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{{#Wiki_filter: | {{#Wiki_filter:CLASSROOM LESSON TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MIN TITLE NUMBER AND NRC 2016-A1a-RO TITLE: Calculate QPTR with Inoperable Power Range (PR) REVISION: 0 Instrument Examinees Name: :_________________________________________________________ | ||
:_________________________________________________________ | Evaluators Name: :_________________________________________________________ | ||
Date Performed: : _________________________________________________________ | |||
:_________________________________________________________ | Result (Circle One): SAT / UNSAT Number of Attempts: :________________________________________________________ | ||
Date Performed: | Time to Complete: :_________________________________________________________ | ||
: | |||
Result (Circle One): | |||
SAT | |||
:________________________________________________________ | |||
Time to Complete: | |||
Comments:__________________________________________________________________ | Comments:__________________________________________________________________ | ||
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REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-032 Quadrant Power Tilt Calculation K/A Number: 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation SYS 015 A1.04 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: Quadrant Power Tilt Ratio K/A Imp.: RO: 4.4 SRO: 4.7 3.5 3.7 Task Number: 0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT | |||
2-OHP-4030-214-032 Quadrant Power Tilt Calculation K/A Number: | * Calculator | ||
* Ruler HANDOUTS Task Briefing Completed 2-OHP-4030-214-032 and Data Sheet 3 ATTACHMENTS NI Calibration Data Card N41, N42, N43, and N44 Pictures EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE: | |||
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to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation SYS 015 A1.04 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: Quadrant Power Tilt Ratio K/A Imp.: RO: 4.4 | |||
0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT Calculator | |||
-OHP-4030-214-032 and Data Sheet 3 ATTACHMENTS | |||
NI Calibration Data Card | |||
N41, N42, N43, and N44 Pictures EVALUATION SETTINGS | |||
Classroom | |||
PERFORM: | |||
OPERATIONS JPM SIMULATOR/LAB SETUP None EVALUATOR INSTRUCTIONS | |||
: 1. Ensure simulator setup is complete | |||
: 2. Brief the operator (May be performed by giving out Task Briefing Sheet) | |||
: 3. Announce start of the JPM | |||
: 4. Perform evolution | |||
: 5. At completion of evolution, announce the JPM is complete. | |||
: 6. Document evaluation performance. | |||
TASK BRIEFING You are an extra RO. | |||
The following conditions exist: | The following conditions exist: | ||
NI Channel N | * NI Channel N-42 has failed low | ||
-42 has failed low Unit 2 is currently at 72% power. | * Unit 2 is currently at 72% power. | ||
All actions of 2 | * All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed | ||
-OHP-4022-013-004, Power Range Malfunction have been completed The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 2 | * The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 2-OHP-4030-214-032, Quadrant Power Tilt Calculation. | ||
-OHP-4030-214-032, Quadrant Power Tilt Calculation. | |||
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | ||
NOTE Simulator Indications are NOT applicable to this JPM | NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS Correctly obtain values and calculates a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 2-OHP-4030-214-032. | ||
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GENERAL STANDARDS/PRECAUTIONS | |||
Correctly obtain values and calculates a Quadrant Power Tilt Ratio calculation with one power range channel out | |||
-of-service using 2 | |||
-OHP-4030-214-032. | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
Operator records Upper & Lower Detector blanks for N-41, 43 and 44 on Data Sheet 3. | |||
SAT: UNSAT: | |||
Note: See Page 6-7 For expected values Operator records NI detector readings (within +0.5) on a division mark and within the division marks for all others. | |||
SAT: UNSAT: | |||
CS: Operator enters data from cards provided. | |||
SAT: UNSAT: | |||
Operator divides respective NI channel with its 120% value (from cards on Channel 3 NI panel) | Operator divides respective NI channel with its 120% value (from cards on Channel 3 NI panel) | ||
SAT: | SAT: UNSAT: | ||
Operator totals 3 channels of normalized values SAT: | Operator totals 3 channels of normalized values SAT: UNSAT: | ||
Operator enters the highest calculated QPTR (CS: | Operator determines upper and lower QPTR using data sheet 3 SAT: UNSAT: | ||
N/A Operator enters the highest calculated QPTR (CS: Covered on Page 6) | |||
SAT: UNSAT: | |||
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OPERATIONS JPM NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
STANDARD: CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering SAT: UNSAT: | |||
CUE: SM Acknowledges that QPTR has Exceeded TS value and will address the required actions. | |||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
CS: Data entered on this page based on Simulator readings. | CS: Data entered on this page based on Simulator readings. | ||
See page 7 for acceptable range of readings | See page 7 for acceptable range of readings 41 99 135.4 .7312 43 98 134.4 .7292 44 98 136.7 .7169 2.1772 Upper Tilt Ratio 1.007 (range 1.001 to 1.022) 41 91.5 135.6 .6748 SAT: UNSAT: | ||
43 98.5 134.7 .7313 44 97.5 136.2 .7159 2.1219 Lower Tilt Ratio 1.034 (range 1.026 to 1.041) | |||
Upper Tilt Ratio 1.007 (range 1.001 to 1.022 | SAT: UNSAT: | ||
) SAT: | 1.007 1.034 CS: Operator enters the highest calculated QPTR of previous 2 1.034 values 1.034 (range 1.026 to 1.041) | ||
Lower Tilt Ratio 1. | N/A Candidate marks N/A CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering Candidate Signs, Dates, & enters Time and reports task completed. | ||
CUE: SM Acknowledges the report and will address the required actions. | |||
CS: | Evaluator: This JPM is complete. | ||
Candidate marks | NRC 2016-A1a-RO Revision: 0 Calculate QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-RO.doc Page 6 of 12 | ||
Candidate Signs, Dates, & enters Time and reports task completed. | |||
CUE: SM Acknowledges the report and will address the required actions. Evaluator: | |||
OPERATIONS JPM Acceptable Ranges Based on Scale used on Pictures Detector A (UPPER) | |||
SCALE 5 5 1 1 500 500 100 100 Low High Low High Low High Low High N41 4.9 5 0.985 0.995 490 500 98.5 99.5 N43 4.85 4.95 0.975 0.985 485 495 97.5 98.5 N44 4.85 4.95 0.975 0.985 485 495 97.5 98.5 Using the 500 Scale (UPPER QPTR ranges Calculated using combinations of High/Low values above) | |||
Lowest, Lowest, Highest ---- 1.001 Highest, Lowest, Lowest ----- 1.022 Detector B (LOWER) | |||
SCALE 5 5 1 1 500 500 100 100 Low High Low High Low High Low High 4.55 4.6 0.91 0.92 455 460 91 92 4.9 4.95 0.98 0.99 490 495 98 99 4.85 4.9 0.97 0.98 485 490 97 98 (LOWER QPTR Ranges Calculated using combinations of High/Low values above) | |||
Highest, Lowest, Highest ---- 1.026 Lowest, Highest, Lowest ----- 1.041 NRC 2016-A1a-RO Revision: 0 Calculate QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-RO.doc Page 7 of 12 | |||
Task Briefing You are an extra RO. | |||
The following conditions exist: | The following conditions exist: | ||
NI Channel N | * NI Channel N-42 has failed low | ||
-42 has failed low Unit 2 is currently at 72% power. | * Unit 2 is currently at 72% power. | ||
All actions of 2 | * All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed | ||
-OHP-4022-013-004, Power Range Malfunction have been completed The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 2 | * The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 2-OHP-4030-214-032, Quadrant Power Tilt Calculation. | ||
-OHP-4030-214-032, Quadrant Power Tilt Calculation. | |||
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | ||
NOTE Simulator Indications are NOT applicable to this JPM - Use Supplied Pictures for readings. | |||
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NRC 2016-A1a- | NRC 2016-A1a-RO Revision: 0 Calculate QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-RO.doc Page 12 of 12 | ||
TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MIN TITLE NUMBER AND NRC 2016-A1a-SRO TITLE: Review QPTR with Inoperable Power Range (PR) REVISION: 0 Instrument Examinees Name: :_________________________________________________________ | |||
Evaluators Name: :_________________________________________________________ | |||
Date Performed: : _________________________________________________________ | |||
- | Result (Circle One): SAT / UNSAT Number of Attempts: :________________________________________________________ | ||
Time to Complete: :_________________________________________________________ | |||
Comments:__________________________________________________________________ | |||
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Classroom | REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-032 Quadrant Power Tilt Calculation K/A Number: 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation SYS 015 A1.04 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: Quadrant Power Tilt Ratio K/A Imp.: RO: 4.4 SRO: 4.7 3.5 3.7 Task Number: 0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT | ||
PERFORM: | * Calculator | ||
* Ruler HANDOUTS Task Briefing Completed 2-OHP-4030-214-032 and Data Sheet 3 ATTACHMENTS NI Calibration Data Card N41, N42, N43, and N44 Pictures EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE: | |||
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SIMULATOR/LAB SETUP None EVALUATOR INSTRUCTIONS | |||
: 1. Ensure simulator setup is complete | : 1. Ensure simulator setup is complete | ||
: 2. Brief the operator (May be performed by giving out Task Briefing Sheet) | : 2. Brief the operator (May be performed by giving out Task Briefing Sheet) | ||
: 3. Announce start of the JPM | : 3. Announce start of the JPM | ||
: 4. Perform evolution | : 4. Perform evolution | ||
: 5. At completion of evolution, announce the JPM is complete. | : 5. At completion of evolution, announce the JPM is complete. | ||
: 6. Document evaluation performance. | : 6. Document evaluation performance. | ||
TASK BRIEFING You are the Unit SRO. | TASK BRIEFING You are the Unit SRO. | ||
The following conditions exist: | The following conditions exist: | ||
NI Channel N | * NI Channel N-42 has failed low | ||
-42 has failed low Unit 2 is currently at 72% power. | * Unit 2 is currently at 72% power. | ||
All actions of 2 | * All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed | ||
-OHP-4022-013-004, Power Range Malfunction have been completed The Plant Process Computer (PPC) is INOPERABLE | * The Plant Process Computer (PPC) is INOPERABLE The SM directs you to Review the manual 2-OHP-4030-214-032, Quadrant Power Tilt Calculation. | ||
-OHP-4030-214-032, Quadrant Power Tilt Calculation. | |||
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | ||
NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS Review a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 2-OHP-4030-214-032 and identify error and required TS Actions NRC 2016-A1a-SRO Revision: 0 Review QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-SRO.doc Page 3 of 12 | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) 41 99 135.4 .7312 43 98 134.4 .7292 44 98 136.7 .7169 2.1772 41 91.5 135.6 .6748 43 98.5 134.7 .7313 44 97.5 136.2 .7159 2.1219 1.0074 1.0034 CS: Operator identifies that value was incorrectly calculated. | |||
Should be 1.034 resulting in excessive QPTR. | |||
1.0074 1.034 (range 1.026 to 1.041) | |||
SAT: UNSAT: | |||
N/A CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM SAT: UNSAT: | |||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering SAT: UNSAT: | |||
CS: | |||
CUE: SM Acknowledges that QPTR has Exceeded TS value requests that you review the Required Technical Specification and determine the required Actions. | CUE: SM Acknowledges that QPTR has Exceeded TS value requests that you review the Required Technical Specification and determine the required Actions. | ||
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OPERATIONS JPM | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
CUE: (If Required) Ask Operator to determine the Technical Specification LCO that applies. | CUE: (If Required) Ask Operator to determine the Technical Specification LCO that applies. | ||
CS: Determines that Power is limited to 3% for each 1% over 1.00 (3.4 x 3% = 10.2%) per LCO 3.2.4 Action A.1 - (note power limit is from RTP - 89.9% is limit) | |||
(Range of 7.8% to 12.3% reduction with a 92.2% to 87.7% power limit) | |||
SAT: UNSAT: | |||
Also Determines that QPTR must be calculated every 12 hours, Verify F Q (Z ) is within limit., Verify F Q (Z ) is within limit, & Verify C W F | |||
N h | |||
is within limits specified in the COLR. | |||
SAT: UNSAT: | |||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
OPERATIONS JPM | |||
Identify that safety analyses must be evaluated before raising power above the limit.(92.2% to 87.7% power limit) | Identify that safety analyses must be evaluated before raising power above the limit.(92.2% to 87.7% power limit) | ||
SAT: | SAT: UNSAT: | ||
A.5 & A.6 required if power is raised above above the limit.(92.2% | A.5 & A.6 required if power is raised above above the limit.(92.2% | ||
to 87.7% power limit) | to 87.7% power limit) | ||
SAT: | SAT: UNSAT: | ||
Evaluator: This JPM is complete. | |||
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Task Briefing You are the Unit SRO. | |||
The following conditions exist: | |||
* NI Channel N-42 has failed low | |||
* Unit 2 is currently at 72% power. | |||
* All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed | |||
* The Plant Process Computer (PPC) is INOPERABLE The SM directs you to Review the manual 2-OHP-4030-214-032, Quadrant Power Tilt Calculation. | |||
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly. | |||
