Text

Walk-through Retake Exam Administered 3/24-25/2014
	ML14164A048
Person / Time
Site:	Vermont Yankee
Issue date:	03/25/2014
From:	; NRC Region 1
To:	;
Shared Package
ML13204A095	List: IR 05000271/2014301; ML14029A320; ML14055A041; ML14057A726; ML14057A796; ML14058A125; ML14059A020; ML14059A056; ML14059A542; ML14059A546; ML14063A514; ML14064A051; ML14164A048;
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JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 1 of 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Perform a Core Thermal Hydraulics Limits Evaluation Failure Mode: NA

Reference:

OP 4401 "Core Thermal Hydraulics Limits Evaluation" Task Number: 34202603 Task Performance: AO/RO/SRO RO/~ X SEOnly Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom X Simulator Plant Performance Expected Completion Time: minutes Evaluation Results:

Performance: PASS _ FAll... __ Time Required:

Prepared by:

Facility Exam Developer Date Reviewed by:

SRO Licensed /Certified Reviewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 2 of 11 Directions Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Classroom and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

The plant is at rated conditions

APRM "D" has failed downscale and is bypassed

The Daily Core Thermal Hydraulics Limit Evaluation has not yet been performed

The current Admin Limits are:

o MFLCPR: 0.975 o MFLPD: 0.964 o MAPRAT: 0.980 Initiating Cues:

Perform The Daily Core Thermal Hydraulics Limit Evaluation lAW OP 4401 using the 3D Monicore Case provided. If any limits are exceeded, determine the required action.

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 3 of 11 Task Standards:

All of the following:

Daily Core Thermal Hydraulics Limit Evaluation performed lAW OP 4401

The AGAF for APRM "B" is determined to be out of spec

The required action for the out of spec AGAF is also identified

MFLCPR and MAPRAT are identified as having exceeded their Admin Limits

MAPRAT is identified as exceeding the T<~ch Spec limit.

The required action for exceeding the Tecb Spec limit is correctly identified Reguired Materials:

OP 4401, Core Thermal Hydraulics Limit Evaluation

Attachment 1 to this JPM, For Training, 3D Monicore Case

Blank Core Thermal Hydraulics Limit Evaluation (VYOPF 4401.01) form

VY Tech Specs Simulator Setup:

NA

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 4 of 11 Evaluation Performance Steps TIME START:

SAT/UNSAT Step 1: Obtain procedure OP 4401, Core Thermal Hydraulics Limit Evaluation Standard: Procedure reviewed Evaluator Note A completed VYOPF 4401.01. is provided as Attachment 2 to this JPM to aid in evaluating the form completed by the operator.

SAT/UNSAT *Step 2: Records the required information on VYOPF 4401.01.

Standard: Steps 1 through 6 of form completed with all critical elements satisfied.

Interim Cue: If asked cue that the control rod positions as indicated on CRP 9-5 are the same as indicated on the 3D Monicore printout.

SATIUNSAT *Step 3: Operator evaluates APRM system gains (step 7 of form)

Standard: Operator reviews the AGAFs on the 3D Monicore Case and determines that the AGAF for APRM "B" indicates that its gain has exceeded the limit (AGAF > 1).

Interim Cue: If asked, cue that the APRM system gains using the REO display on ERFIS are the same as indicated on the 3D Monicore Case.

Critical Step

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 5 of 11 Evaluation Performance Steps SATIUNSAT *Step 4: Operator determines the reguired action for the APRM gain.

Standard:

Operator determines that the gain of APRM "B" must be adjusted lAW OP 4400, CALIBRATION OF THE AVERAGE POWER RANGE MONITORING SYSTEM TO CORE THERMAL POWER.

The gain should be adjusted as soon as possible. If not adjusted within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , APRM "B" must be declared inoperable.

SATIUNSAT *Step 5: Operator compares current values for MFLCPR1 MFLPD and MAPRAT to the Admin Limits {step 8 of form).

Standard: Determines that MFLPD and MAPRAT have exceeded their Admin Limits.

SATIUNSAT *Ste)! 6: O)!£rator determines the reguired action for exceeding; the Admin Limits Standard: Operator determines that Reactor Engineering must be contacted.

SATIUNSAT *Sten 7: Operator compares current values for MFLCPR1 MFLPD and MAPRAT to the Accentance Criteria listed on the form {sten 9 of form).

Standard: Determines that MAPRAT does not meet the associated Acceptance Criteria.

Critical Step

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 6 of 11 Evaluation Performance Steps SAT/UNSAT *Step 8: Operator determines the required action for not satisfying the Acceptance Criteria.

Standard:

Operator d~etermines that the APLHGR LCO, TS 3.ll.A, is not met.

Operator determines that APLHGR (MAPRAT) must be returned to within prescribed limits within two (2) hours; otherwise, the reactor shall be brought to< 23%

Rated Thermal Power within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Interim Cue: After the operator has determined the required action for exceeding the TS limit, cue the operator that the task has been completed.

TIME FINISH:

All of the following have been completed:

Terminating Cue:

Daily Core Thermal Hydraulics Limit Evaluation performed lAW 01, 4401

The AGAF for APRM "B" is determined to be out of spec

The required actiolll for the out of spec AGAF is also identified

MFLCPR and MAPRAT are identified as having exceeded their Admin Limits

MAPRAT is identified as exceeding the Tech Spec limit.

The required action for exceeding the Tech Spec limit is correctly identified

Critical Step

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 7 of 11 Evaluator Comments:

JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 8 of 11 Tear Out Sheet Initial Conditions:

The plant is at rated conditions

APRM "D" has failed downscale and is bypassed

The Daily Core Thermal Hydraulics Limit Evaluation has not yet been performed

The current Admin Limits are:

o MFLCPR: 0.975 o MFLPD: 0.964 o MAPRAT: 0.980 Initiating Cues:

Perform The Daily Core Thermal HydrauHcs Limit Evaluation lAW OP 4401 using the 3D Monicore Case provided. If any limits are exceeded, determine the required action.

Attachment 1 JPM 2014A NRC SRO A-1 FOR TRAINING ONLY Rev.0,03/14 Page 9 of 11 PAGE 1 VERMONT YANKEE C26 SEQUENCE NO 23 CORE PARAMETERS 3DM/P11 25-Mar-2014 00:00 CALCULATED POWER MWT 1910.7 PERIODIC LOG 25-Mar-2014 00:00 PRINTED POWER MWE 652.8 AUTOMATIC CASE ID FMLS1120815000053 FLOW MLB/HR 48.121 CALC RESULTS RESTART FMLS1120815000053 FPAPDR 0.815 LPRM SHAPE - FULL CORE SUBC BTU/LB 26.96 Keff 1. 0040 PR PSI a 1029.95 XE WORTH % -2.387 LOAD LINE

SUMMARY

CORE MWD/sT 20163.0 XE RATED 1.03 CORE POWER 99.9%

CYCLE MWD/sT 5796.8 AVE VF 0.480 CORE FLOW 100.3%

MCPR 1.552 LOAD LINE 99.8%

CORRECTION FACTOR: MFLCPR= 1.002 MFLPD= 0.999 MAPRAT= 0.998 OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM= 1.400 MOST LIMITING LOCATIONS (NON-SYMMETRIC)

MFLCPR LOC MFLPD LOC MAPRAT LOC PCRAT LOC 0.902 25-34 0.968 23-34-10 1.003 23-36-10 0.999 23 9 0.869 27-32 0.960 23-36-11 1.001 23-34-11 0.998 25-36-11 0.896 23-32 0.952 9 5 0.998 15 4 0.991 23-38-11 0.869 29-34 0.950 15 4 0.920 9 5 0.969 25-38-11 0.865 27-36 0.920 17 5 0.920 9 5 0.966 25-32-11 0.827 23-36 0.912 9 5 0.899 13 4 0.962 9 5 0.822 35-24 0.910 25-34-11 0.895 11 4 0.959 15 5 0.813 31-36 0.872 25-36-11 0.894 15 5 0.956 17 5 0.809 27-34 0.869 11 5 0.890 11 4 0.956 11 5 SEQ. B-1 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 00 0.469 24 02 0.649 23 43 04 0.783 22 L 06 0.854 21 39 08 0.897 20 M 10 0.912 19 35 32 12 0.921 18 L *C 14 0.945 17 31 16 0.943 16 18 0.982 15 27 10 08 10 20 1.147 14 L 22 1.177 13 23 24 1. 236 12 26 1. 280 11 19 10 08 10 28 1. 286 10 L 30 1. 291 09 15 32 1. 303 08 34 1. 304 07 11 32 36 1. 319 06 L 38 1.347 05 07 40 1. 319 04 42 1.190 03 03 44 0.919 02 L L L L L 46 0.333 01 02 06 10 14 18 22 26 30 34 38 42 CORE AVERAGE RADIAL POWER DISTRIBUTION RING i 1 2 3 4 5 6 REL PW 0.947 1.056 1.121 1.224 1.142 0.689 PAGE 2 VERMONT YANKEE C26 INSTRUMENT READINGS/STATUS SEQUENCE NO 23 CALIBRATED LPRM READINGS 15-Aug-2012 00:00 CALCULATED 15-Aug-2012 00:00 PRINTED 41D 24.0 28.4C CASE ID FMLS1120815000053 c 34.3 40.9 LPRM SHAPE - FULL CORE

Attachment 1 JPM 2014A NRC SRO A-1 FOR TRAINING ONLY Rev.0,03/14 Page 10 of 11 B 41.0* 49.4 A 34.9 43.2 FAILED SENSORS:

33D 29.5 42.0 44.3 37.4 LPRM ( 1 SIGNAL FAILED) c 39.7 53.3 57.2 48.0 3209A B 49.1 32.4 65.7 56.1 LPRM ( 0 PANACEA REJECTED)

A 54.1 61.9 51.3 60.3 OTHER SENSORS ( 0 TOTAL)

SUB RODS 25D 37.0 51.2 52.2 45.7 26.8 NONE c 45.9 44.1 44.0 44.4 35.8 B 56.4 49.5 47.1 53.2 45.6 T = TIP RUN RECOMMENDED A 60.6 45.6 38.3 54.2 49.4 c MFLCPR LOCATION M MAPRAT LOCATION 17D 34.3 47.9 49.3 43.5 23.9 D MFLPD LOCATION c 44.1 46.6 47.7 44.7 31.1 p PCRAT LOCATION B 55.0 53.1 53.1 53.6 37.9

