ML113640128: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:NRC ADM. A
{{#Wiki_filter:REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING AND MAKEUP FLOW FOR BOILOFF A-1 NOTE TO EXAMINER: Do not handout Attachment 6, Minimum Flow to Makeup for Boil-off (1-AOP-01.08, RCS Leakage Abnormal Operations) until Applicant requests attachment.
-1 Rev. 1  REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM
 
DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING AND MAKEUP FLOW FOR BOILOFF A-1 NOTE TO EXAMINER:
Do not handout Attachment 6, Minimum Flow to Makeup for Boil-off (1-AOP-01.08, 'RCS Leakage Abnormal Operations') until Applicant requests attachment.      
 
Applicant ____________________________
Applicant ____________________________
Examiner____________________________
Examiner____________________________
NRC ADMINISTRATIVE JPM A
NRC ADM. A-1 Rev. 1
-1 Rev. 1 PAGE 2  REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING AND MAKEUP FLOW FOR BOILOFF KA Statement:
 
2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING AND MAKEUP FLOW FOR BOILOFF KA Statement: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
KA #: 3.9 / 4.2
KA #:         3.9 / 4.2


==References:==
==References:==
1-AOP-03.02. Shutdown Cooling Abnormal Operations 1-AOP-01.08, RCS Leakage Abnormal Operations Attachment 6, Minimum Flow to Makeup for Boil-off.
Validation Time: _____15 minutes______
Start Time: _____________              Finish Time: ______________
Performance Rating:        Sat                  Unsat Comments NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 2


1-AOP-03.02. 'Shutdown Cooling Abnormal Operations
NRC ADM JPM A-1 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING Directions to the candidate for Administrative JPMS:
'
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.
1-AOP-01.0 8 , 'RCS Leakage Abnormal Operations' Attachment 6, Minimum Flow to Makeup for Boil
Initial Conditions Unit 1 is in a Refueling outage. Core shuffle or reload has NOT been completed.
-off.                                                                                                       
 
Validation Time:
_____15 minutes______
Start Time:
_____________        Finish Time:
______________
Performance Rating:    Sat 
 
Unsat Comments NRC ADM JPM A
-1  NRC  ADMINISTRATIVE JPM A
-1 Rev. 1 PAGE 3 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING Directions to the candidate for Administrative JPMS:
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you. Initial Conditions Unit 1 is in a Refueling outage. Core shuffle or reload has NOT been completed.
A loss of shutdown cooling occurs.
A loss of shutdown cooling occurs.
Initiating Cue The US has directed you to determine the time to core boiling and time boiling will occur using 1
Initiating Cue The US has directed you to determine the time to core boiling and time boiling will occur using 1-AOP-03.02, Shutdown Cooling Abnormal Operations, ATTACHMENT 1, Estimated Time to Core Boiling AND determine flow to makeup for boil - off.
-AOP-03.02, Shutdown Cooling Abnormal Operations, ATTACHMENT 1, 'Estimated Time to Core Boiling
Given:
AND determine flow to makeup for boil  
* RCS temperature is 114°F
- off.
* RCS level is 31 feet
Given:   RCS temperature is 11 4°F RCS level is 3 1 feet The Unit was tripped on Oct. 18, at 00 15  Loss of Shutdown Cooling occurred at: Oct 2 2, 01 15  Current date / time is Oct. 2 2, 01 20 
* The Unit was tripped on Oct. 18, at 0015
 
* Loss of Shutdown Cooling occurred at: Oct 22, 0115
NRC ADM JPM A
* Current date / time is Oct. 22, 0120 NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 3
-1  NRC ADMINISTRATIVE JPM A
-1 Rev. 1 PAGE 4 START TIME: __________
1-AOP-03.02, 'Shutdown Cooling Abnormal Operations' ATTACHMENT 1  STEP 1 (4.2.2):    ATTACHMENT 1 step 1A Record the following information Time SDC was lost
 
STANDARD: Records 0115    EXAMINER'S CUE:
NONE  COMMENTS:      _____ SAT 
 
_____ UNSAT STEP 2 (4.2.2):  ATTACHMENT 1 step 1A Record the following information RCS Temperature STANDARD: Records 11 4ºF  EXAMINER'S CUE:
NONE  COMMENTS:      _____ SAT 
 
_____ UNSAT STEP 3 :        ATTACHMENT 1 step 1A


Record the following information Vessel / Cavity Level  
NRC ADM JPM A-1 START TIME: __________
1-AOP-03.02, Shutdown Cooling Abnormal Operations ATTACHMENT 1
_____ SAT STEP 1 (4.2.2):  ATTACHMENT 1 step 1A Record the following information                                 _____ UNSAT
* Time SDC was lost STANDARD:      Records 0115 EXAMINERS CUE:          NONE COMMENTS:
STEP 2 (4.2.2): ATTACHMENT 1 step 1A Record the following information                                    _____ SAT
* RCS Temperature STANDARD:      Records 114ºF                                                        _____ UNSAT EXAMINERS CUE:          NONE COMMENTS:
STEP 3 :    ATTACHMENT 1 step 1A Record the following information                                          _____ SAT Vessel / Cavity Level
_____ UNSAT STANDARD:      Records 31 ft.
EXAMINERS CUE:          NONE COMMENTS:
NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 4