NOTE Simulator Indications are NOT applicable to this JPM - Use Supplied Pictures for readings. | |||
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NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument | NRC 2016-A1a-SRO Revision: 0 Review QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-SRO.doc Page 9 of 12 | ||
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NI CALIBRATION DATA DET A 120% I in µAmps N41 = 135.4 N42 = 136.6 N43 = 134.4 N44 = 136.7 DET B 120% I in µAmps N41 = 135.6 N42 = 133.6 N43 = 134.7 N44 = 136.2 Verified: Print ____John Smithe__ | |||
Sign ___ John Smithe _____ | |||
Date 5/11/2016____ | |||
DATAforA1a.doc | |||
OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-A1b-SRO TITLE: Verify Appropriate LCO Action for Inoperable REVISION: 0 Radiation Monitors Examinees Name: _________________________________________ __________ | |||
Evaluators Name: : ___________________________________________________ | |||
Date Performed: : ____________________________________________________ | |||
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________ | |||
Date Performed: : | |||
Result (Circle One): | |||
SAT | |||
Time to Complete: : ____________________________________________________ | Time to Complete: : ____________________________________________________ | ||
Comments:___________________________________________________________ | Comments:___________________________________________________________ | ||
NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 1 of 13 | |||
OPERATIONS JPM | OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedures: 12-OHP-4024-139 Annunciator #139 Response: Radiation TRM 8.3.8 Radiation Monitoring Instrumentation PMP-4030-EIS-001 Event-Initiated Surveillance Testing PMP-6010-OSD-001 Off-Site Dose Calculation Manual K/A Number: 2.1.12 Ability to apply Technical Specifications for a system. | ||
: 12-OHP-4024-139 TRM 8.3.8 PMP-4030-EIS-001 PMP-6010-OSD-001 Annunciator #139 Response: Radiation Radiation Monitoring Instrumentation | K/A Imp.: RO: 2.9 SRO: 4.0 Task Number: ADM0370302 Verify Limiting Conditions for Operation are met in accordance with Technical Specifications. | ||
Verify Limiting Conditions for Operation are met in ADM0420302 accordance with the Offsite Dose Calculation Manual. | |||
TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 12-OHP-4024-139, Annunciator #139 Response: Radiation Drop 24 Unit 2 - TRM 8.3.8., Radiation Monitoring Instrumentation PMP-4030-EIS-001, Event-Initiated Surveillance Testing PMP-6010-OSD-001, Off-Site Dose Calculation Manual ATTACHMENTS None EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE: | |||
NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 2 of 13 | |||
OPERATIONS JPM SIMULATOR/LAB SETUP | |||
OPERATIONS JPM | |||
: 1. None EVALUATOR INSTRUCTIONS | : 1. None EVALUATOR INSTRUCTIONS | ||
: 1. Brief the operator (May be performed by giving out Task Briefing Sheet) | : 1. Brief the operator (May be performed by giving out Task Briefing Sheet) | ||
: 3. Announce start of the JPM | : 3. Announce start of the JPM | ||
: 4. Perform evolution | : 4. Perform evolution | ||
: 5. At completion of evolution, announce the JPM is complete. | : 5. At completion of evolution, announce the JPM is complete. | ||
: 6. Document evaluation performance. | : 6. Document evaluation performance. | ||
TASK BRIEFING | TASK BRIEFING You are an extra SRO. | ||
Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS-2505, Low Range Noble Gas went into External Failure (WHITE) 5 minutes ago. | |||
You are an extra SRO. | |||
Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS | |||
-2505, Low Range Noble Gas went into External Failure (WHITE) 5 minutes ago. | |||
The Channel did NOT fail Low. | The Channel did NOT fail Low. | ||
There is NO Waste Gas release in progress. | There is NO Waste Gas release in progress. | ||
The Unit Supervisor directs you to investigate, perform any required actions, and complete required documentation. | The Unit Supervisor directs you to investigate, perform any required actions, and complete required documentation. | ||
NOTE Simulator Indications are NOT applicable to this JPM | NOTE Simulator Indications are NOT applicable to this JPM. | ||
Provide ONLY 12-OHP-4024-139 Drop 24 Unit Vent Effluent Monitor at this time GENERAL STANDARDS/PRECAUTIONS Respond to a failed RMS channel and determine the appropriate LCO actions in accordance with applicable procedures. | |||
-OHP-4024-139 Drop 24 Unit Vent Effluent Monitor at this time GENERAL STANDARDS/PRECAUTIONS | NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 3 of 13 | ||
Respond to a failed RMS channel and determine the appropriate LCO actions in accordance with applicable procedures. | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
General CUES: | General CUES: | ||
If contacted as Rad Protection, report Channel 2505 is in EXTERNAL FAIL | If contacted as Rad Protection, report Channel 2505 is in EXTERNAL FAIL. | ||
. | Provide 12-OHP-4024-139 Drop 24 Unit Vent Effluent Monitor STANDARD: Operator reviews conditions for WHITE light. | ||
SAT: UNSAT: | |||
Provide 12 | NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 4 of 13 | ||
-OHP-4024-139 Drop 24 Unit Vent Effluent Monitor | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
CUE: Provide TRM 8.3.8 when recognizes need to reference STANDARD: Operator references TRM 8.3.8 actions (None Required for VRS-2505) | |||
OPERATIONS JPM | SAT: UNSAT: | ||
CUE: If asked, Channel VRS-2505 is NOT due to a low failure and will be out-of-service for at least 5 days. | |||
CUE: Provide TRM 8.3.8 when recognizes need to reference | |||
STANDARD: Operator references TRM 8.3.8 actions (None Required for VRS | |||
-2505) SAT: | |||
-2505 is NOT due to a low failure and will be out | |||
-of-service for at least 5 days. | |||
CUE: If required, acknowledge report to RP of Channel Failure CUE: US will initiate AR processing. | CUE: If required, acknowledge report to RP of Channel Failure CUE: US will initiate AR processing. | ||
CUE: Provide PMP | CUE: Provide PMP-4030-EIS-001, Event-Initiated Surveillance Testing when recognizes need to reference STANDARD (CS): Operator reports VRS-2505 as Inoperable and references PMP-4030-EIS-001, Attachment 1. | ||
-4030-EIS-001, | SAT: UNSAT: | ||
-2505 as Inoperable and references PMP | NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 5 of 13 | ||
-4030-EIS-001, Attachment 1. | |||
SAT: | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
CUE: US will coordinate with RP to determine if channel should be removed from service. | CUE: US will coordinate with RP to determine if channel should be removed from service. | ||
CUE: Provide PMP | CUE: Provide PMP-4030-EIS-001, Event-Initiated Surveillance Testing when recognizes need to reference NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 6 of 13 | ||
-4030-EIS-001, | |||
STANDARD: Operator identifies applicability of Item 17, which references ODCM Attachment 3.4, Items 2.a and 4.a SAT: | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
STANDARD: Operator identifies applicability of Item 17, which references ODCM Attachment 3.4, Items 2.a and 4.a SAT: UNSAT: | |||
NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 7 of 13 | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
STANDARD: Operator identifies applicability of Item 17. | STANDARD: Operator identifies applicability of Item 17. | ||
SAT: | SAT: UNSAT: | ||
STANDARD: Notifies Chemistry of Required Surveillance requirements. | STANDARD: Notifies Chemistry of Required Surveillance requirements. | ||
SAT: | SAT: UNSAT: | ||
CUE: Chemistry acknowledges requirements CUE: US has logged the event in the Control Room Log. | |||
STANDARD: Completes DATA Sheet 1 Steps 1.1 through 1.7 SAT: | STANDARD: Completes DATA Sheet 1 Steps 1.1 through 1.7 SAT: UNSAT: | ||
N/A | N/A NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 8 of 13 | ||
Note: Operator may reference action item 9 for VRS | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
-2505 being inoperable. | STANDARD: Operator references action item 6 for VRS-2505 being inoperable. | ||
(ONLY required if release is in progress which briefing stated was NOT) | SAT: UNSAT: | ||
Note: Operator may reference action item 9 for VRS-2505 being inoperable. (ONLY required if release is in progress which briefing stated was NOT) | |||
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OPERATIONS JPM | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
STANDARD: Operator reports requirement that release may continue for up to 30 days provided grab samples are taken shiftly and analyzed within 24 hours. (If Not returned in 30 days provide a description in Annual Report) (may be entered on PMP-4030-EIS-001, Data Sheet 1) | |||
STANDARD: Operator reports requirement that release may continue for up to 30 days provided grab samples are taken shiftly and analyzed within 24 hours. (If Not returned in 30 days provide a description in Annual Report) (may be entered on PMP | SAT: UNSAT: | ||
-4030-EIS-001, Data Sheet 1) | NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 10 of 13 | ||
SAT: | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
Note: Operator may report requirement that release may continue for up to 14 days provided contingency actions are taken. (ONLY required if release is in progress which briefing stated was NOT) | |||
CUE: If Required, Unit Supervisor acknowledges ability to continue release up to 14 days provide contingencies are met. | CUE: If Required, Unit Supervisor acknowledges ability to continue release up to 14 days provide contingencies are met. | ||
CUE: If required, ask What Documentation is required? (to ensure PMP-4030-EIS-001, Data Sheet 1 is initiated). | |||
(to ensure PMP | NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 11 of 13 | ||
-4030-EIS-001, Data Sheet 1 is initiated | |||
). | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
-2505, | STANDARD (CS): Enters Data as required in steps 1.1 and 1.2. (Date and Time are NOT Critical Standards) | ||
SAT: UNSAT: | |||
STANDARD: Enters 30 days / (14 days for releases - NA) | |||
SAT: UNSAT: | |||
17 Vent Stack Noble Gas Monitor VRS-2505 Inoperable 2 Current Date Current Time STANDARD (CS): Enters 12-THP-6020-CHM-322 OR "Requirement that release may continue for up to 30 days provided grab samples are taken shiftly and analyzed within 24 hours." (Procedure or Action Required) | |||
SAT: UNSAT: | |||
Instructor Note: If Gaseous Waste release will be performed then may determine ODCM, Attachment 3.4, Action 9, is applicable. | |||
STANDARD (CS):Indicates that Samples are required once per 12 hours and analyzed within 24 hours per ODCM Attachment 3.4 action 6 (and 12-THI-2291-ADM-012) | |||
SAT: UNSAT: | |||
CUE: Provide AR# from Unit Supervisor as 2016-9999 CUE: Step 1.7 is completed and signed off. | |||
CUE: Acknowledge Unit 1 has been notified TERMINATION CUE: This JPM is complete. | |||
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Task Briefing You are an extra SRO. | |||
Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS-2505, Low Range Noble Gas went into External Failure (WHITE) 5 minutes ago. | |||
The Channel did NOT fail Low. | The Channel did NOT fail Low. | ||
There is NO Waste Gas release in progress. | There is NO Waste Gas release in progress. | ||
The Unit Supervisor directs you to investigate, perform any required actions, and complete required documentation. | The Unit Supervisor directs you to investigate, perform any required actions, and complete required documentation. | ||
NOTE Simulator Indications are NOT applicable to this JPM. | NOTE Simulator Indications are NOT applicable to this JPM. | ||
Revision: 0 NRC 2016-A1b-SRO.doc Page 13 of 13 | |||
OPERATIONS JPM NUMBER: NRC 2016-A2-RO TIME: 15 MINUTES TITLE: Perform Unit 2 LTOP Verification REVISION: 0 Examinees Name: _________________________________________ __________ | |||
Evaluators Name: : ___________________________________________________ | |||
Date Performed: : | Date Performed: : ____________________________________________________ | ||
Result (Circle One): | Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________ | ||
SAT | |||
Time to Complete: : ____________________________________________________ | Time to Complete: : ____________________________________________________ | ||
Comments:___________________________________________________________ | Comments:___________________________________________________________ | ||
NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 1 of 9 | |||
OPERATIONS JPM | OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: 2.2.37 K/A Imp.: RO: 3.6 SRO: 4.6 Task Number: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS | ||
: 1. Task Briefing sheet | |||
: 2. Work Management Listing (Open Items) - 2 pages | |||
: 3. Unit 2 Technical Specifications | |||
: 4. 2-OHP-4030-214-030, Daily And Shiftly Surveillance Checks: | |||
* Data Sheet 20,LTOP Verification | |||
* Data Sheet 20A, LTOP Verification LCO 3.4.12.A | |||
* Data Sheet 20B, LTOP Verification LCO 3.4.12.B ATTACHMENTS None EVALUATION SETTINGS Classroom. | |||
EVALUATION METHOD: PERFORM: SIMULATE: | |||
NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 2 of 9 | |||
OPERATIONS JPM SIMULATOR/LAB SETUP None. | |||
EVALUATOR INSTRUCTIONS | EVALUATOR INSTRUCTIONS | ||
: 1. Brief the operator (May be performed by giving out Task Briefing sheet). 2. Announce start of the JPM | : 1. Brief the operator (May be performed by giving out Task Briefing sheet). | ||
: 2. Announce start of the JPM. | |||
: 3. Perform evolution. | |||
: 4. At completion of evolution, announce the JPM is complete. | |||
: 5. Document evaluation performance. | : 5. Document evaluation performance. | ||
TASK BRIEFING The US directs you to determine whether the Unit 2 LTOP Requirements are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. | |||
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | |||
Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS: | |||
2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-152 2-NRV-153 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In) | |||
