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| | issue date = 05/11/1992 | | | issue date = 05/11/1992 |
| | title = Special Rept 92-2-1:on 920324,0414,15 & 25,fire Barriers Impaired for More than 7 Days to Support Planned Work in SW Sys,Sw Project Support & SW Pipe Replacement.Hourly Fire Watch Will Continue Until All Concerns Resolved | | | title = Special Rept 92-2-1:on 920324,0414,15 & 25,fire Barriers Impaired for More than 7 Days to Support Planned Work in SW Sys,Sw Project Support & SW Pipe Replacement.Hourly Fire Watch Will Continue Until All Concerns Resolved |
| | author name = VONDRA C A | | | author name = Vondra C |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:* |
| | Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 11, 1992 |
| | : u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION .LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO .. 1 SPECIAL REPORT 92-2-1 May 11, 1992 This supplemental report addresses additional fire barrier impairments which had not been restored to functional status within seven (7) days. This report has been prepared in accordance with the reporting requirements of Technical Specification Action Statement
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| : 3. -7. 11. a pursuant to Technical Specification
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| : 6. 9. 2. It is being submitted within thirty (30) days as required.
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| MJP:pc Distribution
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| .:. .. ' *' ::i .. _: 9205190067 920511 ' PDR ADOCK 05000272 S PDR Sincerely yours, c. A. Vondra General Manager -Salem Operations
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| /{; 2i I \\/ ,/ v 95*2189 (10/J,) 12*89
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| '.
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| * UNIT 1 SPECIAL REPORT 92-2-1 PLANT IDENTIFICATION:
| |
| Salem Generating Station -Unit 1 Pubiic Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
| |
| * Technical Specification 3.7.11; Fire Barriers Impaired For Greater* Than Seven (7) Days in Support of Planned Work *Event Dates: 3/24/92, 4/14/92,*
| |
| 4/15/92 _and 4/25/92 Date: *5/11/92 This report was initiated by Incident Report Nos. 92-190, 92-229, 92-233 and 92-257. It is a revision to Special Report 272/92-2 which. includes additional Unit 1 penetration seals inoper?ble for greater than seven { 7) . days in support of the tenth refueling outage. CONDITIONS PRIOR TO OCCURRENCE:
| |
| 3/17/92: 4/07/92: 4/08/92: 4/18/92: Mode 1 Reactor Power 100% -Unit Load 1160 MWe Mode 5 {Cold Shutdown);
| |
| *10th Refueling Outage in progress .Mode. 6 *{Refueling)
| |
| Mode 6 DESCRIPTION OF OCCURRENCE: .Per Technical Specification Action Statement 3.7.11.a, a Special Report is required when fire barrier penetration seals are impaired for greater than seven (7)
| |
| This report satisfies this . _requirement. subject fire barrier impairments were initiated to support design . I changes and other Salem Unit 1 outage activities.
| |
| Normally, the I planning of penetration impairments includes repair within seven (7) . days. However, to support the work identified in this report, the penetrations could not be repaired within seven (?)days. On March 17, 1992, two (2) fire barrier penetrations were impaired in support of Service Water System modifications
| |
| .. on April 7, 1992, ten (10) fire barrier penetration seals were impaired in support of Service Water System modifications.
| |
| On April 8,:1992, thirty-four . *c 34) fire barrier penetration seals were impaired in support of Service Water system pipe replacement for the Auxiliary Building Room Coolers. On April. 18, one (1) fire barrier penetration seal was impaired to support Room Cooler cleaning.
| |
| These penetrations are located as follows: Date of No. of Impairment Penetrations 3/17/92 1 Purpose SW System* Modifications Location*
| |
| 122 1 El. Aux. Bldg. Boric Acid Tank Room Floor Plate
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| **
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| * UNIT 1 SPECIAL REPORT 92-2-1 DESCRIPTION OF OCCURRENCE: (cont'd) Date of No. of Impairment Penetrations 1 4/7/92 10 4/8/92 1 4 2 1 1 1 1 2 3 4 7 1 2 1 Purpose Location 84' El. Aux. Bldg. cont. spray Pump, Tank Area Floor Piate
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| * SW project support 78' El. Mechanical Penetrations to containment.
