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{{#Wiki_filter:LESSON TITLE: LESSON NUMBER: REVISION NO: PROGRESS ENERGY -CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C002 (SRO) Evaluate Refueling Technical Specifications SOT -OJT -J P-305-CO 1 01 Evaluate Refueling Technical Specifications SAFETY CONSIDERATIONS:
{{#Wiki_filter:PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C002 (SRO)
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.
LESSON TITLE:  Evaluate Refueling Technical Specifications LESSON NUMBER: SOT-OJT-J SOT                 1
Read the following to trainee. TASK CONDITIONS:
                  -OJT -J P-305-CO 1 REVISION NO:  01
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 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 [[estimated NRC review hours::6 hours]] to support retrieving a Reactor Pressure Vessel Head nut from within the vessel using the Auxiliary Platform. (This is the 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 [[estimated NRC review hours::6 hours]] 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 Evaluate Refueling Technical Specifications ANSWER KEY Technical CONDITION REQUIRED COMPLETION Fuel Movements Specification ACTION TIME Allowed LCO 3.9.7 C. No RHR C.1 Verify reactor 1 hour from YE shutdown coolant circulation discovery of no cooling by an alternate reactor coolant subsystem in method. circulation operation.
Evaluate Refueling Technical Specifications SAFETY CONSIDERATIONS:
AND AND Once per [[estimated NRC review hours::12 hours]] NO thereafter C.2 Monitor reactor coolant temperature.
None EVALUATOR NOTES: (Do not read to trainee)
Once per hour SOT -OJT -J P-305-CO 1 Page 3 of 9 REV. 01 Evaluate Refueling Technical Specifications PERFORMANCE CHECKLIST NOTE: Sequence is not essential to completing the task. TIME START: _____ _ Step 1 -Obtain current revision of Unit Two Tech Specs Current copy of Unit Two Tech Specs is obtained SAT/UNSAT*
: 1. The applicable procedure section WILL be provided to the trainee.
Step 2 -Determine LCO 3.9.7 applies to current plant conditions (may use TOC to determine)
: 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.
LCO 3.9.7 determined to be applicable to current plant conditions.  
: 3. This JPM may be administered in the simulator, control room, or classroom setting.
*CRITICAL STEP*
: 4. Ensure examinee has access to Technical Specifications, Bases, and POM documents.
* SAT/UNSAT*
Read the following to trainee.
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.
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 hours 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 hours 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 hour 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 hours       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 hours in an 8 hour 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 hours in a 8 hour period SATIU NSAT*
SAT/UNSAT*
NOTE: Candidate may propose allowing SDC removal from service for up to 2 hours 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 hours.
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 hours (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 hours (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*
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 [[estimated NRC review hours::2 hours]] in an 8 hour period. Determine that LCO 3.9.7 is modified by a note aI/owing the required RHR shutdown cooling subsystem to be removed from operation for up to [[estimated NRC review hours::2 hours]] in a 8 hour period SAT/UNSAT*
Step 7 - Determine LCO LCD 3.9.7 Condition B does not apply since Condition A does not apply.
NOTE: Candidate may propose allowing SDC removal from service for up to [[estimated NRC review hours::2 hours]] without entering the Tech Spec ACTION statement.
LCD 3.9.7 Condition B does not apply Determine LCO
PROMPT: If necessary, Direct candidate to address Technical Specifications for removing SDC from service for [[estimated NRC review hours::6 hours]]. SOT -OJT -J P-305-CO 1 Page 4 of 9 REV. 01 Evaluate Refueling Technical Specifications Step 5 -Determine LCO 3.9.7 will not be met if RHR shutdown cooling is removed from service for [[estimated NRC review hours::6 hours]] (more than the allowable two hour time) Determine that LCO 3.9.7 will not be met if RHR shutdown cooling is removed from service for [[estimated NRC review hours::6 hours]] (more than the allowable two hour time) *CRITICAL STEP*
                                                                *CRITICAL STEP* SAT/UNSAT*
* SAT/UNSAT*
                                                                *CRITICAL            SATIUNSAT*
Step 6 -Determine LCO 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* SAT/UNSAT*
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
Step 7 -Determine LCO 3.9.7 Condition B does not apply since Condition A does not apply. Determine LCO 3.9.7 Condition B does not apply *CRITICAL STEP* SAT/UNSAT*
                                                                *CRITICAL STEP*
Step 8 -Determine LCO 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*
* SAT/UNSAT*
SATIUNSAT*
Step 9 -Determine required action C.1 applies and requires verification of reactor coolant circulation by an alternate method 1 hour from discovery of no reactor coolant circulation and once per [[estimated NRC review hours::12 hours]] thereafter Determine that required action C. 1 applies and requires verification of reactor coolant circulation by an alternate method 1 hour from discovery of no reactor coolant circulation and once per [[estimated NRC review hours::12 hours]] thereafter  
Step 9 - Determine required action C.1 applies and requires verification of reactor coolant circulation by an alternate method 1 1 hour from discovery of no reactor coolant circulation and once per 12 hours thereafter Determine that required action C. 1 lapplies applies and requires verification of reactor coolant circulation by an alternate method 1  1 hour from discovery of no reactor coolant circulation and once per 12 hours thereafter
*CRITICAL STEP*
                                                                *CRITICAL STEP* ** SAT/UNSAT*
* SAT/UNSAT*
SATIUNSAT*
Step 10 -Determine required action C.2 also applies and requires monitoring of reactor coolant temperature once per hour Determine that required action C.2 applies and requires monitoring of reactor coolant temperature once per hour *CRITICAL STEP*
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
* SAT/UNSAT*
                                                                *CRITICAL STEP* ** SAT/UNSAT*
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 while still Operable will still allow for in-vessel fuel movement during high water level conditions.
SOT-DJT-JP-305-C01 SOT -OJT-J P-305-CO 1                       Page 5 of 9                                   REV. 01
Step 11 -Determine if in-vessel fuel movement is still allowed. Determines in-vessel fuel movement is still allowed. *CRITICAL STEP*
 
* SAT/UNSAT*
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 13 -Inform Shift Manager of results. SM notified.
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*
SAT/UNSAT*
TERMINATING CUE: When the results are reported to the SM this JPM is complete.
TERMINATING CUE: When the results are reported to the SM this JPM is complete.
TIME COMPLETED:
TIME COMPLETED:         _ _ _ _ __
_____ _
COMPLETED:______________
* Comments required for any step evaluated as UNSAT. SOT -OJT -J P-305-CO 1 Page 6 of 9 REV. 01 Evaluate Refueling Technical Specifications LIST OF REFERENCES RELATED TASKS: 342000 B3 02 Approve requests to remove plant equipment from operation.
** Comments required for any step evaluated as UNSAT.
KIA REFERENCE AND IMPORTANCE RATING: Generic Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.
SOT-OJT-JP-305-CO1 SOT  -OJT-J P-305-CO 1                         Page 6 of 9                               REV. 01
RO I SRO 2.8 I  
 
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==
==3.9 REFERENCES==
:
Unit 2 Technical Specifications Amendment 233 OAP-22 TOOLS AND EQUIPMENT:
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:
None SAFETY FUNCTION (from NUREG 1123, Rev 2 Supp. 1):
Revised to the proper KIA reference, which had changed in supplement
Generic - Conduct of Operations REASON FOR REVISION:
: 1. SOT-OJT-JP-305-C01 Page 7 of 9 REV. 01 Evaluate Refueling Technical Specifications Time Required for Completion:  
K/A reference, which had changed in supplement 1.
.2!L Minutes (approximate).
Revised to the proper KIA SOT-OJT-JP-305-C01                       Page 77 of 99                        REV. 01
APPLICABLE METHOD OF TESTING Performance:
 
Simulate Actual l Unit: _2_ Setting: In-Plant Simulator Admin X Time Critical:
Evaluate Refueling Technical Specifications Time Required for Completion:         .2!L 30  Minutes (approximate).
Yes No -2L Time Limit N/A Alternate Path: Yes No --2L EVALUATION Trainee: -------------------------------------------------
APPLICABLE METHOD OF TESTING Performance:         Simulate                       Actual   lX                  Unit: _2_
JPM: Pass __ Fail __ Remedial Training Required:
2 Setting:               In-Plant                   Simulator                     Admin     X X
Yes No __ Did Trainee Verify Procedure Revision?
Time Critical:               Yes                       No     X
Yes No ____ _ (Each Student should verify one JPM per evaluation)
                                                              -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:
Comments:
Evaluator Signature:
Evaluator Signature: _____________________________                          Date: ___________
____________________________
Date:_______________
_ Date: __________
SOT-OJT-JP-305-C01                                 Page 8 of 9                               REV. 01
_ SOT-OJT-JP-305-C01 Page 8 of 9 REV. 01 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 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 [[estimated NRC review hours::6 hours]] to support retrieving a Reactor Pressure Vessel Head nut from within the vessel using the Auxiliary Platform. (This is the 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 [[estimated NRC review hours::6 hours]] and 2. Determine if in-vessel fuel movements are allowed to continue without SDC in service after the Foreign Material has been retrieved.
TASK CONDITIONS:
LESSON TITLE: LESSON NUMBER: REVISION NO: PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE NRC ADMIN EP (SRO) Classify An Emergency Per PEP-02.1.
TASK       CONDITIONS:
SOT-ADM-JP-301-A 15 02 Classify An Emergency Per PEP-02.1.
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 hours 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 hours 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:
SAFETY CONSIDERATIONS:
None. EVALUATOR NOTES: (Do not read to performer)
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.
: 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.
: 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.
: 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.
: 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. 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-AOM-JP-301-A 15 Page 2 of 8 REV. 02 Classify An Emergency Per PEP-02.1.
: 5. Copies of all remaining PEPs should be available upon request.
Read the following to the J PM performer.
: 6. Task standards (Le.  (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
TASK CONDITIONS:  
: 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.
**This is a Time Critical JPM** Time begins when directed by the evaluator
SOT-ADM-JP-301-A15 SOT-AOM-JP-301-A     15                       Page 2 of 8                               REV. 02
: 1. Unit One is operating at 100% power. 2. Unit Two is operating at 100% power with DG4 under clearance when the following 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.
Classify An Emergency Per PEP-02.1.
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 15 Page 3 of 8 REV. 02 Classify An Emergency Per PEP-02.1.
Read the following to the JPM          JPM performer.
ANSWER KEY CLASSIFICATION EAL IDENTIFIER Site Area Emergency SS2.1 SOT -ADM-JP-301-A 15 Page 4 of 8 REV. 02 Classify An Emergency Per PEP-02.1.
TASK CONDITIONS:
PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
**This is aa Time Critical JPM**
Step 1 -Obtain a current revision of PEP-02.1 if required.
Time begins when directed by the evaluator
Current Revision of PEP-02. 1 obtained.
: 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*
SATIUNSAT*
PROMPT: Ensure a clock is visible for candidates.
PROMPT: Ensure aa clock is visible for candidates. Announce and Write the Start Time on        on the board.
Announce and Write the Start Time on the board. Add 15 minutes to the Start Time and write that in the JPM Completion Time. If all candidates have not Declared a classification, this is the time to STOP all work, put pencils/pens down, and collect all remaining cue sheets. I NOTE: Declaration of event must be made in 15 minutes from the Start Time. TIME START ____ _ NOTE: Loss of Corporate Telephone Communications System (Voicenet), Commercial Telephones, and NRC Emergency Telecommunications System does not reach EAL classification .threshold.
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.
Step 2 -Determine required Classification threshold and associated EAL Number(s) o Alert -HA 1. 1 Seismic event identified by any two of the following:  
down, and collect all remaining IiINOTE:
-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 SAT/UNSAT*
NOTE: Declaration of event must be made in 15 minutes from the Start Time.                         I TIME START _ _ _ __
SOT-ADM-JP-301-A 15 Page 5 of 8 REV. 02 Classify An Emergency Per PEP-02.1.
NOTE:     Loss of Corporate Telephone Communications System (Voicenet), Commercial Telephones, Tephones, and NRC Emergency Telecommunications System does not reach EAL classification .threshold.
NOTE: Automatic Scram fails to shutdown the reactor and manual actions taken from the control console are not successful in shutting down.the reactor. Step 3 -Determine required Classification threshold and associated EAL Number(s) o Site Area Emergency  
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:
-SS2. 1 Automatic scram fails to reduce reactor power < 2% (APRM downscale)
                  - Earthquake felt in plant
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** SA TlUNSAT* DECLARATION TIME ___ _ Step 4 -Classification made within required the required time (Declaration Time minus Start Time 15 minutes).
                  - National Earthquake Center AND Control Room indication of degraded performance of systems required for the safe shutdown of the plant (ATWS provides this)
o Classification declared 15 minutes of Start Time. **CRITICAL STEP** SAT/UNSAT*
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.
TERMINATING CUE: When the event is classified with applicable EAL identifier(s) in the table, this JPM is complete.
TIME COMPLETED
TIME COMPLETED _ _ _ __
____ _ *NOTE: Comments required for any step evaluated as UNSAT. SOT-ADM-JP-301-A 15 Page 6 of 8 REV. 02 Classify An Emergency Per PEP-02.1.
*NOTE: Comments required for any step evaluated as UNSAT.
RELATED TASKS: 3442568502 Direct Initial Emergency Actions Including Emergency Classification per OPEP-02.1 KIA REFERENCE AND IMPORTANCE RATING: GEN 2.4.29 3.1/4.4 Knowledge of the Emergency Plan  
*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:==
==REFERENCES:==


