ML14059A546
| ML14059A546 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/14/2014 |
| From: | Mcneil D Operations Branch III |
| To: | Stewart B Entergy Nuclear Vermont Yankee |
| Jackson D | |
| Shared Package | |
| ML13204A095 | List: |
| References | |
| TAC U01897 | |
| Download: ML14059A546 (121) | |
Text
NRC JPM-A1a Rev. 0, 11/13 Page 1 of 6 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Post surveillance board walkdown Failure Mode Valve and flow controller out of position
Reference:
OP 2121, RCIC System, Rev. 58 Task Number:
2060010101 Task Performance:
AO/RO/SRO RO/SRO X SRO Only Time Critical:
Yes No X Operator Performing Task:
Examiner:
Date of Evaluation:
Activity Code:
Method of Testing: Simulation Performance X Discuss Setting: Classroom Simulator X Plant Performance Expected Completion Time: 12 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed /Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM-A1a Rev. 0, 11/13 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 Simulator 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:
The plant is at 100% power OPOP-RCIC-4121, Reactor Core Isolation Cooling System test was completed last shift.
Initiating Cues:
CRS directs you, the BOP, to walk down the RCIC system components to verify proper alignment using OP 2121 Reactor Core Isolation Cooling System, APPENDIX A, RCIC System Valve Lineup for components on CRP 9-4. When complete, report status to the CRS.
Task Standards:
RCIC-15 is identified as out of position, RCIC Flow Controller is identified in MANUAL. Determines RCIC is inoperable. Determines that RCIC-15 must be opened for RCIC operability.
Required Materials:
OP 2121, RCIC System Rev. 58 VY Technical Specifications Simulator Setup:
Any 100% power IC Close RCIC-15 RCIC Flow Controller in MANUAL
NRC JPM-A1a Rev. 0, 11/13 Page 3 of 6 Evaluation Performance Steps TIME START:
SAT/UNSAT Step 1:
Refer to procedure OP 2121, RCIC System Appendix A, RCIC System Valve lineup for reference.
Standard:
Operator obtains OP 2121, Appendix A for guidance.
Interim Cue:
If the operator requests the completed surveillances, inform the operator that they are in the process of being turned over and are unavailable at this time.
SAT/UNSAT
- Step 2:
Operator walks down CRP 9-4 and identifies RCIC-15 closed.
Standard:
Operator identifies RCIC-15 in the closed position.
Interim Cue:
If operator informs shift manager, acknowledge communication.
Evaluator Note:
The intent of this step is that RCIC-15 was incorrectly positioned. It is not the intent to assume it was tampered with.
SAT/UNSAT
- Step 3:
Operator walks down CRP 9-4 and identifies RCIC Flow Controller in MANUAL.
Standard:
Operator identifies that the controller mode selector is in MANUAL.
Interim Cue:
If operator informs shift manager, acknowledge communication.
Interim Cue:
As the CRS, identify required technical specification actions, if any.
NRC JPM-A1a Rev. 0, 11/13 Page 4 of 6 Evaluation Performance Steps SAT/UNSAT
- Step 4:
Determines that RCIC is inoperable.
Standard:
Operator may refer to OP 2121.
Interim Cue:
If operator informs shift manager, acknowledge communication.
SAT/UNSAT
- Step 5:
Identifies RCIC TS LCO and status.
Standard:
Operator refers to Technical Specifications and identifies entry into LCO 3.5.G.2.
Interim Cue:
If operator informs shift manager, acknowledge communication.
Interim Cue:
As the CRS, identify actions necessary to return RCIC to operable status.
SAT/UNSAT
- Step 6:
Identify actions necessary to return RCIC to operable status.
Standard:
Determines that RCIC -15 must be opened and the controller in automatic to return RCIC to operable
- Critical Step TIME FINISH:
Terminating Cue: RCIC declared inoperable.
NRC JPM-A1a Rev. 0, 11/13 Page 5 of 6 Evaluators Comments:
2.0 GENERIC KNOWLEDGES AND ABILITIES 2.1 Conduct of Operations 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. (4.6 / 4.3)
NRC JPM-A1a Rev. 0, 11/13 Page 6 of 6 EXAMINEE HANDOUT Initial Conditions:
The plant is at 100% power OPOP-RCIC-4121, Reactor Core Isolation Cooling System test was completed last shift.
Initiating Cues:
CRS directs you, the BOP, to walk down the RCIC system components to verify proper alignment using OP 2121 Reactor Core Isolation Cooling System, APPENDIX A, RCIC System Valve Lineup for components on CRP 9-4. When complete, report status to the CRS.
NRC JPM-A1b Rev. 0, 11/13 Page 1 of 9 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Review Daily SRM Response Check prior to Conducting Core Alteration Failure Mode:
N/A
Reference:
OPST-4102 REFUEL OUTAGE/FUEL MOVEMENT PERIODIC TESTS, Rev. 0 OP 2130 Source Range Monitoring System, Rev. 19 Task Number:
2157160101 Task Performance:
AO/RO/SRO RO/ SRO Only X SE Only __
Time Critical:
Yes No X 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: 15 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed /Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM-A1b Rev. 0, 11/13 Page 2 of 9 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 refueling
- Core Alterations commenced 4 days ago
- SRM B is out of service for detector replacement
- The Daily Neutron Response Check required by OPST-4102 REFUEL OUTAGE/FUEL MOVEMENT PERIODIC TESTS, Section 8.3, Attachment 7 (Section C) has just been completed.
- The next scheduled core alteration is to remove the blade for control rod 26-27 Initiating Cues:
As the Shift manager, review the results of the Daily Neutron Response Check provided Task Standards:
SM concludes SRM B and D are inoperable and that the scheduled activity cannot commence.
(SRM A and C quadrants are operable but are not adjacent.)
NRC JPM-A1b Rev. 0, 11/13 Page 3 of 9 Required Materials:
- OPST-4102 REFUEL OUTAGE/FUEL MOVEMENT PERIODIC TESTS, Rev. 0
- OP 2130 SOURCE Range Monitoring System, Rev. 19 (Examinee Handout if requested)
Simulator Set-Up:
- NA
NRC JPM-A1b Rev. 0, 11/13 Page 4 of 9 Evaluation Performance Steps TIME START:
SAT/UNSAT
- Step 1:
Compares the completed Attachment 7 - SRM Response Check with the Acceptance Criteria Standard:
Determines that:
SRM A Passed its response check as indicated because the detector responded as the detector moved.
SRM C Passed its response check as indicated because the detector responded as the detector moved.
SRM D Failed its response check as indicated because it did not show any response as the detector was moved.
Interim Cue:
If asked, respond as the test performer, that the final SRM readings (SRM Reading) were all taken after the detector was fully withdrawn.
SAT/UNSAT
- Step 2:
Determines operability of SRM D Standard:
Determines that SRM D has failed the acceptance criteria of and is inoperable, leaving only two operable SRMs.
Evaluator Note:
Operability requirements are contained within Tec Spec Section 3.12.B and also in OP 2130 SOURCE Range Monitoring System.
Interim Cue:
After SRM Operability has been determined, direct SM to determine requirements for core alterations.
NRC JPM-A1b Rev. 0, 11/13 Page 5 of 9 Evaluation Performance Steps SAT/UNSAT
- Step 3:
Determines SRM requirements for Core Alterations Standard:
Determines that Technical Specifications require that one operable SRM be located in the quadrant where fuel movement, control rod withdrawal, or control rod removal is to be performed and one operable SRM be located in an adjacent quadrant.
Evaluator Note:
OP 2130, Figure 4 defines the primary definition Control Rod Quadrants.
The next scheduled core alteration is to remove the blade for control rod 26-27 (Initial Conditions)
Control Rod 26-27 is in Quadrant A. (Operable)
Quadrant B. (Adjacent but Inoperable)
Quadrant C. (Opposite and Operable)
Quadrant D. (Adjacent but Inoperable), of this JPM is provided as an aid to the evaluator - an OPERABLE SRM is needed in adjacent quadrants for alterations SAT/UNSAT
- Step 4:
Determines whether minimum requirements are met using the Primary Quadrant definition.
Standard:
Refers to OP 2130, Step D. SRM Refueling Requirements, step 2 along with Figure 4, SOURCE Range Monitoring System and determines that requirements are NOT met using the Primary Quadrant Definitions.
- Critical Step TIME FINISH:
Terminating Cue:
SRM D declared INOP. Determination made that the scheduled control rod blade may NOT proceed as planned.
NRC JPM-A1b Rev. 0, 11/13 Page 6 of 9 Evaluator Comments:
SYSTEM: 215004 Source Range Monitor (SRM) System A4. Ability to manually operate and/or monitor in the control room:
A4.07 Verification of proper functioning/ operability (3.4/ 3.6)
NRC JPM-A1b Rev. 0, 11/13 Page 7 of 9 EXAMINEE HANDOUT Initial Conditions:
- The plant is refueling
- Core Alterations commenced 4 days ago
- SRM B is out of service for detector replacement
- The Daily Neutron Response Check required by OPST-4102 REFUEL OUTAGE/FUEL MOVEMENT PERIODIC TESTS, Section 8.3, Attachment 7 (Section C) has just been completed.
- The next scheduled core alteration is to remove the blade for control rod 26-27 Initiating Cues:
- As the Shift manager, review the results of the Daily Neutron Response Check provided.
NRC JPM-A1b Rev. 0, 11/13 Page 8 of 9 THIS PAGE IS FOR EXAMINERS INFORMATION ONLY. DO NOT HAND THIS PAGE TO STUDENT.
PRIMARY DEFINITION CONTROL ROD QUADRANTS Location of Blade to be removed
NRC Audit JPM-(A1b)
Rev. 0, 11/13 Page 9 of 9 OPST-4102 REFUEL OUTAGE/FUEL MOVEMENT PERIODIC TESTS ATTACHMENT 7 Rev. No. 00 Page 1 of 1 ATTACHMENT 7-SRM RESPONSE CHECK SECTION A SRM Channel Detector Core Position DETECTOR TYPE (Indicate One Per SRM Channel)
Dunking Chamber Standard SRM Detector A
B C
D SECTION B (Fill out: Prior to initiating core alterations or following movement of dunking chambers or following a change in input to an SRM channel.
SRM Channel (1)
Detector IN-CORE
[Counts/sec]
(2)
Detector OUT-OF-CORE
[Counts/Sec]
(3)
S/N Ratio S/N = Item(1)-Item(2)
Item(2)
CHANNEL OPERABILITY (Yes or No)
A B
C D
SECTION C (Fill out daily during core alterations).
SRM Channel Initial Reading Selected Control Rod Two Rod Interlock Test Done SRM Reading Rod/Detector Out or Assembly In/Out Channel
Response
(Yes or No)
A 20 CPS 12 CPS Rod/Detector/Assembly YES C
18 CPS 6 CPS Rod/Detector/Assembly YES B
OOS OOS Rod/Detector/Assembly NO D
18 CPS 18 CPS Rod/Detector/Assembly NO ACCEPTANCE CRITERIA:
- 1.
The SRM reads a minimum of 3 counts per second. (Section B)
- 2.
The signal to noise ratio of the SRM is at least 3.0. (Section B)
- 3.
Response in each channel (by movement of an adjacent control rod, a nearby fuel assembly, or detector) verified. (Section C)
Performed By:
/ Today Operator (Print/Sign)
Date S/N Ratio independently verified by:
/
[PS 5.2.6]
Operator (Print/Sign)
Date Evaluated By:
/
Shift Technical Advisor (Print/Sign)
Date Reviewed By:
/
Shift Manager (Print/Sign)
Date
NRC JPM-A2 Rev. 0, 11/13 Page 1 of 9 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Review Completed Surveillance and Take Action for Out of Spec Data Failure Mode:
N/A
Reference:
OPST-RHR-4124-09A, RHR Loop A Valve Operability Test, Rev. 03 Task Number:
3420260302/3 Task Performance:
AO/RO/SRO RO/SRO Only SRO Only _X__
Time Critical:
Yes No X 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: 18 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed/Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM-A2 Rev. 0, 11/13 Page 2 of 9 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.
After providing the initiating cue, ask the individual "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 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:
The RHR Loop A Valve Operability Test, has been submitted to you for review and signature.
Initiating Cues:
As the CRS, perform the IST review per section 12.2 and SRO Review per section 12.4.
Task Standards:
OOS open and closure time for RHR-65A and open time for RHR-27A valve noted on surveillance; 7-day LCO identified per TS 3.5.A.4 Required Materials:
- OPST-RHR-4124-09A, RHR Loop A Valve Operability Test, Rev. 03 (with sections 8.0 - 12.3 filled out with initials and signatures)
- OPST-RHR-4124-09A, Attachment 1 - RHR LOOP A VALVE TEST RESULTS (Student Hand out filled in with time data and visual Observations filled out)
- VY Technical Specifications Simulator Setup: N/A
NRC JPM-A2 Rev. 0, 11/13 Page 3 of 9 Evaluation Performance Steps TIME START:
SAT/UNSAT Step 1:
Review completed procedure OPST-RHR-4124-09A, RHR Loop A Valve Operability Test, Rev. 03 (with attachment 1)
Standard:
Filled out OPST-RHR-4124-09A reviewed Interim Cue:
Provide completed OPST-RHR-4124-09A, RHR Loop A Valve Operability Test, Rev. 03 (with sections 8.0 - 12.3 filled out)
Provide completed OPST-RHR-4124-09A, Attachment 1 - RHR LOOP A VALVE TEST RESULTS (Hand out)
SAT/UNSAT Step 2:
Verify all data, initial and signature blocks are complete.
