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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20141D9651986-03-27027 March 1986 Ro:On 860314,compensatory Measures Implemented Due to Announcement of Bomb at Level 5 Reactor Door.Caused by Contract Employee,Unaware of Seriousness of Threat.No Bomb Found & No Threat to Security Existed ML20099C9631984-10-29029 October 1984 Ro:On 840911,moisture Discovered in Purified Helium Supply Line Wells During Installation of New Moisture Sensing Probes.Tests Indicate Leak Source Is Circulator Penetration A.Rate of Leak Approx .05 Gpm ML20098B3051984-09-0707 September 1984 Ro:On 840904,while Removing CRD & Orifice Assembly,Motor Overcurrent Condition on Auxiliary Transfer Cask Shutters Occurred,Preventing Full Closure.Caused by One Control Rod String Not Fully Retracted.Work Temporarily Discontinued ML20092N4741984-06-18018 June 1984 Ro:Re Failure of Masoneilan C-domotor Actuator During Steam Line Rupture Simulation Testing.Corrective Actions:Closed Shutoff Valves Installed Between Gauges & Taps.Gauges, W/Welded Stainless Steel Bourdon Tubes,Ordered ML20082A8431983-11-0707 November 1983 RO 83-43:on 831011,util Notified NRC of Various Nonconservative Errors Made in Original Analyses Which Constitute Basis of Tech Spec 4.1.9.GA Technologies Provided Interim Curves Which Corrected Deficiencies ML20069H1061983-03-17017 March 1983 RO 83-007:on 830215,instrument Power Inverter 1B Failed. Caused by Blown 150 Amp Fuse.Reactor Manually Scrammed, Instrument Bus re-energized & Blown Fuse Replaced ML20054F8461982-06-0909 June 1982 Ro:On 820605,one of Two Undervoltage Relays Which Monitor Reserve Auxiliary Transformer Tripped,Causing Load Shedding of Essential Busses 1 & 2.Caused by Procedural Inadequacy ML20054H2391982-05-0404 May 1982 Ro:On 820426,crack Found Extending Across Min cross-section Between Coolant Hole & One Face of Fuel Element 1-2415 Down Full Length of Block to Lower Exit.Caused by Mishandling. Damage Does Not Extend to Dowel Pin ML20064G7251978-12-0707 December 1978 Suppl Info to RO 50-267/78-05/03-X-1 on 781107:during Oper at 13% Thermal & 0 Elec Pwr,One of Three 1A Circulator Speed Indication Channels Was at 0,due to Bridge Unbalance.Similar Problem Occurred 7 Times Since 780425 ML20064G5661978-12-0505 December 1978 on 781129 at 4:00 Pm,Due to Problem in Heluim Circulatory Sys,There Was a Minute Release of Radioactivity in Reactor Bldg.No Hazard to Public ML20085L6121976-09-30030 September 1976 RO 50-267/75/05B:on 750323,helium Circulators 1A & 1B Tripped & Buffer Differential Pressure Indication of Helium Circulators 1C & 1D Dropped.Caused by Increased Pressure in Surge Tanks Due to Water Inflow.Procedures Revised ML20085M6621975-12-18018 December 1975 RO 50-267/75/17A:on 750912,orifice Valve Assembly Associated W/Control Rod Drive Observed Falling Vertically from Normally Installed Position.Caused by Improper Final Assembly of Control Rod Drive Unit ML20085M5851975-12-15015 December 1975 RO 50-267/75/18A:on 750924,while Removing Boron Carbide Balls from Reserve Shutdown Assembly of Control Rod Drive, Serial Number 28,core Region 13,light Deposit of White Crystal Noted on Surface of Several Balls ML20085M5141975-11-18018 November 1975 RO 50-267/75/20:on 751024,reactor Plant Supply Fan 1B Developed Fault,Causing Reactor Plant MCC 3 Essential Bus to Be Out of Svc During Repair of Fan 1A.Caused by Loose Electrical Connection.Bus & Motor Meggered & Verified ML20085M5381975-10-17017 October 1975 RO 50-267/75/16:on 751009,apparent Failure of Control Sys for Circulator High Pressure Separator C Resulted in Flooding of High Pressure