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 3 of 9 | |||
OPERATIONS JPM RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized GENERAL STANDARDS/PRECAUTIONS When directed by the Unit Supervisor, determine if LTOP Requirements for Unit 2 are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. | |||
NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 4 of 9 | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
General CUES: | |||
Provide a copy of the following handouts: | |||
: 1) Work Management Listing (Open Items) - 3 pages. | |||
: 2) 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks: | |||
* Data Sheet 20 | |||
* Data Sheet 20A | |||
* Data Sheet 20B CS: Determines based on Task Briefing information that Data Sheet 20A, LTOP Verification LCO 3.4.12.A is applicable. | |||
SAT: UNSAT: | |||
Note: Data Sheet 20B is for LCO 3.4.12.B when Both CCPs are available. | |||
General CUES | |||
: 1) | |||
- 3 pages. 2) | |||
SAT: | |||
Based on the given Conditions One CCP is Locked out, and so the relaxed requirements of 3.4.12.A are applicable. | Based on the given Conditions One CCP is Locked out, and so the relaxed requirements of 3.4.12.A are applicable. | ||
Note: Candidate should complete Data Sheet 20A, per following page prior to completing the remainder of Data Sheet 20. | |||
NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 5 of 9 | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
CS: Marks page as shown [at Xs] (only one PORV is operable and RHR Suction Relief Operable). | |||
OPERATIONS JPM | SAT: UNSAT: | ||
Note: PORV NRV-153 is Inoperable due to low Accumulator Tank Pressure ANN 208 Drop 28 is LIT CS: Determines that LTOP Requirements are Met. | |||
SAT: UNSAT: | |||
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Note: | |||
CS: | |||
SAT: | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
Completes Section 3 based on Task Brief information, Work Management Listing, and Data Sheet 20A: | Completes Section 3 based on Task Brief information, Work Management Listing, and Data Sheet 20A: | ||
SAT: | SAT: UNSAT: | ||
RHR Suctions Isolations Open (Yes) | * Accumulators Isolated (Yes) | ||
PORV Block Valves Open (Yes) | * RHR Suctions Isolations Open (Yes) | ||
Data Sheet 20A is Met (YES) | * PORV Block Valves Open (Yes) | ||
* Data Sheet 20A is Met (YES) | |||
* Data Sheet 20B is met (N/A) | |||
NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 7 of 9 | |||
OPERATIONS JPM | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
CS: Informs US/SM that LTOP Requirements are is Met. | |||
SAT: UNSAT: | |||
CUE: Acknowledge Test Results. When candidate documents FINAL CONDITIONS in step 4.1, then JPM is Complete. | |||
NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 8 of 9 | |||
Task Briefing The US directs you to determine whether the Unit 2 LTOP Requirements are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. | |||
-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. | |||
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | ||
Equipment Availability Table COMPONENT I.D.: DESCRIPTION: | Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS: | ||
STATUS: 2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for 2-NRV-152 | 2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-152 2-NRV-153 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In) | ||
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure | Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized Revision: 0 NRC 2016-A2-RO.doc Page 9 of 9 | ||
-Energized | |||
Open Item # | Unit 2 Open Items Summary Open Item # Component Noun System Open Item Entered 2-2016-0594 2-VTR-300 Control Room Air Temperature VCRAC Tuesday, May 22, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.7.11 2016-13357 Condition Description Notes 12-IHP-5021-IMP-001 (55384995-01) Temperature Instrument Calibration Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0600 2-NTR-12 CORE EXIT THERMOCOUPLE LOCATION F-15 NI Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.3.3 A Modes 1, 2, 3, and 4 Condition Description Notes Failed TC Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0601 2-NRV-153 PRESSURIZER PORV NRV-153 PZR Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 F N/A Modes 5 & 6 3.4.12 E N/A Mode 4 3.4.11 A N/A Modes 1, 2, and 3 Condition Description Notes Emergency Air Tank is depressurized and Isolated due to air leak at pressure connection Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0602 2-IMO-110 Safety Injection Accumulator Discharge Valve ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 1 of 3 | ||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Open Item # | Open Item # Component Noun System Open Item Entered 2-2016-0603 2-IMO-120 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0604 2-IMO-130 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0605 2-IMO-140 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0606 2-PP-26N NORTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 2 of 3 | ||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Open Item # Component Noun System Open Item Entered 2-2016-0607 2-PP-26S SOUTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A B Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0609 2-PP-50E East CCP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, 3 Condition Description Notes CCP Tagged Out to Prevent Injection Required for SR 3.4.12.2 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 23, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 8.3.8 C Condition Description Notes RP has not completed Operability recommendation checks following I & C board replacement under WOT 55403403 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 3 of 3 | |||
- | |||
OPERATIONS JPM NUMBER: NRC 2016-A2-SRO TIME: 15 MINUTES TITLE: Review Unit 2 LTOP Verification REVISION: 1 Changed Error from RHR to NRV-153 Examinees Name: _________________________________________ __________ | |||
Evaluators Name: : ___________________________________________________ | |||
___________________________________________________ | Date Performed: : ____________________________________________________ | ||
Date Performed: : | Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________ | ||
Result (Circle One): | |||
SAT | |||
Time to Complete: : ____________________________________________________ | Time to Complete: : ____________________________________________________ | ||
Comments:___________________________________________________________ | Comments:___________________________________________________________ | ||
NRC 2016-A2-SRO Revision: 0 Review Unit 2 LTOP Verification NRC 2016-A2-SRO.doc Page 1 of 6 | |||
OPERATIONS JPM | OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: 2.2.42 K/A Imp.: RO: 3.9 SRO: 4.6 Task Number: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS | ||
2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: | * Task Briefing sheet | ||
2.2.42 | * Work Management Listing (Open Items) - 2 pages | ||
STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None | * Copy of Completed 2-OHP-4030-214-030, Data Sheet 20 (fill in Sections 3 & 4) | ||
- 2 pages | * Copy of Completed 2-OHP-4030-214-030, Data Sheet 20A (attached) | ||
-OHP-4030-214-030, Data Sheet 20 (fill in Sections 3 & 4) | * TS 3.4.12 and Bases ATTACHMENTS None EVALUATION SETTINGS Classroom. | ||
Copy of Completed 2 | EVALUATION METHOD: PERFORM: SIMULATE: | ||
-OHP-4030-214-030, Data Sheet 20A (attached) | SIMULATOR/LAB SETUP None. | ||
TS 3.4.12 and Bases | EVALUATOR INSTRUCTIONS | ||
: 1. Brief the operator (May be performed by giving out Task Briefing sheet). | |||
None EVALUATION SETTINGS | : 2. Announce start of the JPM. | ||
: 3. Perform evolution. | |||
Classroom. | : 4. At completion of evolution, announce the JPM is complete. | ||
EVALUATION METHOD: | |||
PERFORM: | |||
SIMULATOR/LAB SETUP None. EVALUATOR INSTRUCTIONS | |||
: 1. Brief the operator (May be performed by giving out Task Briefing sheet). 2. Announce start of the JPM | |||
: 5. Document evaluation performance. | : 5. Document evaluation performance. | ||
NRC 2016-A2-SRO Revision: 0 Review Unit 2 LTOP Verification NRC 2016-A2-SRO.doc Page 2 of 6 | |||
OPERATIONS JPM | OPERATIONS JPM TASK BRIEFING The Shift Manager directs you to perform the SRO review of the completed LTOP Verification 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. Determine Tech Spec Action if required. | ||
-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. | |||
Determine Tech Spec Action if required. | |||
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | ||
Equipment Availability Table COMPONENT I.D.: | Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS: | ||
DESCRIPTION: | 2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-152 2-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In) | ||
STATUS: 2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control | Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized GENERAL STANDARDS/PRECAUTIONS Perform the SRO review of the completed LTOP Verification and determine if LTOP Requirements for Unit 2 are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. | ||
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature | NRC 2016-A2-SRO Revision: 0 Review Unit 2 LTOP Verification NRC 2016-A2-SRO.doc Page 3 of 6 | ||
-Energized | |||
-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. | |||
CS: | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
- pg 2). | General CUES: | ||
* Provide a Copy of 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. | |||
CS: | * If required prompt the candidate to identify Tech Spec and correct Data Sheet 20A after determining the error. | ||
CS: Reviews Data Sheet 20A and determines that PORV NRV-153 is In-Operable (Xs in Circles are wrong, Empty Circles Should Have Xs). | |||
SAT: UNSAT: | |||
Note: Annunciator Panel 208 Drop 28 is LIT (not Clear)(See Work Management Listing - pg 2). | |||
CS: Determines that LTOP Requirements are NOT Met. | |||
SAT: UNSAT: | |||
Informs Shift Manager that LTOP Requirements are NOT met. | |||
SAT: UNSAT: | |||
CS: Determines that Tech Spec LCO 3.4.12, Action F N/A applies (Mode 5 - One required relief is In-Operable). | |||
SAT: UNSAT: | |||
CUE: This JPM is complete. | |||
NRC 2016-A2-SRO Revision: 0 Review Unit 2 LTOP Verification NRC 2016-A2-SRO.doc Page 4 of 6 | |||
Task Briefing The Shift Manager directs you to perform the SRO review of the completed LTOP Verification 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. Determine Tech Spec Action if required. | |||
-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. | |||
Determine Tech Spec Action if required. | |||
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below: | ||
Equipment Availability Table COMPONENT I.D.: | Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS: | ||
DESCRIPTION: | 2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-152 2-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In) | ||
STATUS: 2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control | Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized Revision: 0 NRC 2016-A2-SRO.doc Page 5 of 6 | ||
-Energized | |||
Revision: | - FOR TRAINING USE ONLY - | ||
Revision: 0 NRC 2016-A2-SRO.doc Page 6 of 6 | |||
Open Item # | Unit 2 Open Items Summary Open Item # Component Noun System Open Item Entered 2-2016-0594 2-VTR-300 Control Room Air Temperature VCRAC Tuesday, May 22, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.7.11 2016-13357 Condition Description Notes 12-IHP-5021-IMP-001 (55384995-01) Temperature Instrument Calibration Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0600 2-NTR-12 CORE EXIT THERMOCOUPLE LOCATION F-15 NI Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.3.3 A Modes 1, 2, 3, and 4 Condition Description Notes Failed TC Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0601 2-NRV-153 PRESSURIZER PORV NRV-153 PZR Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 F N/A Modes 5 & 6 3.4.12 E N/A Mode 4 3.4.11 A N/A Modes 1, 2, and 3 Condition Description Notes Emergency Air Tank is depressurized and Isolated due to air leak at pressure connection Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0602 2-IMO-110 Safety Injection Accumulator Discharge Valve ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 1 of 3 | ||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Open Item # | Open Item # Component Noun System Open Item Entered 2-2016-0603 2-IMO-120 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0604 2-IMO-130 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0605 2-IMO-140 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0606 2-PP-26N NORTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 2 of 3 | ||
Component Noun System Open Item Entered 2-2016- | |||
Component Noun System Open Item Entered 2-2016- | |||
Open Item # Component Noun System Open Item Entered 2-2016-0607 2-PP-26S SOUTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A B Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0608 2-SV-103 RHR Suction Line Relief Valve RHR Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 E N/A MODE 4 when any RCS cold leg temperature is 299°F 3.4.12 F N/A Modes 5 and 6, when the vessel head is on 5.5.6 Condition Description Notes RHR Suction Line Relief Valve failed to lift at required setpoint Valve did not Open Until 460 psig. | |||
Description Notes RHR Suction Line Relief Valve failed to lift at required setpoint Valve did not Open Until 460 psig. | Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0609 2-PP-50E East CCP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, 3 Condition Description Notes CCP Tagged Out to Prevent Injection Required for SR 3.4.12.2 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 23, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 8.3.8 C Condition Description Notes RP has not completed Operability recommendation checks following I & C board replacement under WOT 55403403 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 3 of 3 | ||
Procedure Title Drop Dead Date Open Item # | |||
