ML14164A048
| ML14164A048 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png (DPR-028) |
| Issue date: | 03/25/2014 |
| From: | NRC Region 1 |
| To: | |
| Shared Package | |
| ML13204A095 | List: |
| References | |
| TAC U01897 | |
| Download: ML14164A048 (98) | |
Text
JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 1 of 11 Task Identification:
VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET
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 Reviewed by:
SRO Licensed /Certified Reviewer Approved by:
Operations Training Superintendent Date Date Date
Directions JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 2 of 11 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.
Task Standards:
All of the following:
JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 3 of 11 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 MAPRA T are identified as having exceeded their Admin Limits MAPRA T 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
- to this JPM, For Training, 3D Monicore Case Blank Core Thermal Hydraulics Limit Evaluation (VYOPF 4401.01) form VY Tech Specs Simulator Setup:
NA
Evaluation SAT/UNSAT Performance Steps TIME START:
JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 4 of 11 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 Interim Cue:
SATIUNSAT Interim Cue:
- Critical Step
- Step 2:
Records the required information on VYOPF 4401.01.
Standard:
Steps 1 through 6 of form completed with all critical elements satisfied.
If asked cue that the control rod positions as indicated on CRP 9-5 are the same as indicated on the 3D Monicore printout.
- 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).
If asked, cue that the APRM system gains using the REO display on ERFIS are the same as indicated on the 3D Monicore Case.
Evaluation SATIUNSAT SATIUNSAT SATIUNSAT 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, APRM "B" must be declared inoperable.
- Step 5:
Operator compares current values for MFLCPR1 MFLPD and MAPRA T to the Admin Limits {step 8 of form).
Standard:
Determines that MFLPD and MAPRA T have exceeded their Admin Limits.
- Ste)! 6:
O)!£rator determines the reguired action for exceeding; the Admin Limits Standard:
Operator determines that Reactor Engineering must be contacted.
- Sten 7:
Operator compares current values for MFLCPR1 MFLPD and MAPRA T to the Accentance Criteria listed on the form {sten 9 of form).
Standard:
Determines that MAPRA T does not meet the associated Acceptance Criteria.
JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 6 of 11 Evaluation Performance Steps SAT/UNSAT Interim Cue:
Terminating Cue:
- Critical Step
- 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 (MAPRA T) 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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:
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 MAPRA T 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
Evaluator Comments:
JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 7 of 11
Tear Out Sheet Initial Conditions:
The plant is at rated conditions APRM "D" has failed downscale and is bypassed JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 8 of 11 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.
CORE PARAMETERS POWER MWT POWER MWE FLOW MLB/HR FPAPDR SUBC PR CORE CYCLE MCPR BTU/LB PSI a MWD/sT MWD/sT FOR TRAINING ONLY 1910.7 652.8 48.121 0.815 26.96 1029.95 20163.0 5796.8 1.552 VERMONT YANKEE C26 3DM/P11 PERIODIC LOG AUTOMATIC CALC RESULTS Keff XE WORTH %
XE RATED AVE VF
- 1. 0040
-2.387 1.03 0.480 JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 9 of 11 PAGE 1 SEQUENCE NO 23 25-Mar-2014 00:00 CALCULATED 25-Mar-2014 00:00 PRINTED CASE ID FMLS1120815000053 RESTART FMLS1120815000053 LPRM SHAPE -
