Text

Initial Exam 2010-301 Final Administrative JPMs
	ML101590195
Person / Time
Site:	Brunswick
Issue date:	05/03/2010
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-324/10-301, 50-325/10-301
	Download: ML101590195 (102)
	v • d • e

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C002 (SRO)

LESSON TITLE: Evaluate Refueling Technical Specifications LESSON NUMBER: SOT-OJT-J SOT 1

-OJT -J P-305-CO 1 REVISION NO: 01

Evaluate Refueling Technical Specifications SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

3. This JPM may be administered in the simulator, control room, or classroom setting.

4. Ensure examinee has access to Technical Specifications, Bases, and POM documents.

Read the following to trainee.

TASK CONDITIONS:

The following plant conditions exist during a fuel shuffle on Unit Two:

- RHR Shutdown Cooling (SDC) Loop A in service

- RHR Shutdown Cooling (SDC) Loop B B under clearance

- Reactor Recirculation Loops A and B under clearance

- Fuel Pool Cooling is in service

- Supplemental Spent Fuel Pool Cooling is in service The Refuel Floor SRO requests that SDC be secured for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to support retrieving a Reactor Pressure Vessel Head nut from within the vessel using the Auxiliary Platform. (This is the jjjy only available opportunity to get the Foreign Material out of the RPV)

No work or maintenance will be performed on SDC Loop A while it is removed from service.

INITIATING CUE:

The Shift Manager has directed you to;

1. Evaluate Technical Specifications to remove Shutdown Cooling from operation for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

2. Determine if in-vessel fuel movements are allowed to continue without SDC in service after the Foreign Material has been retrieved.

SOT-OJT-JP-305-C01 Page 2 of 9 REV. 01

Refueling Technical Specifications Evaluate Refueling Evaluate ANSWER KEY Technical CONDITION REQUIRED COMPLETION Fuel Movements Specification ACTION TIME Allowed LCO 3.9.7 C. No RHR C.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from 1 YE shutdown coolant circulation discovery of no cooling by an alternate reactor coolant subsystem in method. circulation operation. AND AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months NO thereafter C.2 Monitor reactor coolant temperature. Once per hour SOT -OJT-J P-305-CO 1 SOT-OJT-JP-305-CO1 Page of 99 Page 33 of REV. 01 REV. 01

Evaluate Refueling Technical Specifications PERFORMANCE CHECKLIST NOTE: Sequence is not essential to completing the task.

TIME START: _ _ _ _ __

START:_____________

I - Obtain current revision of Unit Two Tech Specs Step 1 Current copy of Unit Two Tech Specs is obtained SAT/UNSAT*

SAT/UNSAT*

Step 2 - Determine LCO 3.9.7 applies to current plant conditions (may use TOC to determine)

LCO 3.9.7 determined to be applicable to current plant conditions.

CRITICAL STEP*

CRITICAL STEP* ** SAT/UNSAT*

SATIUNSAT*

Step 3 - Determine LCO 3.9.7 requires one RHR shutdown cooling subsystem to be Operable and in operation Determine that LCO 3.9.7 requires one RHR subsystem to be Operable and in operation.

SATIU NSAT*

SAT/UNSAT*

Step 4 - Determine LCO 3.9.7 is modified by a note allowing the required RHR shutdown cooling subsystem to be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

Determine that LCO 3.9.7 is modified by a note aI/owing allowing the required RHR shutdown cooling subsystem to be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in a 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period SATIU NSAT*

SAT/UNSAT*

NOTE: Candidate may propose allowing SDC removal from service for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months without entering the Tech Spec ACTION statement.

PROM PT:

PROMPT: If necessary, Direct candidate to address Technical Specifications for removing SDC from service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SOT-OJT-JP-305-COl SOT -OJT-J P-305-CO 1 Page 4 4 of 9 REV. 01

Evaluate Refueling Technical Specifications Step 5 - Determine LCOLCD 3.9.7 will not be met if RHR shutdown cooling is removed from service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (more than the allowable two hour time)

Determine that LCO 3.9.7 will not be met if RHR shutdown cooling is removed seivice for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (more than the allowable two hour time) from service

CRITICAL

CRITICAL STEP* ** SAT/UNSAT*

SATIUNSAT*

Step 6 - Determine LCO LCD 3.9.7 Condition A does not apply because the RHR shutdown cooling loop is only being removed from service and will not be made inoperable Determines LCO 3.9.7 Condition A does not apply

CRITICAL STEP*

CRITICAL STEP* SAT/UNSAT*

SAT/UNSAT*

Step 7 - Determine LCO LCD 3.9.7 Condition B does not apply since Condition A does not apply.

LCD 3.9.7 Condition B does not apply Determine LCO

CRITICAL STEP* SAT/UNSAT*

CRITICAL SATIUNSAT*

Step 8 - Determine LCO LCD 3.9.7 Condition C does apply since no RHR shutdown cooling subsystem will be in operation Determine that LCO 3.9.7 Condition C does apply

CRITICAL STEP*

CRITICAL STEP* ** SAT/UNSAT*

SATIUNSAT*

Step 9 - Determine required action C.1 applies and requires verification of reactor coolant circulation by an alternate method 1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Determine that required action C. 1 lapplies applies and requires verification of reactor coolant circulation by an alternate method 1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter

CRITICAL STEP* ** SAT/UNSAT*

SATIUNSAT*

10 Step 10 - Determine required action C.2 also applies and requires monitoring of reactor coolant temperature once per hour C. 2 applies and requires monitoring of reactor Determine that required action C.2 coolant temperature once per hour

CRITICAL STEP* ** SAT/UNSAT*

SOT-DJT-JP-305-C01 SOT -OJT-J P-305-CO 1 Page 5 of 9 REV. 01

Evaluate Refueling Technical Specifications NOTE: Candidate must evaluate RHR system operability and determine not in operation sUN Operable will still allow for in-vessel while still invessel fuel movement during high water level Iev9 conditions.

Step 11 - Determine if in-vessel fuel movement is still allowed.

Determines in-vessel fuel movement is still allowed.

CRITICAL STEP*

CRITICAL STEP* ** SAT/UNSAT*

SATIUNSAT*

Step 13 - Inform Shift Manager of results.

SM notified.

SAT/U NSAT*

SAT/UNSAT*

TERMINATING CUE: When the results are reported to the SM this JPM is complete.

TIME COMPLETED: _ _ _ _ __

COMPLETED:______________

- Comments required for any step evaluated as UNSAT.

SOT-OJT-JP-305-CO1 SOT -OJT-J P-305-CO 1 Page 6 of 9 REV. 01

Evaluate Refueling Technical Specifications LIST OF REFERENCES RELATED TASKS:

342 000 B3 02 342000 Approve requests to remove plant equipment from operation.

K/A REFERENCE AND IMPORTANCE RATING:

KIA Generic Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.

RO/SRO RO I SRO 2.8/3.9 2.8 I

3.9 REFERENCES

Unit 2 Technical Specifications Amendment 233 OAP-22 TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2 Supp. 1):

Generic - Conduct of Operations REASON FOR REVISION:

K/A reference, which had changed in supplement 1.

Revised to the proper KIA SOT-OJT-JP-305-C01 Page 77 of 99 REV. 01

Evaluate Refueling Technical Specifications Time Required for Completion: .2!L 30 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual lX Unit: _2_

2 Setting: In-Plant Simulator Admin X X

Time Critical: Yes No X

-2L Time Limit N/A Alternate Path: Yes No X

--2L EVALUATION Trainee:

JPM: Pass _ _ Fail _ _

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure Revision? Yes No _____

(Each Student should verify one JPM per evaluation)

Comments:

Evaluator Signature: _____________________________ Date: ___________

Date:_______________

SOT-OJT-JP-305-C01 Page 8 of 9 REV. 01

TASK CONDITIONS:

The following The following plant plant conditions conditions exist exist during during aa fuel fuel shuffle shuffle on on Unit Unit Two:

Two:

- RHR Shutdown RHR Shutdown Cooling Cooling (SDC) Loop A (SDC) Loop A in in service service RHR Shutdown Cooling RHR Shutdown Cooling (SDC)

(SDC) Loop Loop B B under under clearance clearance

- Reactor Recirculation Loops A and B Reactor Recirculation Loops B under under clearance

- Fuel Pool Cooling Fuel Pool Cooling is is in in service

- Supplemental Spent Supplemental Spent Fuel Fuel Pool Pool Cooling Cooling is is in in service service The Refuel Floor SRO requests that SDC be secured for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to support retrieving Reactor Pressure Vessel Head nut from within the vessel using the Auxiliary Platform. (This a Reactor is the only is Qjjy available opportunity to get the Foreign Foreign Material Material out of the RPV)

RPV)

No work or maintenance will be performed on SDC Loop A while it is removed from service.

INITIATING CUE:

The Shift Manager has directed you to;

1. Evaluate Technical Specifications to remove Shutdown Cooling from operation for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

2. Determine if in-vessel fuel movements are allowed to continue without SDC in service after the Foreign Material has been retrieved.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE NRCADMIN NRC ADMIN EP (SRO)

LESSON TITLE: Classify An Emergency Per PEP-02.1.

LESSON NUMBER: SOT-ADM-JP-301-A15 SOT-ADM-JP-301-A 15 REVISION NO: 02

\ji V

Classify An Emergency Per PEP-02.1.

SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not read to performer)

1. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the performer.

2. The examinee will be provided a copy of OPEP-02.1 flowchart.

3. A copy of OPEP-02.2.1, Emergency Action Level Technical Bases, should be available if requested.

4. A clock must be available in the classroom and visible to examiner and examinees.

5. Copies of all remaining PEPs should be available upon request.

6. Task standards (Le. (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.

7. Emphasize to candidates that this is a Time Critical JPM and that following cue sheet review the evaluator will designate the START TIME on the board and stop the JPM at the applicable critical time.

SOT-ADM-JP-301-A15 SOT-AOM-JP-301-A 15 Page 2 of 8 REV. 02

Classify An Emergency Per PEP-02.1.

Read the following to the JPM JPM performer.

TASK CONDITIONS:

- This is aa Time Critical JPM**

Time begins when directed by the evaluator

1. Unit One is operating at 100%

100% power.

100% power with DG4 under clearance when the following

2. Unit Two is operating at 100%

event occurs (consider all items that exceed EAL thresholds occur at the same time).

Unit Two Event Description A seismic event with a magnitude of 0.12g is felt on plant site and is verified I validated by the National Earthquake Center results in aa loss of Corporate Telephone Communications System (Voicenet), Commercial Telephones, and NRC Emergency Telecommunications System.

The Main Turbine Trips and a majority of the control rods remain withdrawn.

A Manual Scram has been inserted, the Mode Switch has been placed in Shutdown, ARI has been initiated, and reactor power indicates 20%.

LEP-02 (Alternate Control Rod Insertions) actions and SLC injection are in progress.

Current indicated reactor power is 12%.

Reactor Water level is being maintained in a band of +60 to +90 inches.

Reactor Pressure is being controlled by EHC at 945 psig.

NO radiological releases are in progress at this time.

There are no indications of an Onsite Security Event.

INITIATING CUE:

You are to evaluate the above event as the Control Room Site Emergency Coordinator (SEC) and determine the highest required classification including the EAL Identifier for Unit Two ONLY:

1. Write the required Classification along with the EAL identifier in the table below.

2. Raise your hand when complete to have the evaluator stop the evaluation Time and collect your cue sheet.

CLASSIFICATION EAL IDENTIFIER SOT-ADM-JP-301-A SOT.-ADM-JP-301-A15 15 Page 3 of 8 REV. 02

PEP-02. 1.

Classify An Emergency Per PEP-02.1.

ANSWER KEY CLASSIFICATION EAL IDENTIFIER Site Area Emergency SS2. I SS2.1 SOT-ADM-JP-301-A15 SOT -ADM-JP-301-A 15 Page 4 of 8 REV. 02

Classify Classify An Emergency Per An Emergency Per PEP-02.1.

PEP-02.1.

PERFORMANCE CHECKLIST PERFORMANCE CHECKLIST NOTE: Sequence NOTE: Sequence is is assumed assumed unless unless denoted denoted in in the the Comments.

Comments.

Step 11 - Obtain Step - Obtain aa current revision of PEP-02.1 ifif required.

of PEP-02.1 Revision of Current Revision of PEP-02. I1 obtained.

SATIU NSAT*

SATIUNSAT*

PROMPT: Ensure aa clock is visible for candidates. Announce and Write the Start Time on on the board.

Add 15 15 minutes to the Start Time and write that in the JPM Completion Time. IfIf all candidates have not Declared aa classification, this is the time to STOP all work, put pencils/pens down, remaining cue sheets.

down, and collect all remaining IiINOTE:

NOTE: Declaration of event must be made in 15 minutes from the Start Time. I TIME START _ _ _ __

NOTE: Loss of Corporate Telephone Communications System (Voicenet), Commercial Telephones, Tephones, and NRC Emergency Telecommunications System does not reach EAL classification .threshold.

Step 2 - Determine required Classification threshold and associated EAL Number(s) o Alert - HA 1. 1 Alert-HAI.I Seismic event identified by any two of the following:

- Earthquake felt in plant

- National Earthquake Center AND Control Room indication of degraded performance of systems required for the safe shutdown of the plant (ATWS provides this)

Seismic event> Operating Basis Earthquake (0.08 g) per analysis SATIU NSAT*

SAT/UNSAT*

SOT-ADM-JP-301-A SOT-ADM-JP-301-A15 15 Page 55 of 88 Page REV. 02 REV.

Classify An Emergency Per PEP-02.1.

NOTE: Automatic Scram fails to shutdown the reactor and manual actions taken from the control console are not successful in shutting down.the down the reactor.

Step 3 - Determine required Classification threshold and associated EAL Number(s) o Site Area Emergency - SS2. 5S2. 1I Automatic scram fails to reduce reactor power << 2% (APRM downscale)

AND Manual scram actions taken at the reactor control console (Manual PBs, Mode Switch, ARI) do not shutdown the reactor as indicated by reactor power> 2%

- CRITICAL STEP**

- CRITICAL STEP** SAT!UNSAT*

SA TlUNSAT*

DECLARATION TIME _ _ __

Step 4 - Classification made within required the required time (Declaration Time minus Start Time<

Time ~ 15 minutes).

o Classification declared ~ < 15 minutes of Start Time.

- CRITICAL STEP**

- CRITICAL STEP** SAT/UNSAT*

SAT/UNSAT*

TERMINATING CUE: When the event is classified with applicable EAL identifier(s) in the table, this JPM is complete.

TIME COMPLETED _ _ _ __

NOTE: Comments required for any step evaluated as UNSAT.

NOTE:

SOT-ADM-JP-301-A SOT-ADM-JP3O1-A15 15 Page 6 of 8 REV. 02

Classify An Emergency Per PEP-02.1.

RELATED TASKS:

344256B502 Direct Initial Emergency Actions Including Emergency Classification per 3442568502 OPEP-02.1 KIA REFERENCE AND IMPORTANCE RATING:

GEN 2.4.29 3.1/4.4 Knowledge of the Emergency Plan

REFERENCES:

OPEP-02.1, Rev 51 TOOLS AND EQUIPMENT:

None.

ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2., Supp.1): Supp.l):

Admin - Emergency Procedures 1

/ Plan REASON FOR REVISION:

2010-1 NRC License Exam - Modified to reflect NEI 99-01 implementation.

SOT-ADM-JP-301-A15 SOT-ADM-JP-301-A 15 Page 7 of 8 REV. 02

Classify An Emergency Per PEP-02.1.

Validation Time: 15 15 Minutes (approximate).

Time Taken: ----

APPLICABLE METHOD METHOD OF TESTING Performance: Simulate Actual X Unit: 22 Setting: In-Plant Simulator Admin X Time Critical: Yes X No Time Limit 15 mm 15 min Alternate Path: Yes No X EVALUATION Performer:

Performer: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass Fail _ _

Remedial Training Required: Yes No _ _

Comments:

Comments reviewed with Performer Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ __ Date:___________

Date: ----

SOT-ADM-JP-301-A SOT-ADM-JP-301-A15 15 Page 8 of 8 REV. 02

TASK CONDITIONS:

- This is aa Time Critical JPM**

JPM**

Time begins when directed by the evaluator

1. Unit One is operating at 100%

1. 100% power.

100% power with DG4 under clearance when the following

2. Unit Two is operating at 100%

event occurs (consider all items that exceed EAL thresholds occur at the same time).

Unit Two Event Description A seismic event with a magnitude of 0.12g is felt on plant site and is verified I/ validated by the National Earthquake Center results in a loss of Corporate Telephone Communications System (Voicenet), Commercial Telephones, and NRC Emergency Telecommunications System.

The Main Turbine Trips and a majority of the control rods remain withdrawn.

A Manual Scram has been inserted, the Mode Switch has been placed in Shutdown, ARI has been initiated, and reactor power indicates 20%.

LEP-02 (Alternate Control Rod Insertions) actions and SLC injection are in progress.

Current indicated reactor power is 12%.

Reactor Water level is being maintained in a band of +60 to +90 inches.

Reactor Pressure is being controlled by EHC at 945 psig.

NO radiological releases are in progress at this time.

There are no indications of an Onsite Security Event.

INITIATING CUE:

You are to evaluate the above event as the Control Room Site Emergency Coordinator (SEC) and determine the highest required classification including the EAL Identifier for Unit Two ONLY:

1. Write the required Classification along with the EAL identifier in the table below.

2. Raise your hand when complete to have the evaluator stop the evaluation Time and collect your cue sheet.

CLASSIFICATION EAL IDENTIFIER

CAROLINA POWER POWER & & LIGHT LIGHT COMPANY BRUNSWICK TRAINING SECTION BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE JOB MEASURE IN-PLANT NRC ADMIN EC (ROISRO)

(RO/SRO)

LESSON TITLE: Develop a Clearance Boundary - RBCCW Pump 2C.

REVISION REVISION NO:

NO: 01

Develop aa Clearance Develop Boundary - RBCCW Clearance Boundary - Pump 2C.

RBCCW Pump 2C.

SAFETY CONSIDERATIONS:

None None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.

1.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, 1021, Appendix E, or similar to the trainee.

3. If desired, the evaluator may provide the examinee with aa copy of OPS-NGGC-1 OPS-NGGC-1301, 301, 20P-21, and the referenced prints.

0-02538 Sheets 1

4. The evaluator should have available copies of prints D-02538 & 2 and I &

LL-09241 sheets 88 & & 24 to support performance of JPM, or perform JPM in a location where aa print machine is available.

OPS-NGGC-1 301 with "N/A"

5. Provide examinee a marked up copy of Attachment 4 of OPS-NGGC-1301 N/A in the Clearance No. and Action column.

Read the following to trainee.

