Text

DC Cook 2016 Administered Operating Test Admin JPMs
	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: ML16341B980; ML16341C428; ML16341C481; ML16341C543;
References
	Download: ML16341C428 (91)
	v • d • e

NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 1 of 12 CLASSROOM LESSON TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 15 MIN NUMBER AND TITLE: NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument REVISION: 0 Examinee's Name:

_________________________________________________________

Evaluator's Name:

_________________________________________________________

Date Performed:

_________________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts:

________________________________________________________

Time to Complete: :_________________________________________________________

Comments:__________________________________________________________________

___________________________________________________________________________

NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 2 of 12 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 3.5 SRO: 4.7 3.7 Task Number:

0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT Calculator Ru le r 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:

OPERATIONS JPM NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 3 of 12 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.

OPERATIONS JPM NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 4 of 12 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:

Operator enters the highest calculated QPTR (CS: Covered on Page 6) SAT: UNSAT: N/A OPERATIONS JPM NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 5 of 12 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.

OPERATIONS JPM NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 6 of 12 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

Upper Tilt Ratio 1.007 (range 1.001 to 1.022

) SAT: UNSAT:

Lower Tilt Ratio 1.0 3 4 (range 1.0 26 to 1.041) SAT: UNSAT:

CS: Operator enters the highest calculated QPTR of previous 2 values 1.0 3 4 (range 1.0 26 to 1.0 41)

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.

" 41 43 44 41 43 44 1.00 7 1.03 4 1.03 4 N/A 99 135.4 .7 312 98 134.4 .7 292 98 136.7 .7169 2.1772 91.5 135.6 .67 48 98.5 134.7 .7 313 97.5 136.2 .71 59 2.12 19 OPERATIONS JPM NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 7 of 12 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

1.02 2 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 Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 8 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.

NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 9 of 12 NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 10 of 12

NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 11 of 12 NRC 2016-A1a-RO Calculate QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-RO.doc Page 12 of 12 NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 1 of 12 TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 15 MIN NUMBER AND TITLE: NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument REVISION: 0 Examinee's Name:

_____________________________________________________

____ Evaluator's Name:

_________________________________________________________

Date Performed:

_________________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts:

_____________________________

___________________________

Time to Complete: :_________________________________________________________

Comments:__________________________________________________________________

______________________________________________________________________

_____ ___________________________________________________________________________

NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 2 of 12 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 3.5 SRO: 4.7 3.7 Task Number:

0130180201 Perform Quadrant Power Tilt Ratio Calculation TRAINING AIDS/TOOLS/EQUIPMENT Calculator Rule r 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:

NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 3 of 12 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

OPERATIONS JPM NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 4 of 12 EXPECTED ACTIONS CUES/STANDARDS ("CS" Indicates Critical Standard)

CS: Operator identifies that value was incorrectly calculated. Should be 1.03 4 resulting in excessive QPTR.

1.0 34 (range 1.0 26 to 1.041) SAT: UNSAT:

CS: Operator Determines that Acceptance Criteria is NOT Met (QPTR > 1.02) and Notifies SM SAT: UNSAT: 41 43 44 41 43 44 1.00 74 1.003 4 1.00 74 N/A 99 135.4 .7 312 98 134.4 .7 292 98 136.7 .7169 2.1772 91.5 135.6 .6 7 48 98.5 134.7 .7 313 97.5 136.2 .71 59 2.12 19 OPERATIONS JPM NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 5 of 12 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.

OPERATIONS JPM NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 6 of 12 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 wit h a 92.2% to 87.7%

power limit) SAT: UNSAT:

Also Determines that QPTR must be calculated every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , Verify )(Z F C Q is within limit., Verify )(Z F W Q is within limit, & Verify F N his within limits specified in the COLR.

SAT: UNSAT:

OPERATIONS JPM NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 7 of 12 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."

NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 8 of 12 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.

NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 9 of 12 NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 10 of 12

NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 11 of 12 NRC 2016-A1a-SRO Review QPTR with Inoperable Power Range (PR) Instrument Revision: 0 NRC 2016-A1a-SRO.doc Page 12 of 12 DATAforA1a.doc NI CALIBRATION DATA DET A 120% I in

µAmps N41 = 135.4 N42 = 13 6.6 N43 = 1 34.4 N44 = 136.7 DET B 120% I in

µAmps N41 = 135.6 N42 = 1 3 3.6 N43 = 1 34.7 N44 = 1 36.2 Verified: Print ____John Smithe

__ Sign ___

John Smithe _____ Date 5/11/2016____

NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 1 of 13 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 15 MINUTES NUMBER AND TITLE: NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors REVISION: 0 Examinee's Name: _________________________________________ __________

Evaluator's Name: : ___________________________________________________

Date Performed: : ____________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts: : __________________________________________________

Time to Complete: : ____________________________________________________

Comments:___________________________________________________________

____________________________________________________________________

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 2 of 13 REFERENCES/NRC KA/TASKS Procedures

12-OHP-4024-139 TRM 8.3.8 PMP-4030-EIS-001 PMP-6010-OSD-001 Annunciator #139 Response: Radiation Radiation Monitoring Instrumentation

Event-Initiated Surveillance Testing 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

ADM0420302 Verify Limiting Conditions for Operation are met in accordance with Technical Specifications.

Verify Limiting Conditions for Operation are met in accordance with the Offsite Dose Calculation Manual. TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing 12-OHP-4024-139, Annunciator #139 Response: Radiation Drop 2 4 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:

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 3 of 13 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.

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 4 of 13 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:

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 5 of 13 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:

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 6 of 13 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

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 7 of 13 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:

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 8 of 13 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 OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 9 of 13 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)

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 10 of 13 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (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:

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 11 of 13 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.

C UE: If required, ask "What Documentation is required?"

(to ensure PMP

-4030-EIS-001, Data Sheet 1 is initiated

).

OPERATIONS JPM NRC 2016-A1b-SRO Verify Appropriate LCO Action for Inoperable Radiation Monitors Revision: 0 NRC 2016-A1b-SRO.doc Page 12 of 13 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:

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ." (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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per ODCM Attachment 3.4 action 6 (and 12

-THI-2291-ADM-012) SAT: UNSAT: CUE: Provide AR# from Unit S upervisor as "

201 6-9999" CUE: Step 1.7 is completed and signed off.

CUE: Acknowledge Unit 1 has been notified TERMINATION CUE:

This JPM is complete.

17 Vent Stack Noble Gas Monitor VRS

-2505 Inoperable 2 Current Date Current Time

Revision: 0 NRC 2016-A1b-SRO.doc Page 13 of 13 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.

NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 1 of 9 OPERATIONS JPM NUMBER: NRC 2016-A2-RO TIME: 15 MINUTES TITLE: Perform Unit 2 LTOP Verification REVISION: 0 Examinee's Name: _________________________________________ __________

Evaluator's Name: : ___________________________________________________

Date Performed: : ____________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts: : __________________________________________________

Time to Complete: : ____________________________________________________

Comments:___________________________________________________________

____________________________________________________________________

OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 2 of 9 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:

OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 3 of 9 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 2-NRV-152 Cold Over Press 2-NRV-153 Control Selector Cold Over-Pressure Block for 2-NRV-153 Cold Over Press 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 Drop 27 2-NRV-152 EMER AIR TANK PRESSURE LOW NOT Lit Annunciator Panel 208 Dro p 28 2-NRV-153 EMER AIR TANK PRESSURE LOW Lit 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 OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 4 of 9 RCS WR Pressure 2-NPS-12 1 RCS Highest Reading Pressure 230 psig 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

.

OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 5 of 9 EXPECTED ACTIONS CUES/STANDARDS ("

C S" 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 2 0A Data Sheet 2 0B 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.

OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 6 of 9 EXPECTED ACTIONS CUES/STANDARDS ("

C S" Indicates Critical Standard)

C S: Marks page as shown [at X s] (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:

OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 7 of 9 EXPECTED ACTIONS CUES/STANDARDS ("

C S" 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)

OPERATIONS JPM NRC 2016-A2-RO Perform Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-RO.doc Page 8 of 9 EXPECTED ACTIONS CUES/STANDARDS ("

C S" 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 Complet e."

Revision: 0 NRC 2016-A2-RO.doc Page 9 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.

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 2-NRV-152 Cold Over Press 2-NRV-153 Control Selector Cold Over-Pressure Block for 2-NRV-153 Cold Over Press 2-IMO-1 28 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 Drop 27 2-NRV-152 EMER AIR TANK PRESSURE LOW NOT Lit Annunciator Panel 208 Drop 28 2-NRV-153 EMER AIR TANK PRESSURE LOW Lit 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 2-NPS-121 RCS Highest Reading Pressure 230 psig 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

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-I MO-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

NRC 2016-A2-SRO Review Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-SRO.doc Page 1 of 6 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

Examinee's Name: _________________________________________ __________

Evaluator's Name: :

___________________________________________________

Date Performed: : ____________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts: : __________________________________________________

Time to Complete: : ____________________________________________________

Comments:___________________________________________________________

____________________________________________________________________

______________________________________________________

______________

OPERATIONS JPM NRC 2016-A2-SRO Review Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-SRO.doc Page 2 of 6 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.