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| SW pipe replacement
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| #12 RHR Pump Room *
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| * Laundry, Shower, . & Chemical Pump & Tank Room Nos. 11 & 12 Injection Pump Room Equipment Hatch -122 1 El. Equipment Hatch -'100 1 El. Equipment Hatch -84 1 El. Equipment Hatch -64 I El. #11 Comp. Cooling . Heat Exch. & Pump Room #11 & 12 Cont. Spray-Pumps
| |
| & Spray Add. *Tank Valve Alley #12 Comp. Cooling Heat Exch. & Pump Room #11 & 12 Safety Injection Pump Room 64 1 Aisle #1 Water Recirculation Heater Room
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| * * . UNIT 1 SPECIAL REPORT 92-2-1 DESCRIPTION OF OCCURRENCE: (cont'd) Date of No. of Purpose Impairment*
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| Penetrations
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| : 1. 1 4/25/92 1 Room Cooler Work Location 64 1 Lobby 84 1 Elevator Lobby 100 1 Baling & Storage Area An hourly roving fire watch was previously established for the *above fire areas due to other fire.protection concerns.
| |
| Therefore, the requirements of *Technical Specification 3.7.11 Action "a", were Technical Specification 3.7.11.states: "All fire penetrati9ns (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting.
| |
| safety related areas shall be functional." Action Statement 3.7.11.a states: "With one (1) or more of the above required fire barrier penetrations nori-functional; within one (1) hour either establish a continuous fire watch on at least one (1) side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one (1) side. of the non-functional fire barrier and an hourly fire watch patrol. Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification*
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| 6.9.1, prepare and submit a Special Report to the Commission pursuant to.Specification
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|
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| ====6.9.2 within====
| | SALEM GENERATING STATION |
| the next (30) days outlining the action taken, the cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration(s) to functional status." APPARENT CAUSE OF OCCURRENCE:
| | .LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO .. 1 SPECIAL REPORT 92-2-1 This supplemental report addresses additional fire barrier impairments which had not been restored to functional status within seven (7) days. This report has been prepared in accordance with the reporting requirements of Technical Specification Action Statement 3. -7. 11. a pursuant to Technical Specification 6. 9. 2. It is being submitted within thirty (30) days as required. |
| The cause of the fire barrier penetration impairments is to support ANALYSIS OF OCCURRENCE:
| | Sincerely yours, |
| The functional integrity of fire barrier penetrations ensures that 'fires will. be confined or adequately retarded from spreading to adjacent portions of the facility.*
| | : c. A. Vondra General Manager - |
| This feature minimizes the possibility of a single fire involving several areas of the facility. | | Salem Operations MJP:pc Distribution |
| The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
| | .:. ~- . ' |
| This report satisfies reporting requirements of Technical Specification Action statement 3.7.11.a, pursuant to Technical Specification
| | *' ::i ~-~ ;~ .. _: ~ |
| | /{; 2i I \\/ |
| | 9205190067 920511 ' ,/ 95*2189 (10/J,) 12*89 v |
| | PDR ADOCK 05000272 S PDR |
|
| |
|
| ====6.9.2 since====
| | '. UNIT 1 SPECIAL REPORT 92-2-1 PLANT IDENTIFICATION: |
| the time between impairment and eventual repair of the fire barrier penetrations is greater than seven | | Salem Generating Station - Unit 1 Pubiic Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE: |
| 'A *J ' ** | | Technical Specification 3.7.11; Fire Barriers Impaired For Greater* |
| * UNIT 1 SPECIAL REPORT 92,..2-1 ANALYSIS OF OCCURRENCE:
| | Than Seven (7) Days in Support of Planned Work |
