 14MOV-12A

  • Control LPCI injection:

o Throttle 1OMOV-27A( B) o Secure RHR pumps if needed Termination Criteria:

  • Emergency RPV Depressurization is in progress
  • Reactor water level is controlled above 0" LOI-14-1 NRC Examination Scenario 2 Page 20 of 23

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 85% power during a power reduction.

Service Water pump 8 is out of service for maintenance.

SRV J is inoperable.

L44 is cross-connected to L43.

Vvhen you take the shift:

1. Restore L44 to the normal power source per OP-46A Section G.12.4. The procedure is in progress up to step G.12.4.d.
2. Then, lower Reactor power to 75% using Recirculation flow.

LOI-14-1 NRC Examination Scenario 2 Page 21 of 23

ATTACHMENT 9.4 REACTIVITY MANEUVER INSTRUCTION FORMS Sheet 1 of 1 Reactivity/monitoring Steps- (site specific control rod movement control sheet format is to be used)

Power Reduction EN-RE-215 Attach 9.4 Today Page 1 of 1 From To Cplg RSCS Init Step Action Rod Method Notes Notch Notch Chk Grp Lower power 1

to 75% RTP - - - RWR NA -

Prepared By: SM Approval: Vcwe-Roe-(RxEng) (Shift Manager)

Reviewed By: Bob- T~

(RxEng or SRO)

Stamps CONTROL ROOM OPERATOR LOI-14-1 NRC Examination Scenario 2 Page 22 of 23

ATTACHMENT 9.4 REACTIVITY MANEUVER INSTRUCTION FORMS Sheet 1,of 1 Reactivity/monitoring Steps- (site specific control rod movement control sheet format is to be used)

Power Reduction EN-RE-215 Attach 9.4 Today Page 1 of 1 From To Cplg RSCS Init Step Action Rod Method Notes Notch Notch Chk Grp Lower power 1

to 75% RTP

- - - RWR NA -

Prepared By: SM Approval: Vor.N~'R~

(RxEng) (Shift Manager)

Reviewed By: Bob- [cJt'\.et (RxEng or SRO)

Stamps INDEPENDENT VERIFIER LOI-14-1 NRC Examination Scenario 2 Page 23 of 23

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-:~ Op-Test No.: 14-1 Examiners: Operators:

Initial Conditions: Reactor power is approximately 90%. EHC pump A is out of service for maintenance.

Turnover: Perform ST-3PA, Core Spray Loop A Quarterly Operability Test. The procedure is in progress up to step 8.4.1.

Event Malf. Event Event I No. I No. I T~~e* I Description I N- Perform ST-3PA, Core Spray Loop A Quarterly Operability Test 1 N/A BOP, SRO ST-3PA SLC Squib Loss of Continuity 2 SL04 C-SRO ARP 09-3-3-30, Technical Specifications C- SRV A Inadvertently Opens 3 AD06:A BOP, SRO AOP-36, Technical Specifications ED19:E Fault on 10700 Bus and Service Water Pump A Fails to Auto-Start 4 C-All SW15 AOP-20 Degraded Stator Water Cooling Pump A Flow with Delayed Trip, Remote C- Followed by Degraded Stator Water Cooling Pump B Flow with 5 BOP, Delayed Trip Override SRO ARP 09-7-3-08, OP-11 B, AOP-1 Hydraulic A TWS 6 RD13 M-All EOP-2, EOP-3 RD06 C- CRD Pump Trip and ATWS/RPT Failure to Actuate 7 ATC, RR13 SRO EOP-3, EP-3 I-BOP, MSIVs Isolate 8 RP03 SRO EOP-3

  • l_Nlormal, (Rl_eactivity, _(l)nstrument, _(C)om_gonent, (Mlaj_or

Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 14-1

1. Total malfunctions (5-8) 7 Events 2, 3, 4, 5, 6, 7, 8
2. Malfunctions after EOP entry (1-2) 2 Events 7, 8
3. Abnormal events (2-4) 3 Events 3, 4, 5
4. Major transients (1-2) 1 EventS
5. EOPs entered/requiring substantive actions (1-2) 1 EOP-2
6. EOP contingencies requiring substantive actions (0-2) 1 EOP-3
7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given a failure to scram with Reactor power above 2.5%, the crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

  • Terminating and preventing all RPV injection except SLC, RCIC, and CRD,
  • Tripping Recirculation pumps,
  • Injecting SLC .

CT-2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.

TITLE: LOI-14-1 NRC EXAMINATION SCENARIO 3 SCENARIO NUMBER: NRC3 PATH: STANDALONE Validation: ...= ~ -:7 _____.. _ Training: d~ Operations: _ __;E-::.____;;(_,...;;_ev.;;___ __

LOI-14-1 NRC Examination Scenario 3 Page 1 of 27

RECORD OF CHANGES

      • -~

~:>

LOI-14-1 NRC Examination Scenario 3 Page 2 of 27

A. TITLE: LOI-14-1 NRC EXAMINATION SCENARIO 3 B. SCENARIO SETUP:

1. IC-63
2. Special Instructions:
a. The Plant is operating at approximately 90% power.
b. EHC pump A is out of service for maintenance.
c. Lake temperature is 50°F.
d. Service Water pumps Band Care in service, with A in standby.
3. Preset Conditions:
a. Preset, M:TC02:A, EHC Pump Trip A
b. Trigger 1, M:SL04:A, Standby Liquid Control Squib Loss of Continuity
c. Trigger 2, M:AD06:A, Rx Press Relief Valve (2E-RV-71)
d. Trigger 3, M:ED19:E, Bus 10700 Failure
e. Trigger 4, R:EG05, 94-Y-03, Stator Cooling Pump A Discharge, 68%
f. Trigger 4, OS:EG ZDI11 GSCN01, Stator Water Cool Pmp, TRIP, delay=? minutes
g. Trigger 5, R:EG06, 94-Y-04, Stator Cooling Pump B Discharge, 68%
h. Trigger 5, OS:EG ZDI11GSCN02, Stator Water Cool Pmp, TRIP, delay=4 minutes
i. Trigger 6, M:RD06:A, CRD Hydraulic Pump Trip
j. Trigger 6, M:RP03, Inadvertent Group I Isolation, delay=3 minutes
k. Preset, M:SW15, Service Water Pump A Auto-Start Failure I. Preset, M:RD13:ALL, Control Rod Fa1ilure to Scram
m. Preset, M:RD22:A, West SDV Hydraulic Lock, 100%
n. Preset, M:RD22:B, East SDV HydrauHc Lock, 100%
o. Preset, M:RR13:A, ATWS System Fails to Initiate RWR Pump Trip
p. Preset, M:RR13:B, ATWS System Fails to Initiate RWR Pump Trip
q. Trigger 23, OA:AN941:18, Remote Shutdown Pnl Door Open, ON
r. Trigger 23, M:AD04:A, Rx Press Relief Valve Solenoid Failure A, delay=1 0 sec
s. Trigger 24, R:AD02:A, 'A' SRV Fuse Pull Out, OUT
t. Trigger 26, R:RP20, ARI Test Switch 43SSARI, TEST
u. Trigger 27, R:RH40:A, Relay 10A-K45A Grayboot, REMOVED
v. Trigger 27, R:RH40:B, Relay 10A-K45B Grayboot, REMOVED
w. Trigger 28, R:RD07, 3-56, Charging Water lsol. Valve, 0%
x. Trigger 30, R:EG07, Stator Cooling Local Panel, ACK
y. Event Trigger 1, Action: zdi14as2a(1)==1, Command: None
z. Event Trigger 6, Action: zdi5as1 (1)==1, Command: None
4. Consumable Forms and Procedures:

