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| {{#Wiki_filter:ug Pi(4g'EGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/78 NRC IN 8c MI PWR DATE RCVD: 04/24/78 DOCTYPE: LETTER NOTARIZED: | | {{#Wiki_filter:ug Pi(4g'EGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS) |
| NO COPIES RECEIVED | | DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/78 NRC IN 8c MI PWR DATE RCVD: 04/24/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LTR 1 ENCL 1 FURNISHING REPT PURSUANT TO APPENDIX A TECH SPEC 3.4.8 8(6.5'.1 CONCERNING ON 03/07/78 THE DOSE EQUIVALENT IODINE-131 ACTIVITY IN UNIT 1 REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION... | | LTR 1 ENCL 1 FURNISHING REPT PURSUANT TO APPENDIX A TECH SPEC 3. 4. 8 8( 6. 5'. 1 CONCERNING ON 03/07/78 THE DOSE EQUIVALENT IODINE-131 ACTIVITY IN UNIT 1 REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION... W/ATT SUPPORTING INFO. |
| W/ATT SUPPORTING INFO.PLANT NAME: COOK-UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS++++++%~<+++~+++~~ | | PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL: ~~ |
| GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.(DISTRIBUTION CODE AQOi)FOR ACTION: INTERNAL: EXTERNAL: BR CHIEF SCHWENCER++W/7 ENCL~G F LE~~W/ENCL HANAUER~~W/ENCL E I SENHUT+4 W/ENCL BAER++W/ENCL EE84+W/ENCL J.MCGOUGH>+M/ENCL LPDR S ST.JOSEPH'I<<W/ENCL TI C++W/ENCL ,NS I C4 4W/ENCL;ACRS CAT B+%N/16 ENCL NRC PDR++W/ENCL OELD+<LTR ONLY CHECK4+W/ENCL SHA0%4W/ENCL BUTLER++M/ENCL J COLLINS+<W/ENCL Save~auea,/<pP~~i m f/DuS~m E>CC.+o YArc'~/++7 | | DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++++++%~<+++~+++~~ |
| ~~C y cue~~Voc.bwkw/g~>e A(pm<tCREaER.Ros p EdcL g~Secre i~DISTRIBUTION: | | GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE. |
| LTR ENCL~SIZE: 2P+6P CONTROL NBR: 781150033.1 NR~END I I I I t I"t t t II I I" I t t e lt II I oi o er4can/iEleotrlo INDIANA&MICHIGAN PDNER COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 (616)465-5901 Nr.J.G.Keppler, Regional Director Office of Inspection and Enforcement U.S.Nuclear Regulatory Comission Region III 799 Roosevelt Road Glen Ellyn, Il 60137 April 4, 1978 Operating License DPR-58;"" Docket 0 50-315~t'I CD P1 Cll<<-1 M f%w c'i~l IQ D)l ll Rtv tel CA~cjl~A7"5 CD
| | (DISTRIBUTION CODE AQOi) |
| | FOR ACTION: BR CHIEF SCHWENCER++W/7 ENCL INTERNAL: ~G F LE~~W/ENCL NRC PDR++W/ENCL OELD+<LTR ONLY HANAUER~~W/ENCL CHECK4+W/ENCL E ISENHUT+4 W/ENCL SHA0%4W/ENCL BAER++W/ENCL BUTLER++M/ENCL EE84+W/ENCL J COLLINS+<W/ENCL J. MCGOUGH>+M/ENCL Save~auea, /< pP~~i m EXTERNAL: |
| | f/DuS~ m E>CC. |
| | LPDR S +o ST. JOSEPH'I<<W/ENCL TI C++W/ENCL YArc'~/++7 |
| | ~ ~C |
| | ,NS I C4 4W/ENCL y cue~~ |
| | ;ACRS CAT B+%N/16 ENCL Voc.bwkw /g~>e A( pm< |
| | tCREaER. |
| | Ros p EdcL g Secre i~ |
| | ~ |
| | DISTRIBUTION: |
| | SIZE: 2P+6P LTR ENCL ~ CONTROL NBR: 781150033.1 NR ~ |
| | END |
| | |
| | I I I I t I |
| | "t t t II I I" |
| | I t t e |
| | lt II I |
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| | oi o |
| | er4can |
| | /iEleotrlo INDIANA& MICHIGANPDNER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 |
| | <<-1 f%w c'i |
| | ~l IQ April 4, 1978 D)l ll M Rtv Operating License DPR-58;"" tel CA~ cjl Docket 0 50-315 ~A7 |
| | ~t'I CD "5 CD P1 Cll Nr. J. G. Keppler, Regional Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Region III 799 Roosevelt Road Glen Ellyn, Il 60137 |
| | |
| | ==Dear Mr. Keppler:== |
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| ==Dear Mr.Keppler:==
| |
| This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1, On l1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification. | | This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1, On l1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification. |