MULTIPLE LIMIT A 60.6 48.6 45.3 56.9 37.2 09D 22.2 34.6 38.0 28.6 c 30.3 49.3 55.1 40.4 B 36.6 59.9 64.9 50.0 A 37.1 58.8 49.8 0.0 08 16 24 32 40 CORE

SUMMARY

CORE POWER 99.9% CALC SUB FLOW 100.4% DP MEAS PSI 20.426 CORE FLOW 100.3% OPER SUB FLOW -2.1% DP CALC PSI 24.994 LOAD LINE 99.8% FLOW BASIS MEAS FEEDWTR FLOW MLB/HR 7.90 APRM CALIBRATION A B c D E F READING 100.9 98.9 100.8 0.0 100.8 100.8 AGAF 0.990 1. 010 0.991 **** 0. 992 0.992 APRM - %CTP 1.0 -1.0 0.9 *** 0.9 0.8 TIP RUNS RECOMMENDED STRINGS: NONE

JPM 2014A NRC SRO A-1 Rev.0,03/14 ANSWER KEY Page 11 of 11 Attachment 2 CORE THERMAL HYDRAUI.IC LIMITS EVALUATION

1. Record 30 Monicore Official Monitoring Case 10 FMLS11208150Q0053

2. Verify the control rod positions of the Official Monitoring case are correct.

By/Date: Operator's Name I 25-Mar-2014

3. Record the core thermal power (in MWth). CTP = .::19~1:.::0~.7.___ _ _ _ _.MWth

4. Record the highest MFLCPR and its core location (XX-YY).

MFLCPR = =0-=9=02=-*---- Location == :25~--=34=-*----

5. Record the highest MFLPD and its core location (XX-YY-ZZ).

MFLPD =.::.0:.:.9;.:68::.*----- Location ==23-34-10*

6. Record the highest MAPRAT and its core location (XX-YY-ZZ).

MAPRAT = .::1.=00=3:::...*---- Location == 23-36-10*

Any APRM found to be non-conservative shall be corrected as soon as possible. An APRM is considered inoperable if the AGAF is not restored within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the time of discovery.

7. Check the APRM system gains using the REO display on ERFIS. (Determines that APRM "B" AGAF is above the limit*)

8. Verify MFLCPR, MFLPD and MAPRAT from Steps 4- 6 are less than or equal to Administrative limits posted on Thermal limit Status Board. If not, contact Reactor Engineering. (Determines that MFLCPR and MAPRATare above the limits*)

9. Verify the Acceptance Criteria below are satisfied. If A, B, Cor D below are not satisfied, enter applicable Tech. Spec. LCO. (Determines that MAPRAT is above the TS limit*)

Acceptance Criteria A) Step #4, MFLCPR less than or equal to 1.0 (Tech. Spec. 3.11.C).

B) Step #5, MFLPD less than or equal to 1.0 (Tech. Spec. 3.11.B)

C) Step #6, MAPRAT less than or equal to 1.0 (Tech. Spec. 3.11.A)

Indicates Critical Elements when evaluating the completion of form

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION{PRIVATE}

JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Determine Containment Venting Strategy while Implementing the Severe Accident Guidelines.

Failure Mode: N/A

Reference:

Severe Accident Guidelines (SAGs)

Task Number: 31071403 (Direct Primary Containment Venting)

Task Performance: AO/RO/SRO _ _ _ FlO/SAO _ __ SROOnly X Sequence Critical: Yes No~

Time Critical: Yes No~

Operator Performing Task: _______________

Examiner=------------*--------

Date of Evaluation: _ _ _ _ _ _ _ __

Activity Code: _ _ _ _ _ _ _ _ __

Method of Testing: Simulation__ Performance X Discuss._ _

Setting: Classroom X Simulator_ _. Plant'---

Performance Expected Completion Time: 20 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ _ Time Required: _ _ __

Prepared b y : - - - - - - - - - - - - - - - - - - -

NRC Exam Lead DevelopHr Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

SRO Licensed /Certified Reviewer Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Training Superintendent Date NRC JPM-Alb SRO

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to .. talk through .. the JPM, stating the indications/parameters you are verifying or checking and the steps you are p*~rforming.

Inform me upon completion of this task.

Initial Conditions:

The plant automatically scrammed from normal full power operations due to a large break loss of coolant accident (LOCA).

Equipment malfunctions have resulted in the inability to maintain Adequate Core Cooling (ACC) and Severe Accident Guideline-2 (SAG-2) has been entered.

Containment conditions are as follows:

o Torus water level is 20 feet and slowly rising o Torus 02: 5% and steady o Torus H2: 5% and steady o Drywell 02: 6% and steady o Drywell H2: 5% and steady

Radiological conditions are as follows:

o Stack High Range Monitor (Gas 3 [FIM-17-155]) is reading 175 mR/hr and slowly rising o Dose assessment using actual meteorology indicates doses of 105 mRem/hr and steady at the Site boundary o Field surveys are in progress

The Emergency Plan organization is NOT yet manned NRC JPM-Al b SRO

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 3 of 6 Initiating Cues:

In accordance with the SAG-2, determine the following for each the Torus and Drywall independent of one another:(Fill in chart on handout) o Can high radiation isolations be defeated?

o What is/are the procedures(s) that can be used to vent containment?

o What is the criterion for securing vfmting?

o Can release rate limits be exceeded?

Task Standards:

The correct SAG-2 thresholds for H2/02 and the subsequent containment venting actions have been determined and all questions from the initiating cue answered.

Required Materials:

Severe Accident Guideline (SAG)-2, "RPV, Containment, and Radioactivity Release Control"

AP 3125, "Emergency Plan Classification and Action Level Scheme", Appendix "A" (Hot)

EAL Bases document

Technical Specifications Simulator Set-Up:

N/A NRC JPM-Alb SRO

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 4 of 6 Provide operator with Initial Conditions/Cue and handout (Last 2 pages of this JPM).

TIME START:----

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain SAG-2 flowchart and reviews the flowpath for Hydrogen and Oxygen concentration.

Standard: Obtains SAG-2 Flowchart.

SAT/UNSAT *Step 2: From the given Hydrogen and Oxvaen concentrations, the operator determines the reguired action levels for containment venting/purge operations in the Drywell and Torus:

Standard: From the given Hydrogen and Oxygen concentrations, the operator determin4:lS the following:

Action level 2 for the Drywall

Action level 5 for the Torus SAT/UNSAT Step 3: Obtains and reviews AP 3125, Appendix "A" (Hot) to review the Emergency Action Level thresholds for current radiological conditions.

Standard: Some action levels have criteria for securing venting operations based on reaching General Emergency levels for effluent releases. Based on the initial conditions, the operator determines that the plant is at Site Area Emergency levels for effluent releases with plenty of margin to the General Emergency levels.

NRC JPM-Alb SRO

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 5 of 6 Evaluation Performance Steps SAT/UNSAT *Step 4: Based on the action level for the Drvwell, the operator answers the given questions Standard: The operator answers the Drywall questions as follows (Action level2):

o Can high radiation isolations be defeated? YES o What is/are the procedures(s) that can be used to vent containment? The Drywell is vented using OP 2115, OP 2125, or OE 3107.

o What is the criterion for securing venting?

Hydrogen no longer detected in the Drywell AND EITHER Drywell Oxygen is <5% OR Hydrogen no longer detected in the Torus -or-

RPV water level maintained above TAF AND off site release rates reach General Emergency level.

o Can release rate limits be exceeded? NO (below the limit already)

SATIUNSAT *Step 5: Based on the action level for the Torus. the operator answers the given question!

Standard: The operator answers the Torus questions as follows (Action level 4):

o Can high radiation isolations be defeated? YES o What is/are the procedures(s) that can be used to vent containment? With Torus level at 20 feet, the Torus is vented using OP 2115, OP 2125 or OE 31 07.

o What is the critE~rion for securing venting?

Hydrogen no longer detected in the Torus AND EITHER 'Torus Oxygen is <5% OR Hydrogen no longer detected in the Drywell-or-

RPV water level maintained above TAF AND off site release rates reach General Emergency level.

o Can release rate limits be exceeded? NO (below the limit already)

NRC JPM-Alb SRO

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 6 of 6

Critical Step TIME FINISH:----

Terminating Cue: The operator informs the evaluator that all the questions asked in the initiating cue have been answered.

Evaluator Comments:

System Generic K/A's: 2.1.25 Ability to interpret refe!rence materials, such as graphs, curves, tables, etc. (RO 3.9, SAO 4.2)

NRC JPM-Alb SRO

JPM 2014A NRC SRO A3 Rev 0, 3/14 Page 1 of 3 EXAMINEE HANDOUT Initial Conditions:

The plant automatically scrammed from normal full power operations due to a large break loss of coolant accident (LOCA).

Equipment malfunctions have resulted in the inability to maintain Adequate Core Cooling (ACC) and Severe Accident Guideline-2 (SAG-2) has been entered.

Containment conditions are as follows:

o Torus water level is 20 feet and slowly rising o Torus 02: 5% and steady o Torus H2: 5% and steady o Drywell 02: 6% and steady o Drywell H2: 5% and steady

Radiological conditions are as follows:

o Stack High Range Monitor (Gas 3 [RM-17-155]) is reading 175 mR/hr and slowly rising o Dose assessment using actual meteorology indicates doses of 105 mRem/hr and steady at the Site boundary o Field surveys are in progress

The Emergency Plan organization is NOT yet manned Initiating Cues:

In accordance with the SAG-2, determine the following for each the Torus and Drywell independent of one another:(Fill in chart on handout) o Can high radiation isolations be defE~ated?

o What is/are the procedures(s) that can be used to vent containment?

o What is the criterion for securing venting?

o Can release rate limits be exceeded?

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 2 of 3 EXAMINEE HANDOUT QUESTIONS. DRYWELL TORUS Can high radiation isolations be defeated?

What is/are the procedures(s) that can be used to vent containment?

What is the criterion for securing venting?

Can release rate limits be exceeded?

JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 3 of 3 Answer' sheet NOT for Examinee QUESnONS DRYWELL TORUS Can high radiation isolations be Vel! Yes defeated?

What is/are the procedures(s) The Drywell is vented using The Torus is vented using OP that can be used to vent OP 2115, OP 2125, or OE 2115, OP 2125 or OE 3107.

containment? 31mr.

