ML13032A245
| ML13032A245 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/29/2013 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-324/12-301, 50-325/12-301, LOT-ADM-JP-201-D13 | |
| Download: ML13032A245 (57) | |
Text
Conduct of Operations Evaluate Status of Operator Licenses R, N K/A 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
This is a new JPM that requires the examinee to determine the active/inactive status of licensed operators under different conditions.
Conduct of Operations Evaluate Level Instrument Operability R, N K/A 2.1.25 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
This is a new JPM that requires the examinee to determine operability of reactor water level instruments during single loop recirculation operation.
Equipment Control Develop a Clearance Boundary RBCCW Pump 20
- R, P K/A 2.2.13 Knowledge of tagging and clearance procedures.
This RO portion of this JPM was used on 2010 NRC exam. JPM will require the RO examinee to develop an equipment clearance manually. A new section of the JPM was developed to include SRO review of a clearance.
Radiation Control Determine Total Dose for ALARA R, D K/A 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
This is a bank JPM that will require the examinee to determine the lowest dose path to a work activity.
Emergency Procedures!Plan (SRO Only) Determine Offsite Release Rate Per OPEP-03.4.7 R, D K/A 2.4.40 Knowledge of SRO responsibilities in Emergency Plan implementation.
This is a bank JPM that requires the examinee to determine offsite release rates during accident conditions.
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC Cooi LESSON TITLE: Evaluate Status of Operator Licenses LESSON NUMBER: LOT-ADM-JP-201-D1 3 REVISION NO: 0 Prepared By: Dan Arhelger Nuclear Operations Instructor Date Concurred By Nuclear Operations Instructor Date Validated By:
Operations Department Representative Date Approved By:
Facility Representative / Date
Evaluate Status of Operator Licenses SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 2. The applicable procedure section WILL be provided to the trainee.
- 3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021 Append ix E, or similar to the trainee.
- 4. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
LOT-ADM.-JP-201-D1 3 Page 2 of 8 REV. 0
Evaluate Status of Operator Licenses Read the following to JPM performer.
TASK CONDITIONS:
Three operators have been performing off-shift duties and are now returning to licensed duties on shift. Operators 1 and 2 licenses were active and current when they left shift. The following conditions apply:
Ii NOTE: All shifts worked were full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts including turnovers.
Operator 1 (SRO):
Off shift since: December 31, 2011 Returned to shift: March 24, 2012 Shifts worked: Day shift, March 24 through March 26 Night Shift, March 30 through April 2 Watch position: Unit CRS Operator 2 (SRO):
Off shift since: May 1, 2011 Returned to shift: March 30, 2012 Shifts worked: Night shift, March 30 through April 2 Watch position: UnftCRS Operator 3 (Newly licensed RO):
Started on shift: March 29, 2012 Shifts worked: Day shift, March 29, 2012 through March 31, 2012 Watch position: OAC The Shift Manager conducted a plant walkthrough lAW 001-01 .05with all three operators on March 30, 2012 during their watch.
INITIATING CUE:
status of each operators license (active or inactive) as of April 2, 2012 lAW 001-01.05. -
LOT-ADM-JP-201-D13 Page 3 of 8 REV. 0
Evaluate Status of Operator Licenses PERFORMANCE CHECKLIST NOTE: Sequence of the following actions is NOT critical.
START TIME:
Step I Review data for Operator 1 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are NOT met for Operator I (License still active on return to shift but will be inactive March 31; five 12-hour shifts in a calendar quarter NOT completed to maintain active status through the following quarter; March 31 is NOT counted for maintaining license active since it spans a calendar quarter.)
- CRITICAL STEP** SATIUNSAT*
Step 2 Review data for Operator 2 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are met for Operator 2. (License is inactive due to time off shift; four 12-hour shifts required for reactivation are met as of April 2; Calendar quarter requirement does not apply for reactivation therefore spanning a calendar quarter is not a factor. Plant tour was performed within the required timeframe.)
- CRITICAL STEP** SATIUNSAT*
Step 3 Review data for Operator 3 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are met for Operator 3. (Three 12-hour shifts required for initial activation are met as of March
- 31. Plant tour was performed within the required timeframe.)
- CRITICAL STEP** SATIUNSAT*
LOT-ADM-JP-201 -Dl 3 Page 4 of 8 REV. 0
Evaluate Status of Operator Licenses I TERMINATING CUE: When the examinee has completed a determination of Operator L License status, this JPM is complete, TIME COMPLETED Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-201-D13 Page 5 of 8 REV. 0
Evaluate Status of Operator Licenses RELATED TASKS:
None K/A REFERENCE AND IMPORTANCE RATING:
GEN2.1.4 3.3/3.8 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 1 OCFR55, etc.
REFERENCES:
001-01.05, License Activation And Maintenance TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin - Conduct of Operations REASON FOR REVISION:
New JPM for HLC 2012 LOT-ADM-JP-201-D13 Page 6 of 8 REV. 0
Evaluate Status of Operator Licenses Validation Time: 20 Minutes (approximate)
Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 0 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X z
EVALUATION Trainee:_________________________________
JPM: Pass Fail Remedial Training Required: Yes No (Reference TAP-411 for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature: Date:__________
LOT-ADM-JP-201-D13 Page 7 of 8 REV. 0
TASK CONDITIONS:
)
Three operators have been performing off-shift duties and are nung-toicensd-d-ut1es ewstiift. Operators 1 and 2 licenses were active and current when they left shift. The following conditions apply:
Ii NOTE: All shifts worked were full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts including turnovers.
Operator 1 (SRO):
O Off shiftsince: December31, 2011 Returned to shift: March 24, 2012 Shifts worked: Day shift, March 24 through March 26 3 Night Shift, March 30 through April 2 Watch position: Unit CRS ti/i Operator 2 (SRO):
Off shiftsince: May 1,2011 Returned to shift: March 30, 2012 Shifts worked: Night shift, March 30 through April 2 4 i Watch position: Unit CRS Operator 3 (Newly licensed RO): ci Started on shift: March 29, 2012 Shifts worked: Day shift, March 29, 2012 through March 31, 2012 3 Watch position: OAC The Shift Manager conducted taflcthrough lAW 001-01 .with all three operators on March 30, 2012 during their watch.