STANDARD: Records 31 ft. EXAMINER'S CUE:
NRC ADM JPM A-1 STEP 4:      ATTACHMENT 1 step 1A Record the following information                                              _____ SAT Time since shutdown (hours)
NONE COMMENTS:
_____ UNSAT STANDARD:     Records 97 hours EXAMINERS CUE:          NONE COMMENTS:
STEP 5:      ATTACHMENT 1 step 1B                                                        CRITICAL STEP Record time to boil at mid-loop per Table 1 STANDARD:    13.8 minutes                                                                _____ SAT EXAMINERS CUE:         NONE EXAMINERS NOTE                                                                    _____ UNSAT
* Temperature between columns, select higher temperature
* Time since shutdown between rows, select the lesser time COMMENTS:
STEP 6:      ATTACHMENT 1 step 1C                                                        CRITICAL STEP 3
Record additional time to boil for a 100ft volume per Table 2 3
STANDARD:    0.958 (minutes / 100ft )                                                    _____ SAT EXAMINERS CUE:          NONE EXAMINERS NOTE                                                                    _____ UNSAT
* Temperature between columns, select higher temperature
* Time since shutdown between rows, select the lesser time COMMENTS:
NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 5


_____ SAT
NRC ADM JPM A-1 STEP 7:        ATTACHMENT 1 step 1D                                                      CRITICAL STEP 3
Record additional 100ft volumes above mid-loop per Table 3 3
_____ SAT STANDARD:      1.21 (100 ft )
EXAMINERS CUE:        NONE                                                    _____ UNSAT COMMENTS:
STEP 8 (1E):  ATTACHMENT 1 step 1E                                                      CRITICAL STEP Calculate Time to Boil as Follows:
(__13.8__) +    [(_0.958_)    x    (__1.21__)]    = 14.96 min Time to boil    Additional          Additional      Time to Boil                        _____ SAT 3
Time to boil        100 ft volumes Step 1.B          Step 1.C          Step 1.D
_____ UNSAT STANDARD:      Time to Boil 14.96 minutes (14- 16 minutes is acceptable)
EXAMINERS CUE:        NONE COMMENTS:
NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 6


_____ UNSAT
NRC ADM JPM A-1 STEP 9:        ATTACHMENT 1 step 2                                                          CRITICAL STEP IF core shuffle or reload has NOT been completed, THEN CALCULATE time boiling will occur as follows:
(__0115__) +    (_14.96_) = (0129.96)                                                    _____ SAT Time SDC lost    Time to boil Time boiling will occur Step 1.A        Step 1.E
_____ UNSAT STANDARD:      Time 0129 to 0131 is acceptable EXAMINERS CUE:        NONE COMMENTS:
CRITICAL 1-AOP-01.08, RCS Leakage Abnormal Operations                          STEP Attachment 6 STEP 10:      Attachment 6 Flow to Makeup for Boil - Off                                    _____ SAT STANDARD:      Using Attachment 6 (or Figure 2 from one of the below procedures)            _____ UNSAT determines 4 days shutdown, makeup for boil off is 70 gallons per minute (+/-
2 gpm).
EXAMINERS CUE:        NONE EXAMINERS NOTE: Figure 2 from the below procedures is the same figure as Attachment 6 from the above procedure. Using Figure 2 is acceptable.
1-ONP-01.03 PLANT CONDITION 3 SHUTDOWN COOLING IN OPERATION - NO REDUCED INVENTORY 1-ONP-01.04 PLANT CONDITION 4 SHUTDOWN COOLING IN OPERATION - REDUCED INVENTORY OPERATIONS 1-ONP-01.05 PLANT CONDITION 5 SDC SYSTEM IN OPERATION - REACTOR HEAD REMOVED COMMENTS:
END OF TASK STOP TIME: __________
NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 7


NRC ADM JPM A
CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
-1  NRC  ADMINISTRATIVE JPM A
-1 Rev. 1 PAGE 5  STEP 4: ATTACHMENT 1 step 1A Record the following information Time since shutdown (hours)  STANDARD: Records 97 hours EXAMINER'S CUE:
NONE  COMMENTS:
_____ SAT
_____ UNSAT STEP 5: ATTACHMENT 1 step 1B
 
Record time to boil at mid
-loop per Table 1 STANDARD: 1 3.8 minutes  EXAMINER'S CUE:
NONE              EXAMINERS NOTE    Temperature between columns, select higher temperature Time since shutdown between rows, select the lesser time COMMENTS:
CRITICAL STEP  _____ SAT 
 
_____ UNSAT STEP 6: ATTACHMENT 1 ste p 1C                        Record additional time to boil for a 100ft3 volume per Table 2 STANDARD: 0.958 (minutes / 100ft 3 )  EXAMINER'S CUE:
NONE              EXAMINERS NOTE    Temperature between columns, select higher temperature Time since shutdown between rows, select the lesser time COMMENTS: 
 
CRITICAL STEP  _____ SAT  _____ UNSAT
 
NRC ADM JPM A
-1  NRC  ADMINISTRATIVE JPM A
-1 Rev. 1 PAGE 6  STEP 7: ATTACHMENT 1 step 1D Record additional 100ft3  volum es above mid
-loop per Table 3
 
STANDARD: 1.21  (100 ft 3)  EXAMINER'S CUE:
NO NE  COMMENTS:      CRITICAL STEP  _____ SAT 
 
_____ UNSAT STEP 8 (1E): ATTACHMENT 1 step 1E
 
Calculate Time to Boil as Follows:
 
(__13.8__) +      [(_0.958_)      x    (__1.21__)]        =  14.96  min Time to boil        Additional            Additional              Time to Boil Time to boil          100 ft3 volumes    Step 1.B Step 1.C              Step 1.D STANDARD: Time to Boil 14.96 minutes (14- 1 6 minutes is acceptable)
 
EXAMINER'S CUE:
NONE  COMMENTS:
CRITICAL STEP
_____ SAT
_____ UNSAT
 
NRC ADM JPM A
-1  NRC  ADMINISTRATIVE JPM A
-1 Rev. 1 PAGE 7  STEP 9: ATTACHMENT 1 step 2 IF core shuffle or reload has NOT been completed, THEN CALCULATE time boiling will occur as follows
:    (__0115__) +      (_14.96_)    =    (0129.96)
Time SDC lost      Time to boil  Time boiling will occur Step 1.A              Step 1.E             
 
STANDARD:  Time 0129 to 0131 is acceptable EXAMINER'S CUE:
NONE  COMMENTS:    CRITICAL STEP 
 
_____ SAT
_____ UNSAT 1-AOP-01.0 8 , 'RCS Leakage Abnormal Operations' Attachment 6 STEP 10: Attachment 6 Flow to Makeup for Boil
- Off STANDARD:  Using Attachment 6 (or Figure 2 from one of the below procedures) determines 4 days shutdown, makeup for boil off is 70 gallons per minute
(+/- 2 gpm). EXAMINER'S CUE:
NONE EXAMINER'S NOTE: Figure 2 from the below procedure s is the same figure as Attachment 6 from the above procedure. Using Figure 2 is acceptable.
 