OPEP-02.1, Rev 51 TOOLS AND EQUIPMENT:
OPEP-02.1, Rev 51 TOOLS AND EQUIPMENT:
None. ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2., Supp.1): Admin -Emergency Procedures 1 Plan REASON FOR REVISION:
None.
2010-1 NRC License Exam -Modified to reflect NEI 99-01 implementation.
ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2., Supp.1): Supp.l):
SOT-ADM-JP-301-A 15 Page 7 of 8 REV. 02 Classify An Emergency Per PEP-02.1.
Admin - Emergency Procedures 1
Validation Time: 15 Minutes (approximate).
                                    / Plan REASON FOR REVISION:
Time Taken: ----APPLICABLE METHOD OF TESTING Performance:
2010-1 NRC License Exam - Modified to reflect NEI 99-01 implementation.
Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical:
SOT-ADM-JP-301-A15 SOT-ADM-JP-301-A   15                   Page 7 of 8                               REV. 02
Yes X No Time Limit 15 min Alternate Path: Yes No X EVALUATION Performer:
 
_______________________
Classify An Emergency Per PEP-02.1.
_ JPM: Pass --Fail __ Remedial Training Required:
Validation Time:   15 15    Minutes (approximate).
Yes No __ Comments:
Time Taken: ----
Comments reviewed with Performer Evaluator Signature:
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: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
_ Date: ----SOT-ADM-JP-301-A 15 Page 8 of 8 REV. 02 TASK CONDITIONS:  
JPM:           Pass             Fail _ _
**This is a Time Critical JPM** Time begins when directed by the evaluator
Remedial Training Required:     Yes         No _ _
: 1. Unit One is operating at 100% power. 2. Unit Two is operating at 100% power with DG4 under clearance when the following 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 / 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.
Comments:
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.
Comments reviewed with Performer Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ __              Date:___________
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 LESSON TITLE: REVISION NO: CAROLINA POWER & LIGHT COMPANY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT NRC ADMIN EC (RO/SRO) Develop a Clearance Boundary -RBCCW Pump 2C. 01 Develop a Clearance Boundary -RBCCW Pump 2C. SAFETY CONSIDERATIONS:
Date: ----
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. If desired, the evaluator may provide the examinee with a copy of OPS-NGGC-1301, 20P-21, and the referenced prints. 4. The evaluator should have available copies of prints 0-02538 Sheets 1 & 2 and LL-09241 sheets 8 & 24 to support performance of JPM, or perform JPM in a location where a print machine is available.
SOT-ADM-JP-301-A SOT-ADM-JP-301-A15  15                 Page 8 of 8                             REV. 02
: 5. Provide examinee a marked up copy of Attachment 4 of OPS-NGGC-1301 with "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.
TASK CONDITIONS:
: 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, Equipment Clearance procedure.
**This is aa Time Critical JPM**
LOT -OJT -J P-20 1-E04 Page 2 REV. 01 Develop a Clearance Boundary -RBCCW Pump 2C. ANSWER KEY ATTACHMENT 4 Sheet 1 of 1 OPERATIONS CLEARANCE TAG SHEET Clearance No. N/A PAGE _1_of_1 INT NAME (PRINT) INT NAME (PRINT)
JPM**
* Independent Verification Required?
Time begins when directed by the evaluator
Yes/No If No, N/A the Blocks Seq Action Type Tag Id Position EquipmenUComponent Completed By 1 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 3 N/A RED 2-RCC-V34 CLOSED RBCCWPumpC  
: 1. Unit One is operating at 100%
** Discharge Valve 3 N/A RED 2-RCC-V30 CLOSED RBCCW Pump C ** 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 Discharge Drain Valve 4 N/A RED 2-RCC-V301 OPEN RBCCW Pump C Casing ** Vent Valve Sequence must have either switch off or breaker open prior to operating discharge/suction valves, and 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. IV By LOT -OJT -JP-201-E04 Page 3 REV. 01 Develop a Clearance Boundary -RBCCW Pump 2C. PERFORMANCE CHECKLIST I NOTE: If desired, the examiner may providea copy OPS-NGGC-1301 to the examinee.
: 1.                            100% power.
NOTE: Sequence is assumed unless denoted in the Comments.
100% power with DG4 under clearance when the following
Step 1 -Obtain a current revision of OPS-NGGC-1301.
: 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:
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.
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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.
Current Revision of OPS-NGGC-1301 obtained.
SATIUNSAT*
SAT/UNSAT*
SAT/UNSAT*
TIME START ____ _ NOTE: NOTE: If desired, the examiner may provide a copy of the required prints to the examinee (0-02538, Sheets 1 & 2, LL-9241, Sheets 8 & 24) and 20P-21 lineups. CITs can have position OFF or In-Place I HUNG Step 2 -Obtain copies of required prints (0-02538, Sheets 1 & 2, LL-09241, Sheets 8 & 24). Drawings 0-02538, Sheets 1 & 2, LL-09241, Sheets 8 & 24 obtained.
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*
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. SAT/UNSAT*
Step 3 - Identify control switch 2-RCC-CS-449 should be placed to OFF.
Step 4 -Identify breaker 2XE Compt EA7 should be placed to OFF. Determine 2XE Compt EA 7 should be placed to OFF. ** CRITICAL STEP ** SAT/UNSAT*
Determine 2-RCC-CS-449 should be placed to OFF.
LOT -OJT -JP-201-E04 Page 4 REV. 01 NOTE: Develop a Clearance Boundary -RBCCW Pump 2C. Sequence of suction or discharge valve closing .is not critical so long as the pump motor is de:..energized.
SATIUNSAT*
Step 5 -Identify discharge valve 2-RCC-V34 should be closed. Determine 2-RCC-V34 should be closed. ** CRITICAL STEP ** SA T1UNSAT* Step 6 -Identify suction valve 2-RCC-V30 should be closed. NOTE: NOTE: Determine 2-RCC-V30 should be closed. ** CRITICAL STEP ** SAT/UNSAT*
SAT/UNSAT*
Either2-RCC-V128or 2-RCC-V129is critical.
Step 4 - Identify
Both are notrequired to meet critical task standards.
          - Identify breaker breaker 2XE Compt EA7 EA7 should be     placed to OFF.
Sequence of drain or vent valve opening is not critical.
be placed Determine 2XE Compt EA 77 should be placed to            OFF.
Step 7 -Identify drain valve 2-RCC-V128 should be open. Determine 2-RCC-V128 should be open. ** CRITICAL STEP ** SAT/UNSAT*
to OFF.
Step 8 -Identify drain valve 2-RCC-V129 should be open. Determine 2-RCC-V129 should be open. ** CRITICAL STEP ** SAT/UNSAT*
                                                                    **                   ** SAT/UNSAT*
Step 9 -Identify vent valve 2-RCC-V301 should be open. Determine 2-RCC-V301 should be open. ** CRITICAL STEP ** SAT/UNSAT*
                                                                    **  CRITICAL STEP **   SAT/UNSAT*
LOT -OJT -J P-20 1-E04 Page 5 REV. 01 Develop a Clearance Boundary -RBCCW Pump 2C. Step 10 -Submit proposed boundary to WCC SRO. Proposed boundary submitted to wee SRO. SAT/UNSAT*
LOT -OJT-JP-201-E04 LOT-OJT-JP-201-E04                                  Page 44 Page                                     REV. 01 REV. 01
TERMINATING CUE: When the proposed boundary.
 
has been submitted, thisJPM is complete.  
Develop aa Clearance Boundary - RBCCW Pump 2C.
.. .. TIME COMPLETED
NOTE:        Sequence of suction or discharge valve closing .is    is not critical so long as the de:..energized.
____ _
pump motor is de-energized.
* Comments required for any step evaluated as UNSAT. LOT -OJT -JP-201-E04 Page 6 REV. 01 Develop a Clearance Boundary -RBCCW Pump 2C. RELATED TASKS: 299020B301, Develop A Clearance per OPS-NGGC-1301 KIA REFERENCE AND IMPORTANCE RATING: 2.2.13 (4.1/4.3)
Step 5 - Identify discharge valve 2-RCC-V34 should be closed.
Knowledge of tagging and clearance procedures  
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*
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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:==
==REFERENCES:==


OPS-NGGC-1301 20P-21 0-02538, Sheets 1 & 2 LL-09241, Sheets 8 & 24 TOOLS AND EQUIPMENT:
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.
Referenced prints and procedures.
SAFETY FUNCTION (from NUREG 1123, Rev 2.): A.2 -Equipment Control REASON FOR REVISION:
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
Corrected typos and added NGGC-1301, Attachment
A.2 - Equipment Control REASON FOR REVISION:
: 4. LOT -OJT -J P-20 1-E04 Page 7 REV. 01 Develop a Clearance Boundary -RBCCW Pump 2C. Time Required for Completion: Minutes (approximate).
NGGC-1 301, Attachment 4.
Time Taken: ------APPLICABLE METHOD OF TESTING Performance:
Corrected typos and added NGGC-1301, LOT-OJT-JP-201-E04 LOT -OJT-J P-20 1-E04                   Page 7                 REV. 01
Simulate X Actual Unit: 2 Setting: In-Plant Simulator Admin _X:...:-__ Time Critical:
 
Yes No X Time Limit N/A Alternate Path: Yes No EVALUATION Trainee: ---------------------------
Develop aa Clearance Develop                  Boundary - RBCCW Clearance Boundary       - RBCCW Pump Pump 2C.
JPM: Pass __ Fail __ Remedial Training Required:
2C.
Yes No __ Did Trainee Verify Procedure?
Time             for Completion:
Yes __ No __ _ (Each Student should verify one JPM per evaluation set) Comments:
Required for Time Required          Completion:     ~ 20    Minutes (approximate).
Comments reviewed with Student Evaluator Signature:
Minutes (approximate).
Date: -----LOT-OJT-JP-201-E04 Page 8 REV. 01 ATTACHMENT 4 Sheet 10f 1 Operations Clearance Checklist Clearance No. --------Page __ of __ Checklist Type: Hang; Uft; Boundary Change (Circle one) INT NAME (PRINT) INT NAME (PRINT) " Independent Veriiication R,equired?  
Time Taken:
'YESINO If NO, r'lI.A. Ule Blocks Seq Action Type Tag Id Position Equipment/Component Completed.
Time    Taken:  ------
Verified By By .. Continued Y l N QARECORD I OPS-NGGC-'130 1 Rev. 20 Page 95 of '121 TASK CONDITIONS:
APPLICABLE METHOD APPLICABLE      METHOD OF     OF TESTING TESTING Performance:
: 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.
Performance:      Simulate Simulate      X               Actual Actual                        Unit:
: 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, Equipment Clearance procedure.
Unit:   22 Setting:
ATTACHMENT 1 Page 1 of 2 Reactor Building Closed Cooling Water System Electrical Lineup PERSON(S)
Setting:           In-Plant In-Plant                  Simulator                       Admin   _X:...:-__
PERFORMING OR VERIFYING LINEUP AND INITIALS (PRINT) REMARKS: Started: Completed:
X Time Critical:           Yes                           No No    X X            Time Time Limit Limit  N/A N/A Alternate Path:         Yes                           No   ~X EVALUATION Trainee: - - - - - - - - - - - - - - - - - - - - - - - - - - -
Approved by: DOCUMENT any components NOT in required position and reason below. Page may be duplicated as necessary.
JPM:             Pass _ _            Fail _ _
Date ________ _ Time ________ _ Date ________ _ Time ________ _ / SRO Date Time C Continuous Use 120P-21 Rev. 65 Page 49 of 79 )
Remedial Training Required: Yes                   No _ _
ATTACHMENT 1 Page 2 of 2 Reactor Building Closed Cooling Water System Electrical Lineup Number Description Position/
Did Trainee Verify Procedure? Yes _ _ No _ __
Checked Indication Control Building -Emergency 120V AC Distribution Panel2A -EI23' -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 Solenoid Control Building -Emergency 120V AC Distribution Panel2B -EI23' -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-VS1 Solenoid Reactor Building -Emergency 120V AC Distribution PaneI2A-RX  
(Each Student should verify one JPM per evaluation set)
-EI20' -North -CRD-HCU Area 29 DWEDT Cooler Inlet Isolation Valve RCC-VS4 ON Solenoid Reactor Building -480V MCC 2XC -EI 20' -East DT6 RBCCW Drywell Supply Header Valve, ON RCC-VS2 DT7 RBCCW Drywell Discharge Header Valve, ON RCC-V28 Reactor Building -480V MCC 2XF -EI SO' -East ED7 RB Closed Cooling Water Pump B ON Reactor Building -480V MCC 2XE -EI SO' -West EA1 RB Closed Cooling Water Pump A ON 0.A7 J RB Closed Cooling Water Pump C ON Radwaste Building -MCC RWD-EI 23' -South BR9 RBCCW Pump 2D ON Radwaste Building -Between FDF Area and Waste Precoat Area-EI 23' 2-RCC-2D-PMP-DIS RBCCW Pump 2D Disconnect Switch OFF 120P-21 Rev. 55 Page 50 of 791 ATTACHMENT 2 Page 1 of 2 Reactor Building Closed Cooling Water System Panel Lineup PERSON(S)
Comments:
PERFORMING OR VERIFYING LINEUP AND INITIALS (PRINT) REMARKS: Started: Completed:
Comments Comments reviewed reviewed with with Student Student Evaluator Evaluator Signature:
Approved by: DOCUMENT any components NOT in required position and reason below. Page may be duplicated as necessary.
Signature:                                                Date:___________
Date ________ _ Time ________ _ Date ________ _ Time ________ _ I SRO Date Time C Continuous Use \20P-21 Rev. 65 Page 51 of 791 ATTACHMENT 2 Page 2 of 2 Reactor Building Closed Cooling Water System Panel Lineup Number Description Position/
Date: -----
Checked Indication Control Building -RTGB Panel XU2 -EI49' -Control Room 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 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 OPEN (Pen. X77-C) RCC-V28 RBCCW to OW 1501 Vlvs OPEN RCC-V52 RBCCW to OW 1501 Vlvs OPEN Radwaste Control Room -Panel HB9 RCC-V75 Cooling Wtr Sply OPEN 1 2 0 P-21 Rev. 65 Page 52 of 791 ATTACHMENT 3 Page 1 of 22 Reactor Building Closed Cooling Water System Valve Lineup PERSON(S)
LOT-OJT-JP-201-E04 LOT-OJT-JP-201-E04                                Page 88 Page                                          REV. 01 REV. 01
PERFORMING OR VERIFYING LINEUP AND INITIALS (PRINT) REMARKS: Started: Completed:
 