+ ST-3PA

+ AOP-1

+ AOP-20

+ AOP-36 LOI-14-1 NRC Examination Scenario 3 Page 3 of 27

C. SCENARIO

SUMMARY

I The scenario will begin at approximately 90% power with EHC pump A out of service for maintenance. The crew will begin the shift by performing Core Spray A valve stroke timing per ST-3PA. During the test, a loss of continuity will occur to SLC squib valve A. The SRO will declare one SLC subsystem inoperable and determine the Technical Specification impact.

SRV A will inadvertently open. The crew will execute AOP-36 and close the SRV by removing control power in the field. The crew will place Torus Cooling in service. The SRO will determine the Technical Specification impact.

An electrical fault will cause Bus 10700 to de-energize. The crew will execute AOP-20. Major loads lost include an operating Circulating Water pump, Service Water pump, Condensate pump, and Condensate Booster pump. The standby Service Water pump will fail to auto-start. The crew will manually start the standby Service Water pump, lowering Reactor power to less than 65% using Recirculation flow and CRAM rods, and normalize Control Room controls.

Stator Water Cooling pump A flow will degrade. The crew will execute ARP 09-7-3-08, swap to Stator Water Cooling pump B, and restore flow. If Stator Water Cooling pump A is not secured, it will eventually trip.

Stator Water Cooling pump B flow will also begin to degrade after being started. With an impending loss of both Stator Water Cooling pumps, the crew will enter AOP-1 and attempt a manual Reactor scram. If Stator Water Cooling pump B is not secured, it will eventually trip.

A hydraulic failure to scram will occur. The crew will enter EOP-2 and transition to EOP-3. Recirculation pumps will fail to trip on an A TWS/RPT signal, requiring the crew to manually trip Recirculation pumps. The crew will also intentionally lower Reactor water level and inject boron.

The in-service CRD pump will trip, requiring the crew to place the standby pump in service to drive control rods with RMCS. With CRD pressure restored, the crew will be able to insert control rods using RMCS or by raising cooling water 0/P.

The scenario will be terminated when control rod insertion is in progress or completed, Reactor power is downscale on APRMs, and Reactor water level is controlled above 0".

LOI-14-1 NRC Examination Scenario 3 Page 4 of 27

Shift Turnover The Plant is operating at approximately 90% power.

EHC pump A is out of service for maintenance.

When you take the shift, perform ST-3PA, Core Spray Loop A Quarterly Operability Test. The procedure is in progress up to step 8.4.1. Technical Specification 3.5.1 Condition A has been entered (7 day LCO).

LOI-14-1 NRC Examination Scenario 3 Page 5 of27

Critical Tasks/Standards Critical Task #1: Given a failure to scram with Reactor power above 2.5%, the crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

  • Terminating and preventing all RPV injection except SLC, RCIC, and CRD,
  • Tripping Recirculation pumps,

Critical Task #2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.

LOI-14-1 NRC Examination Scenario 3 Page 6 of 27

EVENT NO. EVENT SEQUENCE Perform ST-3PA, Core Spray Loop A Quart.erly (Normal: BOP, SRO) 1.

Operability Test

2. SLC Squib Loss of Continuity (Component: SRO)
3. SRV A Inadvertently Opens (Component: BOP, SRO)

Fault on 10700 Bus and Service Water Pump A (Component: All) 4.

Fails to Auto-Start Degraded Stator Water Cooling Pump A Flow with (Component: BOP, SRO) 5.

Delayed Trip Degraded Stator Water Cooling Pump B Flow with (Component: ATC, SRO) 6.

Delayed Trip

7. Hydraulic A TWS (Major: All)

CRD Pump Trip and (Component: ATC, SRO) 8.

ATWS/RPT Failure to Actuate

9. MSIVs Isolate (Instrument: BOP, SRO)

D. TERMINATION CUES:

  • Reactor power is downscale on APRMs
  • Reactor water level is controlled above 0" LOI-14-1 NRC Examination Scenario 3 Page 7 of 27

INSTRU~TO' ACTI\AITY POIIT:10N TANDARD EVA~UATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow I All no more than five minutes for panel walkdown

  • Walkdown the control panels and assume the watch Event 1 I SRO SAT I UNSAT INA Perform ST-3PA, Core Spray Loop A Quarterly Operability
  • Perform Crew Brief Test
  • Open and time OUTBD INJ VLV 14MOV-11A, as time allows LOI-14-1 NRC Examination Scenario 3 Page 8 of27
Uti*

Event 2 BOPIATC SAT I UNSAT INA SLC Squib Loss of Continuity

  • Acknowledge report
  • Executes ARP 09-3-3-30: SAT I UNSAT INA If dispatched to investigate o Determine which valve has lost continuity by checking SLC issue, wait 2 minutes and milliamp meters in back of Panel 09-3 then report that you do not see any obvious problems.

LOI-14-1 NRC Examination Scenario 3 Page 9 of 27

Event 3 BOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 2

SRV A Inadvertently Opens o 09-4-1-16, SRV Leaking o 09-4-2-6, SRV Sonic Mon Alarm Hi

  • Recognize I report SRV A open SRO SAT I UNSAT INA
  • Acknowledge report
  • Enter AOP-36 (Stuck Open Relief Valve)
  • Direct initiation of Torus Cooling

SAT I UNSAT INA Booth Operator:

When dispatched to take SRV A isolation switch to LOCAL, o Direct Operator to place SRV A isolation switch in LOCAL at panel 25ASP-5 wait 2 minutes, then insert Trigger 23 and report task o Determine SRV A closed completion after 10 seconds.

o Direct Operator to remove the four control power fuses for the open SRV at panel 09-45 Booth Operator:

o Direct Operator to place SRV A isolation switch in When dispatched to pull SRV REMOTE at panel 25ASP-5 A fuses, wait 2 minutes, then insert Trigger 24 and report o Monitor Torus water temperature task completion.

