ML072960565
| ML072960565 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/31/2007 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-324/07-301, 50-325/07-301, ADMIN A-1-A 2007-301, 50-324/07-301, 50-325/07-301 | |
| Download: ML072960565 (210) | |
Text
{{#Wiki_filter:NRC RO ADMIN A-1-A Page 1 of 8 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN RO NRC JPM A-1-A TITLE: Hand Calculation Of APRM GAFs Per PT-01.8C.
't ) NRC RO ADMIN A-1-A Page 2 of 8 SIMULATOR NOTES: IC-189 EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Validation time: 15 minutes.
SF Read the following to trainee. TASK CONDITIONS:
- 1. Unit Two (2) is performing a startup following refueling. GP-03 is being performed.
- 2. Plant conditions:
Reactor pressure 929 psig Mode Switch Start/Hot Stby Reactor power must be determined as read on APRMs at H12-P608
- 3. GP-03 directs verification of APRM GAFs prior to transfer of the Mode Switch to Run.
- 4. Heat Balance on the process computer is unavailable due to low feedwater flow.
- 5. The Reactor Engineer has calculated core thermal power to be 239.7 MWt per OPT-01.80 INITIATING CUE:
You are directed to perform OPT-01.8C to calculate APRM GAFs. Determine if GAFs are acceptable for transferring the Mode Switch to Run, or state any action(s) required prior to transferring the Mode Switch.
NRC RO ADMIN A-1-A Page 3 of 8 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments. Step 1 - Obtain a current revision of OPT-01.8C. Current Revision of OPT-01.BC obtained and verified, if applicable. SAT/UNSAT START TIME: Step 2 - Record the date, time and Unit on Form 1. Date, Time and Unit recorded on Form 1. SATIUNSAT Step 3 - Record the results of OPT-01.8D, Core Thermal Power Calculation, obtained from the Reactor Engineer on form 1. 239. 7 MWt Recorded. SATIUNSAT Step 4 - Calculate percent rated CTP (desired reading) by dividing 239.7 by 2923, and multiplying times 100 % , and record results on Form 1 Determines percent rated CTP is approximately B.2% (~O.1%).
** CRITICAL STEP ** SATIUNSAT
NRC RO ADMIN A-1-A Page 4 of 8 Step 5 - Obtain APRM Readings from Panel P608 and record on Form 1 APRM readings are recorded on Form 1
**CRITICAL STEP**SAT/UNSAT Step 6 - Calculate the AGAF for each APRM Channel by dividing % rated CTP by APRM reading, and record results on Form 1.
APRM AGAFs determined to be s1.00 for APRM Channels 3 and 4 APRM AGAFs determined to be >1.00 for APRM Channels 1 and 2
** CRITICAL STEP ** SAT/UNSAT
NRC RO ADMIN A-1-A Page 5 of 8 Step 7 - Determine GP-03 requires three APRM to be Operable (GAF s1.00). Determine GP-03 allows conservative GAF adjustments if required and that adjustment of APRMs 1
& 2 would be conservative. Determine the Reactor engineer should be contacted for GAF adjustments prior to turbine roll.
Determine APRMs 1 and 2 (at least 1 of 2) must be adjusted to achieve a GAF of
- S1.0 prior to transferring the Mode switch to Run.
** CRITICAL STEP ** SAT/UNSAT COMPLETION TIME:
- Comments required for any step evaluated as UNSAT.
NRC RO ADMIN A-1-A Page 6 of 8 RELATED TASKS: 2122018101, Transfer The Reactor Mode Switch To Run Per GP-03 KIA REFERENCE AND IMPORTANCE RATING: GEN 2.1.33 3.4/
4.0 REFERENCES
OPT-01.8C OGP-03 TOOLS AND EQUIPMENT: Calculator. SAFETY FUNCTION (from NUREG 1123): Administrative - Conduct Of Operations
NRC RO ADMIN A-1-A Page 7 of 8 Validation Time: ~ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room SimulatorL (N/A for Admin or In-Plant JPMs) Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X Tn 1111 It lUI_Ill Mer" Tn I1R,., EVALUATION Trainee: JPM: Pass - - Fail - - II Comments: Comments reviewed with Student Evaluator Signature: Date: - - - - -
TASK CONDITIONS:
- 1. Unit Two (2) is performing a startup following refueling. GP-03 is being performed.
- 2. Plant conditions:
Reactor pressure 929 psig Mode Switch Start/Hot Stby Reactor power must be determined as read on APRMs at H12-P608
- 3. GP-03 directs verification of APRM GAFs prior to transfer of the Mode Switch to Run.
- 4. Heat Balance on the process computer is unavailable due to low feedwater flow.
- 5. The Reactor Engineer has calculated core thermal power to be 239.7 MWt per OPT-01.80 INITIATING CUE:
You are directed to perform OPT-01.8C to calculate APRM GAFs. Determine if GAFs are acceptable for transferring the Mode Switch to Run, or state any action(s) required prior to transferring the Mode Switch.
BRUNSWICK NUCLEAR PLANT c Continuous Use DATE COMPLETED _ FREQUENCY: UNIT % PWR GMWE _ A. As required by 1/2PT-01.11 with the process SUPERVISOR. _ computer not available. REASON FOR TEST (check one or more): Routine surveillance B. As deemed necessary by the Reactor Engineer. WRIWO # _ _ Other (explain) _ PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT o 1111/11111111111111111111111111111111111111111111111111 OPT-01.8C HAND CALCULATIONS OF AGAFs REVISION 13 IOPT-01.8C Rev. 13 Page 1 of 61
1.0 PURPOSE The purpose of this procedure is to establish a hand method for calculating the APRM gain adjustment factors (AGAFs) to support the requirements of 1/2PT-01.11 with the process computer not avaifable. 2.0 ACCEPTANCE CRITERIA This procedure is acceptable when the data has been collected, the calculations have been p"erformed, and the mathematics have been independently verified as correct. 3.0 SPECIAL TOOLS AND EQUIPMENT Electronic calculator 4.0 DEFINITIONS The APRM gain adjustment factor (AGAF) for the iAPRM channel is defined as: AGAFi= Desired reading for iAPRM Actual reading for iAPRM Where the desired reading is found by dividing the actual core thermal power by the rated core thermal power and then multiplying by 100 %
- The actual reading of the iAPRM is from the iAPRM in percent power.
5.0 PRECAUTIONS AND LIMITATIONS 5.1 The AGAFs are not valid if the APRM reading changes significantly from the value used to obtain the AGAFs prior to calibration. 5.2 Independent verification is required in this procedure. 6.0 PREREQUISITES 6.1 The plant should be brought to a steady state operating condition and held until the calculations are completed. 6.2 Normally the AGAFs are obtained from the process computer. This procedure is used when the process computer is out of seNice. jOPT-01.8C Rev. 13 Page 2 of 61
7.0 ANNUNCIATIONS EXPECTED None 8.0 PROCEDURE Initials 8.1 RECORD the date, time, and unit on Form 1. 8.2 PEFORM OPT-01.8D, Core Thermal Power Calculation, AND RECORD results on Form 1. 8.3 CALCULATE the percent of rated CTP (desired reading) as follows AND RECORD results on Form 1. 0/0 Rated CTP == (CTP7 Rated MWt) x 1000/0 8.4 RECORD the APRM readings from Panel 608 on Form 1. 8.5 CALCULATE the AGAF for each APRM channel as follows AND RECORD results on Form 1. AGAFi= % of rated CTP iAPRM reading in % power 8.6 INDEPENDENTLY VERIFY the AGAF calculation for each APRM is correct AND SIGN on Form 1. 9.0 DATA ANALYSIS N/A IOPT-01.8C Rev. 13 Page 3 of 61
10.0
GENERAL COMMENT
S Initials Name (Print) PT was performed by PT has been satisfactorily completed Responsible Engineering ~anager~~~~~~~~~~~~~~~~ (Signature) PT has NOT been satisfactorily completed Responsible Engineering ~anager~~~~~~~~~~~~~~~~ (Signature) Reviewed By: _~~ ~ _ (Signature) Corrective Action Required
- a. () None
- b. () WR/WO No. - - - - -
- c. () Other (Explain)
IOPT-01.8C Rev. 13 Page 4 of 61
FORM 1 Page 1 of 1 AGAF Calculation Sheet A. Date. ,~- Time- - Unit - - - - - - B. Core Thermal Power (CTP) -'-- MWt C. Percent of Rated Core Thermal Power (desired reading):
% Rated CTP = (CTP 7 Rated MWt) x 100% = % Pwr APRM APRM AGAFi Channel Reading 0/0 Pwr(D) (C/O) 1 2
3 4 AGAFi= % of rated CTP = C APRM reading in % power D Independently verify the AGAF calculations are correct. 1st verification Date - - - - Signature 2nd verification Date - - - - Signature IOPT-01.8C Rev. 13 Page 5 of 61
REVISION
SUMMARY
Revision 13 is an editorial change that incorporates the Progress Energy logo. Ref. PRR 167209. Revision 12 - Revision removes reference to 2558 MWt as rated Unit 2 thermal power. Revision supports implementation of EC 47907, Implement the Unit 2 Power Uprate Modification. Both Units are licensed to 2923 MWT. Revision 11 - Procedure revision incorporated EC 46861, Implement Extended Power Uprate for Unit 1 only. This revision increased the rated power for Unit 1 from 2558 to 2923 Mwt. Revision 10 - Procedure revision incorporates ESR 00-00442, implementation of the power range neutron monitoring system for Unit 1. The number of APRMs has been reduced from 6 to 4 on Unit 1. The Unit 1 APRM channeJ JD's changed from A-F to 1-4. Changed OPT-01.11 to 1/2PT-01.11.which now are unit specific procedures. Revision 9 - Procedure revision converts this document to the proper Microsoft Word 7.0 and the AP-005 format. This revision also incorporates the new Unit 2 rated power value to 2558 mwth due to implementation of Power Uprate. IOPT-01.8e Rev. 13 Page 6of 61
FORM 1 Page 1 of 1 AGAF Calculation Sheet A. Date r: J 0.1 Time ,jo~ Unit - - 2. - - - - B. C<;>re Thermal Power (CTP) ~_:-3_;._-_.1_-~_7..:.- MWt
- c. Percent of Rated Core Thermal Power (desired reading):
Ok Rated CTP = (CTP-=- Rated MWt) x 100 0h = 8-.. ~ 1: 6./ % Pwr APRM APRM AGAFi Channel Reading % Pwr(D) (C/O) 1 7.(, T o. I ~ I-*D'/ to J. D 9 J. o~ to 2 -t 7.'1 0, I 7b I. II 3 9'~'I ! o. J % o. ?r t- 1.0 0 4 r.. .r :t o. / -i: 0.- 91 to 0., 7J AGAFi= Ok of rated CTP = C APRM reading in °h power 0 Independently-verify the AGAF calculations are correct. 1st verification Date - - - - Signature 2nd verification Date - - - - Signature IOPT-01.8C Rev. 13 Page 5 of 61
C BRUNSWICK NUCLEAR PLANT Continuous Use PLANT OPERATING MANUAL VOLUME IV GENERAL PLANT OPERATING PROCEDURE UNIT o OGP-03 UNIT STARTUP AND SYNCHRONIZATION REVISION 67 IOGP-03 Rev. 67 Page 1 of 231
5.1 Transferring The Reactor Mode Switch To RUN (Continued) ( m pl:JmJ)s shouletN rogenexplosion may 5.1.5 INCREASE reactor power to 6-1 O°A> by withdrawing control rods, following the OGP-1 0 designated sequence, in accordance with 1(2)OP-07. NOTE: During Low Power operations, one Feedwater Flow instrument may indicate flow before the other Feedwater Flow instrument due to pipe flow characteristics. The Process computer requires both Feedwater Line flows to perform a valid Heat Balance calculation. NOTE: IF the APRM GAFs require adjustment in the following step, AND the process computer is NOT available or the process computer can not perform a Heat Balance calculation, THEN OPT-01.8C, OPT-01.8D, or 1(2)OP-09, should be used as necessary. e reduced b gain adjustments below Yo a IveAPRM readings (GAFgreater than 1.00) er is increased. Reactor Engineering shall be s ments made prior to turbine synchronization. Three APRMs are required to be RPS Trip Systems. ENSURE APRM GAFs are less than or equal to 1.00 for all operable APRMs. IOGP-03 Rev. 67 Page 7 of23 I
TASK CONDITIONS:
- 1. Unit Two (2) is performing a startup following refueling. GP-03 is being performed.
- 2. Plant conditions:
Reactor pressure 929 psig Mode Switch Start/Hot Stby Reactor power must be determined as read on APRMs at H12-P608
- 3. GP-03 directs verification of APRM GAFs prior to transfer of the Mode Switch to Run.
- 4. Heat Balance on the process computer is unavailable due to low feedwater flow.
- 5. The Reactor Engineer has calculated core thermal power to be 239.7MWt per OPT-01.80 INITIATING CUE:
You are directed to perform OPT-01.8C to calculate APRM GAFs. Determine if GAFs are acceptable for transferring the Mode Switch to Run, or state any action(s) required prior to transferring the Mode Switch.
c _ BRUNSWICK NUCLEAR PLANT
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Continuous
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s~ s . - ,
.. * ..'.,r e::,.*
I Use DATE COMPLETED _ FREQUENCY: UNIT ok PWR_ _GMWE _ A. As required by 1/2PT-01.11 with the process SUPERVISOR:- _ computer not available. REASON FOR TEST (check one or more): Routine surveillance 8. As deemed necessary by the Reactor Engineer. WRIWO# _ __ Other (explain) _ PLANT OPERATING MANUAL VOLUME X PERIODIC TEST UNIT
'0 111111111111111111111111111*111111111111111*111111111111 OPT-01.8C HAND CALCULA TIONS OF AGAFs REVISION 13 IOPT~01.8C Rev. 13 Page 1 Of61
1.0 PURPOSE The purpose of this procedure is to establish a hand method for calculating the APRM gain adjustment factors (AGAFs) to support the requirements of 1/2PT-01.11 with the process computer not available. 2.0 ACCEPTANCE CRITERIA This procedure is acceptable when the data has been collected, the calculations have been performed, and the mathematics have been independently verified as correct. 3.0 SPECIAL TOOLS AND EQUIPMENT Electronic calculator 4.0 DEFINITIONS The APRM gain adjustment factor (AGAF) for the iAPRM channel is defined as: AGAFj= Desired reading for iAPRM Actual reading for iAPRM Where the desired reading is found by dividing the actual core thermal power by the rated core thermal power and then multiplying by 100 %
- The actual re*ading of the iAPRM is from the iAPRM in percent power.