Approved by: DOCUMENT any components NOT in required position and reason below. Page may be duplicated as necessary.
ATTACHMENT 4 Sheet I10f      of I1 Operations Clearance Checklist Clearance No__________________
Date ________ _ Time ________ _ Date ________ _ Time ________ _ / SRO Date Time C Continuous Use 120P-21 Rev. 65 Page 53 of 791 ATTACHMENT 3 Page 2 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
Clearance No. - - - - - - - -
Checked Indication Reactor Building -North RHR Room -EI-17' -North RCC-V76 RBEDT Cooler Inlet Air Operated Valve CLOSED RCC-V76 RBEDT Cooler Inlet Air Operated Valve Manual NEUTRAL Actuator RIA-IV-215 Instrument Air Isolation Valve To RCC-V76 OPEN 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 20' -Northeast RCC-FE-1822-1 High Pressure Root Valve To RCC-FE-1822 CLOSED RCC-FE-1822-2 Low Pressure Root Valve To RCC-FE-1822 CLOSED RCC-FE-2257  
Page _ _ of _ _
-1 High Pressure Root Valve To RCC-FE-2257 CLOSED RCC-FE-2257  
Page_of Checklist Type: Hang;  Hang: Lift; Uft; Boundary Change (Circle one)
-2 Low Pressure Root Valve To RCC-FE-2257 CLOSED Reactor Building -North RHR Pump Room (Overhead) -EI-17 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' -South RCC-V144 CRD Pump 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 120P-21 Rev. 65 Page 54 of 791 ATTACHMENT 3 Page 3 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
INT     NAME (FRINT)(PRINT)                                   INT       NAME (PRINT)
Checked Indication Reactor Building -CRD Pump Area -EI-17' -South RCC-U-V4 CRD Pump B Outboard Bearing Cooling OPEN Isolation Valve RCC-U-V5 CRD Pump B Inboard Bearing Cooling Isolation OPEN Valve RCC-U-V6 CRD Pump B Lube Oil Cooling Isolation Valve OPEN RCC-V142 CRD Pump B Cooling Water Outlet Test Valve CLOSED RCC-V7 CRD Pump B Cooling Water Outlet Valve OPEN RCC-V295 CRD Pump 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 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 120P-21 Rev. 65 Page 55 of 791 ATTACHMENT 3 Page 4 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
  " Independent             Required? YE&NO Veriiication R,equired?
Checked Indication Reactor Building -Post Accident Sampling Skid -EI 20' -South RCC-V315 RBCCW To Post Accident Sampling System LOCKED OPEN RCC-V316 RBCCW From Post Accident Sampling System LOCKED OPEN Reactor Building -Southeast Drywell Wall -EI 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-1824 CLOSED RCC-FE-1824-2 Low Pressure Root Valve To RCC-FE-1824 CLOSED Reactor Building -Penetration X77 -EI. 20' -Az 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 50' -North RCC-V44 RBCCW HX C Inlet Valve OPEN RCC-V158 RBCCW HX C Inlet Test Valve CLOSED RCC-V115 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 Rev. 65 Page 56 of 791 ATTACHMENT 3 Page 5 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
independent Verficticn                              r'lI.A. Ule
Checked Indication Reactor Building -RBCCW HX Area -EI 50' -North RCC-V112 RBCCW HX B Inlet Vent Valve CLOSED RCC-V113 RBCCW HX B Shell Side Drain Valve CLOSED RCC-V123 RBCCW HX B Outlet Vent Valve CLOSED RCC-V160 RBCCW HX B Outlet Test Valve CLOSED RCC-V46 RBCCW HX B Outlet Valve CLOSED RCC-V42 RBCCW HX A Inlet Valve OPEN RCC-V156 RBCCW HX A Inlet Test Valve CLOSED RCC-V109 RBCCW HX A Inlet Vent Valve CLOSED RCC-V110 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 Instrument Isolation Valve OPEN 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 RCC-PT -671, RCC-PS-672, And RCC-PSL-673 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 120P-21 Rev. 65 Page 57 of 791 ATTACHMENT 3 Page 6 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
                                        'YESINO Iff NO, N/A        ciocics the Blocks Seq Action Type                   Tag idId Position               Equipment/Component         Completed. Verified Verified By By           ..
Checked Indication Reactor Building -RBCCW Pump Area -EI 50' -North RCC-V102 Chemical Addition Tank Inlet Valve CLOSED RCC-V103 Chemical Addition Tank Outlet Valve CLOSED RCC-V104 Chemical Addition Tank Vent Valve CLOSED 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 '(RCC-V30 RBCCW Pump C Suction Valve OPEN RCC-V58 RBCCW Pump C Suction Test Valve CLOSED /(
Continued Y lI N QARECORD QA RECORD I OPS-NGGC-'130 OPS-NGGC-i 3011                                                Rev. 20                                       121 Page 95 of '121
RBCCW Pump C Suction Drain Valve CLOSED )
 
RBCCW Pump C Casing Vent Valve CLOSED (' vi RBCCW Pump C Discharge Drain Valve CLOSED _"..;1" RCC-V117 RBCCW Pump C Discharge Pressure Root OPEN Valve To RCC-PI-668 RCC-PI-668-3 RCC-PI-668 Instrument Isolation Valve OPEN RCC-PI-668-6 RCC-PI-668 Instrument Drain Valve CLOSED (:'''" "RCC-V34 -) RBCCW Pump C Discharge Valve OPEN RCC-V31 RBCCW Pump 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 Discharge Pressure Root OPEN Valve To RCC-PI-669 1 2 0 P-21 Rev. 65 Page 58 of 791 ATTACHMENT 3 Page 7 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
TASK CONDITIONS:
Checked Indication Reactor Building -RBCCW Pump Area -EI 50' -North 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 Discharge Valve OPEN RCC-V32 RBCCW Pump A Suction Valve OPEN RCC-V67 RBCCW Pump A Suction Test Valve CLOSED 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-V119 RBCCW Pump A Discharge Pressure Root OPEN Valve To RCC-PI-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 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 High Pressure Root Valve To RCC-FE-1821 CLOSED RCC-FE-1821-2 Low Pressure Root Valve To RCC-FE-1821 CLOSED 120P-21 Rev. 65 Page 59 of 791 ATTACHMENT 3 Page 8 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position!
: 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.
Checked Indication Reactor Building -RBCCW Pump Area -EI 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' RCC-V149 RWCU Pump B Cooler Inlet Test Valve CLOSED RCC-V304 RWCU Pump B Cooler Inlet Valve OPEN RCC-V5087 RWCU Pump B Gear Box Cooling Isolation OPEN Valve RCC-V5088 RWCU Pump B Cooler Outlet Throttle Valve OPEN RCC-V306 RWCU Pump B Cooler Outlet Isolation Valve OPEN RCC-V147 RWCU Pump 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 120P-21 Rev. 65 Page 60 of 791 ATTACHMENT 3 Page 9 of 22 Reactor Building Closed Cooling Water System Valve Lineup Number Description Position/
: 2. A Clearance has been requested by maintenance to place RBCCW Pump 2C under clearance for pump packing replacement.
Checked Indication Reactor Building -RWCU Pump and Heat Exchanger Room -EI 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 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  
: 3. RBCCW Pumps 2A and 2B will remain running.
-1 High Pressure Root Valve To RCC-FE-2887 CLOSED RCC-FE-2887  
INITIATING CUE:
-2 Low Pressure Root Valve To RCC-FE-2887 CLOSED Reactor Building -RWCU Precoat Pump Area -EI 80' -East RCC-V181 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 Rev. 65 Page 61 of 791 CAROLINA POWER & LIGHT COMPANY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT 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 Time Limitations in High Radiation Area SAFETY CONSIDERATIONS:
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.
None. EVALUATOR NOTES: (Do not read to performer)
 
: 1. The attached Radiological Survey WILL be provided to the performer.
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&deg;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.
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.
: 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-102-A03 Page 2 of 9 Rev.01 Determine Stay Time Limitations in High Radiation Area Read the following to the JPM 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:
TASK CONDITIONS:
Two workers will be required to perform an emergent 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.[[estimated NRC review hours::5 hours]] Following completion of the job, an additional 15 mrem per worker will be received during staging activities.
TASK  CONDITIONS:
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.
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.
LOT-ADM-JP-102-A03 Page 3 of 9 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 YES NO (Circle Yes or No) LOT -ADM-JP-1 02-A03 Page 4 of 9 Rev.01 Determine Stay Time Limitations in High Radiation Area PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Worker #1 has accumulated 500 mrem this year (Progress Energy dose only).
NOTE: Provide the examinee the JPM attached survey map. TIME START ___ _ Step 1 -Determines dose for each worker as follows: a. Staging time in access area directly outside the SJAE room (45 min) 0.75 Hr X 5 mrlhr = 3.75 mrem Estimate 3.75 mrem dose accumulation.  
has accumulated 1615 Worker #2 has                 1615 mrem this year (Progress Energy dose only).
** CRITICAL STEP** SAT/UNSAT*
The following times for each worker have been estimated for performance performance of the job.
: b. Staging time in area directly inside SJAE room access door (15 min) 0.25 Hr X 16 mrlhr = 4 mrem Estimate 4 mrem dose accumulation.  
: 1. Staging time in access area directly outside the A SJAE Room           45 minutes
** CRITICAL STEP** SAT/UNSAT*
: 2. Staging time in area directly inside A SJAE room access door           15 minutes
: c. Work time at the SPE 2A 1.5 Hr X 325 mrlhr = 487.5 mrem Estimate 487.5 mrem dose accumulation.  
: 3. Work time at the 2A SPE                                                 1.5 1 .5 hours Following completion of the job, an additional 15 mrem per worker will be received during       de-de staging activities.
** CRITICAL STEP** SAT/UNSAT*
INITIATING CUE:
: d. An additional 15 mr will be accumulated once the job is done for de-staging activities.  
Using the information above and the radiological survey provided, evaluate the leak repair job for possible performance under current plant conditions to include:
** CRITICAL STEP** SAT/UNSAT*
: 1. Determine the projected dose each worker would receive to perform the leak repair.
LOT -ADM-JP-1 02-A03 Page 5 of 9 Rev.01 Determine Stay Time Limitations in High Radiation Area e. Total = 3.75 + 4 + 487.5 + 15 = 510.25 mrem Determines Total dose for job completion  
(Assume the same task times for both workers)
-510.25 mrem. ** CRITICAL STEP** SAT/UNSAT*
: 2. Based upon the projected total accumulated dose, determine if any Progress Energy administrative dose limitations will be exceeded.
Step 2 -Determines that Worker #2 would exceed the PGN administrative limit of 2 REM per calendar year if the estimated dose were accumulated.
LOT-ADM-JP-1    02-A03 LOT-ADM-JP-102-A03                         Page Page 33 of of 99                                    Rev.01 Rev.01
Worker #1 Worker #2 500 mr + 510.25 mr = 1010.25 mr << 2R limit) 1615 mr + 510.25 mr = 2125.25 mr (> 2R limit) ** CRITICAL STEP** SAT/UNSAT*
 
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 +&#xf7; 510.25 mr =
                                                =  1010.25 mr <<(< 2R limit)
Worker #2    1615 mr +&#xf7; 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.
TERMINATING CUE: When the total dose for each worker has been determined and the administrative limits addressed, the JPM is complete.
TIME COMPLETED
TIME COMPLETED _ _ _ __
____ _ *NOTE: Comments required for any step evaluated as UNSAT. LOT-ADM-JP-102-A03 Page 6 of 9 Rev.01 Determine Stay Time Limitations in High Radiation Area RELATED TASKS: (Specify)
*NOTE: Comments required for any step evaluated as UNSAT.
KIA REFERENCE AND IMPORTANCE RATING: 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.  
*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:==
==REFERENCES:==
Line 235: Line 632:
HPS-NGGC-0003 DOS-NGGC-0004 TOOLS AND EQUIPMENT:
HPS-NGGC-0003 DOS-NGGC-0004 TOOLS AND EQUIPMENT:
Calculator.
Calculator.
JPM Survey Map SAFETY FUNCTION (from NUREG 1123): A.3 Radiation Control REASON FOR REVISION:
JPM Survey Map SAFETY FUNCTION (from NUREG 1123):
2010-1 NRC Exam -Modified to different location and rates. LOT -ADM-JP-1 02-A03 Page 7 of 9 Rev.01 Determine Stay Time Limitations in High Radiation Area Validation Time: __
A.3 Radiation Control REASON FOR REVISION:
Minutes (approximate).
2010-1 NRC Exam - Modified to different location and rates.
Time Taken: ___ _ APPLICABLE METHOD OF TESTING Performance:
LOT-ADM-JP-1 LOT-ADM-JP-1 02-A03                         Page 77 of 99                              Rev.01
Simulate Setting: In-Plant Time Critical:
 