INITIATING CUE:
Determine and circle the status of each operators license (active or inactive) as of April 2, 2012 10O[0t05.
Operator I license is: Active I Inactive Operator 2 license is: Active / Inactive Operator 3 license is: Active I Inactive Page 8 of 8
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC COO.B2 LESSON TITLE: Evaluate Level Instrument Operability LESSON NUMBER: LOT-ADM-J P-307-CO 1 REVISION NO: 0 Prepared By: Dan Arhelger Nuclear Operations Instructor Date Concurred By Nuclear Operations Instructor Date Validated By:
Operations Department Representative Date Approved By:
Facility Representative I Date
Evaluate Level Instrument Operability SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to performer)
I. The applicable procedure section WILL be provided to the trainee.
- 2. Provide examinee with completed copy of GP-14, along with the completed data from Attachment 2. Ensure examinee has access to Technical Specifications, TRM, and 001-18.
- 3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
Special Instructions Obtain current revision of GP-14, Attachment 2, Reactor Vessel Water Level Channel Checks and fill in the following data. The filled in Attachment 2 will be provided to the JPM performer.
Page 1 of 4 Item 1 190 Item 2 195 Item 3 175 Item 4 180 Item 5 Item 6 Page 2 of 4 Item 1 190 Item 2 185 Item 3 165 Item 4 175 ItemS Item 6 Page 3 of 4 Item 1 195 Item 2 185 Item 3 170 Item 4 180 Item 5 Item 6 Item 7 +125 Item 8 +150 LOT-ADM-JP-307-C01 Page 2 of 13 REV. 00
Evaluate Level Instrument Operability Read the following to the JPM Performer TASK CONDITIONS:
Unit Two is operating in Extended Single Recirculation Loop Operation per GP-14.
Recirculation Loop 2A is out of service.
INITIATING CUE: n.
ROandSRO: \
You are directed to perform channel checks fyr reactor vessel water level instruments using the data recorded on GP-14, Attachment 2 and determine if channel checks are satisfactory.
SRO ONLY:
You are directed to perform the SRO Review of the completed GP-14, Attachment 2.
Determine IfTech-Spec acceptance criteria is satisfied. Determine required Tech Spec action(s*for any Instrumentation that is Inoperable. I /
/
L LOT-ADM-JP-307-CO1 Page 3 of 13 REV. 00
Evaluate Level Instrument Operability PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Ii NOTE: Sequence of the following actions is NOT critical.
START TIME:
Step 1 Review data for Level Instruments N024A-i-i, N024B-i-1 and determine acceptance criteria are met.
Determined that channel check is satisfactory for N024A-1-1 and N024B-1-1.
SAT/UNSAT*
Step 2 Review data for Level Instruments N025A-1-1, N025B-1-1 and determine acceptance criteria are met.
Determined that channel check-i&s actory for N025A-1-1 and N025B-1-1.
SATIU N SAT*
Step 3 Review data for Level Instruments N03 iA-i, N031 C-i and determine acceptance criteria are met.
Determined that channel check is satisfactory for NO31A-1 and NO3IC-1.
SAT/UNSAT*
Step 4 Review data for Level Instruments N031 B-i, N031 D-1 and determine acceptance criteria are NOT met.
Determined that NO3IB-1 is reading below TS/Oper Limit and channel check criteria is not met.
CRITICAL STEP ** SAT/UNSAT*
LOT-ADM-JP-307-CO1 Page 4 of 13 REV. 00
Evaluate Level Instrument Operability Step 5 Review data for Level Instruments N024A-2, N024B-2 and determine acceptance criteria are met.
Determined that channel check is satisfactoiy for N024A-2 and N024B-2.
SATIU NSAT*
Step 6 Review data for Level Instruments N025A-2, N025B-2 and determine acceptance criteria are met.
Determined that channel check is satisfactory for N025A-2 and N025B-2.
SAT/U NSAT*
Step 7 Review data for Level Instruments N036-1, N 037-1 and determine acceptance criteria is met.
Determined that channel check is satisfactory for N036-1 and N037-1.
SATIU NSAT*
fI NOTE: Steps 8 through 11 are SRO ONLY.
Step 8 Declare Level Instrument NO3IB-1 Inoperable.
Level Instrument N03 lB-I is declared Inoperable.
CRITICAL STEP ** SATIUNSAT*
Step 9Determine NO31B-1 iquiredto comply witLCO.3.5.1 for Functions 1,a, 2.a, 3.a, 4.a and 5.a andLCO 3.3.5.2, Function 1 cL Determined that NO31B-1 is required to comply with LCO 3.3.5.1 for Functions 1.a, 2.a, 3.a, 4.a and 5.a and LCO 3.3.5.2, Function 1 SAT/U N SAT*
LOT-ADM-JP-307-C01 Page 5 of 13 REV. 00
Evaluate Level Instrument OperabIity Step 10 Determine LCD 3.3.5.1 and LCD 3.3.5.2, Action A requires entering Condition referenced by Table immediately (3.3.5.1 Condition B for Function 1.a, 2.a, and 3.a, and Condition E for Functions 4.a, and 5.a, 3.3.5.2 Condition B for Function 1)
Determine LCO 3.3.5.1 and LCD 3.3.5.2, Action A requires entering Condition referenced by Table immediately (3.3.5.1 Condition B for Function 1. a, 2. a, and 3. a, and Condition E for Functions 4.a, and 5.a, 3.3.5.2 Condition B for Function 1)
SATIUNSAT*
NOTE: LCD 3.3.5.1, Action BI and B2 are not required. LCD 3.3.5.1 Action El is not required; LCD 3.3.5.2, Action Bl is not required.