5,;0 PRECAUTIONS AND LIMITATIONS 5.1 The AGAFs are not valid if the APRM reading changes significantly from the value used to*obtain the AGAFs prior to calibration. 5.2 Independent verification is required in this procedure. 6.0 PREREQUISITES 6.1 The plant should be brought to a steady state operating condition and held until the calculations are completed. 6.2 Normally the AGAFs are obtained from the process computer. This procedure is used when the process computer is out of service. IOPT-01.8C Rev.' 13 Page 20f61
7.0 ANNUNCIATIONS EXPECTED None 8.0 PROCEDURE Initials 8.1 RECORD the date, time, and unit on Form 1. 8.2 PEFORM OPT-01.8D, Core Thermal Power Calculation, AND RECORD results on Form 1. 8.3 CALCULATE the percent of rated eTP (desired reading) as follows AND RECORD results on Form 1. 0/0 Rated CTP =(CTP+ Rated MWt) x 1000/0 8.4 RECORD the APRM readings from Panel 608 on Form *1. 8.5 CALCULATE the AGAF for each APRM channel as follows AND RECORD results on; Form 1. AGAFi= % of ratedCTP iAPRM reading in % power 8.6 INDEPENDENTLY VERIFY the AGAF calculation for each APRM is correct AND SIGN on Form 1. 9.0 DATA ANALYSIS N/A IOPT-01.8C Rev. 13 Page 3 of 61
10.0
GENERAL COMMENT
S Initials Name (Print) PT was performed by PT has been satisfactorily completed ResponsjbleEngineering~anager~~~~~~~~~~~~~~~~ (Signature) PT has NOT been satisfactorily completed Responsible EngineeringManager~~~~~~~~~~~~~~~~ (Signature) (Signature) Corrective Action Required .
- a. () None
- b. () WRlWONo.
- c. () Other (Explain)
IOPT-01.8C Rev. 13 Page 4 of 61
FORM 1 Page 1 of 1 AGAF Calculation Sheet A. Date_ _ Time- - Unit - - - - - - B. Core Thermal Power (CTP) MWt C. Percent of Rated Core Thermal Power (desired reading): Ok Rated CTP =(CTP+ Rated MWt) x 100% = % Pwr APRM APRM AGAFi Channel Reading 010 Pwr(D) (C/O) 1 2 3 4 AGAFi= % of rated CTP = ~ APRM reading in % power 0 Independently verify the AGAF calculations are correct. 1st verification Date - - - - Signature Date _ Signature IOPT-01.8C Rev. 13 Page 5 of 61
REVISION
SUMMARY
Revision *13 is an editorial change that incorporates the Progress Energy logo. Ref. PRR 167209. Revision 12 - Revision removes reference to 2558MWt as rated Unit 2 thermal power. Revision supports implementation of EC 47907, Implement the Unit 2 Power Uprate Modification. Both Units are Hcensed to 2923 MWT. Revision 11 -Procedure revision incorporated EC 46861, Implement Extended Power Uprate for Unit 1 only. This revision increased the rated power for Unit 1 from 2558 to 2923 Mwt. Revision 10 - Procedure revision incorporates ESR 00-00442, implementation of the power range neutron monitoring system for Unit 1. The nu.mber of APRMs has been reduced from 6 to 40n Unit 1. The>Unit 1 APRM ch.anneIID.'s changed from A-F to 1-4. Changed OPT-01.11 to 1/2PT-01.11.whichnoware unit specific procedures. Revision 9 - Procedure revision converts this document to the proper Microsoft Word 7.0 and the AP-005.format. This revision also incorporates the new Unit 2 rated power value to 2558 mwth due to implementation of Power Uprate. IOPT-Q1.. 8C Rev. 13 Page 60f6]
NRC ADlVIIN JPlVI A-I- B 1 of 11 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERF,ORMANCE MEASURE ADMIN RO/SRO NRC ADMIN JPM A-1-B TITLE: Control Operator Daily Surveillance Report
NRC ADJ\!lIN JPJ\!I A-I-B 2 of 11 tiAFETY CONSIDERATIONS: None. EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Validation Time: RO 15 minutes SRO 20 minutes Read the following to trainee.
TASK CONDITIONS:
- 1. Unit Two (2) is operating at approximately 75% power in support of scheduled activities. A downpower was performed on the previous shift from 100 % *
- 2. Plant conditions:
Reactor power 75% Mode Switch Run All equipment is Operable INITIATING CUE: You have just assumed the watch as the Unit Two (2) Reactor Operator and have been directed to perform a portion of the Unit Two (2) Control Operator Daily Surveillance Report to support shift activities. Complete pages 34, 35, and 45 of 201-03.2 for Sunday, Dayshift, 07-13 readings.
NRC AD:NIIN JP:NI A-I-B 3 of 11 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments. NOTE: The current copy is utilized due to the procedure being used for a seven day period. START TIME: Step 1 - Obtain a *current copy of 201-03.2 Current copy obtained. SAT/UNSAT
,JE: When the candidate has located the correct procedure, the examiner Will provide the applicable pages of 201-03.2 to the candidate.
Step 2 Complete items on pages 34, 35, and 45 of 201-03.2 for Sunday, Dayshift. NOTE: Item 33 on page 35 of 78 will not be obtained by the candidate. This item is required to be taken at 1700. The initiating cue is to obtain 07-13 readings. Items on pages 34, 35, and 45 of 201-03.2 for Sunday, Dayshift completed. SAT/UNSAT
NRC ADlVIIN JPlVI A-I-B 4 of 11
'ep 3 - Identify the following items as needing evaluation for exceeding acceptance criteria:
. Item 30 Suppression Pool Level -43" (downscale)
Item 32 Division II Backup Nitrogen (2-RNA-PI-5267) 1710 (.:!:- 30) psig Item 76 Fee~water Line A temperature 405.9°F C+/- 10°F) Item 77 Feedwater Line B temperature 405.9°F(.::!: 10°F) Items identified for evaluation: Item 30 SAT/UNSAT-Item 32 SAT/UNSAT Item 76 SAT/UNSAT Item 77 SAT/UNSAT Step 4 Compare* Item 30 reading to the Operating Limit and determine acceptance criteria is not met. Determination made that Operating Limit is not met.
**CRITICAL STEP**
SAT/UNSAT
NRC ADlVllN JPlVI A-I-B 5 of 11
-:>TE: The operating limit in Step 32 is not met due to a greater than 50 psig drop in pressure in the previous day.
Step 5 Compare Item 32 reading to the Operating Limit and determine acceptance criteria is not met. Determination made that Operating Limit is not met.
**CRITICAL STEP**
SAT/UNSAT NOTE: Items 76 and 77 acceptance criteria are determined by referencing 20P-32, Attachment 4. 6 Compare Item 76 reading to the Operating Limit and determine acceptance criteria is met. (Must refer to 20P-32 Att.4 due to power change from previous day) Determination made that Operating Limit is met.
**CRITICAL STEP**
SAT/UNSAT Step 7 Compare Item 77 reading to the Operating Limit and determine acceptance criteria is met. (Must refer to 20P-32 Att.4 due to power change from previous day) Determination made that Operating Limit is met.
**CRITICAL STEP**
SAT/UNSAT
NRC ADlVIIN JPlVI A-I-B 6 of 11
,dp 8 Inform SeQ that Items 30 and 32 readings do not meet acceptance criteria.
seQ informed of items not meeting acceptance criteria.
**CRITICAL STEP**
SAT/UNSAT TERMINATING CUE (CO): SCO has been notified that Items 30 and 32 of the Control Operator Daily Surveillance Report do not meet acceptance criteria. SCO CONTINUES
NRC ADJVIIN JPJVI A-I-B 7 of 11
\SK CONDITIONS #2 The Unit CO has completed pages 34, 35, and 45 of 201-03.2 for Sunday, Dayshift, 07-13 readings.
INITIATING CUE #2: seo As the Unit seo, you are to review the completed Daily Surveillance Report sheets and determine whether acceptance criteria are met and identify any required compensatory measures.
NRC ADlVIIN JPlVI A-I-B 8 of 11 Step 9 seo determines Item 30 Level Instrument is inoperable and Suppression Pool Level must be determined by other means to maintain EGGS Systems and Suppression Pool Operability. Determination made that other level indication must be used to ensure EGGS/Suppression Ghamber Operability.
**CRITICAL STEP**
SAT/UNSAT Step 10 seo determines Item 32 does not meet operating limits but does not result in an Inoperability. Determination made that Item 32 parameter does not result in an inoperability.
**CRITICAL STEP*
SAT/UNSAT TERMINATING CUE (SCQ): SCQ has determined Item 30 requires compensatory Action to satisfy surveillance requirement, and Item 32 parameter is an operating limit but does not result in an Inoperability.
NRC ADlVIIN JPlVI A-I-B 9 of 11 A REFERENCE AND IMPORTANCE RATING: GEN 2.1.18 2.9/
3.0 REFERENCES
001-03.2 20P-32, Attachment 4 Technical Specifications TOOLS AND EQUIPMENT:* None SAFETY FUNCTION (from NUREG 1123): Administrative - Conduct Of Operations APPLICABLE METHOD OF TESTING
~rformance: Simulate Actual L Unit: ~
Setting: Control Room Simulator__ (N/A for Admin or In-Plant JPMs) Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No ~ EVALUATION JPM: Pass - - Fail - - Comments:
TASK CONDITIONS:
- 3. Unit Two (2) is operating atapproximately 75°A> power in support of scheduled activities. A downpower was performed on the previous shift from 100°A>.
- 4. Plant conditions:
Reactor power 75°A> Mode Switch Run All equipment is Operable INITIATING CUE: You have just assumed the watch as the Unit Two (2) Reactor Operator and have been directed to perform a portion of the Unit Two (2) Control Operator Daily Surveillance Report to support shift activities. Complete pages 34,35, and 45 of 201-03.2 for Sunday, Dayshift, 07-13 readings.
TASK CONDITIONS #2 The Unit eo has completed pages 34, 35, and 45 of 201-03.2 for Sunday, Dayshift, 07-13 readings. INITIATING CUE #2: seo As the Unit seo, you are to review the completed Daily Surveillance Report sheets and determine whether acceptance criteria are met and identify any required compensatory measures.
SRO NRC ADMIN JPM A-1 1 of 8 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SRO NRC ADMIN JPM A-1 TITLE: Determine Primary Containment Water Level and Evaluate PCPL-A.
SRO NRC ADMIN JPM A-1 2 of 8 SAFETY CONSIDERATIONS: None EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
Read the following to trainee. TASK CONDITIONS:
- 1. An accident is in progress on Unit Two (2). The Unit SCO is directing actions of 2EOP-01-RVCP and EOP-02-PCCP.
- 2. 480 VAC Substation E7 is de-energized due to a fault. All other electrical buses are energized.
- 3. ERFIS is unavailable.
- 4. The following Containment parameter readings are available on the RTG8 CAC-LI-2601-1, (Suppression Pool level, -10 to +6 feet) reads >+6 feet (upscale)
CAC-LR-2602, (Suppression Pool level, -10 to +6 feet) reads -2 feet CAC-PI-1257-2A (Suppression Chamber pressure, 0 to 75 psig) reads 0 psig CAC-PI-1257-28 (Suppression Chamber pressure, 0 to 75 psig) reads>75 psig (upscale) CAC-PI-1230 (Drywell pressure, 0 to 75 psig) reads 67.5 psig CAC-PI-4176 (Drywell Pressure -5 to 245, psig) reads 72.5 psig CAC-PR-1257-1 (Drywell pressure, -5 to 245 psig) reads 25 psig CAC-LI-1216 (Drywell water level, 61 to 71 feet) reads Gauge Zero INITIATING CUE: You are directed to determine Primary Containment water level per EOP-01-UG, Attachment 11. Account for availability of instrumentation per AOP-36.1, Attachment 2. Determine the current region of operation (Safe/Unsafe) on Primary Containment Pressure Limit A (PCPL-A).
SRO NRC ADMIN JPM A-1 3 of 8 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments. Step 1 - Obtain a current revision of EOP-01-UG and AOP-36.1. Current Revision of EOP-01-UG and AOP-36.1 obtained and verified, if applicable. SAT/UNSAT* START TIME: Step 2 - Determine suppression pool water level instruments cannot be used to determine primary containment water level since CAC-LI-2601-1 is above +6 feet and CAC-LR-2602 is powered from E7 and is de-energized. Determine suppression pool water level instruments cannot be used to determine primary containment water.
**CRITICAL STEP** SAT/UNSAT*
Step 3 - Determine suppression chamber pressure instruments cannot be used to determine primary containment water level since CAC-PI-1257-2Bis not less than 75 psig and CAC-PI-1257-2A is powered from E7 and is de-energized Determine suppression chamber pressure instruments cannot be used to determine primary containment water.
**CRITICAL STEP** SAT/UNSAT*
SRO NRC ADMIN JPM A-1 4 of 8 Step 4 - Determine primary containment water level should be calculated using CAC-PI-1230 and CAC-PI-4176. since both instruments have power and suppression chamber pressure is not less than 75 psig. Determine CAC-PR-1257-1 is powered from E7 and should not be used. Determine primary containment water level should be calculated using CAC-PI-1230 and CAC-PI-4176
**CRITICAL STEP** SAT/UNSAT*
Step 5 - Calculate primary containment water level to be 2.3 ft/psi (72.5 - 67.5) + 28.5 ft. Primary containment water level calculated to be 40 feet.
** CRITICAL STEP ** SAT/UNSAT*
Step 6 - Determine operation to be in the safe region of PCPL-A using the PCPL-A graph, calculated primary containment water level and CAC-PI-4176 for drywell pressure, (or by using CAC-PI-1230). Determine PCPL-A is in the Safe region.
** CRITICAL STEP ** SAT/UNSAT*
COMPLETION TIME:
SRO NRC ADMIN JPM A-1 5 of 8
- Comments required for any step evaluated as UNSAT.
SRO NRC ADMIN JPM A-1 6 of 8 RELATED TASKS: 2006028501, Determine Primary Containment water level per EOP-01-UG KIA REFERENCE AND IMPORTANCE RATING: 2.1.7 3.7/4.4 Ability to evaluate plant performance and make operational judgements based on operating characteristics/reactor behavior/instrument interpretation.
REFERENCES:
OEOP-01-UG OAOP-36.1 TOOLS AND EQUIPMENT: Student may use calculator. SAFETY FUNCTION (from NUREG 1123): A.1 Conduct Of Operations
SRO NRC ADMIN JPM A-1 7 of 8 Validation Time: ~ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual 0 Unit: _2_ Setting: Control Room Simulator__ (N/A for Admin or In-Plant JPMs) Time Critical: Yes No 0 Time Limit N/A Alternate Path: Yes No 0 EVALUATION Trainee: - - - - - - - - - - - - - JPM: Pass - - Fail Comments: Comments reviewed with Student .Evaluator Signature: Date:- - - - -
07/12/07 THU 08:21 FAX 4006 PGN BNP EOF 1 141 003 r " ke'L j 7 TAS< CONDITIONS:
- 1. An accident is in progress on Unit Two (2). The Unit SeQ is directing actions of 2EOP-01-RVGP and EOP-02-PCCP.