Component Noun System Open Item Entered 2-2016-0609 2-PP-50E East CCP ECCS Monday, July 03 , 2016 | |||
Component Noun System Open Item Entered 2-2016-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 23, 2016 | |||
OPERATIONS JPM TRAINING PROGRAM ILT TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-A3 TITLE: REVISION: 0 Respond to a High SJAE Radiation Alarm Examinees Name: _________________________________________ __________ | |||
Evaluators Name: : ___________________________________________________ | |||
Date Performed: : | Date Performed: : ____________________________________________________ | ||
Result (Circle One): | Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________ | ||
SAT | |||
Time to Complete: : ____________________________________________________ | Time to Complete: : ____________________________________________________ | ||
Comments:___________________________________________________________ | Comments:___________________________________________________________ | ||
NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 1 of 15 | |||
OPERATIONS JPM | OPERATIONS JPM REFERENCES Procedures: | ||
12-OHP-4024-139 ANNUNCIATOR #139 RESPONSE: RADIATION, Rev. 19 | 12-OHP-4024-139 ANNUNCIATOR #139 RESPONSE: RADIATION, Rev. 19 Miscellaneous | ||
==References:== | |||
TBD-2-FIG-19-19A Primary to secondary leak rate (Unit 2 at 5 SCFM), Rev. 13 TBD-2-FIG-19-19B Primary to secondary leak rate (Unit 2 at 10 SCFM), Rev. 12 TBD-2-FIG-19-19C Primary to secondary leak rate (Unit 2 at 15 SCFM), Rev. 12 TBD-2-FIG-19-19E Primary to secondary leak rate (Unit 2 at 20 SCFM), Rev. 10 TBD-2-FIG-19-19F Primary to secondary leak rate (Unit 2 at 30 SCFM), Rev. 10 TBD-2-FIG-19-19G Primary to secondary leak rate (Unit 2 at 25 SCFM), Rev. 9 TRAINING AIDS/TOOLS/EQUIPMENT NRC KA APE.037.AK3.05 Knowledge of the reasons for the following responses as they RO/SRO 3.7/4.0 apply to the Steam Generator Tube Leak: | |||
Actions contained in the procedures for radiation Monitoring, RCS water inventory balance, S/G tube failure, and plant shutdown. | |||
APE.037.AA2.01 Ability to determine and interpret the following as they apply RO/SRO 3.0/3.4 to the Steam Generator Tube Leak: | |||
Unusual readings of the monitors; steps needed to verify readings 2.3.14 Knowledge of the radiation or contamination hazards that RO/SRO 3.4/3.8 may arise during normal, abnormal, or emergency conditions or activities. | |||
2.3.14 TASKS ADM0420302 Verify Limiting Conditions for Operation are met in accordance with the Offsite Dose Calculation Manual (ODCM). | |||
NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 2 of 15 | |||
OPERATIONS JPM HANDOUTS: | |||
Task Briefing Copy of Data Sheet 1 of 12-OHP-4024-139 Drop 27 2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, 2-Figure 19.19e, 2-Figure 19.19f, and 2-Figure 19.19g ATTACHMENTS: | |||
12-OHP-4024-139 Drop 27 2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, 2-Figure 19.19e, 2-Figure 19.19f, and 2-Figure 19.19g EVALUATION SETTINGS: | |||
Classroom EVALUATOR INSTRUCTIONS NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 3 of 15 | |||
OPERATIONS JPM | |||
-OHP-4024-139 Drop 27 2-Figure 19.19a, 2 | |||
-Figure 19.19b, 2 | |||
-Figure 19.19c, 2-Figure 19. | |||
12-OHP-4024-139 Drop 27 2-Figure 19.19a, 2 | |||
-Figure 19.19b, 2 | |||
-Figure 19.19c, 2 | |||
-Figure 19. | |||
Classroom | |||
OPERATIONS JPM | OPERATIONS JPM Give copy of Task Briefing and attachments to examinee. | ||
Provide student with 12 | Provide student with 12-OHP-4024-139 Drop 27. | ||
-OHP-4024-139 Drop 27. | 2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, 2-Figure 19.19e, 2-Figure 19.19f, and 2-Figure 19.19g TASK BRIEFING: | ||
2-Figure 19.19a, 2 | Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900. | ||
-Figure 19.19b, 2 | A RCS to Steam Generator Tube Leak is suspected. The activities from SRA-2905 have been recorded at 15 minute intervals on Data Sheet #1. The SJAE flowrate is 17 scfm. | ||
-Figure 19.19c, 2 | You are the extra RO. | ||
-Figure 19. | The US directs you to plot the data and determine the total leak rate in accordance with 12-OHP-4024-139, Drop 27. Report your results and any operational limitations required per 12-OHP-4024-139, Drop 27. | ||
Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900. A RCS to Steam Generator Tube Leak is suspected. The activities from SRA-2905 | |||
-OHP-4024-139, Drop 27. Report your results and any operational limitations required per 12 | |||
-OHP-4024-139, Drop 27. | |||
(Table for information of Proctor as to what is provided to candidate.) | (Table for information of Proctor as to what is provided to candidate.) | ||
Time Activity (uCi/cc) 0300 1.4e-6 0315 1.7e-6 0330 2.0e-6 0345 2.7e-6 0400 3.9e-6 0415 4.8e-6 0430 5.7e-6 0445 7.1.e-6 0500 8.1e-6 0515 8.3e-6 | Time Activity (uCi/cc) 0300 1.4e-6 0315 1.7e-6 0330 2.0e-6 0345 2.7e-6 0400 3.9e-6 0415 4.8e-6 0430 5.7e-6 0445 7.1.e-6 0500 8.1e-6 0515 8.3e-6 JPM OVERVIEW Complete Data Sheet 1 of 12-OHP-4024-139 Drop 27 for accuracy and determine required actions based upon that data. | ||
-OHP-4024-139 Drop 27 for accuracy and determine required actions based upon that data. | NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 4 of 15 | ||
OPERATIONS JPM | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
CS | STANDARD: CS: Operator determines that SJAE graph for 20 scfm (17 scfm actual 2-Fig 19-19e) should be used for graphing radiation reading. | ||
STANDARD: CS: Operator determines that SJAE graph for 20 scfm ( | SAT: UNSAT: | ||
COMMENT: | |||
CS | NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 5 of 15 | ||
STANDARD: CS: | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
CS | STANDARD: CS: Operator determines the final leakrate is 87 GPD (85-90) | ||
SAT: UNSAT: | |||
COMMENT: | |||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
STANDARD: Operator graphs the radiation monitor data as indicated. | STANDARD: Operator graphs the radiation monitor data as indicated. | ||
SAT: | SAT: UNSAT: | ||
COMMENT: | |||
STANDARD: CS: Operator determines slope of curve indicates the rate of rise of the leakrate exceeds 30 GPD/hr. | |||
CS | SAT: UNSAT: | ||
STANDARD: CS: Operator reports the need to reduce power to less than 50% within one hour and be in MODE 3 within the next two hours. SAT: | COMMENT: | ||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
STANDARD: CS: Operator reports the need to reduce power to less than 50% within one hour and be in MODE 3 within the next two hours. | |||
SAT: UNSAT: | |||
COMMENT: | |||
Termination Cue: JPM is complete NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 8 of 15 | |||
TASK BRIEFING: | |||
Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900. A RCS to Steam Generator Tube Leak is suspected. The BOP has taken initial action per 12 | Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900. | ||
- | A RCS to Steam Generator Tube Leak is suspected. The BOP has taken initial action per 12-OHP-4024-139, Drop 27 to record SRA-2905 activity on Data Sheet 1 at 15 minute intervals. | ||
OHP-4024-139, Drop 27 to record SRA | The SJAE flowrate is 17 scfm. | ||
-2905 activity on Data Sheet 1 at 15 minute intervals. The SJAE flowrate is 17 scfm. You are the extra RO. The US directs you to plot the data and determine the total leak rate in accordance with 12 | You are the extra RO. | ||
-OHP-4024-139, Drop 27. Report your results and any operational limitations required per 12 | The US directs you to plot the data and determine the total leak rate in accordance with 12-OHP-4024-139, Drop 27. Report your results and any operational limitations required per 12-OHP-4024-139, Drop 27. | ||
-OHP-4024-139, Drop 27. | Revision: 0 NRC 2016-A3.doc Page 9 of 15 | ||
TDB-2-Figure 19-19a Revision: 0 NRC 2016-A3.doc Page 10 of 15 | |||
TDB-2-Figure 19-19b Revision: 0 NRC 2016-A3.doc Page 11 of 15 | |||
TDB-2-Figure 19-19c Revision: 0 NRC 2016-A3.doc Page 12 of 15 | |||
TDB-2-Figure 19-19e Revision: 0 NRC 2016-A3.doc Page 13 of 15 | |||
TDB-2-Figure 19-19f Revision: 0 NRC 2016-A3.doc Page 14 of 15 | |||
TDB-2-Figure 19-19g Revision: 0 NRC 2016-A3.doc Page 15 of 15 | |||
OPERATIONS JPM | OPERATIONS JPM TRAINING PROGRAM LOR/ILT TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-A4-RO TITLE: Perform the Initial Offsite Notification REVISION: 0 Examinees Name: _________________________________________ __________ | ||
Evaluators Name: : ___________________________________________________ | |||
Date Performed: : ____________________________________________________ | |||
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________ | |||
Time to Complete: : ____________________________________________________ | |||
Comments:___________________________________________________________ | |||
NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 1 of 9 | |||
OPERATIONS JPM REFERENCES Procedures: | |||
PMP-2080-EPP-100 EMERGENCY RESPONSE NRC KA P2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation. (CFR: 45.11) | |||
RO/SRO Importance 3.8/3.9 TASKS EPP0030701 Perform the Initial Offsite Notification OBJECTIVES* | |||
JPM-RO-O-ADM11 Perform the Initial Offsite Notification NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 2 of 9 | |||
Give copy of Task Briefing to examinee. | OPERATIONS JPM HANDOUTS: | ||
Task Briefing EMD-32a Nuclear Plant Event Notification (blank form) | |||
PMP-2080-EPP-100, Emergency Response Sections: | |||
* Attachment 9 MSP Notification | |||
* Attachment 12 Manual Completion of EMD Forms MIDAS Summary as part of the handout (attached) | |||
ATTACHMENTS: | |||
None EVALUATION SETTINGS: Classroom EVALUATION METHOD: PERFORM: SIMULATE: | |||
EVALUATOR INSTRUCTIONS Give copy of Task Briefing to examinee. | |||
TASK BRIEFING: | TASK BRIEFING: | ||
You are an extra Control Room Operator on Unit 2. Both units are operating at 100% with DG2CD OOS. | You are an extra Control Room Operator on Unit 2. | ||
Multiple indications and reports were received indicating a fire in the DG2AB room | Both units are operating at 100% with DG2CD OOS. | ||
-4, Fire or Explosion affecting plant operations. | Multiple indications and reports were received indicating a fire in the DG2AB room The Shift Manager has just declared an ALERT per Initiating Condition H-4, Fire or Explosion affecting plant operations. | ||
No radiological release is in progress. | No radiological release is in progress. | ||
There are no protective action | There are no protective action recommendations. | ||
Classification Time is _________ (Current Time) | |||
The Shift Manager directs you as the Plant Communicator to complete EMD | The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval, obtain approval from the Shift Manager, and then make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response. | ||
-32a, Nuclear Plant Event Notification form for approval, obtain approval from the Shift Manager, and then make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response. Meteorological Data | Meteorological Data - Use the MIDAS Summary provided. | ||
- Use the MIDAS Summary provided. THIS IS A TIME CRITICAL JPM | THIS IS A TIME CRITICAL JPM JPM OVERVIEW Given plant conditions, the operator will complete the EMD-32a, Nuclear Plant Event Notification form, obtain approval, and the MSP within 15 minutes. | ||
NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 3 of 9 | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
OPERATIONS JPM | |||
CS | |||
All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval. | All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval. | ||
STANDARD: | STANDARD: Drill box marked (for purposes of this JPM C1 Actual Event is also acceptable) | ||
SAT: | SAT: UNSAT: | ||
Candidate enters name as Plant Communicator | STANDARD: | ||
STANDARD: CS | * C1 entered as Plant Message Number since this is the initial notification (1, CR1, or equivalent are also acceptable) | ||
STANDARD: CS | * Candidate enters name as Plant Communicator | ||
* Control Room box marked | |||
* CUE: If asked, Time of Communication is current time. | |||
H4 SAT: UNSAT: | |||
STANDARD: CS | |||
* ALERT box MUST be marked | |||
* Date and Time of Classification (given during the briefing) MUST be filled in SAT: UNSAT: | |||
STANDARD: CS | |||
* Hazards and Other Conditions affecting plant safety box marked | |||
* H-4 MUST be filled in SAT: UNSAT: | |||
CONTINUED ON NEXT PAGE. | |||
NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 4 of 9 | |||
OPERATIONS JPM | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
NOTE: The operator should determine from the briefing that no radiological release is in progress and that no PAR is required. If clarification is requested, the evaluator should provide the cues that a release is not in progress and no PAR applies. | |||
STANDARD: CS NO box MUST be marked SAT: UNSAT: | |||
STANDARD: CS None box MUST be marked SAT: UNSAT: | |||
STANDARD: Stability Class E filled in SAT: UNSAT: | |||
STANDARD: CS Wind from 328 to 148 filled in SAT: UNSAT: | |||
STANDARD: CS Wind speed 5.5 mph filled in (may round up to 6 mph SAT: UNSAT: | |||
STANDARD: Precipitation No box marked SAT: UNSAT: | |||
STANDARD: Candidate reports complete and ready for SEC/SM approval 328 148 5.5 SAT: UNSAT: | |||
E EVALUATOR: Sign, date, and fill in time on EMD-32a. | |||
Return the form and direct the operator to make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response. | |||
NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 5 of 9 | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
NOTE: Telephone communications should be simulated. | NOTE: Telephone communications should be simulated. | ||
STANDARD: CS Operator identifies correct phone number for the MSP. | STANDARD: CS Operator identifies correct phone number for the MSP. | ||
SAT: | SAT: UNSAT: | ||
CUE: | CUE: This is Officer Smith of the Michigan State Police. | ||
. Completion Time _________ | |||
. Completion Time _________ | STANDARD: CS Operator provides correct information of all items marked as critical on the EMD-32a within 15 minutes of classification time. | ||
SAT: UNSAT: | |||