LCD 3.3.5.1, Actions B3 and E2 are required (the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time applies to Action E2); and LCD 3.3.5.2, Action B2 is required.
It is critical the examinee determines the channel must be placed in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Step 11 Determine LCO 3.3.5.1, Condition B and LCD 3.3.5.2, Condition B requires placing the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and Condition E requires placing the channel in trip in 8 days.
Determines the channel must be placed in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CRITICAL STEP ** SAT/UNSAT*
COMPLETION TIME:
TERMINATING CUE: When the examinee has completed re\new of GP-l4, attachment 2 and Technical Specifications, this JPM is complete.
Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-307-C0l Page 6 of 13 REV. 00
Evaluate Level Instrument Operability RELATED TASKS:
202009B1 01 Perform actions for extended operation with only one reactor recirculation loop in service per GP-14.
K/A REFERENCE AND IMPORTANCE RATING:
GEN2.1.37 4.3/4.6 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
REFERENCES:
GP-14 Technical Specifications TRM 01-18 TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin - Conduct of Operations REASON FOR REVISION:
New JPM for 2012 NRC Exam.
LOT-ADM-JP-307-C01 Page 7 of 13 REV. 00
Evaluate Level Instrument Operability Validation Time: 30 Minutes Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee:_______________________________
JPM: Pass FaH Remedial Training Required: Yes No Comments:
Comments reviewed with performer Evaluator Signature: Date:__________
LOT-ADM-JP-307-C01 Page 8 of 13 REV. 00
TASK CONDITIONS:
Unit Two is operating in Extended Single Recirculation Loop Operation per GP-14.
Recirculation Loop 2A is out of service.
INITIATING CUE:
RO and SRO:
You are directed to perform channel checks for reactor vessel water level instruments using the data recorded on GP-14, Attachment 2 and determine if channel checks are satisfactory.
SRO ONLY:
You are directed to perform the SRO Review of the completed GP-14, Attachment 2.
Determine if Tech Spec acceptance criteria is satisfied. Determine required Tech Spec action(s) for any instrumentation that is Inoperable.
Page 9 of 13
ATTACHMENT 2 Page 1 of 4 Reactor Vessel Water Level Channel Checks ITEM TS/OPER WED THU FRI SHIFT CHECKLIST NOTES TIME SAT SUN MON TUE NO. LIMITS RECORD Reactor Vessel Water Level 1830-0030 168-196 190 1
B2 1 -LTM-N024A-1 -1 RECORD Reactor Vessel Water Level 1830-0030 168-196 195 2
B21 -LTM-N024B-1 -1 RECORD Reactor Vessel Water Level 1830-0030 168-196 175.
3 B21 -LTM-N025A-1 -1 RECORD Reactor Vessel Water Level 1830-0030 168-196 180.
4 B2 1 -LTM-N0258-1 -1 COMPARE Items 1 and 2; should be within 10 inches of each other. Technical Specification Tables 3.3.6.1-1, Functions within 10 5 C 1830-0030 l.a and 5.g, SR 3.3.6.1.1; and 3.3.6.2-1, inches Function 1, SR 3.3.6.2.1 COMPARE Items 3 and 4, should be within 10 inches of each other. Technical Specification Tables 3.3.61-1, Functions within 10 6 C 1830-0030 l.a and 5.g, SR 3.3.6.1.1; and 3.3.6.2-1, inches Function 1, SR 3.3.6.2.1 OGP-14 Rev. 17 Page 17of21
ATTACHMENT 2 Page 2 of 4 Reactor Vessel Water Level Channel Checks ITEM TS/O PER FRI SHIFT CHECKLIST NOTES TIME SAT SUN MON TUE WED THU LIMITS RECORD Reactor Vessel Water Level 1830-0030 168-196 190 1
B21-LTM-NO31A-1 RECORD Reactor Vessel Water Level 1830-0030 168-196 185 2
B21-LTM-NO3IC-1 RECORD Reactor Vessel Water Level 1830-0030 168-19165 B21-LTM-NO31B-1 RECORD Reactor Vessel Water Level 1830-0030 168-1 96 175 B21-LTM-NO31D-1 COMPARE Items 1 and 2; should be within 7 inches of each other. Technical Specification Tables 3.35.1-1, Functions within 7 /
5 C 1830-0030 la, 2.a, 3.a, 4.a, 5.a, SR 3.3.5.11; and inches 3.3.5.2-1, Function 1, SR 3.3.5.2.1.
COMPARE Items 3 and 4; should be within 7 inches of each other. Technical Specification Tables 3.3.5.1-1, Functions within 7 6 C 1830-0030 1.a, 2.a, 3.a, 4.a, 5.a, SR 3.3.5.1.1: and inches 3.3.5.2-1, Function 1, SR 3.3.5.2.1.
OGP-14 Rev. 17 Page 18of21
ATTACHMENT 2 Page 3 of 4 Reactor Vessel Water Level Channel Checks ITEM TS/OPER SHIFT CHECKLIST NOTES TIME SAT SUN MON TUE WED THU FRI NO. LIMITS RECORD Reactor Vessel Water Level -
1830-0030 165-195 195 1
ATWS B21-LTM-N024A-2 RECORD Reactor Vessel Water Level -
1830-0030 165-195 185 2
ATWS B21-LTM-N024B-2 RECORD Reactor Vessel Water Level -
1830-0030 165-195 170 3
ATWS B21 -LTM-N025A-2 RECORD Reactor Vessel Water Level -
1830-0030 165-195 180.