What is the criterion for Hydrogen no longer detected Hydrogen no longer detected securing venting? in the Drywell AND EITHER in the Torus AND EITHER Drywell Oxygen iis <5% OR Torus Oxygen is <5% OR Hydrogen no longer detected Hydrogen no longer detected in the Torus -or- in the Drywell-or-RPV water level maintained RPV water level maintained above TAF AND off site above TAF AND off site release rates reatch General release rates reach General Emergency level. Emergency level.

Can release rate limits be No No exceeded?

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION{PRIVATE}

JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Evaluate secondary containment for continued refueling Failure Mode: N/A

Reference:

AP 0077. Barrier Control Process Vermont Yankee Technical Requirements Manual Task Number: 34270703 Task Performance: AO/RO/SRO _ RO/SRO _x_ SAO Only _

Sequence Critical: Yes No --.X Time Critical: Yes No --.X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ _,_ _ _ _ _ __

Date of Evaluation: _ _ _ _ _ _ _ _ _,

Activity Code: _ _ _ _ _ _ _ _ _ _,

Method of Testing: Simulation Performance --.X_ Discuss Setting: Classroom lL_ Simulator_ Plant __

Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ _ Time Required: _ _ __

Prepared b y : - - - - - - - - - - - - - - - - - - -

Facility Exam Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

SRO Licensed /Certified Reviewer Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Training Superintendent Date

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat** classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Mea:sure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Classroom and you are to perform the actions.

You are requested to .. talk through .. the procedure, stating the parameters you are verifying or checking and the steps you are performing .

Inform me upon completion of this task.

Initial Conditions:

Refueling is in progress

Reactor building vacuum is -0.25 inches H20

The STA has been called to the Control Room and is expected to arrive shortly.

Initiating Cues:

The Shift Manager has directed you to review OPAP-BCP-0077, Attachment 15, Secondary Containment Permit Index and take any actions, if applicable, after your review.

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 3 of 7 Task Standards:

Reviews secondary containment barrier petrmit index and notes previous permits total 2

19.3 in

2

The operator identifies that the most recent breach is a 3 inch pipe which equals 7.06 in ,

2 which, when added to the previous permits will cause us to exceed 22.4 in at a total of 26.4 in of secondary containment breachE~d by permit.

2

A review of OPAP-BCP- 0077, Barrier control process, shows that for the current plant 2

conditions (0.25 inches H20 reactor building vacuum) we are allowed a total of 22.4 in of secondary containment barriers breached. Therefore, secondary containment is inoperable.

The operator should then consult Tech Specs and determine that refueling operations, core alterations and OPDV's (operations with the potential for draining the reactor vessel) should be halted lAW T.S. 3.7.C.4 a-c.

Required Materials:

Handout 1- OPAP-BCP- 0077, "Barrier Control Process" Handout 2- Vermont Yankee Technical Specifications Simulator Set-Up:

NA

JPM 2014A NRC SRO A-2 Rev 0, 3/14 Page4 of 7 Provide Candidate with Initial Conditions/Cue (Last Pages of this JPM) and OPAP-BCP-OOn, 5, Secondary Containment Permit Index.

Evaluation Performance Steps TIME START: _ _ __

SAT/UNSAT *Step 1: Review OPAP-BCP-oon. Attachment 15, Secondary Containment Permit Index.

Standard: The operator identifies that the most recent breach is a 3 inch pipe which equals 7.06 in2 , which, when added to the previous permits 2 2 (total of 19.3 in ) will cause us to exceed 22.4 in for a total of 2

26.4 in of secondary containment breached by permit. (math is 2

3.1416/4 X dia2 =in2 or 0.7854 X 9=7.0686 in )

SAT/UNSAT Step 2: Obtain Procedure OPAP-BCP-oon and locates Attachment 4, Secondary Containment Barriers (Shift Supervisors).

Standard: The operator obtains OPAP-BCP-0077 and locates Attachment 4.

EVALUATOR CUE When it is apparent that the operator is seeking to find OPAP-BCP- 0077, Examiner provide copy (Handout 1).

SAT/UNSAT *Step 3: Determine the total breach area allowed under current plant conditions.

Standard: A review of OPAP-BCP- 0077, Barrier control process, shows that for the current plant conditions (0.25 inches H20 reactor 2

building vacuum) we are allowed a total of 22.4 in of secondary containment barrie~rs breached. Therefore, secondary containment is inoperable.

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 5 of 7 Evaluation Performance Steps SAT/UNSAT *Step 4: Evaluate Tech Spec requirements and determine required ACTION.

Standard: The operator obtains the Tech Specs and determines that T.S.

LCO 3.7.C.a-c is NOT being met.

EVALUATOR CUE When it is apparent that the operator is seeking to find the Tech Specs, Examiner provide copy (Handout 2).

The operator dete1rmines that T.S. LCO 3.7.C.a-c is NOT being met.

The operator determines that T.S. LCO 3.7.C.a-c is applicable which requires that refueling operations, core alterations and OPDV's (operations with the potential for draining the reactor vessel) should be halted.

Critical Step TIME FINISH:----

Terminating Cue: This JPM is complete.

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

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 6 of 7 Evaluator Comments:

System Generic KIA's: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.(3.9/4.2)

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 1 of 2 EXAMINEE HANDOUT Initial Conditions:

Refueling is in progress

Reactor building vacuum is -0.25 inches H20

The STA has been called to the Control Room and is expected to arrive shortly.

Initiating Cues:

The Shift Manager has directed you to review OPAP-BCP-0077, Attachment 15, Secondary Containment Permit Index and take any actions, if applicable, after your review.

JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 2 of 2 ATTACHMENT 15 -SECONDARY CONTAINMENT PERMIT INDEX CpS 5.3.1)

PERM ASSET DESCRIPTION SECONDARY CLOSURE FIELD DATE EXPIRATION DATE IT NUMBER OR OF WORK CONTAINMENT RESPONSIBIUTY* (By VAUDATED ISSUED DATEmME CLOSED NUMB PENETRATION PENETRATION on-shift title or name) CLOSURE ER DESCRIPTION SIZE/TOTAL AND Contact By TIME*

SIZE Phone# Or Radio (Days/Nights) 1 FB-045-1-262 Fire penetration 10.8 in 2 Westco day shift One week Two days seal replacement supervisor ago from now Cable Vault 555-7312 2 FB-060-1-241 Fire penetration 8.5 in 2 Westco day shift Three One week seal replacement supervisor days ago from now CST pipe trench 555-7312 3 FB-061-1-213 Fire penetration 3 india pipe Westco day shift Last shift 10 days I

seal replacement supervisor from now HPCI west wall 555-7312

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 1 of 12 VERMONT YANKEE JOB PERFORMANCE :MEASURE WORKSHEET Task Identification:

Title:

Evaluate Offsite Implications of a Ground Level Release With ODPS Not A vailabl~

Failure Mode: N/A

Reference:

OP 3513 EVALUATION OF OFF-SITE RADIOLOGICAL CONDITIONS Task Number:

Task Performance: AO/RO/SRO R~~ X SEOruy Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom X Simulator Plant Performance Expected Completion Time:: minutes Evaluation Results:

Performance: PASS _ FAIL __ Time Required:

Prepared by:

Facility Exam Developer Date Reviewed by:

SRO Licensed /Certified Reviewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 2 of 12 Directions Discuss the information given on this page:: with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical s.tep. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Classroom and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are: performing.

Inform me upon completion of this task.

Initial Conditions:

The plant was at rated conditions when a fuel damaging event occurred

Following the scram a steam leak occwTed in the turbine building

The steam leak caused the turbine building blowout panels to open to relieve turbine building pressure

Only partial isolation of the steam leak has been achieved

The Stack Gas Monitor readings (RM 17- 156 and 157) are elevated but remain below the high alarm setpoint

Stack Gas High Range Monitor (RM 17-155) is reading 1.5 mRihr

The wind direction via the 15 min avg data by MET DATA HISTORY-I is from 90 degrees

The Shift Manager has directed entry into EOP-4, Radioactivity Release Control

The Emergency Centers (TSC, OSC, EOF, JIC) have not yet been activated

OOPS is not available

The operating crew is considering whether an RPV -ED is required lAW EOP-4 Initiating Cues:

Conduct an Initial Evaluation of Off-Site Radiological Conditions lAW OP 3513, Evaluation of Off-Site Radiological Conditions. Determine whether an RPV -ED is required based on that assessment. The Shift Manager will detemtine if any Protective Action

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 3 of 12 Recommendations are required following your assessment.

Task Standards:

The operator determines that the estimated dose at the site boundary is 2.4R. The operator determines that RPV-ED is required.

Required Materials:

Attachment 1 to this JPM, For Training Only Attachment 9.16 ofOP 3513

Calculator

OP 3513

EOP-4

EALChart Simulator Setup:

N/A

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 4 of 12 Evaluation Performance Steps TIME START:

SAT/UNSAT Steg 1: Obtain procedure OP 3513, EVALUATION OF OFF-SITE RADIOLOGICAL CONDITIONS Standard: The operator obtains OP 3513 and determines that section 5.9, Initial Evaluation is applicable.

SAT/UNSAT Step 2: Immediate Action by the Shift Manager or Designated Plant Staff Member.

a. Upon receiving an indication of a significant release of radioactivity is occurring and the EOF has not been activated, initiate or assign a qualified individual to perform the appropriate calculations in this procedure to evaluate the otT-site radiological conditions.

Standard: The operator proceeds to the next step Evaluator Note: OP 3513 notes to the operator at this point that the Attachment 9.11 flow chart is available to assist in tht: identification of dose assessment activities to be considered and implemented. However this flowchart is geared mainly to the development of Protective Action Recommendations and is not especially helpful for the task at hand.

SAT/UNSAT *Step 3: b. For an actual ground release, dispatch a Site BoundaQ' Team to obtain a whole body dose rate reading at the fence line in the downwind direction of the release in accordance with OP 3510, and record the whole body dose rate results on Attachment 9.16, Section A.

Critical Step

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 5 of 12 Evaluation Performance Steps Standard: Operator determines that a ground level release is occurring AND dispatches a site boundary team lAW OP 3510 Evaluator Note: Per the defmition section of OP 3513, any release from other than the stack is considered a ground lc::vel release. In this case the release is via the turbine building blow out panels to the environment and is therefore a ground level release.

Interim Cue: Cue the operator that a site bmmdary team was dispatched previously to assess radiological conditions downwind of the release location. Hand the operator the For Training Only Attachment 9.16 (attachment 1 to this JPM) showing the dose rates alt the site boundary.