| At 1003 on March 7, 1978 Unit 1 reactor tripped from 1005 power.Immediately following the trip, letdown purification flow was increased to its maximum.Analysis at 1130 on March 7, 1978, indicated dose equivalent iodine-131 at 1.025.pCi/cc.Maximum dose equivalent iodine-131 concentration was detected at 1345 to be 1.046 pCi/cc*~Dose equi-valent iodine-131 remained out of specification until 1440.All ad-ditional sample analysis indicated the reactor coolant dose equivalent iodine-131 remained in specification and was decreasing. | | At 1003 on March 7, 1978 Unit 1 reactor tripped from 1005 power. |
| No additional spiking was noted during the subsequent reactor startup.No degassing operations were associated with this event.Iodine release at this time period is consistent with data reported in Westinghouse Electric Corporation WCAP-8637,"Iodine Behavior under Transient Conditions in the Pressuirzed Water Reactor".Dose equivalent iodine-131 values were in the"Acceptable Operation" portion of Technical APR 6 1978 781150033 goo I\J~I 0"~*4 o b I, April 4, 1978 Mr.J.G.Keppler Page Two Specification Figure 3,4.1 at all times during the transient. | | Immediately following the trip, letdown purification flow was increased to its maximum. Analysis at 1130 on March 7, 1978, indicated dose equivalent iodine-131 at 1.025. pCi/cc. Maximum dose equivalent iodine-131 concentration was detected at 1345 to be 1.046 pCi/cc* ~ Dose equi-valent iodine-131 remained out of specification until 1440. All ad-ditional sample analysis indicated the reactor coolant dose equivalent iodine-131 remained in specification and was decreasing. No additional spiking was noted during the subsequent reactor startup. No degassing operations were associated with this event. |
| Fuel burnup by core region and all additional data is indicated in the attached table/graphs. | | Iodine release at this time period is consistent with data reported in Westinghouse Electric Corporation WCAP-8637, "Iodine Behavior under Transient Conditions in the Pressuirzed Water Reactor". Dose equivalent iodine-131 values were in the "Acceptable Operation" portion of Technical APR 6 1978 goo 781150033 |
| *Coolant samples are brought to.ambient conditions prior to counting, therefore, units of pCi/g and pCi/cc are considered interchangeable. | | |
| Very truly yours,+c~D.V.Shaller Plant Manager attachments cc: R.W.Jurgensen J.'.Dolan R.Kilburn R.F..Kroeger R.J.Vol 1 en, BPI K.R.Baker, RO: III P.W.Steketee, Esq.R.C.Callan R.Walsh, Esq.G.Olson J.Stietzel PNSRC File G.Charnoff, Esq.J.M.Hennigan Dir, IE (20 copies)Dir, MIPC (2 copies) | | I J |
| | \ |
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| | |
| | April 4, 1978 Mr. J. G. Keppler Page Two Specification Figure 3,4.1 at all times during the transient. Fuel burnup by core region and all additional data is indicated in the attached table/graphs. |
| | * Coolant samples are brought to. ambient conditions prior to counting, therefore, units of pCi/g and pCi/cc are considered interchangeable. |
| | Very truly yours, |
| | +c ~ D. V. Shaller Plant Manager attachments cc: R. W. Jurgensen J.'. Dolan R. Kilburn R. F.. Kroeger R. J. Vol 1 en, BPI K. R. Baker, RO: III P. W. Steketee, Esq. |
| | R. C. Callan R. Walsh, Esq. |
| | G. Olson J. Stietzel PNSRC File G. Charnoff, Esq. |
| | J. M. Hennigan Dir, IE (20 copies) |
| | Dir, MIPC (2 copies) |
| | |
| '( | | '( |
| HARCH 7, 1978 UNIT NO.1 CYCLE NO.2 Fuel Burnup by Core Reason REGION NO.BURNUP FOR PERIOD (~D(WU)CUHULATI VE BURNUP (teD/mu)ENERGY FOR PERIOD (BTU)CUNULAT I VE ENERGY (BTU).0.1799E+04 0.2053E+04 0.2802E+05 0.2397E+05 0.1871E+04 | | HARCH 7, 1978 UNIT NO. 1 CYCLE NO. 2 Fuel Burnup by Core Reason REGION NO. BURNUP CUHULATIVE ENERGY CUNULATI VE FOR PERIOD BURNUP FOR PERIOD ENERGY |
| .0.9543E+04 0.4267E+13 0.4290E+13 0.4867E+13 0.2176E+14 0.6681E+14 0.5685E+14 CORE TOTAL 0.1908E-:04 0.2067E+05 0.1342E+14 0.1454E+15
| | (~D(WU) (teD/mu) (BTU) (BTU) 0.1871E+04 . 0.9543E+04 0.4267E+13 0.2176E+14 |
| , IO 9 8 (7 CC 0 o f C8/AJ 7 Q 2~O I-R~O<L~Cv Oz 0 II 2o O1 I H 4I 0 I 9 L 4I Z u L 2 Z CL Q 14" O 2 Ql Z g I 0~-III OL-I-0 4I p O p>O O>X~4I p)NN 4I U D 2 9 0$'op JS po e iF 0 lvo I I pg Vo~ | | .0.1799E+04 0.2802E+05 0.4290E+13 0.6681E+14 0.2053E+04 0.2397E+05 0.4867E+13 0.5685E+14 CORE TOTAL 0.1908E-:04 0.2067E+05 0.1342E+14 0.1454E+15 |