4 ATWS B21-LTM-N025B-2 COMPARE Items 1 and 2; should be within within 10 5 10 inches of each other. Technical C 1830-0030 JFes Specification SR 3.3.4.1.1 COMPARE Items 3 and 4; should be within 10 6 10 inches of each other. Technical C 1830-0030 inches 7
Specification SR 3.3.4.1.1 RECORD Reactor Vessel Shroud Level B21 -LTM-N036-1. Technical Specification B 1830-0030 Note A 125 7
Table 3.3.5.1-1, Function 2.e, SR 3.3.5.1.1 RECORD Reactor Vessel Shroud Level B2 1 -LTM-N037-1. Technical Specification B 1830-0030 NoteA 150 8
Table 3.3.5.1-1, Function 2.e, SR 3.3.5.1.1 9 SRO Review of Attachment 2 complete 1830-0030 Week Beginning Page of OGP-1 4 Rev. 17 Page 19 of 21
ATTACHMENT 2 Page 4 of 4 Reactor Vessel Water Level Channel Checks NOTES A. The channel check is satisfied if the instrument in the idle loop is relatively steady and is indicating above 0 inches OR if the instrument in the operating loop is oscillating with a large peak to peak value and is above 0 inches. Reactor pressure, core flow and recirculation loop flow generates a large error in the indication provided by this instrument. The use of the instruments for level indication and for performance of its safety function is restricted to conditions in which both reactor recirculation pumps have tripped.
B. The B21-LTM-N037-1 is associated with Recirculation Loop B and the B21-LTM-N036-1 is associated with Recirculation Loop A.
C. Record the difference between the instruments.
OGP-1 4 Rev. 17 I Page 20 of 21
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC EC LESSON TITLE: Develop a Clearance Boundary RBCCW Pump 2C.
LESSON NUMBER: LOT-ADM-JP-201 -E04 REVISION NO: 02 Prepared By: Dan Arhelger Nuclear Operations Instructor Date Concurred By Nuclear Operations Instructor Date Validated By:
Operations Department Representative Date Approved By:
Facility Representative I Date
\ I Th
oundary R-SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 2. An answer key for the RO task is provided to the evaluator.
- 3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021 Appendix E, or similar to the trainee.
- 4. If desired, the evaluator may provide the examinee with a copy of OPS-NGGC-1 301, 20P-21, and the referenced prints.
- 5. The evaluator should have available copies of prints D-02538 Sheets I & 2 and LL-09241 sheets 8 & 24 to support performance of JPM, or perform JPM in a location where a print machine is available.
- 6. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
- 7. Provide ENCLOSURE 1 to the RO examinee.
- 8. Provide ENCLOSURE 2 to the SRO examinee.
LOT-ADM-JP-201-E04 Page 2 of 14 REV. 02
Develop a Clearance Boundary - RBCCW Pump 20 NOTE: Separate task conditions are included for RO and SRO candidates Read the following to the JPM performers RO 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 20 under clearance ftr pump packing replacement.
- 3. RBCCW Pumps 2A and 2B will remain running.
RO INITIATING CUE:
The WCC SRO directs you to propose a Clearance Boundary for RBCCW Pump 20 by completing Attachment 4 of OPS-NGGC-1 301, Equipment Clearance procedure.
SRO TASK CONDITIONS:
- 4. You are an SRO in the Work Control Center. PASSPORT (Equipment Tag Out) is not available for use. No historical clearances are available for review.
- 5. An RO has prepared a Clearance to place RBCCW Pump 20 under clearance for pump packing replacement.
- 6. RBCCW Pumps 2A and 2B will remain running.
SRO INITIATING CUE:
The WCC SRO directs you to review the prepared Clearance Boundary for RBCCW Pump 2C lAW the requirements of OPS-NGGC-1 301, Equipment Clearance procedure.
LOT-ADM-JP-201-E04 Page 3 of 14 REV. 02
Develop a Clearance Boundary - RBCCW Pump 2C LOT-ADM-JP-201 -E04 Page 4 of 14 REV. 02
Develop a Clearance Boundary RBCCW Pump 2C RO ANSWER KEY ATTACHMENT 4 Page 1 of 1 EQUIPMENT CLEARANCE CHECKLIST Clearance No. N/A Page of Checklist Type: LiHang LiLift EBoundary Change (Check one)
INT Passport Short Name (PRINT) INT Passport Short Name (PRINT)
Independent/Concurrent Verificaflon Required? YES / NO If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed By Verified By*
1 N/A No Tag j2-RCC- OFF or RBCCW Pump 2C or CIT (CS-449 HUNG Control Switch OPEN or RBCCW Pump 2C 2 N/A RED f 2-2XE-EA7-52 OFF Circuit Breaker 3 N/A I RED 2-RCC- CLOSED RBCCW Pump C **
V34 Discharge Valve 3 N/A RED 2-RCC- CLOSED RBCCW Pump C **
V30 Suction Valve 4 N/A No Tag 2-RCC- OPEN RBCCW Pump C Suction or RED V128 Drain Valve 4 N/A No Tag 2-RCC- OPEN RBCCW Pump C Discharge or RED V129 Drain Valve 4 N/A No Tag 2-RCC- OPEN RBCCW Pump C Casing **
, or RED, V301 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 iaIve, suction valve, at least one drain valve, and vent valve.
LOT-ADM-JP-201-E04 Page 5 of 14 REV. 02
Develop a Clearance Boundary - RBCCW Pump 2C PERFORMANCE CHECKLIST NOTE: If desirec the examiner may ProvideacoPYOPSNGGCl Oltothej 3
START TIME NOTE: If desired, the examiner may provide a copy of the required prints to the examinee (D-02538, Sheets I & 2, LL-9241, Sheets 8 & 24) and 20P-21 Iineups.
NOTE: CITs can have position OFF or In-Place I HUNG Step I - Obtain copies of required prints (D-02538, Sheets 1 & 2, LL-09241, Sheets 8 & 24).
Drawings D-02538, Sheets I & 2, LL-09241, Sheets 8 & 24 obtained.
SATIUNSAT*
Step 2 - 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 breaker 2XE Compt EA7 should be RED tagged to OFF.
Determine 2XE Compt EA 7 should be RED tagged to OFF.
