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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 |
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| | I I I I t I |
| | "t t t II I I" |
| | I t t e |
| | lt II I |
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| | 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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Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
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Text
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: 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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