Similar Documents at Cook |
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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
4 DISTRIBU ET MATERIAL
'0:~
N ATION FOR PART 50 D (TEMP OR A R Y F 0 RM)
CDMTIIO 0
FILE INCIDENT REPORT FILEI FROMZndiana I)s Michigan Power C ~ DATE OF DOC DATE REC'D LTR TWX RPT OTHER hridgnan, Michigan R.W. Jur 9-12-75 9-18-75 TO: ORIG CC OTHER T NRC None 4O SENT LOCAL PDR CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
40 ~ 0- 1 DESCRIPTION: ENCI OSURES:
Letter trans the following...... Abnormal. Occurrence g,75-55, on,8-l6-'75, Concern ing Valve IMO-325(Vest 'res/dual heat removal.
ump to 2obp 2 h 3'hot 3egs) was un1'ocked "X'or cycling, Valve IM0-,325 opened. but could,'t be shut by remote operation......-.
/0 g 75-56, on 8-14-75, Concerning, the Reactor Pit Floor incapability,oi,pr'oducing.an acceptabl test-calibrate pattern ........
PLANT NAME:Cook 1 h% - Cont-FOR ACTION/INFORMATION SAB 7 BUTLER (L) SCHWENCER (L) ZIEMANN (L) REGAN (E)
W/ Copies CLARK (L) STOLZ (L) DICKER (E) LI:-AR (L)es ACKNOKLEDGPD W/ Copies W/ Copies W/ Copies W/ Copies PARR {L) YASSALLO {L) KNIGHTON {E) SPELS W/ Copies j)P N'PT RgMP+K) gKNIEL (L) PURPLE (L) YOUNGBLOOD (E)
WQ Copies 'W/ Copies W/ Copies W/ Copies INTERNAL DISTR I BUT!ON IL. TECH REVIEW DENTON LIC ASST A/T IND, RCP e ~SCHROEDE R ~G R I MES R. DIGGS (L) BRAITMAN OGC, ROOMi P-606A AMACCARY GAMMILL H. GEARIN {L) SALTZMAN GOSSICK/STAF F KNIGHT KASTNER E. GOULBOURNE (L) ME LTZ
~CASE PAWLICKI BALLARD P. KREUTZER (E)
GIAMBUSSO SHAO SPANGLER J. LEE (L) PLANS BOYD +~~ STE LLO M. RUSHBROOK (L) MCDONALD MOORE (L) >'<"-
HOUSTON ENVIRO S. REED (E) CHAP MAi~l DEYOUNG (L)
SKOVHOLT (L)
"'"'~NOVAK
<<ROSS MULLER DICKER
~. SERVICE {L)
S. SHEPPARD (L)
DUBE (Ltr)
E. COUPF GOLLER (L) (Ltr) ~IPPOLITO KNIGHTON M. SLATER (E) PETERSON P. COLLINS gTEDESCO YOUNG B LOOD H. S~IT~ (L) HARTFIELD (2)
DENISE J. COLLINS . REGAN S. TEETS (L) ~ KLECKER Rf=G OPR LAIN AS PROJECT LDR G. WILLIAMS(E) E ISENHUT u
,
~FI~ E 5 REGION (2) BENAROYA V. WILSON (L) 'Wl GG I Nl OiN
~ . MIPC/P~
Sl EELE (3) ~VOL LME R HAR LESS R. INGRAM (L) m F. lllLLIA~IS Ir EXTERNAL DISTffIBUTION
~1 LOCAL PDR.M~aeph, Michigan
~1 TIC (ABFRNATHY) (1)(2)(10) NATIONALLABS PD R-SAN/LA/NY
~1 NSIC (BUC) IANAN) 1 W. PENNINGTON, Rm E-201 GT BROOKHAVEN NAT LAB 1 ASLB 1 CONSULTANTS G. ULfklKSON, OANL 1 Newton Anderson NEWMARK/DLUME/AGBABIAN AGMED (RUTH GUSSMAN)
~>- ACRS SEPZ TO LIC .",SST M. Service Rm B 127 GT.
~> SEND ONLY TEN DAY REPORTS J. D. RUNKLES, Rm E-20'I GT
0
'I a w I E
A/0 g 75-62, on 8-23-'55, earning Containzmnt Air parti+te Monitor pump geezed.....
(1 Copy Enclosure Received.
,s 'l P
I!' ~ 'I l yl
IIjIDIAPJA 8r NICIIIGANPOPOVER Cob/IPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 40106 September 12, 1975 gjio~'
Reg~1a~o Mr. J.G. Keppler; Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn,'ll. 60137 Operateng License 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 3, Section 2.b, the followigg Abnormal Occurrence Reports are submitted:
AO 50-315/75-55, AO 50-315/75-56 AO '50-315/75-62 Sincerely, Of
~ R.H. Jurgensen Plant Manager
/bab cc: R.S. Hunter D.E. Dolan G.E. Lien R;J. Yollen BPI R. Kilburn R.C. Cullen MPSC.
K.R. Baker RO: III P.M. Steketee, Esq.
, R. Malsh, Esq.
