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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
AEC DISTP I lv.'I r"Qn P"iRT 50 DOCI'ET (TEi'.IPORARY FORi"I)f IC AXIAL I I'CONTROL NO: 5"S FILE~KXE~KZOaz Fp~;,I.Indiana%Michigan Power'r'Legman, Mich.=-49106 R.W.Jurgensen~.TO: Mr.J.G.Keppler OATE OF'DOC 1>>10-ORIG 1 si ed IX RPT CC OTHER SENT AEC PDR SENT LOC'AL PDR DATE R EC'D LTR OTHER CLASS VNC LASS XXXX.PROP INFO INPUT NO CYS REC'D DOC: ETNO: 50-315.PESCRI?TIO~I:
Ltr trans the following Abnorma Occurrences:
'I ENCLOSURES:
A'bnon)al Occurrence's AO-050-315/74-07/74-08/74-10 re fhiling of diesel geneator 5 fuel filters...
MDilII.HSEO Pl ANT NAb;1E: Donald, C.Cook Unit 3.(1 cy encl recid)Do Ntt,.getttove FOR ACilO.'l/~i'.;OR!.1AilOi'NL 1-1888.BUTLER (S)W/Copies CLARK (S)g/Copies PARR (S)~/Copies cCNX L (S)W/Copies SCHWENCER (S)W/Copies STOLZ (S)Wi Copies VASSALLo (s)W/Copies PURPLE (S)W/Copies ZIEKQIN (S)W/Copies DICKER (E)Wi Copies KNXGHTON (E)W/Copies YOUNGBLOOD (E)W/Co ies REGAN (E)W/Copies LEAR (S)W/Copies SPEIS (S)W/Copies KG TECII REVIEW AEC PDR bbGC, ROOM P-F06 A CIIACCANY ifUl r ZING/STAFF WQlXGHT RASE@AWLICKI GIA:mUSSO baHAO BOYD C6TELLO l~iOORH'(S)(BWR)410USTON DEYOUNG (S)(PETR)~AVOVAK SKOVHOLT (S)PgOSS GOLLER, (S)APPOLITO P, COLLINS TEDESCO DENISE~LDNG REG OPR~KAINAS~I'ILE G REGIoN (y IFBENARGTA KT.R.WILSON~STEELE~VOLDIER INTER,'AL DISTR I DENTON GRIIIES GAI'MILL AASTNER BALLARD SPANGLER ENVIRO PtOLLER DICKER,.KNXGhTON YOUNGBLOOD REGAN PROJECT LDR HARLESS":)UTIQN LIC.ASST.A/T IND DIGGS (S)BRAITNAN GEARXN (S)SALTZltAN."~GOULBOURNE (S)B.HURT lQEUTZER (E)LEE (S)PLAÃS NAIGRET (S)HCDOi<ALD PZ.ED (E)CHAPHAN/SERVICE (S)DUBE v/input SHEPPARD (S)E.COUPE SL'ATER (F)~R, Hartfield (2)SMITH (S)+KLEGKER TEETS (S)(fF.WXLLIP~~IS WILLIAMS (E)WILSON (S)INGRAM (S).N-A-TIC(ABERNATHY) 4-NSIC(BUCHANAN) 1"ASLB J.-NEWTON AV)ERSON-V5"ACRS SEihrP'TO ILIC.'ASST.