FULL CORE LOAD LINE
SUMMARY
CORE POWER CORE FLOW LOAD LINE 99.9%
100.3%
99.8%
CORRECTION FACTOR: MFLCPR= 1.002 MFLPD= 0.999 MAPRAT= 0.998 OPTION:
ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM= 1.400 MFLCPR 0.902 0.869 0.896 0.869 0.865 0.827 0.822 0.813 0.809 SEQ. B-1 43 L
39 35 L
31 27 L
23 19 L
15 11 L
07 03 LOC 25-34 27-32 23-32 29-34 27-36 23-36 35-24 31-36 27-34 L
MOST LIMITING LOCATIONS (NON-SYMMETRIC)
MFLPD LOC MAPRAT LOC PCRAT LOC 23 9 25-36-11 23-38-11 25-38-11 25-32-11 0.968 23-34-10 1.003 23-36-10 0.999 0.960 23-36-11 1.001 23-34-11 0.998 0.952 9 5 0.998 15 4 0.991 0.950 15 4 0.920 9 5 0.969 0.920 17 5 0.920 9 5 0.966 0.912 9 5 0.899 13 4 0.962 9 5 15 5 17 5 11 5 0.910 25-34-11 0.895 11 4 0.959 0.872 25-36-11 0.894 15 5 0.956 0.869 11 5 0.890 11 4 0.956 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT 10 10 L
M 32
- C 08 10 08 10 32 L
L L
- =MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 00 0.469 24 02 0.649 23 04 0.783 22 06 0.854 21 08 0.897 20 10 0.912 19 12 0.921 18 14 0.945 17 16 0.943 16 18 0.982 15 20 1.147 14 22 1.177 13 24
- 1. 236 12 26
- 1. 280 11 28
- 1. 286 10 30
- 1. 291 09 32
- 1. 303 08 34
- 1. 304 07 36
- 1. 319 06 38 1.347 05 40
- 1. 319 04 42 1.190 03 44 0.919 02 46 0.333 01 02 06 10 14 18 22 CORE AVERAGE RADIAL POWER 26 30 34 38 42 DISTRIBUTION RING i 1
2 3
4 5
REL PW 0.947 1.056 1.121 1.224 1.142 VERMONT YANKEE C26 41D 24.0 c
34.3 INSTRUMENT READINGS/STATUS CALIBRATED LPRM READINGS 28.4C 40.9 6
0.689 SEQUENCE NO 23 PAGE 2 15-Aug-2012 00:00 CALCULATED 15-Aug-2012 00:00 PRINTED CASE ID FMLS1120815000053 LPRM SHAPE -
FULL CORE FOR TRAINING ONLY B
41.0* 49.4 A
34.9 43.2 33D 29.5 42.0 44.3 37.4 c
39.7 53.3 57.2 48.0 B
49.1 32.4 65.7 56.1 A
54.1 61.9 51.3 60.3 25D 37.0 51.2 52.2 45.7 26.8 c
45.9 44.1 44.0 44.4 35.8 B
56.4 49.5 47.1 53.2 45.6 A
60.6 45.6 38.3 54.2 49.4 17D 34.3 47.9 49.3 43.5 23.9 c
44.1 46.6 47.7 44.7 31.1 B
55.0 53.1 53.1 53.6 37.9 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%
CORE FLOW 100.3%
OPER SUB FLOW
-2.1%
LOAD LINE 99.8%
FLOW BASIS MEAS APRM CALIBRATION A
B c
D READING 100.9 98.9 100.8 0.0 AGAF 0.990
- 1. 010 0.991 APRM -
%CTP 1.0
-1.0 0.9 TIP RUNS RECOMMENDED STRINGS:
NONE JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 10 of 11 FAILED SENSORS:
LPRM (
1 SIGNAL FAILED) 3209A LPRM (
0 PANACEA REJECTED)
OTHER SENSORS (
0 TOTAL)
SUB RODS NONE T = TIP RUN RECOMMENDED c
MFLCPR LOCATION M
MAPRAT LOCATION D
MFLPD LOCATION p
PCRAT LOCATION MULTIPLE LIMIT DP MEAS PSI 20.426 DP CALC PSI 24.994 FEEDWTR FLOW MLB/HR 7.90 E
F 100.8 100.8
- 0. 992 0.992 0.9 0.8
ANSWER KEY CORE THERMAL HYDRAUI.IC LIMITS EVALUATION
- 1.
Record 30 Monicore Official Monitoring Case 10 FMLS11208150Q0053 JPM 2014A NRC SRO A-1 Rev.0,03/14 Page 11 of 11
- 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 by:-------------------
NRC Exam Lead DevelopHr Date Reviewed by: __________________ _
SRO Licensed /Certified Reviewer Date Approved by: _________________ _
Operations Training Superintendent Date NRC JPM-Alb SRO
Directions:
JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 2 of 6 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
Initiating Cues:
JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 3 of 6 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 SAT/UNSAT SAT/UNSAT SAT/UNSAT NRC JPM-Alb SRO Performance Steps Step 1:
Obtain SAG-2 flowchart and reviews the flowpath for Hydrogen and Oxygen concentration.
Standard:
Obtains SAG-2 Flowchart.
- 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:
Step 3:
Action level 2 for the Drywall Action level 5 for the Torus 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.