1-ONP-01.03 'PLANT CONDITION 3 SHUTDOWN COOLING IN OPERATION
- NO REDUCED INVENTORY' 1-ONP-01.04 'PLANT CONDITION 4 SHUTDOWN COOLING IN OPERATION
- REDUCED INVENTORY OPERATIONS'
 
1-ONP-01.05 'PLANT CONDITION 5 SDC SYSTEM IN OPERATION
- REACTOR HEAD REMOV ED'  COMMENTS: END OF TASK CRITICAL STEP
_____ SAT  _____ UNSAT STOP TIME:  __________
 
NRC ADM A-1 Rev. 1 CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Directions to the candidate for Administrative JPMS:
Directions to the candidate for Administrative JPMS:
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you. Initial Conditions Unit 1 is in a Refueling outage. Core shuffle or reload has NOT been completed.
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.
Initial Conditions Unit 1 is in a Refueling outage. Core shuffle or reload has NOT been completed.
A loss of shutdown cooling occurs.
A loss of shutdown cooling occurs.
Initiating Cue The US has directed you to determine the time to core boiling and time boiling will occur using 1
Initiating Cue The US has directed you to determine the time to core boiling and time boiling will occur using 1-AOP-03.02, Shutdown Cooling Abnormal Operations, ATTACHMENT 1, Estimated Time to Core Boiling AND determine flow to makeup for boil - off.
-AOP-03.02, Shutdown Cooling Abnormal Operations, ATTACHMENT 1, 'Estimated Time to Core Boiling
Given:
AND determine flow to makeup for boil  
* RCS temperature is 114°F
- off. Given:   RCS temperature is 114°F RCS level is 31 feet The Unit was tripped on Oct. 18, at 0015 Loss of Shutdown Cooling occurred at: Oct 22, 0115 Current date / time is Oct. 22, 0120
* RCS level is 31 feet
* The Unit was tripped on Oct. 18, at 0015
* Loss of Shutdown Cooling occurred at: Oct 22, 0115
* Current date / time is Oct. 22, 0120 NRC ADM A-1 Rev. 1


REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop an ECO for 2 B CCW - UNIT 2 A-3 APPLICANT   __________________________________________
REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop an ECO for 2B CCW - UNIT 2 A-3 APPLICANT __________________________________________
EXAMINER     __________________________________________
EXAMINER __________________________________________


ST. LUCIE TRAINING DEPT.
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2B CCW pump KA Statement:     Ability to obtain and interpret station electrical and mechanical drawings.
NRC ADM JPM A
KA #:           2.2.41 (3.9)
-3 Rev. 1 PAGE 2  REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2B CCW pump   KA Statement:
Ability to obtain and interpret station electrical and mechanical drawings. KA #: 2.2.41 (3.9)


==References:==
==References:==


P&ID 2998-G-0 83 SH 1 ADM-09.08 Operations In
P&ID 2998-G-083 SH 1 ADM-09.08 Operations In-Plant Equipment Clearance Orders 0-NOP-24.01, Draining Potentially Hazardous Or Toxic Systems to The Environment 2-ADM-03.01A Unit 2 Power Distribution Breaker List Switchgear Operations Policy OPS-406 Clearance Database Conventions Candidate:                                                     Time Start _______
-Plant Equipment Clearance Orders 0-NOP-24.01, Draining Potentially Hazardous Or Toxic Systems to The Environment 2-ADM-03.01A Unit 2 Power Distribution Breaker List Switchgear Operations Policy OPS
Name Time Finish _______
-406 Clearance Database Conventions
Performance Rating:         Sat             Unsat Validation Time       25 minutes Examiner:                                         Signature:
 
Candidate:
Time Start _______
Name Time Finish _______
Performance Rating:
Sat                     Unsat                
 
Validation Time         2 5 minutes Examiner:                                                             Signature:
 
Comments ST. LUCIE TRAINING DEPT.
Comments ST. LUCIE TRAINING DEPT.
NRC ADM JPM A
NRC ADM JPM A-3 Rev. 1 PAGE 2
-3 Rev. 1 PAGE 3 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION  ADMINISTRATIVE JPM Develop ECO for 2B CCW pump  Directions to the candidate for Administrative JPMS:


REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2B CCW pump Directions to the candidate for Administrative JPMS:
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.
Initial Conditions Unit 2 is at 100% power
Initial Conditions Unit 2 is at 100% power. The 2B CCW pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service. The 2C CCW pump has been mechanically and electrically aligned and is running on the B header.
. The 2B CCW pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service. The 2C CCW pump has been mechanically and electrically aligned and is running on the 'B' header.  
 