STANDARD: CS Operator provides correct information of all items marked as critical on the EMD | EVALUATOR: Repeat back information given by the operator NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 6 of 9 | ||
-32a within 15 minutes of classification time. | |||
SAT: | |||
EVALUATOR: Repeat back information given by the operator | |||
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
STANDARD: Operator fills in appropriate information on the attachment and requests a callback. | STANDARD: Operator fills in appropriate information on the attachment and requests a callback. | ||
SAT: | SAT: UNSAT: | ||
JPM TERMINATION: When a callback has been requested and the phone call has been ended, inform the operator that the JPM is complete. | |||
Termination Cue: Complete the EMD-32a, Nuclear Plant Event Notification form and notify of MSP within 15 minutes. | |||
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JPM | OPERATIONS JPM TASK BRIEFING: | ||
You are an extra Control Room Operator on Unit 2. | |||
Both units are operating at 100% with DG2CD OOS. | |||
Multiple indications and reports were received indicating a fire in the DG2AB room The Shift Manager has just declared an ALERT per Initiating Condition H-4, Fire or Explosion affecting plant operations. | |||
No radiological release is in progress. | |||
There are no protective action recommendations. | |||
Classification Time is _________ (Current Time) | |||
The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval, obtain approval from the Shift Manager, and then make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response. | |||
Meteorological Data - Use the MIDAS Summary provided. | |||
THIS IS A TIME CRITICAL JPM Revision: 0 NRC 2016-A4-RO.doc Page 8 of 9 | |||
Revision: 0 NRC 2016-A4-RO.doc Page 9 of 9 | |||
- | |||
OPERATIONS JPM | OPERATIONS JPM TRAINING PROGRAM ILT TIME: 20 MINUTES TITLE NUMBER AND NRC 2016-A4-SRO TITLE: Perform the duties of the Site Emergency REVISION: 1 Coordinator SRO-ONLY Approved for SRO Only JPM JPM-SRO-ADMIN JPM-TIME-CRITICAL Time Critical JPM Examinees Name: _________________________________________ __________ | ||
Evaluators Name: : ___________________________________________________ | |||
Date Performed: : ____________________________________________________ | |||
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________ | |||
Date Performed: : | |||
____________________________________________________ | |||
Result (Circle One): | |||
SAT | |||
Time to Complete: : ____________________________________________________ | Time to Complete: : ____________________________________________________ | ||
Comments:___________________________________________________________ | Comments:___________________________________________________________ | ||
NRC 2016-A4-SRO Revision: 0 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO.docx Page 1 of 8 | |||
OPERATIONS JPM | OPERATIONS JPM REFERENCES Procedures: | ||
PMP-2080-EPP-101 Emergency Classification, Rev. 18 PMP-2080-EPP-100 EMERGENCY RESPONSE, REV. | PMP-2080-EPP-101 Emergency Classification, Rev. 18 PMP-2080-EPP-100 EMERGENCY RESPONSE, REV. 33 Miscellaneous | ||
Miscellaneous | |||
==References:== | ==References:== | ||
TRAINING AIDS/TOOLS/EQUIPMENT NRC KA | TRAINING AIDS/TOOLS/EQUIPMENT NRC KA P2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation. (CFR: 45.11) | ||
RO/SRO Importance 2.7/4.5 P2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR: 43.5 / 45.11) | RO/SRO Importance 2.7/4.5 P2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR: 43.5 / 45.11) | ||
RO/SRO Importance 2.3/4.1 TASKS | RO/SRO Importance 2.3/4.1 TASKS EPP0020703 Classify an Emergency Condition. | ||
EPP0160703 Perform the duties of the Site Emergency Coordinator. | EPP0160703 Perform the duties of the Site Emergency Coordinator. | ||
OBJECTIVES* | OBJECTIVES* | ||
JPM-SR-O-E015 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO Revision: 0 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO.docx Page 2 of 8 | |||
OPERATIONS JPM HANDOUTS: | |||
Copy of current revisions of the following: | |||
OPERATIONS JPM | |||
PMP-2080-EPP-101, Emergency Classification ATTACHMENTS: | PMP-2080-EPP-101, Emergency Classification ATTACHMENTS: | ||
Completed EMD32a Meteorological Summary EVALUATION SETTINGS: | |||
Completed EMD32a | Administrative JPM, may be evaluated in classroom setting EVALUATOR INSTRUCTIONS Give copy of Task Briefing to examinee. | ||
Meteorological Summary EVALUATION SETTINGS: | |||
Administrative JPM, may be evaluated in classroom setting | |||
Give copy of Task Briefing to examinee. | |||
TASK BRIEFING: | TASK BRIEFING: | ||
You are the Shift Manager | You are the Shift Manager Unit 2 experienced a secondary side break due to a failed open SG Safety valve on #21 SG. The Crew tripped the reactor, initiated Safety Injection, and performed actions of E-0, Reactor Trip or Safety Injection. A transition was made to E-2, Faulted SG Isolation. Actions of E-2 were completed for 21 SG. The safety valve remained open and could not be reseated. After completion of E-2, the crew transitioned to ES-1.1, SI Termination, stopped one CCP, isolated BIT injection flow, and stopped both SI pumps. Several minutes after terminating SI, RCS pressure and pressurizer level suddenly started lowering rapidly, along with a rapid increase in 21 SG level. The crew started both CCPs and SI pumps and reinitiated BIT flow based on inability to maintain pressurizer level >21% and transitioned to E-1, Loss of Reactor or Secondary Coolant, and then to E-3, Steam Generator Tube Rupture, based on uncontrolled level increase in 21 SG. The Emergency Plan has not yet been entered during the event. | ||
You are to determine if an Emergency Classification is applicable. Review and approve EMD-32a as required. | |||
Unit 2 experienced a secondary side break due to a failed open SG Safety valve on #21 SG. The Crew tripped the reactor, initiated Safety Injection, and performed actions of E | |||
-0, Reactor Trip or Safety Injection. A transition was made to E | |||
-2, Faulted SG Isolation. Actions of E | |||
-2 were completed for 21 SG. The safety valve remained open and could not be reseated. After completion of E | |||
-2, the crew transitioned to ES | |||
-1.1, SI Termination, stopped one CCP, isolated BIT injection flow, and stopped both SI pumps. Several minutes after terminating SI, RCS pressure and pressurizer level suddenly started lowering rapidly, along with a rapid increase in 21 SG level. The crew started both CCPs and SI pumps and reinitiated BIT flow based on inability to maintain pressurizer level >21% and transitioned to E | |||
-1, Loss of Reactor or Secondary Coolant, and then to E | |||
-3, Steam Generator Tube Rupture, based on uncontrolled level increase in 21 SG. The Emergency Plan has not yet been entered during the event. | |||
You are to determine if an Emergency Classification is applicable | |||
. Review and approve EMD-32a as required. | |||
THIS JPM IS TIME CRITICAL Classification Start Time: _____________________________ | THIS JPM IS TIME CRITICAL Classification Start Time: _____________________________ | ||
JPM OVERVIEW Operator will perform an Emergency Classification of the event based on plant conditions and verify a correctly completed EMD32a | JPM OVERVIEW Operator will perform an Emergency Classification of the event based on plant conditions and verify a correctly completed EMD32a NRC 2016-A4-SRO Revision: 0 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO.docx Page 3 of 8 | ||
OPERATIONS JPM | OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | ||
( | Provide PMP-2080_EPP-101 STANDARD: | ||
-2080_EPP-101 STANDARD: | CS: Identify a Site Area Emergency based on a combination of (EAL 2.2P OR 2.2L) AND 3.3L applies and declare a Site Area Emergency within 15 minutes SAT: | ||
CS: Identify a Site Area Emergency based on a combination of (EAL 2.2P OR 2.2L) AND 3.3L applies and declare a Site Area Emergency within 15 minutes SAT: | UNSAT: | ||
COMMENT: | |||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
STANDARD: | |||
CS: Identify a Site Area Emergency based on a combination of (EAL 2.2P OR 2.2L) AND 3.3L applies and declare a Site Area Emergency within 15 minutes SAT: | |||
UNSAT: | |||
COMMENT: | |||
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) | |||
Classification Completed Time: ________________________ | Classification Completed Time: ________________________ | ||
The Operator should provide the following information to complete the EMD-32a: NOTE: If the operator provided the correct EAL And | |||
NOTE: If the operator provided the correct EAL And Classification Provide the operator with the INCORRECTLY | * Current classification- Site Area Emergency Classification Provide the operator with the INCORRECTLY Completed | ||
* , Date, and Time EMD32a and Meteorological Summary printout for review and Approval | |||
SAT: | * Site Area Emergency STANDARD: CS: Operator identifies that the completed EMD- | ||
NOTE: If the operator provided the INCORRECT | * Reason for classification (Fission Product Barrier Degradation) 32a was INCORRECTLY completed and provides corrections (Changes from Alert to SAE and add 3.3L to IC Number) | ||
* IC Number ((EAL 2.2P OR 2.2L) AND 3.3L) SAT: UNSAT: | |||
Classification ______________ | * Radiological Release in Progress NOTE: If the operator provided the INCORRECT EAL And Classification. Document below and repeat back the incorrect | ||
* No Protective Action Recommendations information. | |||
Reason for Classification | * Classification ______________ | ||
Reason for Classification _______________ | |||
IC Number __________________________ | IC Number __________________________ | ||
CUE: This JPM is complete. | |||
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OPERATIONS JPM NRC 2016-A4-SRO Revision: 0 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO.docx Page 7 of 8 | |||
TASK BRIEFING: | |||
You are the Shift Manager Unit 2 experienced a secondary side break due to a failed open SG Safety valve on #21 SG. The Crew tripped the reactor, initiated Safety Injection, and performed actions of E | You are the Shift Manager Unit 2 experienced a secondary side break due to a failed open SG Safety valve on #21 SG. The Crew tripped the reactor, initiated Safety Injection, and performed actions of E-0, Reactor Trip or Safety Injection. A transition was made to E-2, Faulted SG Isolation. Actions of E-2 were completed for 21 SG. The safety valve remained open and could not be reseated. After completion of E-2, the crew transitioned to ES-1.1, SI Termination, stopped one CCP, isolated BIT injection flow, and stopped both SI pumps. Several minutes after terminating SI, RCS pressure and pressurizer level suddenly started lowering rapidly, along with a rapid increase in 21 SG level. The crew started both CCPs and SI pumps and reinitiated BIT flow based on inability to maintain pressurizer level >21% and transitioned to E-1, Loss of Reactor or Secondary Coolant, and then to E-3, Steam Generator Tube Rupture, based on uncontrolled level increase in 21 SG. The Emergency Plan has not yet been entered during the event. | ||
-0, Reactor Trip or Safety Injection. A transition was made to E | You are to determine if an Emergency Classification is applicable. Review and approve EMD-32a as required. | ||
-2, Faulted SG Isolation. Actions of E | THIS JPM IS TIME CRITICAL NRC 2016-A4-SRO Revision: 0 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO.docx Page 8 of 8}} | ||
-2 were completed for 21 SG. The safety valve remained open and could not be reseated. After completion of E | |||
-2, the crew transitioned to ES | |||
-1.1, SI Termination, stopped one CCP, isolated BIT injection flow, and stopped both SI pumps. Several minutes after terminating SI, RCS pressure and pressurizer level suddenly started lowering rapidly, along with a rapid increase in 21 SG level. The crew started both CCPs and SI pumps and reinitiated BIT flow based on inability to maintain pressurizer level >21% and transitioned to E | |||
-1, Loss of Reactor or Secondary Coolant, and then to E | |||
-3, Steam Generator Tube Rupture, based on uncontrolled level increase in 21 SG. The Emergency Plan has not yet been entered during the event. | |||
You are to determine if an Emergency Classification is applicable | |||
. Review and approve EMD | |||
-32a as required. | |||
THIS JPM IS TIME CRITICAL}} |
Latest revision as of 22:41, 4 February 2020
ML16341C428 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 12/02/2016 |
From: | NRC/RGN-III |
To: | Indiana Michigan Power Co, American Electric Power |
Shared Package | |
ML15274A376 | List: |
References | |
Download: ML16341C428 (91) | |
Text
CLASSROOM LESSON TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MIN TITLE NUMBER AND NRC 2016-A1a-RO TITLE: Calculate QPTR with Inoperable Power Range (PR) REVISION: 0 Instrument Examinees Name: :_________________________________________________________
Evaluators Name: :_________________________________________________________
Date Performed: : _________________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: :________________________________________________________
Time to Complete: :_________________________________________________________
Comments:__________________________________________________________________
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REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-032 Quadrant Power Tilt Calculation K/A Number: 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation SYS 015 A1.04 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: Quadrant Power Tilt Ratio K/A Imp.: RO: 4.4 SRO: 4.7 3.5 3.7 Task Number: 0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT
- Calculator
- Ruler HANDOUTS Task Briefing Completed 2-OHP-4030-214-032 and Data Sheet 3 ATTACHMENTS NI Calibration Data Card N41, N42, N43, and N44 Pictures EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:
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OPERATIONS JPM SIMULATOR/LAB SETUP None EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING You are an extra RO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 2 is currently at 72% power.