Yes Alternate Path: Yes Actual Simulator No L No EVALUATION Unit: 2 Admin X Time Limit N/A Performer:
Stay Time Limitations in High Radiation Area Determine Stay Validation Time: __1.:...;:5~_
___________________
15        Minutes (approximate).
_ JPM: Pass Fail --Remedial Training Required:
Minutes Time Taken: _ _ __
Yes No __ (Reference T AP-411 for evaluation guidance)
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:
Comments reviewed with Performer Evaluator Signature:
Comments reviewed with Performer Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ __                      Date:___________
____________
Date: -----
_ Date: -----LOT -ADM-J P-1 02-A03 Page 8 of 9 Rev.01 2T06 BRUNSWICK NUCLEAR PLANT RADIOLOGICAL SURVEY SURVEY NO 1717 -003 -DATE:
LOT-ADM-JP-1 LOT-ADM-J P-1 02-A03                           Page 8of9 8 of 9                             Rev.01 Rev.O1
0600 DOSE RATE CONTAMINATION TIME: INST. TYPE Telelector IJ"D aD IJ"D aD SURVEYOR Joe H. Physics SERIAL NO. T191A L-l77 M52 pCC' -;t:
 
INSTISN SIGNATURE 100% EFF 0.10 0.'18 -;'1' RX POVVER RE'y'IEWED H2SCFM 3*3 BKGD. 40 CPM 22 CPM 2 TB 20' "An STEAM JET AIR EJECTOR ROOM UNIT __ BLDG --EL --AREA ______________
BRUNSWICK NUCLEAR BRUNSWICK             NUCLEAR PLANT     PLANT RADIOLOGICAL SURVEY RADIOLOGICAL             SURVEY SURVEY SURVEY NO     NO.
_ RWPNO. Cor .... 1PONENT OR TAG NO. SPE 2A WR/JO 002seS62 WORK PERFOR!.,.1ED
1717 1717         - 003 2TO 2T06                                                                                                                                                -
_:-_e"'_h_R_e;..p"_ir
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
PlJo.TFOR\f I 103 1182 1--1 AF"l"ER CD COt..:JE"iG*=-:
                          -;'1' S<<f:{"I:oi4(l~                                                        3*3                                  40                  CPM 22 CPM                        CPM CPM REVIEWED RE'y'IEWED                                                                       H2 CFM H2SCFM                                     BKGD.
CD 325 X I I ! Work Area 1 'Note: This is High nOise area ' .... hile operating.
22 BLDG -        TB- EL -
5 RA -R!o.DiA 710N AREA -HIGH RADIA 71C1N AREA LMRA -LOCK::D H0H AREA RCA C:)NT::;:OL CA HeA -HIG'i COIFAMINAnCN AREA AA -AiRBORNE AREA R8PE L::"
TB                   20- AREA _
E ..
20'                 A_
SMEAR RESULTS IN DPMI100 eM" B=9ETA IH mRAD/HRI!OOCM
                                                                        "An STEAM           AiR_  EJECTOR ROOM UNIT UNITBLDG __                           EL_AREA                              _ _JET    __  AIR  EJECTOR
: M=CF'f,l.'MASLIN NO. RESUL:S *:MD.L, A TASK CONDITIONS:
_ _ _ _ _ _ __                    RWPNO RWPNO.
Two workers will be required to perform an emergent 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.[[estimated NRC review hours::5 hours]] Following completion of the job, an additional 15 mrem per worker will be received during staging activities.
PE 2A SPE                                                                          WR/JO COMPONENT Cor   ....1PONENT OR      OR TAG NO. NO.                                                                                          WRiJC) 002seS62     =
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.
WORK WORK PERFORMED PERFOR!.,.1ED           eak epar_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
LESSON TITLE: LESSON NUMBER: REVISION NO: PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C001 (RO/SRO) Core Performance Parameter Check LOT-ADM-201-D02 01 Core Performance Parameter Check SAFETY CONSIDERATIONS:
_:-_e"'_h_R_e;..p"_ir                                                                                                     SMEAR RESULTS IN DPMI100 eM" B=9ETA IH mRAD/HRI!OOCM :
: 1. NONE. EVALUATOR NOTES: (Do not read to examinee)
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 hours 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.
: 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.
: 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.
: 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.
Read the following to examinee.
TASK CONDITIONS:
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.
: 1. The CODSR requires performance of 2PT-01.11, Core Performance Parameter Check, on Unit Two.
* 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: The Unit SCO has directed you to complete 2PT-01.11, Core Performance Parameter Check, utilizing the Core Performance Log provided and provide the results below upon completion.
: 2. All applicable prerequisites of 2PT-01.11 are met.
2PT-01.11, Core Performance Parameter Check, results are (circle choice): SAT UNSAT Comments (if necessary):
: 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.
_ 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): UNSAT Comments (if necessary):
* The Step number followed by a short description of the Action.
______________________
: 5. Cover page information will be filled out by the Unit SCO.
_ Step 7.1.7 -APRM 1 gain adjustment factor is greater than 1.00 Step 7.1.11 -CMFLPD is greater than 1.00, Unit SCO notified.
INITIATING CUE:
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.
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.
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.
2PT-01.11, Core Performance Parameter Check, results are (circle choice):
Step 1 -Obtain current revision of 2PT-01.11 and verify if applicable.
SAT                       UNSAT Comments (if necessary): _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Current revision of 2PT-01. 11 obtained and verified as required.
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*
SAT/UNSAT*
TIME START ___ _ PROMPT: Provide the Core Performance Log attached to this JPM to be evaluated by candidate.
NOTE:          Steps 7.1.4.1.a and b (WFWFFLG OR NSSCUFLG OR NSSCRFLG are NOT equal to 1) should be marked N/A.
NOTE: APRM gain adjustment and PPC usage are not being evaluated by this JPM. Step 2 -OBTAIN an edit of the process computer core performance program. Core Performance Log obtained from Evaluator.
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 hours, or be below 23%
power within the next 4 hours). 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*
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.
LOT-ADM-JP-201-D02 LOT -ADM-JP-20 1-002                          Page 6 of 12                                 Rev. 01
Determines no failed sensors exist and marks this step as NIA. SATIUNSAT*
 
Step 4 -Evaluates value of NSSFFLG is equal to 1. Determines NSSFFLG is equal to 1 and proceeds to Step 7.1.4. SATIUNSAT*
Core Performance Core Performance Parameter Parameter Check Check NOTE:
NOTE: steps 7.1.3.1.aand b (NSSFFLG is NOTequal to 1) should be marked N/A. LOT -ADM-J P-20 1-D02 Page 4 of 12 Rev. 01 Core Performance Parameter Check Step 5 -Evaluates value of WFWFFLG, NSSCUFLG, and NSSCRFLG all equal to 1. NOTE: Determines WFWFFLG, NSSCUFLG, and NSSCRFLG are all equal to 1 and proceeds to Step 7.1.4. SAT/UNSAT*
NOTE:                  7.2 should be Section 7.2          be marked marked N/A.
Steps 7.1.4.1.a and b (WFWFFLG OR NSSCUFLG OR NSSCRFLG are NOT equal to 1) should be marked N/A. Step 6 -Determine if criteria listed in Section 6.1 of 2PT-1.11 are met. NOTE: NOTE: Checks core performance log and verifies value for CMFLCPR :::1.00. ** CRITICAL STEP ** SAT/UNSAT*
NOTE:
Checks core performance log and verifies value for CMAPRA T :::1.00. ** CRITICAL STEP ** SA TlUNSAT* Checks core performance log and verifies value for CMFDLRX :::1.00. ** CRITICAL STEP ** SAT/UNSAT*
NOTE:         Attachments 2 and 3 may  may be be discarded.
Steps 7.1.6 and 7.1.6.1 (limits specified inSeclion 6.1 are NOT satisfied) should be marked N/A. Report of APRM1 GAF >1.00 is not required to satisfy Critical Step. 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). Determines APRMS 2, 3, and 4 are within limits and APRM 1 is above the limit. ** CRITICAL STEP ** SAT/UNSAT*
Step 13 - ENSURE the required information has been recorded on the cover page.
PROMPT: If informed that APRM 1 GAF is > 1.00, acknowledge the report and inform the trainee the APRM will be adjusted later. Direct the trainee to continue the PT. LOT-ADM-JP-201-D02 Page 5 of 12 Rev. 01 Core Performance Parameter Check NOTE: Steps 7.1.8 and 7.1:9 (APRMgain adjustment) should be marked N/A. Step 8 -Determine if CMFLPD is 1.00. Checks core performance log and recognizes CMFLPD is >1.00. ** CRITICAL STEP ** SAT/UNSAT*
Cover page information to be filled out by Unit SCQ  SCO per cue.
NOTE: Note prior to Step 7.1.10 -Reference 2.5 states.that NRC expects LHGR monitoring (CMFLPD) to remain the same as CPR and APLHGR forGNF fuel (i.e., to restore LHGR within limits within [[estimated NRC review hours::4 hours]], or be below 23% power within the next [[estimated NRC review hours::4 hours]]). 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 ** CRITICAL STEP ** SAT/UNSAT*
SAT/U NSAT*
Step 10-NOTIFY the On-Shift Reactor Engineer to take action to restore CMFLPD to an acceptable value. Notifies RE to restore CMFLPD to 1.0. ** CRITICAL STEP ** SAT/UNSAT*
Step 11 -ENSURE Acceptance Criteria listed in Section 6.0 have been satisfied.
Determines Acceptance Criteria has been satisfied.  
** 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/UNSAT*
SAT/UNSAT*
LOT -ADM-JP-20 1-002 Page 6 of 12 Rev. 01 Core Performance Parameter Check NOTE: Section 7.2 should be marked N/A. NOTE: Attachments 2 and 3 may 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 per cue. 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.
Step 14 -Notify the Unit SCQ that 2PT-01.11 is completed SAT with CMFLPO greater than 1.00 which required RE notification to restore 1.0 and APRM 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.
Unit SCQ notified 2PT-01.11 is completed SAT with APRM 1 requiring gain adjustment to restore GAF to 1.0 and CMFLPD is > 1. O. RE has been notified to take action to restore CMFLPD to 1. O. ** CRITICAL STEP ** SAT/UNSAT*
is> 1.0.
TERMINATING CUE: 2PT..;01.11 acceptance criteria verified.
O. RE has been notified to take action to restore CMFLPD to ~< 1. 1.0.
and the Unit SCQ informed the results are satisfactory.
O.
TIME COMPLETED
                                                        **                      ** SATIUNSAT*
____ _
                                                        **  CRITICAL STEP **       SAT/UNSAT*
* Comments required for any step evaluated as UNSAT. LQT -AOM-JP-20 1-002 Page 7 of 12 Rev. 01 Core Performance Parameter Check LIST OF REFERENCES RELATED TASKS: 2992018201:
TERMINATING CUE: 2PT..;01.11 2PT-01 .11 acceptance criteria verified verified. and the Unit SCQ SCO informed the results are satisfactory.                                   -
Perform Daily Surveillance Report Per 01-3.1 or 01-3.2. KIA REFERENCE AND IMPORTANCE RATING: Generic 2.1.7 (3.7/4.4)
TIME COMPLETED _ _ _ __
Ability to evaluate plant performance and make operational judgments based on operating characteristics 1 reactor behavior 1 and instrument interpretation.  
* 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:==
==REFERENCES:==