TASK CONDITIONS:

1. You are an operator in the Work Control Center. PASSPORT (Equipment Tag Out) is not available for use. No historical clearances are available for review.

2. A Clearance has been requested by maintenance to place RBCCW Pump 2C under clearance for pump packing replacement.

3. RBCCW Pumps 2A and 2B will remain running.

INITIATING CUE:

The WCC SRO directs you you to propose a Clearance Boundary for RBCCW Pump 2C by completing completing Attachment Attachment 44 of OPS-NGGC-1 301, Equipment of OPS-NGGC-1301, Equipment Clearance procedure.

Clearance procedure.

LOT -OJT-J P-20 1-E04 LOT-OJT-JP-201-E04 Page 22 Page REV. 01 REV. 01

Develop aa Clearance Develop Clearance BoundaryBoundary - RBCCW

- RBCCW Pump Pump 2C. 2C.

ANSWER KEY ANSWER KEY ATTACHMENT 44 ATTACHMENT of 11 Sheet 11 of Sheet OPERATIONS CLEARANCE OPERATIONS CLEARANCE TAG TAG SHEET SHEET Clearance No.

Clearance No. N/A N/A PAGE _1_of_1 PAGE 1 of 1 INT NT NAMENAME (PRINT)

(PRINT) INT NAME (PRINT)

NT NAME (PRINT)

Independent Independent Verification Required?

Required? Yes/No Yes/No IfIf No, No, N/A N/A the the Blocks Blocks Seq Seq Action Type Id Tag Id Position Equipment/Component EquipmenUComponent Completed By By IV IV By By 11 N/A CIT 2-RCC-CS-449 OFF or RBCCW Pump 2C HUNG Control Switch 2 N/A RED 2-2XE-EA7-52 OPEN or RBCCW Pump 2C **

OFF Circuit Breaker 33 N/A RED 2-RCC-V34 CLOSED RBCCWPumpC RBCCW Pump C **

Discharge_Valve Discharge Valve 3 N/A RED 2-RCC-V30 CLOSED RBCCW Pump C **

Suction_Valve Suction Valve 4 N/A RED 2-RCC-V128 OPEN RBCCW Pump C Suction Drain Valve **

4 N/A RED 2-RCC-V129 OPEN RBCCW Pump C C Discharge Drain_Valve Drain Valve 4 N/A RED 2-RCC-V301 OPEN RBCCW Pump C Casing **

Vent_Valve Vent Valve Sequence must have either switch off or breaker open prior to operating discharge/suction discharge/suction valves, and discharge/suction discharge/suction valves closed before operating drain/vent valves.

Minimum requirements for satisfactory boundary are breaker, discharge valve, suction valve, at least one drain valve, and vent valve.

LOT -OJT-JP-201-E04 LOT-OJT-JP-201--E04 Page 33 Page REV. 01 REV. 01

Develop aa Clearance Develop Boundary - RBCCW Clearance Boundary - RBCCW PumpPump 2C.

2C.

PERFORMANCE CHECKLIST PERFORMANCE IiINOTE NOTE: IfIf desired, desired, the examiner may provide providea a copy OPS-NGGC-1 OPS-NGGC-1301301 to the exam inee examinee.

NOTE: Sequence is NOTE: is assumed unless denoted denoted in in the Comments.

Step 11 - Obtain aa current revision of OPS-NGGC-1 OPS-NGGC-1301. 301.

Current Revision of OPS-NGGC-1301 obtained.

SATIUNSAT*

SAT/UNSAT*

TIME START TIME START _ _ _ __

NOTE: If desired, the examiner may provide a copy of the required prints to the the (D-02538, Sheets 11 & 2, LL-9241, Sheets 8 & 24) and 20P-21 examinee (0-02538, lineups.

NOTE: CITs can have position OFF or In-Place I/ HUNG (D-02538, Sheets 11 & 2, LL-09241, Sheets 8 & 24).

Step 2 - Obtain copies of required prints (0-02538, D-02538, Sheets 1I &

Drawings 0-02538, & 2, LL-09241, Sheets 8 && 24 obtained.

SAT/U NSAT*

SAT/UNSAT*

Step 3 - Identify control switch 2-RCC-CS-449 should be placed to OFF.

Determine 2-RCC-CS-449 should be placed to OFF.

SATIUNSAT*

SAT/UNSAT*

Step 4 - Identify

- Identify breaker breaker 2XE Compt EA7 EA7 should be placed to OFF.

be placed Determine 2XE Compt EA 77 should be placed to OFF.

to OFF.

- ** SAT/UNSAT*

- CRITICAL STEP ** SAT/UNSAT*

LOT -OJT-JP-201-E04 LOT-OJT-JP-201-E04 Page 44 Page REV. 01 REV. 01

Develop aa Clearance Boundary - RBCCW Pump 2C.

NOTE: Sequence of suction or discharge valve closing .is is not critical so long as the de:..energized.

pump motor is de-energized.

Step 5 - Identify discharge valve 2-RCC-V34 should be closed.

Determine 2-RCC-V34 should be closed.

- CRITICAL STEP ** ** SATIUNSAT*

SAT1UNSAT*

Step 6 - Identify suction valve 2-RCC-V30 should be closed.

Determine 2-RCC-V30 should be closed.

- CRITICAL STEP ** SATIUNSAT*

- SAT/UNSAT*

NOTE: Either2-RCC-V128or Either 2-RCC-V128 or 2-RCC-V129is not required to meet critical. Both are notrequired 2-RCC-V129 is critical.

critical task standards.

NOTE: Sequence of of drain or vent valve opening is not critical.

Step 7 - Identify drain valve 2-RCC-V128 should be open.

2-RCC-V1 28 should be open.

Determine 2-RCC-V128

- ** SATIUNSAT*

- CRITICAL STEP ** SAT/UNSAT*

Step 8 - Identify drain valve 2-RCC-V129 should be open.

Determine 2-RCC-V129 should be open.

- ** SATIUNSAT*

- CRITICAL STEP ** SAT/UNSAT*

Step 9 - Identify vent valve 2-RCC-V301 should be open.

Determine 2-RCC-V301 should be open.

- SATIUNSAT*

CRITICAL STEP ** SAT/UNSAT*

LOT -OJT-J P-20 1-E04 LOT-OJT-JP-201-E04 Page 5 REV. 01

Develop a Clearance Boundary - RBCCW Pump 2C.

10 Step 10 - Submit proposed boundary to WCC SRO.

Proposed boundary submitted to wee WCC SRO.

SATIU NSAT*

SAT/UNSAT*

TERMINATING CUE: When the proposed boundary. boundary has been submitted, thisJPM this JPM is complete. .. ..

TIME COMPLETED _ _ _ __

- Comments required for any step evaluated as UNSAT.

-OJT-JP-201-E04 LOT-OJT-JP-201-E04 LOT Page 6 REV. 01

Develop a Clearance Boundary - RBCCW Pump 2C.

RELATED TASKS:

299020B301, Develop A Clearance per OPS-NGGC-1301 OPS-NGGC-1 301 KIA REFERENCE AND IMPORTANCE RATING:

2.2.13 (4.1/4.3)

Knowledge of tagging and clearance procedures

REFERENCES:

OPS-NGGC-1 301 OPS-NGGC-1301 20P-21 D-02538, Sheets 11 & 2 0-02538, LL-09241, Sheets 8 && 24 TOOLS AND EQUIPMENT:

Referenced prints and procedures.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

A.2 - Equipment Control REASON FOR REVISION:

NGGC-1 301, Attachment 4.

Corrected typos and added NGGC-1301, LOT-OJT-JP-201-E04 LOT -OJT-J P-20 1-E04 Page 7 REV. 01

Develop aa Clearance Develop Boundary - RBCCW Clearance Boundary - RBCCW Pump Pump 2C.

2C.

Time for Completion:

Required for Time Required Completion: ~ 20 Minutes (approximate).

Minutes (approximate).

Time Taken:

Time Taken: ------

APPLICABLE METHOD APPLICABLE METHOD OF OF TESTING TESTING Performance:

Performance: Simulate Simulate X Actual Actual Unit:

Unit: 22 Setting:

Setting: In-Plant In-Plant Simulator Admin _X:...:-__

X Time Critical: Yes No No X X Time Time Limit Limit N/A N/A Alternate Path: Yes No ~X EVALUATION Trainee: - - - - - - - - - - - - - - - - - - - - - - - - - - -

JPM: Pass _ _ Fail _ _

Remedial Training Required: Yes No _ _

Did Trainee Verify Procedure? Yes _ _ No _ __

(Each Student should verify one JPM per evaluation set)

Comments:

Comments Comments reviewed reviewed with with Student Student Evaluator Evaluator Signature:

Signature: Date:___________

Date: -----

LOT-OJT-JP-201-E04 LOT-OJT-JP-201-E04 Page 88 Page REV. 01 REV. 01

ATTACHMENT 4 Sheet I10f of I1 Operations Clearance Checklist Clearance No__________________

Clearance No. - - - - - - - -

Page _ _ of _ _

Page_of Checklist Type: Hang; Hang: Lift; Uft; Boundary Change (Circle one)

INT NAME (FRINT)(PRINT) INT NAME (PRINT)

" Independent Required? YE&NO Veriiication R,equired?

independent Verficticn r'lI.A. Ule

'YESINO Iff NO, N/A ciocics the Blocks Seq Action Type Tag idId Position Equipment/Component Completed. Verified Verified By By ..

Continued Y lI N QARECORD QA RECORD I OPS-NGGC-'130 OPS-NGGC-i 3011 Rev. 20 121 Page 95 of '121

TASK CONDITIONS:

1. You are an operator in the Work Control Center. PASSPORT (Equipment Tag Out) is not available for use. No historical clearances are available for review.

2. A Clearance has been requested by maintenance to place RBCCW Pump 2C under clearance for pump packing replacement.

3. RBCCW Pumps 2A and 2B will remain running.

INITIATING CUE:

The WCC SRO directs you to propose a Clearance Boundary for RBCCW Pump 2C by completing Attachment 4 of OPS-NGGC-1301, OPS-NGGC-1 301, Equipment Clearance procedure.

ATTACHMENT I1 ATTACHMENT CC Continuous Continuous Page Page 11 of of 22 Use Use Reactor Building Building Closed Cooling Water Closed Cooling Water System System Electrical Electrical Lineup Lineup PERSON(S) PERFORMING OR VERIFYING LINEUP AND INITIALS INITIALS (PRINT)

REMARKS: DOCUMENT any components NOT in required position and reason below. Page may be duplicated as necessary.

Started: Date _ _ _ _ _ _ _ __

Date Time Time _ _ _ _ _ _ _ __

Completed: Date Date _ _ _ _ _ _ _ __ Time Time _ _ _ _ _ _ _ __

Approved by: /

SRO Date Time 2OP-21 120P-21 Rev. 65 Page 49 of 79 )

ATTACHMENT 1 I Page2of2 Page 2 of 2 Reactor Building Closed Cooling Water System Electrical Lineup Number Description Position!

Position/ Checked Indication 120V AC Distribution Panel2A Control Building - Emergency 120V

- Panel 2A - EI23'

- El 23 - Cable Spread Area 16 CRD Pump 2A Cooling Water Inlet Valve ON RCC-V74 Solenoid 24 RBCCW Discharge Header Pressure Switch ON RCC-PS-672 26 RBCCW Inlet To Penetration Cooling System ON Valve RCC-V18S RCC-V1 85 Solenoid 12OVAC Control Building - Emergency 120V

- Panel 2B - EI23' AC Distribution Panel2B - El 23 - Cable Spread Area 16 CRD Pump 2B Cooling Water Inlet Valve ON RCC-V73 Solenoid 24 RBCCW Inlet To Water Chiller Isolation Valve ON RCC-V51 Solenoid RCC-VS1

- 12OVAC Reactor Building - Emergency 120V Panel 2A-RX - EI20' AC Distribution PaneI2A-RX - El 20 - North - CRD-HCU Area 29 RCC-V54 DWEDT Cooler Inlet Isolation Valve RCC-VS4 ON Solenoid Reactor Building - 480V MCC 2XC - EI

- - El 20' 20 - East DT6 RBCCW Drywell Supply Header Valve, ON RCC-V52 RCC-VS2 DT7 RBCCW Drywell Discharge Header Valve, ON RCC-V28 Reactor Building - 480V MCC 2XF - EI

- - El SO' 50 - East ED7 RB Closed Cooling Water Pump B B ON Reactor Building - 480V MCC 2XE - EI

- - El SO' 50 - West EAI EA1 RB Closed Cooling Water Pump A ON 0.

(7) A7 J RB Closed Cooling Water Pump C ON Radwaste Building - MCC RWD- EI

- El 23' 23 - South BR9 RBCCW Pump 2D ON Radwaste Building - Between FDF Area and Waste Precoat Area- EI

- El 23' 23 2-RCC-2D-PMP-DIS RBCCW Pump 2D Disconnect Switch OFF 20P-21 120P-21 65 Rev. 55 791 Page 50 of 79

ATTACHMENT 2 C C

Continuous Page 1 1 of 2 Use Reactor Building Closed Cooling Water System Panel Lineup PERSON(S) PERFORMING OR VERIFYING LINEUP AND INITIALS (PRINT)

REMARKS: posftion and reason DOCUMENT any components NOT in required position below. Page may be duplicated as necessary.

Started: Date Date _ _ _ _ _ _ _ __ Time _ _ _ _ _ _ _ __

Completed: Date Date _ _ _ _ _ _ _ __ Time _ _ _ _ _ _ _ __

Time Approved by:

Approved by:

I SRO Date Time 20P-21

\20P-21 Rev. 65 791 Page 51 of 79

ATTACHMENT 2 Page 2 of 2 Reactor Building Closed Cooling Water System Panel Lineup Number Description Position!

Position/ Checked Indication

- - El 49 - Control Room Control Building - RTGB Panel XU2 - EI49' -

RCC-CS-447 RBCCW Pump 2A OFF RCC-CS-448 RBCCW Pump 2B OFF RCC-CS-449 RBCCW Pump 2C OFF RCC-V51 RBCCW to Sample Cooler OPEN RCC-V185 RBCCW to Pen Clg CIg OPEN RCC-SV-1222B RBCCW Sample Valve from Recirc Pump A OPEN (Pen. X77-B)

RCC-SV-1222C RBCCW Sample Valve from Recirc Pump B B OPEN (Pen. X77-C)

RCC-V28 RBCCW to OW DW 1501 Isol Vlvs OPEN RCC-V52 RBCCW to OW DW 1501 Isol Vlvs OPEN Radwaste Control Room - Panel HB9 RCC-V75 Cooling Wtr Sply OPEN 1 220P-21 0 P-21 Rev. 65 791 Page 52 of 79

ATTACHMENT ATTACHMENT 33 CC Continuous Continuous Page 11 of Page of 22 22 Use Use Reactor Building Reactor Closed Cooling Building Closed System Valve Lineup Cooling Water System Lineup PERSON(S) PERFORMING OR VERIFYING LINEUP AND INITIALS INITIALS (PRINT)

REMARKS: DOCUMENT any components NOT in required position and reason below. Page may be duplicated as necessary.

Started: Date _ _ _ _ _ _ _ __

Date Time Time _ _ _ _ _ _ _ __

Completed: Date _ _ _ _ _ _ _ __

Date Time Time _ _ _ _ _ _ _ __

Approved by: /

SRO Date Time 2OP-21 120P-21 Rev. 65 791 Page 53 of 79

ATTACHMENT 3 Page 2 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position?

Position/ Checked Indication Reactor Building - North RHR Room - EI-17'

- - El North RCC-V76 RBEDT Cooler Inlet Air Operated Valve CLOSED RCC-V76 RBEDT Cooler Inlet Air Operated Valve Manual NEUTRAL Actuator RIA-IV-21 5 RIA-IV-215 Instrument Air Isolation Valve To RCC-V76 OPEN RIA-IV-1 15 RIA-IV-115 Instrument Air Supply Valve To RCC-V76 OPEN RCC-V297 RBEDT Cooler Inlet Isolation Valve OPEN RCC-V98 RBEDT Cooler Shell Side Drain Valve CLOSED RCC-V5 RBEDT Cooler Outlet Throttle Valve LOCKED OPEN RCC-V97 RBEDT - Cooler Outlet Test Valve

- CLOSED RCC-FE-2258-1 High Pressure Root Valve To RCC-FE-2258 CLOSED RCC-FE-2258-2 Low Pressure Root Valve To RCC-FE-2258 CLOSED Reactor Building - Northeast Pipe Chase - EI

- - El 20' 20 - Northeast RCC-FE-1822-1 RCC-FE-1 822 High Pressure Root Valve To RCC-FE-1822 CLOSED RCC-FE-1822-2 RCC-FE-1 822 Low Pressure Root Valve To RCC-FE-1822 CLOSED RCC-FE-2257-1 RCC-FE-2257 -1 High Pressure Root Valve To RCC-FE-2257 CLOSED RCC-FE-2257-2 RCC-FE-2257 -2 Low Pressure Root Valve To RCC-FE-2257 CLOSED Reactor Building - North RHR Pump Room (Overhead) -EI-17

- -El -17 RIA-lV-1 14 RIA-IV-114 Instrument Air Supply Valve To RCC-V75 OPEN RIA-IV-214 Instrument Air Isolation Valve To RCC-V75 OPEN RIA-V401 Instrument Air Root Valve to RCC-V75 OPEN RCC-V6 RBCCW Return From Radwaste Isolation Valve OPEN Reactor Building - CRD Pump Area - EI-17'

- - El South RCC-V144 CRD Pump B B Cooling Water Inlet Test Valve CLOSED RCC-V73 CRD Pump B Cooling Water Inlet Air Operated CLOSED Valve RCC-V73 CRD Pump B Cooling Water Inlet Air Operated NEUTRAL Valve Manual Actuator 20P-21 120P-21 Rev. 65 79 Page 54 of 791

ATTACHMENT 33 ATTACHMENT Page Page 33 ofof 22 22 Building Closed Reactor Building Cooling Water Closed Cooling Water System System Valve Valve Lineup Lineup Number Number Description Description Position!

