Similar Documents at Cook |
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Category:Letter
MONTHYEARAEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024 U2C28 Steam Generator Tube Inspection Report AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-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-2024-002-01, 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. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. 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 ML24159A2522024-05-30030 May 2024 10 CFR 50.71(e) Update and Related Site Change Reports AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report 05000316/LER-2024-001, 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 ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 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 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 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 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 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 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 05000316/LER-2024-001, 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 05000316/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 05000315/LER-1999-027, LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination1999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report 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 ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-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) 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 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 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 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 IR 05000316/19780341978-06-19019 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 2024-09-12
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Text
NRC FORM 195 V.S. NUCLEAR RFOVLATORV COMMISSION DO TgtgVI 0 E FI I2 70) o FILE NVMOER NR DISTRIBUTION FDR PART 50 DOCI(ET MATERIAL INCIDENT REPORT To: J.G. Keppl er FRDM: Indiana 8 Michigan Power Co. DATE OF DOCUMENT Bridgman, Michigan 6-2-76 R.lJ. Jurgensen DATE RECEIVED 6-10-76 SLETTER NOTOR I Z E D PROP INPUT FORM NUMBER OF COPIES RECEIVED 0ORIGINAI EI V N C LASS I F I E D QCOPV 30 DESCRIPTldN ENCLOSURE Licensee Event Report (%.0. II 76-23) on 5-2-76 Ltr. trans the followihg........ Concerning Various Valves (Isloation) failed to meet acceptable leak rate Specifications......
- Licensee Event Report (R.O. k'6-24) on 6-76 Concer'ning"Lower. Inlet. Door'-R* opening 'Torque being in excess of Tech. Sepc.......
(30 Carbon Sisgned Cys. REceived)
ACKNOWLEDGED DO NOT REMOVZ PLANT NA1IE. Cook b 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED..
SEND DIRECTLY TO KREGER/J, COLLINS
- SAFETY FOR ACTION/INFORMATION ENVIRO SAB 6-10-76 BRANCH CHIEF: Kniel W 3 CYS FOR ACTION LIC ~ -ASST: Lee W/ CYS ACRS 'YS ENT TO LA INTERNAL DISTRIBUTION NRC PDR ICE 2 SCHROEDER/IPPOLITO NOVAK CHECK IES S . E TEDESCO HACCA EN BAER SHAO VOLLH~BH BUNCH KRE E 0 N EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: ~
TIC NSIC 5879"
3 I~
3 ~ 3 I' 3 Ilt II
~egtffatoty QL cd
@Afar o4 INDIANA 8 NICHIGAN I'DN'E IANy DONALD C. COOK NUCL PL@~>'km P.O. Box 458, Bridgmnn,>hi gran 4SLIC 3
ig gog7.92 June 2, 1976 ANION 876~
g~q teton p~g Clerk
<95. %%%lNtK.'t Hr. J.G. Keppler, Regional Direc a ~jg Office of 'Inspection and Enforcement United States Nuclear Regulatory Commission I.
Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315
Dear lhr'. 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 reports are submitted:
R0-50-315/76-23 RO-50-315/76-24 Sincerely, r
R.M. ge en Plant tan er
/bab cc: R.S. Hunter
-J.E. Dolan G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen 1/PSC K.R. Baker RO:III P.W. Steketee, Esq.