2PT-01.11 TOOLS AND EQUIPMENT:
2PT-01 .11 2PT-01.11 TOOLS AND EQUIPMENT:
None. SAFETY FUNCTION (from NUREG 1123, Rev 2): 7 -Instrumentation (APRM System) REASON FOR REVISION:
None.
Revised to allow classroom performance.
SAFETY FUNCTION (from NUREG 1123,    I 123, Rev 2):
Unit 2 process computer core performance program edit will be provided to examinee.
7 - Instrumentation (APRM System)
LOT -ADM-J P-20 1-002 Page 8 of 12 Rev. 01 Core Performance Parameter Check Time Required for Completion: Minutes (approximate).
REASON FOR REVISION:
Time Taken: ______ _ APPLICABLE METHOD OF TESTING Performance:
Revised to allow classroom performance. Unit 2 process computer core performance program edit will be provided to examinee.
Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical:
LOT-ADM-JP-201-D02 LOT -ADM-J P-20 1-002                      Page 8 of 12                                   Rev. 01
Yes No L Time Limit N/A Alternate Path: Yes No 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 9 of 12 Rev. 01 TASK CONDITIONS:
: 1. The CQDSR 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 SCQ. INITIATING CUE: The Unit SCQ has directed you to complete 2PT-01.11, Core Performance Parameter 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 BRUNSWICK-2 WK-1016 10TODAY-07.00.27 8902 MWD/MTU TRIGR=2HR CORE PERFORMANCE LOG ---LONG EDIT TL 0 TLO TBVINS NSS NFWT BOC TO NEOC CTP CALCULATION
: HEAT BALANCE SYMMETRY : FULL STATE CONDITIONS FLOW (MLB/HR) GMWE 973.2 WT 78.84(102.4%)
CMWT 2905.9 (99.4%) WDP 78.50 PR 1044.2 PSIA NSSFFLG 1. DHS 20.85 BTU/LB WFW 12.72 CRD 0.0931 WFWFFLG 1. CYEXP 8902.3 MWD/MT NSSCUFLG 1. CAVEX 22911.1 MWD/MT NSSCRFLG 1. RODLINE 97.9% WD 36.40 NON_EO XE -1.7% LOCATION 2 3 AXIAL REL POWER 0.40 0.94 1.14 REGION REL POWER 0.94 1.00 0.92 RING REL POWER 0.96 1.14 1.06 APRM GAFS 1.02 1.00 0.98 4 1.18 1.03 1.14 0.99 CORE PARAMTRS CMEO 0.2791 CAEO 0.1634 CAOA 0.1538 CAVF 0.4548 CAPD 58.934 RWL 187.5460 CDLP 25.0146 DPCC 30.3681 KEFF 0.9971 5 6 7 1 .18 1.20 1 .21 1.08 1.05 0.93 1.14 1.09 0.65 NUCLEAR P-PCS P-PCFC CMFLCPR CMAPRAT CMFDLRX CMFLPD CMINCPR 8 9 1. 11 1.07 1.03 0.96 ***************
NUCLEAR LIMITS BY REGION ***************
7 8 9 0.867 13-40 0.860 31-40 0.885 39-40 0.750 17-42-15 0.759 33-44-15 0.767 41-36-15 0.688 09-36-13 0.704 33-42-13 0.702 43-36-13 0.622 11 13 0.652 33-36-18 1.155 41-36-13 -----------------
-+------------------
-+----------------
--4 5 6 0.838 13-32 0.821 31-32 0.865 39-32 0.758 09-20-13 0.714 27-28-18 0.769 43-34-15 0.700 11 13 0.663 33-34-18 0.895 41-34-13 0.611 09-20-13 0.566 27-28-17 0.895 43-34-15 -----------------
-+------------------
-+----------------
--1 2 3 0.864 13-14 0.822 21 -14 0.852 39-14 0.749 11-18-15 0.748 19-10-13 0.736 41-18-13 0.691 09 13 0.693 19-12-13 0.684 43-18-13 0.619 11-18-13 0.602 19-10-13 0.613 41-18-13 REV=usep06 CYCLE: 19 LIMITS LOCATION -0.06 33-36-19 -0.06 33-36-19 0.885 39-40 0.769 43-34-15 0.895 41-34-13 1 .155 41 13 1.528 39-40 10 11 12 0.99 0.90 0.68
**********
* MFLCPR *
* MAPRAT *
* MFDLRX *
* MFLPD * **********
*AXIAL REL POWER* NODE NOTCH REL-POW EXP(GWD/MT) 25 0.187 24 00 0.608 23 02 0.784 D 22 04 0.939 21 06 1.035 20 08 1.088 19 10 1.102 18 12 1.097 17 14 1.078 C 16 16 1.035 -15 18 1.023 14 20 1. 111 13 22 1.116 12 24 1.128 11 26 1.150 B 10 28 1.181 9 30 1.203 8 32 1 .211 7 34 1.216 6 36 1.214 5 38 1.201 A_4 40 1.166 3 42 1.077 2 44 0.846 1 46 0.242 # NODES W/ LIMITS> 1 FLCPR APRAT FDLRX FLPD o o o 1 3.842 11 .154 18.881 23.791 27.184 29.224 30.344 30.901 31.147 30.565 30.935 29.084 29.780 30.578 31.298 31.895 32.380 33.056 33.871 34.675 35.119 34.452 31.119 23.396 6.163 ***************
THE 10 MOST LIMITING BUNDLES *****************
FLCPR LOC CPR LIMIT APRAT LOC APLHGR LIMIT FDLRX LOC LPD LIMIT FLPD LOC LPD LIMIT
---------------------0.909 39-40 1.518 1.381 0.867 43-34-15 8.01 9.25 0.895 41-34-13 9.53 0.00 1 . 1 55 41 13 8.45 13.40 0.905 39-36 1.525 1.381 0.866 41-36-15 8.09 9.35 0.704 33-42-13 9.43 0.00 1 .058 35 13 8.36 13.40 0.894 39-32 1.544 1.381 0.854 35-42-15 7.55 8.84 0.702 43-36-13 9.41 0.00 0.895 43-34-15 8.33 13.40 0.893 35-40 1.546 1.381 0.840 33-44-15 7.78 9.26 0.694 35-44-13 9.30 0.00 0.652 33-36-18 8.19 13.40 0.892 31-40 1.548 1.381 0.833 33-36-18 7.72 9.26 0.691 41-42-05 9.27 0.00 0.610 33-44-13 8.18 13.40 0.888 37-38 1.554 1.381 0.833 41-28-17 9.49 11.38 0.687 35-36-18 9.20 0.00 0.606 35-34-18 8.12 13.40 0.883 39-28 1.563 1.381 0.825 25-42-17 9.35 11.34 0.685 39-40-05 9.18 0.00 0.600 27-42-17 8.04 13.40 0.880 37-34 1.568 1.381 0.818 35-34-18 7.38 9.02 0.676 39-36-13 9.05 0.00 0.598 41-28-16 8.01 13.40 0.876 37-30 1.576 1.381 0.816 39-42-06 7.13 8.73 0.672 41-44-05 9.00 0.00 0.593 43-38-13 7.95 13.40 0.872 43-32 1.583 1.381 0.816 41-32-15 7.21 8.84 0.671 35-40-13 8.99 0.00 0.591 41-32-15 7.92 13.40 BRUNSWICK-2 WK-1016 10TODAY-07.00.27 8902 MWD/MTU TRIGR=2HR 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* 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 38.8 63.3 55.6 56.5 60.3 57.2 C 43.0 61.2 58.9 60.6 61.6 57.9 B 36.2 54.6 45.7 47.7 52.5 86.6 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 DATE COMPLETED
_________
_ FREQUENCY:
c Continuous Use UNIT _2_ % PWR GMWE __ SUPERVISOR
___________
_ REASON FOR TEST (check one or more) A. Once/[[estimated NRC review hours::24 hours]] when operating 23% rated thermal power _ Routine Surveillance
_W/O# ______________________
_ B. Within [[estimated NRC review hours::12 hours]] after thermal power is 23% of rated thermal power _ Other (explain)
PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT 2 2PT-01.11 CORE PERFORMANCE PARAMETER CHECK REVISION 7 1 2PT-0 1.11 Rev. 7 Page 1 of 14/
1.0 PURPOSE This PT provides a procedure for obtaining the basic core performance parameters required by Technical Specifications and calibrates APRM channels to 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 REFERENCES==
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


2.1 Technical Specifications 2.2 NEDE-24011-P-A (GESTAR II), Amendment 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 Heat Generation Rate Monitoring," October 9,1989, LMQ: 89-241 2.6 001-72, Plant Process Computer System Operating Instruction 2.7 00P-55, Process and ERFIS Computer System Operating Procedure 2.8 OPT-01.8C, Hand Calculation of AGAFs 2.9 OPT-01.8D, Core Thermal Power Calculation 2.10 OENP-24.19, Operation of the BWR Process Computer Backup Program 2.11 20P-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 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.  
TASK CONDITIONS:
/2PT-01.11 Rev. 7 Page 2 of 14/
: 1.           CODSR requires performance of The CQDSR                              of2PT-O1.11, 2PT-01.11, Core Performance Parameter Check, on Unit Two.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Special care should be taken in verifying data. Errors on the nonconservative side could cause operation that might lead to a violation of Technical Specifications.
: 2.                                     2PT-O1.11 are met.
3.2 IF the value of a core performance parameter exceeds its limits, THEN the Unit SCQ should be immediately notified.
All applicable prerequisites of 2PT-01.11
3.3 During APRM gain adjustments, the plant should be held at a steady state operating condition.
: 3. No APRM gain adjustments will be performed during this test.
During APRM gain adjustments, the affected APRMs may be bypassed.
: 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.
3.4 IF APRM gain adjustments are made, THEN Independent Verification is required.
* The Step number followed by a short description of the Action.
4.0 PREREQUISITES Thermal power is greater than or equal to 23% 5.0 SPECIAL TOOLS AND EQUIPMENT None 6.0 ACCEPTANCE CRITERIA OTE: 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 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. (See Attachment 2 for parameter location on the core performance edit; applicable to AREVA fuel bundles only) 6.2 At least three operable APRMs are adjusted such that the APRM gain adjustment factors (GAFs) are less than or equal to 1.00. The APRM gain adjustment factor is determined by either the periodic NSS Core Performance Log (Attachment 2), Display 820 (Heat Balance/Core Mon), or hand calculation of AGAFs (OPT-01.8C).
: 5. Cover page information will be filled out by the Unit SCQ.
IF APRM gain adjustments are performed, THEN the postadjustment AGAFs are verified by a second Display 820 or OPT-01.8C.  
SCO.
/2PT-01.11 Rev. 7 Page 3 of 14/
INITIATING CUE:
7.0 PROCEDURALSTEPS Initials NOTE: Attachments 2 and 3 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: Plant process computer operating instructions and report codes are contained within procedures 001-72 and 00P-55. 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.
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.
NOTE: Attachment 2 shows the location of NSSFFLG on the Core Performance Log. 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:
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 hours 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.
: a. NOTIFY the On-Shift Reactor Engineer to evaluate if core flow is accurate for thermal limit calculations.
12PT-01.11
: 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.
: b. IF core flow was changed by the On-Shift Reactor Engineer in Step 7.1.3.1.a, THEN OBTAIN a new Core Performance Log edit. Rev. 7 Page 4 of 14/
2PT-01 .1 1 12PT-01.11                                    Rev. 7                                         14 Page 4 of 14/
7.0 PROCEDURAL STEPS Initials NOTE: Attachment 2 shows the respective locations of WFWFFLG, NSSCUFLG, and NSSCRFLG on the Core Performance Log. 7.1.4 IF WFWFFLG AND NSSCUFLG AND NSSCRFLG are equal to 1, THEN GO TO Step 7.1.5. 1. IF WFWFFLG OR NSSCUFLG OR NSSCRFLG are NOT equal to 1, THEN PERFORM the following:
 
: a. NOTIFY the On-Shift Reactor Engineer to evaluate accuracy of inputs to the heat balance calculation.
7.0 7.0 PROCEDURAL STEPS PROCEDURAL          STEPS                                                        Initials Initials NOTE:
: b. IF inputs to the heat balance were changed by the On-Shift Reactor Engineer in Step 7.1.4.1.a, THEN 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
NOTE:      Attachment 22 shows     the respective locations shows the                        of WFWFFLG, locations of WFWFFLG, NSSCUFLG, NSSCUFLG, NSSCRFLG on the Core Performance Log.
: 2. 7.1.6 IF limits specified in Section 6.1 are NOT satisfied, THEN NOTIFY the Unit SCO of the condition.
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. 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 IF an APRM gain adjustment is necessary, THEN PERFORM applicable section of 20P-09. 7.1.9 IF an APRM gain change was performed, THEN OBTAIN from the process computer a copy of Display 820, Heat Balance/Core Mon, OR PERFORM OPT-01.8C to ensure APRM GAFs satisfy the requirements of Acceptance Criteria, Section 6.2. / IndVer. 12PT-01.11 Rev. 7 Page 5 of 141 7.0 PROCEDURAL STEPS Initials NOTE: Reference 2.5 states that NRC expects LHGR monitoring (CMFLPD) to remain the same as CPR and APLHGR for GNF fuel (Le., to restore LHGR within limits within [[estimated NRC review hours::4 hours]], or be below 23% power within the next [[estimated NRC review hours::4 hours]]). 7.1.10 DETERMINE, from the core performance edit, if CMFLPD is less than or equal to 1.00 (Attachment 2 for CMFLPD location on the core performance edit). 7.1.11 IF CMFLPD is greater than 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.
: 1. IF WFWFFLG OR NSSCUFLGNSSCUFLG OR NSSCRFLG are NOT      NOT equal to 1, 1, THEN PERFORM PERFORM the following:
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.
: a.     NOTIFY the On-Shift Reactor Engineer to evaluate NOTIFY accuracy of inputs to the heat balance calculation.
The On-Shift Reactor Engineer should be contacted to perform this section. 7.2.1 PERFORM OPT-01.8D to calculate core thermal power. 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 Rev. 7 Page 6 of 14/
: 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.
7.0 PROCEDURAL STEPS 7.2.5 IF limits specified in Section 6.1 are NOT satisfied, THEN NOTIFY the Unit SCQ of the condition.
7.1.5       DETERMINE from the core performance edit, if criteria listed in Section 6.1 are met.
: 1. NOTIFY the On-Shift Reactor Engineer to take action to restore thermal limits to acceptable values. 7.2.6 PERFORM OPT-01.8C to determine if acceptance criteria listed in Section 6.2 are satisfied.
NOTE:       Locations on the core performance edit where thermal limit parameters are found are indicated on Attachment 2.
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 another OPT-01.8C to ensure APRM gain adjustment factor satisfies the requirements of Acceptance Criteria, Section 6.2. Initials / IndVer. 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 [[estimated NRC review hours::4 hours]], or be below 23% power within the next [[estimated NRC review hours::4 hours]]). 7.2.9 DETERMINE, from the backup edit, if CMFLPD is less than or equal to 1.00. 7.2.10 IF CMFLPD is greater than 1.00, THEN NOTIFY the Unit SCO of the condition.
7.1.6       IF limits specified in Section 6.1 are NOT satisfied, 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.
: 1. NOTIFY the On-Shift Reactor Engineer to take action to restore thermal limits to acceptable values.
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.
NOTE:       Attachment 2 shows the location of the APRM GAFs. The APRMs are ordered: APRMs 1, 2, 3, 4.
12PT-01.11 Rev. 7 Page 7 of 141 ATTACHMENT 1 Page 1 of 1 Certification and Review Form General Comments and Recommendations Initials Name (Print) Test procedure performed by __ _ Exceptions to satisfactory performance
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.
_ Corrective action required _____________________
7.1.9       IF an APRM gain change was performed, THEN                               /
_ Test procedure has been satisfactorily completed:
OBTAIN from the process computer a copy of                             (nd.Ver.
Unit SCO: Signature Date Test procedure has NOT been satisfactorily completed:
IndVer.
Unit seo: Signature Date Test has been reviewed by: Shift Manager:
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
_ Signature Date 12PT-01.11 Rev. 7 Page 8 of 141 ATTACHMENT 2 Page 1 of 2 Limit Positions on the Core Performance Log -Long Edit BRUNSWICK-1 WK-0739 07SEP29-09.00.27 14505 MWO/MTU TRIGR=2HR REV=usep06 CORE PERFORMANCE LOG ---LONG EDIT TL 12 TLO TBPINS ALL MOC TO EOC OPTB POW DEP MCPR CTP CALCULATION
 