| Ccont'dl (7) days. Appropriate remedial actions were already in place, in accordance with the requirements of Technical Specification Action Statement 3.7.11.a, to establish an hourly roving fire watch patrol .for impaired fire barriers. | | *Event Dates: 3/24/92, 4/14/92,* 4/15/92 _and 4/25/92 .I R~~ort Date: *5/11/92 This report was initiated by Incident Report Nos. 92-190, 92-229, 92-233 and 92-257. It is a revision to Special Report 272/92-2 which. |
| The subject fire areas contain detection devices in addition to the roving fire watch patrol. Therefore, a fire in the areas should be detected before it could involve an adjacent area. This occurrence therefore involved no undue risk to the health or safety of the public. CORRECTIVE ACTION: .The repair of the pranned impaired penetrations was not accompiished , within seven (7) days due to the time required to complete work. The penetrations will be sealed upon completion*of associated work. The hourly fire watch, as addressed in the Description of Occurrence will continue until all fire protection concerns associated with these areas are resolved. | | includes additional Unit 1 penetration seals inoper?ble for greater than seven {7) .days in support of the tenth refueling outage. |
| MJP:pc SORC Mtg. 92-058 General Manager -Salem Operations}} | | CONDITIONS PRIOR TO OCCURRENCE: |
| | 3/17/92: Mode 1 Reactor Power 100% - Unit Load 1160 MWe 4/07/92: Mode 5 {Cold Shutdown); *10th Refueling Outage in progress 4/08/92: .Mode. 6 *{Refueling) 4/18/92: Mode 6 DESCRIPTION OF OCCURRENCE: |
| | .Per Technical Specification Action Statement 3.7.11.a, a Special Report is required when fire barrier penetration seals are impaired for greater than seven (7) days~ This report satisfies this |
| | . _requirement. |
| | ~he subject fire barrier impairments were initiated to support design changes and other Salem Unit 1 outage activities. Normally, the planning of penetration impairments includes repair within seven (7) . |
| | I days. However, to support the work identified in this report, the penetrations could not be repaired within seven (?)days. |
| | On March 17, 1992, two (2) fire barrier penetrations were impaired in support of Service Water System modifications . . on April 7, 1992, ten (10) fire barrier penetration seals were impaired a~so in support of Service Water System modifications. On April 8,:1992, thirty-four . |
| | *c 34) fire barrier penetration seals were impaired in support of Service Water system pipe replacement for the Auxiliary Building Room Coolers. On April. 18, 1992~ one (1) fire barrier penetration seal was impaired to support Room Cooler cleaning. These penetrations are located as follows: |
| | Date of No. of Purpose Location* |
| | Impairment Penetrations 3/17/92 1 SW System* 122 1 El. Aux. Bldg. |
| | Modifications Boric Acid Tank Room Floor Plate |
| | |
| | UNIT 1 SPECIAL REPORT 92-2-1 |
| | * DESCRIPTION OF OCCURRENCE: (cont'd) |
| | Date of No. of Purpose Location Impairment Penetrations 1 84' El. Aux. Bldg. |
| | cont. spray Pump, Tank Area Floor Piate |
| | * 4/7/92 10 SW project support 78' El. Mechanical Penetrations to containment. |
| | 4/8/92 1 SW pipe replacement #12 RHR Pump Room 4 Laundry, Shower, . & |
| | Chemical Pump & |
| | Tank Room 2 Nos. 11 & 12 Safet~ |
| | Injection Pump Room 1 Equipment Hatch - |
| | 122 1 El. |
| | 1 Equipment Hatch - |
| | '100 1 El. |
| | 1 Equipment Hatch - |
| | 84 1 El. |
| | 1 Equipment Hatch - |
| | 64 I El. |
| | 2 #11 Comp. Cooling . |
| | Heat Exch. & Pump Room 3 #11 & 12 Cont. |
| | Spray-Pumps & Spray Add. *Tank 4 ~4' Valve Alley 7 * * #12 Comp. Cooling Heat Exch. & Pump Room 1 #11 & 12 Safety Injection Pump Room 2 64 1 Aisle #1 1 Water Recirculation Heater Room |
| | |
| | . UNIT 1 SPECIAL REPORT 92-2-1 DESCRIPTION OF OCCURRENCE: (cont'd) |
| | Date of No. of Purpose Location Impairment* Penetrations |
| | : 1. 64 1 Lobby 1 84 1 Elevator Lobby 4/25/92 1 Room Cooler Work 100 1 Baling & |
| | Storage Area An hourly roving fire watch was previously established for the |
| | *above fire areas due to other fire.protection concerns. |
| | Therefore, the requirements of *Technical Specification 3.7.11 Action "a", were met~ |
| | Technical Specification 3.7.11.states: |
| | "All fire penetrati9ns (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting. |