  • Initiate Torus Cooling per OP-138 posted attachment:

o Ensure at least one of the RHR pumps is running Booth Operator:

When directed to take SRV A o Open RHR TEST TORUS CLG & SPRAY 1OMOV-39A(B) isolation switch to REMOTE, o Throttle RHR TEST & TORUS CLG 1OMOV-34A(B) to wait 2 minutes, then delete establish desired/flow malfunction AD04:A, then delete override AN941 : 18 and o WHEN RHR Loop A(B) fiow is GREATER THAN 1500 report task completion. gpm, ensure closed MIN FLOWVLV 10MOV-16A(B) o Establish RHRSW flow and temperature control Booth Operator:

If directed to verify SRV A o Start one of the RHRSW pumps isolation switch position, insert and remove override o Throttle RHRSW DISCH VLV FROM HX A( B) 1OMOV-AN941 : 18 as needed to 89A(B) to establish 2500 to 4000 gpm simulate opening and closing o Start the second RHRSW pump if desired panel door.

o Throttle RHRSW DISCH VLV FROM HX A( B) 1OMOV-89A(B) to establish 2500 to 4000 gpm per RHRSW pump o Close HX A( B) BYP VLV 1OMOV-66A(B)

LOI-14-1 NRC Examination Scenario 3 Page 11 of 27

1

'~jiCci~ENTSIEVA,~

Event 4 ATCIBOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 3

Fault on 10700 Bus and o 09-8-5-13, BUS 10700 SUPP BKR 10702 TRIP Service Water Pump A Fails to

  • Recognize I report loss of Bus 10700 Auto-Start
  • Acknowledge reports
  • Enter AOP-20 (Loss of 10700 Bus)
  • Direct power reduction to less than 65%
  • Provide oversight for reactivity manipulation Role Play: BOP SAT I UNSAT INA If dispatched to investigate Bus 10700, wait 2 minutes,
  • Execute AOP-20:

then report that the Bus 10700 o Coordinate with A TC to lower Reactor power to < 65%

supply breaker (10702) is o Verify closed CIRC WTR PUMP DISCH VLV 36MOV-100C tripped and appears to be damaged. o Monitor condenser vacuum o IF only one service water pump is running, AND it is desired to place a second service water pump in service, THEN start second service water pump LOI-14-1 NRC Examination Scenario 3 Page 12 of27

  • oFSefijfp~l]br~~N~stJNQt.~

SAT I UNSAT INA

o Ensure the following pumps are in PULL TO LOCK at panel 09-6:

  • COND BSTR PMP C 33P-9C o Place NSS TO BUS 10700 BKR 10702 in PULL TO LOCK ATC SAT I UNSAT INA
  • Lower Reactor power to< 65%:

o Lower Recirculation flow to -55% of rated o Insert CRAM rods LOI-14-1 NRC Examination Scenario 3 Page 13 of 27

POSfliQN:

EventS BOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 4

  • Acknowledge report
  • Direct ARP response
  • Execute ARP 09-7-3-08: SAT I UNSAT INA Note:

o Verify running or start on of the following pumps at panel Stator Water Cooling flow is 09-7:

expected to stabilize below the alarm setpoint of 446 gpm, but o STATOR WTR COOL PMP 94P-15A above the deiayed Turbine trip o STATOR WTR COOL PMP 94P-i58 setpoint of 421 gpm.

o Dispatch an operator to Hydrogen & Stator Cooling Control Panel 94HSC to report cause of annunciator Role Play:

If dispatched to investigate, o Monitor EPIC alarms associated with Stator Water System wait 2 minutes, then report o Determine cause of alarm and respond per ARP 09-7-3-8, that Stator Water Cooling conditions 1 through 10, as applicable pump A is vibrating and extremely loud; local Stator

Water Cooling flow is low. o Start STATOR WTR COOL PMP 94P-15B at panel 09-7 o Stop STATOR WTR COOL PMP 94P-15A which was Booth Operator: running prior to starting the standby pump at panel 09-7 If dispatched to acknowledge I o Verify system parameters are normal per Section E reset local SWC alarm, wait 2 minutes, activate Trigger 30, then report task completion.

LOI-14-1 NRC Examination Scenario 3 Page 14 of27

";~:r~ ..w Event 5 cont. BOPIATC SAT I UNSAT INA On Lead Examiner Cue:

  • Acknowledge reports Recirculation flow should already be near the minimum
  • Direct ARP response of 55% and all 3 CRAM rod
  • May direct control rod insertion per shutdown sequence groups should be inserted, therefore the crew's ability to
  • Direct Reactor scram rapidly lower Reactor power in

BOP SAT I UNSAT INA Note:

  • Execute ARP 09-7-3-08:

Stator Water Cooling flow is expected to stabilize below the o Verify running or start on of the following pumps at panel alarm setpoint of 446 gpm, but 09-7:

above the delayed Turbine trip o STATOR WTR COOL PMP 94P-15A setpoint of 421 gpm.

o STATOR WTR COOL PMP 94P-15B Role Play: o Dispatch an operator to Hydrogen & Stator Cooling Control If dispatched to investigate, Panel 94HSC to report cause of annunciator wait 2 minutes, then report o Monitor EPIC alarms associated with Stator Water System that Stator Water Cooling o Determine cause of alarm and respond per ARP 09-7-3-8, pump B is vibrating and conditions 1 through 10, as applicable extremely loud; local Stator Water Cooling flow is low.

  • Enter AOP-1 LOI-14-1 NRC Examination Scenario 3 Page 15 of 27

-:;~_-~:>-:- ': -r't-':- i:f:__

-: -\ __ ,, , " ~:c :-:, ,'LJ-

~~ft~I!T~Mft~RD~

'JWSffliJC'rOR ~QTIVIT:f\"

c < ',- , --'-~~- ' - ; <':i ATC SAT I UNSAT INA

are scripted in the next event.

  • Recognize I report failure to scram LOI-14-1 NRC Examination Scenario 3 Page 16 of 27

.,S-~"~;,,Sll ACJt~~**** *~~~.~EN1iSLEVALil)!ift8ft Events 6, 7, & 8 Hydraulic A TWS, CRD Pump Trips and ATWS/RPT Fails to Initiate, MSIVs Isolate Critical Task #1 Given a failure to scram with Reactor power above 2.5%, the Pass I Fail crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

  • Terminating and preventing all RPV injection except SLC, RCIC, and CRD,
  • Tripping Recirculation pumps,

Terminate and prevent all injection except SLC, RCIC and Critical Task #1 Standard:

CRD per EP-5.

AND/OR Trip both Recirculation pumps.

AND/OR Initiate SLC.

Critical Task #2 Given a failure to scram, the crew will initiate Control Rod Pass I Fail insertion, in accordance with EOP-3.

Perform EP-3 Backup Control Rod Insertion Actions to insert Critical Task #2 Standard:

control rods.