SAT/UNSAT Step 4: c. If the Stack High Range Monitor equals or exceeds 20 mR/hr, request the Chemistry Technician to obtain a silver zeolite cartridge air sample from the main stack sample point for an iodine release rate determination.

Standard: Determines that this step is not applicable due to initial conditions.

SAT/UNSAT Step 5: d. If ODPS is operable, then implement Attachment 9.5 to access otT-site dose projection information fromODPS.

Standard: Determines that this step is not applicable due to initial conditions.

SAT/UNSAT Step 6: e. If ODPS is inoperable, then implement Attachment 9.1 to perform the applicable otT-site dose projections.

Critical Step

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 6 of 12 Evaluation Performance Steps Standard: Determines that this step is applicable and transitions to Attachment 9.1 Evaluator Note: The next several steps are from Attachment 9.1, Offsite Dose Projection Methodology When OOPS is Inoperable.

SAT/UNSAT Step 7: Obtain the necessary otT-site dose projection information for stack and ground release as follows:

a. IF A STACK RELEASE IS OCCURRING: have RP implement the NOMOGRAM METHOD-Attachment 9.12 Standard: Determines that this step is not applicable due to the release being a ground le:vel release.

SAT/UNSAT Step 8: b. IF A GROUND RELEASE IS OCCURRING:

(MEASURED SITE BOUNDARY DOSE RATE)

1) Obtain and record input data as follows:

a) Lower Wind Direction (Use 15 min avg data from MET DATA HISTORY-I or use alternate methods on Attachment 9.7) b) Assume Stability Class is as follows: (A unstable)

Standard: Operator records wind direction as 90 degrees on Attachment 9.1 based on initial conditions.

Critical Step

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 7 of 12 Evaluation Performance Steps SAT/UNSAT *Step 9: Obtain and record below the Whole Body Dose Rate (waist height reading) from the Site Boundary Team, or Attachment 9.16, Section A.

Standard: Records 300 mR/hr on attachment 9.1 and uses this value in subsequent calculation.

Evaluator Note: Attachment 9.1 includes a note at this point which directs the operator to use a release duration of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months unless a more defmitive number is available.

Interim Cue: If asked, Cue as Shift Manager to use a release duration of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SAT/UNSAT *Step 10: 2) Calculate the Ground Site Boundarv Dose

,(H) and record below as follows:

Site Boundary Whole Body Dose Rate in mRihr R I Dura* . H Dose (R) = mR x e ease bon m ours 1000-R Standard: Operator determines that the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Boundary Dose is 2.4 R SAT/UNSAT Step 11: Use the applicable meteorological data (wind direction and stability class) and Site Boundary Dose results from above to do the following:

Standard: Operator determines that the remainder of the attachment is not applicable to the task Evaluator Note: The remaining two steps address the task of determining whether RPV-ED is required.

Critical Step

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 8 of 12 Evaluation Performance Steps SAT/UNSAT *Step 12: Review EOP-4 and determine conditions requiring RPV-ED.

Standard: Determines that RPV-ED is required BEFORE Offsite radioactive release rate reaches a general Emergency EAL per AP 3125.

Evaluator Note: The above step may have been completed at the onset of the JPM.

SAT/UNSAT *Step 13: Review AP 3125, Appendix A Hot VY EAL chart Offsite Rad Conditions associated with a General Emergency EAL.

Standard: Operator determines that GE EAL AG 1.2 has been exceeded in that based on a release duration of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , an individual at the :site boundary, downwind of the release point would receive a dose of 2.4 R (EAL threshold being 1 R).

Operator determines that RPV-ED IS now required.

I Evaluator Note: Per the defmition of a "before" statement, if the condition has already occurred when the instruction is reached, the action should still be performed unless expressly prohibited. Therefore an RPV-ED is required.

Interim Cue: When the operator has completed the determination of whether an RPV-ED is required, Cue that the opc~rator has completed the assigned task.

SAT/UNSAT Step 5: Place Keeping and STAR used consistently throughout.

Standard: Steps are circled as performed, crossed out as completed and N/A'd as appropriate. STAR used consistently for each manipulation.

Critical Step

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 9 of 12 Evaluation Performance Steps TIME FINISH: ,_ _ __

Terminating Cue: The operator has determined the dose that would be received at the site boundary is 2.4 Rand that an RPV-ED is required.

Critical Step

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 10 of 12 Evaluator Comments:

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 11 of 12 Tear Out Sheet Initial Conditions:

The plant was at rated conditions when a fuel damaging event occurred

Following the scram a steam leak occurred in the turbine building

The steam leak caused the turbine building blowout panels to open to relieve turbine building pressure

Only partial isolation of the steam leak has been achieved

The Stack Gas Monitor readings (RM 17- 156 and 157) are elevated but remain below the high alarm setpoint

Stack Gas High Range Monitor (RM 17-155) is reading 1.5 mRihr

The wind direction via the 15 min avg data by MET DATA HISTORY-I is from 90 degrees

The Shift Manager has directed entry into EOP-4, Radioactivity Release Control

The Emergency Centers (TSC, OSC, EOF, JIC) have not yet been activated

ODPS is not available

The operating crew is considering whether an RPV -ED is required lAW EOP-4 Initiating Cues:

Conduct an Initial Evaluation of Off-Site Radiological Conditions lAW OP 3513, Evaluation of Off-Site Radiological Conditions. Determine whether an RPV -ED is required based on that assessment. The Shift Manager will determine if any Protective Action Recommendations are required following your assessment.

JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 12 of 12 JPM Attachment 1 FOR TARAININGONLY OP 3513, Attachment 9.16, Excerpt Only

-~Entergy VYNPS EMERGENCY PLAN IMPLEMENTING PROCEDURES

!NON-QUALITY RElATED PROCEDURE REFERENCE USE OP 3513 Page y Rev.36 of §!l Attachment 9.16 TEAM STATUS LOG Sheet :L of 2 Info current at: Time: 5 Minutes ago Date: Today Sample Location: Downwind at Site Boundary Team:

~ 0 Green 0 Blue A. WHOLE BODY DOSE RATE RESULTS

1. Frisker Reading:

a. Waist Height GCPM b. 2" Above Ground GCPM

2. Dose Rate Meter Reading:

a. Waist Height 300 mR/hr b. 2" Above Ground 95 mR/hr

3. To ensure that the Radiological Assessment Coordinator receives the whole body dose rate results expeditiously, forward whole body dose rate results to Radiological Assistant Assessment Coordinator in EOF before an air sample is taken.

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 1 of 10 VERMONT YANKEE JOB PERFORMANCE .MEASURE WORKSHEET Task Identification:

Title:

Activate the INFORM Notification System Failure Mode: NA

Reference:

EPAP-INFORM-10076 "'INFORM Notification System" Task Number: 34202603 Task Performance: AOIRO/SRO RO/~ X SEOnly Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom X Simulator Plant Performance Expected Completion Time: minutes Evaluation Results:

Performance: PASS _ FAIL __ Time Required:

Prepared by:

Facility Exam Developer Date Reviewed by:

SRO Licensed /Certified Reviewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 2 of 10 Directions Discuss the information given on this pag4~ with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk(*), it is a criticallitep. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Classroom and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

The plant was at 50% power for CW chlorination

Due to a loss of station air, the outboard MSIV's drifted shut

The reactor did not automatically scram

The OATC initiated the scram using the m<mual scram pushbuttons

All rods are now in and reactor power is on ranges 5-6 of the IRM' s and lowering fast

RPV pressure and level are stable in normal bands using HPCI in pressure control and feedwater for level control

Due to the MSIV closures, DW pressure is 6.2 psig and lowering slowly

There are no indications of a radiological release Initiating Cues:

The Shift Manager directs you to determine the EAL for the stated plant conditions and activate the ERO using the InForm notification system lAW EPAP-InForm-0076.

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 3 of 10 Task Standards:

All of the following:

EAL SA2.1 correctly determined

InForm notification completed Required Materials:

AP 3125, EMERGENCY PLAN CLASSIFICATION AND ACTION LEVEL SCHEME

EPAP-INFORM-10076 "INFORM Notific:ation System"

Simulator computer terminal with the InForm program Simulator Setup:

Computer Terminal with the InForm application on it

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 4 of 10 Evaluation Performance Steps TIME START:

SAT/UNSAT Step 1; Obtain procedure AP 3125, Emergency Plan Classification and Action Level Scheme Standard: Procedure reviewed.

Evaluator Note Operator may review precaution and limitations or proceed directly to Attachment 'A', Chart of categories and events.

SAT/UNSAT *Step 2: Operator evaluates initial conditions against the EAL's.

Standard: Stated plant initial conditions reviewed against action categories.

Evaluator Note: An EAL determination of SA2.1 based on stated plant conditions is declared to the Shift Manager.

Interim Cue: When informed as SM of EAL determination, direct the Operator to complete the appropriate ERO notification.

SAT/UNSAT Step 3: Operator obtains procedure EPAP-INFORM-10076.

Standard: Operator reviews the procedure precaution and limitations.

Critical Step

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 5 of 10 Evaluation Performance Steps SATIUNSAT *Step 4: Operator determines the InForm software is available on the computer at the STA desk.

Standard: Operator determines that the Icon is available on the STA computer desktop.

SAT/UNSAT *Step 5: Operator accesses the Inform software.

Standard: Uses the installed icon.

SAT/UNSAT Step 6: Operator prepares the form:

Standard: Operator clicks on the Plant Information tab SAT/UNSAT Step 7: Operator enters the following information:

Standard: A. Event Type: (Select 'Training Event' from the dropdown menu)

Evaluator cue: Ensure the operator selects 'Training event' B. This is: (Select 'Initial notification' from the dropdown menu)

C. Form filled out by: (Name of individual filling out the form)

D. Location: (Select 'Control room' from the dropdown menu)

E. We have: (Select 'Declared' from the dropdown menu)

Critical Step

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 6 of 10 Evaluation Performance Steps SAT/UNSAT *Step 8: Operator selects the EAL classification.

Standard: Operator enters 'Alert' SAT/UNSAT Step 9: Operator enters: data on the form.

Standard: Operator enters:

G. At: (Input: time)

H. On: (Current date is automatically displayed)

SAT/UNSAT *Step 10: Operator selects the EAL number.

Standard: Operator enters EAL SA2.1 I. EAL Number: (Select from the dropdown menu)

Critical Step

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 7 of 10 Evaluation Performance Steps SATIUNSAT Step 11: Operator enter.; data on the form.