Evaluation SAT/UNSAT SATIUNSAT NRC JPM-Alb SRO JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 5 of 6 Performance Steps
- 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):
- Step 5:
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)
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)
- Critical Step TIME FINISH:----
JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 6 of 6 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
EXAMINEE HANDOUT Initial Conditions:
JPM 2014A NRC SRO A3 Rev 0, 3/14 Page 1 of 3 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 1 05 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?
QUESTIONS.
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?
EXAMINEE HANDOUT DRYWELL JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 2 of 3 TORUS
QUESnONS 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?
Answer' sheet NOT for Examinee DRYWELL Vel!
The Drywell is vented using OP 2115, OP 2125, or OE 31mr.
Hydrogen no longer detected in the Drywell AND EITHER Drywell Oxygen iis <5% OR Hydrogen no longer detected in the Torus -or-RPV water level maintained above TAF AND off site release rates reatch General Emergency level.
No JPM 2014A NRC SAO A3 Rev 0, 3/14 Page 3 of 3 TORUS Yes The Torus is vented using OP 2115, OP 2125 or OE 3107.
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.
No
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:
Failure Mode:
Evaluate secondary containment for continued refueling N/A
Reference:
Task Number:
Task Performance:
AP 0077. Barrier Control Process Vermont Yankee Technical Requirements Manual 34270703 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 by:-------------------
Facility Exam Developer Date Reviewed by: __________________ _
SRO Licensed /Certified Reviewer Date Approved by: __________________ _
Operations Training Superintendent Date
Directions:
JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 2 of 7 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.
Task Standards:
JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 3 of 7 Reviews secondary containment barrier petrmit index and notes previous permits total 19.3 in2
- 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 will cause us to exceed 22.4 in2 at a total of 26.4 in2 of secondary containment breachE~d by permit.
A review of OPAP-BCP- 0077, Barrier control process, shows that for the current plant conditions (0.25 inches H20 reactor building vacuum) we are allowed a total of 22.4 in2 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 SAT/UNSAT 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 (total of 19.3 in2) will cause us to exceed 22.4 in2 for a total of 26.4 in2 of secondary containment breached by permit. (math is 3.1416/4 X dia2=in2 or 0.7854 X 9=7.0686 in2)
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).
- 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 building vacuum) we are allowed a total of 22.4 in2 of secondary containment barrie~rs breached. Therefore, secondary containment is inoperable.
Evaluation 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.
TIME FINISH:----
Terminating Cue:
This JPM is complete.
~---~~-------~~~----
Evaluator Comments:
~*------**~------------------- ---
JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 6 of 7 System Generic KIA's:
2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.(3.9/4.2)
Initial Conditions:
Refueling is in progress Reactor building vacuum is -0.25 inches H20 JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 1 of 2 EXAMINEE HANDOUT 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.
PERM ASSET IT NUMBER OR NUMB PENETRATION ER DESCRIPTION 1
FB-045-1-262 Cable Vault 2
FB-060-1-241 CST pipe trench 3
FB-061-1-213 HPCI west wall JPM 2014A NRC SAO A-2 Rev 0, 3/14 Page 2 of 2 ATTACHMENT 15 -SECONDARY CONTAINMENT PERMIT INDEX CpS 5.3.1)
DESCRIPTION SECONDARY CLOSURE FIELD DATE EXPIRATION OF WORK CONTAINMENT RESPONSIBIUTY* (By VAUDATED ISSUED DATEmME PENETRATION on-shift title or name)
CLOSURE SIZE/TOTAL AND Contact By TIME*
SIZE Phone# Or Radio (Days/Nights)
Fire penetration 10.8 in2 Westco day shift One week Two days seal replacement supervisor ago from now 555-7312 Fire penetration 8.5 in2 Westco day shift Three One week seal replacement supervisor days ago from now 555-7312 Fire penetration 3 india pipe Westco day shift Last shift 10 days seal replacement supervisor from now 555-7312 DATE CLOSED I
JPM 2014A NRC SRO A-4 Rev.0,03/14 Task Identification:
VERMONT YANKEE JOB PERFORMANCE :MEASURE WORKSHEET Page 1 of 12
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
Directions JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 2 of 12 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
Recommendations are required following your assessment.
Task Standards:
JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 3 of 12 The operator determines that the estimated dose at the site boundary is 2.4R. The operator determines that RPV-ED is required.