: HEAT BALANCE SYMMETRY : FULL CYCLE: 16 *AXIAL REL POWER* FLOW (MLB/HR) CORE PARAMTRS NUCLEAR LIMITS LOCATION NODE NOTCH REL-POW EXP(GWD/MT)
7.0 7.0    PROCEDURAL STEPS PROCEDURAL         STEPS                                                           Initials Initials NOTE:
WT 78.02(101.3%)
NOTE:        Reference 2.5 Reference    2.5 states states that NRC NRC expects   LHGR monitoring expects LHGR    monitoring (CMFLPD)
CMEO 0.3118 P-PCS 0.02 07-28-09 25 0.177 4.766 WOP 77.74 CAEO 0.1667 P-PCFC 0.02 07-28-09 24 GG 13.333 NSSFFLG 1. CADA 0.1538 8.909 39-18 23 02 0.784 18.881 WFW 12.72 CAVF 0.4773 P=O.OOO F=O.OOO 0 22 04 0.939 23.791 CMFLCPR WFWFFLG 1. CAPO 58.934 CMAPRAT", 8.867 41 82 17 -21 86 1.885 27.184 CMAPRAT <.,;yt:;u' 14bUb,;j
(CMFLPD) to  to remain the same as CPR and APLHGR for GNF fuel (i.e.,    (Le., to restore LHGR LHGR next 44 hours).
: 1. RWL 187.5460 P=O.OOO F=O.OOO 20 08 1.088 29.224 NSSCUFLG eAVEX 27956.1 MWOlfliLNSSCRFLG
hours, or be below 23% power within the next within limits within 44 hours, 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).
: 1. CDLP 18.7146 CMFDLRX. G.7S141-30-17 19 10 1.102 30.344 00 34.22 DPCC 24.0078 41-30-17 18 12 1.097 38.981 NSSCRFLG KEFF 0.9933 CMINCPR"",-
7.1.11     IF CMFLPD is greater than 1.00, IF                            1.00, THEN NOTIFY the Unit SCO of the condition.
1 17 14 LOCATION 1 2 3 4 5 6 7 8 AXIAL REL POWER 0.53 1.08 1.17 1.17 1.15 1.10 1.08 0.99 REGION REL POWER 0.94 1.06 0.96 0.85 1.13 1.08 0.90 1.06 RING REL POWER 1. 14 1. 12 1.14 1. 14 1.17 1. 03 0.65 1.078 1.035 APRM GAFS 0.99 1.00 1.000.99 APRM GAFS h**h***hh**
1.
NUCLEAR LIMITS BY REGION ***************
: 1. NOTIFY the On-Shift Reactor Engineer to take action to restore CMFLPD to an acceptable value.
B_ 0.842 0.756 0.667 0.667 789 13-36 0.868 31-36 0.909 39-36 17-38-19 0.830 27-38-20 0.817 35-38-19 13-44-04 0.723 33-38-19 0.688 35-36-19 13-44-04 0.723 33-38-19 0.688 35-36-19 -----------------
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.
--456 0.845 11-20 0.893 29-20 0.905 39-28 0.724 11-22-08 0.854 27-24-19 0.867 41-32-17 0.657 11-20-08 0.780 27-22-18 0.781 41-32-17 0.657 11-20-08 0.780 27-22-18 0.781 41-30-17
The On-Shift Reactor Engineer should be contacted to perform this section.
* MFLCPR *
7.2.1                   OPT-Ol .8D to calculate core thermal power.
* MAP RAT *
PERFORM OPT-01.8D NOTE:       OENP-24.19 should be referenced for instructions on utilizing the backup program.
* MFDLRX *
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.
* MFLPD ------------------+-------------------+------------------
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.
1 2 3 0.872 13-18 0.892 31-18 0.909 39-18 0.783 17-16-19 0.840 27-16-20 0.833 35-16-19 0.666 17-14-19 0.739 33-16-19 0.702 35-14-19 0.666 17-14-19 0.739 33-16-19 0.702 35-14-19 # NODES WI LIMITS > 1 FLCPR APRAT FDLRX FLPD o o o o ***************
2PT-01 .11
THE 10 MOST LIMITING BUNDLES *****************
/2PT-01.11                                     Rev. 77 Rev.                               Page 66 of Page     of 14/
FLCPR LOC CPR LIMIT APRAT LOC APLHGR LIMIT FDLRX LOC LPD LIMIT FLPD LOC LPD LIMIT --------------------------0.909 39-18 1.518 1.381 0.867 41-32-17 8.01 9.25 0.781 41-30-17 10.47 13.40 0.781 41-30-17 10.47 13.40 0.905 39-28 1.5251.381 0.866 43-30-17 8.09 9.35 0.78027-22-18 10.46 13.40 0.780 27-22-18 10.46 13.40 0.894 39-22 1.544 1.381 0.854 27-24-19 7.55 8.84 0.739 33-16-19 9.90 13.40 0.739 33-16-19 9.90 13.40 0.893 29-20 1.546 1.381 0.840 27-16-20 7.78 9.26 0.73743-28-17 9.88 13.40 0.737 43-28-17 9.88 13.40 0.892 31-18 1.5481.381 0.833 35-16-19 7.72 9.26 0.737 43-22-17 9.87 13.40 0.737 43-22-17 9.87 13.40 0.888 37-20 1.554 1.381 0.833 41-30-17 9.49 11.38 0.734 45-30-17 9.83 13.40 0.73445-30-17 9.83 13.40 0.883 41-20 1.563 1.381 0.825 27-22-19 9.35 11.34 0.73427-14-20 9.83 13.40 0.734 27-14-20 9.83 13.40 0.880 41-16 1.5681.381 0.818 41-28-17 7.38 9.02 0.732 39-32-17 9.81 13.40 0.732 39-32-17 9.81 13.40 0.876 35-18 1.576 1.381 0.816 27-28-19 7.13 8.73 0.72429-24-19 9.70 13.40 0.724 29-24-19 9.70 13.40 0.872 39-14 1.583 1.381 0.816 33-14-19 7.21 8.84 0.721 29-20-19 9.66 13.40 0.721 29-20-19 9.66 13.40 12PT-01.11 Rev. 7 r Page 9 Of141 CMFDLRX CMINCPR ATTACHMENT 2 Page 2 of 2 Limit Positions on the Core Performance Log -Long Edit *************
14
CONTROL ROD DATA ************* 02 06 10 14 18 22 26 30 34 38 42 46 50 51 51 47 24 47 43 43 39 14 12 14 39 35 35 31 00 10 16 10 20 31 27 00 00 27 23 10 16 10 20 23 19 19 15 14 12 14 15 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: **********
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.
CALIBRATED LPRM READINGS ***********  
: 1. NOTIFY the On-Shift Reactor Engineer to take action to restore thermal limits to acceptable values.
*LPRM FAILED SENSORS* *OTHER FAILED 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 MAN 65.1 68.4 59.7 69.9 40.1 20-21-0 MAN 37 21.7 41.0 55.3 60.2 54.7 42.6 0 29.8 52.3 52.6 56.5 55.3 54.2 C 39.0 63.2 56.9 58.6 58.6 60.9 B 36.2 70.6 54.7 51.7 58.5 69.6 A 29 17.0 39.0 56.6 61. 3 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 12PT-01.11 Rev. 7 Page 10 of 14/
7.2.6                     OPT-Ol .8C to determine if acceptance PERFORM OPT-01.8C criteria listed in Section 6.2 are satisfied.
ATTACHMENT 3 Page 1 of 3 Definitions and Abbreviations Found on Core Performance Edit 1. 2. 3. APLHGR APLHGR LIMIT APRAT Nodal Average Planar Linear Heat Generation Rate (kw/ft) Nodal limiting value of APLHGR (kw/ft) 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 kept < 2200&deg;F 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.
7.2.7     IF APRM gain adjustment is necessary, THEN PERFORM applicable section of 20P-09.
: 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 3.2.2). Maintaining this value::; 1.00 ensures that departure from nucleate boiling will not occur. 9. CMFLPD Core Maximum Fraction of Limiting Power Density. Formerly a technical specification limit, maintaining this value::; 1.00 ensures that the fuel cladding does not exceed 1 % 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 Rev. 7 Page 11 of 14/
7.2.8     IF APRM gain change was performed, THEN PERFORM                       /
: 13. 14. ATTACHMENT 3 Page 2 of 3 Definitions and Abbreviations Found on Core Performance Edit FLCPR FLPD Maximum Fraction of Limiting CPR = Maximum of CPR LIMIT CPR Fraction of Limiting Power Density (kw/ft) = LHGR = LPD LHGR Limit LPD Limit 15. LHGR Power generation in 1 foot of a 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 = 1: indicates that 8020 is valid. NSSCRFLG = 2 indicates that 8020 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. /2PT-01.11 NSSCUFLG = 1: indicates that WCU1, WCU3, 8047, and 8048 are valid. NSSCUFLG = 2: indicates that WCU1, WCU3, 8047, 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. Rev. 7 Page 12 of 14/
OPT-Ol .8C to ensure APRM gain adjustment another OPT-01.8C                                                  Ind.Ver.
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 wrCF Calculated Total Core Flow representing the summation of the 20 single tap jet pumps. The comparison of wrCF with WOP is :s; 5%. NSSFFLG = 2: indicates WOP Core Plate Differential Core Flow, which is flow resulting from the Core DP and Reactor Power to wrCF correlation.
IndVer.
NSSFFLG = 3: indicates a manually inserted value for wrCF NSSFFLG = 4: indicates wrCF but the comparison with WDP 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.  
factor satisfies the requirements of Acceptance Criteria, Section 6.2.
\2PT-01.11 WFWFFLG = 1: indicates smoothed feedwater flow from U2NSSWFWA and U2NSSWFWB is used in U2CP AFWA and U2CP _AFWB respectively.
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 hours, or be below 23% power within the next 4 hours).
This condition is expected during steady state operation.
7.2.9     DETERMINE, from the backup edit, if CMFLPD is less 1 .00.
WFWFFLG = 2: indicates instantaneous feedwater flow from U2C32B022 and U2C32B023 is used in U2CP AFWA and U2CP _AFWB respectively.
than or equal to 1.00.
This condition can be expected following a large change in reactor power. Rev. 7 Page 13 of 141 REVISION  
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.
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&deg; 2200&deg;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==
==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.
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 was added for CMFDLRX. "Shift Superintendent" has been changed to "Shift Manager".
Acceptance Criteria 6.1.3 6.1 .3 was added for CMFDLRX. "Shift Shift Superintendent" Superintendent has been Shift Manager".
Revision 6 incorporates Child EC 69315 (Master EC 67951) for installation of Powerplex III. Revision 5 incorporates EC 62831 to provide new Attachment 4 for removal of overly conservative PPC thermal limits under certain operating conditions.
changed to "Shift   Manager.
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 Limitation 3.5 previously contained in Step 7.1.3.2, and steps referencing Attachment
Revision 6 incorporates Child EC 69315 (Master EC 67951) for installation of Powerplex Ill.
: 4. 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 Reactor Engineer or PPX software to be used to obtain >LI>BU edits. Revision 1 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.
III.
Revision 0 was issued in accordance with ESR 00-00442, Unit 1 Power Range Neutron Monitoring Replacement, which required the OPT-01.11 be separated into unit specific procedures.
Revision 5 incorporates EC 62831 to provide new Attachment 4 for removal of overly conservative PPC thermal limits under certain operating conditions.
12PT-01.11 Rev. 7 Page 14 of 141 LESSON TITLE: LESSON NUMBER: REVISION NO: PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C002 (RO) Determination of Drywell Volumetric Average Temperature LOT-OJT-JP-002-A01 01 Determination of Drywell Volumetric Average Temperature SAFETY CONSIDERATIONS:
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.
None EVALUATOR NOTES: (Do not read to performer)
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.
: 1. This JPM is performed in the classroom or simulator for Unit Two. 2. If performed in the Simulator:
Revision 2 adds a method to account for PPX CPR convergence failures and allows the
: a. Ensure all simulator computer screens are OFF prior to commencing JPM. b. Reset the simulator to IC-11. c. Input override values to the following points to obtain the associated readings on TR-4426-1A11 B/2A12B
                                                            >Ll>BU edits.
* Div 2A (Channel 3) -5823 40.0
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.
* Div 2A (Channel 4) -5824 185.5
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.
* Div 1A (Channel 4) -5822 185.5
2PT-01.11 12PT-01.11                                 Rev.77 Rev.                                    l4of Page 14    14 of 141
* Div 2B (Channel 1) -5802 174.1
 