Standard: Operator enters:

J. Pilant Conditions: (Select 'Shutdown'from the dropdlown menu)

K. Radiological conditions: (Select 'Has not occurred' from the dropdown menu)

L. Vlind Speed: (Input speed from upper average)

M. \Vind Direction from: (Input direction)

N. Stability Class: (Select from the dropdown menu or use Alternate Stability Class Determination) Stability class input is only required if a radiological Protective Action Recommendation (PAR) is necessary during a General Emergency.

(This is NOT applicable)

0. Authorized By: (Evaluator name)

SATIUNSAT Step 12: Operator performs review of the form.

Standard: Operator enters:

1.1.1 CLICK on the "Show Notification Form" button 1.1.2 REVIEW information on the form for accuracy.

1.1.3 CLICK on the "Print" button to obtain a copy for approval SATIUNSAT Step 13: Operator obtains Emergency Director approval.

Standard: Operator asks evaluator to OBTAIN approval from the Emergency Dirt:=ctor.

Interim cue: Inform the operator that the Emergency Director approves of the notification.

SATIUNSAT *Step 14: Operator transmits the form.

Critical Step

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 8 of 10 Evaluation Performance Steps Standard: If approval is obtained THEN CLICK on the "Send Message" button.

Interim Cue: Inform the operator that the JPM is complete Time finish: - - - - - - - - - -

All of the following ha*ve been completed:

EAL SA2.1 (an Alert) declared and transmitted

Critical Step

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 9 of 10 Evaluator Comments:

JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 10 of 10 Attachment 2 Tear Oult Sheet Initial Conditions:

The plant was at 50% power for CW chlorination

Due to a loss of station air, the outboard MSN's drifted shut

The reactor did not automatically scram

The OATC initiated the scram using the manual scram pushbuttons

All rods are now in and reactor power is on ranges 5-6 of the IRM's and lowering fast

RPV pressure and level are stable in normal bands using HPCI in pressure control and feedwater for level control

Due to the MSN closures, DW pressure is 6.2 psig and lowering slowly

There are no indications of a radiological release Initiating Cues:

The Shift Manager directs you to determine the EAL for the stated plant conditions and activate the ERO using the InForm notification system lAW EPAP-InForm-0076.

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 1 of 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Place the Standby Fuel Pool Cooling System in Service Failure Mode: Insufficient Pump Flow

Reference:

OP 2179 Standby Fuel Pool Cooling System Task Number: 237180104 Task Performance: AO/RO/SRO RO/SRO Only X SEOnly Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom Simulator X Plant Performance Expected Completion Time:: minutes Evaluation Results:

Performance: PASS _ FAllJ __ Time Required:

Prepared by:

Facility Exam Developer Date Reviewed by:

SAO Licensed /Certified l=teviewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 2 of 11 Directions Discuss the information given on this page: with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are: performing.

Inform me upon completion of this task.

Initial Conditions:

The plant is shutdown for refueling.

RPV head removal is in progress.

Normal Fuel Pool Cooling pump P-9-1A is not available.

Normal Fuel Pool Cooling Pump P-9-1B is. in service but is vibrating excessively.

Preparations are underway to place the Standby Fuel Pool Cooling System, SFPC, in service.

Chemistry has been notified that the SFPC system is being placed in service.

'A' RBCCW heat exchanger is in service Initiating Cues:

Place the "B" Train of SFPC in service lAw* OP 2179 Standby Fuel Pool Cooling System, Section A. An AO is standing by to assist you.

ACS Service Water to SFPC (SW-216) will not be used.

Task Standards:

Following report of insufficient flow, STDBY PUMP P-19-28 is secured.

JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 3 of 11 Reguired Materials:

Copy ofOPOP-NFPC-2184, Normal Fuel Pool Cooling System

Copy ofOP 2179 Standby Fuel Pool Cooling System Simulator Setup:

Normal FPC pump P-9-18 in service.

Any IC where the Prerequisites of Procedure OP 2179 are met.

JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 4 of 11 Evaluation Performance Steps TIME START:

SAT/UNSAT Step 1; Obtain procedure OP-2179 and review Precautions, Limitations and Prerequisites.

Standard: Procedure reviewed, starts in section A.

Interim Cue: If asked, cue the operator that all prerequisites have been met.

If asked, spent fuel pool temperature is 100°F and stable.

SAT/UNSAT Step 2; Notify Chemistry that the SFPC will be placed in service and that sampling of the Standby FPC heat exchangers will be required per OP 4649.

Standard: Operator determines that step is has been completed based on the initial conditions and proceeds to the next step.

SAT/UNSAT Step 3; Ensure that leak check analyses of both SFPC heat exchangers is completed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to SFPC operation.

Standard: Operator informs CRS that a leak check analyses is required within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Interim Cue: Acknowledge the report as CRS.

SAT/UNSAT Step 4; Secure the normal FPC pumps per OPOP-NFPC-2184.

Standard: Operator obtains copy of procedure OPOP-NFPC-2184 and determines that section 7.12 section is appropriate.

Critical Step

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 5 of 11 Evaluation Performance Steps Evaluator Note: OP 2184 is now identified as OPOP-NFPC-2184, Normal Fuel Pool Cooling System The next 4 steps are contained within OPOP-NFPC-2184 SATIUNSAT Step 5; Remove demineralizer(s) from service per section on Removing a FID Unit from Service.

Standard: Operator now grn~s to section 7.3 of OPOP-NFPC-2184 and determines that an the steps are performed locally.

Operator directs AO to secure remove the F/D from service.

Interim Cue: As AO cue the Operator that the in service F/D has been removed from service.

SATIUNSAT *Step 6: Place FPC pumps P-9-lA and lB control switches to STOP.

Standard: On panel CAD Panel A momentarily places control switch for FPC pump P-9-1B to the STOP position. Pump running red light goes out, green light on.

Evaluator Note: Only CAD panel A is simulated. FPC pump P-9-1A is on CAD Panel B.

Interim Cue: When Operator provides indication that FPC pump P-9-1A is on CAD Panel B cue that P-9-1A is in STOP.

SATIUNSAT Step 7: Place skimmer pumps P-82-lA and B control switches to STOP.

Standard: Operator contacts AO and directs that the skimmer pumps be secured.

Critical Step

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 6 of 11 Evaluation Performance Steps Interim Cue Cue the operator as the AO that skimmer pumps have been secured.

SAT/UNSAT Step 8: For an extended shutdown, refer to Section 7.3 and backwash and clean F/Ds.

Standard: Operator questions the CRS as to whether the FIDs are to be backwashed and deaned.

Interim Cue: As CRS cue the Operator that the AO will backwash and clean the FIDs.

Evaluator Note The remaining steps are from procedure OP 2179 Standby Fuel Pool Cooling System.

SAT/UNSAT *Step 9: Close the normall FPC suction/discharge isolation valves:

FPC ISOI..ATION FPC-220, (CAD Panel B)

FPC ISOI..ATION FPC-221, (CAD Panel A)

Standard: On CAD Panel A,, operator momentarily places the control switch for FPC ISOLATION FPC-221 to the CLOSE position. The green light comes on immediately and the red light goes out after a period of time. Direct the AO to Close FPC 223, Fuel Pool Cooling Discharge Isolation.

Evaluator FPC ISOLATION FPC-220, is located on CAD Panel Band Note: also has position indicating lights on CAD Panel A.

When Operator provides indication that FPC-220 is located Interim on CAD Panel B, cue the Operator that FPC-220 is closed Cue: and that it also indicates closed on CAD Panel A. Notify the Operator that the AO reports FPC-223 is closed.

Step 10:

SAT/UNSAT Throttle open FPC HX SW OUT SW-257A(B), to achieve a flow of S678 gpm per FI-104-SOA(B) SERV WTR FLOW TO HX (CAD Panel B(A)).

Critical Step

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 7 ofll Evaluation Performance Steps Standard:

On panel CAD Panel 'A', holds control switch for FPC HX SW OUT SW-257B in the open position while observing SVl flow ~678 gpm on FI-104-80A(B) SERV WTR FLOW TO HX located directly above the SW-257B control switch.

SW flow does not exceed 678 gpm.

Evaluator Note: FPC ISOLATION FPC-220, is located on CAD Panel Band also has position indicating lights on CAD Panel A.

Interim Cue: When Operator provides indication that FPC-220 is located on CAD Panel B, cue the Operator that FPC-220 is closed and that it also indicates closed on CAD Panel A. Also, FPC-223 Start STDBY FPC PUMP P-19-2A(B) (CAD Panel B(A))

and observe:

SATIUNSAT *Step 11:

Standard: On CAD Panel A, operator momentarily places control switch for STDBY PUMP P-19-2B to the START position.

Red light on, green light out.

SATIUNSAT Step 12: Service water to SFPC AP remains ~0 psid per DPI-19-76A(B), FPC HX-2A(B) Ml(CAD Panel B(A)).

Standard: On CAD panel A,. operator verifies that the dp across the FPC HX-2B is 2:20 psid as indicated on DPI-19-76A(B),

Critical Step

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 8 of 11 Evaluation Performance Steps SAT/UNSAT Step 13: If plant conditions allow access to the 303' level of the reactor building:

1) On RK 10AA RB 303' SE. verify SFPC flow 700-800 gpm per FI-19-73.

2) If necessary, throttle SFPC-225, SFPC System Discharge to FP. to obtain the required SFPC flow.

Standard: Operator directs AO to verify SFPC flow is between 700 and 800 gpm.

Interim Cue: Inform operator that SFPC flow is steady at 300 gpm.

Evaluator Note: Precaution number 10 of OP-2ll79 states:

"In order to ensure adequate pump cooling, do not operate either SFPC pump at less than 350 gpm."

Interim Cue: If the operator asks the AO to adjust the valve, cue the operator that the valve is stuck and will not movt~.

SAT/UNSAT *Step 14: Operator secures operating SFPC pump based on inadequate flow Standard: On CAD Panel A, operator momentarily places control switch for STDBY PUMP P-19-2B to the STOP position.

Red light out, gree:n light on.

Evaluator Note: If the operator refers to section H, Short Term SFPCS Shutdown, the operator may also close FPC IDC SW OUT SW-257B prior to securing the pump. However the only cri1tical step is to secure the pump.

Interim Cue: Cue the operator that his/her task has been completed.

Critical Step

JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 9 of 11 Evaluation Performance Steps SAT/UNSAT Step 15: Place Keeping and STAR used consistently throughout.