Required Materials:
- to this JPM, For Training Only Attachment 9.16 ofOP 3513 Calculator OP 3513 EOP-4 EALChart Simulator Setup:
N/A
Evaluation SAT/UNSAT SAT/UNSAT JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 4 of 12 Performance Steps TIME START:
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.
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:
- Critical Step
- 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.
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:
Standard:
SAT/UNSAT Step 5:
Standard:
SAT/UNSAT Step 6:
- Critical Step
- 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.
Determines that this step is not applicable due to initial conditions.
- d. If ODPS is operable, then implement Attachment 9.5 to access otT-site dose projection information fromODPS.
Determines that this step is not applicable due to initial conditions.
- e. If ODPS is inoperable, then implement.1 to perform the applicable otT-site dose projections.
Evaluation Performance Steps JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 6 of 12 Standard:
Determines that this step is applicable and transitions to.1 Evaluator Note:
The next several steps are from Attachment 9.1, Offsite Dose Projection Methodology When OOPS is Inoperable.
SAT/UNSAT SAT/UNSAT
- Critical Step 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-.12 Standard:
Determines that this step is not applicable due to the release being a ground le:vel release.
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.1 based on initial conditions.
Evaluation SAT/UNSAT JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 7 of 12 Performance Steps
- Step 9:
Standard:
Obtain and record below the Whole Body Dose Rate (waist height reading) from the Site Boundary Team, or Attachment 9.16, Section A.
Records 300 mR/hr on attachment 9.1 and uses this value in subsequent calculation.
Evaluator Note:.1 includes a note at this point which directs the operator to use a release duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SAT/UNSAT
- Step 10:
Standard:
SAT/UNSAT Step 11:
Standard:
- 2) Calculate the Ground Site Boundarv Dose
,(H) and record below as follows:
Dos (R)
Site Boundary Whole Body Dose Rate in mRihr R I Dura*
. H e
=
mR x
e ease bon m ours 1000-R Operator determines that the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Boundary Dose is 2.4 R Use the applicable meteorological data (wind direction and stability class) and Site Boundary Dose results from above to do the following:
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
Evaluation SAT/UNSAT JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 8 of 12 Performance Steps
- 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 Evaluator Note:
Interim Cue:
SAT/UNSAT
- Critical Step
- 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 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 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.
When the operator has completed the determination of whether an RPV-ED is required, Cue that the opc~rator has completed the assigned task.
Step 5:
Standard:
Place Keeping and STAR used consistently throughout.
Steps are circled as performed, crossed out as completed and N/A'd as appropriate. STAR used consistently for each manipulation.
Evaluation Performance Steps TIME FINISH:, ___ _
JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 9 of 12 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
Evaluator Comments:
JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 10 of 12
Tear Out Sheet Initial Conditions:
JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 11 of 12 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 Attachment 1 FOR TARAININGONLY OP 3513, Attachment 9.16, Excerpt Only JPM 2014A NRC SRO A-4 Rev.0,03/14 Page 12 of 12 VYNPS
!NON-QUALITY RElATED OP 3513 Rev.36
~Entergy EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE USE.16 TEAM STATUS LOG Sheet :L of 2 Page y
of Info current at: Time: 5 Minutes ago Date: Today Sample Location: Downwind at Site Boundary Team:
A.
~
0 Green 0 Blue WHOLE BODY DOSE RATE RESULTS
- 1.
Frisker Reading:
- a.
Waist Height GCPM
- b.
2" Above Ground
- 2.
Dose Rate Meter Reading:
- a.
Waist Height 300 mR/hr b.
2" Above Ground 95
- 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.
§!l GCPM mR/hr
JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 1 of 10 Task Identification:
Title:
Failure Mode:
VERMONT YANKEE JOB PERFORMANCE.MEASURE WORKSHEET Activate the INFORM Notification System NA
Reference:
Task Number:
EPAP-INFORM-10076 "'INFORM Notification System" 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 Reviewed by:
SRO Licensed /Certified Reviewer Approved by:
Operations Training Superintendent Date Date Date
Directions JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 2 of 10 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 OA TC 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.
Task Standards:
All of the following:
EAL SA2.1 correctly determined InForm notification completed Required Materials:
JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 3 of 10 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
Evaluation SAT/UNSAT Evaluator Note SAT/UNSAT JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 4 of 10 Performance Steps TIME START:
Step 1; Standard:
Obtain procedure AP 3125, Emergency Plan Classification and Action Level Scheme Procedure reviewed.