Standard:
Reviews body of procedure as well as attachment 1-test results.
Identifies that the stop watch is out of calibration Section 9.7 has no initials Signature is missing in section 12.1.1 SAT/UNSAT Step 3:
Verifies personnel performing activities are recorded.
Standard:
Reviews section 12.1.1 SAT/UNSAT
- Step 4:
Reviews Acceptance Criteria met in Section 11.0 Standard:
RHR-65A slow open time fails Acceptance Criteria 11.1 SAT/UNSAT
- Step 5:
Reviews Acceptance Criteria met in Section 11.0 Standard:
RHR-65A slow closure time fails Acceptance Criteria 11.1
NRC JPM-A2 Rev. 0, 11/13 Page 4 of 9 Evaluation Performance Steps SAT/UNSAT
- Step 6:
Reviews Acceptance Criteria met in Section 11.0 Standard:
RHR-27A slow open time fails Acceptance Criteria 11.1 SAT/UNSAT Step 7:
Notify SM Standard:
Informs SM that RHR-65A exceeded maximum open and closure time, RHR-27A has exceeded its maximum open time.
Interim Cue:
Acknowledge communication as SM.
SAT/UNSAT Step 8:
Initiate a CR and WR Standard:
Operator informs SM of the need to initiate a CR and WR Interim Cue:
Acknowledge communication as SM. If necessary, cue the operator that another person will initiate the CR and WR SAT/UNSAT Step 9:
Record in section 12.3, remarks.
Standard:
Operator documents in section 12.3 that RHR - 65A has exceeded its maximum open and closing time, RHR-27A has exceeded its maximum open time.
SAT/UNSAT Step 10:
Refer to Technical Specifications Section 3.5 Standard:
Locates 3.5.A.4 as the applicable specification.
Interim Cue:
If necessary, cue operator to identify any applicable Technical Specifications and LCO's
NRC JPM-A2 Rev. 0, 11/13 Page 5 of 9 Evaluation Performance Steps SAT/UNSAT
- Step 11:
Identifies 7-day LCO Standard:
Seven-day LCO per TS 3.5.A.4 identified Interim Cue:
If the candidate states that a Condition Report will determine operability, CUE the candidate that Engineering has responded that RHR-27A will NOT pass full flow within 24 seconds and will not meet its design function.
SAT/UNSAT Step 12:
Ensure results are entered in control room log book.
Standard:
Operator informs SM of the need to enter information in control room logbook.
Interim Cue:
Acknowledge communication as SM. If necessary, cue the operator that another person will initiate enter the information and the control room logbook.
SAT/UNSAT Step 13:
Record date and time SRO review complete.
Standard:
Operator completes step 12.4.7 TIME FINISH:
Terminating Cue:
RHR-65A open and closure time and RHR-27A open time identified as OOS and correct LCO entered.
NRC JPM-A2 Rev. 0, 11/13 Page 6 of 9 Evaluator Comments:
SYSTEM: 203000 RHR/LPCI: Injection Mode A2. Ability to (a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.03 Valve closures (3.2 / 3.3)
A2.13 Valve Openings (3.2 / 3.3)
NRC JPM-A2 Rev. 0, 11/13 Page 7 of 9 EXAMINEE HANDOUT Initial Conditions:
The RHR Loop A Valve Operability Test, has been submitted to you for review and signature.
Initiating Cues:
As the CRS, perform the IST review per section 12.2 and SRO Review per section 12.4.
NRC JPM-A2 Rev. 0, 11/13 Page 8 of 9 OPST-RHR-4124-09A RHR LOOP A VALVE OPERABILITY TEST ATTACHMENT 1 Rev. No. 03 Page 1 of 2 ATTACHMENT 1 - RHR LOOP A VALVE TEST RESULTS Valve Number IST Ref. Value (sec)
Valve Actuation Time (sec)
Visual Observation for abnormal or erratic operation
[PS 3.2.2]
IST Acceptable Range Test Value Open Close Open Close Open Close Open Close Min Max Min Max SAT UNSAT SAT UNSAT RHR-89A 56.00 54.00 47.60 64.40 45.90 62.10 55.25 53.20 RHR-25A 19.00 16.15 21.85 18.85 RHR-27A 43.26 42.63 36.78 48.00 36.24 49.02 70.15 40.12 RHR-160 1.00 0.01 2.00 1.00 RHR-161 1.00 0.01 2.00 1.00 RHR-34A 37.00 38.00 31.45 42.55 32.30 43.70 33.28 40.00 RHR-38A 15.00 16.00 12.75 17.25 13.60 18.40 14.34 17.49 RHR-39A 58.00 57.00 49.30 66.70 48.45 65.55 56.00 57.00 RHR-31A 60.00 59.00 51.00 69.00 50.15 67.85 61.77 62.65 RHR-26A 57.00 56.00 48.45 65.55 47.60 64.40 52.22 58.00 RHR-16A 23.00 22.00 19.55 26.45 18.70 25.30 23.00 23.00 RHR-65A 53.98 53.62 45.89 62.07 45.58 61.66 64.44 62.00 RHR-13A 97.00 95.00 82.45 100.00 80.75 100.00 92.92 94.45 RHR-15A 96.00 95.00 81.60 110.40 80.75 109.25 105.05 98.88 RHR-13C 93.00 93.00 79.05 100.00 79.05 100.00 92.50 93.54 RHR-15C 95.00 94.00 80.75 109.25 79.90 108.10 101.01 99.99 RHR-66 22.00 18.70 25.00 21.33 RHR-57 16.10 13.69 18.51 17.00
NRC JPM-A2 Rev. 0, 11/13 Page 9 of 9 OPST-RHR-4124-09A RHR LOOP A VALVE OPERABILITY TEST ATTACHMENT 1 Rev. No. 03 Page 2 of 2 IST Review
- 1.
Valve Actuation Time Test Values above are within the IST Acceptable Range, without abnormal or erratic operation.
- 2.
RHR-46A back leakage check is satisfactory if recorded PI-10-100A final pressure in Step 9.5.2.H is less than or equal to 100 psig.
Data evaluated by:
RO, SRO, STA (Print/Sign/Title)
Date
NRC JPM-A3 Rev. 0 11/13 Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Determine the Radiological Protection Requirements for Entering a Locked High Radiation Area.
Failure Mode:
N/A
Reference:
EN-RP-101, Access Control for Radiologically Controlled Areas Task Number:
2990100301 Task Performance:
AO/RO/SRO RO/SRO X SRO Only Time Critical:
Yes No X 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: 9 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
NRC Exam Lead Developer Date Reviewed by:
Operations Representative Date Approved by:
Operations Training Superintendent Date
NRC JPM-A3 Rev. 0 11/13 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 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 performing.
Inform me upon completion of this task.
Initial Conditions:
- The plant is at 100% power.
- HPCI-16 is closed and needs to be manually re-opened Initiating Cues:
- For the given scenario and RWP Index provided, determine the following:
o Which type of radiologically controlled area entry is required?
o Which RWP is to be used for the entry o Which RWP task is to be used for the entry?
o What are the dose alarm setpoint for the entry?
o What is the dose rate alarm setpoint for the entry?
Task Standards:
- The answers to the initiating cues have been provided.
NRC JPM-A3 Rev. 0 11/13 Page 3 of 7 Required Materials:
- RWP Index
- RWP 2013-0053, all tasks
- RWP 2013-0002, all tasks
- Survey map of the Steam Tunnel.
Simulator Set-Up:
- N/A Provide operator with Initial Conditions/Cue (Last Page of this JPM).
NRC JPM-A3 Rev. 0 11/13 Page 4 of 7 Evaluation Performance Steps TIME START:
SAT/UNSAT
- Step 1:
Operator reviews Steam Tunnel radiological survey map to determine the type of radiologically controlled area.
Standard:
The operator reviews the radiological survey map of the Steam Tunnel and determines an entry in the Locked High Radiation Area (LHRA).
SAT/UNSAT
- Step 2:
Operator reviews RWP Index to determine the required RWP.
Standard:
The operator reviews the index and determines that the Steam Tunnel is listed under RWP 2013-0053.
Evaluator Cue:
When asked, provide the Operator with a copy the RWP Index.
Evaluator Cue:
When asked, provide the Operator with a copy RWP 2013-0053.
IF RWP 2013-0002 (Operations Activities) is requested, provide RWP 2012-0002 SAT/UNSAT
- Step 3:
Operator reviews the RWP and determines the task number for which he/she will enter under.
Standard:
The operator reviews the RWP and determines that task number 207 applies to the Steam Tunnel entry.
NRC JPM-A3 Rev. 0 11/13 Page 5 of 7 Evaluation Performance Steps SAT/UNSAT
- Step 4:
Operator reviews the RWP and task and determines Dose Alarm setpoint Standard:
The operator determines that the ED dose alarm setpoint is 80 mrem SAT/UNSAT
- Step 5:
Operator reviews the RWP and task and determines Dose Rate alarm setpoint Standard:
The operator determines that the dose rate alarm setpoint is 1,500 mrem/hr.
- Critical Step TIME FINISH:
Terminating Cue:
Answers to the questions have been provided to the evaluator
NRC JPM-A3 Rev. 0 11/13 Page 6 of 7 Evaluator Comments:
2.0 GENERIC KNOWLEDGES AND ABILITIES 2.3 Radiation Control 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5 /
3.6)
NRC JPM-A3 Rev. 0 11/13 Page 7 of 7 EXAMINEE HANDOUT Initial Conditions:
- The plant is at 100% power.
- HPCI-16 is closed and needs to be manually re-opened Initiating Cues:
- For the given scenario and RWP Index provided, determine the following:
o Which type of radiologically controlled area entry is required?
o Which RWP is to be used for the entry o Which RWP task is to be used for the entry?
o What are the dose alarm setpoint for the entry?
o What is the dose rate alarm setpoint for the entry?
- 1. Which type of radiologically controlled area entry is required:
- 3. Which RWP task number is the operator entering under? Task #:
- 4. Electronic Dosimeter (ED) Dose Alarm setpoint:________________
- 5. Electronic Dosimeter (ED) Dose Rate alarm setpoint:_____________
NRC JPM-A4 Rev. 0 11/13 Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Classify an event and complete event notification form.
Failure Mode:
N/A
Reference:
AP 3125, Emergency Plan Classification and Action Level Scheme, rev. 23 Task Number:
3447040302/03 Task Performance:
AO/RO/SRO RO/SRO SRO Only X Time Critical:
Yes X No ___
Operator Performing Task:
Examiner:
Date of Evaluation: ________________________
Activity Code: ___________________________
Method of Testing: Simulation Performance X Discuss Setting: Classroom Simulator X Plant Performance Expected Completion Time: 20 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
NRC Exam Lead Developer Date Reviewed by:
Operations Representative Date Approved by:
Operations Training Superintendent Date
NRC JPM-A4 Rev. 0 11/13 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 Measure.
After providing the initiating cue, ask the operator "Do you understand the task?" State to the candidate: THIS JPM IS TIME CRITICAL 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 performing.
Inform me upon completion of this task.
Initial Conditions:
- The plant is shutdown in mode 5, preparing for a refueling outage.
- A loss of all on-site and all off-site AC power has just occurred.
- The operating crew is taking actions to mitigate the event.
- The first power source is not expected to be available for another 20 minutes.
Initiating Cues:
The Shift Manager has assigned you, an extra SRO, to classify the event IAW AP 3125, Emergency Plan Classification and Action level scheme and fill out Attachment 9 of EPOP-CR-3540 Emergency Classification and PAR Notification / Upgrade Instructions and Form State to the candidate: THIS JPM IS TIME CRITICAL Task Standards:
- The operator has classified an Alert within 15 minutes from initial conditions and completes the event notification form within the next subsequent 13 minutes.
NRC JPM-A4 Rev. 0 11/13 Page 3 of 7 Required Materials:
- AP 3125, Emergency Plan Classification and Action level scheme, Rev. 23
- EPOP-CR-3540, Control Room Actions during an Emergency, Rev. 00 Simulator Set-Up:
N/A
NRC JPM-A4 Rev. 0 11/13 Page 4 of 7 Evaluation Performance Steps Provide operator with Initial Conditions/Cue (Last Page of this JPM).
TIME START:
SAT/UNSAT Step 1:
Obtain AP 3125, Emergency Plan Classification and Action Level Scheme.
Standard:
Obtains AP 3125 and reviews step 4.1 Interim Cue:
Provide the operator with a copy of AP 3125, Emergency Plan Classification and Action Level Scheme.