Standard: Steps are circled as performed, crossed out as completed and N/A'd as appropriate. STAR used consistently for each manipulation.

TIME FINISH:

Terminating Cue: STDBY PUMP P-19-2B secured.

Critical Step

JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 10 ofll Evaluator Comments:

JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 11 of 11 Tear Out Sheet Initial Conditions:

The plant is shutdown for refueling.

RPV head removal is in progress.

Normal Fuel Pool Cooling pump P-9-lA is not available.

Normal Fuel Pool Cooling Pump P-9-lB is in service but is vibrating excessively.

Preparations are underway to place the Standby Fuel Pool Cooling System, SFPC, in service.

Chemistry has been notified that the SFPC system is being placed in service.

'A' RBCCW heat exchanger is in service Initiating Cues:

Place the "B" Train of SFPC in service INW OP 2179 Standby Fuel Pool Cooling System, Section A. An AO is standing by to assist you.

ACS Service Water to SFPC (SW-216) willl not be used.

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 1 of 10 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Emergency Venting of the Primary Containment Failure Mode: NA

Reference:

OE 3107 EOP/SAG Appendices, Appendix HH Task Number: 2007510504 Task Performance: AOIRO/SRO RO/SROOnly X SEOnly Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom Simulator X Plant Performance Expected Completion Time: minutes Evaluation Results:

Performance: PASS FAIL _ Time Required:

Prepared by:

Facility Exam Developer Date Reviewed by:

SRO Licensed /Certified Reviewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 2 of 10 Directions Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the: performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has fai11ed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

EOP-03 execution is in progress following a Steam Leak in the drywell.

Primary Containment pressure is> 50 pounds and rising slowly.

The SM has determined that venting of the containment is required to prevent exceeding thePCPL-A.

The SM has directed that the Torus be vented via the 8 inch hardened vent flowpath to the stack lAW OE 3107 EOP/SAG Appendices, Appendix HH, Section 5

All prerequisites for conducting the vent have been verified.

There is sufficient time to protect and isolate SGTS as required.

Steps 1 through 3a of OE 3107 EOP/SAG Appendices, Appendix HH, Section 5 have been completed Initiating Cues:

Commence torus (TVS-86) venting via the 8 inch hardened vent in accordance with OE 3107 EOP/SAG Appendices, Appendix HH, Section 5, and beginning at step 3.b.

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 3 of 10 Task Standards:

Torus venting in progress via the 8 inch hardened vent flowpath to the stack Reguired Materials:

Copy of OE 3107 EOP/SAG Appendices, Appendix HH, section 5, completed through step 3.a.

Two jumpers with banana plugs from the EOP toolbox in the Control Room Simulator Setup:

Insert mfPC_OSA Safety Relief Valve RV2-71A Line Break

Insert mfAD_OlA Relief Valve Leak RV271A Leak at 40% severity

Insert mfPC_15, Torus Ring Header at 100% severity

WHEN Torus Vent Valve TVS-86 is opened, DELETE mfPC_OSA Safety Relief Valve RV2-71A Line Break

When torus pressure rises to 57 psig, lower severity of mfPCOSA to 20% severity.

Adjust severity as necessary to maintain torus pressure between 57 and 65 psig.

When RPV pressure lowers to 300 psig, control injection flow to maintain RPV level in the normal range.

Verify control switches are in the specified position of Table 1 of OE 3107 EOP/SAG Appendices, Appendix HH

Place the simulator in 'Run' after the jumpers have been installed lAW step 3 Note: IC-966 has been created with the above conditions

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 4 of 10 Evaluation Performance Steps TIME START:

SAT/UNSAT Step 1: Obtain procedu.-e OE 3107 EOP/SAG Appendices, Appendix HH obtained and prerequisites reviewed.

Standard: Procedure OE 3107 EOP/SAG Appendices, Appendix HH obtained and prerequisites reviewed.

Interim Cue: If asked, cue the operator that all pre-requisites have been met and all required power supplies are available.

Evaluator Note: The next step of this JPM begins at step 3.b of Appendix HH and installs jumpers to defeat the Group III isolation signal.

SAT/UNSAT *Step 2; Install the following jumpers;

CRP 9-42: BBSl to AA28 (CWD 1112)

Standard: Obtain a jumper with banana plugs from the EOP toolbox and at panel CRP 9-42

install one end of jumper at terminal strip BB location :51.

install other end of jumper at terminal strip AA location 28.

Critical Step

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 5 of 10 Evaluation Performance Steps

Step 3:

CRP 9-41: BB51 to AA28 (CWD 1116)

SAT/UNSAT Standard Obtain a jumper with banana plugs from the EOP toolbox and at CRP 9-41:

Install one end of jumper at terminal strip BB location 51.

Install other end of jumper at terminal strip AA location 28.

SAT/UNSAT *Step 4: Place both SGTS fans to PfL.

Standard: On panel CRP 9--26, rotates control switch for SBGT FAN A REF 2A counterclockwise to the PTL position and pulls out to lock switch in the PTL position Green light on, red light out.

On panel CRP 9**26, rotates control switch for SBGT FAN B REF 28 counterclockwise to the PTL position and pulls out to lock switch in the PTL position. Green light on, red light out.

SAT/UNSAT *Step 5: CLOSE/confirm CLOSED the following:

1) SGT-3A DISCH ISOLATION Standard: On panel CRP 9-26, rotates control switch for DISCH ISOLATION SGT -3A counterclockwise to the CLOSE AUTO OPposition. Green light on, red light out.

Critical Step

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 6 of 10 Evaluation Performance Steps SAT/UNSAT *Step 6: 2) SGT-3B DISCH ISOLATION Standard: On panel CRP 9-26, verifies control switch for DISCH ISOLATION SGT-3B is in the CLOSE AUTO OPposition and that the assodated the green light is on and the red light is out.

SAT/UNSAT Step 7: 3) SGT-6VENTTOSGTS Standard: On panel CRP 9-26, verifies the control switch for VENT TO SGTS SGT-6 is in the CLOSE position and that the associated the gr1een light is on and the red light is out.

SAT/UNSAT Step 8: 4) SGT-lAINLETBYPASS Standard: On panel CRP 9-*26, verifies the control switch for INLET BYPASS SGT-lA is in the CLOSE AUTO OPposition and that the associated the green light is on and the red light is out.

SAT/UNSAT Step 9: 5) SGT-lB INLET BYPASS Standard: On panel CRP 9--26, verifies the control switch for INLET BYPASS SGT-lB is in the CLOSE AUTO OPposition and that the associatt~d the green light is on and the red light is out.

SAT/UNSAT Step 10: OPEN the following:

1) SGT-2A INLET ISOLATION Standard: On panel CRP 9-26, determines that SGT-2A INLET ISOLATION is already open by observing that the associated green light is out and that red light is on.

Critical Step

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 7 of 10 Evaluation Performance Steps SAT/UNSAT Step 11: 2) SGT-28 INLET ISOLATION Standard: On panel CRP 9-26 rotates the control switch for INLET ISOLATION SGT -2B to the OPEN position and verifies green light off and red light on.

SAT/UNSAT Step 12: 3) SGT-4A COOL AIR INLET Standard: On panel CRP 9-26 rotates the control switch for COOL AIR INLET SGT-4A to the OPEN position and verifies green light off ailld red light on.

SAT/UNSAT Step 13: 4) SGT -48 COOL AIR INLET Standard: On panel CRP 9--26 rotates the control switch for COOL AIR INLET SGT-48 to the OPEN position and verifies green light off and red light on.

SAT/UNSAT *Step 14: Torus Venting through TVS-86; To vent the ton1s, OPEN TVS-86 TORUS VENT VL V.

Standard: Obtain the key and on panel CRP 9-25 rotates the control switch for TVS-86 TORUS VENT VLV momentarily to the OPEN position ~md verifies red light on and the green light extinguishes aft(:r a period of time.

Reports to the CRS that Torus Venting is in progress.

Interim Cue: Inform the Operator that the task is complete

Critical Step

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 8 of 10 Evaluation Performance Steps SAT/UNSAT Place Keeping and STAR used consistently throughout.

Standard: Steps are circled as performed, crossed out as completed and N/A'd as approprilate. STAR used consistently for each manipulation.

TIME FINISH:

Terminating Cue: Torus venting is in progress via TVS-86 through the hardened vent path to the stack.

Critical Step

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 9 of 10 Evaluator Comments:

JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 10 of 10 Tear Out Sheet Initial Conditions:

EOP-03 execution is in progress following a Steam Leak in the drywell.

Primary Containment pressure is> 50 pow1ds and rising slowly.

The SM has determined that venting of the containment is required to prevent exceeding thePCPL.

The SM has directed that the Torus be vented via the 8 inch hardened vent flowpath to the stack lAW OE 3107 EOP/SAG Appendices, Appendix HH, Section 5

All prerequisites for conducting the vent have been verified.

There is sufficient time to protect and isolate SGTS as required.

Steps 1 through 3a ofOE 3107 EOP/SAG Appendices, Appendix HH, Section 5 have been completed Initiating Cues:

Commence torus (TVS-86) venting via the 8 inch hardened vent in accordance with OE 3107 EOP/SAG Appendices, Appendix HH, Section 5, and beginning at step 3.b.

JPM 2014A NRC S-3 Rev.l,03/14 Page 1 of 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

RCIC Manual Injection for RPV Level Control Failure Mode: RCIC Trips and mus1t be reset with an initiation signal present

Reference:

OP 2121. Reactor Core Isolation Cooling System Task Number:

Task Performance: AOIRO/SRO RO/SROOnly X SEOnly Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom Simulator X Plant Performance Expected Completion Time: minutes Evaluation Results:

Performance: PASS _ FAIL __ Time Required:

Prepared by:

Facility Exam Developer Date Reviewed by:

SRO Licensed /Certified Reviewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC S-3 Rev. 1,03/14 Page 2 of 11 Directions Discuss the information given on this page: with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

The reactor was at full power when a small Recirc leak caused Drywell pressure to approach 2.5 psig.

When the Reactor was manually scrammed a loss of all normal feed occurred.

All initial actions of OT 3100 have been completed

HPCI is not available

. ADS has been inhibited

RPV level is approximately 100 inches and lowering slowly Initiating Cues:

Start RCIC in the injection mode and restore RPV level to between 127 and 177 inches.