OPERATIONS JPM NRC 2016-A2-SRO Review Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-SRO.doc Page 3 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.

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 2-NRV-152 Cold Over Press 2-NRV-153 Control Selector Cold Over-Pressure Block for 2-NRV-153 Cold Over Press 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 Drop 27 2-NRV-152 EMER AIR TANK PRESSURE LOW NOT Lit Annunciator Panel 208 Drop 28 2-NRV-153 EMER AIR TANK PRESSURE LOW Lit 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 185 o F RCS WR Pressure 2-NPS-121 RCS Highest Reading Pressure 230 psig 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 400 o 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.

OPERATIONS JPM NRC 2016-A2-SRO Review Unit 2 LTOP Verification Revision: 0 NRC 2016-A2-SRO.doc Page 4 of 6 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

General CUES

Provide a Copy of 2

-OHP-4030-2 14-030, 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 X s). 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 m et. SAT: UNSAT:

CS: Determines that Tech Spec LCO 3.4.12, Action F applies (Mode 5 - One required relief is In

-Operable). SAT: UNSAT:

CUE: "This JPM is complete."

N/A Revision: 0 NRC 2016-A2-SRO.doc Page 5 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.

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 2-NRV-152 Cold Over Press 2-NRV-153 Control Selector Cold Over-Pressure Block for 2-NRV-153 Cold Over Press 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 Drop 27 2-NRV-152 EMER AIR TANK PRESSURE LOW NOT Lit Annunciator Panel 208 Drop 28 2-NRV-153 EMER AIR TANK PRESSURE LOW Lit 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 185 o F RCS WR Pressure 2-NPS-121 RCS Highest Reading Pressure 230 psig 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 400 o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De

-Energized

Revision: 0 NRC 2016-A2-SRO.doc Page 6 of 6 - FOR TRAINING USE ONLY

-

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-I MO-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 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

NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 1 of 15 OPERATIONS JPM TRAINING PROGRAM TITLE ILT TIME: 15 MINUTES NUMBER AND TITLE: NRC 2016-A3 Respond to a High SJAE Radiation Alarm REVISION: 0 Examinee's Name: _________________________________________ __________

Evaluator's Name: : ___________________________________________________

Date Performed: : ____________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts: : __________________________________________________

Time to Complete: : ____________________________________________________

Comments:___________________________________________________________

____________________________________________________________________

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 2 of 15 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-19-19 F Primary to secondary leak rate (Unit 2 at 30 SCFM), Rev.

10 TBD-2-FIG-19-19 G Primary to secondary leak rate (Unit 2 at 2 5 SCFM), Rev.

9 TRAINING AIDS/TOOLS/EQUIPMENT NRC KA APE.037.AK3.05 RO/SRO 3.7/4.0 Knowledge of the reasons for the following responses as they 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 RO/SRO 3.0/3.4 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak:

Unusual readings of the monitors; steps needed to verify readings 2.3.14 RO/SRO 3.4/3.8 Knowledge of the radiation or contamination hazards that 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).

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 3 of 15 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 19.19 e , 2-Figure 19.19 f , and 2-Figure 19.19 g ATTACHMENTS:

12-OHP-4024-139 Drop 27 2-Figure 19.19a, 2

-Figure 19.19b, 2

-Figure 19.19c, 2

-Figure 19.19 e , 2-Figure 19.19 f, and 2-Figur e 19.19 g EVALUATION SETTINGS:

Classroom EVALUATOR INSTRUCTIONS

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 4 of 15 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 19.19 e , 2-Figure 19.19 f , and 2-Figure 19.19 g 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 ha ve 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.

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 5 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: CS: Operator determines that SJAE graph for 20 scfm (1 7 scfm actual 2-Fig 19-19e) should be used for graphing radiation reading. SAT: UNSAT: COMMENT:

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 6 of 15 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

STANDARD: CS: Operator determines the final leakrate is 87 GPD (85-90) SAT: UNSAT: COMMENT:

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 7 of 15 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:

OPERATIONS JPM NRC 2016-A3 Respond to a High SJAE Radiation Alarm Revision: 0 NRC 2016-A3.doc Page 8 of 15 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

Revision: 0 NRC 2016-A3.doc Page 9 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. 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.