Separator.Low Selector Removed, Disassembled,Inspected & Cleaned ML20085M6141975-10-17017 October 1975 RO 50-267/75/19:on 750926,spare Control & Orifice Assembly Modified by Addition of New Seals to Reduce Helium Bypass Flow.Caused by Seal Ring Larger in Outside Diameter than Inside Diameter at Refueling Penetration ML20085M6021975-10-13013 October 1975 RO 50-267/75/13A:on 750911,fan Start Relay for 480-volt Transformer 1B Failed.Caused by Component Failure & Design Flaw.Relays Replaced W/Better Application & Relay Logic Circuitry Reversed to Require Deenergized Relay ML20085M6071975-10-0909 October 1975 RO 50-267/75/13:on 750911,fan Start Relay for 480-volt Tansformer 1B Failed.Caused by Component Failure & Design Flaw.Relays Replaced W/Better Application & Relay Logic Circuitry Reversed Requiring Deenergized Relay ML20085M5521975-10-0202 October 1975 RO 50-267/75/17:on 750912,orifice Valve Assembly Associated W/Control Rod Drive Observed to Have Fallen Vertically Downward from Installed Position.Caused by Improper Final Assembly of Control Rod Drive Unit ML20085M5941975-09-30030 September 1975 RO 50-267/75/18:on 750924,during Removal of Boron Carbide Balls from Reserve Shutdown Hopper Assembly of Control Rod Drive,Serial Number 28,core Region 13,light Deposit of White Crystal Noted on Surface of Several Balls ML20081J5621975-09-29029 September 1975 RO 50-267/75/14:on 750829,480-volt Bus Tie Breaker Between Bus 2 & 3 Opened Removing Power from 280-volt Bus 2.Caused by Opening of Bus Tie Breaker.Tie Breaker Trip Settings Adjusted ML20085L6381975-07-21021 July 1975 RO 50-275/75/8:on 750428,insp Revealed That Adequate Fire Stops in Vertical Cableways Between Floors in Reactor Bldg, in Horizontal Cable Trays & in Vertical Cable Ducts Not Installed Per FSAR Commitment.Cause Not Stated ML20085L5981975-06-18018 June 1975 RO 50-267/75/10:on 750428,analysis of Pcrv Cooling Tube Outlet Temps Revealed Four Tubes W/Temp of 24 F.Caused by Differential Pressure Driving Control Rods Into Annulus. Drive Housings Will Be Modified ML20085M7461975-06-17017 June 1975 RO 50-267/75/2A:on 750115,both Secondary Coolant Loops Appeared Isolated Simultaneously by PPS Action.Caused by Design Error.Capacitors Added Across Collector Load of Output Buffer Transistors ML20085L6341975-05-29029 May 1975 RO 50-267/75/12:on 750516,engine B Failed to Start Due to Fuel Sys Airlock.Caused by Fuel Being Shut Off W/O Engine Being Removed from Svc.Procedure Will Be Revised ML20085L6221975-05-0707 May 1975 RO 50-267/75/7:on 750428,temporary Cables from Auxiliary Electrical Equipment Cabinets Not Segregated from Permanent Cables.Cause Not Stated.Work Authorization Issued to Correct Color Coding ML20085L6391975-04-30030 April 1975 RO 50-267/75/6:on 750402,bearing Water Makeup Pump P-2105 Handswitch Insp Revealed Discrepancies in Maintaining Bus Segregation Requirements.Cause Not Stated.Field Change Notice Issued to Correct Discrepancies ML20085L6981975-04-18018 April 1975 RO 50-267/75/5:on 750323,circulators a & B Tripped Off & Buffer Indications on Circulators C & D Dropped.Caused by Increased Pressure in Surge Tanks Due to Water Inflow Displacing Helium & Increasing Suction Pressure ML20085L6521975-03-14014 March 1975 RO 50-267/75/4:on 750213,control Rod & Orifice Position Indicators Operated Erratically Due to High Moisture Levels in Primary Coolant Circuit.Caused by Shutdown of Purification Sys.Potentiometer Test Developed ML20085L7251975-03-0404 March 1975 RO 50-267/75/3:on 750203,drop in Loop 2 Instrument Bus Voltage Caused Loop 1 Helium Circulator to Trip.Cause Not Stated ML20085L7791975-03-0404 March 1975 RO 