CRITICAL STEP ** SAT/UNSAT*
LOT-ADM-JP-201-E04 Page 6 of 14 REV. 02
Develop a Clearance Boundary RBCCW Pump 20 NOTE: Sequence of suction or discharge valve closing is not critical so long as the pump motor is de-energized.
Step 4 - Identify discharge valve 2-RCC-V34 should be RED tagged closed.
Determine 2-RCC-V34 should be RED tagged closed.
CRITICAL STEP ** SATIUNSAT*
Step 5 - Identify suction valve 2-RCC-V30 should be RED tagged closed.
Determine 2-RCC-V30 should be RED tagged closed.
CRITICAL STEP ** SATIUNSAT*
NOTE: Either 2-RCC-V128 or 2-RCC-V129 is critical. Both are not required to meet critical task standards.
NOTE: Sequence of drain or vent valve opening is not critical.
Step 6 - Identify drain valve 2-RCC-V128 should be open.
Determine 2-RCC-V1 28 should be open.
CRITICAL STEP ** SATIUNSAT*
Step 7 - Identify drain valve 2-RCC-V129 should be open.
Determine 2-RCC-V1 29 should be open.
CRITICAL STEP ** SATIUNSAT*
Step 8 - Identify vent valve 2-RCC-V301 should be open.
Determine 2-RCC-V301 should be open.
CRITICAL STEP ** SAT/UNSAT*
LOT-ADM-JP-201-E04 Page 7 of 14 REV. 02
Develop a Clearance Boundary RBCCW Pu Step 9 Submit proposed boundary to WCC SRO.
Proposed boundaiy submitted to WCC SRO, SATIU NSAT*
TERMINATING CUE: When the proposed boundary has beubiitt,theRO NRO portion of this JPM is complete.
RO TIME COMPLETED Comments required for any step evaluated as UNSAT.
NOTE: Steps 10 and 11 are SRO ONLY.
Step 10- Identify pump isolation valves (discharge valve 2-RCC-V34 and suction valve 2-RCC-V30) closed prior to removing the power source to the pump.
Identify improper sequence of steps (discharge valve 2-RCC-V34 and suction valve 2-RCC-V30 closed prior to opening pump breaker).
CRITICAL STEP ** SATIUNSAT*
Step 11 - Identify vent valve 2-RCC-V301 not provided on clearance.
Identify lack of vent path (2-RCC-V301 should be identified open on clearance).
CRITICAL STEP ** SATIUNSAT*
SRO TIME COMPLETED Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-201-E04 Page 8 of 14 REV. 02
Develop a Clearance Boundary - RBCCW Pump 2C RELATED TASKS:
299020B301, Develop A Clearance per 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 20P-21 D-02538, Sheets 1 & 2 LL-09241, Sheets 8 & 24 TOOLS AND EQUIPMENT:
Referenced prints and procedures.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin - Equipment Control REASON FOR REVISION:
Revised to support HLC 2012 NRC exam. Divided into RO and SRO tasks conditions and initiating cues. Changed NGGC-1 301, Attachment 4 to latest revision (rev 29). Corrected JPM number in footer (ADM vs OJT). Added signature page.
LOT-ADM-JP-201-E04 Page 9 of 14 REV. 02
Develop a Clearance Boundary RBCCW Pump 2C Validation Time: 20 Minutes (approximate).
Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No (Reference TAP-41 1 for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature: Date:__________
LOT-ADM-JP-201-E04 Page 10 of 14 REV. 02
ENCLOSURE I - RO RO 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.
RO INITIATING CUE:
The WCC SRO directs you to propose a Clearance Boundary for RBCCW Pump 2C by completing Attachment 4 of OPS-NGGC-1 301, Equipment Clearance procedure.
ENCLOSURE 1 - RO Page 11 of 14
ENCLOSURE I - RO ATTACHMENT 4 Page 1 of 1 EQUIPMENT CLEARANCE CHECKLIST Clearance No. N/A Page of Checklist Type: LiHang LiLift ElBoundary Change (Check one)
INT Passport Short Name (PRINT) INT Passport Short Name (PRINT)
Independent/Concurrent Verification Required? YES I NO If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed Verified By*
By N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Continued Y/N Vital Record until information is entered into the computer program.
ENCLOSURE 1 - RO Page 12 of 14
ENCLOSURE 2 -SRO SRO TASK CONDITIONS:
- 1. You are an SRO in the Work Control Center. PASSPORT (Equipment Tag Out) is not available for use. No historical clearances are available for review.
- 2. An RO has prepared a Clearance to place RBCCW Pump 2C under clearance for pump packing replacement.
- 3. RBCCW Pumps 2A and 28 will remain running.
SRO INITIATING CUE:
The WCC SRO directs you to review the prepared Clearance Boundary for RBCCW Pump 2C lAW the requirements of OPS-NGGC-1 301, Equipment Clearance procedure.
ENCLOSURE 2- SRO Page 13 of 14
ENCLOSURE 2 SRO -
ATTACHMENT 4 Page 1 of 1 EQUIPMENT CLEARANCE CHECKLIST Clearance No. N/A Page of Checklist Type: EjHang LiLift LiBoundary Change (Check one)
INT Passport Short Name (PRINT) INT Passport Short Name (PRINT)
Independent/Concurrent Verification Required? YES / NO If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed Verified By*
By RBCCW Pump C 2-RCC-1 N/A RED CLOSED Discharge Valve V34 RBCCW Pump C 2-RCC-1 N/A RED CLOSED Suction Valve V30 RBCCW Pump 2C No Tag 2-RCC- OFF or 2 N/A Control Switch or CIT CS-449 HUNG RBCCW Pump 2C RED 2-2XE- OPEN or 3 N/A Circuit Breaker EA7-52 OFF RBCCW Pump C SuctiDn No Tag 2-RCC-4 N/A OPEN Drain Valve or RED V128 RBCCW Pump C Discharge No Tag 2-RCC-4 N/A OPEN Drain Valve or RED V129 Continued Y/N Vital Record until information is entered into the computer program.