Operator may review precaution and limitations or proceed directly to Attachment 'A', Chart of categories and events.
- Step 2:
Standard:
Operator evaluates initial conditions against the EAL's.
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
Evaluation SATIUNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
- 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 ST A computer desktop.
- Step 5:
Operator accesses the Inform software.
Standard:
Uses the installed icon.
Step 6:
Operator prepares the form:
Standard:
Operator clicks on the Plant Information tab 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)
Evaluation SAT/UNSAT SAT/UNSAT SAT/UNSAT
- Step 8:
Operator selects the EAL classification.
Standard:
Operator enters 'Alert' Step 9:
Operator enters: data on the form.
Standard:
Operator enters:
G.
At: (Input: time)
H.
On: (Current date is automatically displayed)
- Step 10:
Operator selects the EAL number.
Standard:
Operator enters EAL SA2.1 I.
EAL Number: (Select from the dropdown menu)
Evaluation SATIUNSAT SATIUNSAT SATIUNSAT SATIUNSAT
Step 12:
Step 13:
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)
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 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.
- Step 14:
Operator transmits the form.
Evaluation
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
Evaluator Comments:
JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 9 of 10
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 JPM 2014A NRC SRO A-5 Rev.0,03/14 Page 10 of 10 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 Task Identification:
VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET
Title:
Failure Mode:
Place the Standby Fuel Pool Cooling System in Service Insufficient Pump Flow
Reference:
Task Number:
OP 2179 Standby Fuel Pool Cooling System 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 Reviewed by:
SAO Licensed /Certified l=teviewer Approved by:
Operations Training Superintendent Date Date Date
Directions JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 2 of 11 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.
Reguired Materials:
JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 3 of 11 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 SAT/UNSAT Interim Cue:
SAT/UNSAT SAT/UNSAT Interim Cue:
SAT/UNSAT
- Critical Step TIME START:
Step 1; Standard:
Obtain procedure OP-2179 and review Precautions, Limitations and Prerequisites.
Procedure reviewed, starts in section A.
If asked, cue the operator that all prerequisites have been met.
If asked, spent fuel pool temperature is 100°F and stable.
Step 2; Standard:
Step 3; Standard:
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.
Operator determines that step is has been completed based on the initial conditions and proceeds to the next step.
Ensure that leak check analyses of both SFPC heat exchangers is completed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to SFPC operation.
Operator informs CRS that a leak check analyses is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Acknowledge the report as CRS.
Step 4; Standard:
Secure the normal FPC pumps per OPOP-NFPC-2184.
Operator obtains copy of procedure OPOP-NFPC-2184 and determines that section 7.12 section is appropriate.
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 SATIUNSAT Interim Cue:
SATIUNSAT The next 4 steps are contained within OPOP-NFPC-2184 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.
As AO cue the Operator that the in service F/D has been removed from service.
- 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
- Critical Step 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.
Evaluation Interim Cue SAT/UNSAT JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 6 of 11 Performance Steps Cue the operator as the AO that skimmer pumps have been secured.
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 SAT/UNSAT
- Critical Step
- 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 Note:
Interim Cue:
- Step 10:
FPC ISOLATION FPC-220, is located on CAD Panel Band also has position indicating lights on CAD Panel A.
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. Notify the Operator that the AO reports FPC-223 is closed.
Throttle open FPC HX SW OUT SW -257 A(B), to achieve a flow of S678 gpm per FI-104-SOA(B) SERV WTR FLOW TO HX (CAD Panel B(A)).
Evaluation Performance Steps JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 7 ofll 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 SATIUNSAT SATIUNSAT
- Critical Step
- Step 11:
Start STDBY FPC PUMP P-19-2A(B) (CAD Panel B(A))
and observe:
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.
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),
Evaluation SAT/UNSAT JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 8 of 11 Performance Steps Step 13:
If plant conditions allow access to the 303' level of the reactor building:
- 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:
Interim Cue:
SAT/UNSAT "In order to ensure adequate pump cooling, do not operate either SFPC pump at less than 350 gpm."
If the operator asks the AO to adjust the valve, cue the operator that the valve is stuck and will not movt~.