LOI-14-1 NRC Examination Scenario 3 Page 17 of 27

SRO SAT I UNSAT INA

  • Acknowledge report
  • Enter EOP-2 (RPV Control) on Reactor power above 2.5% or unknown when a scram is required
  • Determine the Reactor will NOT remain shutdown under all conditions without boron
  • Direct bypassing MSIV low RPV water level isolation interlocks per EP-2
  • Direct terminate and prevent all injection except SLC, RCIC and CRD per EP-5
  • Direct Reactor water level controlled between -19" and 11 0" with only Group 1 Water Level Control Systems (Condensate/Feedwater, CRD, HPCI, RCIC, LPCI)

Note:

Turbine Bypass Valves will

  • Direct Reactor pressure controlled 800-1 000 psig with Turbine only be available until the Bypass Valves and SRVs, as required MSIVs isolate 3 minutes after
  • Ensure ADS overridden
  • Acknowledge CRD pump trip Note:
  • May enter AOP-69 (Control Rod Drive Pump Trouble), as time Based on timing of events, the permits scenario may be terminated prior to the crew raising
  • Direct start of standby CRD pump Reactor water level to the
  • Wait until SLC tank level drops by 26%:

normal control band.

o Direct restoring and maintaining Reactor water level to 177-222.5 inches LOI-14-1 NRC Examination Scenario 3 Page 18 of 27

TRVtJf~ ACTI~I"m ~~~SITION;~

ATC SAT I UNSAT INA

o Ensure Rx Mode Switch in SHUTDOWN o Ensure ARI initiated o Run Recirc flow to minimum o Determine Rx power greater than 2.5%

o Ensure Recirc pumps tripped Critical Task #1 o Override ADS o Place ADS LOGIC OVERRIDE & RESET LOGIC A 2E-S2A in OVERRIDE o Place ADS LOGIC OVERRIDE & RESET LOGIC B 2E-S2B in OVERRIDE o Verify annunciator 09-4-1-27 ADS OVERRIDE SW IN OVERRIDE is in alarm o Verify white ADS LOGIC OVERRIDDEN 2E-DS10 light is on LOI-14-1 NRC Examination Scenario 3 Page 19 of 27

SAT I UNSAT INA o Obtain CRS concurrence to inject SLC o Inject SLC Critical Task #1 Booth Operator: o Verify white SQUIB VLVS READY lights are on When directed to reset ARI, o Note level on TK LVL 11 Ll-66 wait 2 minutes, then activate o Place SLC pup keylock switch in START SYS-A or Trigger 26 and report task START SYS-B completion.

o Verify red SLC pump running light is on o Verify SLC pump discharge pressure on DISCH Booth Operator: PRESS 11 Pl-65 is greater than or equal to RPV pressure When directed to install RPS jumpers, wait two minutes, run o Verify the following:

RPSjumpers.cae, then report o CLN UP SUCT 12MOV-18 is closed task completion.

o CLN UP RETURN ISOL VALVE 12MOV-69 is closed Booth Operator: e Insert !R~.4s and SR~.4s If directed to close 03CRD-56,

  • Range IRMs as necessary wait two minutes, then Critical Task #2 activate Trigger 28 and
  • Perform EP-3 Backup Control Rod Insertion Actions report task completion. o Direct NPO to reset ARI per Subsection 5.4 o May insert rods using RMCS per Subsection 5. 7:

o Ensure ARI is reset Booth Operator:

If directed to close 03CRD-91, o Place RWM keylock switch in BYPASS wait two minutes, then report o If reactor scram can be reset, then reset reactor scram task completion. as follows:

o Place SDIV HI LVL TRIP switch in BYPASS o Place RX SCRAM RESET switch to GROUP 2&3, then to GROUP 1&4, spring return to NORM LOI-14-1 NRC Examination Scenario 3 Page 20 of27

SAT I UNSAT INA o Verify the following lights are on:

o RPS A SCRAM GROUPS 1, 2, 3, and 4 o RPS 8 SCRAM GROUPS 1, 2, 3, and 4 o Raise CRD drive water differential pressure using one or more of the following methods:

o Closing 03CRD-56, if the scram cannot be reset o Starting second CRD pump o Closing CRD DRV WTR PRESS VLV 03MOV-20 o Raising CRD System flow rate using CRD FLOW CNTRL 03FIC-301 o Select control rod on ROD SEL matrix o Insert control rod using ROD MOVEMENT CNTRL or ROD EMERG IN NOTCH OVERRIDE o May insert rods by raising dP using CRD cooling water per Subsection 5.8:

o May direct NPO to close 03CRD-56 o Direct NPO to close 03CRD-91 o Ensure open CRD DRV WTR PRESS VLV 03MOV-20 o Ensure closed CRD CLG WTR PRESS CNTRL VLV 03MOV-22 o Raise CRD system flow rate to maximum by adjusting CRD FLOW CNTRL 03FIC-301 in automatic or manual

  • Recognize I report trip of CRD pump
  • Start standby CRD pump
  • Report progress of control rod insertion to CRS LOI-14-1 NRC Examination Scenario 3 Page 21 of 27

sti,cT.,RAqTIVI UATION BOP SAT/UNSAT/NA

  • Direct NPO to bypass MSIV low RPV water level isolation Booth Operator: interlocks per EP-2 Section 5.1 When directed to install MSIV low water level jumpers, wait 2
  • Terminate and prevent all injection except SLC, RCIC and J Critical Task #1 minutes, run MSIVLEVEL.cae, CRD per EP-5 then report task completion. o Feedwater o If RFP A is running:

o Ensure RFP A FLOW CNTRL 06-84A is in MAN o Lower RFP A FLOW CNTRL 06-84A to minimum o Ensure open RFP A MIN FLOW 34FCV-135A o If RFP B is running:

o Ensure RFP B FLOW CNTRL 06-848 is in MAN o Lower RFP BFLOW CNTRL 06-848 to minimum o Ensure open RFP B MIN FLOW 34FCV-135B o Ensure closed:

o RFP A DISCH 34MOV-100A o RFP B DISCH 34MOV-100B o Ensure FDWTR STARTUP VLV 34FCV-137 in MANUAL o Ensure closed FDWTR STARTUP VLV 34FCV-137 o HPCI o Trip HPCI by depressing TURB TRIP 23A-S19 pushbutton LOI-14-1 NRC Examination Scenario 3 Page 22 of 27

SAT I UNSAT INA Note: o Core Spray Loop A BOP may delay terminate and o Place 14MOV-11A AUTO ACTUATION BYPASS SW prevent steps for Core Spray 14A-S 16A switch in bypass loop A due to earlier failure of 14MOV-11A. o Verify white 14MOV-11A AUTO ACTUATION BYPASS LT 14A-DS35A light is on o Ensure closed OUTBD INJ VLV 14MOV-11A o Ensure PMP 14P-1A is stopped Booth Operator:

o Core Spray Loop B If directed as NPO to pull grayboot connectors for RHR o Place 14MOV-11BAUTOACTUATION BYPASS SW timers, wait 2 minutes, 14A-S 16B switch in bypass activate Trigger 27, then o Verify white 14MOV-11BAUTOACTUATION BYPASS report task completion. LT 14A-DS35B light is on o Ensure closed OUTBD INJ VLV 14MOV-11 B o Ensure PMP 14P-1B is stopped o RHR Loop A o Place 10MOV-27AAUTO CONTROL BYPASS 10A-S23A o Verify white light above 1OMOV-27A AUTO CONTROL BYPASS 1OA-S23A is on o Ensure closed LPCI OUTBD INJ VLV 10MOV-27A o Ensure RHR Loop A pumps which are not required to be running are stopped LOI-14-1 NRC Examination Scenario 3 Page 23 of27