| | safety related areas shall be functional." |
| | Action Statement 3.7.11.a states: |
| | "With one (1) or more of the above required fire barrier penetrations nori-functional; within one (1) hour either establish a continuous fire watch on at least one (1) side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one (1) side. of the non-functional fire barrier and es~ablish an hourly fire watch patrol. Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification* 6.9.1, prepare and submit a Special Report to the Commission pursuant to.Specification 6.9.2 within the next (30) days outlining the action taken, the cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration(s) to functional status." |
| | APPARENT CAUSE OF OCCURRENCE: |
| | The cause of the fire barrier penetration impairments is to support o~tage r~lated activities~ |
| | ANALYSIS OF OCCURRENCE: |
| | The functional integrity of fire barrier penetrations ensures that |
| | 'fires will. be confined or adequately retarded from spreading to adjacent portions of the facility.* This de~ign feature minimizes the possibility of a single fire involving several areas of the facility. |
| | The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections. This report satisfies reporting requirements of Technical Specification Action statement 3.7.11.a, pursuant to Technical Specification 6.9.2 since the time between impairment and eventual repair of the fire barrier penetrations is greater than seven |
| | |
| | 'A ** |
| | UNIT 1 SPECIAL REPORT 92,..2-1 * |
| | *J ' ANALYSIS OF OCCURRENCE: Ccont'dl (7) days. Appropriate remedial actions were already in place, in accordance with the requirements of Technical Specification Action Statement 3.7.11.a, to establish an hourly roving fire watch patrol |
| | .for impaired fire barriers. |
| | The subject fire areas contain detection devices in addition to the roving fire watch patrol. Therefore, a fire in the areas should be detected before it could involve an adjacent area. This occurrence therefore involved no undue risk to the health or safety of the public. |
| | CORRECTIVE ACTION: |
| | .The repair of the pranned impaired penetrations was not accompiished , |
| | within seven (7) days due to the time required to complete work. The penetrations will be sealed upon completion*of associated work. |
| | The hourly fire watch, as addressed in the Description of Occurrence section~ will continue until all fire protection concerns associated with these areas are resolved. |
| | IZ~ |
| | General Manager - |
| | Salem Operations MJP:pc SORC Mtg. 92-058}} |
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Revised Special Rept 90-10-1:on 900707,TS Action Statement 3.7.10.3c.a Entered When 64 Ft & 84 Ft Elevation Switchgear Room CO2 Fire Protection Sys Declared Inoperable.Caused by Equipment Failure.Sys Design Drawing Revised
ML18095A6141990-11-14014 November 1990
Special Rept 90-06:on 901022 & 24,fire Barriers Penetration Seals Impaired for More than Seven Days.Caused by Support Design Change Work.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved
ML18095A5801990-11-0707 November 1990
Supplemental Special Rept 88-3-27:on 880720-901010,listed Fire Barriers Impaired for More than 7 Days.Cause of Degraded Fire Barrier Penetrations Could Not Be Positively Determined
1998-08-31
[Table view]
Category:LER)
MONTHYEARML18106A9621998-11-16016 November 1998
Special Rept:On 981006,train B of Reactor Vessel Level Indicating Sys Was Indicating Malfunction.Caused by Loss of Fill in Capillary Sensing Line.Extensive Troubleshooting Was Performed on Sys
ML18106A8591998-08-31031 August 1998
Special Rept:On 980816,RMS Channel 1R15 Inoperable for Greater than Seven Days.Cause Is Under Investigation. Replacement of Detector Assembly W/Higher Temperature Rated Detector to Mitigate Effects to Be Completed by 981019
ML18106A1771997-11-21021 November 1997
Special Rept 97-15,on 971022,2A EDG Declared Inoperable. Caused by Moisture Build Up in Starting Air headers.2A EDG Equipment Inspected Just Subsequent to Aborted Start
ML18102B6001997-09-30030 September 1997