- All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 2-OHP-4030-214-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS Correctly obtain values and calculates a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 2-OHP-4030-214-032.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Operator records Upper & Lower Detector blanks for N-41, 43 and 44 on Data Sheet 3.
SAT: UNSAT:
Note: See Page 6-7 For expected values Operator records NI detector readings (within +0.5) on a division mark and within the division marks for all others.
SAT: UNSAT:
CS: Operator enters data from cards provided.
SAT: UNSAT:
Operator divides respective NI channel with its 120% value (from cards on Channel 3 NI panel)
SAT: UNSAT:
Operator totals 3 channels of normalized values SAT: UNSAT:
Operator determines upper and lower QPTR using data sheet 3 SAT: UNSAT:
N/A Operator enters the highest calculated QPTR (CS: Covered on Page 6)
SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering SAT: UNSAT:
CUE: SM Acknowledges that QPTR has Exceeded TS value and will address the required actions.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CS: Data entered on this page based on Simulator readings.
See page 7 for acceptable range of readings 41 99 135.4 .7312 43 98 134.4 .7292 44 98 136.7 .7169 2.1772 Upper Tilt Ratio 1.007 (range 1.001 to 1.022) 41 91.5 135.6 .6748 SAT: UNSAT:
43 98.5 134.7 .7313 44 97.5 136.2 .7159 2.1219 Lower Tilt Ratio 1.034 (range 1.026 to 1.041)
SAT: UNSAT:
1.007 1.034 CS: Operator enters the highest calculated QPTR of previous 2 1.034 values 1.034 (range 1.026 to 1.041)
N/A Candidate marks N/A CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering Candidate Signs, Dates, & enters Time and reports task completed.
CUE: SM Acknowledges the report and will address the required actions.
Evaluator: This JPM is complete.
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OPERATIONS JPM Acceptable Ranges Based on Scale used on Pictures Detector A (UPPER)
SCALE 5 5 1 1 500 500 100 100 Low High Low High Low High Low High N41 4.9 5 0.985 0.995 490 500 98.5 99.5 N43 4.85 4.95 0.975 0.985 485 495 97.5 98.5 N44 4.85 4.95 0.975 0.985 485 495 97.5 98.5 Using the 500 Scale (UPPER QPTR ranges Calculated using combinations of High/Low values above)
Lowest, Lowest, Highest ---- 1.001 Highest, Lowest, Lowest ----- 1.022 Detector B (LOWER)
SCALE 5 5 1 1 500 500 100 100 Low High Low High Low High Low High 4.55 4.6 0.91 0.92 455 460 91 92 4.9 4.95 0.98 0.99 490 495 98 99 4.85 4.9 0.97 0.98 485 490 97 98 (LOWER QPTR Ranges Calculated using combinations of High/Low values above)
Highest, Lowest, Highest ---- 1.026 Lowest, Highest, Lowest ----- 1.041 NRC 2016-A1a-RO Revision: 0 Calculate QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-RO.doc Page 7 of 12
Task Briefing You are an extra RO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 2 is currently at 72% power.
- All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 2-OHP-4030-214-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
NOTE Simulator Indications are NOT applicable to this JPM - Use Supplied Pictures for readings.
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TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MIN TITLE NUMBER AND NRC 2016-A1a-SRO TITLE: Review QPTR with Inoperable Power Range (PR) REVISION: 0 Instrument Examinees Name: :_________________________________________________________
Evaluators Name: :_________________________________________________________
Date Performed: : _________________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: :________________________________________________________
Time to Complete: :_________________________________________________________
Comments:__________________________________________________________________
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REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-032 Quadrant Power Tilt Calculation K/A Number: 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrumentation interpretation SYS 015 A1.04 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including: Quadrant Power Tilt Ratio K/A Imp.: RO: 4.4 SRO: 4.7 3.5 3.7 Task Number: 0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT
- Calculator
- Ruler HANDOUTS Task Briefing Completed 2-OHP-4030-214-032 and Data Sheet 3 ATTACHMENTS NI Calibration Data Card N41, N42, N43, and N44 Pictures EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:
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SIMULATOR/LAB SETUP None EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING You are the Unit SRO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 2 is currently at 72% power.
- All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The SM directs you to Review the manual 2-OHP-4030-214-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
NOTE Simulator Indications are NOT applicable to this JPM GENERAL STANDARDS/PRECAUTIONS Review a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 2-OHP-4030-214-032 and identify error and required TS Actions NRC 2016-A1a-SRO Revision: 0 Review QPTR with Inoperable Power Range (PR) Instrument NRC 2016-A1a-SRO.doc Page 3 of 12
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard) 41 99 135.4 .7312 43 98 134.4 .7292 44 98 136.7 .7169 2.1772 41 91.5 135.6 .6748 43 98.5 134.7 .7313 44 97.5 136.2 .7159 2.1219 1.0074 1.0034 CS: Operator identifies that value was incorrectly calculated.
Should be 1.034 resulting in excessive QPTR.
1.0074 1.034 (range 1.026 to 1.041)
SAT: UNSAT:
N/A CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM & Reactor Engineering SAT: UNSAT:
CUE: SM Acknowledges that QPTR has Exceeded TS value requests that you review the Required Technical Specification and determine the required Actions.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: (If Required) Ask Operator to determine the Technical Specification LCO that applies.
CS: Determines that Power is limited to 3% for each 1% over 1.00 (3.4 x 3% = 10.2%) per LCO 3.2.4 Action A.1 - (note power limit is from RTP - 89.9% is limit)
(Range of 7.8% to 12.3% reduction with a 92.2% to 87.7% power limit)
SAT: UNSAT:
Also Determines that QPTR must be calculated every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Verify F Q (Z ) is within limit., Verify F Q (Z ) is within limit, & Verify C W F
N h
is within limits specified in the COLR.
SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Identify that safety analyses must be evaluated before raising power above the limit.(92.2% to 87.7% power limit)
SAT: UNSAT:
A.5 & A.6 required if power is raised above above the limit.(92.2%
to 87.7% power limit)
SAT: UNSAT:
Evaluator: This JPM is complete.
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Task Briefing You are the Unit SRO.
The following conditions exist:
- NI Channel N-42 has failed low
- Unit 2 is currently at 72% power.
- All actions of 2-OHP-4022-013-004, Power Range Malfunction have been completed
- The Plant Process Computer (PPC) is INOPERABLE The SM directs you to Review the manual 2-OHP-4030-214-032, Quadrant Power Tilt Calculation.
The NI amp meters are set to display maximum resolution and the fluke readings confirm that the indicators are reading properly.
NOTE Simulator Indications are NOT applicable to this JPM - Use Supplied Pictures for readings.
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NI CALIBRATION DATA DET A 120% I in µAmps N41 = 135.4 N42 = 136.6 N43 = 134.4 N44 = 136.7 DET B 120% I in µAmps N41 = 135.6 N42 = 133.6 N43 = 134.7 N44 = 136.2 Verified: Print ____John Smithe__
Sign ___ John Smithe _____
Date 5/11/2016____
DATAforA1a.doc
OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-A1b-SRO TITLE: Verify Appropriate LCO Action for Inoperable REVISION: 0 Radiation Monitors Examinees Name: _________________________________________ __________
Evaluators Name: : ___________________________________________________
Date Performed: : ____________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________
Time to Complete: : ____________________________________________________
Comments:___________________________________________________________
NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 1 of 13
OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedures: 12-OHP-4024-139 Annunciator #139 Response: Radiation TRM 8.3.8 Radiation Monitoring Instrumentation PMP-4030-EIS-001 Event-Initiated Surveillance Testing PMP-6010-OSD-001 Off-Site Dose Calculation Manual K/A Number: 2.1.12 Ability to apply Technical Specifications for a system.
K/A Imp.: RO: 2.9 SRO: 4.0 Task Number: ADM0370302 Verify Limiting Conditions for Operation are met in accordance with Technical Specifications.
Verify Limiting Conditions for Operation are met in ADM0420302 accordance with the Offsite Dose Calculation Manual.
TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 12-OHP-4024-139, Annunciator #139 Response: Radiation Drop 24 Unit 2 - TRM 8.3.8., Radiation Monitoring Instrumentation PMP-4030-EIS-001, Event-Initiated Surveillance Testing PMP-6010-OSD-001, Off-Site Dose Calculation Manual ATTACHMENTS None EVALUATION SETTINGS Classroom EVALUATION METHOD: PERFORM: SIMULATE:
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OPERATIONS JPM SIMULATOR/LAB SETUP
- 1. None EVALUATOR INSTRUCTIONS
- 1. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING You are an extra SRO.
Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS-2505, Low Range Noble Gas went into External Failure (WHITE) 5 minutes ago.
The Channel did NOT fail Low.
There is NO Waste Gas release in progress.
The Unit Supervisor directs you to investigate, perform any required actions, and complete required documentation.
NOTE Simulator Indications are NOT applicable to this JPM.
Provide ONLY 12-OHP-4024-139 Drop 24 Unit Vent Effluent Monitor at this time GENERAL STANDARDS/PRECAUTIONS Respond to a failed RMS channel and determine the appropriate LCO actions in accordance with applicable procedures.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
General CUES:
If contacted as Rad Protection, report Channel 2505 is in EXTERNAL FAIL.
Provide 12-OHP-4024-139 Drop 24 Unit Vent Effluent Monitor STANDARD: Operator reviews conditions for WHITE light.
SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: Provide TRM 8.3.8 when recognizes need to reference STANDARD: Operator references TRM 8.3.8 actions (None Required for VRS-2505)
SAT: UNSAT:
CUE: If asked, Channel VRS-2505 is NOT due to a low failure and will be out-of-service for at least 5 days.
CUE: If required, acknowledge report to RP of Channel Failure CUE: US will initiate AR processing.
CUE: Provide PMP-4030-EIS-001, Event-Initiated Surveillance Testing when recognizes need to reference STANDARD (CS): Operator reports VRS-2505 as Inoperable and references PMP-4030-EIS-001, Attachment 1.
SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CUE: US will coordinate with RP to determine if channel should be removed from service.
CUE: Provide PMP-4030-EIS-001, Event-Initiated Surveillance Testing when recognizes need to reference NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 6 of 13
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator identifies applicability of Item 17, which references ODCM Attachment 3.4, Items 2.a and 4.a SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator identifies applicability of Item 17.
SAT: UNSAT:
STANDARD: Notifies Chemistry of Required Surveillance requirements.
SAT: UNSAT:
CUE: Chemistry acknowledges requirements CUE: US has logged the event in the Control Room Log.
STANDARD: Completes DATA Sheet 1 Steps 1.1 through 1.7 SAT: UNSAT:
N/A NRC 2016-A1b-SRO Revision: 0 Verify Appropriate LCO Action for Inoperable Radiation Monitors NRC 2016-A1b-SRO.doc Page 8 of 13
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator references action item 6 for VRS-2505 being inoperable.
SAT: UNSAT:
Note: Operator may reference action item 9 for VRS-2505 being inoperable. (ONLY required if release is in progress which briefing stated was NOT)
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator reports requirement that release may continue for up to 30 days provided grab samples are taken shiftly and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (If Not returned in 30 days provide a description in Annual Report) (may be entered on PMP-4030-EIS-001, Data Sheet 1)
SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Note: Operator may report requirement that release may continue for up to 14 days provided contingency actions are taken. (ONLY required if release is in progress which briefing stated was NOT)
CUE: If Required, Unit Supervisor acknowledges ability to continue release up to 14 days provide contingencies are met.
CUE: If required, ask What Documentation is required? (to ensure PMP-4030-EIS-001, Data Sheet 1 is initiated).
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD (CS): Enters Data as required in steps 1.1 and 1.2. (Date and Time are NOT Critical Standards)
SAT: UNSAT:
STANDARD: Enters 30 days / (14 days for releases - NA)
SAT: UNSAT:
17 Vent Stack Noble Gas Monitor VRS-2505 Inoperable 2 Current Date Current Time STANDARD (CS): Enters 12-THP-6020-CHM-322 OR "Requirement that release may continue for up to 30 days provided grab samples are taken shiftly and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />." (Procedure or Action Required)
SAT: UNSAT:
Instructor Note: If Gaseous Waste release will be performed then may determine ODCM, Attachment 3.4, Action 9, is applicable.
STANDARD (CS):Indicates that Samples are required once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per ODCM Attachment 3.4 action 6 (and 12-THI-2291-ADM-012)
SAT: UNSAT:
CUE: Provide AR# from Unit Supervisor as 2016-9999 CUE: Step 1.7 is completed and signed off.
CUE: Acknowledge Unit 1 has been notified TERMINATION CUE: This JPM is complete.
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Task Briefing You are an extra SRO.
Unit 2 is in Mode 1. Annunciator Radiation Monitor Channel VRS-2505, Low Range Noble Gas went into External Failure (WHITE) 5 minutes ago.
The Channel did NOT fail Low.
There is NO Waste Gas release in progress.
The Unit Supervisor directs you to investigate, perform any required actions, and complete required documentation.