- 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
Evaluation SAT/UNSAT Performance Steps JPM 2014A NRC SRO S-1 Rev. 1, 3/14 Page 9 of 11 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
Evaluator Comments:
JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 10 ofll
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.
JPM 2014A NRC SRO S-1 Rev.1, 3/14 Page 11 of 11 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 Task Identification:
VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET
Title:
Failure Mode:
Emergency Venting of the Primary Containment NA
Reference:
Task Number:
OE 3107 EOP/SAG Appendices, Appendix HH 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 Reviewed by:
SRO Licensed /Certified Reviewer Approved by:
Operations Training Superintendent Date Date Date
Directions JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 2 of 10 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.
Task Standards:
JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 3 of 10 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
Evaluation SAT/UNSAT Performance Steps TIME START:
JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 4 of 10 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; Standard:
- Critical Step Install the following jumpers; CRP 9-42: BBSl to AA28 (CWD 1112)
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.
JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 5 of 10 Evaluation Performance Steps
- Step 3:
SAT/UNSAT Standard SAT/UNSAT
- Step 4:
Standard:
SAT/UNSAT
- Step 5:
Standard:
- Critical Step CRP 9-41: BB51 to AA28 (CWD 1116)
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.
Place both SGTS fans to PfL.
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.
CLOSE/confirm CLOSED the following:
- 1) SGT-3A DISCH ISOLATION 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.
Evaluation SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
- Step 6:
Standard:
Step 7:
Standard:
Step 8:
Standard:
Step 9:
Standard:
Step 10:
Standard:
- 2) SGT-3B DISCH ISOLATION 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.
- 3) SGT-6VENTTOSGTS 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.
- 4) SGT-lAINLETBYPASS 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.
- 5) SGT-lB INLET BYPASS 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.
OPEN the following:
- 1) SGT-2A INLET ISOLATION 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.
Evaluation SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT Interim Cue:
Standard:
Step 12:
Standard:
Step 13:
Standard:
- Step 14:
Standard:
- 2) SGT-28 INLET ISOLATION 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.
- 3) SGT -4A COOL AIR INLET 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.
- 4) SGT -48 COOL AIR INLET 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.
Torus Venting through TVS-86; To vent the ton1s, OPEN TVS-86 TORUS VENT VL V.
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.
Inform the Operator that the task is complete
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
Evaluator Comments:
JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 9 of 10
Tear Out Sheet Initial Conditions:
JPM 2014A NRC SRO S-2 Rev.0,03/14 Page 10 of 10 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.
Task Identification:
VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET JPM 2014A NRC S-3 Rev.l,03/14 Page 1 of 11
Title:
RCIC Manual Injection for RPV Level Control Failure Mode:
Reference:
RCIC Trips and mus1t be reset with an initiation signal present 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
Directions JPM 2014A NRC S-3 Rev. 1,03/14 Page 2 of 11 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
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
Simulator Setup:
JPM 2014A NRC S-3 Rev.l,03/14 Page 3 of 11 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
Evaluation SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
- Critical Step JPM 2014A NRC S-3 Rev.1,03/14 Page*4 of 11 Performance Steps TIME START:
Sl~ul; Obtain mini procedure OP 2121~ Appendix C~
MANUAL RCU~ IN.JECTION.
Standard:
Retrieves mini procedure from CRP 9-4.
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.
Step 3; Start GLAND SEAL VACUUM PUMP.
Standard:
Takes the Gland Seal Vacuum Pump control switch to the right to Start. Observes 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.
- Step 5:
Open STEAM SUPPLY RCIC-131.
Standard:
Takes RCIC-131 (:ontrol switch Clockwise to Open.
Observes Red light lit and Green light out.
Evaluation SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT JPM 2014A NRC S-3 Rev.1,03/14 Page 5 of 11 Performance Steps 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.
Step 7:
If RCIC FLOW CONTROLLER FIC 13-91 automatic 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..
- Step 8:
Open PUMP DISCHARGE RCIC-21.
Standard:
Takes RCIC-21 control switch Clockwise to Open.
Steo 9; Observes Red light lit and Green light out.
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
- Critical Step 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.
JPM 2014A NRC S-3 Rev.1,03/14 Page 6 of 11 Evaluation Performance Steps SAT/UNSAT SAT/UNSAT SAT/UNSAT 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.
Step 12:
- b. MINIMlJM FLOW RCIC-27 is closed.