Special Rept 97-02:on 970909,isolation of Fire Protection Water to Plant Auxiliary Bldgs & Containments Occurred Due to Closure of Valves 1PF186 & 1PF187.Valves Opened on 970916 & Locally Verified Open by Loss Prevention Personnel
ML18102B4241997-06-30030 June 1997
Special Rept 97-01:on 970615,radiation Monitoring Sys Channel 1R15 Was Inoperable for More than Seven Days.Caused by Configuration of Plant.Required Operational Surveillances Will Be Completed on 2R15 & Channel Restored
ML18101B3051996-03-25025 March 1996
Special Rept:On 960224,valid Failure of 1B EDG Was Identified During Surveillance Testing.Caused by Fatigue Due to Normal Machine Vibration.Replaced Threaded Nipple
ML18101B1581995-12-29029 December 1995
Special Rept 95-02:on 951207,valid Failure of 1A EDG Identified Approx 23 & 1/2 H Into 24 H Endurance Surveillance Test.Caused by Lubricating Oil Leak at Threaded Piping Nipple.Threaded Nipple Replaced
ML18101B1541995-12-27027 December 1995
Special Rept 95-001:on 951129,valid Failure of 1B EDG Identified During Routine Monthly Surveillance Test.Caused by Malfunction of Woodward Electronic Governor Control Unit. Unit Replaced & 1B EDG Tested Satisfactorily on 951214
ML18101A8061995-07-0303 July 1995
Special Rept:On 950607,identified That 950601 Failure of EDG 1B Potential Common Mode Failure.Util Unable to Determine Cause at Present Time.Ler Will Be Submitted to NRC
ML18101A7341995-05-19019 May 1995
Special Rept:On 950506,RMS Declared Inoperable Due to Problems Encountered W/Operation of Victoreen Met Package. Caused by Met Package Inconsistencies.Appropriate Computer Software Corrections Being Researched & Will Be Implemented
ML18101A5601995-02-15015 February 1995
Special Rept 95-01:on 950125,shortly After RCP Turned Off to Remove RCP from Svc,Momentary RCS Pressure Transient Occurred & Pressure Peaked 365.5 Psig Due to Pressure Equalization Through 21 RCS Loop.Procedures Will Be Changed
ML18100B0421994-04-27027 April 1994
Special Rept 94-2:on 940329,valid Failure of 1A Diesel Generator Occurred.Caused by Buildup on Contacts of Breaker Position Switch 52HL,resulting in Excessive Electrical Resistance.Breaker Position Switch Replaced
ML18100A8271994-01-20020 January 1994
Special Rept 94-01:on 940106,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable & Exceeded 7-day Time Frame for Restoring Inoperable Channels to Operable Status on 940113.Monitors Returned to Svc on 940118
ML18100A6211993-09-17017 September 1993
Special Rept 93-4:on 930910,radiation Monitoring Channels 2R45B & 2R45C Inoperable Greater than Seven Days.Caused by Design Deficiency.Corrected by Separating Monitors Reference & Chassis Grounds
ML18100A4941993-07-21021 July 1993
Special Rept:On 930707,process Monitor - Noble Gas effluent- Condenser Exhaust Sys Was Removed from Svc Due to Observed Water in Its Sample Line.Sample Line 2R15 Drained & Dried. W/930721 Ltr
ML18096B3511993-03-23023 March 1993
Special Rept 93-2:on 930310,RMS Channels 2R45B & 2R45C Removed from Svc to Functionally Test Low Flow Differential Pressure.Test Results Showed That Switch Inoperable.Caused by Design Deficiency.Design Mod Being Prepared
ML18096B2571993-02-0404 February 1993
Special Rept 93-1:on 930104,fire Barrier Penetration Seal Impaired to Support Welding of RHR Sys Drain Piping.Barrier Inoperable for More than 7 Days.Cables Removed & Access Hatch Closed to Restore Penetration to Operability
ML18096B2331993-01-28028 January 1993
Special Rept 93-1:on 930114,RMS Channels 1R45B & 1R45C Declared Inoperable Upon Annuciation of External Fail Alarm.Cause Not Determined.Upon Completion,Corrective Actions Will Be Taken & Channels Will Return to Svc
ML18096B1701992-12-21021 December 1992
Special Rept 92-9:on 921208,chilled Water Supply Could Not Be Restored Following Completion of Rms Channel Functional Surveillance.Caused by Blow Indication Panel Circuit Fuse. New Solenoid Valve Operator Ordered
ML18096B1601992-12-18018 December 1992
Special Rept 92-9:on 921112,fire Barrier Impairment Initiated to Support Svc Water Sys Design Changes & Penetration Inoperable for More than 7 Days Through 921119. Penetrations Will Be Sealed Upon Completion of Work
ML18096B1171992-11-23023 November 1992