Service 1-18-75.-E>: i'ERi" 4L 0!STRl-"VTION I (1)(2)(10)-NATIONAL LABS l-l<..PENNINGTOiV, R~t E-201 G.T.1 CONSULTA!ATS NEKQIRK/BLUIIE/AGBABXAN 1"PDR SAlE/LA/NY 1"BROOKHAVEN NAT LAB 1"G.ULRIKSON, ORIG 1"AGlKD(RUTH GUS SHAN)F34 B-127 G,T..1-J.RUKLESP R~t E-201',G+T
'n (lw~~~Ig II I V sk I 0')~~M3NJ))i!'M 8VOP.~A 30al-;gQ t, T'B I~4 Re~i)a~%@~p INDIANA&MICIIIGAN POWER CDMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 January 10, 1975 ,),S~>,)(,g%i',A S>>"@U.S.Atomic Energy Commission Director of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Reference:
Operating License DPR-58 Docket No.50-315 Attention:
Nr.J.G.Keppler, Regional Director Gentlemen:
Pursuant to the requirements of Appendix A Technical Specifications and U.S.Atomic Energy Commission Regulatory Guide 1.16, Revision 2, Article 2b, the following Abnormal Occurrence Reports for the month of December, 1974, are submitted:
AO-050-315/74-07 AO-050-315/74-08 AO-050-315/74-10 Sincerely,.W.Jur ns Plant N nage ll Jlegpl S cc: W/Attachments J.E.Dolan R.S.Hunter:G.E.Lien R.J.Vollen BPI K.R.Baker RO: III R;~C.Callen, Esq.P.Steketee, Esq.R.Walsh, Esq.PNSRC JAil 3.5 3.St5 ann A L li aE(ga1 a CONTROL BLOCK: 1 LCENSEE NAME Qpg HX DC.Q.L.O 14 15 LICENSEE EVENT REPORT R,~~>~;~c-.(PL E PRINT ALL REQUIRED INFORMATION) 6 LCENS~'.~~@
LCENSE NUMBER TYPE TYPE G-QQOQc)-OQ A 11 11~01 25 26 30 31 32~01 CON'T 7 8 REPORT~REPORT~tO t I 57 58,59,60 REPORT DATE EVENT DATE DOCKET NUMBER 05'6 32$61 ,68 69 74 75 80 22.OA 4 OX ap la 7 0 9 tm VER,N Fe-ciao-Si v4--c EVENT DESCRIPTION Qpg TEC-HMTC.A L QPEC T'FXC gc TONS Q.UXQ~CQT Fog.SAMF'I Ig 7 89 m M.e.SF-L.Vu~S e.~C~e~<(-AX,QYY'DPYS mP 7 89 tooj4 arse.ossa vogTER P 80 smj.~F7 NAG Mo Ne.~F<RsT.A.HPLE 7 8 9 Jog WAS TAKER OCYo Q..Z.9'll-.F T 5 PLE.wAS AYEW 80 80 80 80 7 89 SYSTEM CAUSE~or~E.F D 7 8 9 10 11 12 CAUSE DESCRIPTION Jag SHE.NPu%P PAME COMPONENT 17.43 COMPONENT MANUFACTURER 2 2 44.47 VIOLATION LYJ~HTC,8.PRQ4YC euT'MPLL45.
~V<PEp<M6~<9 80 80 OVID FO PROBE.Ib PI ZN D57E.S.7 8 9 7 0 9 80[OO~)WP.S'T A%CO~7L PPO 5 MEED.T+'lE-COHPOTEKEKCC~~Y
.'AS..N04J 7 89 FACILITY STATUS METHOD OF DISCOVERY OTHER STATUS DISCOVERY DESCRIPTION POWER 7 09 LOSS OR DAMAGE To FACILITY TYPE DESCRIPTION Q~g 7 0 9 10%PUBLICITY 7 8 9 ADDITIONAL FACTORS~10 (g~7 09 gg 7 09 gg[QJ~ao O 7 8 9 10 12 13 44 45 , 46 FORM OF ACTIVITY COAT(NT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g z.z.v k 7 8 9 10 11 44 45 PERSONNEL EXPOSURES 7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Qg~OO Q IIX 7 89 11'2 PROBABLE CONSEQUENCES gP,y P~q~pPP~~Tg<PP~~~Tt-Ct4S-Qo GFIF-SZR CDQSEQUE<<~
