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Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. 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
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2017-0012017-05-19019 May 2017 1 OF 5, LER 17-001-00 for Cook, Unit 2 re Containment Hydrogen Skimmer Ventilation Fan #1 Inoperable Longer than Allowed by Technical Specifications 05000316/LER-2016-0022017-02-0909 February 2017 Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue, LER 16-002-00 for Donald C. Cook Nuclear Plant Unit 2 Regarding Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue 05000316/LER-2016-0012016-08-31031 August 2016 Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure, LER 16-001-00 for Donald C. Cook Nuclear Plant, Unit 2 Regarding Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure ML16193A3902016-07-15015 July 2016 Donald C. Cook Nuclear Plant Unit 2 - A Loss of Main Condenser Event Occurred Due to a Storm-Induced Debris Damage of the Circulating Water System Pumps in the Forebay (LER-316-2014-003-00) 05000315/LER-2015-0022016-01-18018 January 2016 -Technical Specification Violation due to Inoperable Residual. Heat Removal Pump, LER 15-002-01 for D.C. Cook, Unit 1, Regarding Technical Specification Violation Due to Inoperable Residual Heat Removal Pump 05000316/LER-2015-0012016-01-15015 January 2016 Manual Reactor Trip Due To A Secondary Plant Transient, LER 15-001-01 for D.C. Cook, Unit 2, Regarding Manual Reactor Trip Due to a Secondary Plant Transient ML0528703602005-10-0505 October 2005 Special Report for D. C. Cook Unit 2 Re Unit 2 Reactor Coolant Inventory Tracking System ML0508903452005-03-22022 March 2005 LER 99-001-01 Donald C. Cook Nuclear Plant Unit 2, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations ML0210601432002-04-12012 April 2002 LER 02-02-00, Donald C. Cook Nuclear Plant Unit 2, Technical Specification 3.9.4.c Was Violated During Core Alteration ML0209205342002-03-15015 March 2002 LER 99-012-01 for Cook Nuclear Plant, Unit 1 Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident ML9936300511999-12-20020 December 1999 LER 99-S004-00, Intentionally Falsifying Documentation Results in Unauthorized Unescorted Access, on 11/18/99. with Letter Dated 12/20/99 ML9934002411999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5211978-09-19019 September 1978 09/19/1978 Letter Enclosure of Licensee Event Report ML18219E1531978-09-18018 September 1978 Submit Licensee Event Report No. RO 78-050/03L-0 ML18219B5541978-09-18018 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-062/03L-0) ML18219B5551978-09-12012 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-56/03L-1 and RO 78-061/03L-0) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-0 ML18219B5561978-09-0808 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0) ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-0 ML18219B5571978-09-0505 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0 ML18219B5581978-08-30030 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0 ML18219B5621978-08-22022 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0) ML18219B5611978-08-18018 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0) ML18219E1561978-08-15015 August 1978 Submit Licensee Event Report No. RO 78-047/03L-0 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1601978-08-11011 August 1978 Submit Licensee Event Report Nos. 1978-043-03L & 1978-044-03L ML18219B5641978-08-10010 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-051/03L-0) ML18219B5651978-08-0909 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-1) ML18219B5661978-08-0808 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-050/03L-0) ML18219B5671978-08-0404 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-0) ML18219B5681978-08-0202 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-029/03L-1 and RO 78-048/03L-0) ML18219B5691978-07-21021 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-019/03L-1 and RO 78-023/03L-1) ML18219B5701978-07-18018 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-047/03L-0) ML18219B5711978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-043/03L-0), Submitted Late Due to a Paper Defect ML18219B5721978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0) ML18219B5731978-07-0505 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-042/03L-0) ML18219B5751978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken IR 05000316/19780371978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken ML18219B5771978-06-22022 