Special Rept 92-8:on 921116,RMS Channels Declared Inoperable & Removed from Svc for More than 7 Days.Caused by Bad Ground Wire Connection on Three Wire Power Cable.Connector Repaired & post-maint Testing Successfully Completed
ML18096B0861992-11-0505 November 1992
Special Rept 92-7:on 921008,discovered Door Misaligned & Would Not Close & Latch.Caused by Equipment Failure.Fire Door Declared Functional Upon Completion of Repairs & Testing
ML18096B0731992-10-30030 October 1992
Special Rept 92-8:on 920924,fire Barrier Penetrations Impaired to Support Design Change Work.On 921001, Penetrations Exceeded seven-day Limit,Per TS 3.7.11.a. Impaired Penetrations Resealed & Inspected
ML18096B0591992-10-23023 October 1992
Special Rept 92-6:on 920924,valid Failure,Involving DG 2B, Occurred During Monthly Surveillance Testing & Exhaust Smoke Observed Rising from Around Turbocharger.Caused by Loose Pipe Fasteners.Fasteners Torqued Appropriately
ML18096B0021992-09-24024 September 1992
Special Rept 92-7:on 920826,auxiliary Bldg 100-ft Elevation Corridor Fire Door Found Impaired & Not Returned to Operability within 7 Days.Caused by Broken Internal Hinge Plate Welds.Damaged Door Will Be Replaced
ML18096A9151992-08-21021 August 1992
Special Rept 92-6:on 920814,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable for More than 7 Days. Caused by Degradation on Impellers of Two Sample Pumps. Preventive Maint Applicability Review Will Be Performed
ML18096A8841992-08-0707 August 1992
Special Rept 92-4-1:on 920430,fire Pump 1 Started Knocking 10 Minutes Into half-hour Run.Caused by sheared-off Follower Guide Pin.On 920514,fire Pump Developed Severe Oil Leak.Caused by Piston Failing to Contact Cylinder Head
ML18096A8261992-07-0909 July 1992
Special Rept 92-5:on 920623,actuation Capability of 78-ft Lower Electrical Penetration CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Maint Work.Sys Returned to Svc on 920702
ML18096A7431992-05-22022 May 1992
Special Rept 92-4:on 920430 & 0514,fire Pumps 1 & 2, Respectively,Inoperable for More than 7 Days.Caused by Sheared Cam Follower Pin & Severe Oil Leak.Fire Protection Sys cross-tie Valve Opened to Provide Backup Protection
ML18096A7281992-05-22022 May 1992
Special Rept 92-3,on 920422,discovered That CO2 Sys Was Inoperable.Caused by Maint Work Activities.Upon Completion of Maint Diesel Generator Area CO2 Sys Will Be Returned to Svc
ML18096A7351992-05-15015 May 1992
Ro:On 920423,fire Pump 1 Declared Inoperable & Remains Inoperable Due to Broken Crankshaft.Both Fire Suppression Sys Inoperable.On 920515,fire Pump 2 Declared Inoperable Due to Severe Oil Leak.Written Rept to Be Provided in 14 Days
ML18096A7021992-05-11011 May 1992
Special Rept 92-2-1:on 920324,0414,15 & 25,fire Barriers Impaired for More than 7 Days to Support Planned Work in SW Sys,Sw Project Support & SW Pipe Replacement.Hourly Fire Watch Will Continue Until All Concerns Resolved
ML18096A6501992-04-23023 April 1992
Special Rept 92-2:on 920324,0414 & 15,fire Barriers Impaired for Greater than Seven Days in Support of Planned Work. Hourly Fire Watch Will Continue Until Fire Protection Concerns Associated W/Areas Resolved
ML18096A6491992-04-23023 April 1992
Special Rept 92-4:on 920318,two Fire Barrier Penetrations Were Impaired to Support Turbine/Generator Design Change Work for Greater than Seven Days.Caused by Outage Related Activities.Penetrations Were Resealed on 920326
ML18096A6051992-03-26026 March 1992
Special Rept 92-3:on 920302,jacket Water Leakage Developed After Loading DG 2A.On 920305,DG 2A Tripped on Low Lube Oil Pressure.Both Events Caused by Equipment Failure.Tube Connector Compression Fitting Replaced & Diesel Retested
ML18096A5891992-03-23023 March 1992
Special Rept 92-2:on 920302 & 21,fire Barriers Impaired for More than 7 Days to Support Design Changes & outage-related Activities.Hourly Fire Watch Established & Fire Penetrations Will Be Sealed
ML18096A5671992-03-12012 March 1992
Special Rept 92-1:on 920223,fire Barriers Found Impaired for Greater than Seven Days.Caused by Equipment Failure.Fire Door Will Be Replaced Upon Receipt of New Door
ML18096A5101992-02-0606 February 1992