* Div 1 B (Channel 2) -5803 168.3
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN NRC ADMIN C002 (RO)
* Div 2B (Channel 2) -5804 162.7
LESSON TITLE:  Determination of Drywell Volumetric Average Temperature LESSON NUMBER: LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AO1 REVISION NO:  01
* Div 1 B (Channel 3) -5805 139.3
 
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 2B (Channel 3) -5806 136.8
* Div 1 B (Channel 4) -5807 133.5
* Div 1lBB (Channel 4) -5807 133.5
* Div 2B (Channel 4) -5808 40.0
* Div 2B (Channel 4) -5808 40.0
* Div 1 B (Channel 5) -5809 124.5
              ** Div 1lBB (Channel 5) -5809 124.5
* Div 1A (Channel 3) -5812 121.6
* Div 1AiA (Channel 3) -5812 121.6
* Div 2B (Channel 6) -5813 119.2
* Div 2B (Channel 6) -5813 119.2
* Div 1A (Channel 5) -5817 88.7
            ** Div 1A IA (Channel 5) -5817     88.7
* Div 1A (Channel 6) -5818 40.0
            ** Div 1A IA (Channel 6) -5818     40.0
* Div 2A (Channel 5) -5819 88.7
            ** 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.
* 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.
: 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. 6. The trainee will be given a copy of OPT-16.2.
: 5. The trainee will need a calculator to perform this JPM.
: 7. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step. LOT-OJT-JP-002-A01 Page 2 REV. 01 Determination of Drywell Volumetric Average Temperature Read the following to the JPM performer.
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:
TASK CONDITIONS:
: 1. Today is the 15 th of the month. 2. Drywell air RTDs CAC-TE-1258-8, CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable.
th 15 th
: 3. An LCO has been established that requires the performance of OPT-16.2, Drywell Volumetric Average Temperature, once per [[estimated NRC review hours::24 hours]]. 4. The CAC-TY-4426-1 and 2 Microprocessors are not available for use. 5. The Process Computer and ERFIS are not available.
: 1. Today is the 15 of the month.
: 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 UNSAT LOT-OJT-JP-002-A01 Page 3 REV. 01 Determination of Drywell Volumetric Average Temperature PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
1.
Step 1 -Obtain current revision of OPT-16.2 and verify if applicable.
: 2. Drywell air RTDs CAC-TE-1258-8, CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable.
Current revision of OPT-16.2 obtained and verified as required.
: 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 hours.
TIME START ____ _ NOTE: Figure 1 may be used as a worksheet but is NOT required to be retained.
CAC-TY-4426-i and 2 Microprocessors are not available for use.
NOTE: All temperatures should be rounded off to the nearest tenth of a degree. NOTE: Inoperable channels indicate downscale (40.00). PROMPT: If being performed in a classroom, provide Recorder Attachment to candidate.
: 4. The CAC-TY-4426-1
Step 2 -Obtain drywell temperature readings for the locations listed in step 7.2.1 Records the following readings:
: 5. The Process Computer and ERFIS are not available.
4426-2A Channel 3 -INOP 4426-2A Channel 4 -185.5 (:to. 1) 4426-1 A Channel 4 -185.5 (:to. 1) Step 3 -Add step 7.2.1 recorded temperatures and record in step 7.2.2 SATIUNSAT*
: 6. You have been given permission by the Unit CRS to perform this test.
185.5 (:to. 1) and 185.5 (:to. 1) added totaling 371.0 (:to.2) and documented in step 7.2.2 **CRITICAL STEP** SAT/UNSAT*
: 7. The Unit CRS will record required cover page information INITIATING CUE:
Step 4 -Divide total obtained in step 7.2.2 by the number of temperatures used 371.0 (:to.2) divided by 2 equaling 185.5 (:to. 1) and documented in step 7.2.3 **CRITICAL STEP** SAT/UNSAT*
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.
Step 5 -Obtain drywell temperature readings for the locations listed in step 7.3.1 Records the following readings:
DRYWELL VOLUMETRIC AVERAGE TEMPERATURE                                 SAT OF
4426-28 Channel 1 -174.1 (:to. 1) 4426-18 Channel 2 -168.3 (:to. 1) LOT-OJT-JP-002-A01 Page 4 SAT/UNSAT*
                                          &deg;F UNSAT LOT-OJT-JP-002-A01 LOT-OJT-JP-002-AOI                              Page 3                             REV. 01
REV. 01 Determination of Drywell Volumetric Average Temperature Step 6 -Add step 7.3.1 recorded temperatures and record in step 7.3.2 174.1 (:!:.0.1) and 168.3 (:!:.0.1) added totaling 342.4 (:!:.0.2) and documented in step 7.3.2 **CRITICAL STEP** SAT/UNSAT*
 
Step 7 -Divide total obtained in step 7.3.2 by the number of temperatures used 342.4 (:!:.0.2) divided by 2 equaling 171.2 (:!:.0.1) and documented in step 7.3.3 **CRITICAL STEP** SAT/UNSAT*
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.
Step 8 -Obtain drywell temperature readings for the locations listed in step 7.4.1 Records the following readings:
Comments.
4426-18 Channel 3 -139.3 (:!:.O. 1) 4426-28 Channel 3 -136.8 (:!:.O. 1) 4426-18 Channel 4 -133.S (:!:.0.1) 4426-28 Channel 4 -INOP Step 9 -Add step 7.4.1 recorded temperatures and record in step 7.4.2 SAT/UNSAT*
Step 11 - Obtain current revision of OPT-16.2 and verify if applicable.
139.3 (:!:.0.1), 136.8 (:!:.0.1) and 133.S (:!:.0.1) added totaling 409.6 (:!:.0.3) and documented in step 7.4.2 **CRITICAL STEP** SA TlUNSAT* Step 10-Divide total obtained in step 7.4.2 by the number of temperatures used 409.6 (:!:.0.3) divided by 3 equaling 136.S (:!:.0.1) and documented in step 7.4.3 **CRITICAL STEP** SATIUNSAT*
OPT-16.2 Current revision of OPT-I      6.2 obtained and verified as required.
Step 11 -Obtain drywell temperature readings for the locations listed in step 7.5.1 Records the following readings:
TIME START TIME  START _ _ _ __
4426-18 ChannelS -124.S (:!:.0.1) 4426-1A Channel 3 -121.6 (:!:.0.1) 4426-28 Channel 6 -119.2 (:!:.0.1)
NOTE: Figure 11 may be used as aa worksheet but is NOT required to be retained.
LOT -OJT -JP-002-A01 Page 5 SAT/UNSAT*
NOTE: All temperatures should be rounded off to the nearest tenth of aa degree.
REV. 01 Determination of Drywell Volumetric Average Temperature Step 12 -Add step 7.5.1 recorded temperatures and record in step 7.5.2 124.5 121.6 and 119.2 added totaling 365.3 and documented in step 7.5.2 **CRITICAL STEP** SAT/UNSAT*
NOTE: Inoperable channels indicate downscale (40.00).
Step 13 -Divide total obtained in step 7.5.2 by the number of temperatures used 365.3 divided by 3 equaling 121.8 and documented in step 7.5.3 **CRITICAL STEP** SAT/UNSAT*
PROMPT: If being performed in a classroom, provide Recorder Attachment to candidate.
Step 14 -Obtain drywell temperature readings for the locations listed in step 7.6.1 Records the following readings:
Step 2 - Obtain drywell temperature readings for the locations listed in step 7.2.1 Records the following readings:
4426-1 A Channel 5 -88. 7
4426-2A Channel 3    3 - INOP 4426-2A Channel 4    4 - 185.5 (:to. 1)
: 1) 4426-1A Channel 6 -INOP 4426-2A Channel 5 -88. 7
(+/-0.1) 4426-1 4426-IA A Channel Channel4  4 - 185.5 (:to. 1)
: 1) 4426-2A Channel 6 -88.7 (:!:.O. 1) Step 15 -Add step 7.6.1 recorded temperatures and record in step 7.6.2 SAT/UNSAT*
(+/-0.1)
: 88. 7
SATIUNSAT*
: 88. 7 and 88. 7 added totaling 266.1 and documented in step 7.6.2 **CRITICAL STEP** SAT/UNSAT*
SATIUNSAT*
Step 16 -Divide total obtained in step 7.6.2 by the number of temperatures used 266.1 (:!:.O.3) divided by 3 equaling 88. 7 and documented in step 7.6.3 **CRITICAL STEP** SAT/UNSAT*
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.
Step 17 -Transfer average readings documented in steps 7.2.3,7.3.3,7.4.3,7.5.3 and 7.6.3 into step 7.7.1 185.5 (:!:.O.1), 171.2 136.5 121.8 and 88. 7 transferred into step 7. 7. 1 SAT/UNSAT*
(+/-0.1)                (+/-0.1)                            (+/-0.2) and documented in step
LOT-OJT-JP-002-A01 Page 6 REV. 01 Determination of Drywell Volumetric Average Temperature Step 18 -Multiply each reading in 7.7.1 by the designated factor and document in step 7.7.1 9.3 (:!:.0.1), 15.4 (:!:.0.1), 54.6 (:!:.0.1), 46.3 (:!:.0.1), and 7.1 (:!:.0.1) documented in step 7.7.1 **CRITICAL STEP** SAT/UNSAT*
: 1) added totaling 371.0 (:to.2) 7.2.2
Step 19 -Add weighted averages in step 7.7.1 and document as TOTAL in step 7.7.1.6 9.3 (:!:.0.1), 15.2 (:!:.0.1), 54.6 (:!:.0.1), 46.3 (:!:.0.1), and 7.1 (:!:.0.1) added totaling 132.7 (:!:.0.5) and documented in step 7. 7. 1 **CRITICAL STEP** SAT/UNSAT*
                                                                          **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 (&#xf7;0.1)
(:!:.0.1) and 168.3 (:!:.0.1) 174.1 (&#xf7;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.
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 due to unavailability 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 (not required)
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*
NOTE: Cover page information will be filled out by the Unit CRS. Step 22 -Perform step 7.7.5 Cover page information verified complete SAT/UNSAT*
SAT/UNSAT*
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*
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 Avg Air Temp 132.7 (:!:.0.5) is less than 150&deg;F (acceptance criteria)  
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)
**CRITICAL STEP** SAT/UNSAT*
(+/-0.5) is less than     150&deg;F   (acceptance     criteria)
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 SATIUNSAT TERMINATING CUE: When CRS is informed of test results, this JPM can be terminated.
STEP**
TIME COMPLETED
                                                                                **CRITICAL STEP**
____ _ NOTE: Comments required for any step evaluated as UNSA T. LOT-OJT-JP-002-A01 Page 8 REV. 01 Determination of Drywell Volumetric Average Temperature RELATED TASKS: 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  
                                                                                **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:==
==REFERENCES:==


OPT-16.2, Drywell Volumetric Average Temperature TOOLS AND EQUIPMENT:
OPT-16.2, Drywell Volumetric Average Temperature TOOLS AND EQUIPMENT:
Calculator Simulator or This JPMs Recorder Attachment ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2. Supplement 1): Admin -Conduct of Operations REASON FOR REVISION:
Calculator JPM5 Recorder Attachment Simulator or This JPMs ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev 2. Supplement 1):
Changed to allow classroom performance for HLC2010-1 NRC License Exam. LOT-OJT-JP-002-A01 Page 9 REV. 01 Determination of Drywell Volumetric Average Temperature Validation Time: Minutes (approximate)
Admin - Conduct of Operations REASON FOR REVISION:
Time Taken: ____ _ APPLICABLE METHOD OF TESTING Performance:
HLC2O1O-1 NRC License Exam.
Simulate Setting: In-Plant Time Critical:
Changed to allow classroom performance for HLC2010-1 LOT-OJT-JP-002-A01                           Page 9                             REV. 01
Yes Alternate Path: Yes Actual Simulator No X No X EVALUATION Unit: 2 Admin X Time Limit N/A Performer:
 