NOTE Simulator Indications are NOT applicable to this JPM.
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OPERATIONS JPM NUMBER: NRC 2016-A2-RO TIME: 15 MINUTES TITLE: Perform Unit 2 LTOP Verification REVISION: 0 Examinees Name: _________________________________________ __________
Evaluators Name: : ___________________________________________________
Date Performed: : ____________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________
Time to Complete: : ____________________________________________________
Comments:___________________________________________________________
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OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: 2.2.37 K/A Imp.: RO: 3.6 SRO: 4.6 Task Number: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS
- 1. Task Briefing sheet
- 2. Work Management Listing (Open Items) - 2 pages
- 3. Unit 2 Technical Specifications
- 4. 2-OHP-4030-214-030, Daily And Shiftly Surveillance Checks:
- Data Sheet 20,LTOP Verification
- Data Sheet 20A, LTOP Verification LCO 3.4.12.A
- Data Sheet 20B, LTOP Verification LCO 3.4.12.B ATTACHMENTS None EVALUATION SETTINGS Classroom.
EVALUATION METHOD: PERFORM: SIMULATE:
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OPERATIONS JPM SIMULATOR/LAB SETUP None.
EVALUATOR INSTRUCTIONS
- 1. Brief the operator (May be performed by giving out Task Briefing sheet).
- 2. Announce start of the JPM.
- 3. Perform evolution.
- 4. At completion of evolution, announce the JPM is complete.
- 5. Document evaluation performance.
TASK BRIEFING The US directs you to determine whether the Unit 2 LTOP Requirements are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below:
Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:
2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-152 2-NRV-153 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F NRC 2016-A2-RO Revision: 0 Perform Unit 2 LTOP Verification NRC 2016-A2-RO.doc Page 3 of 9
OPERATIONS JPM RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized GENERAL STANDARDS/PRECAUTIONS When directed by the Unit Supervisor, determine if LTOP Requirements for Unit 2 are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
General CUES:
Provide a copy of the following handouts:
- 1) Work Management Listing (Open Items) - 3 pages.
- 2) 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks:
- Data Sheet 20
- Data Sheet 20A
- Data Sheet 20B CS: Determines based on Task Briefing information that Data Sheet 20A, LTOP Verification LCO 3.4.12.A is applicable.
SAT: UNSAT:
Note: Data Sheet 20B is for LCO 3.4.12.B when Both CCPs are available.
Based on the given Conditions One CCP is Locked out, and so the relaxed requirements of 3.4.12.A are applicable.
Note: Candidate should complete Data Sheet 20A, per following page prior to completing the remainder of Data Sheet 20.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CS: Marks page as shown [at Xs] (only one PORV is operable and RHR Suction Relief Operable).
SAT: UNSAT:
Note: PORV NRV-153 is Inoperable due to low Accumulator Tank Pressure ANN 208 Drop 28 is LIT CS: Determines that LTOP Requirements are Met.
SAT: UNSAT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Completes Section 3 based on Task Brief information, Work Management Listing, and Data Sheet 20A:
SAT: UNSAT:
- Accumulators Isolated (Yes)
- RHR Suctions Isolations Open (Yes)
- PORV Block Valves Open (Yes)
- Data Sheet 20A is Met (YES)
- Data Sheet 20B is met (N/A)
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
CS: Informs US/SM that LTOP Requirements are is Met.
SAT: UNSAT:
CUE: Acknowledge Test Results. When candidate documents FINAL CONDITIONS in step 4.1, then JPM is Complete.
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Task Briefing The US directs you to determine whether the Unit 2 LTOP Requirements are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below:
Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:
2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-152 2-NRV-153 Control Selector Cold Over-Pressure Block for Cold Over Press 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized Revision: 0 NRC 2016-A2-RO.doc Page 9 of 9
Unit 2 Open Items Summary Open Item # Component Noun System Open Item Entered 2-2016-0594 2-VTR-300 Control Room Air Temperature VCRAC Tuesday, May 22, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.7.11 2016-13357 Condition Description Notes 12-IHP-5021-IMP-001 (55384995-01) Temperature Instrument Calibration Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0600 2-NTR-12 CORE EXIT THERMOCOUPLE LOCATION F-15 NI Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.3.3 A Modes 1, 2, 3, and 4 Condition Description Notes Failed TC Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0601 2-NRV-153 PRESSURIZER PORV NRV-153 PZR Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 F N/A Modes 5 & 6 3.4.12 E N/A Mode 4 3.4.11 A N/A Modes 1, 2, and 3 Condition Description Notes Emergency Air Tank is depressurized and Isolated due to air leak at pressure connection Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0602 2-IMO-110 Safety Injection Accumulator Discharge Valve ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 1 of 3
Open Item # Component Noun System Open Item Entered 2-2016-0603 2-IMO-120 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0604 2-IMO-130 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0605 2-IMO-140 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0606 2-PP-26N NORTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 2 of 3
Open Item # Component Noun System Open Item Entered 2-2016-0607 2-PP-26S SOUTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A B Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0609 2-PP-50E East CCP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, 3 Condition Description Notes CCP Tagged Out to Prevent Injection Required for SR 3.4.12.2 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 23, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 8.3.8 C Condition Description Notes RP has not completed Operability recommendation checks following I & C board replacement under WOT 55403403 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 3 of 3
OPERATIONS JPM NUMBER: NRC 2016-A2-SRO TIME: 15 MINUTES TITLE: Review Unit 2 LTOP Verification REVISION: 1 Changed Error from RHR to NRV-153 Examinees Name: _________________________________________ __________
Evaluators Name: : ___________________________________________________
Date Performed: : ____________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________
Time to Complete: : ____________________________________________________
Comments:___________________________________________________________
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OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4030-214-030 Daily and Shiftly Surveillance Checks K/A Number: 2.2.42 K/A Imp.: RO: 3.9 SRO: 4.6 Task Number: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS
- Task Briefing sheet
- Work Management Listing (Open Items) - 2 pages
- Copy of Completed 2-OHP-4030-214-030, Data Sheet 20 (fill in Sections 3 & 4)
- Copy of Completed 2-OHP-4030-214-030, Data Sheet 20A (attached)
- TS 3.4.12 and Bases ATTACHMENTS None EVALUATION SETTINGS Classroom.
EVALUATION METHOD: PERFORM: SIMULATE:
SIMULATOR/LAB SETUP None.
EVALUATOR INSTRUCTIONS
- 1. Brief the operator (May be performed by giving out Task Briefing sheet).
- 2. Announce start of the JPM.
- 3. Perform evolution.
- 4. At completion of evolution, announce the JPM is complete.
- 5. Document evaluation performance.
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OPERATIONS JPM TASK BRIEFING The Shift Manager directs you to perform the SRO review of the completed LTOP Verification 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. Determine Tech Spec Action if required.
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below:
Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:
2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-152 2-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized GENERAL STANDARDS/PRECAUTIONS Perform the SRO review of the completed LTOP Verification and determine if LTOP Requirements for Unit 2 are met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
General CUES:
- Provide a Copy of 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20.
- If required prompt the candidate to identify Tech Spec and correct Data Sheet 20A after determining the error.
CS: Reviews Data Sheet 20A and determines that PORV NRV-153 is In-Operable (Xs in Circles are wrong, Empty Circles Should Have Xs).
SAT: UNSAT:
Note: Annunciator Panel 208 Drop 28 is LIT (not Clear)(See Work Management Listing - pg 2).
CS: Determines that LTOP Requirements are NOT Met.
SAT: UNSAT:
Informs Shift Manager that LTOP Requirements are NOT met.
SAT: UNSAT:
CS: Determines that Tech Spec LCO 3.4.12, Action F N/A applies (Mode 5 - One required relief is In-Operable).
SAT: UNSAT:
CUE: This JPM is complete.
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Task Briefing The Shift Manager directs you to perform the SRO review of the completed LTOP Verification 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20A. Determine Tech Spec Action if required.
To determine equipment status, use the Open Items Summary (attachment) and the Equipment Availability Table, as shown below:
Equipment Availability Table COMPONENT I.D.: DESCRIPTION: STATUS:
2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-152 2-NRV-153 Control Cold Over-Pressure Block for Cold Over Press Selector 2-NRV-153 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 2-NRV-152 EMER AIR TANK NOT Lit Drop 27 PRESSURE LOW Annunciator Panel 208 2-NRV-153 EMER AIR TANK Lit Drop 28 PRESSURE LOW 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure RCS Highest Reading Pressure 230 psig 2-NPS-121 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized Revision: 0 NRC 2016-A2-SRO.doc Page 5 of 6
- FOR TRAINING USE ONLY -
Revision: 0 NRC 2016-A2-SRO.doc Page 6 of 6
Unit 2 Open Items Summary Open Item # Component Noun System Open Item Entered 2-2016-0594 2-VTR-300 Control Room Air Temperature VCRAC Tuesday, May 22, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.7.11 2016-13357 Condition Description Notes 12-IHP-5021-IMP-001 (55384995-01) Temperature Instrument Calibration Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0600 2-NTR-12 CORE EXIT THERMOCOUPLE LOCATION F-15 NI Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.3.3 A Modes 1, 2, 3, and 4 Condition Description Notes Failed TC Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0601 2-NRV-153 PRESSURIZER PORV NRV-153 PZR Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 F N/A Modes 5 & 6 3.4.12 E N/A Mode 4 3.4.11 A N/A Modes 1, 2, and 3 Condition Description Notes Emergency Air Tank is depressurized and Isolated due to air leak at pressure connection Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0602 2-IMO-110 Safety Injection Accumulator Discharge Valve ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 1 of 3
Open Item # Component Noun System Open Item Entered 2-2016-0603 2-IMO-120 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0604 2-IMO-130 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0605 2-IMO-140 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0606 2-PP-26N NORTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 2 of 3
Open Item # Component Noun System Open Item Entered 2-2016-0607 2-PP-26S SOUTH SAFETY INJECTION PUMP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A B Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0608 2-SV-103 RHR Suction Line Relief Valve RHR Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 E N/A MODE 4 when any RCS cold leg temperature is 299°F 3.4.12 F N/A Modes 5 and 6, when the vessel head is on 5.5.6 Condition Description Notes RHR Suction Line Relief Valve failed to lift at required setpoint Valve did not Open Until 460 psig.
Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0609 2-PP-50E East CCP ECCS Monday, July 03, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A A Modes 1, 2, 3 Condition Description Notes CCP Tagged Out to Prevent Injection Required for SR 3.4.12.2 Procedure Title Drop Dead Date Open Item # Component Noun System Open Item Entered 2-2016-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 23, 2016 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 8.3.8 C Condition Description Notes RP has not completed Operability recommendation checks following I & C board replacement under WOT 55403403 Procedure Title Drop Dead Date Monday, July 03, 2016 Page 3 of 3
OPERATIONS JPM TRAINING PROGRAM ILT TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-A3 TITLE: REVISION: 0 Respond to a High SJAE Radiation Alarm Examinees Name: _________________________________________ __________
Evaluators Name: : ___________________________________________________
Date Performed: : ____________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________
Time to Complete: : ____________________________________________________
Comments:___________________________________________________________
NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 1 of 15
OPERATIONS JPM REFERENCES Procedures:
12-OHP-4024-139 ANNUNCIATOR #139 RESPONSE: RADIATION, Rev. 19 Miscellaneous
References:
TBD-2-FIG-19-19A Primary to secondary leak rate (Unit 2 at 5 SCFM), Rev. 13 TBD-2-FIG-19-19B Primary to secondary leak rate (Unit 2 at 10 SCFM), Rev. 12 TBD-2-FIG-19-19C Primary to secondary leak rate (Unit 2 at 15 SCFM), Rev. 12 TBD-2-FIG-19-19E Primary to secondary leak rate (Unit 2 at 20 SCFM), Rev. 10 TBD-2-FIG-19-19F Primary to secondary leak rate (Unit 2 at 30 SCFM), Rev. 10 TBD-2-FIG-19-19G Primary to secondary leak rate (Unit 2 at 25 SCFM), Rev. 9 TRAINING AIDS/TOOLS/EQUIPMENT NRC KA APE.037.AK3.05 Knowledge of the reasons for the following responses as they RO/SRO 3.7/4.0 apply to the Steam Generator Tube Leak:
Actions contained in the procedures for radiation Monitoring, RCS water inventory balance, S/G tube failure, and plant shutdown.
APE.037.AA2.01 Ability to determine and interpret the following as they apply RO/SRO 3.0/3.4 to the Steam Generator Tube Leak:
Unusual readings of the monitors; steps needed to verify readings 2.3.14 Knowledge of the radiation or contamination hazards that RO/SRO 3.4/3.8 may arise during normal, abnormal, or emergency conditions or activities.
2.3.14 TASKS ADM0420302 Verify Limiting Conditions for Operation are met in accordance with the Offsite Dose Calculation Manual (ODCM).
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OPERATIONS JPM HANDOUTS:
Task Briefing Copy of Data Sheet 1 of 12-OHP-4024-139 Drop 27 2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, 2-Figure 19.19e, 2-Figure 19.19f, and 2-Figure 19.19g ATTACHMENTS:
12-OHP-4024-139 Drop 27 2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, 2-Figure 19.19e, 2-Figure 19.19f, and 2-Figure 19.19g EVALUATION SETTINGS:
Classroom EVALUATOR INSTRUCTIONS NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 3 of 15
OPERATIONS JPM Give copy of Task Briefing and attachments to examinee.