June 1978 D.C. Cook - Submit Licensee Event Report RO 78-036/03L-0 for Unit 2 ML18219B5761978-06-21021 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-035/03L-0), a Resubmittal of LER 78-034/03L-0 Dated 6/19/1978 IR 05000316/19780341978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5221978-06-0606 June 1978 06/06/1978 Letter Licensee Event Report ML18219B5741978-06-0303 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-038/03L-0, RO 78-039/03L-0, RO 78-040/03L-0, RO 78-041/03L-0) ML18219B5241978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5231978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5251978-05-25025 May 1978 05/25/1978 Letter Licensee Event Report 2017-05-19
[Table view] |
Text
NUCLEAR REGULATORY COMMISSION DOCKET NUMBER NRC FORM ~195 I2 7g)
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SO- 3(A FILE NUMBER
'NRC DISTRIBUTION FoR ART 50 DOCKET MATERIAL INCIDENT REPORT Tp. J G Keppler FROM: Indiana & Michigan P1m Co DATE OF DOCUMENT l"24-77 Brid'gman, .Mich R W Jurgensen DATE RECEIVED gLETTE goRIGINAI R>> 0 NOTOR IZE 0' PROP INPUT FORM NUMBER OF COPIES RECEIVED
"~ kfUNCLASSIFIED ~ one signed COP Y DESCRIPTION ENCLOSURE
.Ltr ts'ans the follo17ing: RO 76- 9)-on 12-24-76'alent og Reactor coolant malysis tw iodine scapi e~ollowing transient,;...',
du'e'ower lp'LANT NAME Cook g ]
NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J COLLINS
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'%rneramn G,*i:M~ED 8 MCO~llX DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 January 24, 1977 Freed~ >~7>
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Mr. J. G. Keppler., Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevel t Road Glen El lyn, IL 60137 Operating Li cense DPR-58 Docket No. 50-315
Dear Mr. Keppler:
Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 4, Section 2.b, the following report is submi tted:
RO-50-315/76-59 Sin ce rely,
. W. Ju ens Plant M nager 'RegutBto>'u ":Ip RW J/mj
>> g'ac cc: R. S. Hunter J. E. Dolan G. E. Lien R. Ki ~ lb urn R. J.'Vollen BPI R. C. Callen MPSC K. R. Baker RO: III R. Walsh, Esq.
P. W. Steketee, Esq.
G. Charnoff, Esq.
G. Olson J. M. Hennigan PNSRC R. S. Kei th Dir., IE (30 copies)
Dir., MIPC (3 copies)
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Llt"ENSEE EVENT REPORT CONTROL BLOCK: SE PRINT ALL REQUIRED INFORIVIATIOM3 6""
1'ICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE
[opj M I 0 C C 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03 7 89
- 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT OATE Ion~Icon'~ L ~L 0 5 0 0 3 1 5 68 69 1 2 2 4 7 5 74 0
75 1 2 4 7, 7 80 7 8 57 58 59 60 61 I
EVENT DESCRIPTION Qpg ON DECEMBER 23'976 AT 2100 HOURS POWER REDUCTION WAS STARTED WITH THE UNIT TRIPPED 7 8 9 80 FROM APPROXIMATELY 7X AT 0008 HOURS ON DECEMBER 24, 1976. REACTOR COOLANT ANALYSIS 7 89 ~ .. 80
[oOP4 SHOWED DOSE E UIVALENT I-131 ACTIVITY TO BE 3.1 uCi m. THIS IS IN EXCESS OF LIMIT 7 8 9 7 8 9 80
[oaf R0-50-315/76-52,0N NOVEMBER 20, 1976. (RO-50-315/76- 59 )
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-80 SYSTEM CAUSE COMPON84T COMPONENT CODE CODE COMPONENT CODE SUPPLER MANUFACTURER Ioc7I ~zz ~F z z z z z Z
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48 7 8 9 10 .11 12 CAUSE DESCRIPTION
[oOs] SEE SUPPLEMENT 7 8 9 80
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7 8 9 80 QO]
89 80 FACIUTY STATUS POWER 'THER STATUS METHOD OF DISCOVERY DISCOVERY DESCRIPTION
@171 ~G ~00 0 NA 44 45 46 ROUTINE SAMPLING 80 7 8 9 10 .12 13 FORM OF ACTIVITY COATENT REI.EASED OF RELEASE, AMOUNT OF ACTIVITY LOCATiON OF RELEASE 2J Z Z NA
~ 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q~aj ~00 0 Z NA 80 7 89 11 12 13 PERSONNEL INJURIES 7 8 9" 11 12 80 PROBAHLTE CONSEQUENCES Qqg NA 7 8 9 80 LOSS OR DAMAGE TO FACIUTY PE OESCIIIATION 7 89 ~ 10 PUBLICITY NA 7 89 80 ADBITIONAL FACTORS Q~e] NA 7 89 80
~18 NA 7 89 80 J L RI SCHL I NG PHGNE(616)465-5901(368)
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~ i SUPPLEME 0 REPORTABLE OCCURRENCE RO 50 5 76 59 ff INDIANA & MICHIGAN'OWER COMPANY DONALD C. COOK NUCLEAR PLANT Iodine S'ike Followin PowerTransient As this shutdown was planned and, due to the iodine spiking noted following reactor trip on November 20, 1976, a revised sampling program had been set up to increase the data collection frequency. This program consisted of collecting samples each two hours prior to unit shutdown, each half hour for the first four hours following reactor trip and each two hours after that period until data stabilized.