Position/ Checked Indication Indication Reactor Building - CRD Reactor Pump Area - El CRD Pump - South EI-17' - South RCC-U-V4 RCC-U-V4 Pump BB Outboard CRD Pump CRD Outboard Bearing Bearing Cooling Cooling OPEN OPEN Isolation Valve Isolation RCC-U-V5 CRD Pump BB Inboard CRD Bearing Cooling Inboard Bearing Cooling Isolation Isolation OPEN OPEN Valve RCC-U-V6 CRD Pump B B Lube Oil Cooling Isolation Valve OPEN RCC-V142 CRD Pump B B Cooling Water Outlet Test Valve CLOSED RCC-V7 CRD Pump B B Cooling Water Outlet Valve OPEN RCC-V295 CRD Pump B B Cooling Water Inlet Valve OPEN RCC-V294 CRD Pump A Cooling Water Inlet Valve OPEN RCC-V145 CRD Pump A Cooling Water Inlet Test Valve CLOSED RCC-V74 CRD Pump A Cooling Water Inlet Air Operated CLOSED Valve RCC-V74 CRD Pump A Cooling Water Inlet Air Operated NEUTRAL Valve Manual Actuator RNA-IV-552 Instrument Air Isolation Valve To RCC-V74 OPEN RNA-IV-488 Instrument Air Supply Valve To RCC-V74 OPEN RNA-IV-551 Instrument Air Isolation Valve To RCC-V73 OPEN RNA-IV-487 RNA-lV-487 Instrument Air Supply Valve To RCC-V73 OPEN RCC-U-V1 CRD Pump A Outboard Bearing Cooling OPEN Isolation Valve RCC-U-V2 CRD Pump A Inboard Bearing Cooling Isolation OPEN Valve RCC-U-V3 CRD Pump A Lube Oil Cooling Isolation Valve OPEN RCC-V8 CRD Pump A Cooling Water Outlet Valve OPEN RCC-V143 CRD Pump A Cooling Water Outlet Test Valve CLOSED 2OP-21 120P-21 Rev. 65 Page 791 Page 55 of 79

ATTACHMENT 33 Page 4 of 22 Reactor Building Building Closed CoolingCooling Water System Valve Lineup Number Description Description Position!

Position/ Checked Indication Indication Reactor Building - Post Accident Sampling Skid - El

- - EI 20 20' - South 1R171 RCC-V315 RBCCW To Post Accident Sampling System LOCKED OPEN 1R171 RCC-V316 RBCCW From Post Accident Sampling System LOCKED OPEN OPEN Reactor Building - Southeast Drywell Wall - El

- - EI 20 20' - Southeast RNA-IV-239 Instrument Air Isolation Valve To RCC-V51 OPEN RNA-IV-141 Instrument Air Supply Valve To RCC-V51 OPEN RNA-V144 Instrument Air Root Valve To RCC-V51 OPEN RCC-V29 Water Chiller Cooling Water Outlet Valve LOCKED OPEN RCC-FE-1824-1 High Pressure Root Valve To RCC-FE-1 RCC-FE-1824824 CLOSED RCC-FE-1824-2 RCC-FE-1 824-2 RCC-FE-1 824 Low Pressure Root Valve To RCC-FE-1824 CLOSED Reactor Building - Penetration X77 - EI.

- - 20 - Az 295 El. 20' - 295°0 RCC-IV-2374 Test Valve For Sample Valve RCC-SV-1222B LOCKED CLOSED RCC-IV-2375 Test Valve For Sample Valve RCC-SV-1222C LOCKED CLOSED Reactor Building - RBCCW HX Area - EI

- - El 50' 50 - North RCC-V44 RBCCW HX C Inlet Valve OPEN RCC-V158 RBCCW HX C Inlet Test Valve CLOSED RCC-V115 RCC-V1 15 RBCCW HX C Inlet Vent Valve CLOSED RCC-V116 RBCCW HX C Shell Side Drain Valve CLOSED RCC-V124 RBCCW HX C Outlet Vent Valve CLOSED RCC-V161 RBCCW HX C Outlet Test Valve CLOSED RCC-V47 RBCCW HX C Outlet Valve CLOSED RCC-V43 RBCCW HX B Inlet Valve OPEN RCC-V157 RBCCW HX B Inlet Test Valve CLOSED 1 2 0 P-21 20P-21 Rev. 65 791 Page 56 of 79

ATTACHMENT 33 Page 55 of 22 Reactor Building Closed Closed Cooling Water System Valve Lineup Number Description Description Position!

Position/ Checked Indication Indication Reactor Building - RBCCW HX Area - El

- - 50' - North EI 50 -

RCC-V112 RCC-V1 12 RBCCW HX BB Inlet Vent Valve CLOSED RCC-V113 RCC-V1 13 RBCCW HX BB Shell Side Drain Valve CLOSED RCC-V123 RBCCW HX BB Outlet Vent Valve CLOSED RCC-V160 RBCCW HX B B Outlet Test Valve CLOSED RCC-V46 RBCCW HX B B Outlet Valve CLOSED RCC-V42 RBCCW HX A Inlet Valve OPEN RCC-V156 RBCCW HX A Inlet Test Valve CLOSED RCC-V109 RBCCW HXAHX A Inlet Vent Valve CLOSED RCC-V110 RCC-V1 10 RBCCW HX A Shell Side Drain Valve CLOSED RCC-V122 RBCCW HX A Outlet Vent Valve CLOSED RCC-V159 RBCCW HX A Outlet Test Valve CLOSED RCC-V45 RBCCW HX A Outlet Valve CLOSED RCC-V190 RBCCW HX Inlet Sample Root Valve OPEN RCC-V40 RBCCW Header Discharge Pressure Root Valve OPEN To RCC-PT-671, RCC-PS-672, And RCC-PSL-673 RCC-PT -671-3 RCC-PT-671-3 RCC-PT-671 Instrument Isolation Valve OPEN RCC-PT -671-6 RCC-PT-671-6 RCC-PT-671 Instrument Drain Valve CLOSED RCC-PS-672-3 RCC-PS-672 Instrument Isolation Valve OPEN RCC-PS-672-6 RCC-PS-672 Instrument Drain Valve CLOSED RCC-PS-672-7 -671, RCC-PS-672, And RCC-PSL-673 RCC-PT-671, RCC-PT CLOSED Instrument Line Drain Valve RCC-PSL-673-3 RCC-PSL-673 Instrument Isolation Valve OPEN RCC-PSL-673-6 RCC-PSL-673 Instrument Drain Valve CLOSED RCC-FE-2256-1 High Pressure Root Valve To RCC-FE-2256 CLOSED RCC-FE-2256-2 Low Pressure Root Valve To RCC-FE-2256 CLOSED 20P-21 120P-21 Rev. 65 79 Page 57 of 791

ATTACHMENT 3 Page 6 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position!

Position/ Checked Indication Reactor Building - RBCCW Pump Area - EI

- - El 50' 50 - North RCC-V102 RCC-V1 02 Chemical Addition Tank Inlet Valve CLOSED RCC-V103 Chemical Addition Tank Outlet Valve CLOSED RCC-V104 RCC-V1 04 Chemical Addition Tank Vent Valve CLOSED RCC-V1 05 RCC-V105 Chemical Addition Tank Drain Valve CLOSED RCC-V326 RBCCW Return From Post Accident Sampling LOCKED System Valve OPEN RCC-V317 RBCCW Supply To Post Accident Sampling LOCKED System Valve OPEN

~)

7'(RCC-V30 RCC-V30 RBCCW Pump C Suction Valve OPEN RCC-V58 RBCCW Pump C Suction Test Valve CLOSED

HGC~V1Ii:r-',

RCC-V12) RBCCW Pump C Suction Drain Valve CLOSED

/(

(' ~CC:V30'1:C:'>

RCCV301 RBCCW Pump C Casing Vent Valve CLOSED vi 'RCC~V'129~

4RCC-V129N RBCCW Pump C Discharge Drain Valve CLOSED

_"..;1" RCC-V117 RCC-V1 17 RBCCW Pump C Discharge Pressure Root OPEN Valve To RCC-PI-668 RCC-Pl-668 RCC-PI-668-3 RCC-Pl-668-3 RCC-Pl-668 Instrument Isolation Valve RCC-PI-668 OPEN RCC-PI-668-6 RCC-PI-668 Instrument Drain Valve CLOSED

(:" "RCC-V34 1CC-V34 - )

) RBCCW Pump C Discharge Valve OPEN RCC-V31 RBCCW Pump B B Suction Valve OPEN RCC-V63 RBCCW Pump B Suction Test Valve CLOSED RCC-V133 RBCCW Pump B Suction Drain Valve CLOSED RCC-V302 RBCCW Pump B Casing Vent Valve CLOSED RCC-V134 RBCCW Pump B Discharge Drain Valve CLOSED RCC-V118 RBCCW Pump B B Discharge Pressure Root OPEN Valve To RCC-PI-669 1 20P-21 2 0 P-21 Rev. 65 791 Page 58 of 79

ATTACHMENT 3 Page 7 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position!

Position/ Checked Indication Reactor Building - RBCCW Pump Area - EI

- - El 50' 50 - North RCC-Pl-669-3 RCC-PI-669-3 RCC-PI-669 Instrument Isolation Valve OPEN RCC-PI-669-6 RCC-PI-669 Instrument Drain Valve CLOSED RCC-V36 RBCCW Pump B B Discharge Valve OPEN RCC-V32 RBCCW Pump A Suction Valve OPEN RCC-V67 RBCCW Pump A Suction Test Valve CLOSED RCC-V1 38 RCC-V138 RBCCW Pump A Suction Drain Valve CLOSED RCC-V303 RBCCW Pump A Casing Vent Valve CLOSED RCC-V139 RBCCW Pump A Discharge Drain Valve CLOSED RCC-V1 19 RCC-V119 RBCCW Pump A Discharge Pressure Root OPEN Valve To RCC-PI-670 RCC-Pl-670 RCC-PI-670-3 RCC-PI-670 Instrument Isolation Valve OPEN RCC-PI-670-6 RCC-PI-670 Instrument Drain Valve CLOSED RCC-V38 RBCCW Pump A Discharge Valve OPEN RCC-V61 RBCCW Suction Pressure Root Valve To OPEN RCC-PI-666 RCC-PI-666-3 RCC-PI-666 Instrument Isolation Valve OPEN RCC-PI-666-6 RCC-PI-666 Instrument Drain Valve CLOSED RCC-V300 Pass Coolers 604 & & 605 Cooling Return Isolation LOCKED Valve!Chemical Addition Injection Isolation Valve Valve/Chemical OPEN RCC-V39 RCC-TV-695 Inlet Valve OPEN RCC-V41 RCC-TV-695 Outlet Valve OPEN RNA-IV-243 Instrument Air Isolation Valve To RCC-TIC-695 OPEN RNA-IV-145 Instrument Air Supply Valve To RCC-TIC-695 OPEN And RCC-TV-695 RCC-FE-1821-1 RCC-FE-1 821 High Pressure Root Valve To RCC-FE-1821 CLOSED RCC-FE-1 821-2 RCC-FE-1821-2 RCC-FE-1 821 Low Pressure Root Valve To RCC-FE-1821 CLOSED 20P-21 120P-21 Rev. 65 7j Page 59 of 791

ATTACHMENT 3 Page 8 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position! Checked Indication Reactor Building - RBCCW Pump Area - EI

- - El 50 50' - North RNA-IV-555 Instrument Air Isolation Valve To RCC-TV-695 OPEN RNA-V179 Instrument Air Root Valve To RCC-TI- 695 And OPEN RCC-TV-695 Reactor Building - RWCU Pump and Heat Exchanger Room - EI

- - 50 El 50' RCC-V149 RWCU Pump B B Cooler Inlet Test Valve CLOSED RCC-V304 RWCU Pump B B Cooler Inlet Valve OPEN RCC-V5087 RWCU Pump B B Gear Box Cooling Isolation OPEN Valve RCC-V5088 RWCU Pump B B Cooler Outlet Throttle Valve OPEN RCC-V306 RWCU Pump B B Cooler Outlet Isolation Valve OPEN RCC-V147 RWCU Pump B B Cooler Outlet Test Valve CLOSED RCC-V172 RWCU Pump B Cooler Outlet Sample Root OPEN Valve RCC-FE-2888-1 High Pressure Root Valve To RCC-FE-2888 CLOSED RCC-FE-2888-2 Low Pressure Root Valve To RCC-FE-2888 CLOSED RCC-V84 RWCU Non-Regenerative HX Shell Side Outlet CLOSED Drain Valve RCC-V150 RWCU Non-Regenerative HX Shell Side Outlet CLOSED Test Valve RCC-V3 RWCU Non-Regenerative HX Shell Side Outlet OPEN Valve RCC-V4 RWCU Non-Regenerative HX Shell Side Outlet LOCKED Throttle Valve THROTTLED 13.25 turns from full open RCC-V174 RWCU Non-Regenerative HX Outlet Sample OPEN Root Valve 20P-21 120P-21 Rev. 65 791 Page 60 of 79

ATTACHMENT 33 Page 99 of 2222 Reactor Building Building Closed Cooling Cooling Water System Valve Lineup Number Description Description Position!

Position/ Checked Indication Reactor Building - RWCU Pump and Heat

- Heat Exchanger Room - El - EI 50 50' RCC-V83 RWCU Non-Regenerative HX A Shell Side Vent CLOSED Valve RCC-V86 RWCU Non-Regenerative HX Shell Side Drain CLOSED Valve RCC-V151 RWCU Non-Regenerative HX Inlet Test Valve CLOSED RCC-V50 RWCU Non-Regenerative HX Inlet Valve OPEN RCC-V183 RWCU Non-Regenerative HX Shell Side Sample OPEN Root Valve RCC-V85 RWCU Non-Regenerative HX B B Shell Side Vent CLOSED Valve RCC-V148 RWCU Pump A Cooler Inlet Test Valve CLOSED RCC-V307 RWCU Pump A Cooler Inlet Valve OPEN RCC-V5089 RWCU Pump A Gear Box Cooling Isolation OPEN Valve RCC-V5090 RWCU Pump A Cooler Outlet Throttle Valve OPEN RCC-V5091 RWCU Pump A Casing Cooling Isolation Valve OPEN RCC-V309 RWCU Pump A Cooler Outlet Isolation Valve OPEN RCC-V146 RWCU Pump A Cooler Outlet Test Valve CLOSED RCC-V170 RWCU Pump A Cooler Outlet Sample Root OPEN Valve RCC-FE-2887 -1 RCC-FE-2887-1 High Pressure Root Valve To RCC-FE-2887 CLOSED RCC-FE-2887 -2 RCC-FE-2887-2 Low Pressure Root Valve To RCC-FE-2887 CLOSED Reactor Building - RWCU Precoat Pump Area - EI

- - El 80' 80 - East RCC-V181 RCC-V1 81 RBCCW Outlet Test Valve From RWCU Precoat CLOSED Pump RCC-V121 RBCCW Outlet Isolation Valve To RWCU OPEN Precoat Pump 1 2 0 P-21 20P-21 Rev. 65 791 Page 61 of 79

CAROLINA POWER & LIGHT COMPANY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT NRCADMIN NRC ADMIN RC (RO/SRO)

LESSON TITLE: Determine Stay Time Limitations in High Radiation Area LESSON NUMBER: LOT-ADM-JP-102-A03 REVISION NO: 01

Determine Stay Determine Stay Time Time Limitations Limitations in in High High Radiation Radiation Area Area SAFETY CONSIDERATIONS:

SAFETY CONSIDERATIONS:

None.

EVALUATOR NOTES: (Do not not read to performer)

1. The attached Radiological

1. Radiological Survey WILL bebe provided to the performer.

performer.

2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

3. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below each step.

LOT-ADM-JP-1 02-A03 LOT-ADM-JP-102-A03 Page 22 of Page of 99 Rev.01 RevOl

Determine Stay Determine Stay Time Time Limitations Limitations inin High High Radiation Radiation Area Area Read the following to the JPM performer. performer.

TASK CONDITIONS:

required to perform Two workers will be required perform an emergent leak leak repair repair on the Unit Unit Two Steam Packing Exhauster Packing Exhauster 2A.

Worker #1 has accumulated 500 mrem this year (Progress Energy dose only).

has accumulated 1615 Worker #2 has 1615 mrem this year (Progress Energy dose only).

The following times for each worker have been estimated for performance performance of the job.

1. Staging time in access area directly outside the A SJAE Room 45 minutes

2. Staging time in area directly inside A SJAE room access door 15 minutes

3. Work time at the 2A SPE 1.5 1 .5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Following completion of the job, an additional 15 mrem per worker will be received during de-de staging activities.

INITIATING CUE:

Using the information above and the radiological survey provided, evaluate the leak repair job for possible performance under current plant conditions to include:

1. Determine the projected dose each worker would receive to perform the leak repair.

(Assume the same task times for both workers)

2. Based upon the projected total accumulated dose, determine if any Progress Energy administrative dose limitations will be exceeded.

LOT-ADM-JP-1 02-A03 LOT-ADM-JP-102-A03 Page Page 33 of of 99 Rev.01 Rev.01

Determine Stay Time Limitations in High Radiation Area ANSWER KEY WORKER #1 WORKER #2 INITIAL DOSE 500 mrem 1615 mrem PROJECTED DOSE 510.25 mrem 510.25 mrem PROJECTED TOTAL DOSE 1010.25 mrem 2125.25 mrem BNP ADMIN DOSE LIMIT EXCEEDED (Circle Yes or No) j[

YES ?3 NO LOT-ADM--JP-102-A03 LOT -ADM-JP-1 02-A03 Page 4 of 99 Rev.01

Determine Stay Determine Stay Time Time Limitations Limitations in in High High Radiation Radiation Area PERFORMANCE CHECKLIST PERFORMANCE CHECKLIST NOTE: Sequence NOTE: Sequence is is assumed assumed unless unless denoted denoted in in the the Comments.

Comments.

NOTE: Provide the examinee the JPM attached survey map.

TIME START _ _ __

Step 1I - Determines dose for each worker as follows:

a. Staging time in access area directly outside the SJAE room mm) 0.75 Hr X (45 min) mr/hr =

X 5 mrlhr = 3.75 mrem Estimate 3.75 mrem dose accumulation.

- CRITICAL STEP** SAT/UNSAT*

SATIUNSAT*

b. Staging time in area directly inside SJAE room access door (15 min) mm) 0.25 Hr HrX mr/hr =

X 16 mrlhr = 4 mrem Estimate 4 mrem dose accumulation.

- CRITICAL STEP** SATIUNSAT*

SAT/UNSAT*

c. Work time at the SPE 2A mrlhr ==487.5 mrem Hr X 325 mr/hr 1.5 HrX Estimate 487.5 mrem dose accumulation.

- CRITICAL STEP** SATIUNSAT*

SAT/UNSAT*

d. An additional 15 15 mr will be accumulated once the job is done for de-staging activities.

- CRITICAL STEP** SAT/UNSAT*

LOT-ADM-JP-102-A03 LOT -ADM-JP-1 02-A03 Page Page 55 of of 99 Rev.O1 Rev.01

Determine Stay Time Limitations in High Radiation Area

=3.75 + 4 + 487.5 + 15 Total=3.75+4+487.5+

e. Total =510.25 mrem 15=510.25mrem forjob Determines Total dose for job completion - 510.25 mrem.

- STEP**

CRITICAL STEP** SAT/UNSAT*

SAT/UNSAT*

Step 2 - Determines that Worker #2 would exceed the PGN administrative limit of 2 REM per calendar year if the estimated dose were accumulated.