ENCLOSURE 2 - SRO Page 14 of 14
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC RC LESSON TITLE: Determine Total Dose For ALARA.
LESSON NUMBER: LOT-ADM-JP-1 02-AD 1 REVISION NO: 01 Prepared By: Dan Arhelger Nuclear Operations Instructor Date Concurred By Nuclear Operations Instructor Date Validated By:
Operations Department Representative Date Approved By:
Facility Representative I Date
Determine Total Dose for ALARA SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 2. A calculator may be given to Trainee.
- 3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
- 4. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
LOT-ADM-JP-1 02-AOl Page 2 of 7 REV. 01
Determine Total Dose for ALARA Read the following to the JPM performer TASK CONDITIONS:
A task is to be performed in the Unit Two Reactor Building. There are three paths to arrive at the job site as detailed below:
R Path I oee Path 2 0ee Path 3 8 mr/hr Transient time in 8 mr/hr Transient time in 8 mr/hr Transient time in the Unit 2 Turbine the Unit I Turbine the Unit 2 Turbine Building is Building is Building is 6 minutes 3 minutes 6 minutes 9 mr/hr Transient time in 8 mr/hr Transient time in 9 mr/hr Transient time in the Unit 2 Reactor the Unit 2 Turbine Unit 2 Reactor Building is Building is Building is 3 minutes 3 minutes 3 minutes 1 mr/hr Changes into PCs 9 mr/hr Transient time in 1 mr/hr Rides elevator in to go into the Unit 2 Reactor Unit 2 Reactor contaminated area Building is Building for in Unit 2 Reactor 6 minutes 6 minutes Building (Takes 6 minutes 1 mr/hr Transient time 9 mr/hr Transient time in through Arrives at job site Unit 2 Reactor contaminated area Building is is 3 minutes 3 minutes 1 mr/hr Changes out of PCs to exit Arrives at job site contaminated area in Unit 2 Reactor Building (Takes 6 minutes)
Arrives at job site Total Total Total Dose Dose Dose INITIATING CUE:
Determine the dose received for each path and which path maintains dose ALARA.
LOT-ADM-JP-1 02-AOl Paqe3of7 REV. 01
Determine Total Dose for ALARA PERFORMANCE CHECKLIST START TIME:
Step 1 Determine dose for Path 1 is 1.5 mr. (8 x 0.1 + 9 x 0.05 + 1 x 0.1 + 1 x 0.05 + 1 x 0.1)
Dose for Path 1 determined to be 1.5 mr.
CRITICAL STEP ** SAT/UNSAT*
Step 2- Determine dose for Path 2 is 1.7 mr. (8 x 0.05 + 8 x 0.05 + 9 x 0.1)
Dose for Path 2 determined to be 1.7 mr.
CRITICAL STEP ** SATIUNSAT*
Step 3-Determine dose for Path 3 is 1.8 mr. (8 X 0.1 + 9 X 005 + 1 X 0.1 + 9 X 0.05)
Dose for Path 3 determined to be 1.8 mr.
CRITICAL STEP ** SATIUNSAT*
Step 4 Determine Path 1 provides lowest overall dose.
Determined Path I provides lowest overall dose.
CRITICAL STEP **
SAT/U NSAT*
COMPLETION TIME:
TERMINATING CUE: When dose for the three Paths is determined, and Path is determined to provide the lowest dose, this JPM is complete.
Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-102-A01 Page 4 of 7 REV. 01
Determine Total Dose for ALARA RELATED TASKS:
None K/A REFERENCE AND IMPORTANCE RATING:
Gen 2.3.7 3.5/3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
REFERENCES:
None TOOLS AND EQUIPMENT:
Examinee may use calculator.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin Radiation Control REASON FOR REVISION:
Revised to support HLC 2012 NRC Exam. Reformatted for consistency. Added signature page.
LOT-ADM-JP-1 02-AOl Page 5 of 7 REV. 01
Determine Total Dose for ALARA Validation Time: 10 Minutes Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 0 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee:________________________________________
JPM: Pass Fail Remedial Training Required: Yes No (Reference TAP-41 1 for evaluation guidance) za Comments:
Comments reviewed with Student Evaluator Signature: Date:___________
LOT-ADM-JP-102-A01 Page 6 of 7 REV. 01
TASK CONDITIONS:
A task is to be performed in the Unit Two Reactor Building. There are three paths to arrive at the job site as detailed below:
Path I Path 2 Path 3 8 mr/hr Transient time in 8 mr/hr Transient time in 8 mr/hr Transient time in the Unit 2 Turbine the Unit I Turbine the Unit 2 Turbine Building Building Building 6 minutes 3 minutes 6 minutes 9 mr/hr Transient time in 8 mr/hr Transient time in 9 mr/hr Transient time in the Unit 2 Reactor the Unit 2 Turbine Unit 2 Reactor Building Building Building 3 minutes 3 mnutes 3 minutes 1 mr/hr Changes into PC5 9 mr/hr Transient time in 1 mr/hr Rides elevator in to go into the Unit 2 Reactor Unit 2 Reactor contaminated area Building Building for in Unit 2 Reactor 6 minutes 6 minutes Building (Takes 6 minutes) 1 mr/hr Transient time 9 mr/hr Transient time in through Arrives at job site Unit 2 Reactor contaminated area Building is 3 minutes 3 minutes 1 mr/hr Changes out of PCs to exit Arrives at job site contaminated area in Unit 2 Reactor Building (Takes 6 minutes)
Arrives at job site Total Total Total Dose Dose Dose INITIATING CUE:
Determine the dose received for each path and which path maintains dose ALARA.