2~ 480 VAC Substation E7 is de-energized due to a fault. All other electricar buses are energized. 3_ ERFIS is unavaUable. 4~ Th~ following Containment parameter readings are available on the RTGB CAC-LI-2~01-1, (Suppression Pool levels -10 to +6 feet) readS>+6 feet (upscale) INP/' f/'/~ ---7' CAC-LR-2602, (Suppression Pool level, -~O to +6 feet) reads -2 feet {Nfll !~". -?,CAC-PI-1257-2A (Suppression Chamber pressure, 0 to 75 psig) reads 0 psig CAC-PI-1257-2B (Suppression Chamber pressure, 0 to 75 psig) reads)75 psig (upscale) CAC-PI-1230 (Drywell pressure, 0 to 75 psig) reads 67.5 psig
~ .... ' '\
( CAC-PI-4176 (Drywell Pressure -5 to 245 psig) reads 72.5 psig JII/(,)I'/....~;;:71 CAC-PR-1257~1 (Drywell pressure, -5 to 245 psig) reads 25 psig CAC-ll...1216 (Drywell water level, 61 to 71 feet) reads Gauge Zero INITIATING CUE: You are directed to determine Primary Containment water level per EOP~01-UG, Attachment 11. Account for availability of instrumentation per AOP-36.1 Attachment 2. J Determine the current region of operation' (Safe/Unsafe) on Primary Containment Pressure limit A (PCPL-A)_
o
-l
- /(ey-I\:)
~ "-
o
-:a ATIACHMEN,2 Page 3 of 4 ~
~
Unit 2 Critical Instruments and. Components o 00 480V SUBSTATION E7 I\:)
~
~
~
o Rx Water Levej I B21-LT..N026A & ] 0 to +21 0 in~ I H12.. P601 , Ckt 4 ... Emerr 120 VAC Dist PnL 32A o a:> B21-ll-R*604A R*x Water Level 821-LT.. N027A & 621 ..L I-R605A* I +150 to 550 in. I H12..P603 I Ckt 5 - Emer. 120 VAC Dist. PnL 2AB (-Note 1) Dryweff Pressure CAC-pr-2685 & CAC*PI~2685 ..1 10 to 2 psig I XU-51 I Ckt. 7 ~ Emer. 120 VAC Dist. Pnl, 2A Ckt. 9 Emer. 120 VAC Dist Pnl. 2A w
~
DryWall Pressure j CAe-PT-4175 -5 to 245 psfg XU-51 Ckt. 4 ... Emer. 120 VAC Dist Pnl. 32A '=' ~ G') z CAC.. PR-1257~1 Ckt. 19 .. Emer. 120 VAC DisC Pnl. 32A "'J to
)tl Z
~
.SuPPfeSSron Chamber CAC..PT-.r1257..2A & oto 75 pSlg XU*51 Ckt 7 '" Emer, 120 VAC Dist. PnL 2A ~ tt:1
. Pre~sure 0 CAC*Pl.. 1257.--2A Ckt. 9 ... Emer. 120 VAG D~st Pnl. 2A "rj
~
Su-ppression poor- CAe-L T~2602 ..10 to +6 feet XU-51 Ckt. 4 - Erne r 120 VA*C Dist.. PI1 L 32A 4 i ~r lever . '--
. CAC-LR..2602 Ck.t, 24 ... Emer: 120 VAC Dfst. Pnl. 32A Suppressi"on PooJ CAC--LT-4177 &. -42 to -1 B in~ XU ..S1 Ckt, 7 - Emer. 120 VAC Dfst. Pnl. 2A Level CAC;.LI-4177 Ckt. 9 -:E-merr 120 VAG Dfst Pnl. 2A .Div~ I $PTMS I CAC-TR-4426-1A &
1B
! I XU~3 r Ckt. 13- Emer, 120 VAC Dlsl Pnl. 2A (N~te 1")
NOTE 1: These instruments can b-e powered from 2E*8, but must be manuaHy transferred. IOAOP-36. 1 I Rev. 43 [ Page 78 of 91 J [§l o o
~
07/12/07 THU 08:22 PAX 4006 PGN BNP EOP 1 I4l 005 - I ,~ * *", EOP-Ol-UG Attachment 11 Page 1 of 3 ATTACHM:ENT 11 p~rMARY CONTAINMENT WATER LEVEL CALCULATION
- 1. Supp~ession ~ool water level instrumants roay be used for levels up to
+2 feet.
A_ CAC-LI~2601-1 (XU-51) "9 Ket:lf); >1-1 her C'er/fctf/;;J B~ CAC-LR-2602 (XU-51) _ -7 r /'If/f' J0, fdwe/
- 2. IF supP,~ession Chamber pressure is l~ss th~n 75 psig, THBN CALCULATE P.rimcary Containment water level as follQw,s" ---..-.. --......- L I
.. ..>f;(~/".t'jf' It? n 4!- /'
<.. '14,-,.1>,,,.
PI = Suppression Chamber pressure plus head of Wat:er {;e!'l' tt/~ I ( Cl\C-PI-1257-2A (XU-51) Z/fIPI'- ~ ,~ ~ M CAC-Pr-1257-2B (P601) >7;rJ'r (1(1'.luk) fr 4,,-1 7)#
~1 ~ Orywell pressure at greater than 8S it elevation CAC-PI-~Z30 (PGOl) psi
/'
TIME
.~ /
PI (psig) ~ /'
/'
E'2 (psig)
~ /'
PI - iz
~ :/
x 2-3 X2.3/ ~.3 :x 2.3 x 2 .. 3
/'
x 2 .. 3
.....5.3 pewl (ft)
+ 5_3
/
/
~
+ Sr3 +
5 .. 3 + 5.3
~
~.
+ 5.3
/'
~;OP-01-UG Rev. 47 =~age 132 of 13~
07/12/07 THU 08:22 FAX 4006 PGN BNP EOP 1 14I 006 EOp-Ol-UG iTf/f A-I Attachment 11 Page 2 6f 3 ATTACHMENT 11 (Contrd)
- 3. IF Supp~ession Ch~~be~ p~e~sure is greater than 75 psig, THEN CALCULATE
~rimary Containment water level as follow~:
PI ~ Primary containment pressur~ plus head of water CAC-PI-4176 (XU-51) 72 ~ S- l$'~ CAC-PR-1257-1 (XU-Sl) I/1t';' - ~ J:,tVe/ P2 Drywel1 pressure at 9r~at~r than 85 ft elevation CAC-PI-1230 PI measured using CAC-PI-4176 peW] ;=. 2.3 fe@t (PI - P;z) + 28 - 5 feet psi P 1 measured using CAC-PR-1257-1 pew1 = 2 -.3 feet (PI - P2) .... 30.5 feet psi Using P!-4176 TIME NC'lf,/ P1 (psig) 72,5 P2 (psig) t7~ s-PI ... P2 s:{) X 2.3 x 2.3 x 2.3 .x: 2.3 x 2 .. 3 x 2-3 II, j
+28-5 + 28.5 +28.5 + 28 . . 5 +2S-5 +28 .. 5 PCwi (it)
Yo
~EOP-01-UG Page 133 o~ 1381
07/12/07 THU 08:22 FAX 4006 PGN BNP EOF 1 [4J 007 .. \ ~~
,4- , EOP-Ol . . . UG Attachment 11 Page 3 of 3 AT~ACHMENT 11 (Cont'd)
Using P~1257~; J 1J1l? f - ~ e?Ve/ TiME PI (psig)
~z (psig)
PI - l?2 X 2.3 x 2_3 " 2-3 x 2 .. 3 x 2 ... 3 x 2.3
+.30_5 + 30_5 + 30TS + 30.5 + 30_5 +30T5
'PC"'l (ft) 4.. IF drywell water lev(!l is greater th.;ln GO .. 5 feet l 'l'HEN USg CAe DRYWEL~*
WATER LEVEL INDIC, CAC-LI-1216 on P601.
~::OP-01-UG [ ~ __~_:a_ge__1_.34"""",,-o_f1_3_
81
07/12/0'7 TBU 08: 22 FAX 4006 PGN BNP EOF 1 14I 008 EOP-Ol-UG A.ttachment 5 Page 16 of 26 ) ATT~CaMENT 5 (Cont'd) FIGURe 2 PRIMARY CONTAINMENT PRESSURe LIMIT-A 100 90
~
~ 80 en t 1/~r--"""ji- 70~--1-J--+-+-+-1--+-+-+-+-t ..-..."'f--f-t--t-+-t-t-+-+-t-~~-t-+-+-+-+-+-+-+-+-+--+--f--ti 11.
- J 60 - .........~I-+'-+-+-+-+-f--lt-t-+--t--t-"+-t- ...........-+++-+-+-+--1H-+-+-+-~I-I-+-""'-I-+-
o
~ 50 --I-I-~-+--J-+-+-+-+-+-t-+-+-t-f-~-+-+-+-+-lf-t--t--t--t-t--+r+-+-+-~-+-+-
~
a.
...J 40
..J SAFE W 30 ....---.........+-+-f-4--t.-+-+++-I-+-+-t-++-ri-ow+-t-t~-+-+-+-+-f--+-+-f---+r.~!-I--4-+--J- ...-.;
~o 20 10 --t-+-+-++-+--+-+-t-+-t--t-t-+-t--t-t--+-t-++-+-+-t--+-i~-t-+-t-t-.,.p..p.+-+-~.-fY:a:
*10 0 10 20 30 40 50 60 70 80 PRIMARY CONTAINMENT fER LEVEL (FEET)
If using the followinq pcPt-A is: CAC"'PI-1230 10 psig CAC-PI-4176 Use the graph CAC-PR-1257-1
'-10 Use the graph f}
Rev. 4~
TASK CONDITIONS:
- 1. An accident is in progress on Unit Two (2). The Unit SCO is directing actions of 2EOP-01-RVCP and EOP-02-PCCP.
- 2. 480 VAC Substation E7 is de-energized due to a fault. All other electrical buses are energized.
- 3. ERFIS is unavailable.
- 4. The following Containment parameter readings are available on the RTGB CAC-LI-2601-1, (Suppression Pool level, -10 to +6 feet) reads >+6 feet (upscale)
CAC-LR-2602, (Suppression Pool level, -10 to +6 feet) reads -2 feet CAC-PI-1257-2A (Suppression Chamber pressure, 0 to 75 psig) reads 0 psig CAC-PI-1257-2B (Suppression Chamber pressure, 0 to 75 psig) reads >75 psig (upscale) CAC-PI-1230 (Drywell pressure, 0 to 75 psig) reads 67.5 psig CAC-PI-4176 (Drywell Pressure -5 to 245 psig) reads 72.5 psig CAC-PR-1257-1 (Drywell pressure, -5 to 245 psig) reads 25 psig CAC-LI-1216 (Drywell water level, 61 to 71 feet) reads Gauge Zero INITIATING CUE: You are directed to determine Primary Containment water level per EOP-01-UG, Attachment 11. Account for availability of instrumentation per AOP-36.1, Attachment 2. Determine the current region of operation (Safe/Unsafe) on Primary Containment Pressure Limit A (PCPL-A).
NRC RO/SRO ADMIN A-3 1 of 8 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN RO/SRO NRC JPM A-2 TITLE: Generate a Clearance for maintenance activities on the 2C TBCCW pump.
NRC RO/SRO ADMIN A-3 2 of 8 SAFETY CONSIDERATIONS: None. EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
Read the following to trainee. TASK CONDITIONS:
- 1. The 2C TBCCW has been removed from service for maintenance activities to repack the shaft on the pump.
- 2. The pump must be vented and drained.
- 3. The manual suction (2-TCC-V?) and discharge (2-TCC-V13) valves for the 2C TBCCW pump are leaking by and cannot be used as an isolation for the pump.
- 4. The on-line Operations Experience (OE) database is not available for reference.
INITIATING CUE: Generate a proposed clearance boundary for the 2C TBCCW pump to support repacking of the pump. PASSPORT is not available and the Clearance checklist must be filled out manually. Complete Attachment 4 of OPS-NGGC-1301. The Attachment 4 columns for Sequence, Type, Position, and EquipmenUComponent are to be filled in.
NRC RO/SRO ADMIN A-3 3 of 8 NOTE: Procedure OPS-NGGC-1301 should be made available. In addition to the procedural references available for JPM performance, the examinee may choose to reference plant prints/drawings. If requested, prompt the applicant to use aperture cards to print drawings Examiner's Note: Drawings D-2033, Sht.1, LL-92018 and LL-09218 reflect the boundary/blocking valves and power supplies needed to develop the clearance proposal. Step 1 - Obtain references and determine the required blocking points: References obtained for blocking points identification SAT/UNSAT Step 2 - Identify required blocking points for 2C TBCCW Pump Clearance. The following Blocking Points Identified:
- 1. MCC 2TH COMPT 017 **CRITICAL STEP** SAT/UNSAT
- 2. MCC 1TH COMPT D16 **CRITICAL STEP** SAT/UNSAT
- 3. MCC 2TH COMPT D20 **CRITICAL STEP** SAT/UNSAT
- 4. MCC 2TH COMPT 021 **CRITICAL STEP** SAT/UNSAT
- 5. MCC 1TH COMPT 020 **CRITICAL STEP** SAT/UNSAT
- 6. MCC 1TH COMPT D21 **CRITICAL STEP** SAT/UNSAT
- 7. 2-TCC-V3 HANDWHEEL **CRITICAL STEP** SAT/UNSAT
- 8. 2-TCC-V14 HANDWHEEL **CRITICAL STEP** SAT/UNSAT
- 9. 2-TCC-V4 HANDWHEEL **CRITICAL STEP** SAT/UNSAT
- 10. 2-TCC-V15 HANDWHEEL **CRITICAL STEP** SAT/UNSAT
- 11. 2-TCC-V249 HANDWHEEL **CRITICAL STEP** SAT/UNSAT
- 12. 2-TCC-V252 HANDWHEEL **CRITICAL STEP** SAT/UNSAT Step - 3 Determines clearance sequence as follows:
NRC RO/SRO ADMIN A-3 4 of 8
- a. Tags 1 & 2 may be applied in either order but they must be the first blocking points tagged.
**CRITICAL STEP**SAT/UNSAT NOTE: Tags 3, 4, 5, and 6 may be sequenced prior to tags 7, 8, 9, and 10. That is, the candidate may sequence all of the valve power supplies prior to the first handwheel tag, which is acceptable.
