ML113640128: Difference between revisions
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Calculate Time to Boil as Follows: | 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: | EXAMINER'S CUE: | ||
Line 124: | Line 124: | ||
_____ SAT | _____ SAT | ||
_____ UNSAT 1-AOP-01.0 8 , 'RCS Leakage Abnormal Operations' Attachment 6 STEP 10: Attachment 6 Flow to Makeup for Boil | _____ 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 | - 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: | (+/- 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. | 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. | ||
Line 199: | Line 199: | ||
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 NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 2 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. | |||
of radiation exposure limits under normal or emergency conditions. | |||
KA #: 3.2 / 3.7 | KA #: 3.2 / 3.7 | ||
Revision as of 06:25, 30 April 2019
ML113640128 | |
Person / Time | |
---|---|
Site: | Saint Lucie |
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
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 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 ADMINISTRATIVE JPM A
-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.
KA #: 3.9 / 4.2
References:
1-AOP-03.02. 'Shutdown Cooling Abnormal Operations
'
1-AOP-01.0 8 , '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 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.
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 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
NRC ADM JPM A
-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
STANDARD: Records 31 ft. EXAMINER'S CUE:
NONE COMMENTS:
_____ SAT
_____ UNSAT
NRC ADM JPM A
-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 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> 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:
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 Loss of Shutdown Cooling occurred at: Oct 22, 0115 Current date / time is Oct. 22, 0120
REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop an ECO for 2 B CCW - UNIT 2 A-3 APPLICANT __________________________________________
EXAMINER __________________________________________
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 KA Statement:
Ability to obtain and interpret station electrical and mechanical drawings. KA #: 2.2.41 (3.9)
References:
P&ID 2998-G-0 83 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 2 5 minutes Examiner: Signature:
Comments ST. LUCIE TRAINING DEPT.
NRC ADM JPM A
-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:
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.
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.
- 2B CCW Control Room Pump Switch 2-CS-205 Pull to Lock Position.
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'.
- 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.
(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
NRC ADM JPM A-3 Rev. 1 Component Name Position Tag (type)
ST. LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM
DETERMINE EXPOSURE LIMITS UNDER NON EMERGENCY CONDITIONS RO A 4 APPLICANT __________________________________________
EXAMINER __________________________________________
Developed/Revised by:
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:
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 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.
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 a n 85 0 mrem/hr field.
Below are the employee's dose records:
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?
NRC JPM RO A4 Rev. 1 ADMINISTRATIVE JPM PAGE 4 START TIME: __________
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.
COMMENTS:
CRITICAL STEP
_____ SAT
_____ UNSAT
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.
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
. EXAMINERS NOTE:
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:
CRITICAL STEP _____ SAT
_____ UNSAT STEP (done): Candidate informs the Examiner that the task is complete.
STANDARD: INFORMS the Examiner that the task is complete
.
EXAMINER'S CUE:
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.
The repair is estimated to take 85 minutes in an 850 mrem/hr field.
Below are the employee's dose records:
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?