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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARBVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999
Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831
ML20209J0081999-07-14014 July 1999
Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting
BVY-97-171, Special Rept:On 971105,fire Alarm Panel & Suppression Sys Were Out of Svc Greater than 14 Days.Caused by Hardware Problems W/New Zone Modules Developed During Mods.Sys Placed Back in Svc on 9711211997-12-12012 December 1997
Special Rept:On 971105,fire Alarm Panel & Suppression Sys Were Out of Svc Greater than 14 Days.Caused by Hardware Problems W/New Zone Modules Developed During Mods.Sys Placed Back in Svc on 971121
BVY-97-101, Special Rept:On 970717,determined Ongoing or Recent Contamination Event Could Be Source of Detected Environ Radioactivity.Collection,Analysis & Review of Results of Addl Grab Samples from North Storm Drain Outfall1997-08-0808 August 1997
Special Rept:On 970717,determined Ongoing or Recent Contamination Event Could Be Source of Detected Environ Radioactivity.Collection,Analysis & Review of Results of Addl Grab Samples from North Storm Drain Outfall
ML20148B8701997-04-22022 April 1997
Special Rept:On 970123,periodic Source Leakage Test of 150 Uci Cs-137 Source Revealed Presence of Greater than 0.005 Uci of Removable Contamination.Source Removed from Svc & Will Be Disposed of IAW Applicable Regulatory Requirements
ML20135E0261997-02-27027 February 1997
Special Rept:On 970116,Cable Vault CO2 & Diesel Fire Pump Day Tank Room CO2 Sys Place in Abort.Caused by Installation of New Low Pressure CO2 Sys for Switchgear Rooms.Established Compensatory Measures & Required Manual Initiation for Sys
ML20112F8001996-06-0707 June 1996
Special Rept:On 960424,fire Protection Sys Declared Inoperable as Conservative Precaution for Greater than 14 Days.Calculations for Sys May Not Accurately Reflect Pressure Loss.Mods Being Developed
ML20108C6711996-05-0202 May 1996
Special Rept:On 960320,switchgear CO2 Sys Declared Inoperable.Suppression Sys Remains Capable of Automatic Initiation & Compensatory Measure Will Remain in Effect Until Confirmatory Testing Completed
ML20064C3501994-02-23023 February 1994
Special Rept:On 940127 & 0209,electric Fire Pump Motor Failed to Start Due to Motor Breaker Trip.Redirected Room Heater Discharge to Diesel Fire Pump Engine Area
BVY-92-105, Special Rept:On 920810,electric Fire Pump Portion of Vital Fire Suppression Water Sys Equipment Inoperable for 17 Days. Caused by Need to Perform Preventive maint.Diesel-driven Fire Pump Remained Operable & Contingency Plans Developed1992-09-11011 September 1992
Special Rept:On 920810,electric Fire Pump Portion of Vital Fire Suppression Water Sys Equipment Inoperable for 17 Days. Caused by Need to Perform Preventive maint.Diesel-driven Fire Pump Remained Operable & Contingency Plans Developed
ML20248B9851989-06-0202 June 1989
Special Rept:On 890421,cable Vault Carbon Dioxide (CO2) Sys & on 890424,diesel Fire Pump Day Tank Room CO2 Sys Declared Inoperable.Fire Protection Sys Out of Svc for More than 14 by 890602.Fire Watches Established
ML20236E2751989-03-14014 March 1989
Special Rept:U Slab Source Found to Be Leaking Contamination During Semiannual Radioactive Source Leak Test.Caused by Break Down of Adhesive That Hold Mylar Covering.Source Removed from Svc & Deconned & Resealed W/New Covering
ML20112E1821983-10-0707 October 1983
Rev 1 to RO 83-06:accumulative from 840810-23,buildup of Detectable Quantities of plant-related Co-60 in Connecticut River.Caused by Turbine Bldg Roof Vents Failing to Filter Waste.Procedural Changes Implemented
ML20086E2201975-03-10010 March 1975
Ro:On 750209 & 10,excessive Level of Heat Rejected to Connecticut River & Filter Paper Sample Whisked from Numbed Technician Hand by Wind,Respectively.Events Caused by Lack of Communication & Wind,Respectively
ML20086E4101975-01-0909 January 1975
Ro:On 741126,RHR Svc Water Pump C (P-8-1C) 1,200-amp Circuit Breaker Encountered Significant Damage During Attempted Start.Caused by Migrating Ionized Gases Causing Front Primary Disconnect Device Failure.Breaker Replaced
ML20086E6571974-04-25025 April 1974
Ro:On 740414-16,each Operable Control Rod Not Fully Inserted Was Not Exercised One Notch During Surveillance Exercise. Cause Not Stated.Strict Adherence to Surveillance Test Schedule Emphasized
ML20086D8711973-03-0606 March 1973
Ro:On 730205,all-purpose Fuel Grapple Became Detached from Jib Crane Hoist Cable When Tension Applied to Cable.Caused by Design Error.Grapple & Cable End Stud Reassembled,End Stud Drilled & Roll Pin Installed & Staked
1999-08-19
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999
Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18
ML20217G2041999-10-13013 October 1999
Safety Evaluation Supporting Amend 179 to License DPR-28
BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With
ML20212C2551999-09-17017 September 1999
Safety Evaluation Supporting Amend 175 to License DPR-28
BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Vermont Yankee.With
BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999
Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831
BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Vermont Yankee. with
ML20209J0081999-07-14014 July 1999
Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting
BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With
ML20196G5071999-06-23023 June 1999
Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading
BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With
BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Vynp.With
ML20206E8741999-04-29029 April 1999
SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application
ML20206D9301999-04-27027 April 1999
1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion)
ML20205S4211999-04-16016 April 1999
Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion
ML20205K7581999-04-0707 April 1999
Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV
BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With
ML20205F6631999-03-0404 March 1999
Jet Pump Riser Weld Leakage Evaluation
BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With
ML20205P8241999-02-28028 February 1999
Rev 2 to Vermont Yankee Cycle 20 Colr
ML20203H9881999-02-18018 February 1999
SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl
ML20203A6951999-02-0404 February 1999
Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam)
ML20199K7151999-01-21021 January 1999
Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification
ML20199K6991999-01-20020 January 1999
Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable
ML20199L5951999-01-14014 January 1999
Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i)
BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998
Corp 1998 Annual Rept. with
BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station
ML20198H5481998-12-23023 December 1998
Rev 2 to Vermont Operational QA Manual,Voqam
ML20196H8641998-12-0101 December 1998
Cycle 19 Operating Rept
BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With
ML20195C4161998-11-0909 November 1998
SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds
BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With
ML20155B6471998-10-26026 October 1998
Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage
ML20154N0891998-10-16016 October 1998
Rev 1 to Vermont Operational QA Program Manual (Voqam)
ML20154B6951998-10-0101 October 1998
SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station
BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With
ML20239A1361998-09-0202 September 1998
SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program
BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With
ML20151U0361998-08-28028 August 1998
Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project
ML20237E9221998-08-20020 August 1998
Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603
BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station
ML20205F6491998-07-31031 July 1998
Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee
ML20236G0011998-06-30030 June 1998
Individual Plant Exam External Events
BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station
ML20248C5081998-05-31031 May 1998
Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20
ML20248C4951998-05-31031 May 1998
Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr
BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station
ML20247J8341998-05-31031 May 1998
Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998
ML20247G4001998-05-12012 May 1998
Interview Rept of Ej Massey
ML20247E6351998-04-30030 April 1998
Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee
1999-09-30
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Text
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6
- - VERhiONT YANKEE NUCLEAR POWER CORPOR ATION P. O. BOX 157 !
GOVERNOR HUNT ROAD VERNON, VERMONT 05354 ,
o March 14, 1989 j VYV +89-064 1
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
REFERENCE:
Operating' License DPR-28 Docket.No. 50-271
'Special Report
Dear Sirs:
. As defined by Technical Specification 6.5.F., we are submitting the attached Special Report.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION
, , ih E'N&
ames P. Pelletier Plant Manager cc Regional Administrator USRNC Office of Inspection and Enforcement Region I 475 Allendale Road King of Prussia, PA ~19406
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DESCRIPTION'0F EVENT. l During performance of the semi-annual radioactive source leak test our 4"x4"x0.25" Uranium slab source was. found to be leaking contamination. The
' total activity measured by the:1eak test was 0.017 uCi which is in excess of 4 the limit 0.005 uCi specified in our Technical Specification 6.5.F. The source -i is'used to verify Beta response on our Eber11ne R0-2 dose rate instruments.
J CAUSE OF TE EVENT 1
Tha source had successfully passed its last routine leak test. The source has been in use for many years and the adhesive that holds the mylar covering has begun to break down and this allowed contamination to escape.
CORRECTIVE ACTION A comprehensive smear survey was performed of the areas where the source is used and stored. No additional contamination was found. The source was removed- i from service, and deconned and re-sealed with a new protective covering. The source successfully passed a leak test, and it was returned to service, l'
u l-