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MONTHYEARAEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. 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Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System ML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) 2024-09-09
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Text
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DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 04/04/78 NRC IN 8c MI PWR DATE RCVD: 04/24/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FURNISHING REPT PURSUANT TO APPENDIX A TECH SPEC 3. 4. 8 8( 6. 5'. 1 CONCERNING ON 03/07/78 THE DOSE EQUIVALENT IODINE-131 ACTIVITY IN UNIT 1 REACTOR COOLANT SYSTEM WAS FOUND OUT OF SPECIFICATION... W/ATT SUPPORTING INFO.
PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL: ~~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++++++%~<+++~+++~~
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AQOi)
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/iEleotrlo INDIANA& MICHIGANPDNER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901
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~l IQ April 4, 1978 D)l ll M Rtv Operating License DPR-58;"" tel CA~ cjl Docket 0 50-315 ~A7
~t'I CD "5 CD P1 Cll Nr. J. G. Keppler, Regional Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Region III 799 Roosevelt Road Glen Ellyn, Il 60137
Dear Mr. Keppler:
This report is submitted persuant to the requirement of Appendix A Technical Specification 3.4.8 and 6.9.1, On l1arch 7, 1978, the dose equivalent iodine-131 activity in Unit 1 reactor coolant system was found out of specification.
At 1003 on March 7, 1978 Unit 1 reactor tripped from 1005 power.
Immediately following the trip, letdown purification flow was increased to its maximum. Analysis at 1130 on March 7, 1978, indicated dose equivalent iodine-131 at 1.025. pCi/cc. Maximum dose equivalent iodine-131 concentration was detected at 1345 to be 1.046 pCi/cc* ~ Dose equi-valent iodine-131 remained out of specification until 1440. All ad-ditional sample analysis indicated the reactor coolant dose equivalent iodine-131 remained in specification and was decreasing. No additional spiking was noted during the subsequent reactor startup. No degassing operations were associated with this event.
Iodine release at this time period is consistent with data reported in Westinghouse Electric Corporation WCAP-8637, "Iodine Behavior under Transient Conditions in the Pressuirzed Water Reactor". Dose equivalent iodine-131 values were in the "Acceptable Operation" portion of Technical APR 6 1978 goo 781150033
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April 4, 1978 Mr. J. G. Keppler Page Two Specification Figure 3,4.1 at all times during the transient. Fuel burnup by core region and all additional data is indicated in the attached table/graphs.
- Coolant samples are brought to. ambient conditions prior to counting, therefore, units of pCi/g and pCi/cc are considered interchangeable.
Very truly yours,
+c ~ D. V. Shaller Plant Manager attachments cc: R. W. Jurgensen J.'. Dolan R. Kilburn R. F.. Kroeger R. J. Vol 1 en, BPI K. R. Baker, RO: III P. W. Steketee, Esq.
R. C. Callan R. Walsh, Esq.
G. Olson J. Stietzel PNSRC File G. Charnoff, Esq.
J. M. Hennigan Dir, IE (20 copies)
Dir, MIPC (2 copies)
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HARCH 7, 1978 UNIT NO. 1 CYCLE NO. 2 Fuel Burnup by Core Reason REGION NO. BURNUP CUHULATIVE ENERGY CUNULATI VE FOR PERIOD BURNUP FOR PERIOD ENERGY
(~D(WU) (teD/mu) (BTU) (BTU) 0.1871E+04 . 0.9543E+04 0.4267E+13 0.2176E+14
.0.1799E+04 0.2802E+05 0.4290E+13 0.6681E+14 0.2053E+04 0.2397E+05 0.4867E+13 0.5685E+14 CORE TOTAL 0.1908E-:04 0.2067E+05 0.1342E+14 0.1454E+15
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