50-267/75-1-A:on 750117,insp Revealed Discrepancies in Maintaining Loop & Bus Segregation Requirements.Caused by Error in Installation.Wires,Switches & Relays Not Meeting Segregation Requirements Separated ML20085L7831975-01-31031 January 1975 RO 50-267/75/1:on 750117,insp Revealed Discrepancies in Maintaining Loop & Bus Segregation.Caused by Error in Installation.Wires,Switches & Relays Separated ML20085L7971975-01-14014 January 1975 RO 50-267/75/2:insp of Steam/Water Dump Valves Revealed That Portions of Electrical Conduit Runs to Valves Violated Loop & Bus Segregation Criteria.Caused by Improper Installation. Cables,Switches,Solenoids & Junction Boxes to Be Modified ML20086E2261974-11-0606 November 1974 RO 50-267/74/1:on 741106,during Review,Short That Could Potentially Lead to Loss of Both Power Supplies on Circulatory Auxiliary Control Panel I-29 Discovered.Caused by Design Error.Three Wires Removed ML20086E2091974-01-14014 January 1974 Ro:On 740112,during Insp of Permanent Half Size Top Reflector,Seven Elements Failed to Meet Specs for Chips & Gauges.Spare Reflectors Replaced Failed Elements.Great Lakes Carbon,Supplier of Elements,Contacted ML20086E1951974-01-14014 January 1974 Ro:On 740114,during Insp of Metal Clad Keyed Top Reflector Elements,Burrs Found on Drilled Holes in Bottom of Distribution Plate.Seven Elements Installed Will Be Removed. Procedure from Ga Co Awaited ML20086B1431971-10-29029 October 1971 Ro:On 710514,0819 & 0924,reactor Trip Breakers Failed to Open When Trip Signal Applied.After Investigation, Westinghouse Determined Undervoltage Device Latch Spring Pressure Improperly Set.Devices Adjusted 1991-11-05
[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 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results 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 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 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. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00: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.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx 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 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/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
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o o puhuc service con.pany *e Cohndo P. O. Box 361, Platteville, Colorado 80651 December 15, 1975 Fort St. Vrain [
Unit No. 1 P-75023 #
4 (c Mr. E. Morris Howard, Director y Nuclear Regulatory Commission _ ,;'.,
Region IV 2' O /S/
y"',7J'*/> .g hj Office of Inspection and Enforcement *D,j* " J'/
Suite 1000 _I
./
Arlington, Texas 76012 9 . ;f ,
REF: Facility Operating License No. DPR-34 Docket No. 50-267
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Dear Mr. Howard:
Enclosed please find a copy of Unusual Event Report No. 50-267/75/18A, Final, submitted per the requirements of the Technical Specifications.
Very truly yours,
[
h' 6[*b' vfN j i Frederic E. Swart !
Superintendent, Nuclear Producti'on Fort St. Vrain Nuclear Generating Station FES/alk cc: Mr. Roger S. Boyd oule t etN1 itEGION ' -
PJTe8FdBhapg 80 S
o c .. O REPORT DATE: December 15, 1975 UNUSUAL EVENT 75/18A OCCURRENCE DATE: September 24, 1975 IDRT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO -
P. O. BOX 361 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/75/18A FINAL IDENTIFICATION 0F OCCURRENCE:
While removing the boron carbide balls from the Reserve Shutdown hopper assembly of control rod drive, serial number 28, core region 13, it was noted that there was a light deposit of white crystals on the surface of several of the balls.