Initiating Cue On the attached matrix, develop a Tag out boundary for the 2B CCW Pump that would facilitate replacing the pump shaft seal.
Initiating Cue On the attached matrix, develop a Tag out boundary for the 2B CCW Pump that would facilitate replacing the pump shaft seal.
ST. LUCIE TRAINING DEPT.
NRC ADM JPM A-3 Rev. 1 PAGE 3


NRC ADM JPM A-3 Rev. 1  Component Name Position Tag (type) Prior to opening drain, contact Chemistry (see note bottom of page)   NOTE: Pull to Lock position is critical step in that if pump were left in spring loaded stop position the 2C CCW pump would not start on LOOP.  
Component                       Name                     Position                 Tag (type)
  *2B CCW Control Room Pump Switch 2-CS-205 Pull to Lock Position.
Prior to opening drain, contact Chemistry (see note bottom of page)
Info Tag *Breaker 2-20404 2B CCW Pump Racked Out Plus Danger Breaker 2-20404 Trip Fuse Removed N/A Breaker 2-20404 Close Fuse Removed N/A *SB14148 2B CCW Pump Discharge Valve Closed Plus Danger *SB14133 2B CCW Pump Suction Valve Closed Plus Danger                                   #As per Ops Policy 406, 'Vents and Drains do not require a danger tag. It is preferred, but not required'.
NOTE: Pull to Lock position is critical step in that if pump were left in spring loaded stop position the 2C CCW pump would not start on LOOP.
*V14536 Drain Open #Danger *V14145 Drain Open #Danger *V14149 V14549 Vent Open #Danger     NOTE: Only one of the two drains are required. If both drains are opened that is acceptable also.             *Critical Step NOTE From ADM-09.08, Operations In
  *2B CCW Control                   2-CS-205             Pull to Lock Position.           Info Tag Room Pump Switch
-Plant Equipment Clearance Orders, step 3.3.12:
  *Breaker 2-20404               2B CCW Pump               Racked Out Plus                 Danger Breaker 2-20404                   Trip Fuse                 Removed                       N/A Breaker 2-20404                 Close Fuse                 Removed                       N/A
        *SB14148                 2B CCW Pump                 Closed Plus                   Danger Discharge Valve
        *SB14133                 2B CCW Pump                 Closed Plus                   Danger Suction Valve
  #As per Ops Policy 406, Vents and Drains do not require a danger tag. It is preferred, but not required.
        *V14536                       Drain                     Open                   #Danger
        *V14145                       Drain                     Open                   #Danger
  *V14149 V14549                       Vent                     Open                   #Danger NOTE: Only one of the two drains are required. If both drains are opened that is acceptable also.
*Critical Step NOTE From ADM-09.08, Operations In-Plant Equipment Clearance Orders, step 3.3.12:
Prior to draining, obtains verification from chemistry that NO biocide hazard exists before issuing a clearance on the TCW system, CCW system or EDG Cooling Water Systems that may require the draining of liquid from the system.
Prior to draining, obtains verification from chemistry that NO biocide hazard exists before issuing a clearance on the TCW system, CCW system or EDG Cooling Water Systems that may require the draining of liquid from the system.
From 0-NOP-24.01, Draining Potentially Hazardous Or Toxic Systems to The Environment. Chemistry should also be questioned if the CCW system has any activity. If Chemistry questioned, state there is no activity in the CCW system. (Normally the SRO would coordinate with Chemistry to determine the drain path for CCW. i.e. activity and nitrate concentration).  
From 0-NOP-24.01, Draining Potentially Hazardous Or Toxic Systems to The Environment. Chemistry should also be questioned if the CCW system has any activity. If Chemistry questioned, state there is no activity in the CCW system. (Normally the SRO would coordinate with Chemistry to determine the drain path for CCW. i.e. activity and nitrate concentration).
NRC ADM JPM A-3 Rev. 1


NRC ADM JPM A-3 Rev. 1  (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Initial Conditions Unit 2 is at 100% power. The 2B CCW pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service. The 2C CCW pump has been mechanically and electrically aligned and is running on the 'B' header.
Initial Conditions Unit 2 is at 100% power. The 2B CCW pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service. The 2C CCW pump has been mechanically and electrically aligned and is running on the B header.
Initiating Cue On the attached matrix, develop a Tag out boundary for the 2B CCW Pump that would facilitate replacing the pump shaft seal.
Initiating Cue On the attached matrix, develop a Tag out boundary for the 2B CCW Pump that would facilitate replacing the pump shaft seal.
NRC ADM JPM A-3 Rev. 1


(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
NRC ADM JPM A-3 Rev. 1  Component Name Position Tag (type)
Component             Name               Position           Tag (type)
ST. LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM
NRC ADM JPM A-3 Rev. 1
 
DETERMINE EXPOSURE LIMITS UNDER NON EMERGENCY CONDITIONS RO A 4    APPLICANT  __________________________________________
EXAMINER    __________________________________________


ST. LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM DETERMINE EXPOSURE LIMITS UNDER NON EMERGENCY CONDITIONS RO A4 APPLICANT __________________________________________
EXAMINER      __________________________________________
Developed/Revised by:
Developed/Revised by:
Date Training Management Approval:
Date Training Management Approval:
Date NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 2 ST LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS KA Statement:
Date
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
 
KA #: 3.2 / 3.7
ST LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS KA Statement:     2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
KA #:             3.2 / 3.7


==References:==
==References:==
HP-2, Radiation Protection Manual HPP-30, Personnel Monitoring NOTE: HP-2 and/or HPP-30 reference to be available to perform this task.
Applicant:                                                Time Start ______
Name Time Finish ______
Performance Rating:        Sat            Unsat Validation Time      15 minutes Examiner:                                      Signature:
Comments NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 2


HP-2, Radiation Protection Manual HPP-30, Personnel Monitoring NOTE: HP-2 and/or HPP
ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS Directions to the applicant for Administrative JPMS:
-30 reference to be available to perform this task.                                                                                       
 
Applicant:
Time Start
______            Name Time Finish
______        Performance Rating:
Sat Unsat                 
 
Validation Time 15 minutes Examiner:
Signature:
 
Comments NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 3 ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS Directions to the applicant for Administrative JPMS:
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.
I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.
Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Spreader is inoperable.  
Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Spreader is inoperable.
 