CPOSitlgtJ BOP cont. SAT I UNSAT INA o RHR Loop B o Place 1OMOV-27B AUTO CONTROL BYPASS 1OA-S23B o Verify white light above 1OMOV-27B AUTO CONTROL BYPASS 1OA-S23B is on o Ensure closed LPCI OUTBD INJ VLV 10MOV-27B o Ensure RHR Loop B pumps which are not required to be running are stopped

  • Report RPV water level is less than 11 0" to CRS
  • Recognize I report closure of MSIVs
  • Control Reactor pressure 800-1000 psig using SRVs
  • Control RPV water level between -19" and 11 0" with only Group 1 Water Level Control Systems (CondensateiFeedwater, CRD, HPCI, RCIC, LPCI) o Feedwater o If any Reactor feed pump is running:

o Ensure feedwater pump discharge pressure is less than RPV pressure by adjusting reactor feed pump speed o Lineup injection flow path by performing on or both of the following:

o Adjusting FDWTR STARTUP VLV 34FCV-137 o Ensure open or throttled open Reactor feed pump discharge valve for running pump (34MOV-1 OOA or B)

LOI-14-1 NRC Examination Scenario 3 Page 24 of27

SAT I UNSAT INA o Control feed flow to RPV by performing any of the following:

o Adjust RFP speed o Adjust FDWTR STARTUP VLV 34FCV-137 o Close feed pump discharge valves o If both Reactor feed pumps are shutdown, and feedwater discharge header pressure is greater than RPV pressure, then control feed flow to RPV by performing one or both of the following:

o Throttling FDWTR STARTUP VLV 34FCV-137 o Throttling one or both of the following valves, only if APRMs are on scale:

o RFP A DISCH 34MOV-100A o RFP B DISCH 34MOV-100B o HPCI o Preparation for injection:

o Ensure SGT is running per OP-20 o Ensure open one of the following valves:

o HPCI GLAND SEAL SUCT 01-125MOV-13A o HPCI GLAND SEAL SUCT 01-125MOV-13B o Ensure HPCI FLOW CNTRL 23FIC-108-1 setpoint is adjusted to minimum o Ensure HPCI FLOW CNTRL 23FIC-108-1 is in AUTO LOI-14-1 NRC Examination Scenario 3 Page 25 of 27

SAT I UNSAT INA o Injection with initiation signal:

o Depress INITIATION SIGIMAN TURB TRIP RESET 23A-S17 pushbutton o Verify annunciator 09-3-3-28 HPCI TURB TRIP SOLENOID ENERGIZED is clear o Verify HPCI auto-initiation o Control HPCI turbine speed in manual or automatic o Periodically verify HPCI turbine speed is greater than 21 00 rpm

  • Begins restoring and I or maintaining Reactor water level to 177-222.5", if directed Termination Criteria:
  • Reactor power is downscale on APRMs
  • Reactor water level is controlled above 0" LOI-14-1 NRC Examination Scenario 3 Page 26 of 27

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 90% power.

EHC pump A is out of service for maintenance.

When you take the shift, perform ST-3PA, Core Spray Loop A Quarterly Operability Test. The procedure is in progress up to step 8.4.1. Technical Specification 3.5.1 Condition A has been entered (7 day LCO).

LOI-14-1 NRC Examination Scenario 3 Page 27 of 27

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-1 Examiners: Operators:

Initial Conditions: Reactor power is approximately 7% during a startup. The Rod Worth Minimizer is bypassed. IRM F is bypassed.

Turnover: Return IRM F to service per OP-16. Then continue power ascension with control rod withdrawals.

Event Malf. Event Event No. No. Type* Descri~tion I N- Return IRM F to Service 1 N/A BOP, SRO OP-16 R- Withdraw Control Rods 2 N/A ATC, SRO OP-65, OP-26 C- Stuck Control Rod 3 RD10 ATC, SRO OP-25 RPS Level Transmitter Fails High 4 RR22:B 1-SRO ARP 09-5-2-60, Technical Specifications CU07 Reactor Water Cleanup Pump Seal Failure, Reactor Water C-5 CU10 BOP, Cleanup Fails to Automatically Isolate SRO ARP-09-3-3-2(12), EOP-5, Technical Specifications CU12 RC06 C- RCIC Inadvertent Initiation and High Bearing Temperature 6 BOP, Override SRO AOP-77, ARP-09-4-*1-15, Technical Specifications RC09 RCIC Steam Leak and Failure to Isolate 7 RC12 M-All EOP-5, AOP-1, EOP-2 Remote RP01A 1-ATC, RPS Fails to Scram, ARI Inserts Control Rods 8

RP01B SRO AOP-1, EOP-2 C- Multiple SRVs Fail to Open 9 ADO? BOP, SRO EOP-2

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-1

1. Total malfunctions (5-8) 7 Events 3, 4, 5, 6, 7, 8, 9
2. Malfunctions after EOP entry (1-2) 2 Events 8, 9
3. Abnormal events (2-4) 3 Events 3, 5, 6
4. Major transients (1-2) 1 Event 7
5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-5
6. EOP contingencies requiring substantive actions (0-2) 1 EOP-2 Emergency Depressurization Leg
7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT -1: Given the plant operating at power with an un-isolable primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.

CT-2: Given an un-isolable primary system discharging into Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT LOI-14-1 NRC EXAMINATION SCENARIO 4 TITLE: LOI-14-1 NRC EXAMINATION SCENARIO 4 SCENARIO NUMBER: NRC4 PATH: STAND ALONE Validation: _;::z;--"' ? ~* Training: ~ Operations: -.L..A_U.=.:...;;~----

~:~-r-*--------..,......,....,------,--,--------.--------.,..........,------......,

CANDIDATES .