G. Charnoff, Esq.
G. Olson PNSRC R.S. Keith DIrector, IE (30 copies)
Director, MIPC (3 copies)
CONTROL BLOCK PAINT ALL ACOUIAEO INFORMATION
~ 2 6
~ a sv ~ LCEN SEE LICENSE EVENT NAME LICENSE NUMBEA TYPE TYPE 01 I 0 C C I 0 0 OOOO 0 0 8 1 I I 1 ~01 BC'PLEILSE v 89 '14 15 25 26 30 31 32
( CATEGORY
'AEPOAT AEPOAT TYPE SOURCE OOCKET NUMBEA EVENT OATE REPOAT OATE
[OD1] CON'T LP~O L L 0 3 0 0 3 ~l500- 0 n 1 < 7 5 0 J4 1' 7 7 0 57 50 59 60 6'1 69 74 75 EVENT DESCRIPTION Qp 7 8 9 I . ';lhile performing routine surveillance per plant procedure
'
OHP 4030 STP.003, valve SG local III0-320 (liest esidual heat re'moval oumo to le I
09 toOj4 7 09
~ cong. Valve IHO-325 opened but could not be shut by remote operation.
00
. The valve L1as closed normally using the manual hand@heel. Reference Appendix A 7
Technical Soecifications Section'.5.2.a.
0.9'~g (AO 50-315/75-55) 7 0 9 PAIAu 80 SYSTEM CAUSE COMPONENT COMPONENT COMPONENT COOE SUPPUEA MANUFACTURER
~97 ~C~F E A L V 0 L 2 9 0 7 0 9 10 11 12 17 . 43 "
44 47 CAUSE DESCRIPTION toOI .The limitor ue sLIitch.setting had been at its hinimum oossible setting. Th 7 89 80
~os siiitch ivas reset from'2.0 to 2.7o and the valve was cycled successfully both 7 0 9 80
~1 o manually and remotely.
89 FAC'UTY. 80 METHOO OF ~
OTHEA STATUS OISCOVEAY OISCOVEAY OcSCAIPTION
'!)A B Surveillance T st 7 0 9 10 12 13 44 45 i 46 80 FORM OF AciMTY REI.EASEO COAT NT OF f
RELEASE AMOUNT OF ACTIVITY ia Z' i' LOCATION OF RELEASE 7 8 9 10 11 43I 45 80 PERSOi4NEL EXPOSURES NUI.IBER TYPE OESCAIPTION Pig ~00 0 Z HA 7 09 12 13 00 PERS'ONNEL INJURIES NUMBER OESCAIPTION Qig ~00 0 HA 7 09 11 12 00 PROBABLE CO,"lSE(IJEI~ICES Q~g ilA 7 09 LOSS OR DAMAGE TO FACILITY
'TYPE OESCAIPTION 1116j Z iN 7 09 10 PUBLICITY.
I'lA BQ ADDITIONAL FACTORS
+8 l'lA .
I 09 7 09 OD NAMc: ames Bencivenga PIIONE'65 5901 (Ext. 352).
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47 48 CAUSE DESCRIPTION l00m FA.z.LUR< W~ a ~Uk'~ h p xazF-P P Ac-7 8 9 80 Jag ('AZ +I, 89 7 89. FACILITY METHOO OF 80
~
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LocooJ 10 12 13 Il h 44 45 46 SOP LI;=T.L i:".~L= ~iuC 00 FOAhl OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF liELEASE L7J ~z 7 B B 10 11 44 45 PERSONNEL EXPOSURES r
~~~ ~0~0~ 0 PJZ I 7 8 B..r 11 12 13
~ PERS'ONNEL INJURIES 7 89 .11 12 80 OFFSITE COILISEQUEihiCES
-.
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+
TYPE ~ OESCAIPTION Q~g 7 89 10 PUBLICITY 7 89 80 4
ADDITIONAL FACTORS 80 Q~g i A 7 89 PHONE:
(- ~)
CPO I>i>t ~ 667
CONlllOL BLOCI<: ~ t'PLEA E PRI'AlT fiLl. REOLIQI=.D IM .ORFa1ATIDH r 1 6 LICI!NSLE LICf.t4SE EVI.N I' l!CENSL NUtAOC11 II NAMF:
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[ooa) 7 I@4 09 89 KTp fToads po pT'zcu~
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!3 11 12 P u PXX 17 43 CAUSE DESCRIPTION Jog 7 0 9 PUNp Qt-xz.e.D tO I,=K~LV~ M @~~~I-'C~ a POHCY W'XYA 8 aRXW5 teak 00 t005 >~ >H~<<'lED. ~S- ~ XS Cm os <> c, Pi g.C.= ~La P~~C,~~
7 0 9 80 Pia] 'PV P wu gC .SgW& (T<oi.uDZWC> VALE 7 09 FACILffY IAETll00 OF 7
[g 8 9 7 ~os o 10 12 13 H5.
44 OISCOVERY 45 46
( PF.P b,>>~Qkl O!SCOVEAY OESCA!PRON
.Ei/r-vY 80 FOAM OF ACTIVITY COATENT AELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF AELEASE
[>3 7. z 7 0 o 10 11 44 45 80 PERSONNEL EXPOSURES
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8 9..~ 11, 12 13 00
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PERSONNEL INJURIES 7 09 11 12 80 OFFSITE CONSEQUENCES t 0 t= CP6 ~ h,~~> A,l 8 OVR M I I=K.VIl'~
7 Q~g 09 LOSS OR DAMAGE TO FACILITY P A
'0 TYPE OESCA!PTION t11j L2J 7 09 10 PUBLICITY
~17 7 09 00 J'0 ADDITIONAL FACTOFIS
[ii~] ! A 7 09 7 09 PHONE ~ GEO IIIII ~ 6 II'P