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Category:Letter
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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 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 IR 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 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 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 2024-08-08
[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
NRC FORM 'I95 U.S. NUCLEAR REGULATORY CO SION DOCKET NUMBER IS-7S) 50-315 Pi FILE NUMBER NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL INCIDENT REPORT J.G. Keppler Indiana 8 Michigan Power Co. DATE OF DOCUMENT Bridgman Michigan 3-15-76 R.W. Jurgensen DATE RECEIVED 3-19-76 E3LETTER 0 NOTOR IZ E D PROP INPUT FORM NUMBER OF COPIES RECEIVED ABORIGINAL UNCLASSIFIED GCOPY DESCRIPTION ENCLOSURE Ltr. trans the following...... ROk'6-07, on 12-25-75,Concerning a pin hole weld leak that was discovered.......
( I Cy. received)
L PLANT NAME: Cook 8 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY :0 iWSGER/J, COLLINS SAFETY FOR ACTION/INFORMATION ENVIRO BRANCH CHIEF: niemann M 3 CYS FOR ACTION LIC ASST:
V/ CYS ACRS CYS ENT TO LA INTERNAL DISTRIBUTION RE FL NRC PDR ISE 2 SCHROEDER/IPPOLITO NOVAK CHECK TEDE CO MACCA BAER SHAO VOLLMER BUN KREGER OL NS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: t. Ose TIC NSIC 2806
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@loan INDIANA& MICHIGANPDt/I/E8 COMPANY I t! i= p'l C. COOK NUCLEAR+PL'ANT 'ONALD P.O, Box 458, Bridgman, Michigan'~49106kc i,, ~()
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March 15, 1976
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Mr. J.G. Keppler, Regional Dir~ector j'~
Office of Inspection and Enforce. ~egt Uni,ted States Nuclear Regulatory orgmipsion ~I j/ 'Ig~ Qo Region III 799 Roosevel t Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315
Dear Mr. Keppler:
Pursuant to the requirements of Appendix A Technical Specifications and United States Nuclear Regulatory Cormnission Regulatory Guide 1.16, Revision 3, the following report is submitted:
RO 50-315/76-07 At the time of the event it was reviewed and determined not to be reportable under Regulatory Guide 1.16, Revision 3, Section 2.a(3) and a report was not submitted.
However, after subsequent review of the event by the Plant Nuclear Safety Review Committee and discussion with NRC RO: III Resident Inspector, Mr. K.R./Baker, we determined the event should have been reported under the crigeria of Regulatory Guide 1.16, Revision 3, Section 2.b(4).
Sincerely,
(
.W. J gen en Plant Manager
/bab cc: RES. Hunter R. Walsh, Esq.
J.E. Dolan G. Charnoff-, Esq.
G.E. Lien G. Olson R. Kilburn J.M. Hennigan R.C. Callen MPSC PNSRC R.J. Vollen BPI R.S. Keith K.R. Baker RO: III Dir., IE (30 copies)
P.W. Steketee, Esq. Dir., MIPC. (3 copies)
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,. XlP LICENSEE EVENT REPORT CONTROL OLOCK: (PLKMSE PRINT ALL REQUIREO INFORMATION) 6 LCENSEE LCENSE EVENT NAME LCENSE NUMBER I [aa~] I! I 0 CCr:2 0 0 PP 0 PP P 0 4 1 7 89 14 15 25 "'6 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBEA EVE'NT DATE REPORT DATE
[00~]coN'T ~2258 L L 0 5 0 0 3 2 5 1 2 2 5 7 5 0 3 1 )5' 6 7 8 57 59 60 61 68 69 74 75 80 EVENT DESCRIPTION Qo g Durin 'normal o eration a in hole weld leak was discovered, at high pressure side of 7 89 80
[0D3] FI-200. The leakin of the weld was round out and rewelded on 1-2-76. Another 7 89 80 Qo4] section of the weld failed on 1-10-76. This was re aired b chanqin the pi in 7 8 9 80 Qg confi uration to reduce vibration.
7 8 9 80 Qom RO 050-315/76-07 7 8 9 PAME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE 7
[on~I ~I0 8 9 10 CODE E
11 12 P
COMPONENT CODE I P 5 X X 17 SUPPUER Z
43 44 Z
MANUFACTURER 9 9 9
. . 47 48 CAUSE DESCRIPTION
[oOs) Failure was caused by fatigue due to vibration.
7 8 9 80
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7 89 80,
~10 7 89 80 FACILITY METHOD OF STATUS 95 POWER OTHEA STATUS DISCOVERY DISCOVERY DESCRIPTION Qg ~E ~08 I! II/A A Durin routine lant ins ection.
