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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARNPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable NPL-97-0831, Special Rept:On 971201,fire Protection Wrap Required for Svc Water Pump Motor Cables Had Been Rendered Inoperable for More than Seven Days.Caused by Planned Repair activity.Once- per-hour Fire Patrol Established1997-12-23023 December 1997 Special Rept:On 971201,fire Protection Wrap Required for Svc Water Pump Motor Cables Had Been Rendered Inoperable for More than Seven Days.Caused by Planned Repair activity.Once- per-hour Fire Patrol Established NPL-97-0751, Special Rept:On 971023,low Temp Overpressure Protection Sys Operation Occurred.Caused by Starting Reactor Coolant Pump w/water-solid Reactor Coolant Sys.Operating Personnel Will Be Briefed on Event1997-11-21021 November 1997 Special Rept:On 971023,low Temp Overpressure Protection Sys Operation Occurred.Caused by Starting Reactor Coolant Pump w/water-solid Reactor Coolant Sys.Operating Personnel Will Be Briefed on Event NPL-97-0287, Special Rept:On 970421,fire Door 106A in DG Bldg,Separating Mechanical Equipment Room from Unit 2,B-train,4KV Switchgear Room,Found in Open Position (Closed But Not Latched)1997-05-21021 May 1997 Special Rept:On 970421,fire Door 106A in DG Bldg,Separating Mechanical Equipment Room from Unit 2,B-train,4KV Switchgear Room,Found in Open Position (Closed But Not Latched) ML20132E0681996-12-17017 December 1996 Ro:On 961114,declared Noble Gas Monitor Inoperable.Caused by Necessary Addl Repairs on Failed Pump & Subsequent re- Testing of Sys.Will Repair P-707A Pump & Perform in-service Test by 961220 ML20080P9591995-03-0303 March 1995 Special Rept:On 950207,control Rod H8 in Control Bank B Dropped.Investigation Revealed No Abnormal Conditions. Decision Was Made to Recover Dropped Rod ML20099B9551992-07-29029 July 1992 Ro:Fire Penetration Seal Degraded & Inoperable for More than 7 Days.Caused by Voids in Seal Structure.Hourly Fire Watch Established & Mod to Seal Completed on 920720 ML20195B7271988-10-26026 October 1988 Special Rept:On 880831,emergency Diesel Generator Unexpectedly Returned to Full Speed & Voltage Condition. on 880929 & 1012,event Recurred.Exact Cause Not Determined. Addl Testing Planned Over Next 90 Days to Pinpoint Cause ML20072U4281983-03-30030 March 1983 Ro:On 830308,turbine Trip & Subsequent Reactor Trip Experienced.Caused by Bumping of Main Steam Stop Valve Relay by Contractor Employee While Working on Control Panel. Cleanup Flow Maintained.On 830306,I-131 Limit Exceeded ML20087L1071975-02-0404 February 1975 Telecopy Ro:On 750203,Nuclear Fuel Svcs Spent Fuel Shipping Cask 4B Received & Found in Excess of 22,000 Disintegrations Per Minute 100 Centimeters Squared Removable Contamination on Cask Surface ML20087L1121975-02-0404 February 1975 RO 75-2:on 750224,test of Containment Purge Inlet & Exhaust Valves Closing Time Disclosed That Valves 1CV-3212 & 1CV-3244 Exceeded 3-5 Min Closing Time.Caused by Sticking Pneumatic Relays in Valve Air Operators ML20087L1881975-01-24024 January 1975 Ro:On 741219,discovered That One Insp of Station Batteries Not Completed within Prescribed 30 Day Frequency or within Allowable 25% Grace Period.Caused by Scheduling Difficulty Due to New Supervisor ML20087L6331974-02-0606 February 1974 Ro:On 740102,during Quarterly Functional Testing of Emergency Diesel Backup Relays 4D,fast Start Backup Relays SFB1 & SFB2 Would Not Perform Intended Function.Caused by Neoprene Bellows in Timing Chamber ML20085M3951973-10-29029 October 1973 Ro:Describing Possible Backseating Disc Mislocation Problem on 2-inch Darling Valves on S-350 Wdd Welding End.Valves Repaired.Valve Stems Will Be Changed During Next Refueling Outage ML20087L6351973-05-14014 May 1973 Ro:On 730303 & 0426,test of Undervoltage Relays of 1A01 & 1A02 Nonsafeguards Bus Undervoltage Relays Disclosed Three Out of Four Malfunctional.Caused by Setting of Shaft in Guide Bearing.Relays Removed & Returned to Vendor for Exam ML20087L6551973-03-0909 March 1973 Ro:On 730208,during Performance of Functional Test on Purge Valves,Two Containment Purge Inlet Valves Open When Placing Manual Switch to Open Position But Did Not Close.Caused by Loose Screw on Switch.Mod Made to Valve Circuits 1998-03-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
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Wisconsin Electnc l POWER COMPANY l
Point Beach Nuclear Pk2nt (414) 755-2321 6610 Nuclear Rd Two Rivers. WI 54241 NPL 97-0287 I l
May 21,1997 Document Control Desk U.S. NUCLE AR REGULATORY COMMISSION Mail Station PI-137
' Washington, DC 20555 Ladies / Gentlemen:
DOCKETS 50-266 AND 50-301 SPECIAL REPORT PBNP FIRE DOOR 106A DEGRADED CONDITION POINT BEACII NUCLEAR PLANT. UNITS 1 AND 2 The following report describes the condition of a fire door considered part of the Point Beach Nuclear Plant (PBNP) fire protection design previously approved by the NRC. This report is submitted in accordance with PBNP requirements in the Fire Protection Evaluation Report (FPER). The FPER recently incorporated plant fire protection provisions previously contained in the Technical Specifications. These provisions include the reporting ofinoperable fire protection equipment and are implemented by PBNP procedure OM 3.27," Control of Fire Protection and Appendix R Safe Shutdown Equipment." In accordance with these plant documents, all fire barriers (including fire doors) protecting 1 safety-related areas shall be operable. If an inoperable fire barrier is not restored to operable status I within 7 days a special report to the Nuclear Regulatory Commission is required describing the degraded I condition and plans for restoration of the equipment. l Condition Descrintion On April 21,1997, fire door 106A in the Diesel Generator Building, separating the mechanical equipment room from the Unit 2, B-train,4KV switchgear room, was found in the open position (closed ;
, but not latched). The door closer was determined to be sticking and not providing sufTicient force to
[
l automatically close and latch the door aller personnel access through the doorway. The door could be y
' manually closed and latched. Work Order 111114 was initiated to adjust the door closer. A condition gO report was not initiated and the fire door was not reported as inoperable. Fire rounds were not initiated 7
- in accordance with plant requirements in OM 3.27.
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- 3 . , May 21,1997
! Page 2 On 5/19/97, during routine plant activities, personnel from the operations staff noted a work order on the i door. The door had been in this condition for greater than 7 days without being restored to operable l status. A fire watch and condition report were initiated immediately upon this discovery.
Significance Fire door 106A separates a mechanical equipment room containing no safety-related equipment from the Unit 2, B-train,4KV safety-related switchgear and related equipment. Unit I was in cold shutdown and Unit 2 in a defueled condition during the period fire door 106A door closer was inoperable. Fire door !
106A and the fire barrier provide protection of the safety related equ:pment from potential damage from a fire exposure in the mechanical equipment room.
Fire door operability, as defined in OM 3.27, includes a fire door being able to automatically close and latch. Fire doors that do not latch have the potential of swinging open dur:ng a fire allowing the fire to spread between adjacent areas. Fire door 106A swings out from the switthgear room it was installed to !
protect. A fire in the mechanical equipment room would likely have forced the door against the door stops to the closed position.
It is common practice at PBNP to check doors closed after passing through them. Although the door did not automatically latch closed, plant personnel would have likely manually closed and latched the door.
The door is considered operable as a fire barrier when in the closed and latched position. Given these i circumstances, this degraded fire door condition over a period beyond 7 days presented little increased I fire risk to the safety-related equipment and had no affect on plant safe shutdown capability. This fire barrier is not required to provide fire protection separation for safe shutdown capability under 10 CFR 50 Appendix R, Section III.G or III.L.
Actions laken A fire watch and condition report were initiated immediately upon discovery by the operations staff.
Additional corrective actions outlined in OM 3.27 were applied. The work order was reviewed and restoration expedited. This 30 day report was initiated as required by existing plant fire protection program requirements.
Cattsc Fire door 106A was considered inoperable because the door closer was sticking and required l maintenance and adjustment. Personnel discovering the condition were unavare of the requirements for fire doors in the FPER and OM 3.27, and did not consider the door inoperable because the closer required adjustment. The condition was not reported promptly under the existing corrective action program and therefore a fire watch was not initiated and the door not restored to full operable status within 7 days from identifying the degraded condition.
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1 l
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y NPL 97-0287
.- , , May 21,1997 Page 3 Corrective Actions and Plan for Restoration Work Order 111114 was completed. The door closer was adjusted and door tested. Fire door 106A has been restored to operable status.
j Plant personnel will be informed of the operability requirements for fire doors and need to report fire l door degradation under the condition reporting system.
l l Please contact us if you have any questions or require additional information.
1 Sincerely, f .
sh~-
Douglas F. Johnson, Manager Regulatory Services and Licensmg l
TGM/ lam l
cc: NRC Regional Administrator NRC Resident Inspector h
i
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