R. Walsh, Esq.
G , Charnoff, Esq G. Olson J.N. Hennigan PNSRC R.S..Keith
'Dir., IE (30 copies)
Dir., 1<IPC {3 copies)
~ LICENSES SVSNT aePORTi CONTROL 0LOCK: (PLEASE PRINT ALL REOUIREO INFORIVIATION) 1 0 LtCENSf f LCT NSE EVENT NAhtf LtCLNSE t6uhtIILA IVPL. TYPE 0 0 0 0: 0 0 0 0 4 1 1 1 1 +0+]
~'9 14 15 5 30 31 32 AFT'OAT AfPOAT CAT EOOAY kuhIOIA fVENT OA'If Aft'CAT OATF
'0 TYPE SOUSE OOCKET
[oagcow T L050 03 15/ 0 5 O 8 Z 6 ~0 7 0 57 59 74 75 EVENT DESCRIPTION Jog WHILE IN t'lODE 5 DURING SURVEILLANCE TESTIttG OF CONTAINMENT ISOLATION VALVES VARIOUS UD AC l P TYP . AK' P 7 0 9 UD toOj R N A P IFICATIOt NA 9 00 LOSS OR DAMAGE TO FACILITY T v PE OESCA:P T TON Z NZ 7 8 9 10 PUULICITY tIA 7 8 9 t'DDITIONAL I'ACTORS pg I ttA 7
7 gH 09 l~ UO JACK RISCHLIttG p~,ig.~616 465 59~01 368)
G>0 ddI 46 1
'4 P SUPPLEt1EHT TO REPORTABLE OCCURREtfCE RO-50-315 76- 23 SUPPLEHENT TO EVEtiT DESCRIPTION THE FOLLOMIt<G VALVES MERE FOUND=TO HAVE EXCESSIVE LEAKAGE:
DCR-621 MCR-905 ECR-15 HSW-415-3 GCR-314 NSW-415-4 NCR-105 WCR-922 NCR-106 WCR-921 NSW-244-2 HSW-417-3 NSW-244-3 VCR-106 NSM-244-4 VCR-206 MCR-958 SI-189 HSW-417-4 N-102 NSM-415-1 SH-1 NSW-415-2
t>>
l,i
CONTROL BLOCK:
~ LICENSEE EVENT REIoORI (PLEASE PAINT ALL AEOUIREO INFORMATION)
LiCKNSTE LtCI ttSE. IVTNT NL'VE LL IttSE tiUMBLR TYPE I v I'E toOjI t1 I D C C 1 0 0 0 0 0 0 4 t i l l ~03
~
)
7 09 14 15 20 Jo 31 32 Afponr ntpont CLTT Gonv OOCKK t t'UMrB'LR f VINT Ontf ntPORT OATK
[oagcour ~L 0 5 0 0 3 1 5 0 5 0 6 7 6 0 6 0 I 7 6 7 0 57 50 59 00 60 09 74 75 UO EVENT OESCRIPTION
[oO] WHILE It( NCDE 5, DURING ICE CONDENSER INLET DOOR OPENING TORQUE SURVEILLANCE TESTING, 7 0 9 UO LOWER INLET DOOR 1-R OPENING TORQUE WAS FOUND IN EXCESS'OF TECHNICAL SPECIFICATION 7 0 9 UO Qpjn PARAGRAPH 4.6.5.3.1 b3 LllklT OF 195 ItlCkt POUNDS. LOWER INLET DOOR 3-L. INITIAL 7 0 9 UO Jag OPENlt,G TOR UE WAS FOUr(D TO BE IN EXCESS OF TECHNICAL SPECIFICATION PARAGRAPH 4.6.5.3.1 7 0 9 toOQ bl Llt1IT OF 675 It(CH POUt<DS. DOOR 1-R SPRING TEttSIOt< (SEE SUPPLEtkENT) (RO-50-315/76<i0 7 0 9 Pnnr E SYSTKti CAUSE CCrrtrt 4 O4'I COLrPONINT COOK CODE COVPONENT CODE 'Uf R MLtuUt LOT UrrtR
[nn') ~so F X X X X X X W 1 2 0 7 0 0 10 11 12 17 43 44 CAUSE OESCRIPTION
[oa~j DOOR 1-R Llt>IT WAS EXCEEDED DUE TO SPRING TENSION DRIFT. DOOR 3-L INITIAL OPENING 7 0 9 00 X EEDED L"ItlITS BECAUSE OF AN ICE BUILDUP FROtl CONDENSATION ON THE LOWER SILL.
7 0 9
~1O 7 09 TLCtLITY MEIHOO OF STLTUS POtttf n otiiKA sTntUs OISCOVf A V otscovf AY of scn'.ptIQN
~00 UO'u)
Lsj o NA SURVEILLANCE TESTING 7 0 9 10 12 13 45 40 FOtttl OF ACTIVITY CO@TENT aMourtt of nctiv:tv LOfnttON OF RELKnSE NA 7 0 9 10 11 nn 45 PERSONNEL EXPOSURES tiUMBER TYPE OESCRlPTtON
~00 0 T ttA 7 09 11 'l2 13 PERSONNEL INJURIES tiUMBEA OESCRIPTtON
[i')0 9~00 7
0 11 12 ttA UU PROBABLE CONSEQUENCES t115j tiA 7 0'9 Uo LOSS OR DAMAGE TO FACILITY T'vpE oEscnpooti tIIsj Z tlA 7 09 10 PUULICITY
[lli) t'iA 0 9 AOOITIONAL FACTORS rtA Qg I 7 8 9 9] NA 7 04J J. RISCHLlttG P>IOIIE{616)4G5 5901(368 Gt'4t e tt I ~ a 0 1
SUPPLEt'iEt<T TO REPORTABLE OCCURRENCE RO-50-315/76- 4 SUPPLEMENT TO EVENT DESCRIPTION WAS ADJUSTED TO PROVIDE A 189 INCH POUND OPENING TORQUE. DOOR 3-L BOTTOM SILL WAS CLEANED At40 INITIAL OPEttING TORQUE h'AS REMEASURED AT, 287 INCH
'POUNDS.