The repair is estimated to take 85 minutes in an 850 mrem/hr field.
The repair is estimated to take 85 minutes in a n 85 0 mrem/hr field.
Below are the employees dose records:
 
Current Year Lifetime  Current Year Westinghouse                                       total at all Age     Dose   FPL at St. Lucie Employee                                              sites (TEDE)      (TEDE)
Below are the employee's dose records:
(TEDE) 1           35      27 R       250 mR       3050 mR 2           58      35 R       700 mR       2400 mR Current Year Lifetime  Current Year FPL                                             total at all Age     Dose   FPL at St. Lucie Employee                                              sites (TEDE)      (TEDE)
Westinghouse Employee Age Lifetime Dose (TEDE) Current Year FPL at St. Lucie (TEDE) Current Year total at all sites (TEDE) 1 3 5 27 R 250 mR 3 050 mR 2 5 8 35 R 700 mR 2 400 mR     FPL Employee Age Lifetime Dose (TEDE) Current Year FPL at St. Lucie (TEDE) Current Year total at all sites (TEDE) 1 4 5 27 R 8 50 mR 1050 mR 2 4 8 33 R 1320 mR 1320 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to repair the spreader without the Site Vice President's approval?
(TEDE) 1           45      27 R       850 mR       1050 mR 2           48      33 R     1320 mR       1320 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to repair the spreader without the Site Vice Presidents approval?
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 4 START TIME: __________
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 3
STEP 1: Calculates the dose the employee will receive performing the repair. STANDARD: CALCULAT ES 850 mR/hr x 1.416 hr = 1204.2 mR. COMMENTS:
_____ SAT 
 
_____ UNSAT
 
HP-2, FP&L Health Physics Manual
 
STEP 2: Determines Westinghouse employee #1 "s FPL Site and Total for All Sites doses.
STANDARD: DETERMINE S that Westinghouse employee #1 will NOT exceed 4500 mR/year for All Sites
. Westinghouse employee #1 CAN be used without Site VP approval
. EXAMINERS NOTE:
Westinghouse employee #1 would receive 1454.2 mR for St. Lucie site and 4 254.2 mR for all sites.
Reference HP
-2 step 4.1.1.4.c.(1) page 33. If asked - cue the examinee that the provided dose is the total dose received as read from the individual's TLD.
COMMENTS:    CRITICAL STEP   
 
_____ SAT  _____ UNSAT STEP 3: Determines Westinghouse employee #2"s FPL Site and Total for All Sites doses. STANDARD: DETERMINES that Westinghouse employee #
2 will NOT exceed FPL Site and Total for All Sites dose limits. Westinghouse employee #1 CAN be used without Site VP approval
. EXAMINERS NOTE:
Westinghouse employee #2 would receive 1904.2 mR for St. Lucie site and 3604.2 mR for all sites.
Reference HP
-2 step 4.1.1.4.b.(1) page 32.


START TIME: __________
STEP 1:      Calculates the dose the employee will receive performing the repair.        _____ SAT STANDARD:    CALCULATES 850 mR/hr x 1.416 hr = 1204.2 mR.
_____ UNSAT COMMENTS:
HP-2, FP&L Health Physics Manual CRITICAL STEP 2:      Determines Westinghouse employee #1s FPL Site and Total for All Sites      STEP doses.
STANDARD:      DETERMINES that Westinghouse employee #1 will NOT exceed 4500 mR/year for All Sites. Westinghouse employee #1 CAN be used without Site VP approval.                                                            _____ SAT EXAMINERS NOTE: Westinghouse employee #1 would receive 1454.2 mR for St. Lucie site and 4254.2 mR for all sites. Reference HP-2 step          _____ UNSAT 4.1.1.4.c.(1) page 33.
If asked - cue the examinee that the provided dose is the total dose received as read from the individuals TLD.
COMMENTS:
COMMENTS:
CRITICAL STEP  
STEP 3:      Determines Westinghouse employee #2s FPL Site and Total for All Sites      CRITICAL doses.                                                                    STEP STANDARD:      DETERMINES that Westinghouse employee #2 will NOT exceed FPL Site and Total for All Sites dose limits. Westinghouse employee #1 CAN be used without Site VP approval.
_____ SAT EXAMINERS NOTE: Westinghouse employee #2 would receive 1904.2 mR for St. Lucie site and 3604.2 mR for all sites. Reference HP-2 step 4.1.1.4.b.(1) page 32.                                                      _____ UNSAT COMMENTS:
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 4


_____ SAT
STEP 4:       Determines FPL employee #1s FPL Site and Total for All Sites doses.           CRITICAL STEP STANDARD:     DETERMINES that FPL employee #1 will NOT exceed 2500 mR/year for St.
_____ UNSAT
Lucie Site and will NOT need the St. Vice President approval. Therefore FPL employee #1 CAN be used without Site VP approval.
 
_____ SAT EXAMINERS NOTE: FPL employee #1 would receive 2054.2 mR for St.
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 5  STEP 4: Determines FPL employee #1"s FPL Site and Total for All Sites doses.
Lucie site and 2254.2 mR for all sites. Reference HP-2 step 4.1.1.4.b.(1) page 32.                                                                       _____ UNSAT COMMENTS:
STANDARD: DETERMINES that FPL employee #1 will NOT exceed 2500 mR/year for St. Lucie Site and will NOT need the St. Vice President approval. Therefore FPL employee #1 CAN be used without Site VP approval
STEP 5:       Determines FPL employee #2s FPL Site and Total for All Sites doses.           CRITICAL STEP STANDARD:     DETERMINES that FPL employee #2 WILL EXCEED FPL Site but NOT all site dose limits. Therefore FPL employee #2 CANNOT be used without Site VP approval.                                                                       _____ SAT EXAMINERS NOTE: FPL employee #2 would receive 2524.2 mR for St.
. EXAMINERS NOTE:
Lucie site and 2524.2 for all sites. Reference HP-2 step 4.1.1.4.b.(1) page     _____ UNSAT 32.
FPL employee #1 would receive 2054.2 mR for St. Lucie si te and 2254.2 mR for all sites
. Reference HP
-2 step 4.1.1.4.b.(1) page 32.
COMMENTS:
 
CRITICAL STEP
_____ SAT  _____ UNSAT
 
STEP 5: Determines FPL employee #2"s FPL Site and Total for All Sites doses.
 