- b. The following pairs of tags may be applied in any order. The electrical tag must be applied first.
-Tags 3 and 7 are paired and Tag 3 must be applied first SAT/UNSAT
-Tags 4 and 8 are paired and Tag 4 must be applied first SAT/UNSAT
-Tags 5 and 9 are paired and Tag 5 must be applied first SAT/UNSAT
-Tags 6 and 10 are paired and Tag 6 must be applied first SAT/UNSAT
- c. Tags 11 & 12 must be applied next in any order.
SAT/UNSAT Step 4 - Identify sequence Items 1 through 12 Type as RED. Sequence Items 1 through 12 Type Identified as RED
**CRITICAL STEP**SAT/UNSAT
NRC RO/SRO ADMIN A-3 5 of 8 Step 5 - Identifies Unit 2 Mode Switch for 2C TBCCW Pump for Clearance Information Tag (CIT) SAT/UNSAT Step 6 - Identifies Unit 1 Mode Switch for 2C TBCCW Pump for Clearance Information Tag (CIT) SAT/UNSAT TERMINATING CUE: When the blocking points and sequence have been determined the JPM is complete. COMMENTS:
NRC RO/SRO ADMIN A-3 6 of 8 KIA REFERENCE AND IMPORTANCE RATING: 2.2.13 3.6/3.8 Knowledge of tagging and clearance procedures
REFERENCES:
OPS-NGGC-1301, Revision 17 Prints: 0-2033, Sht.1, LL-92018 and LL-09218 TOOLS AND EQUIPMENT: NONE SAFETY FUNCTION (from NUREG 1123, Rev 2.): A.2 - Equipment Control Time Required for Completion: ~ Minutes (approximate). APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: --l Setting: Control Room Simulator Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION JPM: Pass Fail
NRC RO/SRO ADMIN A-3 7 of 8 ATTACHMENT 4 Sheet 1 of 1 OPERATIONS CLEARANCE Checklist Clearance No. PAGE _1_of_1 INT NAME (PRINT) INT NAME (PRINT)
- Independent Verification Required? Yes/No If No, N/A the Blocks Seq Action Type Tag Id Position EquipmenUComponent Completed By IV By 1 RED OFF/ MCC 2TH COMPT 017 LOCKED 2C TBCCW PP MTR BKR 2 RED OFF/ MCC 1TH COMPT 016 LOCKED 2C TBCCW PP MTR BKR (Alternate Feed) 3 RED OFF/ MCC 2TH COMPT 020 LOCKED 2-TCC-V3 MTR BKR 4 RED OFF/ MCC 2TH COMPT 021 LOCKED 2-TCC-V14 MTR BKR 5 RED OFF/ MCC 1TH COMPT 020 LOCKED 2-TCC-V4 MTR BKR 6 RED OFF/ MCC 1TH COMP 021 LOCKED 2-TCC-V15 MTR BKR 7 RED CLOSED 2-TCC-V3 HANDWHEEL 8 RED CLOSED 2-TCC-V14 HANDWHEEL 9 RED CLOSED 2-TCC-V4 HANDWHEEL 10 RED CLOSED 2-TCC-V15 HANDWHEEL 11 RED OPEN 2-TCC-V249 HANDWHEEL 12 RED OPEN 2-TCC-V252 HANDWHEEL 13* CIT CIT HUNG 2C TBCCW PUMP MODE SELECTOR SWITCH - UNIT 2 RTGB 14 CIT CIT HUNG 2C TBCCW PUMP MODE SELECTOR SWITCH - UNIT 1 RTGB
TASK CONDITIONS:
- 1. The 2C TBCCW has been removed from service for maintenance activities to repack the shaft on the pump.
- 2. The pump must be vented and drained.
- 3. The manual suction (2-TCC-V?) and discharge (2-TCC-V13) valves for the 2C TBCCW pump are leaking by and cannot be used as an isolation for the pump.
- 4. The on-line Operations Experience (OE) database is not available for reference.
INITIATING CUE: Generate a proposed clearance boundary for the 2C TBCCW pump to support repacking of the pump. PASSPORT is not available and the Clearance checklist must be filled out manually. Complete Attachment 4 of OPS-NGGC-1301. The Attachment 4 columns for Sequence, Type, Position, and EquipmenUComponent are to be filled in.
ATTACHMENT 4 Sheet 1 of 1 Operations Clearance Checklist Clearance No. - - - - - - - - Page _ _ of __ Checklist Type: Hang; Lift; Boundary Change (Circle one) INT NAME (PRINT) INT NAME (PRINT)
- Independent Verification Required? YES/NO If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed. Verified By By Continued Y / N QA RECORD I OPS-NGGC-1301 Rev. 17 Page 77 of 99 I
9.3.1.1 Administrative (Cant.)
- 11. The Personal Clearance Preparer shall identify any significant loss of function incurred by clearance activities and document the loss of function in the clearance Special Instructions.
Some potential examples of significant loss of function may include disabled annunciators, defeated protective relays, defeated trip functions, disabled indicators, disabled meters or gauges, masked annunciators, or loss of monitoring capabilities.
- 12. For systems where a pump or fan is affected by a clearance, the clearance should be installed and removed in the sequence listed in the table below to prevent damage to equipment.
Deviations from the sequence and specific instructions below are allowed for safety, ALARA, or if the deviation would not impact personnel or equipment safety. I Clearance Installation I Clearance Removal I Secure pump/fan and hang a tag on Remove tags from handwheels of its control switch. valves and reposition manual valves as required. For pumps, open the suction vaJve before opening the discharge valve. Remove the power source for the Remove tags on power sources to pump/fan prime mover (open valves and restore the power supply breaker, remove fuse, shut steam as required. supply valve and so forth) and place tag on the power source. Reposition valves from control Remove tags from valve control switches, as required by the switches and reposition valves as clearance, and place tags on the required. control switches. Include tags for switches in alternate locations if applicable. Remove power source (electrical, air, Remove the tag*from the power hydraulic, and so forth) from valves, if source for the pump/fan prime applicable, and tag the power source mover. Restore the power source as removed. directed by restoration lineup. Reposition manual valves as required Remove the tag on pump/fan control by the clearance and place tag on switch and reposition the switch as handwheels of the valves covered by required.
*the Clearance. For pumps, shut the discharge valve before shutting the suction valve.
IOPS-NGGC-1301 Rev. 17 Page 56 of 99 I
ATTACHMENT 11 Sheet 2 of 5 Boundary Device Tagging Guidelines Boundary Device Restrictions Tagout Method Motor Operated Valve - Some Limitorque operated - Position valve from control switch valves are prone to drift if in - Place a CIT or clearance tag on manual control switch as required If primary use of valve is flow control, monitor for seat leakage If manual torquing is required, S Place tag on power supply Place tag on valve handwheel that indicates valve position (handwheel should only be manually engaged if untorque valve prior to leak by is present stroking electrically - If torqued, refer to site procedures for additional requirements Hydraulic Operated Valve - Evaluate on a case by case - Position valve from control switch (Fails Closed) basis to determine if valve - Place a CIT or clearance tag on can perform adequately as a control switch as required boundary device - Place tag on power supply to hydraulic pump
- If the operator has a handwheel or other manual positioning device that could open the valve, it should also be tagged
- If the operator does not have a handwheel or other manual positioning device, tag the operator to prevent inadvertent violation of the boundary Hydraulic Operated Valve - Normally not used as a - Position valve from control switch (Fails Open) boundary device - Place> a CIT or clearance tag on
- Either a manual positioning control switch as required device or a mechanical gag - Place tag on power supply to hydraulic is required (SOER 85-5) pump
- Evaluate on a case by case - If the operator has a handwheel or basis to determine if valve other manual positioning device it can perform adequately as a should be tagged boundary device - If a mechanical gag is installed, it should be tagged
- If the operator does not have a handwheel or other manual positioning device, tag the operator to prevent inadvertent violation of the boundary IOPS-NGGC-1301 Rev. 17 Page 88 of 99 I
TASK CONDITIONS:
- 1. The 2C TSCCW has been removed from service for maintenance activities to repack the shaft on the pump.
- 2. The pump must be vented and drained.
- 3. The manual suction (2-TCC-V?) and discharge (2-TCC-V13) valves for the 2C rsccw pump are leaking by and cannot be used as an isolation for the pump.
- 4. The on-line Operations Experience (OE) database is not avai.lable for reference.
INITIATING CUE: Generate a proposed .clearancebol.lndary for the. 2C TBCCW pump to support re.packingof the pump. PASSPORT is not available and the Clearance checklist must be filled outmanually. Complete Attachment 4 of OPS-NGGC-1301. The Attachment 4 columns for Sequence, Type, Position,and EquipmenUComponent are to be filled .in.
ATTACHMENT 4 Sheet 1 of 1 Operations Clearance Checklist Clearance No.- - - - - - - - Page _ _ of _ _ Checklist Type: Hang; Lift; Boundary Change (Circle one) tNT NAME (PRINT) INT NAME (PRINT)
- Independent Verification Required? YES/NO If NO, N/A the Blocks Seq Action Type Tagld Position Equipment/Component Completed. Verified By By Continued YIN QARECORO IOPS-NGGC-1301 Rev. 17 Page 77 of 99 1
~RC RO ADMIN IPM A-3 1 of 7 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMIN RO NRC JPM A-3 TITLE: Determine Stay Time limitations for performing work in a High Radiation Area.
NRC RO ADMIN JPM A-3 2 of? SAFETY CONSIDERATIONS: None. EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
TASK CONDITIONS: Two workers will be performing a lube check and coupling alignment on the Unit One (1) RWCU Pump 1B. Worker #1 has accumulated 1640 mr this year. Worker #2 has accumulated 1655 mr this year. The elevator is out of service The following times for each worker have been estimated for performance of the job.
- 1. Traversing Southwest stairwell 20' - 50' Rx Bldg 12 minutes
- 2. Staging time in access area outside the RWCU room 6 minutes
- 3. Staging time in area directly inside room access door 12 minutes
- 4. Work time at the "B" RWCU pump 2 hours It has been estimated that a total of 30 mr per person will be accumulated once the job is completed. This includes de-staging and use of stairs to return to the maintenance shop.
INITIATING CUE: Using the information above and the provided radiological survey using best ALARA practices:
- 1. Determine the total dose accumulated in performance of the job on the Unit One (1) "B" RWCU pump for both workers. (assume the same task times for both workers)
- 2. Determine if any Brunswick dose limitations will be exceeded.
NRC RO ADMIN JPM A-3 3 of 7 PERFORMANCE CHECKLIST NOTE: Provide the examinee the attached survey map. Each substep is a CRITICAL STEP. Step 1 - Determines dose for each worker as follows:
- a. Traversing SW stairwell 20' - 50' Rx Bldg (SW is the lowest dose stairwell)
(12 min) .2 Hr X 5 mr/hr = 1 mr Estimate 1 millirem dose accumulation **CRITICAL TASK** SAT/UNSAT
- b. Staging time in access area outside the RWCU room (6 min) .1 Hr X 10 mr/hr =1 mr Estimate 1 millirem dose accumulation. **CRITICAL TASK**
SAT/UNSAT
- c. Staging time in area directly inside room access door (12 min) .2 Hr X 75 mr/hr =15 mr Estimate 5 millirem dose accumulation. **CRITICAL TASK**
SAT/UNSAT
NRC RO ADMIN JPM A-3 4of7
- d. Work time at the "8" RWCU pump 2 Hrs X 150 mr/hr =300 mr Estimate 300 millirem dose accumulation. **CRITICAL TASK**
SAT/UNSAT
- e. An additional 30 mr will be accumulated once the job is done for de-staging activities.
Total =1 + 1 + 15 + 300 + 30 =347 mr
** CRITICAL STEP**
SAT/UNSAT Step 2 - Determines that Worker #2 would exceed the Brunswick administrative limit of 2 REM per calendar year if the estimated dose were accumulated. Worker #1 1640 mr + 347 mr =1987 mr << 2R limit) Worker #2 1655 mr + 347 mr =2002 mr (> 2R limit)
** CRITICAL STEP**
SAT/UNSAT
NRC RQ ADMIN JPM A-3 5 of 7 Comments
NRC RO ADMIN IPM A-3 6 of? KIA REFERENCE AND IMPORTANCE RATING: 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (2.9) 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements (2.6)
REFERENCES:
TOOLS AND EQUIPMENT: Calculator. SAFETY FUNCTION (from NUREG 1123): A.3 Radiation Control Validation Time: ~ Minutes r 21 APPLICABLE METHOD OF TESTING Performance: Simulate Actual L Unit: _1_ Setting: Control Room Simulator__ (N/A for Admin or In-Plant JPMs) Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X ill F7 EVALUATION JPM: Pass - - Fail - -
TASK CONDITIONS: Two workers will be performing a lube check and coupling alignment on the Unit One (1) RWCU Pump 1B. Worker #1 has accumulated 1640 mr this year. Worker #2 has accumulated 1655 mr this year. The elevator is out of service The following times for each worker have been estimated for performance of the job.
- 1. Traversing Southwest stairwell 20' - 50' Rx Bldg 12 minutes
- 2. Staging time in access area outside the RWCU room 6 minutes
- 3. Staging time in area directly inside room access door 12 minutes
- 4. Work time at the "B" RWCU pump 2 hours It has been estimated that a total of 30 mr per person will be accumulated once the job is completed. This includes de-staging and use of stairs to return to the maintenance shop.
INITIATING CUE: Using the information above and the provided radiological survey using best ALARA practices:
- 1. Determine the total dose accumulated in performance of the job on the Unit 1B RWCU pump for both workers. (assume the same task times for both workers).
- 2. Determine if any Brunswick dose limitations will be exceeded.