SAT/UNSAT Step 2:
Operator refers to Appendix A for Cold Conditions.
Standard:
The operator refers to Appendix A. (Page 2 of 2)
Evaluator Note:
Appendix A, Page 1 of 2 is for hot conditions.
SAT/UNSAT
- Step 3:
Operator Classifies event.
Standard:
The operator identifies an Alert, code CA1.1within 15 minutes of being provided initial conditions.
TIME : _________
SAT/UNSAT Step 4:
Operator Implements EPOP-CR-3540, Attachment 9.
Standard:
The operator refers to Attachment 9.
NRC JPM-A4 Rev. 0 11/13 Page 5 of 7 Evaluation Performance Steps SAT/UNSAT
- Step 5:
Operator records time of EAL declaration and EAL on Attachment 9 Form, Section A1.
Standard:
Operator records EAL declaration time and EAL on Notification Form Block A1.
SAT/UNSAT
- Step 7:
Operator records Plant Conditions in Section B Standard:
Operator checks shut down box in Section B.
SAT/UNSAT
- Step 8:
Operator records Radiological Conditions in Section C.
Standard:
Operator checks Has not occurred box in Section C SAT/UNSAT
- Step 9:
Operator records Meteorological Conditions in Section D.
Standard:
Operator determines 12.61 mph and 1.7 degrees using met data handout and records in Section D.
SAT/UNSAT
- Step 10:
Operator records PAR recommendations in Section E.
Standard:
Operator checks None box in Section E.
SAT/UNSAT
- Step 10:
Operator signs as preparer in Section II.
Standard:
Operator signs in Section II.
TIME:________ (form to be completed < 13 minutes from event classification)
- Critical Step TIME FINISH:
Terminating Cue:
The event has been classified and the Event Notification Form has been completed.
NRC JPM-A4 Rev. 0 11/13 Page 6 of 7 Evaluator Comments:
2.4 Emergency Procedures / Plan 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (2.4 / 4.4)
NRC JPM-A4 Rev. 0 11/13 Page 7 of 7 EXAMINEE HANDOUT Initial Conditions:
- The plant is shutdown in mode 5, preparing for a refueling outage.
- A loss of all on-site and all off-site AC power has just occurred.
- The operating crew is taking actions to mitigate the event.
- The first power source is not expected to be available for another 20 minutes.
Initiating Cues:
The Shift Manager has assigned you, an extra SRO, to classify the event IAW AP 3125, Emergency Plan Classification and Action level scheme and fill out Attachment 9 of EPOP-CR-3540 Emergency Classification and PAR Notification / Upgrade Instructions and Form THIS JPM IS TIME CRITICAL
JPM-NRC CR (a)
Rev. 0, 11/13 Page 1 of 12 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Startup the Turbine to Rated Speed Failure Mode:
Turbine develops Hi Vibration during startup
Reference:
OP 0105 Reactor Operations Task Number:
2450020101 Task Performance:
AO/RO/SRO RO/SRO X SRO Only Time Critical:
Yes No X Operator Performing Task:
Examiner:
Date of Evaluation:
Activity Code:
Method of Testing: Simulation Performance X Discuss Setting: Classroom Simulator X Plant Performance Expected Completion Time: 15 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed/Certified Reviewer Date Approved by:
Operations Training Superintendent Date
JPM-NRC CR (a)
Rev. 0, 11/13 Page 2 of 12 Directions:
Discuss the information given on this page with the operator being evaluated. Allow time for the candidate 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.
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 Simulator 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:
A Plant Startup in progress. Reactor pressure is 950 psig. Main Turbine is on the Turning Gear. OP 0105 Phase 3, actions have been completed satisfactorily through Phase B, step 6. Generator H2 pressure is normal and does not need charging. The Generator Core Monitor is in service. The turbine is "hot" with 1st stage shell temperature > 350°F.
Initiating Cues:
The CRS directs you, the BOP, to startup the Main Turbine to rated speed in preparation for synchronization in accordance with OP 0105 Phase 3B starting at step 7.
Task Standards:
The Main Turbine has been tripped following a Hi Vibration IAW ARS 7-F-2.
Required Materials:
OP 0105 Reactor Operations, Revision 96, Phase 3 completed thru step 3B 6 VYOPF 0105.05, Reactor and Generation Systems Heatup to Low Power Check Sheet completed through end of Phase 3 Phase B, step 6. (Examinee Handout)
ARS 21005, CRP 9-7 Alarm Response Sheets, Revision 23. (7-F-2)
JPM-NRC CR (a)
Rev. 0, 11/13 Page 3 of 12 Simulator Setup:
IC-827, Plant at power with 1 1/2 bypass valves open, Turbine on jacking gear, chest warming complete, ready to bring the turbine up to speed.
OP 0105 completed through Phase 3 B step 6.
MALF Bearing 5, 6, 7 VIB 100%, 300SEC Ramp (mfTU_03E-G; Key 1)
The Simulator malfunction for Main Turbine Hi Vibration is on standby waiting for cue from evaluator or trigger when Main Turbine Reaches 200 and 300 RPM. Malfunction must have severity to exceed 10 mils on bearings 5, 6 and 7.
Post turbine trip enter mfTU 03E-G at 0%; Key 2 Ensure the following:
Open 1T ATB and 81-1T ATB and close T1-MOD Select and display or trend computer point ID T039 and T040 On CRP 9-7 bypass vibration trips by placing TURBINE VIB BYP SW-110-10 switch to the BYPASS position.
Place the manual selector for EXH HOOD SPRAY C-FCV-5 in the AUTO position (9-23).
Ensure annunciator STOP/CTRL VLV FAST CLOSURE BYP (5-K-8) is alarmed.
JPM-NRC CR (a)
Rev. 0, 11/13 Page 4 of 12 Evaluation Performance Steps TIME START:
NOTE:
All actions performed at CRP 9-7 unless otherwise noted.
SAT/UNSAT Step 1:
Review Procedure OP 0105 Phase 3.
Standard:
OP 0105 Phase 3 reviewed.
Examiner note:
Give the operator VYOPF 0105.05 at this time.
SAT/UNSAT
- Step 2:
Slowly open control valves with the LOAD LIMITER to roll unit off the turning gear.
Standard:
LOAD LIMITER control is slowly increased until TURNING GEAR ENGAGED alarm clears, RPMs increase as indicated on CRP 9-7 display.
SAT/UNSAT Step 3:
As soon as the unit rolls off turning gear: close the load limit Control to keep the speed from rising too fast.
Standard:
LOAD LIMITER control is decreased to close the control valves as indicated by control valve green lights on and red lights off.
SAT/UNSAT Step 4:
Carefully listen for rubs or unusual noises.
Standard:
Operator directs the floor operator stationed at the turbine operating floor to listen for rubs or unusual noises.
Interim Cue:
Floor operator reports no unusual noises.
SAT/UNSAT Step 5:
Correct any unstable intercept valve performance.
Standard:
Operator determines no unstable valve performance correction required by observing steady position indication.
SAT/UNSAT
- Step 6:
Reopen load limit.
Standard:
LOAD LIMITER control is slowly increased to raise turbine speed.
JPM-NRC CR (a)
Rev. 0, 11/13 Page 5 of 12 Evaluation Performance Steps SAT/UNSAT
- Step 7:
Maintain the appropriate acceleration rate while and load limit control position Standard:
Acceleration rate of 180 RPM per minute is not exceeded on and load limit control position of 40% is not exceeded on POI-110-25.
SAT/UNSAT Step 8:
Monitor bearing temperatures periodically.
Standard:
Operator periodically monitors turbine bearing temperatures during the startup on Recorder R 110-5/R-1 on CRP 9-23.
Evaluators Note:
At approximately 200 to 300 RPM (or when ready) cue simulator instructor to insert MALF Bearing 5, 6, 7 VIB 100%, 300SEC Ramp.
The operator may continue on with the procedure until alarm 7-F-2 is received at which point the operator should stop the turbine startup and address the Hi Vibration Alarm.
SAT/UNSAT Step 9:
Obtain Procedure ARS 21005, Alarm 7-F-2, Hi Vibration Alarm Standard:
Procedure ARS 21005, Window 7-F-2, TURB EXCESSIVE VIBRATION is obtained.
SAT/UNSAT Step 10:
Check for causes and correct if possible.
Standard:
Operator checks ERFIS Turbine Bearing Data display, Computer points W110 through W131, and Computer point T000. Operator may ask for local verification of vibration. Operator identifies cause #1 as Excessive vibration on main Turbine bearings 5, 6, and 7 exceeding the alarm setpoint.
Interim Cue:
If asked, the floor operator reports Hi vibration from the main turbine.
SAT/UNSAT Step 11:
Reduce Reactor power if approaching 10 mils.
Interim Cue:
If the operator attempts to reduce reactor power, inform the operator that another operator will address lowering reactor power.
JPM-NRC CR (a)
Rev. 0, 11/13 Page 6 of 12 Evaluation Performance Steps SAT/UNSAT Step 12:
Determine if turbine trip criteria is present for > 25% RTP.
Standard:
Operator determines that trip criteria are NOT met. Power is <25% and annunciator STOP/CTRL VLV FAST CLOSURE BYP (5-K-8) is alarmed.
SAT/UNSAT Step 13:
Determine if turbine trip criteria is present for < 25% RTP.
Standard:
Operator determines that trip criteria are IS met. Power is <25%,
annunciator STOP/CTRL VLV FAST CLOSURE BYP (5-K-8) is alarmed.
SAT/UNSAT
- Step 14:
Trip the Main Turbine when vibration exceeds 10 mils.
Standard:
Operator initiates a turbine trip by depressing the MTS-1 / MTS-2 pushbuttons. The Main Turbine indicates tripped.
SAT/UNSAT Step 15:
Verify Main Turbine tripped.
Standard:
Operator verifies turbine tripped by observing SV / CV position, Alarms and indications.
Interim Cue:
Post trip actions will be performed by other operators. This concludes this JPM.
TIME FINISH:
Terminating Cue:
The main turbine is tripped. Post trip actions will be performed by another operator.
JPM-NRC CR (a)
Rev. 0, 11/13 Page 7 of 12 Evaluators Comments:
SYSTEM: 245000 Main Turbine Generator and Auxiliary Systems A4. Ability to manually operate and/or monitor in the control room:
A4.06 Turbine speed (2.7 / 2.6)
JPM-NRC CR (a)
Rev. 0, 11/13 Page 8 of 12 EXAMINEE HANDOUT Initial Conditions:
A Plant Startup in progress. Reactor pressure is 950 psig. Main Turbine is on the Turning Gear. OP 0105 Phase 3, actions have been completed satisfactorily through Phase B, step 6. Generator H2 pressure is normal and does not need charging. The Generator Core Monitor is in service. The turbine is "hot" with 1st stage shell temperature > 350°F.
Initiating Cues:
The CRS directs you, the BOP, to startup the Main Turbine to rated speed in preparation for synchronization in accordance with OP 0105 Phase 3B starting at step 7.
JPM-NRC CR (a)
Rev. 0, 11/13 Page 9 of 12 EXAMINEE HANDOUT REACTOR AND GENERATION SYSTEMS HEATUP TO LOW POWER CHECK SHEET Date: Today NOTE If a step on these sheets cannot be completed at this time due to plant conditions, a variance will be initiated. On the initial line on the check off sheet a "V" will be placed indicating the step was not completed. A variance form will be filled out by the SM and the step that was bypassed will be tracked until it has been completed.
Corresponding Procedure Step Initials Time/Date PHASE 2 A
Entire Prep for Turbine Gen operation complete.
JRP 10 hr ago/ Today
- 19.
Verify MTS-1, MTS-2, and Emergency Gov tripped.
JRP 9 hr ago/ Today B
- 1.
Circ water system operating and intake gates open if allowed.
JRP 9 hr ago/ Today 5.a Verify main turbine on turning gear.
JRP 9 hr ago/ Today 5.b Steam packing seal exhauster running.
JRP 9 hr ago/ Today 5.d Steam seal established.
JRP 9 hr ago/ Today 5.i RHR-46A(B) leak check performed.
JRP 9 hr ago/ Today 6.d Mechanical vacuum pump started.
JRP 8 hr ago/ Today 6.e Vacuum breaker closed and water seal established.
JRP 8 hr ago/ Today
- 7.
Heatup Chemistry Limits per CHOP-RWS-4612-01 satisfied.
JRP 8 hr ago/ Today 8.e On CRP 9-39 HPCI STM SUPP LO PRESS BYP to NORMAL.
JRP 8 hr ago/ Today 8.e.1)
Independently verify HPCI STM SUPP LO PRESS BYP to NORMAL.
JRP 8 hr ago/ Today 8.e.2)
HPCI System Ready Light on.
JRP 8 hr ago/ Today 8.f HPCI system aligned per OP 2120 App. A.
JRP 7 hr ago/ Today
JPM-NRC CR (a)
Rev. 0, 11/13 Page 10 of 12 Corresponding Procedure Step Initials Time/Date PHASE 2 B
8.h On CRP 9-30 RCIC STM SUPP LO PRESS BYP to NORMAL.