STANDARD: DETERMINES that FPL employee #
2 WILL EXCEED FPL Site but NOT all site dose limits. Therefore FPL employee #
2 CANNOT be used without Site VP approval. EXAMINERS NOTE:
FPL employee #2 would receive 2524.2 mR for St. Lucie site and 2524.2 for all sites
. Reference HP
-2 step 4.1.1.4.b.(1) page 32.
COMMENTS:
COMMENTS:
CRITICAL STEP    _____ SAT
STEP (done): Candidate informs the Examiner that the task is complete.
_____ UNSAT STEP (done): Candidate informs the Examiner that the task is complete.
STANDARD: INFORMS the Examiner that the task is complete.
 
EXAMINERS CUE:       TASK IS COMPLETE
STANDARD: INFORMS the Examiner that the task is complete
_____ SAT COMMENTS:
.
_____ UNSAT END OF TASK STOP TIME: __________
EXAMINER'S CUE:
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 5
TASK IS COMPLETE COMMENTS:
END OF TASK
 
_____ SAT
_____ UNSAT STOP TIME:
__________
 
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 6 CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Initial Conditions
 
Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Spreader is inoperable.


CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Spreader is inoperable.
The repair is estimated to take 85 minutes in an 850 mrem/hr field.
The repair is estimated to take 85 minutes in an 850 mrem/hr field.
 
Below are the employees dose records:
Below are the employee's dose records:
Current Year Lifetime  Current Year Westinghouse                                       total at all Age   Dose     FPL at St. Lucie Employee                                            sites (TEDE)      (TEDE)
Westinghouse Employee Age Lifetime Dose (TEDE) Current Year FPL at St. Lucie (TEDE) Current Year total at all sites (TEDE) 1 3 5 27 R 250 mR 3050 mR 2 5 8 35 R 700 mR 2400 mR     FPL Employee Age Lifetime Dose (TEDE) Current Year FPL at St. Lucie (TEDE) Current Year total at all sites (TEDE) 1 4 5 27 R 850 mR 1050 mR 2 4 8 33 R 1320 mR 1320 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to repair the spreader without the Site Vice President's approval?}}
(TEDE) 1         35    27 R       250 mR         3050 mR 2         58    35 R       700 mR         2400 mR Current Year Lifetime  Current Year FPL                                           total at all Age   Dose     FPL at St. Lucie Employee                                            sites (TEDE)      (TEDE)
(TEDE) 1         45    27 R       850 mR         1050 mR 2         48    33 R     1320 mR         1320 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to repair the spreader without the Site Vice Presidents approval?
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 6}}

Latest revision as of 10:07, 12 November 2019

Initial Exam 2011-302 Final Administrative JPMs
ML113640128
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/14/2011
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
50-335/11-302, 50-389/11-302
Download: ML113640128 (33)


Text

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING AND MAKEUP FLOW FOR BOILOFF A-1 NOTE TO EXAMINER: Do not handout Attachment 6, Minimum Flow to Makeup for Boil-off (1-AOP-01.08, RCS Leakage Abnormal Operations) until Applicant requests attachment.

Applicant ____________________________

Examiner____________________________

NRC ADM. A-1 Rev. 1

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING AND MAKEUP FLOW FOR BOILOFF KA Statement: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

KA #: 3.9 / 4.2

References:

1-AOP-03.02. Shutdown Cooling Abnormal Operations 1-AOP-01.08, RCS Leakage Abnormal Operations Attachment 6, Minimum Flow to Makeup for Boil-off.

Validation Time: _____15 minutes______

Start Time: _____________ Finish Time: ______________

Performance Rating: Sat Unsat Comments NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 2

NRC ADM JPM A-1 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL ON LOSS OF SHUTDOWN COOLING Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is in a Refueling outage. Core shuffle or reload has NOT been completed.

A loss of shutdown cooling occurs.

Initiating Cue The US has directed you to determine the time to core boiling and time boiling will occur using 1-AOP-03.02, Shutdown Cooling Abnormal Operations, ATTACHMENT 1, Estimated Time to Core Boiling AND determine flow to makeup for boil - off.

Given:

  • RCS temperature is 114°F
  • RCS level is 31 feet
  • The Unit was tripped on Oct. 18, at 0015
  • Current date / time is Oct. 22, 0120 NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 3

NRC ADM JPM A-1 START TIME: __________

1-AOP-03.02, Shutdown Cooling Abnormal Operations ATTACHMENT 1

_____ SAT STEP 1 (4.2.2): ATTACHMENT 1 step 1A Record the following information _____ UNSAT

  • Time SDC was lost STANDARD: Records 0115 EXAMINERS CUE: NONE COMMENTS:

STEP 2 (4.2.2): ATTACHMENT 1 step 1A Record the following information _____ SAT

  • RCS Temperature STANDARD: Records 114ºF _____ UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 3 : ATTACHMENT 1 step 1A Record the following information _____ SAT Vessel / Cavity Level

_____ UNSAT STANDARD: Records 31 ft.

EXAMINERS CUE: NONE COMMENTS:

NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 4

NRC ADM JPM A-1 STEP 4: ATTACHMENT 1 step 1A Record the following information _____ SAT Time since shutdown (hours)

_____ UNSAT STANDARD: Records 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> EXAMINERS CUE: NONE COMMENTS:

STEP 5: ATTACHMENT 1 step 1B CRITICAL STEP Record time to boil at mid-loop per Table 1 STANDARD: 13.8 minutes _____ SAT EXAMINERS CUE: NONE EXAMINERS NOTE _____ UNSAT