Worker #1 500 mr +÷ 510.25 mr =

= 1010.25 mr <<(< 2R limit)

Worker #2 1615 mr +÷ 510.25 mr == 2125.25 mr (>(> 2R limit)

- STEP** SAT/UNSAT*

CRITICAL STEP** SATIUNSAT*

TERMINATING CUE: When the total dose for each worker has been determined and the administrative limits addressed, the JPM is complete.

TIME COMPLETED _ _ _ __

NOTE: Comments required for any step evaluated as UNSAT.

NOTE:

LOT-ADM-JP-102-A03 Page 6 of 9 Rev.O1 Rev.01

Determine Stay Time Limitations in High Radiation Area RELATED TASKS:

(Specify)

K/A REFERENCE AND IMPORTANCE RATING:

KIA 2.3.7 Ability to comply with radiation work permit requirements during normal and abnormal conditions 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

REFERENCES:

HPS-NGGC-0003 DOS-NGGC-0004 TOOLS AND EQUIPMENT:

Calculator.

JPM Survey Map SAFETY FUNCTION (from NUREG 1123):

A.3 Radiation Control REASON FOR REVISION:

2010-1 NRC Exam - Modified to different location and rates.

LOT-ADM-JP-1 LOT-ADM-JP-1 02-A03 Page 77 of 99 Rev.01

Stay Time Limitations in High Radiation Area Determine Stay Validation Time: __1.:...;:5~_

15 Minutes (approximate).

Minutes Time Taken: _ _ __

APPLICABLE METHOD OF TESTING Performance: Simulate Actual Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No LX Time Limit N/A Alternate Path: Yes No ~ X EVALUATION Performer: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Performer:_______________________________________________

JPM: Pass Fail --

Remedial Training Required: Yes No _ _

TAP-41 (Reference T AP-4111 for evaluation guidance)

Comments:

Comments reviewed with Performer Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ __ Date:___________

Date: -----

LOT-ADM-JP-1 LOT-ADM-J P-1 02-A03 Page 8of9 8 of 9 Rev.01 Rev.O1

BRUNSWICK NUCLEAR BRUNSWICK NUCLEAR PLANT PLANT RADIOLOGICAL SURVEY RADIOLOGICAL SURVEY SURVEY SURVEY NO NO.

1717 1717 - 003 2TO 2T06 -

Today DOSE RATE CONTAMINATION DATE: Tod~y DATE: TIME:

0600 INST. TYPE Telelector ff C aD IJ"D a IJ"D W aD C JOR H. Physics Joe Physics T191A SURVEYOR SERIAL NO. L-177 L-l77 M52 INST/SN INSTISN pCC' -;t: P4~i<C ~-FACTOR FACTC>R SGNATURE SIGNATURE 100%

100% 0.10 0.'18 012 RX RX POVVER POWER EFF EFF

-;'1' S<<f:{"I:oi4(l~ 3*3 40 CPM 22 CPM CPM CPM REVIEWED RE'y'IEWED H2 CFM H2SCFM BKGD.

22 BLDG - TB- EL -

TB 20- AREA _

20' A_

"An STEAM AiR_ EJECTOR ROOM UNIT UNITBLDG __ EL_AREA _ _JET __ AIR EJECTOR

_ _ _ _ _ _ __ RWPNO RWPNO.

PE 2A SPE WR/JO COMPONENT Cor ....1PONENT OR OR TAG NO. NO. WRiJC) 002seS62 =

WORK WORK PERFORMED PERFOR!.,.1ED eak epar_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

_:-_e"'_h_R_e;..p"_ir SMEAR RESULTS IN DPMI100 eM" B=9ETA IH mRAD/HRI!OOCM :

M=CF'f,l.'MASLIN 103 NO. RESUL:S O"vEF'~';EAD PlJo.TFOR\f I

MD.L, 1182 1--1 AF"l"ER CC~D=h'~,=R CD Ih~ie:~

COt..:JE"iG=-:

CD 325 r'~

X A

I I ! ~

Work Area 1

L::" "'DC.U~~

E..ECT~JC..J.L vJTL~D Note: This

'Note: is a~ High This is High no;se nOise area '....hile operating.

area while operating. 5

~------------~--------------------

RA -RAD RA -R!o.DiA AON 710N AREA AREA CA CA -CONTA1INATO.

-CONTAMI\JAnl)~~ AREA~.R=A

-IRA

~Ri\ -HOH RADIA 71C1N AREA

-HIGH RADIA O4 Th AREA NOA HeA -HIS-I COIFAMINAnCN AREA

-HIG'i CONAIAAATON AREA OOSE RAES I r,R,HR LMRA -LOCEC L-iRJ -LOCK::D H0H R.ADI:"710~~ AREA

-3H RAD.A1ON AREA AR -AiRBORNE AREA AA -AREORNEAREA RCA -RADIAiO RCA C:)NT::;:OL AREA

~RADIA7!O~ CONTROL A~E;'. ~ R8PE BOJADAFY BO",I~~C'AFY -NEJTRON :-Re-H

CONDITIONS:

TASK CONDITIONS:

Two workers will be be required to perform an emergent leak leak repair on the Unit Two Steam Packing Exhauster 2A.

Worker #1 has accumulated 500 mrem this year (Progress Energy dose only).

Worker #2 has accumulated 1615 mrem this year (Progress Energy dose only).

The following times for each worker have been estimated for performance of the job.

1. Staging time in access area directly outside the A SJAE Room 45 minutes

2. Staging time in area directly inside A SJAE room access door 15 minutes

3. Work time at the 2A SPE 1 .5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 Following completion of the job, an additional 15 mrem per worker will be received during de-de staging activities.

INITIATING CUE:

Using the information above and the radiological survey provided, evaluate the leak repair job for possible performance under current plant conditions to include:

1. Determine the projected dose each worker would receive to perform the leak repair.

(Assume the same task times for both workers)

2. Based upon the projected total accumulated dose, determine if any Progress Energy administrative dose limitations will be exceeded.

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN COOl C001 (ROISRO)

(RO/SRO)

LESSON TITLE: Core Performance Parameter Check LESSON NUMBER: LOT-ADM-201-D02 REVISION NO: 01

Core Performance Parameter Check SAFETY CONSIDERATIONS:

1.

1. NONE.

EVALUATOR NOTES: (Do not read to examinee)

1. The applicable procedure WILL be provided to the examinee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the examinee.

3. This JPM may be administered in the simulator, control room, or classroom setting.

4. Performance Frequency A (every 24 hrs when >25% RTP) is required.

Read the following to examinee.

TASK CONDITIONS:

1. The CODSR requires performance of 2PT-01.11, Core Performance Parameter Check, on Unit Two.

2. All applicable prerequisites of 2PT-01.11 are met.

3. No APRM gain adjustments will be performed during this test.

4. If independent verification, notifications, or other actions are required during performance, assume the action is complete as applicable by providing the following in the comments area of this cue sheet.

The Step number followed by a short description of the Action.

5. Cover page information will be filled out by the Unit SCO.

INITIATING CUE:

2PT-01 .11, Core Performance Parameter The Unit SCO has directed you to complete 2PT-01.11, Check, utilizing the Core Performance Log provided and provide the results below upon completion.

2PT-01.11, Core Performance Parameter Check, results are (circle choice):

SAT UNSAT Comments (if necessary): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

LOT -ADM-JP-201-D02 LOT-ADM-JP-201-D02 Page 2 of 12 Rev. 01

Core Performance Parameter Check ANSWER KEY 2PT-01 .11, Core Performance Parameter Check, results are (circle choice):