Provide student with 12-OHP-4024-139 Drop 27.
2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, 2-Figure 19.19e, 2-Figure 19.19f, and 2-Figure 19.19g TASK BRIEFING:
Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900.
A RCS to Steam Generator Tube Leak is suspected. The activities from SRA-2905 have been recorded at 15 minute intervals on Data Sheet #1. The SJAE flowrate is 17 scfm.
You are the extra RO.
The US directs you to plot the data and determine the total leak rate in accordance with 12-OHP-4024-139, Drop 27. Report your results and any operational limitations required per 12-OHP-4024-139, Drop 27.
(Table for information of Proctor as to what is provided to candidate.)
Time Activity (uCi/cc) 0300 1.4e-6 0315 1.7e-6 0330 2.0e-6 0345 2.7e-6 0400 3.9e-6 0415 4.8e-6 0430 5.7e-6 0445 7.1.e-6 0500 8.1e-6 0515 8.3e-6 JPM OVERVIEW Complete Data Sheet 1 of 12-OHP-4024-139 Drop 27 for accuracy and determine required actions based upon that data.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS: Operator determines that SJAE graph for 20 scfm (17 scfm actual 2-Fig 19-19e) should be used for graphing radiation reading.
SAT: UNSAT:
COMMENT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS: Operator determines the final leakrate is 87 GPD (85-90)
SAT: UNSAT:
COMMENT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator graphs the radiation monitor data as indicated.
SAT: UNSAT:
COMMENT:
STANDARD: CS: Operator determines slope of curve indicates the rate of rise of the leakrate exceeds 30 GPD/hr.
SAT: UNSAT:
COMMENT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: CS: Operator reports the need to reduce power to less than 50% within one hour and be in MODE 3 within the next two hours.
SAT: UNSAT:
COMMENT:
Termination Cue: JPM is complete NRC 2016-A3 Revision: 0 Respond to a High SJAE Radiation Alarm NRC 2016-A3.doc Page 8 of 15
TASK BRIEFING:
Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900.
A RCS to Steam Generator Tube Leak is suspected. The BOP has taken initial action per 12-OHP-4024-139, Drop 27 to record SRA-2905 activity on Data Sheet 1 at 15 minute intervals.
You are the extra RO.
The US directs you to plot the data and determine the total leak rate in accordance with 12-OHP-4024-139, Drop 27. Report your results and any operational limitations required per 12-OHP-4024-139, Drop 27.
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OPERATIONS JPM TRAINING PROGRAM LOR/ILT TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-A4-RO TITLE: Perform the Initial Offsite Notification REVISION: 0 Examinees Name: _________________________________________ __________
Evaluators Name: : ___________________________________________________
Date Performed: : ____________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________
Time to Complete: : ____________________________________________________
Comments:___________________________________________________________
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OPERATIONS JPM REFERENCES Procedures:
PMP-2080-EPP-100 EMERGENCY RESPONSE NRC KA P2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation. (CFR: 45.11)
RO/SRO Importance 3.8/3.9 TASKS EPP0030701 Perform the Initial Offsite Notification OBJECTIVES*
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OPERATIONS JPM HANDOUTS:
Task Briefing EMD-32a Nuclear Plant Event Notification (blank form)
PMP-2080-EPP-100, Emergency Response Sections:
- Attachment 9 MSP Notification
- Attachment 12 Manual Completion of EMD Forms MIDAS Summary as part of the handout (attached)
ATTACHMENTS:
None EVALUATION SETTINGS: Classroom EVALUATION METHOD: PERFORM: SIMULATE:
EVALUATOR INSTRUCTIONS Give copy of Task Briefing to examinee.
TASK BRIEFING:
You are an extra Control Room Operator on Unit 2.
Both units are operating at 100% with DG2CD OOS.
Multiple indications and reports were received indicating a fire in the DG2AB room The Shift Manager has just declared an ALERT per Initiating Condition H-4, Fire or Explosion affecting plant operations.
No radiological release is in progress.
There are no protective action recommendations.
Classification Time is _________ (Current Time)
The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval, obtain approval from the Shift Manager, and then make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response.
Meteorological Data - Use the MIDAS Summary provided.
THIS IS A TIME CRITICAL JPM JPM OVERVIEW Given plant conditions, the operator will complete the EMD-32a, Nuclear Plant Event Notification form, obtain approval, and the MSP within 15 minutes.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval.
STANDARD: Drill box marked (for purposes of this JPM C1 Actual Event is also acceptable)
SAT: UNSAT:
STANDARD:
- C1 entered as Plant Message Number since this is the initial notification (1, CR1, or equivalent are also acceptable)
- Candidate enters name as Plant Communicator
- Control Room box marked
- CUE: If asked, Time of Communication is current time.
H4 SAT: UNSAT:
STANDARD: CS
- ALERT box MUST be marked
- Date and Time of Classification (given during the briefing) MUST be filled in SAT: UNSAT:
STANDARD: CS
- Hazards and Other Conditions affecting plant safety box marked
- H-4 MUST be filled in SAT: UNSAT:
CONTINUED ON NEXT PAGE.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: The operator should determine from the briefing that no radiological release is in progress and that no PAR is required. If clarification is requested, the evaluator should provide the cues that a release is not in progress and no PAR applies.
STANDARD: CS NO box MUST be marked SAT: UNSAT:
STANDARD: CS None box MUST be marked SAT: UNSAT:
STANDARD: Stability Class E filled in SAT: UNSAT:
STANDARD: CS Wind from 328 to 148 filled in SAT: UNSAT:
STANDARD: CS Wind speed 5.5 mph filled in (may round up to 6 mph SAT: UNSAT:
STANDARD: Precipitation No box marked SAT: UNSAT:
STANDARD: Candidate reports complete and ready for SEC/SM approval 328 148 5.5 SAT: UNSAT:
E EVALUATOR: Sign, date, and fill in time on EMD-32a.
Return the form and direct the operator to make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response.
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: Telephone communications should be simulated.
STANDARD: CS Operator identifies correct phone number for the MSP.
SAT: UNSAT:
CUE: This is Officer Smith of the Michigan State Police.
. Completion Time _________
STANDARD: CS Operator provides correct information of all items marked as critical on the EMD-32a within 15 minutes of classification time.
SAT: UNSAT:
EVALUATOR: Repeat back information given by the operator NRC 2016-A4-RO Revision: 0 Perform the Initial Offsite Notification NRC 2016-A4-RO.doc Page 6 of 9
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Operator fills in appropriate information on the attachment and requests a callback.
SAT: UNSAT:
JPM TERMINATION: When a callback has been requested and the phone call has been ended, inform the operator that the JPM is complete.
Termination Cue: Complete the EMD-32a, Nuclear Plant Event Notification form and notify of MSP within 15 minutes.
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OPERATIONS JPM TASK BRIEFING:
You are an extra Control Room Operator on Unit 2.
Both units are operating at 100% with DG2CD OOS.
Multiple indications and reports were received indicating a fire in the DG2AB room The Shift Manager has just declared an ALERT per Initiating Condition H-4, Fire or Explosion affecting plant operations.
No radiological release is in progress.
There are no protective action recommendations.
Classification Time is _________ (Current Time)
The Shift Manager directs you as the Plant Communicator to complete EMD-32a, Nuclear Plant Event Notification form for approval, obtain approval from the Shift Manager, and then make notifications to the Michigan State Police per Attachment 9 of PMP-2080-EPP-100, Emergency Response.
Meteorological Data - Use the MIDAS Summary provided.
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OPERATIONS JPM TRAINING PROGRAM ILT TIME: 20 MINUTES TITLE NUMBER AND NRC 2016-A4-SRO TITLE: Perform the duties of the Site Emergency REVISION: 1 Coordinator SRO-ONLY Approved for SRO Only JPM JPM-SRO-ADMIN JPM-TIME-CRITICAL Time Critical JPM Examinees Name: _________________________________________ __________
Evaluators Name: : ___________________________________________________
Date Performed: : ____________________________________________________
Result (Circle One): SAT / UNSAT Number of Attempts: : __________________________________________________
Time to Complete: : ____________________________________________________
Comments:___________________________________________________________
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OPERATIONS JPM REFERENCES Procedures:
PMP-2080-EPP-101 Emergency Classification, Rev. 18 PMP-2080-EPP-100 EMERGENCY RESPONSE, REV. 33 Miscellaneous
References:
TRAINING AIDS/TOOLS/EQUIPMENT NRC KA P2.4.40 Knowledge of the SRO's responsibilities in emergency plan implementation. (CFR: 45.11)
RO/SRO Importance 2.7/4.5 P2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR: 43.5 / 45.11)
RO/SRO Importance 2.3/4.1 TASKS EPP0020703 Classify an Emergency Condition.
EPP0160703 Perform the duties of the Site Emergency Coordinator.
OBJECTIVES*
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OPERATIONS JPM HANDOUTS:
Copy of current revisions of the following:
PMP-2080-EPP-101, Emergency Classification ATTACHMENTS:
Completed EMD32a Meteorological Summary EVALUATION SETTINGS:
Administrative JPM, may be evaluated in classroom setting EVALUATOR INSTRUCTIONS Give copy of Task Briefing to examinee.
TASK BRIEFING:
You are the Shift Manager Unit 2 experienced a secondary side break due to a failed open SG Safety valve on #21 SG. The Crew tripped the reactor, initiated Safety Injection, and performed actions of E-0, Reactor Trip or Safety Injection. A transition was made to E-2, Faulted SG Isolation. Actions of E-2 were completed for 21 SG. The safety valve remained open and could not be reseated. After completion of E-2, the crew transitioned to ES-1.1, SI Termination, stopped one CCP, isolated BIT injection flow, and stopped both SI pumps. Several minutes after terminating SI, RCS pressure and pressurizer level suddenly started lowering rapidly, along with a rapid increase in 21 SG level. The crew started both CCPs and SI pumps and reinitiated BIT flow based on inability to maintain pressurizer level >21% and transitioned to E-1, Loss of Reactor or Secondary Coolant, and then to E-3, Steam Generator Tube Rupture, based on uncontrolled level increase in 21 SG. The Emergency Plan has not yet been entered during the event.
You are to determine if an Emergency Classification is applicable. Review and approve EMD-32a as required.
THIS JPM IS TIME CRITICAL Classification Start Time: _____________________________
JPM OVERVIEW Operator will perform an Emergency Classification of the event based on plant conditions and verify a correctly completed EMD32a NRC 2016-A4-SRO Revision: 0 Perform the duties of the Site Emergency Coordinator NRC 2016-A4-SRO.docx Page 3 of 8
OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Provide PMP-2080_EPP-101 STANDARD:
CS: Identify a Site Area Emergency based on a combination of (EAL 2.2P OR 2.2L) AND 3.3L applies and declare a Site Area Emergency within 15 minutes SAT:
UNSAT:
COMMENT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD:
CS: Identify a Site Area Emergency based on a combination of (EAL 2.2P OR 2.2L) AND 3.3L applies and declare a Site Area Emergency within 15 minutes SAT:
UNSAT:
COMMENT:
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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Classification Completed Time: ________________________
The Operator should provide the following information to complete the EMD-32a: NOTE: If the operator provided the correct EAL And
- Current classification- Site Area Emergency Classification Provide the operator with the INCORRECTLY Completed
- , Date, and Time EMD32a and Meteorological Summary printout for review and Approval
- Site Area Emergency STANDARD: CS: Operator identifies that the completed EMD-
- Reason for classification (Fission Product Barrier Degradation) 32a was INCORRECTLY completed and provides corrections (Changes from Alert to SAE and add 3.3L to IC Number)
- Radiological Release in Progress NOTE: If the operator provided the INCORRECT EAL And Classification. Document below and repeat back the incorrect
- No Protective Action Recommendations information.
- Classification ______________
Reason for Classification _______________
IC Number __________________________
CUE: This JPM is complete.
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TASK BRIEFING:
You are the Shift Manager Unit 2 experienced a secondary side break due to a failed open SG Safety valve on #21 SG. The Crew tripped the reactor, initiated Safety Injection, and performed actions of E-0, Reactor Trip or Safety Injection. A transition was made to E-2, Faulted SG Isolation. Actions of E-2 were completed for 21 SG. The safety valve remained open and could not be reseated. After completion of E-2, the crew transitioned to ES-1.1, SI Termination, stopped one CCP, isolated BIT injection flow, and stopped both SI pumps. Several minutes after terminating SI, RCS pressure and pressurizer level suddenly started lowering rapidly, along with a rapid increase in 21 SG level. The crew started both CCPs and SI pumps and reinitiated BIT flow based on inability to maintain pressurizer level >21% and transitioned to E-1, Loss of Reactor or Secondary Coolant, and then to E-3, Steam Generator Tube Rupture, based on uncontrolled level increase in 21 SG. The Emergency Plan has not yet been entered during the event.
You are to determine if an Emergency Classification is applicable. Review and approve EMD-32a as required.
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