JRP 7 hr ago/ Today 8.h.1)
Independently verify RCIC STM SUPP LO PRESS BYP to NORMAL.
JRP 7 hr ago/ Today 8.i RCIC system aligned per OP 2121 App. A.
JRP 7 hr ago/ Today 8.j HPCI/RCIC overspeed testing complete if required, otherwise N/A.
JRP 7 hr ago/ Today 8.j.1)
Verify HPCI/RCIC recoupled if required.
JRP 7 hr ago/ Today 9.a MS-10 throttled.
JRP 7 hr ago/ Today C
- 6.
Aux Feed Reg Blocking Valve FDW-10 checked open.
JRP 6 hr ago/ Today
- 7.
First reactor feed pump started.
JRP 6 hr ago/ Today
- 13.
Second reactor feed pump in normal after stop, and third in PULL-TO-LOCK.
JRP 6 hr ago/ Today
- 15.
Aux. feedwater reg. valve response satisfactory.
JRP 6 hr ago/ Today 21.a LOW COND VAC ISOL BYPASS switches on CRP 9-15 and 9-17 in NORMAL position.
JRP 6 hr ago/ Today 21.e MTS-2 reset.
JRP 6 hr ago/ Today 22.a Mechanical vacuum pump (Hogger) secured.
JRP 6 hr ago/ Today 22.b Hogger suction valve AE-FCV-35 closed.
JRP 6 hr ago/ Today 23.a Hogger seal water valve CST-86B closed.
JRP 6 hr ago/ Today 23.b Hogger cooling water valve TCW-83 closed.
JRP 6 hr ago/ Today
JPM-NRC CR (a)
Rev. 0, 11/13 Page 11 of 12 Corresponding Procedure Step Initials Time/Date PHASE 2 D
- 1.
Turbine steam chest warming started.
JRP 6 hr ago/ Today 2.a Bypass steam to condenser.
JRP 5 hr ago/ Today 2.b
- 1 BPV 7 to 15% open.
JRP 5 hr ago/ Today 2.e Turbine pressure control shifted to EPR.
JRP 4 hr ago/ Today
- 3.
RWCU reject flow discontinued.
JRP 4 hr ago/ Today 5
Additional circ water pumps started as necessary.
JRP 4 hr ago/ Today
- 7.
Chemistry requested to verify chem. limits for operating condition satisfied per CHOP-RWS-4612-01.
JRP 4 hr ago/ Today 10.d Mode switch in RUN.
JRP 4 hr ago/ Today 10.e Initiate Containment Inerting and establish DW/Torus P per OP 2115.
JRP 4 hr ago/ Today 10.f Recorders selected to APRM.
JRP 4 hr ago/ Today 10.g IRM detectors withdrawn.
JRP 4 hr ago/ Today 10.h Reactor Engineering initiated APRM GAF per OP 4400.
JRP 3 hr ago/ Today
- 11.
Initiate procedure for Placing SRV Backup Nitrogen Supply System In Service per OP 2191.
JRP 3 hr ago/ Today
- 12.
MS-74, MS-77, MS-78, and MS-23 closed.
JRP 3 hr ago/ Today
- 14.
Rx power held 5 to 7% until cChemistry limits for operating condition per CHOP-RWS-4612-01 are satisfied.
JRP 2 hr ago/ Today 16.i Aux. feedwater reg. valve is in MANUAL.
JRP 2 hr ago/ Today
JPM-NRC CR (a)
Rev. 0, 11/13 Page 12 of 12 Corresponding Procedure Step Initials Time/Date PHASE 2 D
16.j Level control transferred to one feed regulating valve.
JRP 2 hr ago/ Today
- 18.
Power increased until 11/2 bypass valves are open.
JRP 2 hr ago/ Today PHASE 3 JRP 1 hr ago/ Today A
- 2.
Generator hydrogen, seal-oil and isolated phase bus cooling operating.
JRP 1 hr ago/ Today
- 3.
HP feedheaters lined up for normal operation.
JRP 1 hr ago/ Today B
9.d If operated to correct unstable intercept valve performance, close bleed valves.
/
9.e If operated, verify bleed valves closed.
(ER2001-0819_01)
/
- 25.
Turbine started/minimum speed oil trip test completed.
/
- 36.
Generator core monitor in service per RP 2161.
/
C
- 1.
Turbine Control Valve Fast Closure Scram reset.
/
10.c&
g Generator phased to grid.
/
- 11.
Main and auxiliary steam drains and trap bypass valves closed.
/
- 27.
Feedwater heater startup vents closed.
/
- 28.
Heater drain pumps in AUTO.
/
- 30.
RPRP-USER-0527, Radiation Protection Department Site Specific Expectations and Requirements
/
- 32.
AP 0145 Data Collection initiated.
/
Check List Completed
/
Shift Manager (Print/Sign)
Date
NRC JPM-CR (b)
Rev. 0, 11/13 Page 1 of 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Open the MSIVs after a Group I Isolation Failure Mode:
N/A
Reference:
OP 2113, Main and Auxiliary Steam, Rev. 34 Task Number:
2000030501 Task Performance:
AO/RO/SRO RO/SRO Only X STA Only ___
Time Critical:
Yes No X 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: 15 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed/Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM-CR (b)
Rev. 0, 11/13 Page 2 of 8 Directions:
Discuss the information given on this page with the operator being evaluated. Allow time for the candidate 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.
After providing the initiating cue, ask the individual "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 Simulator 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:
A Group 1 isolation occurred five minutes ago, due to early rolling of the mode switch. OT 3100, Scram procedure has been carried out, mode switch is in shutdown. The Group 1 ISOL has been reset.
Initiating signals are clear.
Initiating Cues:
The Shift Manager has determined that the MSIVs need to be reopened. The CRS has directed you, the RO, to re-open the MSIVs in accordance with OP 2113, Main and Auxiliary Steam, starting at step 5i. Steps 5a through 5h were successfully performed by another operator. RPV pressure is being controlled with the SRVs between 800 and 1000 psig by another operator.
Task Standards:
MSIVs reopened in accordance with OP 2113, Main and Auxiliary Steam Required Materials:
OP 2113, Main and Auxiliary Steam Revision 34
NRC JPM-CR (b)
Rev. 0, 11/13 Page 3 of 8 Simulator Setup:
IC 828 Complete OT 3100 actions including the MODE Switch to SHUTDOWN Control pressure using SRVs 800-900 psig using the simulator soft panels.
Place each MSIV control switch to the CLOSE position.
Place Sample Isolation RV-39 control switch to CLOSE.
Place Sample Isolation RV-40 control switch to CLOSE.
Ensure condenser vacuum has recovered to > 12 HgA On CRP 9-5, verify PCIS SYS 1 and SYS 2 RESET PERMISSIVE lights are energized.
Reset the Group 1 isolation by positioning the GRP 1 ISOL RESET switch (CRP 9-5) to the INBD and OUTBD positions.
NRC JPM-CR (b)
Rev. 0, 11/13 Page 4 of 8 Evaluation Performance Steps TIME START:
SAT/UNSAT Step 1:
Review Procedure OP 2113 Standard:
OP 2113 reviewed Interim Cue:
Inform Operator that all prerequisites are completed satisfactory.
NOTE:
Operator should begin at step 5i, Re-opening the MSIVs following a PCIS Group 1 Isolation SAT/UNSAT
- Step 2:
Open the outboard MSIVs by placing their control switched to the AUTO OPEN position.
Standard:
On CRP 9-3, places the following control switches to AUTO/OPEN:
MS-86A MS-86B MS-86C MS-86D On CRP 9-3, verifies MS-86A through 86D are open by observing red light ON, green light OFF SAT/UNSAT
- Step 3:
To equalize the upstream and downstream pressures:
- 1) Open Stm Line Drain MS-74 Standard:
On CRP 9-3, places MS-74 control switch to OPEN and observes MS-74 red light ON, green light OFF SAT/UNSAT *Step 4:
- 2) Open Stm Line Drain MS-77 Standard:
On CRP 9-3, places MS-77 control switch to OPEN and observes MS-77 red light ON, green light OFF
NRC JPM-CR (b)
Rev. 0, 11/13 Page 5 of 8 Evaluation Performance Steps SAT/UNSAT
- Step 5:
- 3) Open Stm Line Drain MS-78 Standard:
On CRP 9-3, places MS-78 control switch to OPEN and observes MS-78 red light ON, green light OFF SAT/UNSAT Step 6:
If the bypass valves open, raise the setpoint of the turbine pressure regulator which is in service until the bypass valves shut.
Standard:
On CRP 9-7, verifies bypass valves BV1 - BV10 indicate shut, by verifying green lights ON, red lights OFF for the ten bypass valves or observing the position meter for bypass valve number 1, or the white lights on for all three pressure regulators.
SAT/UNSAT Step 7:
If the MSIVs have been closed for 30 minutes or more:
Standard:
Determines how long the MSIVs have been closed by asking the SM/CRS.
Interim Cue:
If asked, the MSIVs have been shut for only 10 minutes SAT/UNSAT
- Step 8:
When RX PRESS PI 2-3-56A(B) and MAIN STEAM PRESSURE PI-101-2 pressures are within 50 psig, open the inboard MSIVs.
Standard:
Using PI-2-3-56A or B (on CRP 9-5), and PI-101-2 (on CRP 9-7),
monitors steam pressure indications and determines when they are within 50 PSIG.
At CRP 9-3, Operator places the following control switches to AUTO-OPEN:
MS-80A MS-80B MS-80C MS-80D Operator observes red light ON, green light OFF for MS-80A through 80D
NRC JPM-CR (b)
Rev. 0, 11/13 Page 6 of 8 Evaluation Performance Steps SAT/UNSAT Step 9:
When the inboard MSIVs are open:
- 1) Close Stm Line Drain MS-74 Standard:
On CRP 9-3, places MS-74 control switch to CLOSE and observes MS-74 red light OFF, green light ON SAT/UNSAT Step 10:
- 2) Close Stm Line Drain MS-77 Standard:
On CRP 9-3, places MS-77 control switch to CLOSE and observes MS-77 red light OFF, green light ON SAT/UNSAT Step 11:
- 3) Close Stm Line Drain MS-78 Standard:
On CRP 9-3, places MS-78 control switch to CLOSE and observes MS-78 red light OFF, green light ON TIME FINISH:
Terminating Cue:
Inboard and Outboard MSIVs Open
NRC JPM-CR (b)
Rev. 0, 11/13 Page 7 of 8 Evaluators Comments:
SYSTEM: 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off A4. Ability to manually operate and/or monitor in the control room:
A4.03 Reset system isolations (3.6 / 3.5)
NRC JPM-CR (b)
Rev. 0, 11/13 Page 8 of 8 EXAMINEE HANDOUT Initial Conditions:
A Group 1 isolation occurred five minutes ago, due to early rolling of the mode switch. OT 3100, Scram procedure has been carried out, mode switch is in shutdown. The Group 1 ISOL has been reset.
Initiating signals are clear.
Initiating Cues:
The Shift Manager has determined that the MSIVs need to be reopened. The CRS has directed you, the RO, to re-open the MSIVs in accordance with OP 2113, Main and Auxiliary Steam, starting at step 5i. Steps 5a through 5h were successfully performed by another operator. RPV pressure is being controlled with the SRVs between 800 and 1000 psig by another operator.
NRC JPM-CR (c)
Rev. 0, 11/13 Page 1 of 9 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Manually Start HPCI and Inject to the Vessel Failure Mode:
Failure of Automatic Flow Controller
Reference:
OP 2120, High Pressure Coolant Injection System, Rev. 62 Task Number:
2060050101 Task Performance:
AO/RO/SRO RO/SRO Only X SRO Only ___
Time Critical:
Yes No X 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: 10 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed/Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM-CR (c)
Rev. 0, 11/13 Page 2 of 9 Directions:
Discuss the information given on this page with the operator being evaluated. Allow time for the candidate 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.
After providing the initiating cue, ask the individual "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 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:
A malfunction has occurred in the Feedwater System, resulting in a reactor scram on low level. Plant parameters are being controlled IAW EOP-1.
Initiating Cues:
The CRS has directed you to place HPCI in pressure control and inject with HPCI to restore / maintain RPV level 127 to 177 inches IAW OP 2120, Appendix D.
Task Standards:
HPCI is started and injecting with level control in MANUAL.
Required Materials:
OP 2120, High Pressure Coolant Injection System, revision 62 Simulator Setup:
- IC 829
- Take initial actions for scram at CRP 9-5
- Allow plant conditions to stabilize below 127 and above 90 inches.
- Insert mfHP_04 to 0% (HPCI Flow Controller failure) when the AUX OIL PUMP, P-85-1A, is started in step #10.- Event Trigger HPCI Controller Fails
NRC JPM-CR (c)
Rev. 0, 11/13 Page 3 of 9 Evaluation Performance Steps TIME START:
SAT/UNSAT Step 1:
Obtain OP 2120 Appendix D and review procedure Standard:
Operator obtains Appendix D and reviews requirements Interim Cue:
If asked, all pre-requisites are met.