Page 7 of 7
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC EP LESSON TITLE: Determine Off-Site Release Per PEP-03.4.7 LESSON NUMBER: SOT-ADM-J P-301 -A0 1 REVISION NO: 03 Prepared By: Dan Arhelger Nuclear Operations Instructor Date Concurred By Nuclear Operations Instructor Date Validated By:
Operations Department Representative Date Approved By:
Facility Representative I Date
\
Determine Off-Site Release per PEP-03.4.7 SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 3. The applicable procedure section WILL be provided to the trainee.
- 4. An answer key is provided for the evaluator.
- 5. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
- 6. Ensure Saved case files (dates with first Names) ARE DELETED prior to administering JPM to successive candidates.
7, Ensure any case files saved by candidates have candidates first name attached for ease of identification (this is in addition to PEP-03.4.7 id. requirements).
- 8. Provide filled out OPEP-03.4.7, Attachment 5 of this JPM to Trainee following INITIATING CUE delivery, with the CURRENT TIME (JPM START TIME ) AND minus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time hand written on form.
- 9. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
LOT-ADM-JP-201-D13 Page 2 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 Read the following to the JPM Performer TASK CONDITIONS:
- 1. A General Emergency has been declared due to a steam line break in the Unit 1 Turbine Building which is at a positive pressure.
- 2. Main Steam Line B MSIVs have failed to close and there are indications of fuel failure.
- 3. The operating crew is currently executing the RRCP and RVCP with one CRD pump providing the only RPV injection source.
- 4. The Unit One reactor was shutdown 30 minutes ago.
- 6. There is no rain on plant site and Attachment 5 of PEP-3.4.7 has been filled out to support Actual Observation MET data entry.
INITIATING CUE:
You are directed by the Shift Manager (SEC) to:
- 1. Perform an initial dose calculation per PEP 03.4.7, Automation of Off-Site Dose Projection procedure using default data where required.
- 2. Determine whether projected TEDE dose at the Site Boundary exceeds Protective Action Guides (PAG5) and the Total Activity Released.
- 3. Notify the Shift Manager (SEC) of the results of your projection.
LOT-ADM-JP-201-D13 Page 3 of 14 REV. 03
CHARACTERISTIC Core Uncovered Drywell Hih Rane Radiation Momtor ReacIins (RihfJ Effective Filtration Release Heiciht Release Durahan Shutdown TIME Time (1) lost! 2i Returned Yes / No Ground Elevated Anticipated Length oTime Date ATTACHMENT 5 cr r
Page 1 of 1 Data Sheet for Dose Projection Inputs go STARTT/
3 NO mm 5cur go CD CD D
II CD Time c mm go 0
z I
Met Dma Wind Speed Cl) Cr)
Lower CD Met Data Direcuon Lower 5 75 m CD CD E. (1)
Stability Class CD Seabreeze Yes No O NO -o m CD
-< -D m
CD 1
f OPEP-03 4.7 Rev. 21 Page 26 of 31
Determine Off-Site Release per PEP-03.4.7 PERFORMANCE CHECKLIST IIN0TE: Sequence is assumed unless otherwise denoted.
START TIME (Write this time for the current time and subtract 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for previous time prior to giving Attachment 5 to Trainee)
NOTE: Trainee should calculate Shutdown and Core Uncovered times from the START TIME provided on Attachment 5.
Step 1 - Obtain a current revision of PEP-03.4.7.
Current Revision of PEP-03. 4.7 obtained.
SATIU NSAT*
Step 2 Access RASCAL 3.0.5 program.
Start the RASCAL program from the desktop screen by selecting:
Start>Programs>Emergency Preparedness >RASCAL>RASCAL 3.0.5 Shell.
SAT/U N SAT*
Step 3 Selects the OK button (lower right) on the screen to initiate projection process.
Selects 0K button (lower right) to initiate projection process.
SATIUNSAT*
NOTE: SRO responsibilities are limited to providing dose projections using the following source terms: 1) Containment Rad Monitor; 2) Time Core is uncovered 3) Spent Fuel Step 4 Selects the model to be used (STDose).
Selects the Source Term to Dose model.
SATIUNSAT*
LOT-ADM-JP-201-D13 Paqe 5 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 OTE: A / mark will appear in front of each Step Location when the step is complete.
Step 5 Selects EVENT TYPE and chooses NUCLEAR POWER PLANT event type selection and proceeds with the case development by selecting OK in the lower right corner of the Event Type Selection window.
NUCLEAR POWER PLANT event type selected.
SATIU NSAT*
NOTE: Trainee should verify Plant Parameters in the program match PEP-03.4.7 default parameters.
Step 6 Selects EVENT LOCATION and chooses Brunswick Unit 1, and then clicking on OK button (lower right) on the screen.
Brunswick Unit I event location selected.
SATIUNSAT*
Step 7Selects SOURCE TERM. and chooses TIME CORE UNCOVERED and selects OK.
TIME CORE UNCOVERED selected as Source Term.
SATIUNSAT*
Step 8 Enters the date/time the reactor was shut down.
Enters todays date and TIME START minus 30 minutes for time reactor was shutdown.
SAT/U NSAT*
Step 9 Selects YES Core uncovered and enters date/time the Core was uncovered.
Core uncovered selected YES and enters todays date and TIME START minus 15 minutes for time uncovered.
SATIUNSAT*
LOT-ADM-JP-201-D13 PaQe 6 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 PROMPT: Level remains below TAR Step 10 Selects NO for Core recovered and selects OK.
Core recovered selected NO and selects OK.
SATIU NSAT*
Step 11Selects Release Path and chooses Bypass secondary containment and selects OK.
Bypass secondary containment release path selected.
SATIUNSAT*
Step 12 Selects not an isolated stack, enters 0 meters for release height, and selects YES for Building Wake effects.
Not an isolated stack selected at 0 meters and Building Wake YES selected SATIUNSAT*
Step 13 Verifies/enters current date and time the core was uncovered.
Core uncovered date and time verified at TIME START minus 15 minutes SATIU NSAT*
PROMPT Inform Trainee to use the default leak rate.
Step 14 Under Event selects Leak Rate Under Event Setting enters the estimated flow for the coolant bypassing containment the default is 100 gal/mm.