BRUNSWICK. NUCLEAR PLANT RADIOLOGICAL SURVEY SURVEY NO. 0'7 - J 3Z R
. *\l~...,.--_--._--------------------.;..~_--.--r-----------------,.-r---------------,,--- -......;...---_
( DATE: . TOD**A:Y* - TiME: 0-.' 0 *0 DOSE RATE . .CO.NTAMINATION
~Ci aD JrO aD
- - - - - - 1 INST/SN
'EFF_
6KGD_ CPM CPM COMPONENT OR TAG NO. J:Hl,~~;wc.tt, Pv...HP WRiJO 1'131(1 - 02 WOR.KPERFORMEO pLLHt i.~Ib=*l.J.1;::*~HEcl( /co"fL/NG Al(GJH£A1T '." '-. &-MEARRESULTS iN DPM/100 CM2 B=BETAIN.mRJ\OfHR/100CM 2 M:::CPMlMASUN
*J.t111 NO. RESULTS
'_I_~_ _--
¥J/oo A PUMP 8 PUMP 10 S
B .' G. T . B lflO SLCTANK ORAtNUNE CORE SPRAY
- S B
G T A
.. I B
... £
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5.0 PREREQUISITES N/A 6.0 PRECAUTIONS AND LIMITATIONS N/A 7.0 SPECIAL TOOLS AND EQUIPMENT N/A 8.0 ACCEPTANCE CRITERIA N/A 9.0 INSTRUCTIONS R2.1 9.1 Adult Occupational Dose Limits 9.1.1 Whole Body - The more limiting of a total effective dose equivalent equal to 5 rem or the sum of the deep dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye equal to 50 rem. 9.1.2 Skin - A shallow dose equivalent equal to 50 rem. 9.1.3 Lens of Eye - A lens dose equivalent equal to 15 rem. 9.1.4 Extremities - A shallow dose equivalent equal to 50 rem. 9.2 Occupational Dose to Minors Minors shall not be employed to work in radiation control areas, although they may enter as visitors. 9.3 Progress Energy Annual Administrative Dose Limits 9.3.1 0.5 rem Progress Energy dose if non-Progress Energy dose for the current year has not been determined. No dose extension is (\permitted. 9.3.2 rem Progress Energy dose not to exceed 4 rem total dose if non-rogress Energy dose for the current year has been determined. I OOS-NGGC-0004 Rev. 9 Page 4 of 91
TASK CONDITIONS: Two workers will be performing a lube check and coupling alignment on the Unit One (1) RWCU Pump 1B. Worker #1 has accumulated 1640 mr this year. Worker #2 has accumulated 1655 mr this year. The elevator is out of service The following times for each worker have been estimated for performance of the job.
- 1. Traversing Southwest stairwell 20' - SO' Rx Bldg 12 minutes
- 2. Staging time in access area outside the RWCU room 6 minutes
- 3. Staging time in area directly inside room access door 12 minutes
- 4. Work time at the"S" RWCU pump 2 hours It has been estimated that a total of 30 mr per person will be accumulated once the job is completed. This includes de-staging and use of stairs to return to the maintenance shop.
INITIATING CUE: Using the information above a.nd the provided radiological survey using best ALARA practices:
- 1. Determine the total dose accul11ulatedin performance of the job on the Unit 1B RWCU pump for both workers. (assume the same task times for both workers).
- 2. Determine if any Brunswick dose limitations willbeex.ceeded.
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NRC SRO ADMIN JPM A-3 Page 1 of 33 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SRO NRC ADMIN JPM A-3 TITLE: Determine Off-Site Release Per PEP-03.4.7 And Complete Notification Form.
NRC SRO JPM A-3 Page 2 of 33 SIMULATOR NOTES:
- 1. Perform this JPM PRIOR to the first applicant's performance and AFTER the last applicant's performance. This information will bound the actual applicant performance results.
EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. This JPM may be performed in any location with a computer loaded with the Rascal 3.0.4 program.
- 3. The Attachment 5 data specifies three release points being the Main Stack, Unit 2 Turbine Building, and Unit 1 Turbine Building
- 4. The release at the site boundary should be approximately 1.267E+08 mrem TEDE and 1.4203E+09 mrem CDE.
NRC SRO JPM A-3 Page 3 of 33 TASK CONDITIONS:
- 1. The site is in a General Emergency due to a failure of 2 out of 3 fission product barriers with a potential for the loss of the third barrier on Unit Two (2). Fuel failure exists with an unisolable steam line break in the Turbine Building.
EXAMINER NOTE: Provide Specific Time for blank in task condition 2 which is 15 minutes prior to actual time
- 2. The Unit 2 reactor was successfully scrammed at _
- 3. Attachment 5 of PEP-3.4.7 has been filled out for data entry. (Give examinee Attachment 5. Fill out current time and current date with time of shutdown as 15 minutes ago)
- 4. A follow-up Emergency Notification has been completed with the exception of lines 15 and 16 for the Shift Superintendent (SEC) approval.
INITIATING CUE: You are directed by the Shift Superintendent (SEC) to perform an initial dose calculation per PEP 03.4.7, Automation of Off-site dose projection procedure. You are to transfer the projected dose data to lines 15 and 16 of the attached follow-up notification form in accordance with PEP-02.6.21. Once lines 15 & 16 are completed, you are to give the Emergency Notification form to the Shift Superintendent (SEC) for approval.
NRC SRO JPM A-3 Page 4 of 33 ATTACHMENT 5 Data Sheet for Dose Projection Inputs CHARACTERISTIC TIME Main Stack Release Rate (~Ci/cc) 4.2E5 Flow Rate (CFM) 42000 Turbine Building #1 Release Rate (~Ci/cc) 2.2E6
#1 Flow Rate (CFM) 15000
#2 Release Rate (~Ci/cc) 2.2E6
#2 Flow Rate (CFM) 15000 Reactor Building Release Rate (~Ci/cc) 3.5E2 Flow Rate (CFM) 0 Torus Vent Release Rate (~Ci/cc) 0 Core Uncovered Time (1) lost! (2) Returned 10 Minutes Effective Filtration Yes / No Yes Release Height Ground Yes Elevated No Release Duration Anticipated Length of Time 1 Hours Shutdown Date Time Met Data Wind Speed Upper 15MPH Lower 13 MPH Met Data Direction Upper 68 DEG Lower 67 DEG Stability Class E Seabreeze Yes / No No Precipitation None
NRC SRO JPM A-3 Page 5 of 33 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments. Step 1 - Obtain a current revision of PEP-03.4.7. Current Revision ofPEP-03.4.7 obtained.
**CRITICAL STEP**SAT/UNSAT Step 2 - Access Rascal 3.0.4 program.
Rascal Program accessed.
**CRITICAL STEP** SAT/UNSAT NOTE: lAW PEP-03.4.7, a separate dose projection is to be performed for each release point with the results being entered on Attachment 6 of the procedure and, subsequently, totaled.
NOTE: The Unit 2 Turbine Building Dose Projection begins with Step 3 The Unit 1 Turbine Building Dose Projection begins with Step 29 The Stack Dose Projection begins with Step 56 TURBINE BUILDING #2 Dose Projection: Step 3 - Select Source Term to Dose Model (STOose). ST Dose selected.
**CRITICAL STEP** SAT/UNSAT Step 4 - Click on the Event Type button.
Event Type selected.
**CRITICAL STEP** SAT/UNSAT Step 5 - Select Nuclear Power Plant and then OK.
NPP and OK selected.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 6 of 33 NOTE: OPEP-03 ..4.7, Steps 7.7.3 - 7.7.5 are N/A due to not being the source. Step 6 - Select Event Location. Event Location selected.
**CRITICAL STEP** SAT/UNSAT Step 7 - Using the drop down box under sites select Brunswick Unit 2.
Brunswick Unit 2 selected.
**CRITICAL STEP** SAT/UNSAT Step 8 - Click on the Source Term button.
Source Term selected.
**CRITICAL STEP** SAT/UNSAT Step 9 - Select Monitored Releases - Mixtures and then select OK.
Monitored Releases - Mixtures selected.
**CRITICAL STEP** SAT/UNSAT Step 10 - Select Reactor Shutdown YES and enter today as the date and 15 minutes ago as the time.
YES selected and date and time entered.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 7 of 33 Step 11 - Enters Sample ID as current date and time in the format of mmddyyhhmm. Sample 10 is entered.
**CRITICAL STEP** SAT/UNSAT Step 12 - Enters Sample time as current date and the time the sample was taken.
Sample time is entered.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.9.3.3,7.9.3.5, and 7.9.3.6 are N/A based on those locations not being the release points.
NOTE: Candidate must ensure that the correct units are selected. May have to select something different than the default. Concentration is in fJCi/cc which is the same as fJCi/cm3. Flow rate is in CFM which is ft3/ min. Step 13 - Enters effluent gross concentration as 2.2E6 fJCi/cc. 3 2.2E6 JiCi/cm entered.
**CRITICAL STEP** SAT/UNSAT Step 14 - Enters effluent flow rate as 15000 cfm.
15000 ft3/min entered.
**CRITICAL STEP** SAT/UNSAT NOTE: The program default isotopic mixture percentages for Noble Gases and Halogens are 980/0 and 20/0, respectively. The percentages will require the candidate to change the values.
NRC SRO JPM A-3 Page 8 of 33 Step 15 - Selects Noble gases to 99% and Halogens to 1% and then clicks on OK. Percentages are entered.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.9.5,7.9.6,7.9.7,7.9.8,7.9.9, and 7.9.10 are N/A based on source of release.
Step 16 - Clicks on the release path button. Release path panel pops up.
**CRITICAL STEP** SAT/UNSAT Step 17 - Selects not an isolated path with a release height of 0 meters and considers building wake effects as YES.
Not an Isolated path selected, release height entered as 0, and YES selected for building wake effects.
**CRITICAL STEP** SAT/UNSAT Step 18 - Enters the start of release as the sample time.
Enters the sample time as the starl of the release.
**CRITICAL STEP** SAT/UNSAT NOTE: The release duration is specified in the conditions provided.
Step 19 - Selects release duration as 1 hour and then selects OK. Selects release duration and enters 1 hour.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 9 of 33 NOTE: OPEP-03.4.7, Steps 7.10.3,7.10.4 and 7.10.5 are N/A due to those locations not being the source of the release. Step 20 - Clicks on Meteorology button. Meteorology screen pops up.
**CRITICAL STEP** SAT/UNSAT Step 21 - From data set type, selects actual observations and forecasts and then enter new data.
Enter new data selected.
**CRITICAL STEP** SAT/UNSAT Step 22 - Selects enter new data.
Enter new data selected.
**CRITICAL STEP** SAT/UNSAT Step 23 - Enters the following data; type =obs, date =today, time =sample time, degrees of ground level, wind speed at ground level, stability class =E. After data is entered select OK.
Data entered and OK selected.
**CRITICAL STEP** SAT/UNSAT Step 24 - Select Save and Process data button.
Save and Process data screen pops up.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 10 of 33 Step 25 - Enter new name as date and time (mmddyyhhmm), then click on OK. Enters file name and selects OK.
**CRITICAL STEP** SAT/UNSAT Step 26 - Close screens and select calculate doses.
Calculate doses selected.
**CRITICAL STEP** SAT/UNSAT Step 27 - Select distance of calculation as close in, default value for end of calculations as 6 hours, and enter a case description of BNP and the hour (i.e. BNP1230). Then selects OK.
Close in selected, 6 hours selected, and BNPhhhh entered.
**CRITICAL STEP** SAT/UNSAT The results for the Unit 2 Turbine Building release are:
NOTE: Values from the Rascal program are in Rem and the form requires mrem. NOTE: TEDE values are: Site Boundary (0.5 miles) is 6.2E7 mrem. 2 miles is 1.4E7 mrem. 5 miles is 4.4E6 10 miles is 1.4E6 Adult Thyroid CDE (mrem) values are: Site Boundary (0.5 miles) is 7.1 E8 mrem. 2 miles is 1.2E8 mrem. 5 miles is 2.9E7 10 miles is 8.7E6
NRC SRO JPM A-3 Page 11 of 33 NOTE: Attachment 6 has only one line for Turbine Building. The candidate should either total Unit 1 and Unit 2 Turbine Building results prior to entering on Attachment 6 or enter both sets of data in the same table fields. Step 28 - Record the values obtained on Attachment 6. Values recorded on Attachment 6
**CRITICAL STEP** SAT/UNSAT TURBINE BUILDING #1 Dose Projection:
Step 29 Using the "File" pull down, Select "New Case" New Case Selected
**CRITICAL STEP** SAT/UNSAT Step 30 - Select Source Term to Dose Model (STDose).
ST Dose selected.
**CRITICAL STEP** SAT/UNSAT Step 31 - Click on the Event Type button.
Event Type selected.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 12 of 33 Step 32 - Select Nuclear Power Plant and then OK. NPP and OK selected.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03..4.7, Steps 7.7.3 - 7.7.5 are N/A due to not being the source.
Step 33 - Select Event Location. Event Location selected.
**CRITICAL STEP** SAT/UNSAT Step 34 - Using the drop down box under sites select Brunswick Unit 2.
Brunswick Unit 2 selected.
**CRITICAL STEP** SAT/UNSAT Step 35 - Click on the Source Term button.
Source Term selected.
**CRITICAL STEP** SAT/UNSAT Step 36 - Select Monitored Releases - Mixtures and then select OK.
Monitored Releases - Mixtures selected.
**CRITICAL STEP** SAT/UNSAT
NRC SRO IPM A-3 Page 13 of 33 Step 37 - Select Reactor Shutdown YES and enter today as the date and 15 minutes ago as the time. YES selected and date and time entered.
**CRITICAL STEP** SAT/UNSAT Step 38 - Enters Sample ID as current date and time in the format of mmddyyhhmm.
Sample 10 is entered.
**CRITICAL STEP** SAT/UNSAT Step 39 - Enters Sample time as current date and the time the sample was taken.
Sample time is entered.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.9.3.3,7.9.3.5, and 7.9.3.6 are N/A based on those locations not being the release points.
NRC SRO JPM A-3 Page 14 of 33 NOTE: Candidate must ensure that the correct units are .selected. May have to select something differentthan th.e default. Concentration is in (JCi/cc which is the 3 same as (JCi/cm .Flow.rate is in CFM which is ft3/ min . Step 40 - Enters effluent gross concentration as 2.2E6 (JCi/cc. 2.2E6 pCi/cm3 entered.
**CRITICAL STEP** SAT/UNSAT Step 41 - Enters effluent flow rate as 15000 cfm.
15000 ft3/min entered.
**CRITICAL STEP** SAT/UNSAT NOTE: The program default isotopic mixture percentages for Noble Gases and Halogens are 98% and 2%, respectively. The percentages will require the candidate to change the values.
Step 42 - Selects Noble gases to 990/0 and Halogens to 1% and then clicks on OK. Percentages are entered.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.9.5,7.9.6,7.9.7,7.9.8,7.9.9, and 7.9.10 are N/A based on source of release.
NRC SRO JPM A-3 Page 15 of 33 Step 43 - Clicks on the release path button. Release path panel pops up.
**CRITICAL STEP** SAT/UNSAT Step 44 - Selects not an isolated path with a release height of 0 meters and considers building wake effects as YES.
Not an Isolated path selected, release height entered as 0, and YES selected for building wake effects.
**CRITICAL STEP** SAT/UNSAT Step 45 - Enters the start of release as the sample time.
Enters the sample time as the start of the release.
**CRITICAL STEP** SAT/UNSAT NOTE: The release duration is specified in the conditions provided.
Step 46 - Selects release duration as 1 hour and then selects OK. Selects release duration and enters 1 hour.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 16 of 33 NOTE: OPEP-03.4.7, Steps 7.10.3,7.10.4 and 7.10.5 are N/A due to those locations not being the source of the release. Step 47 - Clicks on Meteorology button. Meteorology screen pops up.