This was identified as an unusual event per ADM 31, Attachment 4.1, II.C.
CONDITIONS PRIOR TO OCCURRENCE: Steady State Power Routine Shutdown Hot Shutdown Routine Load Change X Cold Shutdown Other (specify)
Refueling Shutdown Routine Startup The major plant parameters at the time of the event were as follows: -
./
Power RTR 0~ MWth ELECT 0 NWe -
Secondary Coolant Pressure N/A psig Temperature N/A *F Flow N/A f/hr.
Primary Coolant Pressure O psig ,
Temperature 120 *F Core Inlet l 120 *F Core Outlet Flow 1 circulator at 4,000 RPM f/hr. ., ,
.(
o
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O UNUSUAL EVENT 75/18A
- Page 2 of 2 ..
. I DESCRIPTION OF '
OCCURRENCE: l As stated in the attached report, " Status Report on Reserve Shutdown System",
by General Atomic Company Staff, November, 1975; GA-A 13742.
APPARENT CAUSE OF OCCURRENCE:
As stated in the attached report, " Status Report on Reserve Shutdown System",
by General Atomic Company Staff, November,1975; GA-A 13742.
ANALYSIS OF OCCURRENCE:
As stated in the attached report, " Status Report on Reserve Shutdown System",
by General Atomic Company Staff, November,1975; GA-A 13742.
CORRECTIVE ACTION:
Since the capability of the system or related systems is in no way effected, no further corrective action will be taken. ,
FAILURE DATA /SIMILAR REPORTED OCCURRENCES:
None PROGRAMMATIC IMPACT: .
None CODE IMPACT: ,
None <-
r.
! Submitted by: / .
l Harvey N. Hillfard, Jr. /
Technical Services Supervisor ,
l -
Reviewed by: e I Dick Nirschl GAC' Fuels Division Representative 1
Approved by: z$<- > . M tu n F ederic E. Swart I -
uperintendent, Nuclear Production
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. O O IMUSUAL EVENTS AND ABNORMAL OCCURRENCE REPORTS DISTRIBtTTIONS Number of Copips San Francisco Operations Office ERDA 1333 Broadway Oakland, California 94612 Attna K2 nager 2*
California Patent Group la Division of Reactor Research and Development ERDA Washington, D.C. 20545 Attnz Director le Asst. Dir. for Cas Cooled Reactor Projects 2*
Asst. Dir. for Engrg. and Technology 1*
Asst. Dir. for Reactor Safety 1*
ERDA-SCRPO-SD 18 F. O. Box 81325 San Diego, California 92138 Project Engineer 1*
ERDA - SCRPO F. O. Box 1446 Canoga Park, California 91304 Address ~ Director 1
To F. O. Box 1446
,Canoga Park, California 91304 Technical Information Center '
3e
. IRDA*
F. 0. Box 62 .
Oak Ridge. Tennessee.37830 Address ~ John M. Waage', Project Manager 10*
FFLG General Atomic Company To P. O. Box 81608 San Diego, California 92138 Address - Mr. E. Morris Howard, Director Letter Region IV,
- To Office of Inspection & Enforcement Nuclear Regulatory Cosrnission 611 Ryan Plaza Drive Seite 1000 Arlington, Texas 76012 Director of Nuclear Reactor Regulation 1 (copy of Howard's letter &
Atta: Mr. Roger S. Boyd, Acting Director asilogram)
Division of Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 .
Secretary, NFSC, Belleview 1 Tice President, Engineering & Planning, 39th Avenue Engineering 1 Manager of Production (Chairman, NFSC), Belleview 1 Director Quality Assurance 1 Technical Services Supervisor 1 Superintendent, Nuclear Production . 1 1 Superintendent. Operations
Training Coordinator 1 1
, FORC Committee 1 l l Technical Services Files -
1 1 Training Review 6 )
l l
- Indicates a zerox copy of the letter to the Director ERDA-SCRPO, is sent with the copies l l of the report. I J
1 1
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