SAT/UNSAT
- Step 2:
Open TEST RETURN HPCI-24 Standard:
Operator opens HPCI-24 fully.
SAT/UNSAT Step 3:
Close/check closed PUMP DISCHARGE HPCI-19 Standard:
Operator verifies using valve light indication that HPCI-19 is closed.
SAT/UNSAT Step 4: Throttle open FULL FLOW TEST HPCI 21 8-10 seconds Standard:
Operator holds the control switch for HPCI-21 to OPEN for 8-10 seconds.
SAT/UNSAT Step 5:
Start HPCI GL SL VAC FN-2-1A Standard:
Operator takes HPCI Gland Seal Vacuum Pump control switch to START and observes Red light ON, Green light OFF above HPCI Gland Seal Vacuum Pump control switch SAT/UNSAT Step 6:
Verify both trains of SBGT start Standard:
Operator checks SBGT fan and flow indication to verify both SBGTs are running.
NRC JPM-CR (c)
Rev. 0, 11/13 Page 4 of 9 Evaluation Performance Steps SAT/UNSAT Step 7:
Open MINIMUM FLOW HPCI-25 Standard:
Operator takes control switch for HPCI-25 to OPEN and verifies HPCI-25 is open by observing Red light ON, Green light OFF above control Switch.
SAT/UNSAT
- Step 8:
Open STEAM SUPPLY HPCI 14 Standard:
Operator takes the HPCI-14 control switch to OPEN and verifies HPCI-14 is open by observing Red light ON, Green light OFF above control switch SAT/UNSAT Step 9:
Verify that STM LINE DRAIN HPCI-42 and HPCI-43 close.
Standard:
Operator verifies that HPCI-42 and HPCI-43 close by observing Green lights ON, Red lights OFF above valve control switches SAT/UNSAT
- Step 10:
Start AUX OIL PUMP P-85-1A and monitor SI 23-2 TURBINE SPEED.
Standard:
Operator places HPCI Aux Oil Pump in START and verifies HPCI Aux Oil Pump running by observing Red light ON, Green light OFF above control switch.
Operator monitors turbine speed at CRP 9-3 on SI-23-2 Evaluator Note:
Ensure that simulator instructor inserts simulator malfunction, mfHP_04 to 0% (HPCI Flow Controller failure) when the AUX OIL PUMP, P-85-1A, is started.
NRC JPM-CR (c)
Rev. 0, 11/13 Page 5 of 9 Evaluation Performance Steps SAT/UNSAT Step 11:
As flow increases above 800 gpm, verify that MINIMUM FLOW HPCI-25 closes Standard:
Operator monitors speed and HPCI-25 position.
SAT/UNSAT
- Step 12:
Recognize failure of flow to increase; failure of auto flow controller Standard:
Operator recognizes that HPCI flow does not rise to the expected 4,000 gpm, and informs CRS Interim Cue:
Acknowledge report as CRS. If asked for direction, direct Operator to inject as necessary to maintain 127 - 177 inches SAT/UNSAT
- Step 13:
Place HPCI PUMP FLOW CONTROLLER FIC 23-108 in MANUAL.
Standard:
Operator transfers the HPCI Pump Flow Controller to MANUAL Interim Cue:
If report of transfer to MANUAL made, acknowledge report as CRS.
SAT/UNSAT
- Step 14:
Control flow using the MANUAL knob Standard:
Operator adjusts the manual potentiometer to raise turbine speed (>2200-4000 rpm) / pump flow rate.
SAT/UNSAT Step 15:
Monitor the following HPCI parameters:
Exhaust Pressure (0-50 psig)
Suction Pressure (6-30 psig)
Steam Supply Pressure (150-1120 psig)
Turbine Speed (>2200-4000 rpm)
Discharge Pressure (<1250 psig)
Standard:
Operator monitors parameters on CRP 9-3 as indicated above
NRC JPM-CR (c)
Rev. 0, 11/13 Page 6 of 9 Evaluation Performance Steps SAT/UNSAT
- Step 16: Open PUMP DISCHARGE HPCI-19 Standard:
Operator takes HPCI-19 switch to open and throttles HPCI-21 as necessary to slowly raise level. Operator monitors PI 23-109 (Pump Discharge Pressure) and PI 23-109 (Steam Supply Pressure) for pressures indicative of HPCI injection.
RPV level is at or approaching 127 inches.
Interim Cue:
Once parameters are monitored, inform Operator that no further actions are required for this JPM.
SAT/UNSAT Step 17:
Place Keeping and STAR used consistently throughout.
Standard:
Steps are circled as performed, crossed out as completed and N/Ad as appropriate. STAR used consistently for each manipulation.
TIME FINISH:
Terminating Cue:
HPCI injecting into vessel with flow controller in MANUAL and RPV level rising.
NRC JPM-CR (c)
Rev. 0, 11/13 Page 7 of 9 Evaluator Comments:
SYSTEM: 206000 High Pressure Coolant Injection System A4. Ability to manually operate and/or monitor in the control room:
A4.02 Flow controller: BWR-2,3,4 (4.0 / 3.8)
NRC JPM-CR (c)
Rev. 0, 11/13 Page 8 of 9 EXAMINEE HANDOUT Initial Conditions:
A malfunction has occurred in the Feedwater System, resulting in a reactor scram on low level. Plant parameters are being controlled IAW EOP-1.
Initiating Cues:
The CRS has directed you to place HPCI in pressure control and inject with HPCI to restore / maintain RPV level 127 to 177 inches IAW OP 2120, Appendix D.
NRC JPM IP (i)
Rev. 0, 11/13 Page 1 of 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Perform Local Firing of Squib Valves Failure Mode:
Valve fails to fire initially
Reference:
OE 3107, Rev 29, OE Appendices, Appendix I Task Number:
20070705 Task Performance:
AO/RO/SRO X RO/SRO SRO Only AO Only 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: 15 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed/Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM IP (i)
Rev. 0, 11/13 Page 2 of 8 Directions:
Discuss the information given on this page with the operator being evaluated. Allow time for the candidate 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.
After providing the initiating cue, ask the individual "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.
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:
Scram condition exists. Reactor is not shutdown, steps are being taken per EOP-2. Torus temperature is approaching 110°F and normal squib valve firing did not function. SLC keylock switch on CRP 9-5 is in OFF position.
Initiating Cues:
CRS directs you to assist them with Alternate SLC Injection by local firing of the squib valves using OE 3107, Appendix I starting at Step 4.b.
Task Standards:
SLC squib valve fired locally after identification of the failed squib valve in accordance with OE 3107, Appendix I.
Required Materials:
OE 3107, OE Appendices, Appendix I, Revision 29
NRC JPM IP (i)
Rev. 0, 11/13 Page 3 of 8 Evaluation Performance Steps TIME START:
SAT/UNSAT Step 1:
Obtain the procedure, review prerequisites.
Standard:
OE 3107 Appendix I obtained; prerequisites reviewed.
Interim Cue:
When asked, inform the operator that all the prerequisites are satisfied.
SAT/UNSAT
- Step 2:
Obtain the 1.5 VDC Squib valve firing battery available with an alligator clip on each end.
Standard:
The 1.5 VDC Squib valve firing battery available with an alligator clip on each end.
Note:
EOP toolbox is not be opened for this JPM.
Interim Cue:
When the operator locates EOP Toolbox and indicates he will get battery firing device, inform him he has the battery firing device.
All other prerequisites are satisfied.
SAT/UNSAT
- Step 3:
At SLC-14A(B): unscrew Amphenol connector from the squib valve Standard:
Squib Valve Amphenol connector removed from SLC-14A(B).
Interim Cue:
When the operator locates squib valve and describes method to remove connector, inform him that the Amphenol connector is disconnected.
SAT/UNSAT
- Step 4:
Clip one of the leads from the battery to Pin A.
Standard:
Jumper connected from battery terminal to Pin A; Pin A is the thicker pin (see Figure 1).
Interim Cue:
When the operator indicates he will clip one lead from the battery to Pin A (using Figure 1 if necessary), inform him that the lead is connected.
NRC JPM IP (i)
Rev. 0, 11/13 Page 4 of 8 Evaluation Performance Steps SAT/UNSAT Step 5:
Touch the other battery lead to Pin B (next clockwise terminal).
Standard:
Other lead from battery touched to Pin B (see Figure 1).
Interim Cue:
When the operator indicates he will touch the other lead to the next clockwise terminal, inform operator that no pop was heard when terminal B was contacted.
SAT/UNSAT
- Step 6:
If a pop is not heard, THEN change location of the battery leads to the other two pins: ie, C and D.
Standard:
Location changed of the battery leads to Pin C and D (see Figure 1).
Interim Cue:
When the operator indicates he will touch the lead to the other terminal Pins C and D, inform operator that a pop was heard when the last terminal was contacted.
SAT/UNSAT Step 7:
Remove the Battery Standard:
Battery and leads unclipped from Amphenol terminals.
Interim Cue:
When the operator indicates he will remove the battery and leads, inform him they are removed.
SAT/UNSAT Step 8:
Turn SLC Switch (Keylock) to SYS 1 or SYS 2.
Standard:
Contacts the Control Room to place the SLC switch (keylock) to SYS 1 or SYS 2.
Interim Cue:
When the operator indicates that he will call to place the SLC switch (keylock) to SYS 1 or SYS 2, inform operator that the CRO has placed the switch in SYS 1 and that they will perform the remainder of Appendix I.
NRC JPM IP (i)
Rev. 0, 11/13 Page 5 of 8 Evaluation Performance Steps SAT/UNSAT Step 9:
Place-keeping and STAR used consistently throughout.
Standard:
Steps are circled as performed crossed out as complete and N/Ad as appropriate. STAR used consistently for each simulated manipulation TIME FINISH:
Terminating Cue:
Squib Valve fired locally in accordance with OE 3107, Appendix I.
NRC JPM IP (i)
Rev. 0, 11/13 Page 6 of 8 Evaluator Comments:
SYSTEM: 211000 Standby Liquid Control System A2. Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.02 Failure of explosive valve to fire (3.6 / 3.9)
NRC JPM IP (i)
Rev. 0, 11/13 Page 7 of 8 EXAMINEE HANDOUT Initial Conditions:
Scram condition exists. Reactor is not shutdown, steps are being taken per EOP-2. Torus temperature is approaching 110°F and normal squib valve firing did not function. SLC keylock switch on CRP 9-5 is in OFF position.
Initiating Cues:
CRS directs you to assist them with Alternate SLC Injection by local firing of the squib valves using OE 3107, Appendix I starting at Step 4.b.
NRC JPM IP (i)
Rev. 0, 11/13 Page 8 of 8 Figure 1
NRC JPM IP (j)
Rev. 0, 11/13 Page 1 of 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Startup the "A" RPS MG Set Failure Mode:
N/A
Reference:
OP 2134, "Reactor Protection System," Rev. 24 Task Number:
2127040104 (AO) / 2127080101 (RO/SRO)
Task Performance:
AO/RO/SRO X RO/SRO SRO Only Time Critical:
Yes No X Operator Performing Task:
Examiner:
Date of Evaluation:
Method of Testing: Simulation X Performance Discuss Setting: Classroom Simulator Plant X Performance Expected Completion Time: 15 minutes Evaluation Results:
Performance: PASS FAIL Time Required:
Prepared by:
Operations Training Instructor Date Reviewed by:
SRO Licensed/Certified Reviewer Date Approved by:
Operations Training Superintendent Date
NRC JPM IP (j)
Rev. 0, 11/13 Page 2 of 8 Directions:
Discuss the information given on this page with the operator being evaluated. Allow time for the candidate 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.
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.
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 "A" RPS MG set is being returned to service after brush replacement.
There is an Operator waiting in the Control Room to assist you.
Initiating Cues:
The CRS directs you to startup the "A" RPS MG set per OP 2134 Section A starting at step A 3.
Steps A 1 and A 2 has been successfully completed by another operator. Inform the CRS when the MG set is ready to be placed in service.
Task Standards:
"A" RPS M/G Set running, producing 118+/-1 volts.
"A" RPS M/G Set output breaker shut.
Power Panels A-1 and A-2 breakers shut.
Required Materials:
OP 2134, Reactor Protection System, revision 24
NRC JPM IP (j)
Rev. 0, 11/13 Page 3 of 8 Evaluation Performance Steps TIME START:
SAT/UNSAT Step 1:
Obtain Procedure, review administrative limits, precautions and prerequisites.
Standard:
OP 2134 obtained, administrative limits, precautions and prerequisites reviewed.
Interim Cue:
If asked, all prerequisites have been met.
SAT/UNSAT Step 2:
Check MG 3-1A Output Breaker on local panel is OFF Standard:
Checks position of MG Output Breaker, observes breaker in the OFF (Down) position Interim Cue:
When checked, inform Operator that breaker is in the OFF (Down) position.