Revision: 0 NRC 2016-A3.doc Page 10 of 15 TDB-2-Figure 19-19a Revision: 0 NRC 2016-A3.doc Page 11 of 15 TDB-2-Figure 19-19b Revision: 0 NRC 2016-A3.doc Page 12 of 15 TDB-2-Figure 19-19 c Revision: 0 NRC 2016-A3.doc Page 13 of 15 TDB-2-Figure 19-19 e Revision: 0 NRC 2016-A3.doc Page 14 of 15 TDB-2-Figure 19-19f Revision: 0 NRC 2016-A3.doc Page 15 of 15 TDB-2-Figure 19-19g NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 1 of 9 OPERATIONS JPM TRAINING PROGRAM TITLE LOR/ILT TIME: 15 MINUTES NUMBER AND TITLE: NRC 2016-A4-RO Perform the Initial Offsite Notification REVISION: 0

Examinee's Name: _________________________________________ __________

Evaluator's Name: : ___________________________________________________

Date Performed: : ____________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts: : __________________________________________________

Time to Complete: : ____________________________________________________

Comments:___________________________________________________________

____________________________________________________________________

OPERATIONS JPM NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 2 of 9 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

OPERATIONS JPM NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 3 of 9 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 recommendation

s. 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

.

OPERATIONS JPM NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 4 of 9 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 "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. SAT: UNSAT:

STANDARD: CS "ALERT" box MUST be marked Date a nd T ime 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

. C1 H 4 OPERATIONS JPM NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 5 of 9 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 SAT: UNSAT: 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.

E 328 148 5.5

OPERATIONS JPM NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 6 of 9 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

OPERATIONS JPM NRC 2016-A 4-RO Perform the Initial Offsite Notification Revision: 0 NRC 2016-A4-RO.doc Page 7 of 9 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.

OPERATIONS JPM Revision: 0 NRC 2016-A4-RO.doc Page 8 of 9 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 recommendation

s. 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 9 of 9 NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 1 of 8 OPERATIONS JPM TRAINING PROGRAM TITLE ILT TIME: 20 MINUTES NUMBER AND TITLE: NRC 2016-A4-SRO Perform the duties of the Site Emergency Coordinator REVISION: 1 SRO-ONLY Approved for SRO Only JPM JPM-SRO-ADMIN JPM-TIME-CRITICAL Time Critical JPM Examinee's Name: _________________________________________ __________

Evaluator's Name: : ___________________________________________________

Date Performed: :

____________________________________________________

Result (Circle One):

SAT / UNSAT Number of Attempts: : __________________________________________________

Time to Complete: : ____________________________________________________

Comments:___________________________________________________________

____________________________________________________________________

OPERATIONS JPM NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 2 of 8 REFERENCES Procedures:

PMP-2080-EPP-101 Emergency Classification, Rev. 18 PMP-2080-EPP-100 EMERGENCY RESPONSE, REV. 3 3

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*

JPM-SR-O-E015 Perform the duties of the Site Emergency Coordinator

.

OPERATIONS JPM NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 3 of 8 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

OPERATIONS JPM NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 4 of 8 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:

OPERATIONS JPM NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 5 of 8 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:

OPERATIONS JPM NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 6 of 8 EXPECTED ACTIONS CUES/STANDARDS ("

CS" Indicates Critical Standard)

The Operator should provide the following information to complete the EMD-32a: Current classification

- Site Area Emergency

, Date, and Time Site Area Emergency Reason for classification (Fission Product Barrier Degradation)

IC Number ((EAL 2.2P OR 2.2L) AND 3.3L) Radiological Release in Progress No Protective Action Recommendations

Classification Completed Time: ________________________

NOTE: If the operator provided the correct EAL And Classification Provide the operator with the INCORRECTLY Complete d EMD32a and Meteorological Summary printout for review and Approval STANDARD: CS: Operator identifies that the completed EMD

-32a was INCORRECTLY completed and provides corrections (Changes from Alert to SAE and add 3.3L to IC Number)

SAT: UNSAT:

NOTE: If the operator provided the INCORRECT EAL And Classification. Document below and repeat back the incorrect information.

Classification ______________

Reason for Classification _________

______

IC Number __________________________

CUE: "This JPM is complete."

OPERATIONS JPM NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 7 of 8 NRC 2016-A 4-SRO Perform the duties of the Site Emergency Coordinator Revision: 0 NRC 2016-A4-SRO.docx Page 8 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

-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

ML16341C428

Text

References:

References:

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