CRS ATC BOP LOI-14-1 NRC Examination Scenario 4 Page 1 Clf 20

RECORD OF CHANGES

DATE SOURCE OF CHANGE BRIEF DESCRIPTION OF CHANGE INmATOR REVIEWED 7/23/13 LOI-14-1 NRC Exam New Scenario T. Hooper ")1~

~-,

LOI-14-1 NRC Examination Scenario 4 Page 2 of 20

A. TITLE: LOI-14-1 NRC EXAMINATION SCENARIO 4 B. SCENARIO SETUP:

1. IC-64
2. Speciallnstructions:
a. The Plant is operating at approximately 7% power in STARTUP.
b. The Rod Worth Minimizer is bypasse!d.
c. IRM F is bypassed and selected to range 2.
3. Preset Conditions:
a. Preset, M:RD10:38:15, Control Rod (38-15) Blade Stuck
b. Trigger 1, M:RR22:B, Rx Vessel Scram Level Transmitter, 100%
c. Trigger 2, M:CU07, RWCU Pipe Break Between 12-MOV-15 and 12-MOV-18, 2%
d. Preset, M:CU10, RWCU 12MOV-18 Auto Isolation Failure
e. Preset, M:CU12, RWCU 12MOV-15 Auto Isolation Failure
f. Trigger 3, M:RC06, RCIC System Inadvertent Initiation
g. Trigger 3, OA:AN941 :15, RCIC Turb Gov End Brg Temp Hi, delay=30 seconds, ON
h. Trigger 4, M:RC09, RCIC Steam Line Break, 2.5%
i. Preset, M:RC12, RCIC Isolation Relay, 13A-K15, Failure
j. Preset, M:RP01A, Reactor Protection System Automatic Scram Failure
k. Preset, M:RP01 B, Reactor Protection System Manual Scram Failure I. Preset, M:AD07:B, Rx Press Relief Vlv (2E-RV2-71 B) Fails to Open
m. Preset, M:AD07:F, Rx Press Relief Vlv (2E-RV2-71 F) Fails to Open
n. Preset, M:AD07:G, Rx Press Relief Vlv (2E-RV2-71 G) Fails to Open
o. Preset, M:AD07:1, Rx Press ReliefVIv (2E-RV2-71J) Fails to Open
p. Preset, M:AD07:K, Rx Press Relief Vlv (2E-RV2-71 L) Fails to Open
q. Trigger 25, R:RC13, 13-MOV-15 Circuit Breaker, OPEN
r. Event Trigger 5, Event: zdi1csari==1, Command: imf rc09 (0 0) 8 3:00 2.5
s. Event Trigger 24, Event: rdpdrvdp>300, Command: dmf rd10:38:15
t. Event Trigger 25, Event: zlo13as1 (1 )==1, Command: none
u. Event Trigger 26, Event: rcfm>40, Command: dmf rc06
4. Consumable Forms and Procedures:

+ AOP-1

+ AOP-24

+ AOP-77 LOI-14-1 NRC Examination Scenario 4 Page 3 of 20

C. SCENARIO

SUMMARY

The scenario will begin at approximately 7% power during a startup. The Rod Worth Minimizer is bypassed.

IRM F is bypassed and ready to be returned to service following I&C repairs. The crew will begin by restoring IRM F to service per OP-16 Section E.8.1. Then the crew will continue to raise Reactor power by withdrawing control rods.

The third control rod to be moved, 38-15, will be stuck at its initial position of 04. The crew will enter AOP-24, Stuck Control Rod. The control rod will move once CRD drive water pressure is raised above 300 psig.

Then the crew will continue with control rod withdrawals per the startup sequence.

Reactor water level transmitter, 02-3LT-1 01 B, will fail upscale. This transmitter is one of the inputs to the RPS scram function. With the transmitter failed high, the SRO will determine that it cannot perform its scram function, declare that function inoperable, and determine the Technical Specification impact.

Reactor Water Cleanup pump A develops a seal failure. This will cause at least one Reactor Building area temperature to exceed max normal and require entry into EOP-5, Secondary Containment Control. The Reactor Water Cleanup pumps will eventually trip on high room temperature, but the suction line will fail to automatically isolate. The crew can isolate the leak by manually closing 12MOV-15 and/or 12MOV-18. The SRO will determine the Technical Specification impact of the PCIV automatic isolation failure.

RCIC will inadvertently initiate. The crew will execute AOP-77 in response to the inadvertent start. Once RCIC comes up to near rated flow, the initiation signal will clear, allowing full control of the system. Shortly thereafter, a high bearing temperature will occur. The crew will secure RCIC. The SRO will determine the Technical Specification impact.

RCIC will develop a steam leak. This will cause high area temperatures near RCIC and HPCI. HPCI will automatically isolate, however RCIC will fail to automatically isolate. The crew will be able to close 13MOV-16, however the breaker for 13MOV-15 trip open, preventing isolation of the steam leak. The crew will execute EOP-5. The crew will enter AOP-1 and insert a manual Reactor scram. On the scram attempt, the RPS pushbuttons and Mode Switch will fail to work. The crew will insert control rods by initiating ARI. The crew will enter EOP-2, RPV Control. As Reactor Building area temperatures approach max safe levels, the crew will anticipate Emergency Depressurization by rapidly lowering Reactor pressure with Turbine Bypass Valves. Once two max safe temperatures are exceeded, the crew will perform an Emergency Depressurization. Two of the ADS valves will fail to open. The SRO will direct two other SRVs open, but only one other SRV will open. The SRO will determine that Emergency Depressurization requirements are still met with only six SRVs open.

The scenario will be terminated when all control rods are inserted, the Emergency RPV Depressurization is in progress, and Reactor water level is controlled above 0".

LOI-14-1 NRC Examination Scenario 4 Page 4 of 20

I Shift Turnover The Plant is operating at approximately 7% power with the Mode Switch in STARTUP.

The Rod Worth Minimizer is inoperable and bypassed.

IRM F is bypassed and ready to be returned to service following I&C repair.

When you take the shift:

1. Return IRM F to service per OP-16 Section E.8.1.
2. Continue control rod withdrawals per the startup control rod sequence. The next movement is A2-1 Sequence, RSCS Group 14, Step 16, Control Rod 14-39. Complete Step 16, then hold. The next shift will transition to Mode 1.

LOI-14-1 NRC Examination Scenario 4 Page 5 of 20

Critical Tasks/Standards Critical Task #1: Given the plant operating at power with an un-isolable primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.

Critical Task #2: Given an un-isolable primary system discharging into Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.