80 80 I 80 80 80 80 80 80 80 80 NAME T 0 PLUMY EX%.PHONE: GPO IIIII I ply~t 0 P il i)j j 1'Vy s, y too~j 7 89 LICENSEE EVENT REPORT CONTROL BLOCK: 1 LICENSEE NAME 0 C'I 14 15 6 LICENSE NUMBER ou-g roc 8 pl~DpI TYPEYPE 26 30 31 32 25 Roget~'4"Q'.t'PL.6 PRINT ALL REQUIRED INFORMATION)
REPORT~REPORT CATEGORY TYPE SOURCE I001jcQNT~rrr 2 4.L c7 7 8 57 58 59 60 6'I EVENT DESCRIPTION
[OO~]OOCKET NUMOER EVENT OATE REPORT OATE ggy~-y ag~gy ol'r c 68 69 74 75~C.'~r'80 7 8 9 7 89~04 7 8 9 QOg g 7 8 9 Jog 7b 80 wu 80~J 80 c p a w Zi 80 7 8 9 SYSTEM CAUSE 7 8 9 10 11 12'I7 CAUSE DESCRIPTION
~08 e PRME COMPONENT SUPPUER o 43 COMPONENT MANUFACTURER 47 VIOLATION'48 80 7 8 9[OD9]7 89[isa]7 8 FACIUTY STATUS%POWER OTHER STATUS Q~g[gJ~oo g 7 8 9 10 12 13 FORM OF ACTMTY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Qg z 7 8 9 10 11 PERSONNEL EXPOSURES Q~g pQFOJ V.7 89 12 13 PERSONNEL INJURIES~4~OYER ct 7~8 9 11 12 PROBABLE CONSE(UENCES Jig onp J" 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION
~16~7 89 10 PUBLICITY 7 89 ADDITIONAL FACTORS METHOD OF OISCOVERY 44 45 , 46 44 45 OISCOVERY OESCRIPTION u~/~7 LOCATION OF RELEASE 80 80 80 80 80 80 80 80 80 80 7 89 Q~g 7 89 NAME:~PHONE:4/~80 80 GPO Obl o 66T
.~g"~'C'f;g.b,C>.'5r,,', IL C~C~~le r'<p,v , CQNTROL'LOCK LICENSEE NAME[op~]H 1 P C C 1 14 7 89 LICENSEE EVENT REPORT.Aag~@~M~Cj (PLEXURE PRINT ALL REQUIRED INFORM ON)1 6 LIC'iCh@55%~,.$
.V LICENSE NUMBER TYPE TYPE oo-ooooo-oo 4<z1l.LDD1J 15 25 26 30 31 32 REPORT~REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT DATE[oO~]co>>>>v
~PO I L 0 Io G-0&1.c>>1.2.2 T,'T 4 0 i.L.O'7&7'57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION roO~J DOPIQC~PE/4'-TOE.
PRO~CY<MA%&YE'H%HE.88SP0MSE, I~VX.~Ca A FALM 80 1 ueQSCAVzQ e r,c vms 7 89 tooj4 PROPER~S~L eAa<X.~TPPW OV 7 8 9 80+OS]TM<TRAP AQH~4C>AS<AT MIII~REPLIED WVM ewe.O VZOE, 7 8 9 80 Jog 5~5 MME: U~V..46 PX&Sa.L, M;TEb V Ee.a--XS h-ic)7 8 9 80 SYSTEM CAUSE PAME COMPONENT COMPONENT MANUFACTURER 7 8 9 80 I, SAFE TABLE.c;TXGt4 vJks ERE,Rk~.c.DIE, H c Ek)ERICK)R.
E=Az~0 7, 8 9 10 11 12 17.43 CAUSE DESCRIPTION
+os]QR+SX~@MT 4 gq LV p I 44 t4C.C7X.L S 47 48 7 8 9 Hog tuSQXCA7I:t4CI em PP~u~e.O SuzuO ue S WrZCra4m 7 8 9 P~g GX.L.TRmwu>>>>E EXI'o A,RMFD (LQ SE~OIDS).80 LQu 80 7 89 FACILITY STATUS POWER OTHER STATUS[Q~oo a wk 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Q~g 7 8 9 10 11 PERSONNEL EXPOSURES 7 89 11 12 13 PERSONNEL INJURIES 7 89 11 12 PROBABLE CONSE(UENCES gg P~ggg~@~ERA LOlF'C~Y METHOO OF OISCOVERY OISCOVERY DESCRIPTION cP~~KKL EV~T 44 45.46 LOCATION OF RELEASE 44 45 92DPBPL(-%to eFw Srte.g~vEi4c,Es 80 80 80 80 80 7 89 LOSS OR DAMAGE To FACILITY 7 89 10 PUBLICITY Nk 7 89 ADDITIONAL FACTORS Ce 80 80 80 APORT-..ALEP 6 ERR bL Qr-E 7 89 S~-AD-AFTER.Lu 7 89 NAME.T.C.I2I-OQM PHONE: 80 GPO 8IIl e$67
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