**CRITICAL STEP** SAT/UNSAT Step 48 - From data set type, selects actual observations and forecasts and then enter new data.
Enter new data selected.
**CRITICAL STEP** SAT/UNSAT Step 49 - Selects enter new data.
Enter new data selected.
**CRITICAL STEP** SAT/UNSAT
= = =
Step 50 - Enters the following data; type obs, date today, time sample time, degrees of
=
ground level, wind speed at ground level, stability class E. After data is entered select OK. Data entered and OK selected.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 17 of 33 Step 51 - Select Save and Process data button. Save and Process data screen pops up.
**CRITICAL STEP** SAT/UNSAT Step 52 - Enter new name as date and time (mmddyyhhmm), then click on OK.
Enters file name and selects OK.
**CRITICAL STEP** SAT/UNSAT Step 53 - Close screens and select calculate doses.
Calculate doses selected.
**CRITICAL STEP** SAT/UNSAT Step 54 - Select distance of calculation as close in, default value for end of calculations as 6 hours, and enter a case description of BNP and the hour (Le. BNP1230). Then selects OK.
Close in selected, 6 hours selected, and BNPhhhh entered.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 18 of 33 The results for the Unit 1 Turbine Building release are: NOTE: Values from the Rascal program are in Rem and the form requires mrem. NOTE: TEDE values are: Site Boundary (0.5 miles) is 6.2E7 mrem. 2 miles is 1.4E7 mrem. 5 miles is 4.4E6 10 miles is 1.4E6 Adult Thyroid CDE (mrem) values are: Site Boundary (0.5 miles) is 7.1 E8 mrem. 2 miles is 1.2E8 mrem. 5 miles is 2.9E7 10 miles is 8.7E6 NOTE: Attachment 6 has only one line for Turbine Building. The candidate should either total Unit 1 and Unit 2 Turbine Building results prior to entering on Attachment 6 or enter both sets of data in the same table fields. Step 55 - Record the values obtained on Attachment 6. Values recorded on Attachment 6
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 19 of 33 MAIN STACK Dose Projection: Step 56 - Using the "File" pull down, Select "New Case" New Case Selected
**CRITICAL STEP** SAT/UNSAT Step 57 - Select Source Term to Dose Model (STDose).
ST Dose selected.
**CRITICAL STEP** SAT/UNSAT Step 58 - Click on the Event Type button.
Event Type selected.
**CRITICAL STEP** SAT/UNSAT Step 59 - Select Nuclear Power Plant and then OK.
NPP and OK selected.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03..4.7, Steps 7.7.3 - 7.7.5 are N/A due to not being the source.
NRC SRO IPM A-3 Page 20 of33 Step 60 - Select Event Location. Event Location selected.
**CRITICAL STEP** SAT/UNSAT Step 61 - Using the drop down box under sites select Brunswick Unit 2.
Brunswick Unit 2 selected.
**CRITICAL STEP** SAT/UNSAT Step 62 - Click on the Source Term button.
Source Term selected.
**CRITICAL STEP** SAT/UNSAT Step 63 - Select Monitored Releases - Mixtures and then select OK.
Monitored Releases - Mixtures selected.
**CRITICAL STEP** SAT/UNSAT Step 64 - Select Reactor Shutdown YES and enter today as the date and 15 minutes ago as the time.
YES selected and date and time entered.
**CRITICAL STEP** SAT/UNSAT
NRC SRO IPM A-3 Page 21 of 33 Step 65 - Enters Sample 10 as current date and time in the format of mmddyyhhmm. Sample 10 is entered.
**CRITICAL STEP** SAT/UNSAT Step 66 - Enters Sample time as current date and the time the sample was taken.
Sample time is entered.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.9.3.4,7.9.3.5, and 7.9.3.6 are N/A based on those locations not being the release points.
NOTE: Gandi9c;ltElrT1ustensur~th~tthecorrectunitsClreselected. May have to sel.ect
~0rTl~thinQdiff~rentthanthedefault.Corl<~entrationis in ~GilcG\Nhich is the 3
sameasIJCi/cm .Flo.w rate isin CFM which. is ft3/ min. Step 67 - Enters effluent gross concentration as 4.2E5 f.,JCi/cc. 3 4.2E5 pCi/cm entered.
**CRITICAL STEP** SAT/UNSAT
NRC SRO IPM A-3 Page 22 of33 Step 68 - Enters effluent flow rate as 42000 cfm. 42000 ft3 jmin entered.
**CRITICAL STEP** SAT/UNSAT NOTE: The program default isotopic mixture percentages for Noble Gases and Halogens are 98% and 2%, respectively. The percentages will require the candidate to change the values.
Step 69 - Selects Noble gases to 99% and Halogens to 1% and then clicks on OK. Percentages are entered.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.9.5,7.9.6,7.9.7,7.9.8,7.9.9, and 7.9.10 are N/A based on data provided.
Step 70 - Clicks on the release path button. Release path panel pops up.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 23 of 33 Step 71 - Selects Isolated Stack with a release height of 100 meters. Isolated Stack with a release height of 100 meters selected.
**CRITICAL STEP** SAT/UNSAT Step 72 - Selects NO for plume rise.
NO selected for plume rise.
**CRITICAL STEP** SAT/UNSAT Step 73 - Selects NO for Seabreeze.
NO selected for Seabreeze.
**CRITICAL STEP** SAT/UNSAT Step 74 - Enters the start of release as the sample time.
Enters the sample time as the start of the release.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 24 of 33 NOTE: The release duration is specified in the conditions provided. Step 75 - Selects release duration as 1 hour and then selects OK. Selects release duration and enters 1 hour.
**CRITICAL STEP** SAT/UNSAT NOTE: OPEP-03.4.7, Steps 7.10.3,7.10.4 and 7.10.5 are N/A due to those locations not being the source of the release.
Step 76 - Clicks on Meteorology button. Meteorology screen pops up.
**CRITICAL STEP** SAT/UNSAT Step 77 - From data set type, selects actual observations and forecasts and then enter new data.
Enter new data selected.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 25 of 33 Step 78 - Selects enter new data. Enter new data selected.
**CRITICAL STEP** SAT/UNSAT Step 79 - Enters the following data; type =obs, date =today, time =sample time, degrees of Upper level, wind speed at Upper level, stability class =E. After data is entered select OK.
Data entered and OK selected.
**CRITICAL STEP** SAT/UNSAT Step 80 - Select Save and Process data button.
Save and Process data screen pops up.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 26 of 33 Step 81 - Enter new name as date and time (mmddyyhhmm), then click on OK. Enters file name and selects OK.
**CRITICAL STEP** SAT/UNSAT Step 82 - Close screens and select calculate doses.
Calculate doses selected.
**CRITICAL STEP** SAT/UNSAT Step 83 - Select distance of calculation as close in, default value for end of calculations as 6 hours, and enter a case description of BNP and the hour (Le. BNPhhmm1230).
Then selects OK. Close in selected, 6 hours selected, and BNPhhmm entered.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 27 of 33 The results for the Main Stack release are: NOTE: Values from the Rascal program are in Rem and the form requires mrem. NOTE: TEDE values are: Site Boundary (0.5 miles) is 2.7E6 mrem. 2 miles is 2.3E6 mrem. 5 miles is 9.9E5 mrem 10 miles is 3.6E5 mrem Adult Thyroid CDE (mrem) values are: Site Boundary (0.5 miles) is 3.0E5 mrem. 2 miles is 1.3E7 mrem. 5 miles is 5.7E6 10 miles is 2.1E6 Step 84 - Record the values obtained for the Stack release on Attachment 6. Values recorded on Attachment 6
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 28 of 33 Step 85 - Total the columns on Attachment 6 and record the results in the applicable fields. NOTE: The totals for Attachment 6 are: TEDE Site Boundary (0.5 miles) is 1.267E8 mrem 2 miles is 3.03E7 mrem 5 miles is 9.79E6 mrem 10 miles is 3.16E6 mrem Adult Thyroid CDE (mrem) values are: Site Boundary (0.5 miles) is 1.4203E9 mrem 2 miles is 2.53E8 mrem 5 miles is 6.37E7 mrem 10 miles is 1.95E7 mrem Totals recorded on Attachment 6
**CRITICAL STEP** SAT/UNSAT NOTE: I. hstructipnsJ()rsprnpletion of Unes15& 16 of the Notification Form are contained inPEP-02.6.21 ,Attachment.2.
Step 86 - Complete line 15 of the Emergency Notification form. Projection period is 6 hours. Estimated release duration is 1 hour. Enters time and date.
**CRITICAL STEP ** SAT/UNSAT
NRC SRO JPM A-3 Page 29 of33 NOTE: Values from the Rascal program are in Rem and the form requires mrem. NOTE: TEDE values are: Site Boundary (0.5 miles) is 1.307E8 mrem. 2 miles is 3.13E7 mrem. 5 miles is 9.99E6 10 miles is 3.16E6 Adult Thyroid CDE (mrem) values are: Site Boundary (0.5 miles) is 1.2803E9 mrem. 2 miles is 2.43E8 mrem. 5 miles is 6.27E7 10 miles is 1.91E7 Step 87 - Complete line 16 of the Emergency Notification form. TEDE and CDE data transferred from dose projection to Notification Form for Site Boundary, 2 Miles, 5 Miles and 10 Miles.
** CRITICAL STEP ** SAT/UNSAT Step 88 - Notifies Shift Superintendent of results.
Shift Superintendent notified of off-site dose projection results and given the Emergency Notification form for approval.
**CRITICAL STEP** SAT/UNSAT
NRC SRO JPM A-3 Page 30 of 33 TERMINATING CUE: >'{Vhenth~offsitedoseprojection hasb~13n. performed and lines .15&. 16 of the Emergency. Notification form arefiUed in, this JPM. is. complete. COMMENTS:
NRC SRO JPM A-3 Page 31 of 33 KIA REFERENCE AND IMPORTANCE RATING: GEN 2.3.10 2.9/3.3 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure
REFERENCES:
OPEP-03.4.7 OPEP-02.1 TOOLS AND EQUIPMENT: Computer loaded with Rascal 3.0.4. SAFETY FUNCTION (from NUREG 1123, Rev 2.): A.3 Radiation Control Time Required for Completion: ~ Minutes (approximate). APPLICABLE METHOD OF TESTING Performance: Simulate Actual L Unit: 2 Setting: Control Room Simulator__ ( Not applicable to In-Plant JPMs ) Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No L JPM: Pass - - Fail - -
TASK CONDITIONS:
- 1. The site is in a General Emergency due to a failure of 2 out of 3 fission product barriers with a potential for the loss of the third barrier on Unit Two (2). Fuel failure exists with an unisolable steam line break in the Turbine Building.
EXAMINER NOTE: Provide Specific Time for blank in task condition 2 which is 15 minutes prior to actual time
- 2. The Unit 2 reactor was successfully scrammed at _
- 3. Attachment 5 of PEP-3.4.7 has been filled out for data entry. (Give examinee Attachment 5. Fill out current time and current date with time of shutdown as 15 minutes ago)
- 4. A follow-up Emergency Notification has been completed with the exception of lines 15 and 16 for the Shift Superintendent (SEC) approval.
INITIATING CUE: You are directed by the Shift Superintendent (SEC) to perform an initial dose calculation per PEP 03.4.7, Automation of Off-site dose projection procedure. You are to transfer the projected dose data to lines 15 and 16 of the attached follow-up notification form in accordance with PEP-02.6.21. Once lines 15 & 16 are completed, you are to give the Emergency Notification form to the Shift Superintendent (SEC) for approval.
Handout for applicant ATTACHMENT 5 Data Sheet for Dose Projection Inputs CHARACTERISTIC TIME Main Stack Release Rate (IlCi/cc) 4.2E5 Flow Rate (CFM) 42000 Turbine Building #1 Release Rate (IlCi/cc) 2.2E6
#1 Flow Rate (CFM) 15000
#2 Release Rate (IlCi/cc) 2.2E6
#2 Flow Rate (CFM) 15000 Reactor Building Release Rate (IlCi/cc) 3.5E2 Flow Rate (CFM) 0 Torus Vent Release Rate (IlCi/cc) 0 Core Uncovered Time (1) losV (2) Returned 10 Minutes Effective Filtration Yes I No Yes Release Height Ground Yes Elevated Yes Release Duration Anticipated Length of Time 1 Hours Shutdown Date Time Met Data Wind Speed Upper 15MPH Lower 13 MPH Met Data Direction Upper 68DEG Lower 67DEG Stability Class E Seabreeze Yes / No No Precipitation None
Summary Report Case description: bnp0835 Run date/time: 07/24/2007 08:40 Maximum Dose Values (rem) - Close-In Dist from release miles 0.1 0.2 0.3 0.5 0.7 1. 1.5 2. (kilometers) (0.16) (0.32) (0.48) (0.8) (1.13) (1.61 ) (2.41 ) (3.22) Total EDE 4.8E+05 1.8E+05 1.1 E+05 6.2E+04 4.3E+04 3.0E+04 2.0E+04 1.4E+04 Thyroid CDE 7.7E+06 2.5E+06 1.4E+06 7.1E+05 4.6E+05 2.9E+05 1.7E+05 1.2E+05 Acute Lung 3.4E+05 1.1 E+05 6.1E+04 3.1E+04 2.0E+04 1.3E+04 8.0E+03 5.7E+03 Total Acute Bone 1.7E+05 7.9E+04 5.3E+04 3.3E+04 2.5E+04 1.9E+04 1.2E+04 9.0E+03 Inhalation CEDE 2.8E+05 9.0E+04 5.0E+04 2.5E+04 1.7E+04 1.1 E+04 6.3E+03 4.3E+03 Cloud Shine 1.1 E+05 5.9E+04 4.2E+04 2.8E+04 2.1E+04 1.6E+04 1.1E+04 7.9E+03 Period Gnd Shine 5.3E+04 1.7E+04 9.6E+03 4.9E+03 3.2E+03 2.0E+03 1.3E+03 9.4E+02 4-day Ground Shine 9.8E+04 3.2E+04 1.8E+04 9.0E+03 5.9E+03 3.8E+03 2.3E+03 1.6E+03 Notes:
- 1. Doses exceeding PAGs are underlined.