LOI-14-1 NRC Examination Scenario 4 Page 6 of 20

EVENT NO. EVENT SEQUENCE

1. Return IRM F to Service (Normal: BOP, SRO)
2. Withdraw Control Rods (Reactivity: ATC, SRO)
3. Stuck Control Rod (Component: ATC, SRO)
4. RPS Level Transmitter Fails High (Instrument: SRO)

Reactor Water Cleanup Pump Seal Failure, Reactor (Component: BOP, SRO)

5. Water Cleanup Fails to Automatically Isolate RCIC Inadvertent Initiation and High Bearing (Component: BOP, SRO) 6.

Temperature

7. RCIC Steam Leak and Failure to Isolate (Major: All)
8. RPS Fails to Scram, ARIInserts Control Rc>ds (Instrument: ATC, SRO)
9. Multiple SRVs Fail to Open (Component: BOP, SRO)

D. TERMINATION CUES:

  • Emergency RPV Depressurization is in progress
  • Reactor water level is controlled above 0" LOI-14-1 NRC Examination Scenario 4 Page 7 of ~~0

1Q~t*f\(:1Vf $STANb~~.:, JATIOfiil Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow I All no more than five minutes for panel walkdown

  • Walkdown the control panels and assume the watch Event 1 I SRO SAT I UNSAT INA Return IRM F to Service
  • Perform Crew Brief
  • Return IRM F to service per OP-16 Section E.8.1:

o IF RX MODE SWITCH is not in RUN, THEN perform the following o Ensure RANGE SWITCH for IRM F is selected to range 10 o Ensure associated panel recorder CHAN SEL switch in IRM o Operate RANGE SWITCH for IRM F to establish BETWEEN 5 and 75 for IRM F on 0 to 125 scale on panel 09-5 recorder or on panel 09-12 indicator o Ensure IRM F reading is consistent with other IRMs LOI-14-1 NRC Examination Scenario 4 Page 8 of20

POSrttdN~ 'l :GlPE~Tq~ A~1~~tsT4UVAR'" ~i;"'bQMJiefltstEVALt BOP cont. SAT I UNSAT INA o Verify the following lights for IRM Fare off at panel 09-12:

o INOP o UPSCL TRIP o Place IRM BYP switch for IRM Fin center position o Verify IRM F is returned to service using one or both of the following:

o IRM F BYPASS indicating light is off o No EPIC bypassed alarm for IRM F o Verify the four IRM channels associated with the same IRM BYP switch are in service using one or both of the following:

o BYPASS indicating lights for the four IRMs are off o No EPIC bypassed alarms for the four IRMs LOI-14-1 NRC Examination Scenario 4 Page 9 of 20

' ',' OP~MTOR ACTI~O

~~""  ;;r 3 'J9 f..J Event 2 SRO SAT I UNSAT INA Withdraw Control Rods

  • Provide oversight of reactivity manipulation ATC SAT I UNSAT INA Note:

The first four control rods in the withdrawal sequence are o Nuclear instrumentation 14-39, 38-39, 38-15, and 14- o Control rod position indication

15. These control rods are being moved from position 04
  • Ensure control rod to be moved is selected by depressing rod be stuck at position 04, which select pushbutton on ROD SEL matrix, if necessary will lead to the next event.
  • Verify the following:

o Select pushbutton is brightly backlit o Control rod indicating light is on o ROD OUT PERM light is on

  • Place ROD MOVEMENT CNTRL switch to OUT NOTCH, spring return to OFF
  • Verify control rod latches in the expected even numbered position before ROD SETTLE light goes off
  • Verify ROD SETTLE light is off
  • Repeat as necessary LOI-14-1 NRC Examination Scenario 4 Page 10 of 20

1Nf't¥< '" ~'"K,f!Q&lTJeN"" ,'()f?W!6RAC1"fONs~

Event 3 ATC SAT I UNSAT INA Stuck Control Rod

  • Acknowledge report
  • Direct continuing control rod withdrawals Role Play: ATC SAT I UNSAT INA If asked about HCU valve lineup, wait 2 minutes, then
  • Execute OP-25 Section E.6:

report that the valve lineup is o Raise drive water differential pressure in approximately 50 SAT. psig increments o Attempt to move the control rod one notch per OP-26 Role Play:

o Recognize I report successfui controi rod withdrawal If asked for Rx Analyst instruction, report that the Rx o Lower drive water differential pressure to approximately Analyst concurs with 260 to 270 psig attempting to free the stuck

Booth Operator:

When CRD drive water DIP is above 300 psig, verify Trigger 24 automatically deletes malfunction rd10:38:15. This will allow control rod 38-15 to move.

LOI-14-1 NRC Examination Scenario 4 Page 11 of 20

'tJ .r~,e~lfR~+;~r* .~Ll1ATiofJ Event4 ATCI80P SAT I UNSAT INA On Lead Examiner Cue:

  • Acknowledge reports SAT I UNSAT INA
  • Direct ARP response
  • May reference OP-27 A Attachment 7
  • Determine an input for the low Reactor water level RPS, PC IS, and SCIS functions is inoperable
  • Determine Technical Specification Table 3.3.1.1-1 Function 4 is not met
  • Determine Technical Specification 3.3.1.1 Condition A requires placing the channel or associated trip system in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
  • Determine Technical Specification Table 3.3.6.1-1 Functions 2.a, 2.g, 5.e, 6.b, and 7.a are not met
  • Determine Technical Specification 3.3.6.1 Condition A requires placing the channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
  • Determine Technical Specification Table 3.3.6.2-1 Function 1 is not met
  • Determine Technical Specification 3.3.6.2 Condition A requires placing the channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Role Play: ATCI80P
  • Execute ARP 09-5-2-60: SAT I UNSAT INA If dispatched to investigate, o Dispatch operator to check red gross fail lights on panel wait 2 minutes, then report 09-92 and 94 panel MTUs that narrow range level MTU 02-3MTU-201 8 has failed o Dispatch operator to check position of calibration unit, upscale (225") with the gross select switches and test switches at panel 09-92 and 94 fail light lit.

LOI-14-1 NRC Examination Scenario 4 Page 12 of 20

  • ~ueu6f{r~c1'tvr Q!ERATOI APIION:fiSfANDAAOf: J\NA11oN Event 5 ATC I BOP SAT I UNSAT INA On Lead Examiner Cue:

ACTIVATE TRIGGER 2

Seal Failure, Reactor Water AMBIENT TEMP HI Cleanup Fails to Automatically

  • Recognize I report RWCU pump trip and failure to isolate Isolate SRO SAT I UNSAT INA Note:
  • Acknowledge reports The crew may isolate RWCU by closing 12MOV-15,
  • May direct area/building evacuation
  • As time permits, exits EOP-5
  • If isolation failure is revealed based on timing of crew actions:

o Determines Technical Specification Table 3.3.6.1-1 Function 5.b was not met o Determines Technical Specification 3.3.6.1 Conditions A and B were not met and required restoring isolation capability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; determines this is met following manual isolation LOI-14-1 NRC Examination Scenario 4 Page 13 of 20

'NIMrtD1t~,

Role Play: BOP SAT I UNSAT INA If dispatched to investigate,

  • Executes ARP 09-3-3-02(12) wait 2 minutes, then report that there is significant steam o Respond for system isolation per OP-28 Section G coming from the RWCU pump o Identify affected areas using red lights at panel 09-21 A room and you are unable to and/or EPIC get very close. After isolation, report that the leak seems to o Consider evacuation of personnel from affected areas be getting better and the area o Dispatch operator to check affected areas and ensure any is starting to clear of steam.