_______________________
Determination of Determination     of Drywell Drywell Volumetric Volumetric Average Average Temperature Temperature Validation Time:
_ JPM: Pass __ Fail --Remedial Training Required:
Validation  Time: ~20    Minutes (approximate)
Yes No __ (Reference TAP-411 for evaluation guidance)
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:
Comments reviewed with Performer Evaluator Signature:
Comments reviewed with Performer Evaluator Evaluator Signature:
____________
Signature: _ _ _ _ _ _ _ _ _ _ _ __                  Date:___________
_ Date: -----LOT-OJT-JP-002-A01 Page 10 REV. 01
Date: -----
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TASK CONDITIONS:
TASK CONDITIONS:
: 1. Today is the 15 th of the month. 2. Drywell air RTDs CAC-TE-1258-8, CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable.
th 15 th
: 3. An LCO has been established that requires the performance of OPT-16.2, Drywell Volumetric Average Temperature, once per [[estimated NRC review hours::24 hours]]. 4. The CAC-TY-4426-1 and 2 Microprocessors are not available for use. 5. The Process Computer and ERFIS are not available.
: 1. Today is the 15 of the month.
: 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 UNSAT Progress Energy BRUNSWICK NUCLEAR PLANT DATE COMPLETED
1.
_________
: 2. Drywell air RTDs CAC-TE-1258-8,
_ FREQUENCY:
: 2.                      CAC-TE-1258-8, CACTE-1258-18 CAC-TE-1258-18 and CAC-TE-1258-23 are inoperable.
c Continuous Use UNIT __ % PWR, ____ GMWE ___ _ SUPERVISOR, ___________
: 3. An LCO has been established that requires the performance of OPT-16.2, Drywell Volumetric Average Temperature, once per 24 hours.
_ REASON FOR TEST (check one or more): _ Routine sUNeillance Once every [[estimated NRC review hours::24 hours]] when at least one SPTMS air RTD is inoperable in each division of SPTMS and the unit is in Mode 1, 2, or 3. _WO# ____________
Microprocessors are not available for use.
_ _ Other (explain)
: 4. The CAC-TY-4426-1 and 22 Microprocessors
_________
: 5. The Process Computer and ERFIS are not available.
_ PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT o OPT-16.2 DRYWELL VOLUMETRIC AVERAGE TEMPERATURE REVISION 35 IOPT-16.2 Rev. 35 Page 1 of 12 )
: 6. You have been given permission by the Unit CRS to perform this test.
1.0 PURPOSE 2.0 1.1 This test is performed to determine the operability of the drywell in conformance with the requirements specified in Technical Specification SR 3.6.1.4.1.
: 7. The Unit CRS will record required cover page information INITIATING CUE:
1.2 2.1 2.2 2.3 2.4 2.5 2.6 This test involves averaging air temperatures within the drywell. REFERENCES Technical Specifications FSAR, Section 6.2 System Description SD-24, Containment Atmosphere Control System EER 93-578 (SPTMS Air RTD Divisions/Channels Defined) 2SP-95-208, Temperature Measurement for SPTMS RTD ESR 98-00387, Rev. 0, TS Change to ContainmentlDrywell Air Temperature Requirements 3.0 PREREQUISITES None Applicable 4.0 PRECAUTIONS AND LIMITATIONS None Applicable 5.0 SPECIAL TOOLS AND EQUIPMENT Calculator 6.0 ACCEPTANCE CRITERIA This test may be considered satisfactory when the drywell volumetric average temperature is less than or equal to 150&deg;F. IOPT-16.2 Rev. 35 Page 2 of 12 )
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.
7.0 PROCEDURAL STEPS Initials 7.1 NOTE: NOTE: NOTE: NOTE: IOPT-16.2 OBTAIN permission from Unit CRS to perform this test. Figure 1 may be used as a worksheet but is NOT required to be retained with th is PT. All temperatures used in this procedure should be rounded off to the nearest tenth of a degree. Primary containment temperatures may be obtained from the CAC-TY -4426-1 (2) microprocessor per OP-24, Operator Interface With The SPTMS Microprocessors, from the recorders in the Control Room, from ERFIS display screens 740 and 745 of the Validation Menu; or as a backup method, the designated process computer points may be used. Microprocessor point values may also be obtained by I&C manually taking temperature measurements of SPTMS RTDs. Technical Specifications requires at least one operable temperature detector in each channel for each location.
DRYWELL VOLUMETRIC AVERAGE TEMPERATURE                                     SAT OF
Rev. 35 Page 3 of 12) 7.0 PROCEDURAL STEPS 7.2 90' Elevation And Above 7.2.1 OBTAIN drywell temperature for the locations listed below AND RECORD in the spaces provided.
                                        &deg;F UNSAT
Recorder/ERFIS Display 4426-2A Channel 3 __ _ 4426-2A Channel 4 __ _ 4426-1A Channel 4 __ _ SPTMS (5823) __ (5824) __ (5822) __ CHAN II II I N/A N/A N/A 7.2.2 ADD the recorded temperatures AND RECORD the total in the following space: __________
 
-Recorder/ERFIS display total __________
BRUNSWICK NUCLEAR BRUNSWICK       NUCLEAR PLANT PLANT Cc Energy Progress Energy                                                                              Continuous Continuous Use Use DATE COMPLETED DATE COMPLETED _ _ _ _ _ _ _ _ __                      FREQUENCY:
-SPTMS total 7.2.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 90' elevation and above in the following space: = total no. of temperatures average Initials I OPT-16.2 Rev. 35 Page 4 of 12 )
FREQUENCY:
7.0 PROCEDURAL STEPS 7.3 Between 70' And 80' Elevation 7.3.1 OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.
UNIT _
Recorder/ERFIS Display SPTMS CHAN PPC Unit 1 Only 4426-2B Channel 1 (5802) II W109 4426-1 B Channel 2 (5803) I F148 4426-2B Channel 2 (5804) II W110 Unit 2 Only 4426-2B Channel 1 (5802) II W109 4426-1 B Channel 2 (5803) I F148 NOTE: Notify BESS duty manager if any temperatures between 70' and 80' elevation exceed 240&deg;F. 7.3.2 ADD the recorded temperatures AND RECORD the total in the following spaces: _________  
UNIT____ _ %PWR_______
-Recorder/ERFIS display total ________ -SPTMS total _________
              % PWR,_ _ _ _ GMWE_______
-PPC total 7.3.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 70' -80' elevation in the following space: = total no. of temperatures average Initials / IOPT-16.2 Rev. 35 Page 5 of 121 7.0 PROCEDURAL STEPS 7.4 Between 28' And 45' Elevation 7.4.1 OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.
GMWE_ _ __
Recorder/ERFIS Display SPTMS CHAN PPC 4426-1 B Channel 3 (5805) I F149 4426-2B Channel 3 (5806) II W085 4426-1 B Channel 4 (5807) I F150 4426-2B Channel 4 (5808) II W086 7.4.2 ADD the recorded temperatures AND RECORD the total in the following spaces: ________ -Recorder/ERFIS display total ________ -SPTMS total ________ -PPC total 7.4.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 28' -45' elevation in the following space: = total no. of temperatures average 7.5 Between 10' And 23' Elevation 7.5.1 OBTAIN drywell temperatures for the locations listed below AND RECORD in the spaces provided.
SUPERVISOR,   _    _  _  _  _  _  _ _ _ _ __          Once every Once   every 24   hours when at 24 hours            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):
Recorder/ERFIS Display SPTMS CHAN PPC Initials 4426-1 B Channel 5 __ _ (5809) __ (5812) __ (5813) __ F151 ____ _ 4426-1A Channel 3 __ _ W105 ____ _ 4426-2B Channel 6 __ _ II W088 ____ _ IOPT-16.2 Rev. 35 Page 6 of 12/
more):              and  the unit and the unit is in Mode is in      1, 2, Mode 1,  2, or or 3.
7.0 PROCEDURAL STEPS 7.5.2 ADD the recorded temperatures AND RECORD the total in the following spaces: _________
3.
-Recorder/ERFIS display total ________ -SPTMS total _________
_            sUNeillance Routine surveillance
-PPC total 7.5.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the 10' -23' elevation in the following space: = total no. of temperatures average 7.6 Below 5' Elevation 7.6.1 OBTAIN primary containment temperatures for the locations listed below AND RECORD in the spaces provided.
_WO#       _ _ _ _ _ _ _ _ _ _ _ __
Recorder/ERFIS Display PPC Initials 4426-1A Channel 5 __ _ SPTMS (5817) __ (5818) __ (5819) __ (5820) __ CHAN I W106 ____ _ 4426-1A Channel 6 __ _ W107 ____ _ 4426-2A Channel 5 __ _ II II W115 ____ _ 4426-2A Channel 6 __ _ 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.
WO #__________________________
7.6.2 ADD the recorded temperatures AND RECORD the total in the following spaces: IOPT-16.2
_   Other (explain) _ _ _ _ _ _ _ _ __
_________
Other (explain)_________________________________
-Recorder/ERFIS display total _________
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 )
-SPTMS total _________
of 12
-PPC total Rev. 35 Page 7 of 12 )
 
7.0 PROCEDURAL STEPS Initials NOTE: 7.7 7.6.3 DIVIDE the total by the number of temperatures used to obtain the average temperature for the below 5' elevation in the following space: = total no. of temperatures average The total in Step 7.7.1.6 is the volumetric average temperature for the drywell. If this temperature is greater than 150&deg;F, actions should be taken as required by Technical Specification SR 3.6.1.4.1.
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.
Volumetric Average 7.7.1 1. DETERMINE the volumetric average temperature by performing the following calculations:
SR 3.6.1.4.1.
Average above 90' elevation x 0.05 = ___ _ Step 7.2.3 2. Average 70' -80' elevation x 0.09 = ___ _ Step 7.3.3 3. Average 28' -45' elevation x 0.40 = ___ _ Step 7.4.3 4. Average 10' -23' elevation x 0.38 = ___ _ Step 7.5.3 5. Average below 5' elevation x 0.08 = ___ _ Step 7.6.3 6. Total ____________
11.2
_ Steps 7.7.1.1 through 7.7.1.5 IOPT-16.2 Rev. 35 Page 8 of 121 7.0 PROCEDURAL STEPS Initials NOTE: NOTE: Computer point C074 may only be used to satisfy EOP concerns and may NOT be used to satisfy Technical Specifications.
      .2   This test involves averaging   air temperatures within the drywell.
7.7.2 RECORD computer point C074 value (for information).
averaging air                            drywell.
C074 ____ _ Performance of Steps 7.7.3 and 7.7.4 is only required once a 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 Step 7.7.3 is greater than 10&deg;F, THEN ENSURE that 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.
==2.0      REFERENCES==
IOPT-16.2 Rev. 35 Page 9 of 121 ATTACHMENT 1 Page 1 of 1 Certification and Review Form General Comments and Recommendations  
 
-------------------------------
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)
Initials Name (Print) Performed by: Exceptions to satisfactory performance
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&deg;F.
_______________________________
equal to 150&deg;F.
_ Corrective action required _____________________________
IOPT-16.2 OPT-i 6.2                                  Rev. 35 Rev. 35                              Page 22 of Page      12 )
_ Test procedure has been satisfactorily completed:
of 12
Unit CRS/SRO: ____________
 
_ Signature Date Test procedure has NOT been satisfactorily completed:
7.0     PROCEDURAL STEPS                                                         Initials 7.1     OBTAIN permission from Unit CRS to perform this test.
Unit CRS/SRO: ____________
NOTE:      Figure 11 may be used as aa worksheet but is NOT required to be retained th is PT.
_ Signature Date Test has been reviewed by: Shift Manager: Signature Date IOPT-16.2 Rev. 35 Page 10 of 121 TIME 4426-2A (Channel 3)-5823 4426-2A (Channel 4)-5824 4426-1A (Channel 4)-5822 Unit 1 only 4426-2B (Channel 1 )-5802 4426-1 B (Channel 2)-5803 4426-2B (Channel 2)-5804 Unit 2 only 4426-2B (Channel 1 )-5802 4426-1 B (Channel 2)-5803 4426-1 B (Channel 3)-5805 4426-2B (Channel 3)-5806 4426-1 B (Channel 4)-5807 4426-2B (Channel 4)-5808 4426-1 B (Channel 5)-5809 4426-1A (Channel 3)-5812 4426-2B (Channel 6)-5813 4426-1A (Channel 5)-5817 4426-1A (Channel 6)-5818 4426-2A (Channel 5)-5819 4426-2A (Channel 6)-5820 AVERAGE TEMPERATURE FIGURE 1 Page 1 of 1 Containment Temperature Worksheet
with this NOTE:      All temperatures used in this procedure should be rounded off to the nearest tenth of aa degree.
___ 0.05 ___ 0.09 ___ 0.09 ___ 0040 ___ 0.38 ___ 0.08 I OPT-16.2 Rev. 35 REVISION  
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&deg;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&deg;F, actions should be taken as drywell. If this temperature is greater than 150&deg;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&deg;F, THEN ENSURE that Step 7.7.3 is greater than 10&deg;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:
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==
==SUMMARY==
Revision 35 incorporates temporary change EC 75096 which temporarily disables temperature indication 2CAC-TE-1258-4 (4426-2B [channel 2]-5804).
 
This revision also updated operations titles Shift Superintendent to Shift Manager and SCQ to CRS or CRS/SRQ as applicable.
REVISION   
Revision 34 restores 2CAC-TE-1258-20 (4426-2A [channel 6]-5820) that was temporarily removed lAW EC 63061. Revision 33 incorporates temporary change EC 63061 which temporarily disables temperature indication 2CAC-TE-1258-20 (4426-2A [channel 6]-5820).
 
Revision 32-Removes the Unit Specific items and associated notes that were added per Temporary Plant Modification ESR 99-00485.
==SUMMARY==
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 to channel 1, 2, 3, 4, 5, & 6. IOPT-16.2 Rev. 35 Page 12 of 121}}
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}}

Latest revision as of 17:02, 21 March 2020

Initial Exam 2010-301 Final Administrative JPMs
ML101590195
Person / Time
Site: Brunswick  Duke Energy icon.png
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


Text

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period SATIU NSAT*

SAT/UNSAT*

NOTE: Candidate may propose allowing SDC removal from service for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of no reactor coolant circulation and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of no reactor coolant circulation and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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:

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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:

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.

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:

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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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.

    • 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be below 23%

power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). 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.

    • 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 **

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

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

  1. 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

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />).

hours, or be below 23% power within the next within limits within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />, 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be below 23% power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />).

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.

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

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

                          • 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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*

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 ~

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

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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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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:

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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