Similar Documents at Cook |
---|
Category:Letter
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. 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 ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 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 AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 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 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 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report 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
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/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 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 AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 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 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
[Table view] |
Text
AEC DISTP I lv.'I r"Qn P "iRT 50 DOCI'ET f IC AXIAL (TEi'.IPORARY FORi"I) I I
'CONTROL NO: 5"S FILE ~KXE~KZOaz Fp~;,I. Indiana % Michigan Power OATE OF 'DOC DATE R EC'D LTR IX RPT OTHER
'r'Legman, Mich. 49106
=-
R.W. Jurgensen 1>>10-
~. TO: ORIG CC OTHER SENT AEC PDR Mr. J.G. Keppler 1 si ed SENT LOC'AL PDR CLASS VNC LASS PROP INFO INPUT NO CYS REC'D DOC: ETNO:
XXXX .
50-315
.PESCRI?TIO~I: Ltr trans the following Abnorma ENCLOSURES: A'bnon)al Occurrence's AO-050-Occurrences: 315/74-07/74-08/74-10 re fhiling of diesel geneator 5 fuel filters...
'I MDilII.HSEO (1 cy encl recid) Do Ntt,.getttove Pl ANT NAb;1E: Donald, C. Cook Unit 3.
FOR ACilO.'l/~i'.;OR!.1AilOi'NL 1-1888.
BUTLER (S) SCHWENCER (S) ZIEKQIN (S) REGAN (E)
W/ Copies W/ Copies W/ Copies W/ Copies CLARK (S) STOLZ (S) DICKER (E) LEAR (S) g/ Copies Wi Copies Wi Copies W/ Copies PARR (S) VASSALLo (s) KNXGHTON (E) SPEIS (S)
~
/ Copies W/ Copies W/ Copies W/ Copies cCNX L (S) PURPLE (S) YOUNGBLOOD (E)
W/ Copies W/ Copies W/ Co ies INTER,'AL DISTR I ":)UTIQN KG TECII REVIEW DENTON LIC. ASST. A/T IND AEC PDR GRIIIES DIGGS (S) BRAITNAN bbGC, ROOM P-F06 A CIIACCANY GAI'MILL GEARXN (S) SALTZltAN ifUl r ZING/STAFF WQlXGHT AASTNER ." GOULBOURNE
~
(S) B. HURT RASE @AWLICKI BALLARD lQEUTZER (E)
GIA:mUSSO baHAO SPANGLER LEE (S) PLAÃS BOYD C6TELLO NAIGRET (S) HCDOi<ALD l~iOORH '(S) (BWR) 410USTON ENVIRO PZ.ED (E) CHAPHAN DEYOUNG (S) (PETR) ~AVOVAK PtOLLER /SERVICE (S) DUBE v/input SKOVHOLT (S) PgOSS DICKER,. SHEPPARD (S) E. COUPE GOLLER, (S) APPOLITO KNXGhTON SL'ATER (F) ~R, Hartfield (2)
P, COLLINS TEDESCO YOUNGBLOOD SMITH (S) +KLEGKER DENISE ~LDNG REGAN TEETS (S) (fF. WXLLIP~~IS REG OPR ~KAINAS PROJECT LDR WILLIAMS (E)
~I'ILE G REGIoN (y IFBENARGTA WILSON (S)
KT.R. WILSON ~STEELE ~VOLDIER HARLESS INGRAM (S).
E>: i'ERi" 4L 0!STRl-"VTION N- I (1) (2) (10) -NATIONAL LABS 1"PDR SAlE/LA/NY A-TIC(ABERNATHY) l-l<.. PENNINGTOiV, R~t E-201 G.T. 1 "BROOKHAVEN NAT LAB 4-NSIC(BUCHANAN) 1 CONSULTA!ATS 1"G. ULRIKSON, ORIG 1"ASLB NEKQIRK/BLUIIE/AGBABXAN 1 "AGlKD(RUTH GUS SHAN)
J.-NEWTON AV)ERSON F34 B-127 G,T.