  • Temperature between columns, select higher temperature
  • Time since shutdown between rows, select the lesser time COMMENTS:

STEP 6: ATTACHMENT 1 step 1C CRITICAL STEP 3

Record additional time to boil for a 100ft volume per Table 2 3

STANDARD: 0.958 (minutes / 100ft ) _____ SAT EXAMINERS CUE: NONE EXAMINERS NOTE _____ UNSAT

  • Temperature between columns, select higher temperature
  • Time since shutdown between rows, select the lesser time COMMENTS:

NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 5

NRC ADM JPM A-1 STEP 7: ATTACHMENT 1 step 1D CRITICAL STEP 3

Record additional 100ft volumes above mid-loop per Table 3 3

_____ SAT STANDARD: 1.21 (100 ft )

EXAMINERS CUE: NONE _____ UNSAT COMMENTS:

STEP 8 (1E): ATTACHMENT 1 step 1E CRITICAL STEP Calculate Time to Boil as Follows:

(__13.8__) + [(_0.958_) x (__1.21__)] = 14.96 min Time to boil Additional Additional Time to Boil _____ SAT 3

Time to boil 100 ft volumes Step 1.B Step 1.C Step 1.D

_____ UNSAT STANDARD: Time to Boil 14.96 minutes (14- 16 minutes is acceptable)

EXAMINERS CUE: NONE COMMENTS:

NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 6

NRC ADM JPM A-1 STEP 9: ATTACHMENT 1 step 2 CRITICAL STEP IF core shuffle or reload has NOT been completed, THEN CALCULATE time boiling will occur as follows:

(__0115__) + (_14.96_) = (0129.96) _____ SAT Time SDC lost Time to boil Time boiling will occur Step 1.A Step 1.E

_____ UNSAT STANDARD: Time 0129 to 0131 is acceptable EXAMINERS CUE: NONE COMMENTS:

CRITICAL 1-AOP-01.08, RCS Leakage Abnormal Operations STEP Attachment 6 STEP 10: Attachment 6 Flow to Makeup for Boil - Off _____ SAT STANDARD: Using Attachment 6 (or Figure 2 from one of the below procedures) _____ UNSAT determines 4 days shutdown, makeup for boil off is 70 gallons per minute (+/-

2 gpm).

EXAMINERS CUE: NONE EXAMINERS NOTE: Figure 2 from the below procedures is the same figure as Attachment 6 from the above procedure. Using Figure 2 is acceptable.

1-ONP-01.03 PLANT CONDITION 3 SHUTDOWN COOLING IN OPERATION - NO REDUCED INVENTORY 1-ONP-01.04 PLANT CONDITION 4 SHUTDOWN COOLING IN OPERATION - REDUCED INVENTORY OPERATIONS 1-ONP-01.05 PLANT CONDITION 5 SDC SYSTEM IN OPERATION - REACTOR HEAD REMOVED COMMENTS:

END OF TASK STOP TIME: __________

NRC ADMINISTRATIVE JPM A-1 Rev. 1 PAGE 7

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is in a Refueling outage. Core shuffle or reload has NOT been completed.

A loss of shutdown cooling occurs.

Initiating Cue The US has directed you to determine the time to core boiling and time boiling will occur using 1-AOP-03.02, Shutdown Cooling Abnormal Operations, ATTACHMENT 1, Estimated Time to Core Boiling AND determine flow to makeup for boil - off.

Given:

  • RCS temperature is 114°F
  • RCS level is 31 feet
  • The Unit was tripped on Oct. 18, at 0015
  • Current date / time is Oct. 22, 0120 NRC ADM A-1 Rev. 1

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop an ECO for 2B CCW - UNIT 2 A-3 APPLICANT __________________________________________

EXAMINER __________________________________________

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2B CCW pump KA Statement: Ability to obtain and interpret station electrical and mechanical drawings.

KA #: 2.2.41 (3.9)

References:

P&ID 2998-G-083 SH 1 ADM-09.08 Operations In-Plant Equipment Clearance Orders 0-NOP-24.01, Draining Potentially Hazardous Or Toxic Systems to The Environment 2-ADM-03.01A Unit 2 Power Distribution Breaker List Switchgear Operations Policy OPS-406 Clearance Database Conventions Candidate: Time Start _______

Name Time Finish _______

Performance Rating: Sat Unsat Validation Time 25 minutes Examiner: Signature:

Comments ST. LUCIE TRAINING DEPT.

NRC ADM JPM A-3 Rev. 1 PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2B CCW pump Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 is at 100% power. The 2B CCW pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service. The 2C CCW pump has been mechanically and electrically aligned and is running on the B header.

Initiating Cue On the attached matrix, develop a Tag out boundary for the 2B CCW Pump that would facilitate replacing the pump shaft seal.

ST. LUCIE TRAINING DEPT.

NRC ADM JPM A-3 Rev. 1 PAGE 3

Component Name Position Tag (type)

Prior to opening drain, contact Chemistry (see note bottom of page)

NOTE: Pull to Lock position is critical step in that if pump were left in spring loaded stop position the 2C CCW pump would not start on LOOP.

  • 2B CCW Control 2-CS-205 Pull to Lock Position. Info Tag Room Pump Switch
  • Breaker 2-20404 2B CCW Pump Racked Out Plus Danger Breaker 2-20404 Trip Fuse Removed N/A Breaker 2-20404 Close Fuse Removed N/A
  • SB14148 2B CCW Pump Closed Plus Danger Discharge Valve
  • SB14133 2B CCW Pump Closed Plus Danger Suction Valve
  1. As per Ops Policy 406, Vents and Drains do not require a danger tag. It is preferred, but not required.
  • V14536 Drain Open #Danger
  • V14145 Drain Open #Danger
  • V14149 V14549 Vent Open #Danger NOTE: Only one of the two drains are required. If both drains are opened that is acceptable also.
  • Critical Step NOTE From ADM-09.08, Operations In-Plant Equipment Clearance Orders, step 3.3.12:

Prior to draining, obtains verification from chemistry that NO biocide hazard exists before issuing a clearance on the TCW system, CCW system or EDG Cooling Water Systems that may require the draining of liquid from the system.