2PT-01.11,

~~~ UNSAT UNSAT Comments (if necessary): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Step 7.1.7 - APRM 1 I gain adjustment I .00 adiustment factor is greater than 1.00 Step 7.1.11 - CMFLPD is greater than 1.00, Unit SCO notified.

Step 7.1.11.1 - CMFLPD is greater than 1.00, On-Shift Reactor Engineer notified to take action to restore CMFLPD to an acceptable value.

Step 7.1.7 - Notify Unit SCO test is complete.

LOT-ADM-JP-201-D02 LOT -ADM-JP-201-D02 Page 3 of 12 Rev. 01

Core Performance Parameter Check PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1I - Obtain current revision of 2PT-01.11

- 2PT-O1.11 and verify if applicable.

2PT-O1. 11 obtained and verified as required.

Current revision of 2PT-01.

SAT/UNSAT*

TIME START _ _ __

PROMPT: Provide the Core Performance Log attached to this JPM to be evaluated by candidate.

NOTE: APRM gain adjustment and PPC usage are not being evaluated by by this JPM.

Step 2 - OBTAIN an edit of the process computer core performance program.

Core Performance Log obtained from Evaluator.

SAT/U NSAT*

SAT/UNSAT*

NOTE: No failed sensors, this step may be initialed or marked N/A.

Step 3 - IF there are failed inputs on the failed sensor list, THEN ENSURE correct values have been substituted where appropriate.

DetermInes no failed sensors exist and marks this step as NIA.

Determines N/A.

SATIUNSAT*

Step 4 - Evaluates value of NSSFFLG is equal to 1.

Determines NSSFFLG is equal to 11 and proceeds to Step 7.1.4.

SAT!UNSAT*

SATIUNSAT*

NOTE: Steps 7.1.3.1.a steps and b (NSSFFLG is NOTequal 7.1.3.1.aand NOT equal to 1)

1) should be marked N/A.

LOT-ADM-JP-201-D02 LOT-ADM-J P-20 1-D02 Page 4 of 12 12 Rev. 01

Core Performance Core Performance Parameter Parameter Check Check Step 5 - Evaluates Evaluates value of WFWFFLG, NSSCUFLG, NSSCUFLG, and and NSSCRFLG NSSCRFLG all equal to 1. 1.

Determines WFWFFLG, NSSCUFLG, Determines NSSCUFLG, and NSSCRFLG NSSCRFLG are are all equal equal to to 1I and proceeds to StepStep 7.1.4.

7.1.4.

SAT/U NSAT*

SAT/UNSAT*

NOTE: Steps 7.1.4.1.a and b (WFWFFLG OR NSSCUFLG OR NSSCRFLG are NOT equal to 1) should be marked N/A.

2PT-1 .11 are met.

Step 6 - Determine if criteria listed in Section 6.1 of 2PT-1.11 Checks core performance log and verifies value for CMFLCPR :::1.00. 1. 00.

- ** SAT!UNSAT*

- CRITICAL STEP ** SAT/UNSAT*

Checks core performance log and verifies value for CMAPRA CMAPRAT T :::1.00.

1.00.

- ** SAT/UNSAT*

- CRITICAL STEP ** SATlUNSAT*

Checks core performance log and verifies value for CMFDLRX :::1.00. 1.00.

- ** SAT/UNSAT*

- CRITICAL STEP **

NOTE: in Section 6.1 are NOT satisfied)

Steps 7.1.6 and 7.1.6.1 (limits specified inSeclion should be marked N/A.

NOTE: Report of APRM APRM1I GAF> 1.00 is not required to satisfy Critical Step.

GAF >1.00 Step 7 - Determine if the acceptance criteria listed in Section 6.2 are satisfied (at least three APRM gain adjustment factors are less than or equal to 1.00). 1.00).

Determines APRMS 2, 3, and 4 are within limits and APRM 11 is above the limit.

- CRITICAL STEP ** ** SAT/UNSAT*

PROMPT: i: IfIf informed informed that APRM I1 GAF GAF is>

is > 1.00, 1.00, acknowledge the report and and inform the trainee the APRM will be adjusted later. Direct later. Direct the trainee to continue the PT.PT.

LOT-ADM-JP-201 LOT-ADM-JP-201-D02 -D02 Page Page 55 of of 12 12 Rev. 01 Rev. 01

Core Performance Parameter Check NOTE:

INOTE: Steps 7.1.8 and 7.1:9 (APRM gain adjustment) should be marked N/A.

7.1.9 (APRMgain Step 8 - Determine if CMFLPD is ~

- < 1.00.

Checks core performance log and recognizes CMFLPD is >1.00.

- ** SATIUNSAT*

- CRITICAL STEP ** SAT/UNSAT*

NOTE: Reference 2.5 states.that Note prior to Step 7.1.10 -Reference

- states that NRC expects LHGR monitoring (CMFLPD) to remain the same as CPR and APLHGR forGNF for GNF fuel (i.e., to restore LHGR within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be below 23%

power within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). This information may be included in the comments, but is not required to satisfy the JPM.

Step 9 - NOTIFY the Unit SCO that CMFLPD is greater than 1.00.

Notifies Unit SCO that CMFLPD is greater than 1.00

- ** SAT/UNSAT*

- CRITICAL STEP ** SAT/UNSAT*

10 NOTIFY the On-Shift Reactor Engineer to take action to restore CMFLPD to an Step 10- -

acceptable value.

Notifies RE to restore CMFLPD to ~ < 1.0.

- ** SAT/UNSAT*

- CRITICAL STEP ** SAT/UNSAT*

Step 11 - ENSURE Acceptance Criteria listed in Section 6.0 have been satisfied.

Determines Acceptance Criteria has been satisfied.

- ** SAT!UNSAT*

- CRITICAL STEP ** SAT/UNSAT*

NOTE: Attaching edits and coversheet information is not required for classroom performance.

Step 12 - ATTACH the collected edits.

Attaches the collected edits to the procedure.

SAT/U NSAT*

SAT/UNSAT*

LOT-ADM-JP-201-D02 LOT -ADM-JP-20 1-002 Page 6 of 12 Rev. 01

Core Performance Core Performance Parameter Parameter Check Check NOTE:

NOTE: 7.2 should be Section 7.2 be marked marked N/A.

NOTE:

NOTE: Attachments 2 and 3 may may be be discarded.

Step 13 - ENSURE the required information has been recorded on the cover page.

Cover page information to be filled out by Unit SCQ SCO per cue.

SAT/U NSAT*

SAT/UNSAT*

SCO that 2PT-01.11 Step 14 - Notify the Unit SCQ 2PT-01 .11 is completed SAT with CMFLPOCMFLPD greater than 1.00 which required RE notification to restore ~ < 1.0 and APRM 1 1 requires adjustment.

SCO notified 2PT-01.11 Unit SCQ 2PT-01. Illsis completed SAT with APRM 1 I requiring gain adjustment to restore GAF to ~< 1.0 and CMFLPD is > 1.

is> 1.0.

O. RE has been notified to take action to restore CMFLPD to ~< 1. 1.0.

O.

- ** SATIUNSAT*

- CRITICAL STEP ** SAT/UNSAT*

TERMINATING CUE: 2PT..;01.11 2PT-01 .11 acceptance criteria verified verified. and the Unit SCQ SCO informed the results are satisfactory. -

TIME COMPLETED _ _ _ __

Comments required for any step evaluated as UNSAT.

LOT-ADM-JP-201-D02 LQT-AOM-JP-20 1-002 Page Page 77 of of 12 12 Rev. 01 Rev. 01

Core Performance Parameter Check LIST OF REFERENCES RELATED TASKS:

299201 B201: Perform Daily Surveillance Report Per 01-3.1 or 01-3.2.

2992018201:

K/A REFERENCE AND IMPORTANCE RATING:

KIA Generic 2.1.7 (3.7/4.4)

Ability to evaluate plant performance and make operational judgments based on operating characteristics 1 / reactor behavior 1

/ and instrument interpretation.

REFERENCES:

2PT-01 .11 2PT-01.11 TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, I 123, Rev 2):

7 - Instrumentation (APRM System)

REASON FOR REVISION:

Revised to allow classroom performance. Unit 2 process computer core performance program edit will be provided to examinee.

LOT-ADM-JP-201-D02 LOT -ADM-J P-20 1-002 Page 8 of 12 Rev. 01

Core Performance Parameter Check Time Required for Completion: ~ 15 Minutes (approximate).

Time Taken: _ _ _ _ _ __

Time Taken:

APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No LX Time Limit N/A Alternate Path: Yes No ~X EVALUATION Trainee: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

JPM: Pass - - - Fail Remedial Training Required: Yes No _ __

Did Trainee Verify Procedure as Authorized Copy?: Yes No _ __

(Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Performer Evaluator Signature: Date: - - - - - -

LOT-ADM-JP-201-D02 Page 99 of 1212 Rev. 01

TASK CONDITIONS:

1. CODSR requires performance of The CQDSR of2PT-O1.11, 2PT-01.11, Core Performance Parameter Check, on Unit Two.

2. 2PT-O1.11 are met.

All applicable prerequisites of 2PT-01.11

3. No APRM gain adjustments will be performed during this test.

4. If independent verification, notifications, or other actions are required during performance, assume the action is complete as applicable by providing the following in the comments area of this cue sheet.

The Step number followed by a short description of the Action.

5. Cover page information will be filled out by the Unit SCQ.

SCO.

INITIATING CUE:

The Unit SCQ SCO has directed you to complete 2PT-01.11, 2PT-O1 .11, Core Performance Parameter Check, utilizing the Core Performance Log provided and provide the results below upon completion.

2PT-O1 .11, Core Performance Parameter Check, results are (circle choice):

2PT-01.11, SAT UNSAT Comments (if necessary):

BRUNSWICK -2 BRUNSWICK-2 WK-1016 10TODAY-07.00.27 WK-1016 1OTODAY-07.OO.27 8902 8902 MWD/MTUM\ND/MTU TRIGR=2HR TRIGR=2HR REV=usep06 REV=usepo6 CORE PERFORMANCE CORE PERFORMANCE LOG LOG --- LONG

- - - LONG EDIT EDIT TL 00 TLO TL TLO TBVINS TBVINS NSS NSS NFWTNFWT BOC BOC TO TO NEOC NEOC CTP CALCULATION CTP CALCULATION :: HEAT HEAT BALANCE BALANCE SYMMETRY SYMMETRY :: FULL FULL CYCLE:

CYCLE: 19 19

AXIAL

AXIAL REL REL POWER*

POWER*

STATE CONDITIONS STATE CONDITIONS FLOW (MLB/HR)

FLOW (MLB/HR) CORE PARAMTRS CORE PARAMTRS NUCLEAR NUCLEAR LIMITS LIMITS LOCATION LOCATION NODE NODE NOTCH NOTCH REL-POW REL-POW EXP(GWD/MT)

EXP(GWD/MT)

GMWE 973.2 GMWE 973.2 WT 78.84(102.4%)

WT 78.84(102.4%) CMEO CMEQ 0.2791 0.2791 P-PCS P-PCS -0.06

-0.06 33-36-19 33-36-19 25 25 0.187 0.187 3.842 3.842 CMWT 2905.9 CMWT 2905.9 (99.4%) (99.4%) WDP WDP 78.50 78.50 CAEO CAEQ 0.1634 0.1634 P-PCFC P-PCFC -0.06

-0.06 33-36-19 33-36-19 24 24 00 00 0.608 0.608 11 .154 11.154 PR PR 1044.2 PSIA 1044.2 PSIA NSSFFLG 1.

NSSFFLG 1. CAOA CAQA 0.1538 0.1538 CMFLCPR CMFLCPR 0.885 0.885 39-40 39-40 23 23 02 02 0.784 0.784 18.881 18.881 DHS DHS 20.85 BTU/LB 20.85 BTU/LB WFW WFW 12.72 12.72 CAVF CAVF 0.4548 0.4548 CMAPRAT CMAPRAT 0.769 0.769 43-34-15 43-34-15 D 22 D_22 04 04 0.939 0.939 23.791 23.791 CRD 0.0931 CRD 0.0931 WFWFFLG 1.

WFWFFLG 1. CAPD CAPD 58.934 58.934 CMFDLRX CMFDLRX 0.895 0.895 41-34-13 41-34-13 21 21 06 06 1.035 1.035 27.184 27.184 CYEXP 8902.3 CYEXP 8902.3 MWD/MT MWD/MT NSSCUFLG 1.

NSSCUFLG 1. RWL 187.5460 RWL 187.5460 CMFLPD CMFLPD 11.155

.155 41 13 41-36-13 20 20 08 08 1.088 1.088 29.224 29.224 CAVEX 22911.1 CAVEX 22911.1 MWD/MT MWD/MT NSSCRFLG 1. 1. CDLP CDLP 25.0146 25.0146 CMINCPR CMINCPR 1.528 1 .528 39-40 39-40 19 19 10 10 1.102 1.102 30.344 30.344 RODLINE 97.9%

RODLINE 97.9% WO WD 36.40 36.40 DPCC DPCC 30.3681 30.3681 18 18 12 12 1.097 1.097 30.901 30.901 NON_EQ XE NON_EO XE -1.7%

-1.7% KEFF 0.9971 KEFF 0.9971 17 17 14 14 1.078 1.078 31.147 31.147 C 16 C_16

- 15 16 16 1.035 1.035 30.565 30.565 LOCATION LOCATION 1 22 33 44 55 66 77 88 99 10 10 11 11 12 12 15 18 18 1.023 1.023 30.935 30.935 AXIAL REL POWER 0.40 0.40 0.94 0.94 1.14 1.14 1.18 1.18 11.18

.18 1.20 1.20 11.21 .21 1. 1.1111 1.07 1.07 0.990.99 0.90 0.90 0.68 0.68 14 14 20 20 1. 111 1.111 29.084 29.084 REGION REL REGION REL POWER 0.94 1.00 1.00 0.92 1.03 1.03 1.08 1.05 1.08 1.05 0.93 1.03 1.03 0.96 13 13 22 1.116 1.116 29.780 RING REL POWER RING 0.96 1.14 1.14 1.06 1.06 1.14 1.14 1.14 1.09 1.14 1.09 0.65 12 12 24 1.128 1.128 30.578 APRM GAFS 1.02 1.02 1.00 1.00 0.98 0.99 11 26 1.150 1.150 31.298 B 10 B_1O 28 1.181 31.895

- - - - NUCLEAR LIMITS BY REGION *************** ***************

9 30 1.203 1.203 32.380 8 32 11.211

.211 33.056 7 8 I 9 7 34 1.216 33.871 0.867 0.867 13-40 0.860 31-40 0.885 39-40 6 36 1.214 34.675 0.750 17-42-15 0.759 33-44-15 I 0.767 41-36-15 5 38 1.201 35.119 0.688 09-36-13 0.704 33-42-13 I 0.702 43-36-13 A_4 40 1.166 34.452 0.622 0.622 11-36-13 11 13 0.652 33-36-18 I 1.155 41-36-13 3 42 1.077 31.119

- - - - - - - - - - - - - - - - - -+-

+ - - - - - - - - - - - - - - - - - -+- - - - - - - - - - - - - - - - -- 2 44 0.846 23.396 44 5 6 **********

11 46 0.242 6.163 0.838 13-32 0.821 31 -32 31-32 I 0.865 39-32 ** MFLCPR **

0.758 09-20-13 0.714 27-28-18 I 0.769 43-34-15 ** MAPRAT **

0.700 11 11-20-13 13 0.663 33-34-18 I 0.895 41-34-13 ** MFDLRX **

0.611 09-20-13 0.566 27-28-17 I 0.895 43-34-15 ** MFLPD **

- - - - - - - - - - - - - - - - - -+-

+ - - - - - - - - - - - - - - - - - -+- + - - - - - - - - - - - - - - - -- **********

NODES W/ LIMITS>

LIMITS > 1 1 1 2 3 0.864 0.864 13-14 0.822 21-14 21 -14 I 0.852 39-14 FLCPR 0o 0.749 0.749 11-18-15 0.748 19-10-13 0.736 41-18-13 APRAT 0o 0.691 0.691 09-18-13 09 13 0.693 19-12-13 I 0.684 43-18-13 FDLRX 0o 0.619 0.619 11-18-13 11-18-13 0.602 19-10-13 I 0.613 41-18-13 FLPD 11

- - - - THE 10 10 MOST LIMITING BUNDLES BUNDLES *****************

FLCPR FLCPR LOC LOC CPR CPR LIMIT LIMIT I APRAT APRAT LOC LOC APLHGR LIMIT APLHGR LIMIT FDLRX FDLRX LOC LOC LPD LPD LIMIT FLPD LIMITj FLPD LOC LOC LPD LIMIT LPD LIMIT

~------ ------ ------- --------

0.909 0.909 39-40 39-40 1.518 1.518 1.381 1.381 0.867 0.867 43-34-15 43-34-15 8.01 8.01 9.25 9.25 0.895 0.895 41-34-13 41-34-13 9.53 9.53 0.00 0.001 1 . 155 1.155 41 13 8.45 41-36-13 8.45 13.40 13.40 0.905 0.905 39-36 39-36 1.525 1.525 1.381 1.381 0.866 0.866 41-36-15 41-36-15 8.09 8.09 9.35 9.35 0.704 0.704 33-42-13 33-42-13 9.43 9.43 0.00 0.001 1 .058 1.058 35 13 8.36 35-42-13 13.40 8.36 13.40 0.894 0.894 39-32 39-32 1.544 1.544 1.381 1.381 0.854 0.854 35-42-15 35-42-15 7.55 7.55 8.84 8.84 0.702 0.702 43-36-13 43-36-13 9.41 9.41 0.00 0.001 0.895 0.895 43-34-15 8.33 43-34-15 13.40 8.33 13.40 0.893 0.893 35-40 35-40 1.546 1.546 1.381 1.381 0.840 0.840 33-44-15 33-44-15 7.78 7.78 9.26 9.26 0.694 0.694 35-44-13 35-44-13 9.30 9.30 0.00 0.001 0.652 0.652 33-36-18 8.19 33-36-18 13.40 8.19 13.40 0.892 0.892 31-40 31-40 1.548 1.548 1.381 1.381 0.833 0.833 33-36-18 33-36-18 7.72 7.72 9.26 9.26 0.691 0.691 41-42-05 41-42-05 9.27 9.27 0.00 0.001 0.610 0.610 33-44-13 8.18 33-44-13 8.18 13.40 13.40 0.888 0.888 37-38 37-38 1.554 1.554 1.381 1.381 0.83341-28-17 0.833 41-28-17 9.49 9.49 11.38 11.38 0.687 0.687 35-36-18 35-36-18 9.20 9.20 0.00 0.001 0.606 0.606 35-34-18 8.12 35-34-18 8.12 13.40 13.40 0.883 0.883 39-28 39-28 1.563 1.563 1.381 1.381 0.825 0.825 25-42-17 25-42-17 9.35 9.35 11.34 11.34 0.685 0.685 39-40-05 39-40-05 9.18 9.18 0.00 0.001 0.600 0.600 27-42-17 8.04 27-42-17 13.40 8.04 13.40 0.880 0.880 37-34 37-34 1.568 1.568 1.381 1.381 0.818 0.818 35-34-18 35-34-18 7.38 7.38 9.02 9.02 0.676 0.676 39-36-13 39-36-13 9.05 9.05 0.00 0.001 0.598 0.598 41-28-16 8.01 41-28-16 8.01 13.40 13.40 0.876 0.876 37-30 37-30 1.576 1.576 1.381 1.381 0.816 0.816 39-42-06 39-42-06 7.13 7.13 8.73 8.73 0.672 0.672 41-44-05 41-44-05 9.00 9.00 0.00 0.001 0.593 0.593 43-38-13 7.95 43-38-13 7.95 13.40 13.40 0.872 0.872 43-32 43-32 1.583 1.583 1.381 1.381 0.816 0.816 41-32-15 41-32-15 7.21 7.21 8.84 8.84 0.671 0.671 35-40-13 35-40-13 8.99 8.99 0.00 0.001 0.591 0.591 41-32-15 7.92 41-32-15 7.92 13.40 13.40

BRUNSWICK- 2 BRUNSWICK-2 1OTODAY-07.OO.27 8902 MWDfMTU WK-1016 10TODAY-07.00.27 MWD/MTU TRIGR=2HR REV=usepO6 REV=usep06

- - - - CONTROL ROD DATA *************

02 06 10 14 18 22 26 30 34 38 42 46 50 51 51 47 47 43 26 -- 20 -- 26 43 39 39 35 - - -- 26 -- 16 -- 08 -- 16 -- 26 --

- 35 31 - -

- 31 27 --

-- 20 - - 08 -- 18 -- 08 -- 20 -- -- 27 23 --

- 23 19 --

- 26 - - 16 -- 06 -- 12 -- 26 -- -- 19 15 15 11 26 -- 20 -- 26 11 07 07 03 03 02 06 10 14 18 22 26 30 34 38 42 46 50 RODS OUT OF MIRROR SYMMETRY: 26-35 26-19 34-19 SUBST. RODS:

CALIBRATED LPRM READINGS ************

- - - - *LPRM FAILED SENSORS* *OTHER FAILED SENSORS*

OTHER 45 32.7 43.5 44.4 38.9 26.9 LOCATION STATUS SENSOR STATUS 46.2 60.6 60.2 56.7 37.5 ~-~-----

54.3 59.7 59.3 56.9 44.3 52.1 52.4 54.7 52.9 88.1 37 26.7 46.0 53.3 54.2 52.7 39.6 D D

38.8 63.3 55.6 56.5 60.3 57.2 C C

43.0 61.2 58.9 60.6 61.6 57.9 B B

36.2 54.6 45.7 47.7 52.5 86.6 A A

29 34.0 48.0 55.6 58.3 54.2 44.4 49.7 59.7 52.0 55.3 55.6 60.0 60.4 59.4 58.7 58.3 60.2 60.2 53.4 48.0 45.5 43.1 48.7 56.5 21 32.1 48.6 54.7 50.5 52.2 42.1 46.0 62.7 54.6 48.3 54.5 60.3 55.4 61.0 59.6 57.4 61.6 61.2 51.0 47.3 47.8 45.9 49.9 55.9 13 39.5 47.5 48.7 44.8 31.0 57.4 62.4 60.6 58.7 44.8 66.9 60.1 59.5 60.6 53.7 66.8 51.5 46.5 53.4 51.5 05 31.9 32.1 26.7 45.9 46.5 37.2 53.1 55.3 43.5 49.3 55.8 37.0 04 12 20 28 36 44

BRUNSWICK NUCLEAR PLANT c

C Progress Energy Continuous Use Use DATE COMPLETED DATE COMPLETED _ _ _ _ _ _ _ _ __ FREQUENCY:

FREQUENCY:

UNIT UNIT _2_2 % PWR

% PWR GMWE_ _

GMWE A. OnceI24 Once/24 hours hours when when operating operating ~ 23%

23% rated rated SUPERVISOR_ _ _ _ _ _ _ _ _ _ __

SUPERVISOR_______________________________ power thermal power REASON FOR REASON FOR TEST TEST (check (check one one or or more) more)

_ Routine Routine Surveillance Surveillance B. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Within 12 hours after after thermal power power is is

_W/O#

wio # _______________________ ~ 23% of of rated thermal power power

_ Other (explain)

PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT 2

2PT-01.11 2PT-O1 .11 CORE PERFORMANCE PARAMETER CHECK REVISION 7 1 2PT - 0 1.11 2PT-O1.11 Rev. 7 Page 11 of 14/14