- 2. Early-Phase PAGs: TEDE - 1 rem, Thyroid CDE - 5 rem
- 3. *** indicates values less than 0.1 mrem To view all values - use Detailed Results I Numeric Table
- 4. Total EDE =CEDE Inhalation + Cloud Shine + 4-Day Ground Shine
- 5. Total Acute Bone = Bone Inhalation + Cloud Shine + Period Ground Shine Maximum Dose Values (rem) - To 10 miles Dist from release miles 3 4 5 7 10 (kilometers) (4.8) (6.4) (8.0) (11.3) (16.1 )
Total EDE 2.4E+03 7.9E+03 4.4E+03 2.3E+03 1.4E+03 Thyroid CDE 3.1E+04 4.4E+04 2.9E+04 1.5E+04 8.7E+03 Acute Lung 1.5E+03 2.2E+03 1.5E+03 7.8E+02 4.4E+02 Total Acute Bone 1.1 E+03 6.1E+03 3.2E+03 1.7E+03 1.0E+03 Inhalation CEDE 1.2E+03 1.7E+03 1.1 E+03 5.8E+02 3.3E+02 Cloud Shine 8.5E+02 5.7E+03 2.9E+03 1.5E+03 9.4E+02 Period Gnd Shine 2.4E+02 3.4E+02 2.3E+02 1.2E+02 6.0E+01 4-day Ground Shine 4.2E+02 5.9E+02 3.9E+02 2.0E+02 1.1E+02 Notes:
- 1. Doses exceeding PAGs are underlined.
- 2. Early-Phase PAGs: TEDE - 1 rem, Thyroid CDE - 5 rem
- 3. *** indicates values less than 0.1 mrem To view all values - use Detailed Results I Numeric Table
- 4. Total EDE =CEDE Inhalation + Cloud Shine + 4-Day Ground Shine
- 5. Total Acute Bone = Bone Inhalation + Cloud Shine + Period Ground Shine Case Summary Event Type Nuclear Power Plant Location Name: Brunswick - Unit 2 City, county, state: Southport, Brunswick, NC Printed: Tuesday, July 24,2007 08:42 by RASCAL v3.0.4 Source Term to Dose Model Page 1 of 2
Summary Report Lat I Long I Elev: 33.9583° N, 78.0106° W, 5 m Time zone: Eastern Population (2000): 1,074 I 6,771 /25,619 (2/ 5 I 10 mi) Reactor Parameters Reactor power: 2923 MW(t) Average fuel burn-up: 32500 MWD I MTU Containment type: BWR Mark I Containment volume: 1.64E+05 ft3 Design pressure: 62 psig Design leak rate: 0.50 0/0/d Coolant volume: 3.22E+04 gal Assemblies in core: 560 Source Term Type: Monitored Release - Mixtures Shutdown: 07/24/2007 08:20 Sample 10: 0724070835 Sample taken: 07/24/07 08:35 Gross concentration: 2.20E+06 ~Ci/cm3 Flow rate: 1.50E+04 ft 3 /min User defined percentages Noble gases: 99.000% Halogens: 1.000% Alkali metals: 0.000% Tellurium group: 0.000% Barium, Strontium: 0.000% Noble metals: 0.000% Lanthan ides: 0.000% Cerium group: 0.000% Release Pathway Type: Direct to Atmosphere Release point: Not an isolated stack Release height: O.m Building wake effects: Computed Release timings To atmosphere start: 07/2412007 08:35 To atmosphere duration: o days, and 01 :00 Meteorology Type: Actual Observations Data set name: 0724070835 Data set desc: BRUN Dir=67 Spd=13 Stab=E Precp=N Summary of data Dir Speed Stability Temp at release point: Type deg mph class Precip 07/24/2007 08:30 Obs 067 13.0 E None Calculations Case description: bnp0835 End of calculations: 07/24/2007 14:35 Distance of calculation: Close-in + to 10 miles Close-in distances: 0.1,0.2, 0.3, 0.5, 0.7, 1.0, 1.5,2.0 miles Printed: Tuesday, July 24, 2007 08:42 by RASCAL v3.0.4 Source Term to Dose Model Page 2 of 2
Summary Report Case description: bnp0835 Run date/time: 07/24/2007 09:07 Maximum Dose Values (rem) - Close-In Dist from release miles 0.1 0.2 0.3 0.5 0.7 1. 1.5 2. (kilometers) (0.16) (0.32) (0.48) (0.8) (1.13) (1.61) (2.41 ) (3.22) Total EDE 4.8E+05 1.8E+05 1.1E+05 6.2E+04 4.3E+04 3.0E+04 2.0E+04 1.4E+04 Thyroid CDE 7.7E+06 2.5E+06 1.4E+06 7.1E+05 4.6E+05 2.9E+05 1.7E+05 1.2E+05 Acute Lung 3.4E+05 1.1 E+05 6.1E+04 3.1E+04 2.0E+04 1.3E+04 8.0E+03 5.7E+03 Total Acute Bone 1.7E+05 7.9E+04 5.3E+04 3.3E+04 2.5E+04 1.9E+04 1.2E+04 9.0E+03 Inhalation CEDE 2.8E+05 9.0E+04 5.0E+04 2.5E+04 1.7E+04 1.1 E+04 6.3E+03 4.3E+03 Cloud Shine 1.1E+05 5.9E+04 4.2E+04 2.8E+04 2.1E+04 1.6E+04 1.1 E+04 7.9E+03 Period Gnd Shine 5.3E+04 1.7E+04 9.6E+03 4.9E+03 3.2E+03 2.0E+03 1.3E+03 9.4E+02 4-day Ground Shine 9.8E+04 3.2E+04 1.8E+04 9.0E+03 5.9E+03 3.8E+03 2.3E+03 1.6E+03 Notes:
- 1. Doses exceeding PAGs are underlined.
- 2. Early-Phase PAGs: TEDE - 1 rem, Thyroid CDE - 5 rem
- 3. *** indicates values less than 0.1 mrem To view all values - use Detailed Results I Numeric Table
- 4. Total EDE = CEDE Inhalation + Cloud Shine + 4-Day Ground Shine
- 5. Total Acute Bone = Bone Inhalation + Cloud Shine + Period Ground Shine Maximum Dose Values (rem) - To 10 miles Dist from release miles 3 4 5 7 10 (kilometers) (4.8) (6.4) (8.0) (11.3) (16.1)
Total EDE 2.4E+03 7.9E+03 4.4E+03 2.3E+03 1.4E+03 Thyroid CDE 3.1E+04 4.4E+04 2.9E+04 1.5E+04 8.7E+03 Acute Lung 1.5E+03 2.2E+03 1.5E+03 7.8E+02 4.4E+02 Total Acute Bone 1.1 E+03 6.1E+03 3.2E+03 1.7E+03 1.0E+03 Inhalation CEDE 1.2E+03 1.7E+03 1.1E+03 5.8E+02 3.3E+02 Cloud Shine 8.5E+02 5.7E+03 2.9E+03 1.5E+03 9.4E+02 Period Gnd Shine 2.4E+02 3.4E+02 2.3E+02 1.2E+02 6.0E+01 4-day Ground Shine 4.2E+02 5.9E+02 3.9E+02 2.0E+02 1.1E+02 Notes:
- 1. Doses exceeding PAGs are underlined.
- 2. Early-Phase PAGs: TEDE - 1 rem, Thyroid CDE - 5 rem
- 3. *** indicates values less than 0.1 mrem To view all values - use Detailed Results I Numeric Table
- 4. Total EDE = CEDE Inhalation + Cloud Shine + 4-Day Ground Shine
- 5. Total Acute Bone = Bone Inhalation + Cloud Shine + Period Ground Shine Case Summary Event Type Nuclear Power Plant Location Name: Brunswick - Unit 2 City, county, state: Southport, Brunswick, NC Printed: Tuesday, July 24, 2007 09:07 by RASCAL v3.0.4 Source Term to Dose Model Page 1 of 2
Summary Report Lat / Long / Etev: 33.9583° N, 78.0106° W, 5 m Time zone: Eastern Population (2000): 1,074/6,771 /25,619 (2/5/ 10 mi) Reactor Parameters Reactor power: 2923 MW(t) Average fuel burn-up: 32500 MWD / MTU Containment type: BWR Mark I Containment volume: 1.64E+05 ft3 Design pressure: 62 psig Design leak rate: 0.50 %/d Coolant volume: 3.22E+04 gal Assemblies in core: 560 Source Term Type: Monitored Release - Mixtures Shutdown: 07/24/2007 08:20 Sample ID: 0724070835 Sample taken: 07/24/07 08:35 Gross concentration: 2.20E+06 IJCi/cm 3 Flow rate: 1.50E+04 ft3/ min User defined percentages Noble gases: 99.0000/0 Halogens: 1.000 % Alkali metals: 0.000% Tellurium group: 0.0000/0 Barium, Strontium: 0.0000/0 Noble metals: 0.000% Lanthanides: 0.000% Cerium group: 0.000% Release Pathway Type: Direct to Atmosphere Release point: Not an isolated stack Release height: O. m Building wake effects: Computed Release timings To atmosphere start: 07/24/2007 08:35 To atmosphere duration: o days, and 01 :00 Meteorology Type: Actual Observations Data set name: 0724070835 Data set desc: BRUN Dir=67 Spd=13 Stab=E Precp=N Summary of data Dir Speed Stability Temp at release point: Type deg mph class Precip 07/24/2007 08:30 Obs 067 13.0 E None Calculations Case description: bnp0835 End of calculations: 07/24/2007 14:35 Distance of calculation: Close-in + to 10 miles Close-in distances: 0.1,0.2,0.3,0.5,0.7,1.0,1.5,2.0 miles Printed: Tuesday, July 24, 2007 09:07 by RASCAL v3.0.4 Source Term to Dose Model Page 2 of 2
Summary Report Case description: bnp0835 Run date/time: 07/24/2007 09:22 Maximum Dose Values (rem) - Close-In Dist from release miles 0.1 0.2 0.3 0.5 0.7 1. 1.5 2. (kilometers) (0.16) (0.32) (0.48) (0.8) (1.13) (1.61) (2.41 ) (3.22) Total EDE 2.7E+03 2.8E+03 2.8E+03 2.7E+03 2.6E+03 2.7E+03 2.7E+03 2.3E+03 Thyroid CDE *** *** *** 3.0E+02 2.8E+03 8.2E+03 1.3E+04 1.3E+04 Acute Lung *** *** *** 1.3E+01 1.2E+02 3.6E+02 5.5E+02 6.0E+02 Total Acute Bone 2.7E+03 2.8E+03 2.8E+03 2.7E+03 2.5E+03 2.4E+03 2.2E+03 1.8E+03 Inhalation CEDE *** *** *** 1.1 E+01 1.0E+02 2.9E+02 4.5E+02 4.7E+02 Cloud Shine 2.7E+03 2.8E+03 2.8E+03 2.7E+03 2.5E+03 2.3E+03 2.1E+03 1.7E+03 Period Gnd Shine *** *** *** 2.1E+00 1.9E+01 5.7E+01 8.7E+01 9.8E+01 4-day Ground Shine *** *** *** 3.8E+00 3.5E+01 1.0E+02 1.6E+02 1.7E+02 Notes:
- 1. Doses exceeding PAGs are underlined.
- 2. Early-Phase PAGs: TEDE - 1 rem, Thyroid CDE - 5 rem
- 3. *** indicates values less than 0.1 mrem To view all values - use Detailed Results I Numeric Table
- 4. Total EDE = CEDE Inhalation + Cloud Shine + 4-Day Ground Shine
- 5. Total Acute Bone = Bone Inhalation + Cloud Shine + Period Ground Shine Maximum Dose Values (rem) - To 10 miles Dist from release miles 3 4 5 7 10 (kilometers) (4.8) (6.4) (8.0) (11.3) (16.1)
Total EDE 6.6E+02 1.3E+03 9.9E+02 7.5E+02 3.6E+02 Thyroid CDE 6.4E+03 7.7E+03 5.7E+03 4.3E+03 2.1E+03 Acute Lung 3.0E+02 3.6E+02 2.8E+02 2.1E+02 1.1 E+02 Total Acute Bone 4.0E+02 9.6E+02 7.5E+02 5.7E+02 2.8E+02 Inhalation CEDE 2.3E+02 2.8E+02 2.1E+02 1.6E+02 7.9E+01 Cloud Shine 3.4E+02 8.9E+02 7.0E+02 5.3E+02 2.6E+02 Period Gnd Shine 4.8E+01 5.9E+01 4.5E+01 3.5E+01 1.7E+01 4-day Ground Shine 8.5E+01 1.0E+02 7.aE+01 6.0E+01 2.9E+01 Notes:
- 1. Doses exceeding PAGs are underHned.
- 2. Early-Phase PAGs: TEDE - 1 rem, Thyroid CDE - 5 rem
- 3. *** indicates values less than 0.1 mrem To view all values - use Detailed Results I Numeric Table
- 4. Total EDE = CEDE Inhalation + Cloud Shine + 4-Day Ground Shine
- 5. Total Acute Bone = Bone Inhalation + Cloud Shine + Period Ground Shine Case Summary Event Type Nuclear Power Plant Location Name: Brunswick - Unit 2 City, county, state: Southport, Brunswick, NC Printed: Tuesday, July 24, 2007 09:22 by RASCAL v3.0.4 Source Term to Dose Model Page 1 of 2
Summary Report Lat / Long / Elev: 33.9583° N, 78.0106° W, 5 m Time zone: Eastern Population (2000): 1,074/6,771 /25,619 (2 /5/ 10 mi) Reactor Parameters Reactor power: 2923 MW(t) Average fuel burn-up: 32500 MWD / MTU Containment type: BWR Mark I Containment volume: 1.64E+05 ft3 Design pressure: 62 psig Design leak rate: 0.50 0/0/d Coolant volume: 3.22E+04 gal Assemblies in core: 560 Source Term Type: Monitored Release - Mixtures Shutdown: 07/24/2007 08:20 Sample 10: 0724070835 Sample taken: 07/24/07 08:35 Gross concentration: 4.20E+05 JJCi/cm 3 Flow rate: 4.20E+04 ft3 /min User defined percentages Noble gases: 99.0000/0 Halogens: 1.0000/0 Alkali metals: 0.0000/0 Tellurium group: 0.000% Barium, Strontium: 0.000% Noble metals: 0.000% Lanthanides: 0.0000/0 Cerium group: 0.0000/0 Release Pathway Type: Direct to Atmosphere Release point: Isolated stack Stack height: 100. m Plume rise: Not computed Release timings To atmosphere start: 07/24/2007 08:35 To atmosphere duration: o days, and 01 :00 Meteorology Type: Actual Observations Data set name: 0724070835 Data set desc: BRUN Dir=68 Spd=15 Stab=E Precp=N Summary of data Dir Speed Stability Temp at release point: Type deg mph class Precip 07/24/2007 08:30 Obs 068 15.0 E None Calculations Case description: bnp0835 End of calculations: 07/24/2007 14:35 Distance of calculation: Close-in + to 10 miles Close-in distances: 0.1,0.2,0.3,0.5,0.7, 1.0, 1.5,2.0 miles Printed: Tuesday, July 24,2007 09:22 by RASCAL v3.0.4 Source Term to Dose Model Page 2 of 2
ATTACHMENT 6
, R~,.~/fs rc-c..or~ eS ""rc:.....,.., .