Standard:
On CRP 9-4 verifies RCIC-27 Green light LIT and Red light OUT.
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.
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
Evaluation SAT/UNSAT SAT/UNSAT JPM 2014A NRC S-3 Rev. 1,03/14 Page 7 of 11 Performance Steps
- 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:
Standard:
On RCIC PUMP FLOW CONTROLLER FIC 13-91 on CRP9-4:
- Step 16:
Rotates sdector switch clockwise to the MAN position Adjusts manual potentiometer until the controller output meter (meter above selector switch) indicates 50% of scale.
- 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
- Critical Step
- 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.
Evaluation SAT/UNSAT JPM 2014A NRC S-3 Rev.l,03/14 Page 8 of 11 Performance Steps
- 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.
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
- Critical Step Step 19:
- g. Verify that after a few seconds RCIC-1 opens and 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.
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.
- Step 21:
Place the flow controller in AUTO.
Standard:
Rotates the selector switch on the controller counterclockwise to the AUTO position.
Step 22:
If equalization or RCIC steam line Ap was required, close/check closed:
Evaluation SAT/UNSAT SAT/UNSAT Interim Cue:
SAT/UNSAT JPM 2014A NRC S-3 Rev.1,03/14 Page 9 of 11 Performance Steps Standard:
Operator determines that this step is not applicable and continues on to the next step.
Step 23:
Enter RCIC Automatic Initiation section of this procedure.
Standard:
Operator transitions to Section B, RCIC Automatic Initiation 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.
Cue operator that the operator' H task has been completed.
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
Evaluator Comments:
JPM 2014A NRC S-3 Rev.l,03/14 Page 10 of 11
Tear Out Sheet Initial Conditions:
JPM 2014A NRC S-3 Rev.1,03/14 Page 11 of 11 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.
Task Identification:
VERMONT Y ANKEE{PRIVATE }
JOB PERFORMANCE :MEASURE WORKSHEET JPM 2014A NRC SRO P-1 Rev. 0, 03114 Page 1 of6
Title:
Reference:
Task Number:
Place Standby CRD Flow Control Valve in Service OPON-3145-01, Loss ofCRD Regulating Function Rev. 4 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
Directions:
JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page 2 of6 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
1 Evaluation SATIUNSAT Performance Steps T~ESTART: __________ _
JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page 3 of6 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:
Standard:
From CRP 9-5, DIAL the flow controller (FIC-3-301) in MANUAL to zero valve position.
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 19 A(8) is closed.
SATIUNSAT Interim Cue:
Step 3:
a) b)
Standard:
Isolate the flow control valve CRD FCV-19A(B) being removed from service as follows:
Close CRD-68A(B), Inlet To CRD FCV-19A(B).
Close CRD-69A(B), Outlet Of CRD FCV-19A(B)
CRD-68A and 69A (688/698) valve handles rotated clockwise until valves full shut.
Handles rotate freely clockwise, valve sterns move inward until resistance is felt, and valve handle stops moving.
Evaluation SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page4 of6 Performance Steps
- Step 4:
Standard:
Select CRD FCV-19A(B) to be placed in service at the liP Converter Selector Switch.
Local FCV-3-19A(8) liP Converter selector switch located behind FCV 19A (198), and taken to FCV-3-19B(A)
The switch handle rotates freely to the FCV-3-19B(A) position.
- Step 5:
Standard:
Position loca13-way valve CRD-126, Supply Air to FCV, to flow control valve CRD FCV-l9A(B) to be placed into service.
CRS SA-3-126, located on the CRD flow control pneumatic control panel to 207A(8)
Valve control knob rotates freely until resistance is felt with the pointer at the 207 A(B) position.
- Step 6:
a) b)
Standard:
For the flow control valve CRD FCV -19A(B) being placed in service:
Open CRD-68A(B), Inlet To CRD FCV-19A(B).
Open CRD-69A(B), Outlet OfCRD FCV-19A(B).
CRD-688 and 698 (68A/69A) handles rotated counter-clockwise until full open.
Valve handles rotate freely counter-clockwise and valve stems move outward until resistance is felt and handle stops moving.
Evaluation SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
SATIUNSAT
Standard:
Adjust CRD parameters at CRP 9-5 to normal operating ranges.
Operator calls Control Room to inform them the alternate FCV has been placed in service and to adjust CRD parameters.