1.0 1.0 PURPOSE PT provides This PT procedure for obtaining the basic core performance provides aa procedure parameters required by Technical Specifications and calibrates APRM channels to parameters read greater than or equal to actual core thermal power. The procedure satisfies Technical Specifications SR 3.2.1.1, SR 3.2.2.1, SR 3.2.3.1, and SR 3.3.1.1.3.

2.0 20 REFERENCES 2.1 Technical Specifications 2.2 1-P-A (GESTAR II), Amendment 19 NEDE-24011-P-A NEDE-2401 19 2.3 NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications 2.4 Core Operating Limits Report 2.5 Letter, L. M. Quintana to B. A. Morgan, Linear "Linear Heat Generation Rate Monitoring,"

Monitoring, October 9, 1989, LMQ: 89-241 9,1989, 2.6 00 1-72, Plant Process Computer System Operating Instruction 001-72, 2.7 00P-55, OOP-55, Process and ERFIS Computer System Operating Procedure 2.8 OPT-01.8C, Hand Calculation of AGAFs 2.9 OPT-01.8D, OPT-Ol .8D, Core Thermal Power Calculation 2.10 OENP-24.19, Operation of the BWR Process Computer Backup Program 2.11 20P-09, 2OP-09, Neutron Monitoring System Operating Procedure 2.12 GE SIL 516 Supplement 1, Recirculation Drive Flow/Core Flow Correlation 2.13 NEDO-32465-A, licensing Licensing Topical Report: Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applicability GE Nuclear Energy, August 1996.

2.14 EC 49527, Modify Thermal Limits Surveillance Method to Account for Powerplex CPR Convergence Failures.

2PT-01 .11

/2PT-01.11 Rev. 7 14 Page 2 of 14/

3.0 3.0 PRECAUTIONS AND PRECAUTIONS AND LIMITATIONS LIMITATIONS 3.1 3.1 Special care Special care should should be be taken taken in in verifying verifying data. Errors on data. Errors the nonconservative on the nonconservative side could side could cause cause operation operation that that might might lead lead to violation of to aa violation of Technical Technical Specifications.

3.2 3.2 the value of IF the IF of aa core performance performance parameter exceeds its parameter exceeds limits, THEN the its limits, the Unit SCO Unit SCQ should should be be immediately notified.

3.3 During APRM gain adjustments, the plant should be held at aa steady state operating condition. During APRM gain gain adjustments, the affected APRMs may be bypassed.

3.4 IF APRM gain adjustments are made, THEN Independent Verification is required.

4.0 PREREQUISITES Thermal power is greater than or equal to 23%

5.0 SPECIAL TOOLS AND EQUIPMENT None 6.0 ACCEPTANCE CRITERIA OTE:

NOTE: Attachment 3 contains definitions and abbreviations of terms.

6.1 This PT is acceptable when it is shown by the certifying signature that the parameters have been obtained correctly according to this instruction and these conditions exist:

6.1.1 6.1 .1 CMFLCPR is less than or equal to 1.0 (See Attachment 2 for parameter location on the core performance edit).

6.1.2 CMAPRAT is less than or equal to 1.0 (See Attachment 2 for parameter location on the core performance edit).

6.1.3 CMFDLRX is less than or equal to 1.0. 1.0. (See Attachment 2 for parameter location on the core performance edit; applicable to AREVA fuel bundles only) 6.2 6.2 At least three three operable APRMs are adjusted such such that that the the APRM gain adjustment factors (GAFs)(GAFs) are less less than or equal 1 .00. The APRM gain equal to 1.00.

adjustment factor is is determined determined by periodic NSS by either the periodic NSS Core Performance Core Performance Log Log (Attachment (Attachment 2), 2), Display Display 820 820 (Heat (Heat Balance/Core Balance/Core Mon),Mon), or hand or hand calculation of calculation of AGAFs AGAFs (OPT-01.8C).

(OPT-Ol .8C). IF IF APRM APRM gain adjustments are gain adjustments are performed, THEN the performed, THEN the postadjustment postadjustment AGAFs AGAFs are verified by are verified Display second Display by aa second 820 820 or or OPT-01.8C.

OPT-Ol .8C.

/2PT-01.11 2PT-01.11 Rev.

Rev.7 7 Page3of14 Page 3 of 14/

7.0 PROCEDURALSTEPS PROCEDURAL STEPS Initials NOTE:

NOTE: Attachments 22 and 33 may be discarded after completion of test.

NOTE: IF unable to obtain the required process computer edits, THEN the On-Shift Reactor Engineer should be contacted prior to performance of Section 7.2.

7.1 Using the Process Computer NOTE:

NOTE: Plant process computer operating instructions and report codes are contained within procedures 001-72 and OOP-55.

00P-55.

7.1.1 7.1 .1 OBTAIN an edit of the process computer core performance program.

7.1 .2 IF there are failed inputs on the failed sensor list, THEN ENSURE correct values have been substituted where appropriate.

NOTE: Attachment 2 shows the location of NSSFFLG on the Core Performance Log.

H 7.1.3 IF NSSFFLG is equal to 1, THEN GO TO Step 7.1.4.

1. IF NSSFFLG is NOT equal to 1, THEN PERFORM the following:

a. NOTIFY the On-Shift Reactor Engineer to evaluate if core flow is accurate for thermal limit calculations.

b. IF core flow was changed by the On-Shift Reactor 7.1.3.1 .a, THEN OBTAIN a new Engineer in Step 7.1.3.1.a, Core Performance Log edit.

2PT-01 .1 1 12PT-01.11 Rev. 7 14 Page 4 of 14/

7.0 7.0 PROCEDURAL STEPS PROCEDURAL STEPS Initials Initials NOTE:

NOTE: Attachment 22 shows the respective locations shows the of WFWFFLG, locations of WFWFFLG, NSSCUFLG, NSSCUFLG, NSSCRFLG on the Core Performance Log.

and NSSCRFLG 7.1.4 IF WFWFFLG AND NSSCUFLG IF NSSCUFLG AND NSSCRFLG are equal to 1, 1, THEN GO TO Step 7.1.5.

1.

1. IF WFWFFLG OR NSSCUFLGNSSCUFLG OR NSSCRFLG are NOT NOT equal to 1, 1, THEN PERFORM PERFORM the following:

a. NOTIFY the On-Shift Reactor Engineer to evaluate NOTIFY accuracy of inputs to the heat balance calculation.

b. IF inputs to the heat balance were changed by the On-Shift Reactor Engineer in Step 7.1.4.1 .a, THEN 7.1.4.1.a, OBTAIN a new Core Performance Log edit.

7.1.5 DETERMINE from the core performance edit, if criteria listed in Section 6.1 are met.

NOTE: Locations on the core performance edit where thermal limit parameters are found are indicated on Attachment 2.

7.1.6 IF limits specified in Section 6.1 are NOT satisfied, THEN NOTIFY the Unit SCO of the condition.

1. NOTIFY the On-Shift Reactor Engineer to take action to restore thermal limits to acceptable values.

NOTE: Attachment 2 shows the location of the APRM GAFs. The APRMs are ordered: APRMs 1, 2, 3, 4.

7.1.7 DETERMINE, from the core performance edit, if Acceptance Criteria listed in Section 6.2 are satisfied (at least three APRM gain adjustment factors are less than or equal to 1.00).

7.1.8 7.1 .8 IF an APRM gain adjustment is necessary, THEN PERFORM applicable section of 20P-09.2OP-09.

7.1.9 IF an APRM gain change was performed, THEN /

OBTAIN from the process computer a copy of (nd.Ver.

IndVer.

Display 820, Heat Balance/Core Mon, OR PERFORM 0PT-01 .8C to ensure APRM GAFs satisfy the OPT-01.8C requirements of Acceptance Criteria, Section 6.2.

2PT-01 .1 1 12PT-01.11 Rev. 77 Rev. Page 55 of Page of 141 14

7.0 7.0 PROCEDURAL STEPS PROCEDURAL STEPS Initials Initials NOTE:

NOTE: Reference 2.5 Reference 2.5 states states that NRC NRC expects LHGR monitoring expects LHGR monitoring (CMFLPD)

(CMFLPD) to to remain the same as CPR and APLHGR for GNF fuel (i.e., (Le., to restore LHGR LHGR next 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months ).

hours, or be below 23% power within the next within limits within 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months , 7.1.10 DETERMINE, from the core performance edit, if CMFLPD is less 1.00 (Attachment 22 for less than or equal to 1.00 CMFLPD location on the core performance edit).

7.1.11 IF CMFLPD is greater than 1.00, IF 1.00, THEN NOTIFY the Unit SCO of the condition.

1.

1. NOTIFY the On-Shift Reactor Engineer to take action to restore CMFLPD to an acceptable value.

7.1.12 ENSURE Acceptance Criteria listed in Section 6.0 have been satisfied.

7.1.13 ATTACH the collected edits.

7.2 Using a Process Computer Backup Program NOTE: This section is performed only when Section 7.1 can NOT be completed.

The On-Shift Reactor Engineer should be contacted to perform this section.

7.2.1 OPT-Ol .8D to calculate core thermal power.

PERFORM OPT-01.8D NOTE: OENP-24.19 should be referenced for instructions on utilizing the backup program.

7.2.2 OBTAIN LPRM readings, control rod pattern, core flow, reactor pressure, and additional data as required by the computer backup program AND RUN the program.

7.2.3 OBTAIN the output of the backup program.

7.2.4 DETERMINE from the backup edit if criteria listed in Section 6.1 are met.

2PT-01 .11

/2PT-01.11 Rev. 77 Rev. Page 66 of Page of 14/

14

7.0 PROCEDURAL STEPS Initials 7.2.5 IF limits specified in Section 6.1 are NOT satisfied, THEN NOTIFY the Unit SCQ SCO of the condition.

1. NOTIFY the On-Shift Reactor Engineer to take action to restore thermal limits to acceptable values.

7.2.6 OPT-Ol .8C to determine if acceptance PERFORM OPT-01.8C criteria listed in Section 6.2 are satisfied.

7.2.7 IF APRM gain adjustment is necessary, THEN PERFORM applicable section of 20P-09.

7.2.8 IF APRM gain change was performed, THEN PERFORM /

OPT-Ol .8C to ensure APRM gain adjustment another OPT-01.8C Ind.Ver.

IndVer.

factor satisfies the requirements of Acceptance Criteria, Section 6.2.

NOTE: Reference 2.5 states that NRC expects LHGR monitoring (CMFLPD) to remain the same as CPR and APLHGR for GNF fuel (i.e., to restore LHGR within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be below 23% power within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ).

7.2.9 DETERMINE, from the backup edit, if CMFLPD is less 1 .00.

than or equal to 1.00.

7.2.10 IF CMFLPD is greater than 1.00, THEN NOTIFY the Unit SCO of the condition.

1. INITIATE actions to restore CMFLPD to an acceptable value.

7.2.11 ENSURE Acceptance Criteria listed in Section 6.0 have been met satisfactorily.

7.2.12 ATTACH the backup program edits.

7.3 ENSURE the required information has been recorded on the cover page.

7.4 NOTIFY the Unit SCO when this test is complete or found to be unsatisfactory.

2PT-01.11 12PT-01.11 Rev.77 Rev. Page7of14 Page 7 of 141

ATTACHMENT 11 1 of 11 Page 1 Certification and Review Form General Comments and Recommendations Initials Name (Print)

Test procedure performed by _ __

Exceptions to satisfactory performance _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Corrective action required _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Corrective action Test procedure has been satisfactorily completed:

Unit SCO:

Signature Date Test procedure has NOT been satisfactorily completed:

Unit seo:

SCO:

Signature Date Test has been reviewed by:

Shift Manager: ~=-=--_~_ _ _ _ _ _ _ _ _ __

Signature Date 2PT-O1 .11 12PT-01.11 Rev. 7 14 Page 8 of 141

ATTACHMENT 2 Page 1 1 of 2 Limit Positions on the Core Performance Log - Long Edit BRUNSWICK-1 BRUNSWICK-i WK-0739 07SEP29-09.00.27 14505 MWD/MTU WK-0739 07SEP29-09.0O.27 MWO/MTU TRIGR=2HR REV=usep06 REV=usepo6 CORE PERFORMANCE LOG --- LONG EDIT - - -

TL 12 12 TLO TBPINSTBPINS ALL MOC TO EOC OPTB POW DEP MCPR OPTS CALCULATION :: HEAT BALANCE CTP CALCULATION SYMMETRY :: FULL CYCLE: 16 16

PJ(IAL

AXIAL REL POWER*

CONDITIONS FLOW (MLB/HR) CORE PARAMTRS PARAMTRS NUCLEAR LIMITS LOCATION NODE NOTCH REL REL-POW EXP(GWD/MT)

POW EXP(GWD/MT)

G 5 WT 78.02(101.3%) CMEQ CMEO 0.3118 PPCS P-PCS 0.02 07-28-09 25 0.177 4.766 CMFLCPR 92O:9% WDP WOP 77.74 77.74 CAEO 0.16670.1667 P-PCFC 0.02 07-28-09 24 GG 8.~78 13.333 WFWFFLG 1044. NSSFFLG 1. 1. CADA 0.1538 CMFLCPR CAOA CMFLCPR~ 8.909 39-18 23 02 0.784 18.881 DHS WFW 12.72 12.72 CAVF 0.4773 P=O.OOO F=O.000 P=O.000 F=O.OOO 00 22 04 0.939 0.939 23.791 CRD 0.102 CYEXP 14bUb,;j Mw',,~NSSCUFLG

<.,;yt:;u' 14505 WFWFFLG 1.

NSS CUFLG 1.

1.

CAPD CAPO 58.934 CMAPRAT RWL 187.5460 187.5460 CMAPRAT", I O.OC7 P=O.OOO F=O.000 P=O.000 8.867 41 32 F=O.OOO 82 17 17 -21 21 20 86 DC 08 1.885 1.088

.088 27.184 29.224 II CMAPRAT CMAPT I

~ eAVEX 27956.1 MWOlfliLNSSCRFLG CRFLG 1. 1. 18.7146 CMFDLRX*O-8i CDLP 18.7146 CMFDLRX. G.7S141-30-17 A1fli7 19 19 10 10 1.102 30.344 FLNSSCUFLG ~onl TN~ 00 1~~WO 34.22 34.22 DPCC 24.0078 CMFLPD CMFLPD~781 41-30-17 18 12 1.097 38.981 KEFF 0.9933 CMINCPR"",- 1 ~ 17 14 1.078 CMFDLRX 1.035 30.565 TI LOCATION ON 11 22 3 44 5 66 77 8 9 15 0 935 NSSCRFLG I AXIAL REL POWER 0.53 1.08 1.08 1.17 1.17 1.17 1.17 1.15 1.15 1.10 1.10 1.08 1.08 0.99 1.05 1.06 0.95 O.6_1&

REGION REL POWER 0.94 1.06 0.96 0.85 1.13 1.06 0.96 1.13 1.08 1.08 0.90 1.06 1.06 0.97 RING REL POWER 1.

1.1414 1. 12 1.14 1.12 1.14 1. 1.1414 1.17 1.17 1. 03 0.65 1.03 30 578

~ APRM GAFS 0.99 1.00 1.00 1.000.99 1.00 0.99 11 26 BB_ 10 28 APRM GAFS AFS h**h***hh** NUCLEAR LIMITS BY REGION *************** *************** 3D CMINCPR 32 .211 33.056 7

7 8 8 9 9 7 34 1.216 33.871 0.842 13-36 13-36 0.868 31-36 31-36 0.909 0.909 39-36 39-36 6 36 1.214 34.675 0.756 17-38-19 0.756 0.830 27-38-20 0.817 35-38-19 0.817 35-38-19 5 38 1.201 35.119 0.667 13-44-04 0.667 13-44-04 0.723 33-38-19 0.688 35-36-19 0.688 35-36-19 A4 40 1.166 34.452 0.667 13-44-04 0.667 13-44-04 0.723 33-38-19 0.723 0.688 35-36-19 0.688 35-36-19 3 42 1.077 31.119

- - - - - - - - - - - - - - - - - -+- - - - - - - - - - - - - - - - - - -+- - - - - - - - - - - - - - - - --

+ + 2 44 0.846 23.396 4

4 5 5 6 6 1 46 0.242 6.163 0.845 11-20 11-20 0.893 29-20 0.905 0.905 39-28 39-28

MFLCPR **

0.724 11-22-0811-22-08 0.854 0.854 27-24-19 0.867 41-32-17 *

MAP MAPRATRAT

0.657 11-20-0811-20-08 0.780 27-22-18 0.781 41-32-17 ** MFDLRX **

0.657 11-20-0811-20-08 0.780 27-22-18 0.781 41-30-17 ** MFLPD *

+-------------------+------------------ ********** # NODES WI LIMITS >> 11 1 2 3 0.872 0.872 13-18 13-18 0.892 31-18 31-18 0.909 39-18 39-18 FLCPR 0o 0.783 17-16-1917-16-19 0.840 27-16-20 35-16-19 0.833 35-16-19 APRAT 0o 0.666 17-14-1917-14-19 0.739 33-16-19 35-14-19 0.702 35-14-19 FDLRX 0o 0.666 17-14-1917-14-19 1 0.739 33-16-19 1 0.702 35-14-19 35-14-19 FLPD 0o

- - - - THE 10 MOST LIMITING BUNDLES *****************

FLCPR LOC CPR LIMIT APRAT LOC APLHGR LIMIT APLHGR FDLRX LOC LPD LIMIT FLPD LOC LPD LIMIT 0.909 39-18 39-18 1.518 1.518 1.381 1.381 0.867 41-32-17 41-32-17 8.01 9.25 0.781 41 41-30-17 17 10.4710.47 13.40 13.40 41-30-17 10.47 0.781 41-30-17 10.47 13.40 13.40 0.905 39-28 39-28 1.5251.381 1.525 1.381 0.866 43-30-17 43-30-17 8.09 9.35 0.78027-22-18 0.780 27-22-18 10.46 10.46 13.40 13.40 0.780 27-22-18 10.46 0.780 10.46 13.40 13.40 0.894 39-22 39-22 1.544 1.544 1.381 1.381 0.854 27-24-19 7.55 8.84 0.739 33-16-19 9.90 13.40 13.40 0.739 33-16-19 9.90 13.40 0.739 13.40 0.893 29-20 1.546 1.546 1.381 1.381 0.840 27-16-20 7.78 9.26 0.737 43-28-17 9.88 13.40 0.73743-28-17 13.40 0.737 43-28-17 0.737 43-28-17 9.88 13.40 13.40 0.892 31-18 31-18 1.5481.381 1.548 1.381 0.833 35-16-19 7.72 9.26 0.737 43-22-17 9.87 13.40 13.40 0.737 0.737 43-22-17 43-22-17 9.87 13.40 13.40 0.888 37-20 37-20 1.554 1.554 1.381 1.381 0.833 41-30-17 41-30-17 9.49 11.38 11.38 0.734 45-30-17 9.83 13.40 13.40 0.734 45-30-17 9.83 13.40 0.73445-30-17 13.40 0.883 41-20 1.563 1.563 1.381 1.381 0.825 27-22-19 9.35 11.34 11.34 0.734 27-14-20 9.83 13.40 0.73427-14-20 13.40 0.734 27-14-20 9.83 13.40 0.734 13.40 0.880 41-16 1.5681.381 1.568 1.381 0.818 41-28-17 41-28-17 7.38 9.02 0.732 39-32-17 9.81 13.40 13.40 0.732 39-32-17 0.732 39-32-17 9.81 13.40 13.40 0.876 35-18 35-18 1.576 1.676 1.381 1.381 0.816 27-28-19 7.13 8.73 0.72429-24-19 0.724 29-24-19 9.70 13.40 13.40 0.724 29-24-19 9.70 13.40 0.724 13.40 0.872 39-14 39-14 1.583 1.583 1.381 1.381 0.816 33-14-19 7.21 8.84 29-20-19 9.66 13.40 0.721 29-20-19 13.40 0.721 29-20-19 9.66 13.40 13.40 2PT-O1.11 12PT-01.11 Rev.7 Rev. 7 r Page9of14 Page 9 Of141

ATTACHMENT 22 Page 22 of 22 Limit Positions on the Core Performance Log - Long Edit

- - - - CONTROL ROD DATA

- - - - DATA *************

02 06 10 10 14 14 18 18 22 26 26 30 30 34 34 38 38 42 46 46 50 50 51 51 51 47 24 24 47 43 43 39 14 14 - 12 12 14 14 39 35 -

- 35 31 31 - 00 00 - - 10 10 - 16 16 - 10 10 20 20 - -

- 31 31 27 27 00 00 0000 -

- 27 27 23 23 10 10 16 16 10 10 20 20 --

- 23 23 19 -

- 19 15 14 14 - 12 12 14 14 15 15 11 11 11 11 07 24 07 03 03 02 06 10 14 18 22 26 30 34 38 42 46 50 RODS OUT OF MIRROR SYMMETRY: 06-31 10-31 42-31 06-27 10-27 42-27 46-27 SUBST. RODS:

CALIBRATED LPRM READINGS ***********

- - - - SENSORS*

LPRM FAILED SENSORS* *OTHER FAILED SENSORS*

OTHER SENSORS*

45 30.7 45.5 51.4 41.9 25.9 LOCATION STATUS SENSOR STATUS 41.2 54.6 61.2 50.7 32.5 -

52.3 59.7 57.3 58.9 39.3 12-21-B 12-21-B MAN 65.1 68.4 59.7 69.9 40.1 20-21-0 20-21-D MAN 37 21.7 41.0 55.3 60.2 54.7 42.6 0D 29.8 52.3 52.6 56.5 55.3 54.2 C C

39.0 63.2 56.9 58.6 58.6 60.9 B B

36.2 70.6 54.7 51.7 58.5 69.6 A A

29 17.0 39.0 56.6 61.