- V5"ACRS SEihrP'TO ILIC.'ASST. . 1-J. RUKLESP R~t E-201 Service 1-18-75 .- ',G+T
'n
( lw
~ ~
V
~ Ig sk I II I
0 ') ~
~M3NJ))i!'M 8VOP. ~A 30al-; gQ t, T 'B I
~ 4
Re~i)a~ %@~p INDIANA& MICIIIGANPOWER CDMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106
,),S ~>, )(,g%
January 10, 1975 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, ll
.W.
Plant Jur N nage ns 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
LICENSEE EVENT REPORT R,~~> ~;~c-.
CONTROL BLOCK: (PL E PRINT ALL REQUIRED INFORMATION) 1 6 LCENSEE NAME LCENSE NUMBER LCENS~'.~~@
TYPE TYPE Qpg HX DC.Q.L.
14 15 O G QQOQc) OQ 25 26 A 11 1130 ~01 31 32 05' REPORT ~ REPORT
~01 CON'T 7 8
~tO t 57 58,59,60 I
61 DOCKET NUMBER 6 32$ ,68 69 22.OA EVENT DATE 4
74 75 OX REPORT DATE ap la 80 EVENT DESCRIPTION Qpg TEC-HMTC.A L QPEC T'FXC gc TONS Q. UXQ~CQT Fog. SAMF'I Ig 7 89 80 7
m89 M.e.SF-L. Vu ~ S e.~C ~e ~<( -AX,QYY 'DPYS mP 80 tooj4 arse.ossa vogTER P 80 smj.~F7 NAG Mo Ne. F<RsT . A.HPLE ~
7 8 9 80 Jog WAS TAKER OCYo Q..Z. 9'll-. F T 5 PLE. wAS AYEW 7 0 9 80 tm VER,N Fe - ciao- Si v4--c 7 89 PAME 80 SYSTEM CAUSE COMPONENT COMPONENT MANUFACTURER VIOLATION 7
~or ~E. F 8 9 10 D
11 12 17 . 43 44 .
2 247 LYJ CAUSE DESCRIPTION 7
Jag 0 9 SHE. NPu%P ~HTC,8. PRQ4YC euT'MPLL45. ~V<PEp <M6 ~<9 80 7
[OO~)
8 9 WP.S 'T A%CO ~7L PPO 5 MEED . T+'lE- COHPOTEKEKCC~~Y 'AS.. N04J .
80 OVID FO PROBE. Ib PI ZN D57E.S.
7 89 80 FACILITY METHOD OF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION gg8 [QJ ~ao O 7 9 10 12 13 44 45 , 46 80 FORM OF ACTIVITY COAT(NT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g z. z. vk I 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Qg ~OO Q11'2 IIX 7 89 80 PROBABLE CONSEQUENCES 7 09 gP,y P~q ~pPP ~~Tg <PP~~~Tt-Ct4S- Qo GFIF- SZR CDQSEQUE<<~
80 LOSS OR DAMAGE To FACILITY TYPE DESCRIPTION Q~g 7 0 9 10% 80 PUBLICITY 7 8 9 80 ADDITIONAL FACTORS
~10 (g ~
7 09 80 gg09 7 80 NAME T 0 PLUMYEX% .
PHONE:
GPO IIIII
I ply ~
0 P
t il i) j j s, y 1'Vy
LICENSEE EVENT REPORT Roget~ '4"Q'.