7 8 9 FORM OF 10 12 13 44 45 .,46 80 ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Z ~2 !I/A N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~is ~00 0 2 II/A 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q>4j ~00 0 II A 7 89 11 12 80 PROBABLE CONSEQUENCES Qsg N/A 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g Z N A 7 89 10 80 PUBLICITY N/A 7 89 80 ADDITIONAL FACTORS Q1g N/A 7 89 80 7 89 80 David G. Wizner PHONE. 465 5901 Gr 0 8ST 60T
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U.S. NUCLEAR REGULATORV COMMISSION DOCKET NUMBER NAC I'ORM 195 I2.7SI <o-gl g FILE NUMBER NRC DISTRIBUTION FDR PART 50 DOCI<ET MATERIAL XNCXDENT REPORT FROM:INDIANA & MICH DATE OF DOCUMENT 3 - lS-z4 TO: POWER CO BRIDGMAN, MICH S MR J G KEPPLER DATE RECEIVED R JURGENSEN 4
5IJ ABORIGINAL ETTER 0 N0 TO R Z E D I PROP INPUT FORM NUMBER OF COPIES RECEIVED QCOI V
+UNCLASSIFIED l DESCRIPTION ENCLOSURE I
1 LTR TRANS THE FOLLOWING....... LICENSEE EVENT REPORT 50-'15/76-07 ON 12-25-75 RE A PIN HOLE WELD LEAK WAS DIS-COVERED AT HI-PRESSURE SIDE OF OFI-200......
PLANT NAIIH: Comic. 4< NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION ENVXRO BRANCHA CHIEF:
W 3 CYS FOR ACTTON LXC ~ ASST:
W/ CYS ACRS CYS HOLDXNG/ HNT TO LA INTERNAL DISTRIBUTION L'Q FILE PDR I&E 2 NO~VAK
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SCHROEDER/IPPOLXTO CHECK CLJalmm BAHR IMUH' SHAO VOLLMER BUNCH KK!G~ER 1 COL. NR LXTERNAL DISTRIBUTION CONTROL NUMBER naagQ Hx,.
TXC NSIC NfiC FORM 195 (2-7G)
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), +'o IllfDIANA8 MICHIGA/VPOWER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106
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p March 15, 19?6
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Man 17 19761 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement Uni.ted States Nuclear Regulatory Commission 0j P
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~ ggQEAR RKV~i Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315
Dear Mr. Keppler:
Pursuant to the requirements of Appendix A Technical Specifications and United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 3, the following report is submitted:
RO 50-315/76-07 At the time of the event it .was reviewed and determined not to be reportable under Regulatory Guide 1.16, Revision 3, Section 2.a(3) and a report was not submitted.
However, after subsequent review of, the event by the Plant Nuclear Safety Review Committee and discussion with NRC RO: III Resident Inspector, Mr. K.R. Baker, we determined the event should have been reported under the criteria of Regulatory Guide 1.16, Revision 3, Section 2.b(4).
Sincerely, g
(
.W. J gen en 0 Plant Manager 9
/bab QIIigh~, gyp'~
cog ~y(y'll CC: R.S. Hunter R. Halsh, Esq.
J.E. Dolan G. Charnoff, Esq. ~
G.E. Lien G. Olson R. Kilburn J.M. Hennigan R.C. Callen MPSC PNSRC R.J. Vollen BPI R.S. Keith K.R. Baker RO: III Dir., IE (30 copies)
P.H. Steketee, Esq. Dir., MIPC (3 copies)
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LlCENSEE EVENT REPORT CONTROL 8LOCK: SE PAINT ALL AEQUIAED INFOAIVIATION)
UCENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE
[oa~] N I 0 C C 1 0 0 OO O OO 0 0 4 1 1 1 0 7 89 14 15 26 30 3'I 32 REPORT, REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE
~01 CQN'T ~gp58 . L L 0 5 0 0 3 ). 5 1 2 2 5 7 5 0 3 1 5 7 6 7 8 57 59 60 61 68 69 74 75 80 I
EVENT DESCRIPTION Durin 'ormal eration in hole weld leak discovered at high pressure side of 7'9 toOI o a was 80 FI-200. The leakin of the weld was round out and rewelded on 1-2-76. Another 7 89 80 Qo 4j section of the weld failed on 1-10-76. This was re aired b chanqin the piping 7 89 80 Qg confi uration to reduce. Vibration.
7 8 9 80 Jog RO 050-315/76-07 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPOI4ENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VCLAIION
~a~ LIIDI P I P E X X ~Z Z 9 9 9 7 8 9 10 11 12 17 . 43 44 . 47 CAUSE DESCRIPTION IDOI Failure was caused by fatigue due to vibration.
7 8 9 80 Jog 7 89 80.
~10 7 89 80 FACIUTY METHOD OF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q~g E ~08 1 N/A ~A Durin routine lant ins ection.
7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COAT)MT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q1g Z ~Z N/A N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~is ~00 0 ~Z '3 N/A 7 89 11 12 PERSONNEL INJURIES NUMBER DESCRIPTION
~44 ~00 0 ', NA 7 8 9 11/12 80 PROBABLE CONSEQUENCES Q~g N/A 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g Z N A 7 89 10 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS
[>is] N/A 7 89 80 7 89 80 NAME. David G. Ilizner PHONE. 465-5901 CPO bb I 667
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