SAT/UNSAT Step 3:
Check Circuit Breakers on RPS Power Protection Panels A1 and A2 are OFF Standard:
Checks position of the RPS Power Protection Panel breakers, observes breakers in the OFF (Down) position Interim Cue:
When checked, inform Operator that breakers are in the OFF (Down) position.
SAT/UNSAT
- Step 4:
Depress the Motor ON Pushbutton on local control panel Standard:
Simulates starting the "A" RPS MG Set by depressing the Motor ON pushbutton Interim Cue:
When simulated, inform Operator that the pushbutton has been depressed.
NRC JPM IP (j)
Rev. 0, 11/13 Page 4 of 8 Evaluation Performance Steps SAT/UNSAT Step 5:
Verify RPS MG Set "A" starting Standard:
Verifies that "Motor On" red light is ON, and that MG Set is starting and coming up to speed Interim Cue:
When checked, inform Operator that the "Motor On" red light is ON, and that the MG Set has started and is coming up to speed.
SAT/UNSAT Step 6:
Check Output Voltage Standard:
Checks MG Set output voltage on local panel "A-C Volts" meter after MG Set reaches normal operating speed Interim Cue:
When checked, inform Operator that output voltage indication has increased and presently indicates 119 volts.
SAT/UNSAT
- Step 7:
Close the M/G Set A Output Breaker Standard:
Simulates positioning the output breaker to the CLOSED (Up) position Interim Cue:
When simulated, inform Operator that the breaker is in the CLOSED (Up) position.
SAT/UNSAT Step 8:
Request Maintenance to check M/G Output of 118 +/- 1 volts in RPS Power Protection Panel PPP-A-1 Standard:
Requests Maintenance to verify M/G Output of 118 +/- 1 volts in RPS Power Protection Panel PPP-A-1 Interim Cue:
When requested, inform Operator that the MG Set output voltage is 117.8 volts as read on the portable calibrated meter.
NRC JPM IP (j)
Rev. 0, 11/13 Page 5 of 8 Evaluation Performance Steps SAT/UNSAT Step 9:
Check RPS Power Protection Panel PPP-A-1 POWER IN Light is ON Standard:
Checks "Power In, Motor Gen" red light ON on Panel PPP-A-1 Interim Cue:
When checked, inform Operator that Power In, Motor Gen" red light ON SAT/UNSAT
- Step 10:
Place Panel PPP-A-1 Output Breaker to OFF Standard:
Simulates placing breaker in OFF Interim Cue:
When simulated placing breaker in OFF, inform Operator that breaker is in the OFF (Down) position SAT/UNSAT
- Step 11:
Place Panel PPP-A-1 Output Breaker to ON Standard:
Simulates placing breaker in ON Interim Cue:
When simulates placing breaker in ON, inform Operator that breaker is in the ON (Up) position SAT/UNSAT Step 14:
Check that the POWER OUT light on Panel PPP-A-1 is ON Standard:
Checks that the POWER OUT light on PPP-A-1 is ON Interim Cue:
When checked, inform Operator that the POWER OUT light on PPP-A-1 is ON SAT/UNSAT Step 15:
Check Panel PPP-A-2 POWER IN light is ON Standard:
Checks "Power In" light on A-2 is ON Interim Cue:
When checked, inform Operator that the "Power In" light is ON
NRC JPM IP (j)
Rev. 0, 11/13 Page 6 of 8 Evaluation Performance Steps SAT/UNSAT
- Step 16:
Place Panel PPP-A-2 Output Breaker to OFF Standard:
Simulates placing breaker to the OFF (Down) position Interim Cue:
When simulated, inform Operator that breaker is in the OFF (Down) position SAT/UNSAT
- Step 17:
Place Panel PPP-A-2 Breaker to ON Standard:
Simulates placing breaker to the ON (Up) position Interim Cue:
When simulated, inform Operator that breaker is in the ON (Up) position SAT/UNSAT Step 18:
Check that the POWER OUT light on Panel PPP-A-2 is ON Standard:
Checks that the POWER OUT light on PPP-A-2 is ON Interim Cue:
When checked, inform Operator that the POWER OUT light on PPP-A-2 is ON SAT/UNSAT Step 19:
Inform CRS that the A RPS MG Set is ready to be placed in service.
Standard:
Makes report to CRS.
Interim Cue:
Acknowledge report as CRS, and inform Operator that another operator will place the MG Set in service TIME FINISH:
Terminating Cue:
A RPS MG Set started and ready to be placed in service (through Step A.11 of OP 2134)
NRC JPM IP (j)
Rev. 0, 11/13 Page 7 of 8 Evaluators Comments:
SYSTEM: 212000 Reactor Protection System A1. Ability to predict and/or monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including:
A1.01 RPS motor-generator output voltage (2.8 / 2.9)
NRC JPM IP (j)
Rev. 0, 11/13 Page 8 of 8 EXAMINEE HANDOUT Initial Conditions:
The "A" RPS MG set is being returned to service after brush replacement.
There is an Operator waiting in the Control Room to assist you.
Initiating Cues:
The CRS directs you to startup the "A" RPS MG set per OP 2134 Section A starting at step A 3.
Steps A 1 and A 2 has been successfully completed by another operator. Inform the CRS when the MG set is ready to be placed in service.
Page 1 of 21 Facility:
Vermont Yankee Scenario No.:
1 Op Test No.:
2014 NRC Examiners:
Operators:
Initial Conditions:
100% MOL Steady State conditions. SBO EDG is out of service (tagged out) for Electrical Maintenance trouble shooting of the voltage regulator. A & F APRMs are bypassed. House Heating Boilers in service.
Turnover:
Perform Turbine Oil Pump Test in accordance with OP 4160 section B, steps B.1.a and B.1.b Critical Tasks: See scenario summary Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-BOP N-CRS Perform Turbine Oil Pump Test IAW OP 4160 2
KEY 1 mfRD_15 0%
I-RO I-CRS Control Rod Drive flow controller fails low 3
KEY 2 mfAD_09B TS-SRO RV-71B de-energized 4
KEY 3 KEY 4 mfRR_07A 50% over 300 sec mfRR_08A 15% over 800 sec.
N/A C-ALL C-RO C-SRO TS-SRO R-ALL A Recirc Pump # 1 Seal Failure A Recirc Pump # 2 Seal Failure Rapid load reduction - Single Loop Operation (TS) 5 KEY5 mfRR_05B mfRD12A 35%
Preinsert mfRD12B 40%
Preinsert M-ALL B Recirculation Pump Trip; Hydraulic ATWS
Page 2 of 21 mfRP_09 A&B Preinsert C-ALL PCIS Group V Isolation Failure mfSL_01 A or B C-RO Operating SLC Pump Trips 60 seconds after start mfRD_01B Preinsert B CRD fails to start (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Summary The crew assumes the watch with the unit at 100% power. SBO EDG is out of service (tagged out) for Electrical Maintenance trouble shooting of the voltage regulator. A & F APRMs are bypassed. House Heating Boilers in service. The SRO will direct the BOP to Perform Turbine Oil Pump Test in accordance with OP 4160 section B.
After the performance of the Turbine Oil Pump test, the Control Rod Drive flow controller will fail low resulting in the in-service FCV throttling close. The RO will respond to typer alarms, review CRD indications and diagnose the controller failure. The SRO will enter OPON-3145-01, Loss of CRD Regulating Function, and direct the RO to place the CRD flow controller in manual and restore CRD flow.
Once CRD flow has been stabilized, the BOP will respond to annunciator 3-A-4, ADS Power Failure and determine that the position indicating lights for RV-71B are extinguished. The SRO will review Technical Specifications, determine that RV-71B is inoperable and enter TS LCO 3.5.F.2.
As a result of the CRD flow controller failure, the A Recirculation Pump #1 Seal will fail.
The BOP will respond to seal indications and alarms and diagnose the failure of the #1 seal. The SRO will enter OPON-3142-01, Recirc Pump Seal Failure and direct the BOP to increase monitoring of seal parameters. After the commencement of monitoring, the
- 2 seal will fail requiring the A Recirculation Pump to be shut down and the crew to conduct a rapid load reduction IAW OPOT-3118-01 Recirculation Pump Trip. The RO will insert control rods to lower reactor power to approximately 45%. The SRO will review Technical Specifications and enter TS LCO 3.6.G.1 for single loop operation.
After reactor power is reduced to approximately 45% and the B Recirculation pump speed is being lowered, the B Recirculation Pump will trip. The crew will recognize the need to manually scram the reactor. Manual scram will result in partial rod insertion and the SRO will direct inhibiting ADS (Critical Task) and insertion of control rods / boron injection (Critical Task). With the reactor not shutdown, the SRO will direct the RO to inject boron using the standby liquid control system. The operating SLC pump will trip after 60 seconds and the RO will diagnose failure and start the remaining SLC Pump to re-establish boron injection. PCIS Group V valves (RWCU-15, 18, and 68) will fail to isolate. The RO will diagnose the failure and manually close the valves.
During the ATWS, conditions will be met to perform power/level control TERMINATE AND PREVENT INJECTION into the RPV using appendix GG, until conditions are met to re-establish injection (Critical Task)..
Page 3 of 21 The scenario will be terminated when all rods are inserted and RPV level is restored.
Page 4 of 21 SIMULATOR EVALUATION GUIDE 2014 NRC Examination, Scenario #1 NRC Evaluators:
ILO Candidates CRS OATC BOP Critical Task Performance:
SAT UNSAT (Circle One)
Date Administered:
Prepared by:
Date:
Lead Exam Developer Reviewed by:
Date:
Operations Representative Approved by:
Date:
Operations Training Superintendent
Page 5 of 21 CREW BRIEF:
-Power level: 100%
-Rod Sequence:
Rapid Shutdown Sequence A2
-Rod Group: 20
-Equipment out of service and/or tagged or abnormalities:
- 1.
- 2.
Booster Pumps
- 3.
-Reason For Equipment out of Service or tagged:
- 1.
Cooling Towers - Winter Operations
- 2.
Booster Pumps - Winter Operations
- 3.
SBO EDG is out of service (tagged out) for Electrical Maintenance trouble shooting of the voltage regulator
-Applicable Tech Spec LCOs:
- 1.
NONE EOOS Color: Green
-Plant evolutions in progress/Scheduled Shift Evolutions:
- 1.
Perform Turbine Oil Pump Test in accordance with OP 4160 section B, steps B.1.a and B.1.b SCENARIO
SUMMARY
See ES-D-1 for summary TERMINATING CONDITION(S):
- 1. All rods inserted
- 2. RPV Level restored and maintained between 127 and 177
Page 6 of 21
REFERENCES:
- 1. OP 4160, Once/Week Pump Performance Test
- 2. OPON-3145-01, Loss of CRD Regulating Function.
- 3. 3-A-4, ADS POWER FAILURE
- 4. 4-G-2, Recirc Pump A Inner Seal Leaking Hi/Lo annunciator
- 5. OPON-3142-01, Recirc Pump Seal Failure
- 6. 4-G-2, Recirc Pump A Outer Seal Leaking Hi/Lo annunciator
- 7. OP 2111, Control Rod Drive System
- 8. OT 3118 Recirc Pump Trip
- 11. EOP-3, Primary Containment Control
Page 7 of 21 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up:
- 1. IC# 830, 100% Power, winter line-up
- 2. Over ride annunciator 8-D-9, SBO EDG Trouble to ON
- 3. Ensure Hotwell level controllers are functioning correctly Discretionary Distracter Malfunctions/RFs/IOs:
No.
MF/RF/IO #
Severity Ramp REM #
Act. Time Description
- 1.
mfRD_12A 35%
N/A Pre-insert Partial SCRAM
- 2.
mfRD_12B 40%
N/A Partial SCRAM
- 3.
mfRP_09 A&B N/A N/A PCIS Group V Isolation Failure
- 4.
mfRD_01B N/A N/A B CRD Pump fails to start
- 5.
mfRD_15 0%
N/A KEY 1 After oil pump test Control Rod Drive flow controller fails low
- 6.
mfAD_09B N/A N/A KEY 2 After CRD flow re-established RV-71B de-energized
- 7.
mfRR_07A 50%
300 sec KEY 3 After TS evaluated A Recirc Pump # 1 Seal Failure
- 8.
mfRR_08A 15%
800 sec KEY 4 After initial response A Recirc Pump # 2 Seal Failure
- 9.
mfRR_05B N/A N/A KEY 5 When B recirc pump speed is lowered B Recirculation Pump Trip; Hydraulic ATWS
- 10.
mfSL_01 A or B N/A N/A
>60 seconds after start Operating SLC Pump Trips 60 seconds after start
Page 8 of 21 SIMULATOR OPERATOR INSTRUCTIONS (Continued)
Additional Instructions:
- 1. Time compression may be used at the discretion of the Lead Evaluator. If time compression is used the crew will be notified.
- 2. A call to the Work Week Manager (WWM) will initiate all expected activities (including Duty Manager, Ops Manager, Maintenance, and AOs) outside the Control Room for a particular malfunction.
- 3. The Lead Evaluator will determine when the event objectives have been met and the next event may be initiated. Event actuation times will be referenced and scenario flow will be considered during this determination.