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.
Step 8:
Standard:
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).
Operator checks charging header pressure on PI-3-234 and reports it to the control room.
The control reports no further adjustments are needed.
Step 9:
Standard:
Place Keeping and STAR used consistently throughout.
Steps are circled as performed crossed out as complete and N/A'd as appropriate. STAR Utsed consistently for each simulated manipulation.
TIME FINISH:---------
Terminating Cue:
The Standby CRD FCV is placed in service.
Evaluators Comments:
System: 201001 Generic K/A's:
K/A's:
Kl.08 Kl.09 K3.03 Al.03 A2.02 A2.07 2.1.27 2.1.10 2.2.25 2.1.28 2.1.30 2.1.32 2.1.23 K4.12 JPM 2014A NRC SRO P-1 Rev. 0, 03/14 Page6 of6 K6.03 K6.06
EXAMINEE HANDOUT Initial Conditions:
Plant at 100% power.
JPM SRO P-1 Handout Rev. 0, 3/14 Page 1 of 1 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 Task Identification:
VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET
Title:
Failure Mode:
Locally Start an EDG During Station Blackout NA
Reference:
Task Number:
OPOT-3122-02. Station Blackout 2640090101 Task Performance:
AOIRO/SRO X
RO/SRO Only Sequence Critical:
Yes No Time Critical:
Yes No Individual Performing Task:
Examiner:
Date of Evaluation:
Activity Code:
Method of Testing:
Simulation X
Performance Setting:
Classroom Simulator Performance Expected Completion Time:
minutes Evaluation Results:
SEOnly Discuss Plant Performance: PASS FAIL __ Time Required:
Prepared by:
Operations Training Instmctor Reviewed by:
SRO Licensed /Certified R1;::viewer Approved by:
Operations Training Superintendent Date Date Date
Directions JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 2 of9 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
Simulator Setup: NA JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 3 of9
Evaluation SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
SAT/UNSAT JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 4 of9 Performance Steps TIME START:
Steo 1; Obtain procedure; review admin limits, precautions, pre-requisites.
Standard:
Procedure obtained, admin limits, precautions, prerequisites.
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.
- 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.
Switch is in AT ENGINE position. Alarm LOCAL ENGINE CONTROL annunciates (DA-G-1). Prompt, if needed as CRS, "Continue to start EDG
'B'.
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.
The cause of the trip has been msolved but lockout device is tripped.
- Step 4:
RESET any lockout.
Standard:
Operator turns red handle lockout reset on the diesel room control panel in the clockwise direction
- Critical Step
Evaluation Interim Cue:
SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
Performance Steps JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 5 of9 Lockout device is reset. The lockout relay light illuminates. Control room reports that the DG-A Lockout: Trip alarm has cleared.
- Step 5:
DEPRESS reset pushbutton on diesel engine panel to reset shutdown relay.
Standard:
Pushbutton depressed and released Pushbutton depresses when pushed and springs back when released.
- Step 6:
WAIT for stopping relay to time out (approximately 100 seconds).
Standard:
Operator waits at least 100 seconds before proceeding.
When operator indicates that he/she is waiting at least 100 seconds then cue that > 100 seconds has elapsed.
- Step 7:
Auto start diesel by placing REMOTE/AT ENGINE control switch to REMOTE.
Standard:
Operator places control switch to REMOTE position.
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 Interim Cue:
SAT/UNSAT Interim Cue:
SAT/UNSAT Interim Cue:
- Critical Step
- 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 The Manual Operator Stem is rotated 180 degrees. Cue the operator that air is heard flowing and that the di1esel engine is rolling.
- Step 9:
ROTATE stem counterclockwise 180 degrees to disengage manual operator.
Standard:
Operator rotates manual operator 180 degrees in the counterclockwise direction.
The Manual Operator Stem is now back in its original position. The diesel is now up to 900 RPM.
Step 10:
REPORT diesel status to the SM.
Standard:
Operator informs the SM that the diesel is running Acknowledge the operator's report. Inform the operator that the task is complete.
Evaluation SAT/UNSAT Performance Steps JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 7 of9 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
Evaluator Comments:
JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 8 of9
Tear Out: Sheet Initial Conditions:
Station Blackout Conditions Exist JPM 2014A NRC SRO P-2 Rev.0,03/14 Page 9 of9 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