systems discharging steam in the affected area are isolated

  • As time permits, executes OP-28 Section G.2 o Ensure the following pumps are stopped at panel 09-4:

o CLN UP PMP 12P-1A Note: o CLN UP PMP 12P-1 B The crew may isolate RWCU o Dispatch operator to perform field actions for isolation by closing 12MOV-15, 12MOV-18, and/or 12MOV-69 o Ensure closed the following valves:

prior to referencing ARP Oi OP o CLN UP SUCT 12MOV-15 guidance based on direction in EOP-5 or EN-OP-115 for o CLN UP SUCT 12MOV-18 failed automatic actions. o CLN UP RETURN ISOL VLV 12MOV-69 o FILTER DEMIN BYP 12MOV-74 Role Play:

If dispatched to perform field o CLN UP SLOWDOWN FLOW CNTRL 12FCV-55 actions for RWCU isolation, o SLOWDOWN ORIFICE BYP 12MOV-53 acknowledge request.

o SLOWDOWN TO MAIN CNDSR 12MOV-56 o SLOWDOWN TO ROW 12MOV-57 LOI-14-1 NRC Examination Scenario 4 Page 14 of20

Event 6 BOPIATC SAT I UNSAT INA On Lead Examiner Cue:

  • Recognize I report EPIC RCIC speed alarm ACTIVATE TRIGGER 3 RCIC Inadvertent Initiation
  • Recognize I report inadvertent RCIC initiation and High Bearing

SRO SAT I UNSAT INA Note:

  • Acknowledge reports High bearing temperature is included to ensure RCIC must
  • Enter AOP-77 (Inadvertent Initiation of ECCS or RCIC) be tripped and becomes

verifying HPCI operable by administrative means immediately and RCIC to be restored to operable status within 14 days.

BOP SAT I UNSAT INA Note:

  • Execute AOP-77:

The crew may trip RCIC prior to referencing AOP-77, since o Verify by two independent means, initiation is not required these are immediate actions. o IF an inadvertent HPCI or RCIC start occurred, THEN depress associated TURB TRIP pushbutton Role Play: o IF an unplanned power change occurred, THEN enter If dispatched to investigate, AOP-32 wait 2 minutes, then report that nothing looks abnormal at o Determine cause of ECCSIRCIC initiation signal(s) and the RCIC skid. initiate corrective actions LOI-14-1 NRC Examination Scenario 4 Page 15 of 20

INSTR~drdR ACTI/1171 i

- _,_ -;, ', ,_;o;. '

~;postlrl1H' ID'iAattl~

Events 7. 8, & 9 ATC I BOP SAT I UNSAT INA On Lead Examiner Cue:

  • Recognize I report EPIC high area temperature alarms ACTIVATE TRIGGER 4 RCIC Steam Leak and Failure

to Isolate, RPS Fails to Scram, o 09-3-3-33, HPCIISOL TRIP INITIATED ARI Inserts Control Rods, Multiple SRVs Fail to Open o 09-4-1-22, RCIC ISOL TRIP LOGIC INITIATED

  • Recognize I report RCIC failed to isolate Critical Task #1 Given the plant operating at power with an un-isolable Pass I Fail primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.

Critical Task #1 Standard: Manually initiate ARI.

Critical Task #2 Given an un-isolable primary system discharging into Pass I Fail Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.

Critical Task #2 Standard: Open at least 5 SRVs.

LOI-14-1 NRC Examination Scenario 4 Page 16 of 20

SRO SAT I UNSAT INA

  • Acknowledge report
  • Direct isolation of RCIC
  • Direct area/building evacuation, if not previously performed
  • Acknowledge manual RCIC isolation failure
  • Direct Reactor pressure controlled 900 to 1000 psig using TBVs
  • Direct Reactor water level controlled 180 to 220 inches using Note: Feedwater Tf1e SRO will likely anticipate Emergency Depressurization
  • May direct Reactor cooldown < 100°F/hr by ordering a rapid
  • Recognize I acknowledge two area temperature above Max cooldown rate of 100°F/hr may Safe Value be violated since area
  • Enter Emergency Depressurization leg of EOP-2 temperatures are approaching Max Safe Values.
  • Direct 7 ADS valves open
  • Acknowledge two ADS valves failed to open
  • Direct additional SRVs open
  • Acknowledge only 6 SRVs open
  • Determine an adequate number of SRVs are open for Emergency Depressurization (~ 5)

LOI-14-1 NRC Examination Scenario 4 Page 17 of 20

tritrRU~QR AC'lj~-Jt ITION l:,~~~~~~tQ11;~cTfONSI4TA (jbMJnEINTS/E ATC SAT I UNSAT INA

  • Place Mode Switch to Shutdown Critical Task #1 Role Play:
  • Initiate ARI If dispatched to investigate
  • Report all control rods have inserted high temperature, wait 2

. minutes, then report you see

  • Enter AOP-1 I steam coming from the West
  • Fully insert IRMs and SRMs Crescent and cannot access the area.
  • Observe Reactor power downscale on APRMs
  • Observe SDIV vent and drain valves closed
  • Transfer APRMIIRM recorders to IRMs
  • Attempt to isolate RCIC Note:

The crew may attempt to o Close 13MOV-16 isolate RCIC by closing o Attempt to close 13MOV-15 13MOV-15 and 13MOV-16 o Recognize I report 13MOV-15 breaker failure and dual before referencing an ARP or position indication OP as a backup to a failed automatic action (EN-OP-115) or based on guidance in EOP-5.

LOI-14-1 NRC Examination Scenario 4 Page 18 of 20

INS1R!IC

-,- "':wr ~crtitrrnr Pli)SITION *~*ACTION.STlNDJiRD BOP cont. SAT I UNSAT INA

  • Announce Reactor Building Evacuation, if not previously performed
  • Enter AOP-1 o Control RPV water level between 180 and 220" using any of the following methods:

o Adjust feedwater level control auto-setpoint o Take manual control of reactor feed pump and adjust FDWTR STARTUP VLV (34FCV-137)

  • Update crew on RB area temperatures
  • Report two area temperatures above Max Safe Value
  • Attempt to open 7 ADS valves Critical Task #2
  • Recognize I report only 5 ADS valves are open
  • Attempt to open additional SRVs
  • Recognize I report only 6 SRVs are open Termination Criteria:
  • Emergency RPV Depressurization is in progress
  • Reactor water level is controlled above 0" LOI-14-1 NRC Examination Scenario 4 Page 19 of 20

ATTACHMENT 1 Shift Turnover The Plant is operating at approximately 7% power with the Mode Switch in STARTUP.

The Rod Worth Minimizer is inoperable and bypassed.

IRM F is bypassed and ready to be returned to service following I&C repair.

When you take the shift:

1. Retum lRM F to service per OP-16 Section E.8.1.
2. Continue control rod withdrawals per the startup control rod sequence. The next movement is A2-1 Sequence, RSCS Group 14, Step 16, Control Rod 14-39. Complete Step 16, then hold. The next shift will transition to Mode 1.

LOI-14-1 NRC Examination Scenario 4 Page 20 of 20

Retrieved from "https://kanterella.com/w/index.php?title=ML14119A392&oldid=2511428"