Task Standards:

RCIC is injecting in Automatic at 400 gpm after reset Required Materials:

Copy of OP 2121, Reactor Core Isolation Cooling System

ARS 21002, 4-T-1, RCIC Turbine Trip ARS

JPM 2014A NRC S-3 Rev.l,03/14 Page 3 of 11 Simulator Setup:

From any full power IC perform the following in the specified sequence:

o Insert RR_01A at 0.5%

o Insert mfliPOl, HPCI Turbine Trip, IMP mfHP_01 f: 1 or take HPCI to 'Inhibit' o Trip all Reactor Feed Pumps and SCRAM the reactor. Complete SCRAM initial actions.

o Insert mtRCOl, RCIC Turbine Trip, on KEY 1: {key[l]}IMF mtRC_Ol f:O k:l after Step #9 o When level lowers to below the RCIC auto initiation setpoint, DELETE mtRCOl, RCIC Turbine Trip, DMF mtRC_Ol o Place compensated wide range level indication on CRP 9-6

JPM 2014A NRC S-3 Rev.1,03/14 Page*4 of 11 Evaluation Performance Steps TIME START:

SAT/UNSAT Sl~ul; Obtain mini procedure OP 2121~ Appendix C~

MANUAL RCU~ IN.JECTION.

Standard: Retrieves mini procedure from CRP 9-4.

SAT/UNSAT Stco 2; Open lube oil COOLING WATER RCIC-132.

Standard: On panel 9-4 takes RCIC-132 control switch Clockwise to Open. Observes Red light lit and Green light out.

SAT/UNSAT Step 3; Start GLAND SEAL VACUUM PUMP.

Standard: Takes the Gland Seal Vacuum Pump control switch to the right to Start. Observes SAT/UNSAT Step 4; Open MINIMUI\f FLOW RCIC-27.

Standard: Takes RCIC-27 control switch Clockwise to Open.

Observes Red light lit and Green light out.

SAT/UNSAT *Step 5: Open STEAM SUPPLY RCIC-131.

Standard: Takes RCIC-131 (:ontrol switch Clockwise to Open.

Observes Red light lit and Green light out.

Critical Step

JPM 2014A NRC S-3 Rev.1,03/14 Page 5 of 11 Evaluation Performance Steps SAT/UNSAT Step 6; Confirm turbine start by observing TURBINE SPEED SI 13-2 and PUMP DISCHARGE PRESSURE PI 13-93 increasing.

Standard: Verifies turbine speed and pump discharge pressure increasing.

If RCIC FLOW CONTROLLER FIC 13-91 automatic SAT/UNSAT Step 7: feature fails or significant flow oscillations occur:

Standard: Operator determin.es that the controller operating properly by observing stable flow indication and controller output meter indications .

SAT/UNSAT *Step 8: Open PUMP DISCHARGE RCIC-21.

Standard: Takes RCIC-21 control switch Clockwise to Open.

Observes Red light lit and Green light out.

SAT/UNSAT Steo 9; Verify that MINIMUM FLOW RCIC-27 closes (automatic) at approximately 80 gpm.

Standard: Verifies that RCIC-27 auto closes at approximately 80 gpm.

Evaluator Note: Enter KEY 1 after RCIC injection has been initiated and RPV water level is below 82.5 inches.

SAT/UNSAT Steo 10; Acknowledge and respond to RCIC Turbine TRIP.

Standard: Notes Turbine trip alarm, informs CRS and then refers to ARS 4-T-1 and OP 2121 section G.

Critical Step

JPM 2014A NRC S-3 Rev.1,03/14 Page 6 of 11 Evaluation Performance Steps SAT/UNSAT Step 11: If any valid trip condition exists, verify:

a. TRIP THROTTLE RCIC-1 is closed.

Standard: On CRP 9-4 verifies RCIC-1 Green light LIT and Red light OUT.

b. MINIMlJM FLOW RCIC-27 is closed.

SAT/UNSAT Step 12:

Standard: On CRP 9-4 verifies RCIC-27 Green light LIT and Red light OUT.

SAT/UNSAT Steg 13; If an initiation signal is present then reset the turbine trip per the RCIC Turbine Reset With Initiation Signal Present section of this procedure.

Standard: Verifies that an in~ection signal is present (RPV water level below 82.5 inches) and goes to section H of OP 2121 to reset RCIC.

SAT/UNSAT Steu 14; For a turbine overspeed trip, locally reset the mechanical overspeed trip linkage as follows:

Standard: Informs CRS of need to fmd the cause of the turbine trip in order to determine:: need/method to reset RCIC-1.

Interim Cue: Inform the operator that the RCIC trip throttle valve (RCIC-1) trip latch was inadvertently tripped while locally monitoring turbine operation. The relatch trip linkage has been manipulated to reset RCIC-1 trip linkage (Step H.1. is complete).

Evaluator Note: Delete malfunction RC_01.

Critical Step

JPM 2014A NRC S-3 Rev. 1,03/14 Page 7 of 11 Evaluation Performance Steps SAT/UNSAT *Step 15: When the cause of the trip signal has been corrected and all the turbine trip signals have cleared, then reset TRIP THROTTLE RCIC-1 as follows:

c. Place RCIC PUMP FLOW CONTROLLER FIC 13-91 in MAN and set to 50% demand.

Standard: On RCIC PUMP FLOW CONTROLLER FIC 13-91 on CRP9-4:

Rotates sdector switch clockwise to the MAN position

Adjusts manual potentiometer until the controller output meter (meter above selector switch) indicates 50% of scale.

SAT/UNSAT *Step 16: d. Place and hold TRIP THROTTLE RCIC-1 RESET switch in the RESET position.

Standard: On panel CRP 9-4, vertical section, rotates the TRIP THROTTLE RCIC-1 RESET switch clockwise to the RESET position ~md holds it there until RCIC-131 reaches the full closed position (see next two steps).

Evaluator Note: Valve STEAM SUPPLY RCIC-131 will stroke full close in the next step and then reopen because an initiation signal is present. However the trip will reset when the valve reaches the full close position.

SATIUNSAT *Step 17: e. Place STEAM SUPPLY RCIC-131 to CLOSE and release.

Standard: On panel CRP 9-4, momentarily places control switch for STEAM SUPPLY RCIC-131 valve in the CLOSE position.

Critical Step

JPM 2014A NRC S-3 Rev.l,03/14 Page 8 of 11 Evaluation Performance Steps SAT/UNSAT *Step 18: f. When RCIC-131 reaches full closed, then release RCIC-1 reset switch Standard: On panel CRP 9-4, releases the TRIP THROTTLE RCIC-1 RESET switch when valve STEAM SUPPLY RCIC-131 is full closed. White light above the reset switch is illuminated.

Evaluator Note: RCIC may not actually inject into the RPV during the next step if discharge pressure is less than RPV pressure.

g. Verify that after a few seconds RCIC-1 opens and SAT/UNSAT Step 19: the turbine starts and runs at reduced speed.

Standard: On panel CRP 9-4 verifies RCIC-1opens by observing indicating lights. Pump discharge pressure and turbine speed increases and stabilizes on CRP 9-4 vertical.

SAT/UNSAT Step 20: Adjust the flow controller setpoint tape to null automatic and manual demand signals.

Standard: Adjusts setpoint tape adjust on RCIC flow controller until deviation meter on the controller is mid-scale indicating that the automatic and manual demand signals are nulled.

SAT/UNSAT *Step 21: Place the flow controller in AUTO.

Standard: Rotates the selector switch on the controller counterclockwise to the AUTO position.

SAT/UNSAT Step 22: If equalization or RCIC steam line Ap was required, close/check closed:

Critical Step

JPM 2014A NRC S-3 Rev.1,03/14 Page 9 of 11 Evaluation Performance Steps Standard: Operator determines that this step is not applicable and continues on to the next step.

SAT/UNSAT Step 23: Enter RCIC Automatic Initiation section of this procedure.

Standard: Operator transitions to Section B, RCIC Automatic Initiation SAT/UNSAT Step 24: When the RCIC System initiates, the following steps should be taken:~

Maintaining pump flow at 400 gpm using RCIC PUMP FLOW CONTROLLER FIC 13-91.:

Standard: On panel CRP 9-4, operator increases flow to 400 gpm by raising the setpoint tape adjust until flow indicator on controller indicates 400 gpm.

Interim Cue: Cue operator that the operator' H task has been completed.

SAT/UNSAT Step 25: Place Keeping and STAR used consistently throughout.

Standard: Steps are circled as performed, crossed out as completed and N/A'd as appropriate. STAR used consistently for each manipulation.

TIME FINISH:

Terminating Cue: RCIC controller is in Auto and the system is injecting at 400 gpm.

Critical Step

JPM 2014A NRC S-3 Rev.l,03/14 Page 10 of 11 Evaluator Comments:

JPM 2014A NRC S-3 Rev.1,03/14 Page 11 of 11 Tear Out Sheet Initial Conditions:

The reactor was at full power when a smaH Recirc leak caused Drywell pressure to approach 2.5 psig.

When the Reactor was manually scrammed a loss of all normal feed occurred.

All initial actions of OT 3100 have been completed

HPCI is not available

ADS has been inhibited

RPV level is approximately 100 inches and lowering slowly Initiating Cues:

Start RCIC in the injection mode and restore RPV level to between 127 and 177 inches.

JPM 2014A NRC SRO P-1 Rev. 0, 03114 Page 1 of6 VERMONT YANKEE{PRIVATE }

JOB PERFORMANCE :MEASURE WORKSHEET Task Identification:

Title:

Place Standby CRD Flow Control Valve in Service

Reference:

OPON-3145-01, Loss ofCRD Regulating Function Rev. 4 Task Number: 2007280501 Task Performance: AO/RO/SRO _lL RO/SRO _ SRO Only_

Sequence Critical: Yes No ._X Time Critical: Yes No ._X Operator Performing Task: - - - - - - - - * - - -

Examiner: _______________________

Date of Evaluation: --------------

Activity Code: _ _ _ _ _ _ _ _ __

Method of Testing: Simulation .x_ Performance Discuss Setting: Classroom_ Simulator_ Plant X Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS FAIL Time Required:

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Exam Developer Date Reviewed by =---------------

SRO Licensed/Certified Reviewer Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.

Operations Training Superintendent Date

JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page 2 of6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling dther "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Plant and you are to simulate all actions while exercising ALARA, being respective of plant Protected Areas and identifying components to the evaluator's satisfaction.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

Plant at 100% power.