CONTROL BLOCK: t'PL . 6 PRINT ALL REQUIRED INFORMATION) 6 LICENSEE 1
pl~ DpI 7
too~ j89 0 NAME C' I 14 15 ou g roc LICENSE NUMBER 8
25 26 TYPE
'
30
'YPE 31 32 REPORT REPORT ol'r
~
I001jcQNT ~rrr 7 8 CATEGORY 57 2
58 TYPE 4
59 SOURCE
. L 60 c7 6'I ggy~-
OOCKET NUMOER 68 69 y ag~gy EVENT OATE 74 75 REPORT OATE c
80 EVENT DESCRIPTION
[OO~] ~ C.'~r' 7 8 9 80 wu 7 89 80
~04 7 8 9
~ J 80 QOg g c p a w Zi 7 8 9 80 Jog 7b 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT SUPPUER MANUFACTURER VIOLATION 7 8 9 10 'I7 o
11 12 43 47 '48 CAUSE DESCRIPTION
~08 e 7 8 9 80
[OD9]
7 89 80
[isa]
7 8 80 FACIUTY METHOD OF STATUS % POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION Q~g 7 8 9
[gJ ~oo g 44 u~/~ 7 10 12 13 45 , 46 80 FORM OF ACTMTY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY 7
Qg 8 9 z 10 11 44 45 LOCATION OF RELEASE 80 PERSONNEL EXPOSURES Q~g pQFOJ V.
7 89 12 13 80 PERSONNEL INJURIES
~4 ~OYER ct 7 ~ 8 9 11 12 80 PROBABLE CONSE(UENCES Jig onp J" 7 8 9 80 LOSS OR DAMAGE TO FACILITY
~16 7 89
~
TYPE 10 OESCRIPTION 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS 7 89 80 Q~g 7 89 80 NAME: ~
PHONE:4/~
GPO Obl o 66T
~le IL C
.~
~C ~
g" ~'C'f;g. b,C>.'5r,,',
r
'<p,v
, CQNTROL'LOCK LICENSEE EVENT REPORT (PLEXURE
.Aag~@~M PRINT ALL REQUIRED INFORM
~ Cj ON) 1 6 LICENSEE LIC'iCh@55%~,.$ . V
[op~] H 7 89 1 P NAME C C 1 14 15 oo ooooo LICENSE NUMBER oo 25 26 4 <z1l.
TYPE 30 TYPE LDD1J 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 7
7 I, SAFE 8 9 89 TABLE.c;TXGt4 vJks ERE,Rk~. c. DIE, H c Ek)ERICK)R. E=Az~ 0 80 80 tooj4 PROPER~ S~L eAa< X. ~TPPW OV 1 ueQSCAVzQ e r,c vms 7 8 9 80
+OS] TM< TRAP AQH~ 4C>AS<AT MIII~ REPLIED WVM ewe. O VZOE, 7
Jog 7
8 9 8 9 5~5 MME: U~V.. 46 PX&Sa.L, PAME M;TEb V Ee.a - - XS h-ic) 80 80 SYSTEM CAUSE COMPONENT COMPONENT MANUFACTURER 7, 8 9 10 11 12 17 . 43 44 47 48 CAUSE DESCRIPTION
+os]
7 8 9 QR+SX ~ @MT 4 gq LV p I t4C. C7X.L S 80 7
Hog 8 9 tuSQXCA7I:t4CI em PP~ u~e. O SuzuO ue S WrZCra4m LQu 80 7
P~g 89 GX.L. TRmwu>>>>E EXI'o A,RMFD (LQ SE~OIDS).
FACILITY METHOO OF 80 STATUS POWER OTHER STATUS OISCOVERY OISCOVERY DESCRIPTION 7 8
[Q 9
~oo a12 10 13 wk 44 45 . 46 cP~~KKL EV~T 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PERSONNEL INJURIES 7 89 11 12 80 PROBABLE CONSE(UENCES 7
gg89 P~ggg~ @~ERA LOlF' C~Y 92DPBPL(- %to eFw Srte. g~vEi4c,Es 80 LOSS OR DAMAGE To FACILITY 7 89 10 80 PUBLICITY Nk 7 89 80 ADDITIONAL FACTORS Ce APORT ..ALEP 6 ERR bL Qr- E 7 89 80 7 89 S~ - AD- AFTER. Lu NAME. T.C. I2I-OQM PHONE:
GPO 8IIl e $ 67
n p s ~
~ ~ ~
4
~ ~
~~'HOG ~
4