61.33 59.2 52.4 23.7 48.7 54.0 59.3 57.6 65.0 31.4 57.4 58.7 57.3 57.2 56.2 21.4 54.0 51.5 44.1 50.7 59.5 21 25.1 43.6 57.7 62.5 58.2 49.1 36.0 53.7 53.6 58.3 57.5 59.3 49.4 65.0 58.6 59.4 58.6 55.2 52.0 65.3 51.8 48.9 54.9 59.9 13 40.5 54.5 59.7 52.8 34.0 53.4 54.4 57.6 55.7 43.8 64.9 59.1 60.5 60.6 52.7 69.8 59.5 55.5 62.4 63.5 05 34.9 41.1 28.7 44.9 50.5 35.2 49.1 44.3 40.5 57.3 43.8 43.0 04 12 20 28 36 44 2PT-O1.11 12PT-01.11 Rev.7 Rev. 7 Page 10lOof 14 of 14/

ATTACHMENT 33 Page 11 of Page of 33 Definitions and Abbreviations Found on Core Performance Performance Edit Edit 1.

1. APLHGR Nodal Average Planar Linear Heat Generation Rate (kw/ft)

2. APLHGR Nodal limiting value of APLHGR (kw/ft)

LIMIT

3. APRAT Maximum fraction of limiting APHLGR rate

=Maximum of APLHGR

=

APLHGR LIMIT

4. APRM GAFS Average Power Range Monitor Gain Adjustment Factors

5. CMAPRAT Core Maximum APRAT (TIS 3.2.1). Maintaining this value 1 .00 ensures that the peak cladding temperature will be

1.00 kept << 2200° 2200°FF and, therefore, core geometry will be maintained during a LOCA.

6. CMINCPR The MCPR used to determine the requirement for RBM operability iaw Tech Spec 3.3.2.1. This is the lowest core CPR and corresponding bundle location.

7. CMFDLRX Core Maximum Fuel Design Limit Ratio X, similar to CMFLPD for GNF fuel, but only applies to AREVA fuel.

8. CMFLCPR Core Maximum Fraction of limiting CPR (TIS (T/S 3.2.2).

Maintaining this value::;

value 1.001 .00 ensures that departure from nucleate boiling will not occur.

9. CMFLPD Core Maximum Fraction of Limiting Power Density. Formerly 1 .00 value 1.00 a technical specification limit, maintaining this value::;

ensures that the fuel cladding does not exceed 11% % plastic strain. (GNF fuel bundles only)

10. CPR Critical Power Ratio

11. CPR LIMIT The limiting CPR

12. FDLRX Fuel Design Limit Ratio X (AREVA fuel bundles only)

=

= LHGR LHGR Limit

/2PT-01.11 2PT-01 .1 1 Rev. 7 Page 111 1 of of 14/

14

ATTACHMENT 33 Page 22 of of 33 Definitions and Abbreviations Found on Core Performance Edit 13.

13. FLCPR Maximum Fraction of Limiting CPR

=Maximum of CPR LIMIT

=

CPR 14.

14. FLPD Fraction of Limiting Power Density (kw/ft)

=

LHGR

= LPD LHGR Limit LPD Limit

15. LHGR Power generation in 1 1 foot of aa fuel rod (kw/ft)

16. LPD Limiting fuel rod Power Density (LHGR)

17. LPD LIMIT Fuel Rod Power Density Limit (LHGR limit)

18. NSSCRFLG The NSSCRFLG on the Core Performance Log indicates when CRD flow used in the heat balance calculation is valid.

NSSCRFLG = B020 is valid.

= 1: indicates that 8020 NSSCRFLG = = 2 indicates that 8020 B020 is invalid. The last good value is used to help prevent use of non-conservative values in the heat balance. Check page 2 of MON edit for Failed Sensors.

19. NSSCUFLG The NSSCUFLG on the Core Performance Log indicates when RWCU cleanup flow values used in the heat balance calculation are valid.

NSSCUFLG = WCUI, WCU3, 8047,

= 1: indicates that WCU1, B047, and 8048 B048 are valid.

NSSCUFLG = = 2: indicates that WCU1, WCU3, 8047, B048 B047, or 8048 are invalid. The last good value is used to help prevent use of non-conservative values in the heat balance. Check page 2 of MON edit for Failed Sensors.

/2PT-01.11 2PT-O1.11 Rev.7 Rev. 7 l2of Page 12 14 of 14/

ATTACHMENT 3 Page 3 of 3 Definitions and Abbreviations Found on Core Performance Edit

20. NSSFFLG The NSSFFLG on the Core Performance Log indicates which core flow value is used for thermal limit calculations NSSFFLG == 1: indicates WTCF wrCF Calculated Total Core Flow representing the summation of the 20 single tap jet pumps. The wrCF with WDP comparison of WTCF WOP is :s; 5%.

NSSFFLG = = 2: indicates WDP WOP Core Plate Differential Core Flow, which is flow resulting from the Core DP and Reactor Power to WTCF wrCF correlation.

NSSFFLG =

= 3: indicates a manually inserted value for WTCF wrCF NSSFFLG = wrCF but the comparison with WDP

= 4: indicates WTCF is> 5%

21. WFWFFLG The WFWFFLG on the Core Performance Log indicates when instantaneous or smoothed feedwater flow values are used in the heat balance calculation.

WFWFFLG = = 1: indicates smoothed feedwater flow from U2NSSWFWA and U2NSSWFWB is used in U2CP U2CP_AFWA AFWA and U2CP_AFWB U2CP _AFWB respectively. This condition is expected during steady state operation.

WFWFFLG = = 2: indicates instantaneous feedwater flow from U2C32B022 and U2C32B023 is used in U2CP U2CP_AFWA AFWA and U2CP_AFWB U2CP _AFWB respectively. This condition can be expected following a large change in reactor power.

2PT-01.11

\2PT-01.11 Rev.77 Rev. l3of Page 13 14 of 141

REVISION

SUMMARY

Revision 7 incorporates EC 70517, Unit 2 Core Reload. This resulted in deletion of old Precaution and Limitation 3.5, all references to Attachment 4 and the attachment itself, revision of Steps 7.1.6 and 7.2.5 and the addition of notes where appropriate.

Acceptance Criteria 6.1.3 6.1 .3 was added for CMFDLRX. "Shift Shift Superintendent" Superintendent has been Shift Manager".

changed to "Shift Manager.

Revision 6 incorporates Child EC 69315 (Master EC 67951) for installation of Powerplex Ill.

III.

Revision 5 incorporates EC 62831 to provide new Attachment 4 for removal of overly conservative PPC thermal limits under certain operating conditions.

Revision 4 incorporates EC 62384, revising definition of WTSUB on Attachment 3, deleting Attachment 4, Precaution and Limitation 3.5, and reference to Precaution and 7.1 .3.2, and steps referencing Attachment 4.

Limitation 3.5 previously contained in Step 7.1.3.2, Revision 3 adds rods 47-36 and 45-34 to Attachment 4 for MCPR monitoring when PPX CPR convergence fails.

Revision 2 adds a method to account for PPX CPR convergence failures and allows the

>Ll>BU edits.

Reactor Engineer or PPX software to be used to obtain >LI>BU Revision 11 incorporated EC, 47907, Unit 2 Extended Power Uprate Implementation, and EC 46730, Replace Unit 2 Power Range Neutron Monitoring System, required changes and updated to Word 2000 software.

Revision 0 was issued in accordance with ESR 00-00442, Unit 1I Power Range Neutron OPT-Ol .11 be separated into unit specific Monitoring Replacement, which required the OPT-01.11 procedures.

2PT-01.11 12PT-01.11 Rev.77 Rev. l4of Page 14 14 of 141

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C002 (RO)

LESSON TITLE: Determination of Drywell Volumetric Average Temperature LESSON NUMBER: LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AO1 REVISION NO: 01

Determination of Determination Drywell Volumetric of Drywell Average Temperature Volumetric Average SAFETY CONSIDERATIONS:

SAFETY None None EVALUATOR NOTES: NOTES: (Do not read to performer)

1. This JPM is performed in the classroom or simulator for Unit Two.

1.

2. IfIf performed in the Simulator:

a. Ensure all simulator computer screens are OFF prior to commencing JPM.

b. IC-11.

Reset the simulator to IC-i 1.

c. Input override values to the following points to obtain the associated readings on CAC CAC-TR-4426-1A11 B/2A12B TR-4426-i A/i BI2A/2B

- Div 2A (Channel 3) -5823 40.0

- Div 2A (Channel 4) -5824 185.5

- Div 1A iA (Channel 4) -5822 185.5

- Div 2B (Channel 1) -5802 174.1 174.1

- Div 1lB B (Channel 2) -5803 168.3

- Div 2B (Channel 2) -5804 162.7

- Div 1lBB (Channel 3) -5805 139.3

Div 2B (Channel 3) -5806 136.8

Div 1lBB (Channel 4) -5807 133.5

Div 2B (Channel 4) -5808 40.0

- Div 1lBB (Channel 5) -5809 124.5

Div 1AiA (Channel 3) -5812 121.6

Div 2B (Channel 6) -5813 119.2

- Div 1A IA (Channel 5) -5817 88.7

- Div 1A IA (Channel 6) -5818 40.0

- Div 2A (Channel 5) -5819 88.7

Div 2A (Channel 6) -5820 88.7

3. If performed in the classroom, provide Recorder Attachment with readings to performer.

4. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the performer.

5. The trainee will need a calculator to perform this JPM.

OPT-I 6.2.

6. The trainee will be given a copy of OPT-16.2.

7. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.

LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AOI Page 22 Page REV. 01 REV.

Determination of Drywell Volumetric Average Temperature Read the following to the JPM performer.

TASK CONDITIONS:

th 15 th

1. Today is the 15 of the month.

1.

2. Drywell air RTDs CAC-TE-1258-8, CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable.

3. An LCO has been established that requires the performance of OPT-i 6.2, Drywell OPT-16.2, Volumetric Average Temperature, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

CAC-TY-4426-i and 2 Microprocessors are not available for use.

4. The CAC-TY-4426-1

5. The Process Computer and ERFIS are not available.

6. You have been given permission by the Unit CRS to perform this test.

7. The Unit CRS will record required cover page information INITIATING CUE:

You have been directed by the Unit Two CRS to perform OPT-16.2, Drywell Volumetric Average Temperature, and record the Volumetric Average Temperature (Step 7.7.1.6) and the results of the test (circle choice) in the table below.

DRYWELL VOLUMETRIC AVERAGE TEMPERATURE SAT OF

°F UNSAT LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AOI Page 3 REV. 01

Determination of Determination of Drywell Drywell Volumetric Average Temperature Volumetric Average Temperature PERFORMANCE CHECKLIST NOTE: Sequence NOTE: Sequence is is assumed assumed unless unless denoted denoted inin the the Comments.

Comments.

Step 11 - Obtain current revision of OPT-16.2 and verify if applicable.

OPT-16.2 Current revision of OPT-I 6.2 obtained and verified as required.

TIME START TIME START _ _ _ __

NOTE: Figure 11 may be used as aa worksheet but is NOT required to be retained.

NOTE: All temperatures should be rounded off to the nearest tenth of aa degree.

NOTE: Inoperable channels indicate downscale (40.00).

PROMPT: If being performed in a classroom, provide Recorder Attachment to candidate.

Step 2 - Obtain drywell temperature readings for the locations listed in step 7.2.1 Records the following readings:

4426-2A Channel 3 3 - INOP 4426-2A Channel 4 4 - 185.5 (:to. 1)

(+/-0.1) 4426-1 4426-IA A Channel Channel4 4 - 185.5 (:to. 1)

(+/-0.1)

SATIUNSAT*

Step 3 - Add step 7.2.1 recorded temperatures and record in step 7.2.2 3Add 185.5 (:to. 1) and 185.5 (:to.

(+/-0.1) (+/-0.1) (+/-0.2) and documented in step

1) added totaling 371.0 (:to.2) 7.2.2

- CRITICAL STEP**

- CRITICAL SATIUNSAT*

STEP** SAT/UNSAT*

Divide total obtained in step 7.2.2 by the number Step 4 - Divide number of temperatures used 371.0 371.0 (:to.2) divided by 2 equaling 185.5

(+/-0.2) divided 185.5 (:to. 1) and documented

(+/-0.1) 7.2.3 documented in step 7.2.3

- CRITICAL STEP**

- CRITICAL SATIUNSAT*

STEP** SAT/UNSAT*

Step Step 55 - Obtain Obtain drywell drywell temperature temperature readings readings forfor the the locations locations listed in step listed in 7.3.1 step 7.3.1 Records Records the the following following readings:

readings:

4426-28 4426-2B Channel Channel 1 I -

174.1 174.1 (:to. 1)

(+/-0.1) 4426-18 Channel 22 4426-lB Channel - 168.3 168.3 (:to. 1)

(+/-0.1)

SATIU N SAT*

SAT/UNSAT*

LOT-OJT-JP-002-A01 LOT-OJT-JP-002-A01 Page Page 44 REV. 01 REV. 01

Determination of Drywell Volumetric Average Temperature Determination

- Add step 7.3.1 recorded temperatures and record in step 7.3.2 Step 66 Add 7.3.2 168.3 (÷0.1)

(:!:.0.1) and 168.3 (:!:.0.1) 174.1 (÷0.1) added totaling 342.4 342.4 (:!:.0.2) and documented in step

(+/-0.2) 7.3.2

- CRITICAL

- CRITICAL STEP**

STEP** SATIUNSAT*

SAT/UNSAT*

Step 77 - Divide total obtained in step 7.3.2 by the number of temperatures used

(:!:.0.2) divided by 2 equaling 171.2 (+/-0.1) 342.4 (+/-0.2) (:!:.0.1) and documented in step 7.3.3

- CRITICAL STEP** SATIUNSAT*

- CRITICAL STEP** SAT/UNSAT*

Step 88 - Obtain drywell temperature readings for the locations listed in step 7.4.1 Records the following readings:

4426-lB 4426-18 Channel 3 3 - 139.3 (+/-0.1)

(:!:.O. 1) 4426-28 Channel 3 4426-2B 3 - 136.8 (+0.1)

(:!:.O. 1) 4426-18 Channel 4 4426-lB 4 - 133.S 133.5 (:!:.0.1)

(+/-0.1) 4426-28 Channel 4 4426-2B 4 - INOP SATIU NSAT*

SAT/UNSAT*

Step 9 - Add step 7.4.1 recorded temperatures and record in step 7.4.2

(+/-0.1), 136.8 (:!:.0.1) 139.3 (:!:.0.1), (+/-0.1) and 133.S133.5 (:!:.0.1) (+/-0.3) and

(+/-0.1) added totaling 409.6 (:!:.0.3) documented in step 7.4.2 STEP** SA

- CRITICAL STEP**

- CRITICAL SAT!UNSAT*

TlUNSAT*

Step 10-10 Divide total obtained in step 7.4.2 by the number of temperatures used

(+/-0.3) divided by 3 equaling 136.S 409.6 (:!:.0.3) 136.5 (:!:.0.1)

(+/-0.1) and documented in step 7.4.3

- CRITICAL STEP**

- CRITICAL SATIUNSAT*

STEP** SATIUNSAT*

Step 11 - Obtain drywell temperature readings for the locations listed in step 7.5.1 Records the following readings:

4426-18 ChannelS 4426-lB ChannelS 124.5 (:!:.0.1)

- 124.S (+/-0.1)

Channel3 4426-IA Channel 4426-1A 3 - 121.6 (:!:.0.1)

(+/-0.1)

Channel6 4426-28 Channel 6 - 119.2 (:!:.0.1)

(+/-0.1)

SATIUNSAT*

SAT/UNSAT*

LOT -OJT-JP-002-A01 LOT-OJT-JP-002-A01 Page 5 REV. 01

Determination of Determination of Drywell Volumetric Average Temperature Drywell Volumetric Temperature Step 12 Step 12 - Add step step 7.5.1 temperatures and 7.5.1 recorded temperatures and record in step 7.5.2 in step 7.5.2

(~O.1), 121.6 124.5 (+/-0.1),

124.5 (~O.1) and 121.6 (+/-0.1) and 119.2 (~O.1) added 119.2 (+/-0.1) added totaling 365.3 (~O.3) and 365.3 (+/-0.3) and documented in step step 7.5.2

- CRITICAL STEP** SATIUNSAT*

- CRITICAL STEP** SAT/UNSAT*

13 - Divide total obtained in step 7.5.2 by the number Step 13 number of temperatures used used

(~O.3) divided by 3 equaling 121.8 365.3 (+/-0.3) (~O.1) and documented in step 7.5.3 121.8 (+/-0.1)

- CRITICAL STEP**

- CRITICAL STEP** SAT/UNSAT*

SAT/UNSAT*

14 - Obtain drywell temperature readings for the locations listed in step 7.6.1 Step 14 Records the following readings:

4426-1 A Channel 5 4426-IA 5 - 88.7 (~O. 1)

88. 7 (+/-0.1) 4426-1A Channel 6 4426-IA 6 -INOP INOP 4426-2A Channel 5 5 - 88.7 (~O. 1)

88. 7 (+/-0.1) 4426-2A Channel 6 6 - 88.7 (+/-0.1)

(:!:.O. 1)

SATIU NSAT*

SAT/UNSAT*

Step 15 - Add step 7.6.1 recorded temperatures and record in step 7.6.2 15Add 88.77 (~O.1),

88. (+/-0.1), 88.88.77 (~O.1)

(+/-0.1) and 88. 88.77 (+/-0.1) (+/-0.3) and

(~O.1) added totaling 266.1 (~O.3) documented in step 7.6.2

- CRITICAL STEP**

- CRITICAL SATIUNSAT*

STEP** SAT/UNSAT*

Step 16 - Divide total obtained in step 7.6.2 by the number of temperatures used

(+/-0.3) divided by 3 equaling 88.

266.1 (:!:.O.3) 88.77 (~O.1)

(+/-0.1) and documented in step 7.6.3

- CRITICAL STEP**

- CRITICAL SAT/UNSAT*

STEP** SAT/UNSAT*

Step 17 17 7.2.3, 7.3.3, 7.4.3, 7.5.3 and 7.6.3

- Transfer average readings documented in steps 7.2.3,7.3.3,7.4.3,7.5.3 into step 7.7.1 185.5 (+/-0.1), 171.2 (~O.1),

185.5 (:!:.O.1), (+/-0.1), 136.5 (~O.1),

(+/-0.1), 121.8 (~O.1),

(+/-0.1), and 88. (+/-0.1) transferred 7 (~O.1) 88.7 into step 7. 7. 1 7.7.1 SATIU NSAT*

SAT/UNSAT*

LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AO1 Page 66 Page REV. 01 REV. 01

Determination of Drywell Volumetric Average Temperature 18 - Multiply each reading in 7.7.1 by the designated factor and document in step 7.7.1 Step 18

(:!:.0.1), 15.4 9.3 (+/-0.1), 15.4 (+0.1), (:!:.0.1), 46.3 (+0.1),

(:!:.0.1), 54.6 (+/-0.1), (:!:.0.1) documented in step

(:!:.0.1), and 7.1 (+/-0.1) 7.7.1

- CRITICAL STEP** SATIUNSAT*

- CRITICAL STEP** SAT/UNSAT*

19 - Add weighted averages in step 7.7.1 and document as TOTAL in step 7.7.1.6 Step 19Add

(:!:.0.1), 15.2 9.3 (+/-0.1), (:!:.0.1), 54.6 (+/-0.1),

15.2 (+/-0.1), (:!:.0.1), and 7.1 (+0.1)

(:!:.0.1), 46.3 (+/-0.1), (:!:.0.1) added totaling 132.7

(:!:.0.5)

(+/-0.5) and documented in step 7. 7.

7.7.1 1

- CRITICAL STEP** SATIUNSAT*

- CRITICAL STEP** SAT/UNSAT*

PROMPT: If asked the status of computer point C074, report it is unavailable.

Step 20 - Record computer point C074 value in step 7.7.2 Step 7.7.2 marked NIA N/A due to unavailability SAT/U NSAT*

SAT/UNSAT*

Step 21 - Perform steps 7.7.3 and 7.7.4 (only on the first day of the month)

Step 7.7.3 and 7.7.4 marked NIA N/A (not required)

SATIU N SAT*

SAT/UNSAT*

NOTE: Cover page information will be filled out out by the Unit CRS.

Step 22 - Perform step 7.7.5 Cover page information verified complete SAT/U NSAT*

SATIUNSAT*

Step 23 - Determine whether the test is SAT or UNSAT based on the cue sheet instructions Applicant determines the test is SAT because calculated Drywell Diywell Avg Air Temp 132.7 (:!:.0.5)

(+/-0.5) is less than 150°F (acceptance criteria)

STEP**

- CRITICAL STEP**

- CRITICAL SATIUNSAT*

SAT/UNSAT*

LOT-OJT-JP-002-A01 Page 7 REV. 01