A mechanical failure of the operating CRD flow control valve has occurred. OPON-3145-01 has been entered.

Initiating Cues:

You are the in-plant operator. The CRS directs you to place the Standby CRD FCV in service in accordance with OPON-3145-01 step 6.1.2.

Task Standards:

The Standby CRD flow control valve in service.

Required Materials:

OPON-3145-01, Loss ofCRD Regulating Function

JPM 2014A NRC SRO P-1 1 Rev. 0, 03/14 Page 3 of6 Evaluation Performance Steps T~ESTART: ___________

SATIUNSAT Step 1: Obtain procedure; review admin limits, precautions, pre-requisites.

Standard: Procedure obtained, admin limits, precautions, prerequisites.

Interim Cue: If asked, all prerequisites are met. Place the FCV that is in standby into service.

SATIUNSAT Step 2: From CRP 9-5, DIAL the flow controller (FIC-3-301) in MANUAL to zero valve position.

Standard: Operator requests Control Room Operator to shift the CRD Flow Controller to MANUAL and close FCV-3-19A(8)

Interim Cue: Inform Operator that the CRD Flow Controller has been shifted to MANUAL and FCV 19A(8) is closed.

SATIUNSAT Step 3: Isolate the flow control valve CRD FCV-19A(B) being removed from service as follows:

a) Close CRD-68A(B), Inlet To CRD FCV-19A(B).

b) Close CRD-69A(B), Outlet Of CRD FCV-19A(B)

Standard: CRD-68A and 69A (688/698) valve handles rotated clockwise until valves full shut.

Interim Cue: Handles rotate freely clockwise, valve sterns move inward until resistance is felt, and valve handle stops moving.

JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page4 of6 Evaluation Performance Steps SAT/UNSAT *Step 4: Select CRD FCV-19A(B) to be placed in service at the liP Converter Selector Switch.

Standard: Local FCV-3-19A(8) liP Converter selector switch located behind FCV 19A (198), and taken to FCV-3-19B(A)

Interim Cue: The switch handle rotates freely to the FCV-3-19B(A) position.

SAT/UNSAT *Step 5: Position loca13-way valve CRD-126, Supply Air to FCV, to flow control valve CRD FCV-l9A(B) to be placed into service.

Standard: CRS SA-3-126, located on the CRD flow control pneumatic control panel to 207A(8)

Interim Cue: Valve control knob rotates freely until resistance is felt with the pointer at the 207 A(B) position.

SAT/UNSAT *Step 6: For the flow control valve CRD FCV-19A(B) being placed in service:

a) Open CRD-68A(B), Inlet To CRD FCV-19A(B).

b) Open CRD-69A(B), Outlet OfCRD FCV-19A(B).

Standard: CRD-688 and 698 (68A/69A) handles rotated counter-clockwise until full open.

Interim Cue: Valve handles rotate freely counter-clockwise and valve stems move outward until resistance is felt and handle stops moving.

JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page 5 of6 Evaluation Performance Steps SAT/UNSAT Step 7: Adjust CRD parameters at CRP 9-5 to normal operating ranges.

Standard: Operator calls Control Room to inform them the alternate FCV has been placed in service and to adjust CRD parameters.

Interim Cue: When operator desires to contact the Control Room, inform him that CRD parameters have been adjusted. Control room asks what the local charging header pressure gauge reads.

SAT/UNSAT Step 8: If required, throttle CRD-36A(B), CRD Pump A(B) Discharge Stop Check, to maintain charging header pressure at 1420-1470 psig (PI-3-234).

Standard: Operator checks charging header pressure on PI-3-234 and reports it to the control room.

Interim Cue: The control reports no further adjustments are needed.

SATIUNSAT Step 9: Place Keeping and STAR used consistently throughout.

Standard: Steps are circled as performed crossed out as complete and N/A'd as appropriate. STAR Utsed consistently for each simulated manipulation.

Critical Step TIME F I N I S H : - - - - - - - - -

Terminating Cue: The Standby CRD FCV is placed in service.

JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page6 of6 Evaluators Comments:

System: 201001 K/A's: Kl.08 K3.03 K4.12 K6.03 Kl.09 K6.06 Al.03 A2.02 A2.07 Generic K/A's: 2.1.27 2.1.10 2.2.25 2.1.28 2.1.30 2.1.32 2.1.23

JPM SRO P-1 Handout Rev. 0, 3/14 Page 1 of 1 EXAMINEE HANDOUT Initial Conditions:

Plant at 100% power.

A mechanical failure of the operating CRD flow control valve has occurred. OPON-3145-01 has been entered.

Initiating Cues:

You are the in-plant operator. The CRS directs you to place the Standby CRD FCV in service in accordance with OPON-3145-01 step 6.1.2.

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 1 of9 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Locally Start an EDG During Station Blackout Failure Mode: NA

Reference:

OPOT-3122-02. Station Blackout Task Number: 2640090101 Task Performance: AOIRO/SRO X RO/SRO Only SEOnly Sequence Critical: Yes No Time Critical: Yes No Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation X Performance Discuss Setting: Classroom Simulator Plant Performance Expected Completion Time: minutes Evaluation Results:

Performance: PASS _ FAIL __ Time Required:

Prepared by:

Operations Training Instmctor Date Reviewed by:

SRO Licensed /Certified R1;::viewer Date Approved by:

Operations Training Superintendent Date

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 2 of9 Directions Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Plant and you are to simulate all actions while exercising ALARA, being respective of pl:mt Protected Areas and identifying components to the evaluator's satisfaction.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

Station Blackout Conditions Exist

OPOT-3122-02, Station Blackout, e~xecution is in progress

The "A" Diesel Generator tripped upon initial startup due to a Generator Lockout

The cause of the lockout has been repaired Initiating Cues:

You are the in-plant operator. The CRS directs you to reset and restart the "A" Diesel Generator lAW OPOT-3122-02, Station Blackout commencing at step 3.5.2. C Task Standards:

The "A" EDG is running and the REMOTE/AT ENGINE control switch is in REMOTE.

Reguired Materials:

OPOT-3122-02, Station Blackout

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 3 of9 Simulator Setup: NA

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 4 of9 Evaluation Performance Steps TIME START:

SAT/UNSAT Steo 1; Obtain procedure; review admin limits, precautions, pre-requisites.

Standard: Procedure obtained, admin limits, precautions, prerequisites.

Interim Cue: If asked, report that all pre-requisites have been met for resetting the lockout and starting the diesel. EDG lB, E-1 , Start Failure, alarm is in.

SAT/UNSAT *Step 2: PLACE diesel engine panel REMOTE/AT ENGINE control switch to AT ENGINE position to remove auto start capabilities.

Standard: Operator places control switch to AT ENGINE position.

Interim Cue: Switch is in AT ENGINE position. Alarm LOCAL ENGINE CONTROL annunciates (DA-G-1). Prompt, if needed as CRS, "Continue to start EDG

'B'.

SAT/UNSAT Step 3: ASSIST in resolvi.ng cause of the trip.

Standard: Operator determin:s that this step is not applicable and continues with next step.

Interim Cue: The cause of the trip has been msolved but lockout device is tripped.

SAT/UNSAT *Step 4: RESET any lockout.

Standard: Operator turns red handle lockout reset on the diesel room control panel in the clockwise direction

Critical Step

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 5 of9 Evaluation Performance Steps Interim Cue: Lockout device is reset. The lockout relay light illuminates. Control room reports that the DG-A Lockout: Trip alarm has cleared.

SAT/UNSAT *Step 5: DEPRESS reset pushbutton on diesel engine panel to reset shutdown relay.

Standard: Pushbutton depressed and released Interim Cue: Pushbutton depresses when pushed and springs back when released.

SAT/UNSAT *Step 6: WAIT for stopping relay to time out (approximately 100 seconds).

Standard: Operator waits at least 100 seconds before proceeding.

Interim Cue: When operator indicates that he/she is waiting at least 100 seconds then cue that > 100 seconds has elapsed.

SAT/UNSAT *Step 7: Auto start diesel by placing REMOTE/AT ENGINE control switch to REMOTE.

Standard: Operator places control switch to REMOTE position.

Interim Cue: Switch is in the REMOTE position. Alarm LOCAL ENGINE CONTROL clears (DA-G-1).

After a few seconds cue the operator that the diesel is not rolling.

Critical Step

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 6 of9 Evaluation Performance Steps SAT/UNSAT *Step 8: IF diesel does not roll, THEN OPEN AS-24-2A(B) air start solenoid as follow..!:,

1. ROT ATE manual operator stem clockwise 180 degrees.

2. LEAVE manual override engaged for at least 15 secon~

until diesel starts, Standard: Operator rotates manual operator 180 degrees in the clockwise direction Interim Cue: The Manual Operator Stem is rotated 180 degrees. Cue the operator that air is heard flowing and that the di1esel engine is rolling.

SAT/UNSAT *Step ROTATE stem counterclockwise 180 degrees to disengage 9: manual operator.

Standard: Operator rotates manual operator 180 degrees in the counterclockwise direction.

Interim Cue: The Manual Operator Stem is now back in its original position. The diesel is now up to 900 RPM.

SAT/UNSAT Step 10: REPORT diesel status to the SM.

Standard: Operator informs the SM that the diesel is running Interim Cue: Acknowledge the operator's report. Inform the operator that the task is complete.

Critical Step

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 7 of9 Evaluation Performance Steps SAT/UNSAT Step 11: Place Keeping and STAR used consistently throughout.

Standard Steps are circled as performed crossed out as complete and N/A'd as appropriate. STAR used consistently for each simulated manipullation.

TIME FINISH: _ _ __

Terminating Cue: The "A" EDG is running and the REMOTE/AT ENGINE control switch is in REMOTE.

Critical Step

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 8 of9 Evaluator Comments:

JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 9 of9 Tear Out: Sheet Initial Conditions:

Station Blackout Conditions Exist

OPOT-3122-02, Station Blackout, 'execution is in progress

The "A" Diesel Generator tripped upon initial startup due to a Generator Lockout

The cause of the lockout has been repaired Initiating Cues:

You are the in-plant operator. The CRS directs you to reset and restart the "A" Diesel Generator lAW OPOT-3122-02, Station Blackout commencing at step 3.5.2. C

v t e Letter Sequence Other
TAC:U01897, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML14055A041, ML14059A542, ML14059A546, ML14063A514, ML14064A051, ML14164A048
MONTHYEAR2014-02-14 [Table View]

ML14164A048

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