Reactor power had been slowly decreasing during the week prior to shutdown due to core stretch out, with power in the 90%%d range 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first out-of-specification sample.* On December 23, 1976, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, reactor power reduction was started with the unit tripped from approximately 7S power at 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on December 24, 1976. In pre-paration for shutdown, CVCS purification flow had been increased to maximum (120-125 gpm) on December 13, 1976, and maintained at this level through shutdown.", Volume control tank hydrogen pressure was reduced at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on December 23, 1976, in preparation for degassing of the system with remain-ing degassing operations (VCT level increase and venting to the gas header) starting at 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on December 24, 1976, with three tank purges completed by 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on December 25, 1976.
Primary coolant I-131 activity following return to equilibrium after the November 30, 1976 reactor trip had stabilized at 1.5-- 2.0xlO-z wCi/cc.~
I-131 activity remained at this level until 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on December 24, 1976 when the activity increased to 2.5 yCi/cc, approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> following initiation of power reduction. Iodine release at this time period is consis-tent with data reported in Westinghouse Electric Corporation WCAP-8637, "Iodine Behavior Under Transient Conditions in the Pressurized Water Reactor." The increased data collection sampling frequency after the spike indicates that the I-131 activity began decreasing immediately following the initial spike with values remaining constant at approximately 1.6 pCi/cc for an 8 - 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period before further decrease (See Figure 2). I-133, 135 values showed trends similar to the I-131 activity (Figure 3). DOSE E(UIVALENT I-131 values peaked at 3. 1 pCi/gm at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on December 24, 1976, with values exceeding the 1.0 pCi/gm specification for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the spike. DOSE EQUIVALENT I-131 values were in the "Acceptable Operation" portion of Technical Specifications Figure 3.4-1 at all times during the transient.*
Fuel burnup by core region is indicated in Table 1.
As iodine values began decreasing immediately following the spike and have remained at low values during fuel movement operations (1.5x10 " pCi/cc) and with all data similar to that following the November 20, 1976, incident, the December 24, 1976 spike is also attributed to the normal spiking phenomena during power transients rather than fuel clad failure. No iodine spiking was noted during depressurization of the reactor coolant system.
- See Figure 1 Coolant samples are brought to ambient conditions before counting; therefore, units of pCi/cc and pCi/gm are interchangeable.
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INDIANA 8 MICHIGAN POKIER COMPANY DONALD C. COOK NUCLEAR PLANT TABLE 1 FUEL BURNUP BY CORE REGION REGION NO. BURNUP FOR CUMULATIVE ENERGY FOR CUMULATI>/E PERIOD BURNUP PERIOD ENERGY (MMD/MTU (MHD/MTU) (BTU), (BTU) 0.3023E+04 0.1894+05 0.7285+13 0.6565+14 0 '272+04 0. 1915+05 0. 7803+13 0. 4566+14
- 3. 0.2375+04 0.1350+05 0.5632-:13 0.3201+14 Core Total 0.2891+04 0.1721+05 0.2072+14 0.1233+15 Period: October 1, 1976 - December 30, 1976
INDIANA 5 MICHIGAN POWER COMPANY DONALD C. COOK t'IUCLEAR PLANT TABLE 1 FUEL BURNUP BY CORE REGION REGION NO. BURNUP FOR CUMULATIVE Ei'lERGY FOR CUMULATIVE PERIOD BURNUP PERIOD ENERGY (MWD/MTU) 'MWD/MTU (BTU) (BTU) 0.3023E+04 0.1894+05 0.7285+13 0.6565+14
- 2. 0.3272+04 0 '915+05 0.7803+13 0.4566+14
- 3. 0.2375+04 0.1350+05 0.5632+13 0.3201+14 Core Total 0.2891+04 0.1721+05 0.2072+14 0.1233+15 Period: October 1, 1976 - December 30, 1976
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