Determination of Drywell Volumetric Average Temperature Step 24 - Perform step 7.7.6 Unit CRS notified test is complete SATIU NSAT SATIUNSAT TERMINATING CUE: When CRS is informed of test results, this JPM can be terminated.

TIME COMPLETED _ _ _ __

UNSAT.

NOTE: Comments required for any step evaluated as UNSA T.

LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AO1 Page 8 REV. 01

Determination of Drywell Volumetric Average Temperature RELATED TASKS:

223*206*B1*01 223*206*81*01 Obtain Air and Water RTD Temperatures from the SPTMS lAW OP-24 KIA REFERENCE AND IMPORTANCE RATING:

GEN 2.1.20 4.6/4.6 Ability to interpret and execute procedure steps

REFERENCES:

OPT-16.2, Drywell Volumetric Average Temperature TOOLS AND EQUIPMENT:

Calculator JPM5 Recorder Attachment Simulator or This JPMs ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2. Supplement 1):

Admin - Conduct of Operations REASON FOR REVISION:

HLC2O1O-1 NRC License Exam.

Changed to allow classroom performance for HLC2010-1 LOT-OJT-JP-002-A01 Page 9 REV. 01

Determination of Determination of Drywell Drywell Volumetric Volumetric Average Average Temperature Temperature Validation Time:

Validation Time: ~20 Minutes (approximate)

Minutes (approximate)

Taken: _ _ _ __

Time Taken:

Time APPLICABLE METHOD APPLICABLE METHOD OF OF TESTING TESTING Performance:

Performance: Simulate Actual Unit:

Unit: 22 Setting: In-Plant Simulator Admin X Time Critical: Yes No X X Time Limit N/A Alternate Path: Yes No X X

EVALUATION Performer: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Performer:

JPM: Pass _ _ Fail --

Remedial Training Required: Yes No _ _

(Reference TAP-411 TAP-41 1 for evaluation guidance)

Comments:

Comments reviewed with Performer Evaluator Evaluator Signature:

Signature: _ _ _ _ _ _ _ _ _ _ _ __ Date:___________

Date: -----

LOT-OJT-JP-002-A01 LOT-OJT-JP-002-A01 Page 10 Page 10 REV. 01 REV. 01

tJ CD (")

o 0-Recorder Attachment

""'I CD ~

(") ::T -

CD 3 :::l I.)

I 1J (0 0

4.

1 (0

5- :

Cl 0

TORUS AND DR(WELL TEMP TORUS AND DRYWELL TEMP OW II DIV II 2 CACTR--44 2CAC-TR262 2.

I I I 1$ I iI , i I ._.i.__J_ .i_._4 I I I I__I__iJ

24GG 4OQ +

I i I - I ii . .t .1.1.1

0 I CD C,

0 CI)

(")

o a.,

CD CI)

C,

~

(")

r 3CI)

I. ELKWTR -POOL TE 24 2l 0 345 CD

l I

2. CThIT AV AiR 5, 38 215 4 1 TE 5. TE-

3. TE125823 2i0 255 20 Y8 320 6. TEt

TASK CONDITIONS:

th 15 th

1. Today is the 15 of the month.

1.

2. Drywell air RTDs CAC-TE-1258-8,

2. CAC-TE-1258-8, CACTE-1258-18 CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable.

3. An LCO has been established that requires the performance of OPT-16.2, Drywell Volumetric Average Temperature, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Microprocessors are not available for use.

4. The CAC-TY-4426-1 and 22 Microprocessors

5. The Process Computer and ERFIS are not available.

6. You have been given permission by the Unit CRS to perform this test.

7. The Unit CRS will record required cover page information INITIATING CUE:

You have been directed by the Unit Two CRS to perform OPT-16.2, Drywell Volumetric Average Temperature, and record the Volumetric Average Temperature (Step 7.7.1.6) and the results of the test (circle choice) in the table below.

DRYWELL VOLUMETRIC AVERAGE TEMPERATURE SAT OF

°F UNSAT

BRUNSWICK NUCLEAR BRUNSWICK NUCLEAR PLANT PLANT Cc Energy Progress Energy Continuous Continuous Use Use DATE COMPLETED DATE COMPLETED _ _ _ _ _ _ _ _ __ FREQUENCY:

FREQUENCY:

UNIT _

UNIT____ _ %PWR_______

% PWR,_ _ _ _ GMWE_______

GMWE_ _ __

SUPERVISOR, _ _ _ _ _ _ _ _ _ _ __ Once every Once every 24 hours when at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months least one at least one SPTMS SUPERVISOR air RTD isis inoperable in each division of SPTMS inoperable in REASON FOR REASON FOR TEST TEST (check (check one one or or more):

more): and the unit and the unit is in Mode is in 1, 2, Mode 1, 2, or or 3.

3.

_ sUNeillance Routine surveillance

_WO# _ _ _ _ _ _ _ _ _ _ _ __

WO #__________________________

_ Other (explain) _ _ _ _ _ _ _ _ __

Other (explain)_________________________________

PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT o0 OPT-16.2 DRYWELL VOLUMETRIC AVERAGE TEMPERATURE TEMPERATURE REVISION 35 IOPT-16.2 OPT-16.2 Rev. 35 Rev. 35 Page 11 of Page 12 )

of 12

1.0 1.0 PURPOSE PURPOSE 1.1 1.1 This test is is performed performed toto determine the operability determine the operability of drywell in of the drywell in conformance with the requirements specified in in Technical Specification Specification 3.6.1.4.1.

SR 3.6.1.4.1.

11.2

.2 This test involves averaging air temperatures within the drywell.

averaging air drywell.

2.0 REFERENCES

REFERENC ES 2.1 Technical Specification Specificationss 2.2 FSAR, Section 6.2 2.3 System Description SD-24, Containment Atmosphere Control System 2.4 Divisions/Channels Defined)

EER 93-578 (SPTMS Air RTD Divisions/Channels 2.5 Measurement for SPTMS RTD 2SP-95-208, Temperature Measurement 2.6 ContainmenflDrywell Air Temperature ESR 98-00387, Rev. 0, TS Change to ContainmentlDrywell Requirements Requirements 3.0 PREREQUISITES PREREQUISITES None Applicable 4.0 PRECAUTIONS LIMITATIONS PRECAUTIONS AND LIMITATIONS None Applicable 5.0 SPECIAL TOOLS AND EQUIPMENT EQUIPMENT Calculator 6.0 6.0 ACCEPTANCE ACCEPTANCE CRITERIA CRITERIA This test may may be volumetric average be considered satisfactory when the drywell volumetric temperature isis less less than or or equal 150°F.

equal to 150°F.

IOPT-16.2 OPT-i 6.2 Rev. 35 Rev. 35 Page 22 of Page 12 )

of 12

7.0 PROCEDURAL STEPS Initials 7.1 OBTAIN permission from Unit CRS to perform this test.

NOTE: Figure 11 may be used as aa worksheet but is NOT required to be retained th is PT.

with this NOTE: All temperatures used in this procedure should be rounded off to the nearest tenth of aa degree.

NOTE: Primary containment temperatures may be obtained from the CAC-TY-4426-1 (2) microprocessor per OP-24, Operator Interface With The CAC-TY-4426-1 SPTMS Microprocessors, from the recorders in the Control Room, from ERFIS display screens 740 and 745 of the Validation Menu; or as aa backup method, the designated process computer points may be used.

Microprocessor point values may also be obtained by I&Cl&C manually taking measurements of SPTMS RTDs.

temperature measurements NOTE: Technical Specifications requires at least one operable temperature detector in each channel for each location.

OPT-16.2 IOPT-16.2 Rev. 35 Page3ofl2j Page 3 of 12)

7.0 7.0 PROCEDURAL PROCEDUR STEPS AL STEPS Initials Initials 7.2 7.2 90' Elevation 90 Elevation And And Above Above 7.2.1 7.2.1 OBTAIN drywell OBTAIN drywell temperature temperature for for the the locations locations listed listed below AND below AND RECORD RECORD in in the the spaces spaces provided.

provided.

Recorder/ERFIS Recorder/ER Display FIS Display SPTMS SPTMS CHAN CHAN PPC 4426-2A Channel 33 _ __

4426-2A Channel (5823) _ _

(5823) IIII N/A N/A 4426-2A Channel 4426-2ACha nnel44 _ __ (5824) _ _

(5824) IIII N/A N/A 4426-1A 4426-lA Channel Channel4 4 _ __ (5822) _ _

(5822) II N/A N/A 7.2.2 7.2.2 ADD the the recorded temperatures temperatures AND RECORD the the total in in the following space:

_ _ _ _ _ _ _ _ _ _ - Recorder/ER - Recorder/ERFIS display total FIS display

_ _ _ _ _ _ _ _ _ _ - SPTMS total -

7.2.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 90 90' elevation and above in the following space:

=

total no. of temperatures average I OPT-16.2 OPT-16.2 Rev.

Rev. 3535 Page of 12 Page 44 of 12 )

7.0 7.0 PROCEDURAL STEPS PROCEDURAL STEPS Initials Initials 7.3 7.3 Between 70 Between And 80 70' And 80' Elevation Elevation 7.3.1 7.3.1 temperatures for the locations drywell temperatures OBTAIN drywell locations listed below AND RECORD below AND RECORD in in the the spaces spaces provided.

provided.

Recorder/ERFIS Display SPTMS SPTMS CHAN CHAN PPC PPC Unit I1 Only Unit 4426-2B Channel 11 4426-28 (5802) IIII W109 /

/

4426-1 B Channel2 4426-lB Channel 2 (5803) II F148 4426-2B Channel 2 4426-2BChannel2 (5804) IIII WhO W110 Unit 22 Only 4426-2B Channel 1 1 (5802) II W109 4426-1 B Channel 4426-lB Channel2 2 (5803) II F148 NOTE: Notify BESS duty manager if any temperatures between 70' 70 and 80' 80 elevation exceed 240°F.

7.3.2 ADD the recorded temperatures AND RECORD the total in the following spaces:

_________ - - Recorder/ERFIS display total SPTMS total PPC total 7.3.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 70' 70 - 80'

- 80 elevation in the following space:

=

total no. of temperatures average IOPT-16.2 OPT-16.2 Rev.

Rev. 3535 Page of 121 Page 55 of 12

7.0 7.0 PROCEDURAL STEPS PROCEDURAL STEPS InWals Initials 7.4 7.4 Between 28 Between And 45 28' And 45' Elevation Elevation 7.4.1 7.4.1 OBTAIN OBTAIN drywell temperatures drywell temperatures for the locations for the locations listed listed below AND below AND RECORD RECORD in in the the spaces spaces provided.

provided.

Recorder/ERFIS Display Recorder/ERFIS Display SPTMS SPTMS CHAN CHAN PPC PPC 4426-1 B Channel3 4426-lB Channel 3 (5805)

(5805) II F149 F149 4426-2B Channel 4426-2B Channel 33 (5806)

(5806) IIII W085 W085 4426-lB Channel44 4426-1 B Channel (5807)

(5807) II F150 F150 4426-2B Channel 4426-2B Channel 44 (5808)

(5808) IIII W086 W086 7.4.2 7.4.2 ADD the ADD the recorded temperatures temperatures ANDAND RECORD RECORD the the in the total in total the following following spaces:

spaces:

________ - Recorder/ERFIS display total

________ - SPTMS SPTMS total

________ - PPC total 7.4.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 28 28' - 45

- 45' elevation in the following space:

=

total no. of temperatures average 7.5 Between Between 10' 10 And 23' 23 Elevation Elevation 7.5.1 OBTAIN OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN PPC 4426-1 4426-lB B Channel ChannelS 5 _ __ (5809) _ _ I F151 F151 _ _ _ __

4426-1A Channel 4426-lA Channel3 3 _ __ (5812) _ _ I W105 _ _ _ __

4426-2B 4426-2BCha Channel nneI66 _ __ (5813)

(5813) _ _ IIII W088 _ _ _ __

IOPT-16.2 OPT-16.2 Rev.

Rev. 3535 Page6of12 Page 6 of 12/

7.0 7.0 PROCEDURAL STEPS PROCEDURAL STEPS Initials Initials 7.5.2 7.5.2 ADD the ADD the recorded temperatures AND RECORD temperatures AND RECORD the the in the total in total the following following spaces:

spaces:

_ _ _ _ _ _ _ _ _ - Recorder/ERFIS display

- display total total

_ _ _ _ _ _ _ _ - SPTMS -

SPTMS total total

_ _ _ _ _ _ _ _ _ - PPC -

PPC total total 7.5.3 DIVIDE the total by the number of temperatures used used to obtain the average temperature for the 10 10' - 23

- 23' elevation in elevation in the the following following space:

space:

=

total no. of temperatures average 7.6 5' Elevation Below 5 7.6.1 OBTAIN primary containment temperatures for the locations listed below AND RECORD in the spaces provided.

Recorder/ERFIS Display SPTMS CHAN PPC 4426-1A Channel 5 4426-lAChannelS _ __ (5817) _ _ II W106 _ _ _ __

4426-1A 4426-lA Channel Channel6 6 _ __ (5818) _ _ I W107 W107 _ _ _ __

4426-2A Channel 5 4426-2AChanneI5 _ __ (5819) _ _ II W115 _ _ _ __

4426-2A Channel 6 _ __ (5820) _ _ II W116 _ _ _ __

CAUTION If microprocessor is used to obtain data, failure to restore mode selector switch to the ERFIS (NORMAL) position will cause loss of SPTMS indications on the ERFIS Control Room displays.

displays 7.6.2 ADD the recorded temperatures AND RECORD the total in the following spaces:

_ _ _ _ _ _ _ _ _ - Recorder/ERFIS display total

_ _ _ _ _ _ _ _ _ - SPTMS total-

_ _ _ _ _ _ _ _ _ - PPC - PPC total IOPT-16.2 OPT-16.2 Rev.

Rev. 35 35 Page7of12 Page 7 of 12 )

7.0 PROCEDURAL STEPS STEPS Initials 7.6.3 DIVIDE the total by the number of temperatures used used to obtain the average temperature for the below 5'5 elevation in the following space:

=

total no. of temperatures average NOTE: The total in Step 7.7.1.6 is the volumetric average temperature for the 150°F, actions should be taken as drywell. If this temperature is greater than 150°F, required by Technical Specification SR 3.6.1.4.1.

7.7 Volumetric Average 7.7.1 DETERMINE the volumetric average temperature by performing the following calculations:

1. Average above 90' 90 elevation x 0.05 =____

=

Step 7.2.3

2. Average 70'70 - 80'

- 80 elevation x 0.09 == _ _ __

Step 7.3.3

3. Average 28'28 - 45'

- 45 elevation x 0.40 =

= ____

Step 7.4.3

4. Average 10' 10 - 23'

- 23 elevation x 0.38 =

= ____

Step 7.5.3

5. Average below 5' 5 elevation x 0.08 == _ _ __

Step 7.6.3 6.

6. Total _ _ _ _ _ _ _ _ _ _ _ __

Total______________________________

Steps 7.7.1.1 through 7.7.1.5 IOPT-16.2 roPT-16.2 Rev. 35 Page8of12 Page 8 of 121

7.0 PROCEDURAL STEPS Initials NOTE: Computer point C074 may only be used to satisfy EOP concerns and may NOT be used to satisfy Technical Specifications.

7.7.2 RECORD computer point C074 value (for information).

C074 _ _ _ __

NOTE: Performance of Steps 7.7.3 and 7.7.4 is only required once aa month (perform on the first day of the month).

7.7.3 SUBTRACT the value obtained in Step 7.7.2 from the value obtained in Step 7.7.1.6.

=

Step 7.7.1.6 Step 7.7.2 Difference 7.7.4 IF the absolute value of the difference obtained in 10°F, THEN ENSURE that Step 7.7.3 is greater than 10°F, Unit CRS is informed of the discrepancies in the computer point reading (EOP concern).

7.7.5 ENSURE required information has been recorded on the cover page.

7.7.6 NOTIFY Unit CRS when this test is complete or found to be unsatisfactory.

OPT-I 6.2 IOPT-16.2 Rev. 35 12 Page 9 of 121

ATTACHMENT I1 ATTACHMENT of I1 Page 11 of Page Certification and Certification and Review Review Form Form General Comments Comments and and Recommendations Recommendations General Initials Initials Name (Print)

Name (Print)

Performed by:

Exceptions to Exceptions to satisfactory satisfactory performance performance ________________________________

Corrective Corrective action required ______________________________

action required Test Test procedure procedure hashas been been satisfactorily satisfactorily completed:

Unit CRSISRO: _ _ _ _ _ _ _ _ _ _ _ __

Unit CRS/SRO:

Signature Signature Date Test Test procedure procedure hashas NOT been been satisfactorily satisfactorily completed:

Unit CRS/SRO: _ _ _ _ _ _ _ _ _ _ _ __

Unit CRS/SRO:

Signature Signature Date Date Test Test has has been been reviewed reviewed by:

by:

Shift Shift Manager:

Manager:

Signature Signature Date Date IOPT-16.2 OPT-16.2 Rev. 35 Rev. 35 Page 10 of Page 10 12 of 121

FIGURE 1 1 Page 1 1 of 1 1 Containment Temperature Worksheet TIME 4426-2A (Channel 3)-5823 _ _ _ 0.05 4426-2A (Channel 4)-5824 4426-1A (Channel 4)-5822 4426-lA 1 only Unit 1 4426-2B (Channel 1 1)-5802

)-5802 4426-lB 4426-1 B (Channel 2)-5803 _ _ _ 20.09 4426-2B (Channel 2)-5804 Unit2only Unit 2 only 4426-2B (Channel 1 1)-5802

)-5802 4426-lB 4426-1 B (Channel 2)-5803 ___ 2 0.09 4426-1 BB (Channel 3)-5805 4426-2B (Channel 3)-5806 4426-lB 4426-1 B (Channel 4)-5807 _ _ _ 0040 4426-2B (Channel 4)-5808 4426-lB 4426-1 B (Channel 5)-5809 4426-lA 4426-1A (Channel 3)-5812 _ _ _ 20.38 4426-2B (Channel 6)-5813 4426-lA 4426-1A (Channel 5)-5817 4426-lA 4426-1A (Channel 6)-5818 _ _ _ 20.08 4426-2A (Channel 5)-5819 4426-2A (Channel 6)-5820 AVERAGE TEMPERATURE I OPT-16.2 Rev. 35 Pa~~-1-1-;i121 Page 11 of 12

REVISION

SUMMARY

REVISION

SUMMARY

Revision 35 Revision 35 incorporates incorporates temporary change EC 75096 change EC which temporarily disables 75096 which disables indication 2CAC-TE-1258-4 (4426-2B temperature indication (4426-2B [channel 21-5804). This revision also 2]-5804). This also updated operations updated operations titles Shift Shift Superintendent to Shift Superintendent to Manager and Shift Manager SCQ to and SCO to CRS CRS or or CRS/SRQ as CRSISRO as applicable.

applicable.

Revision 34 Revision 34 restores 2CAC-TE-1 2CAC-TE-1258-20 (4426-2A [channel 61-5820) 258-20 (4426-2A 6]-5820) that was was temporarily removed lAW EC 63061. 63061.

incorporates temporary change EC 63061 which temporarily disables Revision 33 incorporates 258-20 (4426-2A [channel 6]-5820).

2CAC-TE-1258-20 temperature indication 2CAC-TE-1 Revision 32- Removes the Unit Specific items and associated notes that were added per Temporary Plant Modification ESR 99-00485. Temperature Sensor 2-CAC-TE-1258-22 has been repaired during the refuel outage. This revision also revises terminology for PassPort Implementation.

Revision 31 - This revision removes the notes that specified equivalencies during implementation of ESRs 97-00125 and 97-00051, and changed points A, B, C, D, E, &

F F to channel 1, 2, 3, 4, 5, & 6.

IOPT-16.2 OPT-16.2 Rev. 35 Rev. 35 Page l2of Page 12 12 of 121

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