From 0-NOP-24.01, Draining Potentially Hazardous Or Toxic Systems to The Environment. Chemistry should also be questioned if the CCW system has any activity. If Chemistry questioned, state there is no activity in the CCW system. (Normally the SRO would coordinate with Chemistry to determine the drain path for CCW. i.e. activity and nitrate concentration).

NRC ADM JPM A-3 Rev. 1

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Unit 2 is at 100% power. The 2B CCW pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service. The 2C CCW pump has been mechanically and electrically aligned and is running on the B header.

Initiating Cue On the attached matrix, develop a Tag out boundary for the 2B CCW Pump that would facilitate replacing the pump shaft seal.

NRC ADM JPM A-3 Rev. 1

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Component Name Position Tag (type)

NRC ADM JPM A-3 Rev. 1

ST. LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM DETERMINE EXPOSURE LIMITS UNDER NON EMERGENCY CONDITIONS RO A4 APPLICANT __________________________________________

EXAMINER __________________________________________

Developed/Revised by:

Date Training Management Approval:

Date

ST LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS KA Statement: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

KA #: 3.2 / 3.7

References:

HP-2, Radiation Protection Manual HPP-30, Personnel Monitoring NOTE: HP-2 and/or HPP-30 reference to be available to perform this task.

Applicant: Time Start ______

Name Time Finish ______

Performance Rating: Sat Unsat Validation Time 15 minutes Examiner: Signature:

Comments NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 2

ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS Directions to the applicant for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Spreader is inoperable.

The repair is estimated to take 85 minutes in an 850 mrem/hr field.

Below are the employees dose records:

Current Year Lifetime Current Year Westinghouse total at all Age Dose FPL at St. Lucie Employee sites (TEDE) (TEDE)

(TEDE) 1 35 27 R 250 mR 3050 mR 2 58 35 R 700 mR 2400 mR Current Year Lifetime Current Year FPL total at all Age Dose FPL at St. Lucie Employee sites (TEDE) (TEDE)

(TEDE) 1 45 27 R 850 mR 1050 mR 2 48 33 R 1320 mR 1320 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to repair the spreader without the Site Vice Presidents approval?

NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 3

START TIME: __________

STEP 1: Calculates the dose the employee will receive performing the repair. _____ SAT STANDARD: CALCULATES 850 mR/hr x 1.416 hr = 1204.2 mR.

_____ UNSAT COMMENTS:

HP-2, FP&L Health Physics Manual CRITICAL STEP 2: Determines Westinghouse employee #1s FPL Site and Total for All Sites STEP doses.

STANDARD: DETERMINES that Westinghouse employee #1 will NOT exceed 4500 mR/year for All Sites. Westinghouse employee #1 CAN be used without Site VP approval. _____ SAT EXAMINERS NOTE: Westinghouse employee #1 would receive 1454.2 mR for St. Lucie site and 4254.2 mR for all sites. Reference HP-2 step _____ UNSAT 4.1.1.4.c.(1) page 33.

If asked - cue the examinee that the provided dose is the total dose received as read from the individuals TLD.

COMMENTS:

STEP 3: Determines Westinghouse employee #2s FPL Site and Total for All Sites CRITICAL doses. STEP STANDARD: DETERMINES that Westinghouse employee #2 will NOT exceed FPL Site and Total for All Sites dose limits. Westinghouse employee #1 CAN be used without Site VP approval.

_____ SAT EXAMINERS NOTE: Westinghouse employee #2 would receive 1904.2 mR for St. Lucie site and 3604.2 mR for all sites. Reference HP-2 step 4.1.1.4.b.(1) page 32. _____ UNSAT COMMENTS:

NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 4

STEP 4: Determines FPL employee #1s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that FPL employee #1 will NOT exceed 2500 mR/year for St.

Lucie Site and will NOT need the St. Vice President approval. Therefore FPL employee #1 CAN be used without Site VP approval.

_____ SAT EXAMINERS NOTE: FPL employee #1 would receive 2054.2 mR for St.

Lucie site and 2254.2 mR for all sites. Reference HP-2 step 4.1.1.4.b.(1) page 32. _____ UNSAT COMMENTS:

STEP 5: Determines FPL employee #2s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that FPL employee #2 WILL EXCEED FPL Site but NOT all site dose limits. Therefore FPL employee #2 CANNOT be used without Site VP approval. _____ SAT EXAMINERS NOTE: FPL employee #2 would receive 2524.2 mR for St.

Lucie site and 2524.2 for all sites. Reference HP-2 step 4.1.1.4.b.(1) page _____ UNSAT 32.

COMMENTS:

STEP (done): Candidate informs the Examiner that the task is complete.

STANDARD: INFORMS the Examiner that the task is complete.

EXAMINERS CUE: TASK IS COMPLETE

_____ SAT COMMENTS:

_____ UNSAT END OF TASK STOP TIME: __________

NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 5

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Spreader is inoperable.

The repair is estimated to take 85 minutes in an 850 mrem/hr field.

Below are the employees dose records:

Current Year Lifetime Current Year Westinghouse total at all Age Dose FPL at St. Lucie Employee sites (TEDE) (TEDE)

(TEDE) 1 35 27 R 250 mR 3050 mR 2 58 35 R 700 mR 2400 mR Current Year Lifetime Current Year FPL total at all Age Dose FPL at St. Lucie Employee sites (TEDE) (TEDE)

(TEDE) 1 45 27 R 850 mR 1050 mR 2 48 33 R 1320 mR 1320 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to repair the spreader without the Site Vice Presidents approval?

NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 6