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Category:LICENSEE EVENT REPORT (SEE ALSO AO
[Table view] Category:RO)
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept 05000267/LER-1996-001, :on 960120,test Interval to Test Area Radiation Monitors Exceeded Due to Inattention to Controls for Identifying & Performing Required Surveillance Tests.Test Procedure Reissued & Completed1996-02-22022 February 1996
- on 960120,test Interval to Test Area Radiation Monitors Exceeded Due to Inattention to Controls for Identifying & Performing Required Surveillance Tests.Test Procedure Reissued & Completed
ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation 05000267/LER-1995-006-02, :on 950903,TS Violation Occurred Due to Failure to Meet Minimum Degree of Redundancy.Caused by Equipment Malfunction.Completed Actions to Remove Channel PT-446 from Svc Per Procedure Owp1995-10-0303 October 1995
- on 950903,TS Violation Occurred Due to Failure to Meet Minimum Degree of Redundancy.Caused by Equipment Malfunction.Completed Actions to Remove Channel PT-446 from Svc Per Procedure Owp
ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station 05000267/LER-1993-004, :on 930927,discovered Incorrect Reactor Building Ventilation Sys HEPA Filters Installed Due to Human Error.Replaced Train a Filters1993-10-26026 October 1993
- on 930927,discovered Incorrect Reactor Building Ventilation Sys HEPA Filters Installed Due to Human Error.Replaced Train a Filters
ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning 05000267/LER-1993-003, :on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well Operator1993-06-0303 June 1993
- on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well Operator
ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20035G7381993-04-26026 April 1993 SER Supporting Util 921125 Request for Exemption from Revised Requirements of 10CFR20 to Permit Decommissioning Activities Under Current Requirements of 10CFR20.1 Through 20.601 ML20035E4861993-04-0707 April 1993 Part 21 Rept Re K-400 Circuit Breaker Failed to Meet Certain Rating Requirements Based on ANSI C37.16.Licensees Scheduled Tests on Modified Arc Chutes in Several Different Modes at KEMA-Powertest Lab in Chalfont,Pa 05000267/LER-1993-002, :on 930210,plant Placed in Unanalyzed Condition When Reactor Bldg Crane Detached from Fuel Handling Machine. Caused by Misinterpretation of Applicable Procedural Requirements.Procedure Revised1993-03-11011 March 1993
- on 930210,plant Placed in Unanalyzed Condition When Reactor Bldg Crane Detached from Fuel Handling Machine. Caused by Misinterpretation of Applicable Procedural Requirements.Procedure Revised
05000267/LER-1993-001, :on 930126,discovered That Oil Separator in Radioactive Liquid Effluent Release Line Had Overflowed. Caused by an Ice Plug in Drain Line Downstream of Oil Separator.Ice Plug Thawed & Path Restored1993-02-25025 February 1993
- on 930126,discovered That Oil Separator in Radioactive Liquid Effluent Release Line Had Overflowed. Caused by an Ice Plug in Drain Line Downstream of Oil Separator.Ice Plug Thawed & Path Restored
ML20035D1731992-12-31031 December 1992 Annual Rept 1992 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 05000267/LER-1992-004, :on 920520,FHM Was Moved While Louvers Were Open.Caused by Failure to Follow Procedures.Louvers Were Closed & Personnel Reminded of Necessity to Follow Procedures1992-06-19019 June 1992
- on 920520,FHM Was Moved While Louvers Were Open.Caused by Failure to Follow Procedures.Louvers Were Closed & Personnel Reminded of Necessity to Follow Procedures
ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ 05000267/LER-1992-003, :on 920226,discovered That TS Surveillance Requirement 5.7.1a Re Verification of Fuel Handling Machine Internal Pressure Not Documented Every 12 H.Caused by Inadequate Procedure.Procedure Revised1992-03-27027 March 1992
- on 920226,discovered That TS Surveillance Requirement 5.7.1a Re Verification of Fuel Handling Machine Internal Pressure Not Documented Every 12 H.Caused by Inadequate Procedure.Procedure Revised
05000267/LER-1992-002, :on 920213 & 920216,reactor Bldg Integrity Not Maintained,Per TS LCO 4.5.1 Due to Inadequate Procedure & Failure to Follow Procedure.Truck Bay Door Opening Procedure & Permit as Contained in G-4 Revised1992-03-13013 March 1992
- on 920213 & 920216,reactor Bldg Integrity Not Maintained,Per TS LCO 4.5.1 Due to Inadequate Procedure & Failure to Follow Procedure.Truck Bay Door Opening Procedure & Permit as Contained in G-4 Revised
ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 05000267/LER-1992-001, :920106,discovered That Alternate Cooling Method Exhaust Stack Activities Monitors Not Included in Test Procedure.Caused by Failure to Update Functional Test Procedure.Procedure Revised1992-02-0505 February 1992
- 920106,discovered That Alternate Cooling Method Exhaust Stack Activities Monitors Not Included in Test Procedure.Caused by Failure to Update Functional Test Procedure.Procedure Revised
1997-07-01
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSitN
'T.77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil8l 9C l 0LICENSEE 7
l F l CODE S lV l 1 l@l 010 l- l 0LICENSE 14 15 l0 l0 l010 l- l0 l0 25l@l4 NUMBER 26 l1LICENSE l1 l2TYPE l 0 JOl@l 57 CAT l 58 l@
CON'T IoI11 s$RCI60 l L l@l 0 l 5OOCKET l 0 lNUM8ER 0 l0 l 2 l 686 l 769 @lEVENT 0 l 312 l0 l 8 l075 l@l0 74 REPORT l4 CATE l1 l 8 l 808 l0 l@
7 8 61 DATE EVENT OESCRIPTION AND PROB ABLE CONSEQUENCES h l o l 21 l From 1105 to 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on March 20, 1980, with the plant operating at approximately l lo lal 1 60% thermal power and 216 MWe, the emergency feedwater header supply to Loop 2 helium l l o la I [ circulator water turbine driver was isolated to repair a leaking pressure control l Ioisl l valve. This resulted in operation in a degraded mode of LCO 4.2.2(a) and is re- l ITTs 1 l portable per Fort St. Vrain Technical Specification AC 7.5.2(b)2. No accompanying l
[ol7l l occurrence or probable consequences. No affect on public health or safety. l l0l8l l 80 7 8 9 E COE SUSC E COMPON ENT CODE 508 ODE SU E lo19l lH lH l@ y@ l Bl@ l Vl Al Ll Vl El Xl@ l Fl@ lHl@ 13 18 19 20 7 8 9 10 11 12
_ SEQUENTI AL OCCURRENCE REPCRT REVISION LER EVENT YEAR R EPORT NO. COOE TYPE NO.
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33 34 33 36 31 40 41 43 44 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS h lilol lCause of valve leakage was a loose bole on hinck .rh4 rb i n ch nn a m *
- sta - mh I g istem of a Masoneilan pressure control valve. This did not allow proper stroking, _i i,;7, lresulting in valve leakage. Block cleaned and re-assembled. Valve stroke calibrated. J i, ;3l l Valve and system returned to service. No further corrective action anticipated or l
[il4[ l required. l 7 a 9 80 ST % POWER oTHER STATUS 015 O RY DISCOVERY OESCRIPTION l1 l5 l l E l@ l 0l 6l 0l@lN/A l l Al@l Personnel Observation l ACTIVITY CC TENT RELEASED vP AELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE It i6I l Z l lZh!N/A l l N/A l 7 3 3 10 11 44 45 80 PERSONNEL ExPOSUMES NUM8ER TYPE OESCRIPTION 39 l l i 17 l l 0 l 0 l 0 l@l Z l@l N/A l l PERSON ~EL mu'AEs NUMBER DESCRIPTION li t a8l 31010101@l 12N/A 7 11 80 I
'#$ Eo'i s'C"^i1 cN' ' '^c' " @ 8004240 3Jgl~
l t l 9d l 9l Z l@ltoN/A 7 80 PUBLICITY NRC USE ONLY
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