- 4. When called as AO during oil pump testing, report oil pump(s) are operating normally.
- 5. When AO is asked to investigate the ADS power failure alarm, report that the breaker for CKT 8 on DC-1C and the breaker for CKT2 on DC-2C are closed. Report as I&C after approximately five minutes that the A ADS power loss was caused by an apparent short in the valve control circuitry, causing fuses F3A & F11A on (CWD 752) to blow.
- 6. If requested to replace the blown fuses for SRV-71A, recommend as I&C that the fuses NOT be replaced until troubleshooting can be completed.
- 7. If requested as AO to secure A recirc pump seal purge then take rfRD_11 to 0%.
- 8. If requested to shut CRD-56, use rfRD_02, when RPV level is being controlled < 90.
Page 9 of 21 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task
Description:
Perform OP 4160 Once/Week Pump Performance Test Section 1.a and b.
POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
SRO Briefs Crew Directs performance OP 4160 Once/Week Pump Performance Test Section 1.a and b.
- 2.
BOP To test the Auxiliary oil Pump, perform the following:
ON CRP 9-7 take Aux Oil Pump Test switch to the TEST
- 3.
BOP Contacts AO to check that the auxiliary oil pump starts and is operating satisfactorily
- 4.
BOP Place the test switch to NORM
- 5.
BOP Verify the auxiliary oil pump does not automatically stop
- 6.
BOP Stop the auxiliary oil pump
- 7.
BOP Verify the control switch returns to normal after stop (green flag).
- 8.
BOP To test the Turning Gear Oil Pump, perform the following:
On CRP 9-23 take Turn Gear L.O. Pump Test switch to the TEST position.
- 9.
BOP Contacts AO to check that the turning gear oil pump starts and is operating satisfactorily.
- 10.
BOP Allow the test switch to return to midposition
- 11.
BOP Verify the turning gear oil pump does not automatically stop
Page 10 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 12.
BOP Stop the turning gear oil pump
- 13.
BOP Verify the control switch returns to AUTO Once the test is complete continue with EVENT 2 OR at lead evaluators discretion.
Page 11 of 21 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task
Description:
Respond to a failure of the CRD flow controller.
POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
CREW Recognize a loss of CRD flow (ERFIS typer alarm and 9-5 panel indications)
KEY 1:________
- 2.
SRO Direct actions in accordance with OPON-3145-01, Loss of CRD Regulating Function.
- 3.
SRO Place flow controller in manual and attempt to open
- 4.
RO Take manual control of the Flow Control valve and attempt to open it.
- 5.
RO Transfer CRD System Flow Control from Automatic to Manual as follows :
- 6.
RO On CRD SYSTEM FLOW CONTROL FIC 3-301 depress the A/M pushbutton.
- 7.
RO To make adjustments when in manual, proceed as follows:
- Adjust output as required by plant conditions using the adjustment knob.
Page 12 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 8.
RO Adjust the CRD parameters to normal.
Once CRD flow is restored and conditions stabilized continue with EVENT 3 OR at lead evaluators discretion.
Page 13 of 21 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task
Description:
Respond to a failure of RV-71B POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
BOP Acknowledge 3-A-4 ADS POWER FAILURE and determine RV-71B is deenergized.
KEY 2 :________
- 2.
BOP Directs AO to verify breaker for DC-1C CKT #8 is closed.
- 3.
BOP Directs AO to verify breaker for DC-2C CKT #2 is closed.
- 4.
BOP Verify that DC-1, DC-2 are energized.
- 5.
SRO Consult Tech. Specs. 3.5, declare RV-71B inoperable and enter TS LCO 3.5.F.2 Once TS are evaluated continue with EVENT 4 OR at lead evaluators discretion.
Page 14 of 21 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task
Description:
Respond to A Recirc Pump seal failures and securing the recirc pump.
POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
CREW Acknowledge/respond to Recirc Pump A Inner Seal Leaking Hi/Lo annunciator (4-C-2)
KEY 3 :________
Recognize Recirc A Outer Seal pressure rising; inform SRO
- 2.
SRO Enter/direct actions IAW OPON-3142-01 (Recirc Pump Seal Failure)
Monitor seal pressures Monitor seal temperatures
- 3.
RO When directed, monitor seal pressures
- 4.
BOP When directed, monitor seal temperatures
- 5.
CREW Acknowledge/respond to Flow Det A Outer Seal LKG Hi annunciator (4-C-1)
KEY 4 :________
Recognize Recirc A Outer Seal pressure lowering; inform CRS
- 6.
SRO Enter/Direct actions IAW OPON-3142-01 Shutdown A Recirc pump Close Pump Suction RV-43A Close Pump Discharge RV-53A Secure seal purge A pump
Page 15 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 7.
RO When directed, shutdown A Recirc pump Close Pump Suction RV-43A Close Pump Discharge RV-53A
- 8.
SRO Direct seal purge to affected pump secured per OP 2111
- 9.
SRO Enter / direct actions IAW OPOT-3118-01 (Recirc Pump Trip):
Depress PB2 to set down level setpoint to 155 inches.
Monitor APRM indications Identify location on Power-to-Flow Map (Figure 2.4-1)
- 10.
RO When directed:
Depress PB2 to set down level setpoint to 155 inches.
Monitor APRM indications Identify location on Power-to-Flow Map (Figure 2.4-1)
- 11.
CREW Make Plant announcements for RR pump trip and power reduction
- 12.
SRO Direct rod insertion to 40-45%
RTP using the rapid Shutdown Sequence
- 13.
RO When directed, insert control rods using the rapid Shutdown Sequence to 40-45% RTP
- 14.
SRO Direct running recirc pump speed reduced to 65-70% rated speed
Page 16 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 15.
RO When directed, lower running recirc pump speed to 65-70%
rated speed
- 16.
SRO Consult TS 3.6.G to determine requirements for single loop operation; 3.6.G.1.a & 3.6.G.1.c
- 17.
CREW Inform WWM of the A Recirc Pump Trip Once A Recirc Pump speed is lowered and TS evaluates, continue with Event 5 OR at lead evaluators discretion.
TS for single loop operation may be accomplished as a follow up question after the scenario is terminated.
Page 17 of 21 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task
Description:
Respond to Trip of the B Recirculation Pump, ATWS POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
SRO When B Recirc Pump trips:
KEY 5 :________
Scram the reactor
- 2.
RO When directed, scram the reactor Recognize failure of rods to insert; inform CRS
- 3.
RO Actuate the ARI/RPT logic AND ensure that the recirc drive motor breakers are tripped within 2 minutes of the scram Both Recirc pumps previously tripped
- 4.
SRO When informed of the scram failure enter and direct crew actions IAW EOP-1 and EOP-2
- 5.
STA When directed, verify EOP-1 Table A automatic actions
- 6.
CT-1 With a reactor scram required and the reactor not shutdown, INHIBIT ADS to prevent an uncontrolled RPV depressurization and thereby prevent a potentially significant power excursion.
Standard:
Inhibit ADS prior to automatic initiation.
Page 18 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 7.
SRO Enter and direct actions per EOP-2:
Appendix BB and G are available; Do NOT close CRD-56 until Terminate and Prevent Appendix GG has been completed and vessel level is lowered below 90 Implement App P to keep the MSIVs Open When steam flow <0.5lbm/hr per steamline, place Mode Switch in SHUTDOWN Verify ARI/RPT initiated Insert control rods with one or more appropriate appendices Stabilize pressure 800-1050 psig with BPVs
- 8.
BOP When directed:
Inhibit ADS Implement App P to keep the MSIVs Open Stabilize pressure 800-1050 psig with BPVs.
- 9.
CT-2 With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.
Standard:
Page 19 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS Actions taken within 10 minutes of the scram failure to implement appropriate appendices and/or inject SLC.
Only one method needs to be used. The method must result in successful control rod insertion or SLC injection
- 10.
RO When steam flow <0.5lbm/hr per steamline, place Mode Switch in SHUTDOWN Note: This step is an Immediate Action, and may be performed without direction.
Coordinate with AOs (as necessary) to insert rods using appropriate Appendices Appendix BB and G will be available.
RO may perform this as a immediate action.
Inject SLC. Recognize trip of operating SCL Pump and start other SLC Pump
- 11.
RO Recognizes failure of PCIS Group 5, closes RWCU-15, 18 and 68.
Informs SRO
- 12.
CT-3 During an ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION (with the exception of boron, RCIC and CRD) into the RPV until conditions are met to re-establish injection.
STANDARD:
Completion of Terminate and prevent injection IAW OE 3107 Appendix GG within 5 minutes of loss of forced circulation
- 13.
SRO Terminate and prevent injection per Appendix GG
Page 20 of 21 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 14.
RO/BOP When directed, terminate and prevent injection per Appendix GG. Inform CRS when:
Appendix GG complete RPV level reaches 90 inches Power drops to <2%
- 15.
SRO When conditions are met to re-establish injection, direct RPV level restored and maintained between -19" and 90" using feed and condensate
- 16.
RO When directed, restore and maintain RPV level between
-19" and 90", using feed and condensate Terminate scenario when terminate & prevent is complete, all rods inserted and RPV level is being controlled OR at lead evaluators discretion.
Evaluator Follow-up question (at examiners discretion): Classify event. Site Area Emergency IAW AP 3125 Appendix A (SS2.1)
Page 21 of 21 SCENARIO 1 EVALUATOR NOTES:
Page 1 of 18 Facility:
Vermont Yankee Scenario No.:
2 Op Test No.:
2014 NRC Examiners:
Operators:
Initial Conditions:
80% reactor power, MOL. Power was reduced to allow maintenance to evaluate A Main Feedwater Pump seal leakage. A main feedwater pump is in service. SBO EDG is out of service (tagged out) for Electrical Maintenance trouble shooting of the voltage regulator. A & F APRMs are bypassed. House Heating Boilers in service.
Turnover:
Place Torus Cooling in service in accordance with OPOP-RHR-2124 Residual Heat Removal System.
Section 7.3 Torus Cooling during normal operations, using the A RHR Pump and the A RHRSW Pump.
RHR fill and vent has been completed.
Critical Tasks: See scenario summary Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-BOP N-SRO Establish Torus Cooling 2
KEY 1 mfNM_05C 0%
I-RO I-SRO TS-SRO C APRM Fails downscale 3
KEY 2 mfSW_07A mfSW_18C Preinsert C-BOP C-SRO TS-SRO A Service Water Pump trips; standby pump (C) fails to auto start 4
KEY 3 mfHP_09 5% over 300 sec mfPC_1HP15 mfPC_1HP16 Preinsert M-ALL HPCI Steam Leak in Reactor Building - small - Unisolable HPCI Steam Supply valves fail to isolate (automatic & manual) 4 (cont)
KEY 4 mfHP_09 50% over 900 sec M-ALL Post Scram - HPCI Steam Leak in Reactor Building - large
Page 2 of 18 mfRP_08A mfRP_08B Preinsert C-ALL PCIS Group 3 failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Page 3 of 18 Scenario Summary The crew assumes the watch with the unit at 80% power. Reactor power was reduced to allow Maintenance to evaluate A Main Feedwater Pump seal leakage. House Heating Boilers are in service. The SRO will direct the BOP to place Torus Cooling in service in accordance with OPOP-RHR-2124 Residual Heat Removal System. Section 7.3 Torus Cooling during normal operations to reduce torus temperature.
After tours cooling has been established, C APRM will fail downscale. The RO will respond to APRM Downscale and Rod Withdrawal Block alarms and diagnose the failure of C APRM. The SRO will direct the RO to remove A APRM from bypass and place C APRM in bypass. The SRO will determine the impact with 2 APRMs inoperable in the same channel (TS Table 3.1.1 Action 1). Once C APRM is bypassed the SRO will exit the APRM TS LCO.
After the Technical Specifications for C ARPM have been addressed, A Service Water Pump will trip and the standby Service Water Pump will fail to auto start. The BOP will diagnose the failures. The SRO will direct the BOP to start the standby Service Water Pump, address actions in ON 3148 Loss of Service Water, declare the A Service water Pump inoperable and enter TS LCO 3.5.D.2.
A small steam leak will develop from the HPCI steam supply line in the reactor building. The fire detection Zone 11 Reactor Building Panel will alarm. The SRO will initially enter OP 3020 Control Room Response to a Fire and exit the procedure when the report of a steam leak is received. The SRO will enter ON-3158 Reactor Building High Area Temperature / Water Level and direct the BOP to isolate HPCI. The HPCI steam supply valves will fail to isolate automatically and will not close manually from the control room.
As area temperatures rise, the SRO will enter EOP-4 due to area temperature and will direct a reactor scram prior to any area in the reactor building exceeding the maximum safe operating level (Critical Task) and enter EOP-1.
The HPCI steam leak will increase after the reactor scram. PCIS Group 3 will fail to actuate requiring the crew to align and start standby gas (Critical Task). Additional attempts to isolate the HPCI steam leak will be unsuccessful requiring the crew to enter EOP-5 and perform an emergency depressurization of the reactor pressure vessel when two reactor building area temperatures exceed the maximum safe operating limits (Critical Tack).