Leak Rate with Leak Rate setting of 100 gal/mm SATIU NSAT*
LOT-ADM-JP-201-D13 Pace 7 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 PROMPT Inform Trainee the Turbine Building is positive.
Step 15 Under Event selects Filters Under Event Setting
- selects OFF selects OK.
Filters OFF and OK selected SATIU N SAT*
Step 16Selects Meteorology and chooses ACTUAL OBSERVATION AND FORECASTS and selects CREATE NEW.
Create New under Actual Obseivation and Forecasts selected for Meteorology.
SATIU NSAT*
NOTE: The Minimum Met data required for dose projection model is wind speed and direction. Air Temperature, Air Pressure, and Dew Point are all OPTIONAL.
NOTE: Time entered for MET data must be before release start time. When Calculate Dose is performed, candidate will be prompted to adjust this time if input was incorrect.
PROMPT: Inform Trainee that it is not raining.
Step 17 Selects ENTER DATA and inputs the Attachment 5 data o Selects OBS for observed data o Date/Time of met data o Direction From in degrees. Use lower direction if available.
o Speed in mph. Use lower Wind Speed if available.
o Stability class (Using dropdown listing, select determined classification).
o Precipitation (Using dropdown listing, select condition)
Met data entered with correct date and time at START TIME.
SATIUNSAT*
Ii NOTE: Trainee may elect to input both current & 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> earlier MET data.
Page 8 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 NOTE: The Name is the current date and time. (Example: 0213101500). This allows for repeated update of new met data saved under different names for future retrieval.
PROMPT: Have Trainee add their first name to the end (for exam retrieval) i.e. 0213101500TED First Names will follow all case file names for the remainder.
Step 18 Selects the SAVE AND PROCESS DATA button on the screen.
Enters a name for the met data set just entered and selects Return.
SAVE AND PROCESS DATA selected with todays date and START TIME as the Name and selects Return.
SATIUNSAT*
Step 19 Ensures the saved file is highlighted and selects OK.
Saved file highlighted and selects OK.
SATIU NSAT*
Step 20Selects Calculate Doses and specifies the options and descriptions for this set of calculations.
Calculate Doses selected with close in + out 10 miles with default for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> duration.
SATIU NSAT*
Step 21Assigns a Case Description of BNP and the current time and selects OK.
Case Description provided as BNP + current time + first name (BNPI53OTED) and OK selected.
SAT/U N SAT*
Step 22 Determines projected TEDE dose at the Site Boundary (0.5 mile) exceeds PAGs.
TEDE dose at Site Boundary is ABOVE PAGs.
CRITICAL STEP ** SATIUNSAT*
LOT-ADM-JP-201-D13 Pacie 9 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 Step 23Determines Total activity released is 3.2E+08 Ci.
Total activity released is 3.2E+08 Ci CRITICAL STEP ** SATIUNSAT*
Step 24 Notifies Shift Manager of results.
Shift Manager notified of off-site dose projection results.
SAT/U N SAT*
TERMINATING CUE: When the offsite dose Proiection has been performed, anj informed of results, this JPM is Comments required for any step evaluated as UNSAT.
TIME STOP PaaelOofl4 REV. 03
Determine Off-Site Release per PEP-03.4.7 RELATED TASKS:
344 058 B3 02 Perform Initial Dose Projection Calculation Using Computer per PEP-03A.7 KIA REFERENCE AND IMPORTANCE RATING:
GEN 2.4.40 2.7/4.5 Knowledge of SRO responsibilities in emergency plan implementation.
REFERENCES:
OPEP-03.4.7 TOOLS AND EQUIPMENT:
Computer loaded with RASCAL.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin Emergency Procedures/Plan REASON FOR REVISION:
Revised to support HLC 2012. Reformatted and corrected minor typographical errors.
Deleted unused references.
LOT-ADM-JP-201-D13 Pacie 11 of 14 REV. 03
Determine Off-Site Release per PEP-cJ3.4.7 Time Required for Completion: 30 Minutes (approximate)
Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit:
Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee:
JPM: Pass Fail Remedial Training Required: Yes No (Reference TAP-41 1 for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature: Date:
Paael2ofl4 REV. 03
ATTACHMENT 5 Page 1 of 1 Data Sheet for Dose Projection Inputs CHARACTERISI1C TIME Core Uncovered Time (1) Iost/ (2) Returned 15 miii ago Drywell High Range Radiation Monitor Readngs (R?hr) nop mop Effective Filtration Yes I No NO Release Height Ground Eievated Release Duration Anticipated Length otTime Shutdown Date Time SC mm ago
-o Met Data Wind (a Speed CD Lower 22 C.)
Met Data Directon 0
-4, Lower /5 15 Stability Class 3 5 Seabreeze Yes / No ND -________
OPEPO34J Rev 21 Page 26 of 31
TASK CONDITIONS:
- 1. A General Emergency has been declared due to a steam line break in the Unit 1 Turbine Building which is at a positive pressure.
- 2. Main Steam Line B MSIV5 have failed to close and there are indications of fuel failure.
- 3. The operating crew is currently executing the RRCP and RVCP with one CRD pump providing the only RPV injection source.
- 5. The Unit One reactor was shutdown 30 minutes ago.
- 6. There is no rain on plant site and Attachment 5 of PEP-3.4.7 has been filled out to support Actual Observation MET data entry.
INITIATING CUE:
You are directed by the Shift Manager (SEC) to:
- 1. Perform an initial dose calculation per PEP 03.4.7, Automation of Off-Site Dose Projection procedure using default data where required.
- 2. Determine whether projected TEDE dose at the Site Boundary exceeds Protective Action Guides (PAGs) and the Total Activity Released.
- 3. Notify the Shift Manager (SEC) of the results of your projection.
TOTAL ACTIVITY RELEASED SITE BOUNDARY DOSE (Curies) (Circle Choice)