Page 1 of 1 Multiple Release Point Calculation Sheet NOTE: TEDE and Thyroid CDE Summation are in units of REM and must be converted to Units of mrem prior to entering the information onto the Emergency Notification Form (OPEP-02.6.21). ( (1) or (3) Rem x 1000 =__ mrem) (1) Each TEDE Column Total corresponds to line 16 (TEDE) of the Emergency Notification Form (OPEP-02.6.21). (2) Enter the Sum of Total Curies on line 14 MAGNITUDE: (Other) of the Emergency Notification Form (OPEP-02.6.21). (3) Thyroid CDE Column Total corresponds to line 16 (Thyroid CDE) of the Emergency Notification Form (OPEP-02.6.21 ). IOPEP-03.4.7 I Rev. 19 . I Page 50 of 541
NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM
- 1. DRILL ~ ACTUAL EVENT MESSAGE # 1+
2.~IN1TIAL I FOLLOW-UP NOTIFICATION: TIME' OATE_ _'_ _'_._ AUTHENTICATION # _
- 3. SITE: _ _B;::;...:ru;.....:..;...;.ns~Wl-*c~k:..---_ _ Confirmation Phone # ~ _
- 5. PROTECTIVE ACTION RECOMMENOATIONS: ~ NONE I EVACUATE ---.A B c. D E I SHELTER [IJ G'... H/ Ii'
§ CONSIDER THE USE OF KI (POTASSIUM 10000E) IN ACCOR£?ANCE WITH STATE PLANS AND POLlCY. ~ OTHER:.--..,.-- _
- 6. EMERGENCY RELEASE: ~Nooe
- Is Occurring § Has Occurred "Within fl<Xllla( opecatiog Above normal operating
- 7. RELEASE SIGNIFICANCE: ~ Not applicable ~ Under evaluation limits limits
- 8. EVENT PROGNOStS: ~Improving I Stable ~Oegrading
- 9. METEOROLOGICAL DATA: Wind Direction* from b 8: degrees Wind Speed* I :r mph
(*Not Required for loitialNotificatiQos) Precipitation* ti~ n e... Stability C1ass* Ej ~ § § * ~ ~. 10*.1 DECLARATION ~ TERMINATION Time Date Tol;Atl_ _' _
- 11. 'AFFECTED UNIT(S}: [J § 12_ UNIT STATUS: ~ U1 _ _% Power Shutdown at Ttme Date _ ,_ _, _
(Unaffected Unit(s) Status Not Required for Initial Notifications) .'U2 _ _% Power ShutdoYln at Tame Date (, FOLlOW-UP"INFORMATION (Lines 14 through 16 Not Required for Initial Notifications) EMERGENCY RELEASE DATA. NOT REQU1REO IF LINE 6 A IS SELECTED.
- 14. RELEASE CHARACTERIZATION: TYPE:EjElevated ~"Mixed I*Ground UN1TS:EjCi MAGNITUDE: Noble Gases: N/A lodines: N/A Particulates: NfA Other: _
FORM: I Airborne Start Time Date tbb1~/ __Stop Time Date _ ,_ _,_ _
~ Liquid Start Time" Date _ '_ _I_ _Stop Time Date _ ,_ _,_ _
- 15. PROJECTION PARAMETERS: Projection period: , Hours Estimated Release Duration I Hours Projection performed: Time Date _ '_ _'_ _
- 16. PROJECTED DOSE: DISTANCE TEOE (mrem) Adult Thyroid CDE (mrem)
Site boundary /- 2/,2 f"f J. '1:2 oj £ 'f 2 Miles 3.01 f::> SMiles 10 Miles
- 17. APPROVED BY: Title _ Time Oate_'_ _' _ _
NOTIFIED RECEIVED BY: "BY: _ Time Date _1_ _' __ EM-78t Nuclear Power-Facility Emergency Notification Form December 2004
NRC SRO ADMIN JPM A-4 1 of 11 PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SRO NRC ADMIN JPM A-4 TITLE: *Event Classification/PAR
NRC SRO ADMIN JPM A-4 2 of 11 TASK CONDITIONS: The following conditions exist in Unit Two (2) which had been operating at 1OOo~ power. TIME 1200
- 1. A Tornado has hit the site causing a Station Blackout.
- 2. Emergency Diesel Generators #1 ,#3, and #4 tripped immediately after starting and can not be re-started.
- 3. A scram signal occurred and numerous control rods did not insert, current power level is 70/0.
- 4. Drywell Pressure is 1.1 psig and slowly rising.
- 5. Reactor Water Level is being maintained 170" to 200".
- 6. The current Wind Speed is 6 MPH from 45 degrees.
- 7. Weather Stability Class is "D". There is no precipitation.
INITIATING CUE: Based on the above conditions, you are to determine the event classification and complete the required notification paperwork per OPEP-02.1, Initial Emergency Actions. This is a time critical JPM.
NRC SRO ADMIN JPM A-4 3 of 11 EXAMINER NOTE: The 15 minute clock will not start until the applicant states they understand the task conditions. No procedures can be referenced prior to the clock starting. 15 Minute Clock Start Time- - - Time of Declaration - - - - - Time Notification Form is provided _ Step 1 - Reviews the given conditions and within 15 minutes determines that a Site Area Emergency declaration is required per OPEP-02.1, Attachment 1, Step 05.03.01 Within 15 minutes Declares SITE AREA EMERGENCY per Att.1 Step 05.03.01 CRITICAL TASK SAT/UNSAT
NRC SRO ADMIN JPM A-4 4 of 11 PROMPT: 5 Minutes after the declaration of the Site Area Emergency, provide the second set of conditions for evaluation to the candidate. TIME of updated conditions : _ TASK CONDITIONS - SECOND SET
- 1. Reactor power is 3%.
- 2. Emergency Diesel Generator #3 has been returned to service and has energized Emergency Bus E-3.
- 3. Reactor Water Level is being maintained 170" to 200"
- 4. Drywell Pressure is 1.1 psig and stable.
- 5. SLC Pump 2A is in-service, injecting Boron into the Reactor vessel.
- 6. The current Wind Speed is 6 MPH from 45 degrees.
- 7. Weather Stability Class is "0". There is no precipitation.
- 8. Security supervision has just notified the control room that two terrorists have taken control of the DG building.
- 9. A loss of control power annunciator to #4 Emergency Diesel Generator has just alarmed.
INITIATING CUE: Based on. the above conditions, you are to determine any impact on the event classification and complete the required notification paperwork per OPEP-02.1, Initial Emergency Actions.
NRC SRO ADMIN JPM A-4 5 of 11 Step 2 - Review the given conditions and within 15 minutes determines that a General Emergency declaration is required per OPEP-02.1, Attachment 1, Step 11.04.01. 15 Minute Clock Start Time- - - Time of Declaration - - - - - Within 15 minutes Declares GENERAL EMERGENCY per Att.1 step 11.04.01. CRITICAL TASK SAT/UNSAT NOTE: The 14-minute time limit in the following step is based on the allowance of 1 minute for the Emergency Communicator to contact off-site agencies. NOTE: In the following notification steps, two potential sequences exist. Sequence 1: If the candidate reports the events separately, clocks are running for each event, with a 14 minute notification time requirement for each event. Sequence 2: The candidate may choose to only make the report for the General Emergency. If this option is used, the notification with the required Protective Action Recommendations (PARs) must be completed within 14 minutes of the declaration of the first event. In this case, the notification will be for a General Emergency.
NRC SRO ADMIN JPM A-4 6 of 11 Step 3 - Within 14 minutes of the declaration of the Site Area Emergency, provide the completed Emergency Notification Form to the evaluator for transmittal. Critical items on notification form are #1,2,4,5,6,7,8,10,11,12, 17. Emergency Notification Form provided.
**CRITICAL TASK*
*SAT/UNSAT NOTE: If the applicant refers to Att. 4 of OPEP-02.1.1 for Hostile events, state that another operator is addressing those actions.
NOTE: See description above for one, versus two, notifications. Step 4 - Completes Emergency Notification Form for the General Emergency Declaration with associated Protective Action Recommendations (PARs) within 14 minutes of the emergency declaration. Critical items on notification form are
- 1,2,4,5,6,7,8,10,11,12,17 Within 14 minutes of General Emergency declaration, completes Emergency Notification Form with associated Protective Action Recommendations.
Evacuate -A,B,C,D and Shelter- E,F,G,H,&K Time of declaration - - - - Time Notification Form is provided _
**CRITICAL STEP**
NRC SRO ADMIN JPM A-4 7 of 11 SAT/UNSAT
NRC SRO ADMIN JPM A-4 8 of 11 NOTE: The Applicant should provide you the completed notification form within the specified time frames. (see keys provided) Terminating CUE: The JPM is complete once the declarations are made and the Nuclear Power Plant Emergency Notification Forms are provided. '
NRC SRO ADMIN JPM A-4 9 of 11 KIA REFERENCE AND IMPORTANCE RATING: 2.4.44/4.0 Knowledge of Emergency Plan Protective Action Recommendations
REFERENCES:
OPEP-02.1, Rev 50 TOOLS AND EQUIPMENT: None. SAFETY FUNCTION (from NUREG 1123, Rev 2.): A.4 - Emergency Procedures/Plan APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit: -l Setting: Control Room _ Simulator Time Critical: Yes X No Time Limit: 15 minutes for each declaration and 14 minutes for each notification form Alternate Path: Yes No X EVALUATION JPM: Pass - - - - Fail - - - - Comments:
TASK CONDITIONS: The following conditions exist in Unit Two (2) which had been operating at 1000/0 power. TIME 1200
- 1. A Tornado has hit the site causing a Station Blackout.
- 2. Emergency Diesel Generators #1, #3, and #4 tripped immediately after starting and can not be re-started.
- 3. A scram signal occurred and numerous control rods did not insert, current power level is 7%.
- 4. Drywell Pressure is 1.1 psig and slowly rising.
- 5. Reactor Water Level is being maintained 170" to 200".
- 6. The current Wind Speed is 6 MPH from 45 degrees.
- 7. Weather Stability Class is "0". There is no precipitation.
INITIATING CUE: Based on the above conditions, you are to determine the event classification and complete the required notification paperwork per OPEP-02.1, Initial Emergency Actions. This is a time critical JPM.
TIME of updated conditions : _ TASK CONDITIONS - SECOND SET
- 1. Reactor power is 3%.
- 2. Emergency Diesel Generator #3 has been returned to service and has energized Emergency Bus E-3.
- 3. Reactor Water Level is being maintained 170" to 200"
- 4. Drywell'Pressure is 1.1 psig and stable.
- 5. SLC Pump 2A is in-service, injecting Boron into the, Reactor vessel.
- 6. The current Wind Speed is 6 MPH from 45 degrees.
- 7. Weather Stability Class is "D". There is no precipitation.
- 8. Security supervision has just notified the control room that two terrorists have taken control of the DG building.
- 9. A loss of control power annunciator to #4 Emergency Diesel Generator has just alarmed.
INITIATING CUE: Based on the above conditions, you are to determine any impact on the event classification and complete the required notification paperwork per OPEP-02.1, Initial Emergency Actions. This is a time critical JPM.
KEY-Eye-f)! I NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM
- 1. lDRILL f§l ACTUAL EVENT MESSAGE # [lfl 2*IINfTIAL f§l FOLLOW-UP NOTIFICATION: TIME DATE_ _I_ _I_ _ AUTHENTICATION # _
- 3. SITE: _ _~B..:....;;ru_n~sw_i~c~k _ Confirmation Phone # L-) _
- 4. EMERGENCY CLASSIFICATION:
~ UNUSUAL EVENT f§l ALERT I SITE AREA EMERGENCY IQl GENERAL EMERGENCY BASED ON EAL #~_-L-~~ -P I None ~ Is Occurring § Has Occurred
- 7. RELEASE SIGNIFICANCE: I Not applicable Within normal operating limits Above normal operating limits (Q] Under evaluation
- 8. EVENT PROGNOSIS: ~ Improving I Stable ~ Degrading
- 9. METEOROLOGICAL DATA: Wind Direction* from ,,~ degrees Wind Speed* 6:, mph
(*Not Required for Initial Notifications) Precipitation* Nu n ~ Stability Class* ~ ~ § I [§ [B ~. 10*1 DECLARATION ~ TERMINATION Time Per :rPH Date fQ-pA,_i__, _
- 11. AFFECTED UNIT(S): mI
- 12. UNIT STATUS: ~U1 _ _o,fo Power Shutdownatl1me Date _ ,_ _, _
(Unaffected Unit(s) Status Not Required for Initial Notifications) I.U2 -L-% t7. Power Shutdown at Time Date _ ,_ _, _ On - ~ill:.. :p:c-;l~ CL~e be ,0 ~~~4r4.r? ii (s- ---:D -:::z.
- 13. REMARKS: .. 5 off - s ( t~ If () LL. 0 i; I",=~ ~ e. aI L ~f CL
- i 0 c e.
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications) EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED~
- 14. RELEASE CHARACTERIZATION: TYPE: ~ Elevated [§l Mixed § Ground UNITS: ~ Ci MAGNITUDE: Noble Gases: N/A lodines: N/A Particulates: N/A Other: _
FORM: ~ Airborne Start Time Date _1_ _' _ _Stop Time Date _ '_ _I__ I§] Liquid Start Time Date _1_ _I_ _Stop Time Date _ '_ _1__
- 15. PROJECTION PARAMETERS: Projection period: Hours Estimated Release Duration Hours Projection performed: Time Date _ ,_ _,_ _
- 16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid COE (mrem)
Site boundary 2 Miles 5 Miles 10 Miles
- 17. APPROVED fer Jr'J1 ~f)\)11'1 BY: Titre _---.....S~£c__c....... _ Time c{<? e-/C.. Date_'_ _I__
NOTIFIED RECEIVED By:-.,..- _ "BY: _ Time Date _ ,_ _,_ _ EM..78 I Nuclear Power Facility Emergency Notification Form December 2004
(£y- £~~nf 2 . NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM 1*IORILL I§l ACTUAL EVENT MESSAGE # 1!12
- 2. I INfTIAL I§l FOLLOW-UP NOTIFICATION: TIME DATE_ _I_ _I_ _ AUTHENTICATION # _
- 3. SITE: B---,ru_n---,sw_i_c~k _ Confirmation Phone # L-) _
- 4. EMERGENCY CLASSIFICATION:
[§l ALERT 19 SITE AREA EMERGENCY I GENERAL EMERGENCY BASED ON EAL #-...:.~~~'--=-- EAL DESeRtPTION: ---I.-l----L.L-=---..l