The scenario will be terminated when Reactor Vessel Emergency Depressurization has been achieved and vessel level is being controlled between 127 to 177 inches.
Page 4 of 18 SIMULATOR EVALUATION GUIDE 2014 NRC Examination, Scenario #2 NRC Evaluators:
ILO Candidates CRS OATC BOP Critical Task Performance:
SAT UNSAT (Circle One)
Date Administered:
Prepared by:
Date:
Lead Exam Developer Reviewed by:
Date:
Operations Representative Approved by:
Date:
Operations Training Superintendent
Page 5 of 18 CREW BRIEF:
-Power level: 80%
-Rod Sequence:
Rapid Shutdown Sequence
-Rod Group: 20
-Equipment out of service and/or tagged or abnormalities:
- 1.
- 2.
Booster pumps
- 3.
-Reason For Equipment out of Service or tagged:
- 1.
Cooling Towers; Booster Pumps - Winter operations
- 2.
SBO EDG is out of service (tagged out) for Electrical Maintenance trouble shooting of the voltage regulator
-Applicable Tech Spec LCOs:
- 1.
NONE EOOS Color: Green
-Plant evolutions in progress/Scheduled Shift Evolutions:
- 1. Place Torus Cooling in service in accordance with OPOP-RHR-2124 Residual Heat Removal System. Section 7.3 Torus Cooling during normal operations, using the A RHR Pump and the A RHRSW Pump. RHR fill and vent has been completed; RP has been informed to survey; Chemistry reports chemical treatment is not required.
Torus cooling required to lower torus temperature to low in band to support RCIC testing next shift.
SCENARIO
SUMMARY
See ES-D-1 for summary TERMINATING CONDITION(S):
- 1. Reactor Vessel Emergency Depressurization achieved.
- 2. RPV level restored and being controlled between 127 to 177 inches
Page 6 of 18
REFERENCES:
- 1.
OPOP-RHR-2124, Residual Heat Removal System
- 2.
OP 2132, Average Power Range Monitor Channels
- 3.
6-A-1, SERV WTR PUMP A TRIP
- 4.
ON 3148, Loss of Service Water
- 5.
- 6.
EOP-4, Secondary Containment Control
- 7.
EOP-5, RPV-ED
- 8.
ON 3158 Reactor Building High Area Temperature / Water level
Page 7 of 18 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up:
- 1. IC# 831, 80% Power, 3 FW Pumps In-service; SBO EDG Trouble alarm lit with Red Tag on touch screen; winter lineup Discretionary Distracter Malfunctions/RFs/IOs:
No.
MF/RF/IO #
Severity Ramp REM #
Act. Time Description
- 1.
mfSW_18C preinsert N/A N/A Standby Service Water Pump(C) auto start failure
- 2.
mfPC_1HP15 mfPC_1HP16 preinsert N/A N/A HPCI Steam Supply valves fail to isolate (automatic & manual)
- 3.
mfRP_08A mfRP_08B preinsert N/A N/A PCIS Group 3 failure
- 4.
mfNM_05C 0%
N/A KEY 1 After torus cooling established C APRM Fails downscale
- 5.
mfSW_07A N/A N/A KEY 2 After C APRM TS evaluated A Service Water Pump trips
- 6.
mfHP_09 5%
300 sec KEY 3 After restoration of alarms and Aux Oil Pp in PTL HPCI Steam Leak in Reactor Building
- 7.
mfHP_09 50%
900 sec KEY 4 Post SCRAM HPCI Steam Leak in Reactor Building increases
Page 8 of 18 SIMULATOR OPERATOR INSTRUCTIONS (Continued)
Additional Instructions:
- 1.
A call to the Work Week Manager (WWM) will initiate all expected activities (including Duty Officer, Ops Manager, Maintenance, and AOs) outside the Control Room for a particular malfunction.
- 2.
Time compression may be directed by the lead evaluator. If time compression is used, this will be reported to the crew.
- 3.
The Lead Evaluator will determine when the event objectives have been met and the next event may be initiated. Event actuation times will be referenced and scenario flow will be considered during this determination.
- 4.
When asked as the outside AO, provide a time compressed report that SW pump A is very warm to the touch.
- 5.
When asked to investigate the A Service Water Pump trip, provide a time compressed report that an instantaneous over current flag on the A and B phases.
- 6.
After HCPI steam leak is initiated and the zone 11 fire alarm annunciates, RP calls the control room to report steam in the HPCI corner room
- 7.
If requested as Maintenance to attempt local closure of the HPCI-15 and 16 valves, report: Reactor building entry cannot be made at this time due to temperatures and the steam environment. The valves will remain open for the duration of the scenario.
Page 9 of 18 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task
Description:
Place Torus Cooling in service POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
SRO Direct Torus Cooling During Normal Operation FILL and VENT the system per OPST-RHR-4124-01A, Maintenance of 'A' RHR Loop Filled Discharge Pipe.
Completed - part of initial conditions During power operation whenever any RHR loop is placed in the Torus Cooling Mode, ENTER the applicable TS LCO for LPCI:
- With one RHR loop in Torus Cooling Mode enter 7 day LCO of TS 3.5.A.4 BOP NOTIFY RP to survey the appropriate RHR corner room and Torus area during Torus cooling operations.
IF condensate transfer is being used to provide keep fill pressure, THEN SECURE the condensate transfer keep fill per the Condensate Transfer Keep Fill Operation section of this procedure.
BOP IF RHRSW pump A/C will be operated, VERIFY RHRSW DISCHARGE, RHR-89A, closed with the RHR-89A TEST switch in AUTO.
Page 10 of 18 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS ENSURE adequate SW pumps are operating to handle RHRSW pump demand.
- VERIFY no more than one SW pump is in Standby mode.
START A RHRSW pump from CRP 9-3.
- Request Chemistry to determine whether RHRSW chemical treatment is necessary.
VERIFY RHRSW cooling water flow is between 5 to 7.5 gpm.
- 2.
On CRP 9-3, OPEN:
TORUS SPRAY/CLG, RHR-39A TORUS COOLING, RHR-34A IF desired, operate Torus Spray by opening TORUS SPRAY RHR-38A. (Not performed)
ADJUST RHRSW DISCHARGE, RHR-89A on CRP 9-3 to maintain RHRSW pressure in the heat exchanger greater than 20 psid above RHR pressure and limit RHRSW flow to 2300 to 3140 gpm.
BOP IF desired, on CRP 9-3, TORUS COOLING RHR-34A may be throttled to produce desired Torus cooling flow rate, provided RHR flow is maintained greater than or equal to 4100 gpm for each pump in service.
Page 11 of 18 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS MONITOR Drywell/Torus P.
IF only one RHR pump in the loop is running, THEN if desired, on CRP 9-3, CLOSE HX BYPASS, RHR-65A.
MONITOR flow on CRP 9-3:
FI-10-139A RHR PUMP A FLOW FI-10-136A CTMT SPRAY A/C FLOW FI-10-132A RHRSW A/C FLOW Once torus cooling is established continue with EVENT 2 OR at lead evaluators discretion.
Page 12 of 18 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task
Description:
Respond to C APRM Downscale Failure POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
CREW Responds to APRM downscale alarm, 5-M-4, Rod Withdraw Block, 5-D-3 and diagnosis failure of C APRM KEY 1 :________
- 2.
SRO SRO directs bypassing of APRMs IAW OP 2132
- 3.
RO On CRP 9-5:
Place 'A APRM in service Place 'F' APRM in service
- 4.
RO On CRP 9-5:
Place 'C' APRM in bypass Place 'D' APRM in bypass
- 5.
SRO Enter TS Table 3.1.1 Action 1; Exit TS Table 3.1.1 Action 1 after C APRM is bypassed.
Once TS have been evaluated continue with EVENT 3 OR at lead evaluators discretion.
Page 13 of 18 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task
Description:
Respond to A SW Pump Trip and Failure of standby SW Pump to Auto Start POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
CREW Respond to 6-4-1 SERV WTR PMP 4 TRIP KEY 2 :________
- 2.
SRO Refer to ON 3148, Loss of Service Water.
- 3.
BOP Check all SW Pump indications.
Verify auto startup of the standby pump.
Start standby SW Pump
- 4.
BOP Verify adequate SW pressure.
- 5.
RO Dispatch AO to visually inspect pump and motor.
- 6.
RO Do not restart pump until cleared by Maintenance Dept.
- 7.
SRO Refer to Tech. Specs. 3.5 for operability requirements. Enter TS LCO 3.5.D.2
- 8.
RO/BOP Monitor plant components.
- 9.
SRO Notify the Duty on Call Officer, and the Operations Manager.
Once TS have been evaluated continue with EVENT 4 OR at lead evaluators discretion.
Page 14 of 18 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task
Description:
Respond to HPCI Steam Leak POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 1.
CREW Respond to/report zone 11 fire alarm KEY 3 :________
- 2.
SRO Enter and direct actions of OP 3020
- 3.
CREW Dispatch Fire Brigade Leader to investigate fire alarm
- 4.
Make plant announcement for fire alarm IAW OP 3020
- 5.
Respond to/report Steam Leak Temp HI alarm, 4-H-1
- 6.
SRO Enter ON 3158, RB Area Hi Temp/Water Level.
RP contacts the control room to report steam in the HPCI corner room
- 7.
Direct crew member to monitor steam leak detection panel and radiation indications
- 8.
BOP Inform CRS of increasing reactor building temps in the HPCI-14 area.
- 9.
CREW Evacuate the Rx Bldg
- 10.
SRO Direct BOP to shut HPCI-15 and
- 16.
- 11.
BOP Attempt to shut HPCI-15 and 16, recognize and inform CRS of failure of HPCI valves to shut.
- 12.
SRO Direct BOP to close HPCI-15 and 16 using the HPCI Auto ISOL Manual Initiate switch
Page 15 of 18 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 13.
BOP Attempt to shut HPCI-15 and 16 using the HPCI Auto ISOL Manual Initiate switch and inform CRS of failure of HPCI valves to shut.
- 14.
SRO Direct maintenance to attempt local valve closure or repair of HPCI-15 and 16.
- 15.
BOP Inform CRS of increasing temperature levels in the secondary containment.
- 16.
CREW Enter EOP-4 Secondary Containment Control
- 17.
CT-1 With the reactor at power, and a primary system discharging into the Secondary Containment, manually scram the reactor BEFORE any area exceeds the maximum safe operating levels Standard:
Manually scram the reactor before any area temperature exceeding max safe or ARM 1, 2, 3, 4, 6, 7, 8, 10 or 11 exceeding 1,000 mR/hr
- 18.
SRO Direct RO to insert manual Rx SCRAM
- 19.
RO When directed, insert manual Rx SCRAM KEY 4: _____
- 20.
SRO Enter and direct actions of OT 3100 and EOP-1
- 21.
Direct STA to verify Table A initiations and isolations
- 22.
STA When directed, verify Table A initiations and isolations
Page 16 of 18 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 23.
CREW Recognize failure of Group Ill valves to close
- 24.
CT-2 When PCIS Group 1, 2, 3, 5, or 6 fails to isolate with a leak present, initiate PCIS Group manually Standard:
Leak or release terminated within 10 minutes of receipt of the auto isolation signal.
(Time from GP Ill Isolation signal to Group Ill IOPL Logic satisfied)
- 25.
SRO Direct BOP to manually initiate a Group Ill isolation/initiation.
- 26.
BOP Manually initiate Group Ill isolation and start both Standby Gas trains
- 27.
SRO Direct RO to maintain reactor level between 127" and 177",
using condensate and feed water per EOP-1.
- 28.
RO Maintain reactor level between 127" and 177".
- 29.
SRO Direct BOP to maintain reactor pressure between 800 and 1000 psig using BPV's.
- 30.
BOP Maintain reactor pressure as directed.
- 31.
SRO Direct Anticipate RPV-ED
- 32.
BOP Rapidly depressurize the RPV using BPVs irrespective of the cooldown rate
Page 17 of 18 POS CANDIDATE ACTIONS/BEHAVIOR S
U N/O COMMENTS
- 33.
CT-3 With a primary system discharging into the Secondary Containment and area radiation/temperature/water levels exceed maximum safe operating levels in more than one area, initiate RPV-ED Standard:
Initiate RPV-ED within 5 minutes of area radiation/temperature/water level exceeding maximum safe operating levels in more than one area.
- 34.
CREW Report area temperatures have exceeded their maximum safe operating levels in two areas
- 35.
SRO Enter and direct actions in EOP-5, RPVED
- 36.
Verify Torus water level above 5.5 feet
- 37.
Direct all SRVs opened
- 38.
- 39.
BOP/RO Restore and Maintain RPV Level between 127 and 177 Terminate scenario when RPV-ED is achieved and RPV water level is restored OR at lead evaluators discretion.
Evaluator Follow-up question (at examiners discretion): Classify event. Site Area Emergency IAW AP 3125 Appendix A (FS1.1)
Page 18 of 18 SCENARIO 2 EVALUATOR NOTES