Special Rept 92-1 on 920104,06 & 25,fire Barriers Impaired for Greater than Seven Days in Support of Outage Related Activities Due to Time Required to Complete Work.Hourly Fire Watch Will Continue Until Concerns Re Areas Are Resolved
ML18096A4231992-01-0909 January 1992
Special Rept 91-3,on 911210,26 & 27:fire Barriers Found Impaired for Greater than 7 Days.Cause of Occurrence Due to Support Outage Related Activities.Penetrations Will Be Sealed
ML18096A4001991-12-23023 December 1991
Special Rept 91-4 Re Valid Failure of Diesel Generator 2B on 911122.Cause Unknown.Surveillance Procedure SP(O)4.8.1.1.2 Performed Satisfactorily
ML18096A2301991-08-22022 August 1991
Special Rept 91-02:on 910725,reactor Trip Breaker Failure Occurred Duing Surveillance Testing of Reactor Trip Bypass Breaker.Detailed Investigation Rept Being Prepared & Breaker Being Replaced
ML18096A0841991-06-20020 June 1991
Special Rept:On 910523 & 910525,valid Failure Re 2B Diesel Generator Occurred When pre-lube Pump Heater Circuit de-energized & non-valid Failure Occurred on 910525 Re Jacket Water Leak
ML18095A8901991-04-17017 April 1991
Special Rept 91-1-1:on 910218,910220,910224 & 910322 Fire Barrier Penetration Seals Impaired for Greater than Seven Days.Cause of Impairment Was to Support Outage Activities. Hourly Fire Watch Will continue.W/910417 Ltr
ML18095A8111991-03-20020 March 1991
Special Rept:On 910211,910213 & 910217 Fire Barrier Impairments Greater than Seven Days in Support of Planned Work.Cause of Impairment of Fire Barrier Penetrations Was to Support Outage Related Activities
ML18095A7831991-03-0707 March 1991
Special Rept 91-1:on 910211,Elevation 64 & 84 Ft Switchgear Rooms & Elevation 78 Ft Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Design Work.Continuous Fire Watch Established
ML18095A7521991-02-20020 February 1991
Special Rept 88-3-28:from 880720-910122,listed Fire Barrier Penetration Seal Impairments Occurred.Cause Not Positively Determined.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved
ML18095A6751990-12-26026 December 1990
Special Rept 90-7:on 901210,switchgear Rooms & Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days to Support Design Change Work on 901126. Adequate Precautions Taken to Ensure Design Capability
ML18095A7511990-12-0505 December 1990
Revised Special Rept 90-10-1:on 900707,TS Action Statement 3.7.10.3c.a Entered When 64 Ft & 84 Ft Elevation Switchgear Room CO2 Fire Protection Sys Declared Inoperable.Caused by Equipment Failure.Sys Design Drawing Revised
ML18095A6141990-11-14014 November 1990
Special Rept 90-06:on 901022 & 24,fire Barriers Penetration Seals Impaired for More than Seven Days.Caused by Support Design Change Work.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved
ML18095A5801990-11-0707 November 1990
Supplemental Special Rept 88-3-27:on 880720-901010,listed Fire Barriers Impaired for More than 7 Days.Cause of Degraded Fire Barrier Penetrations Could Not Be Positively Determined
1998-08-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18107A5581999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr
ML18107A5571999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr
ML18107A5301999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr
ML18107A5311999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913
ML18107A5031999-08-26026 August 1999
LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr
ML18107A5201999-08-12012 August 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF).
ML18107A4811999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr
ML18107A4821999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr
ML18107A4691999-07-28028 July 1999
LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr
ML18107A4441999-07-0606 July 1999
LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr
ML18107A4211999-07-0202 July 1999
LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr
ML18107A4331999-07-0101 July 1999
LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr
ML18107A4321999-07-0101 July 1999
LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr
ML18107A5211999-07-0101 July 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF).
ML18107A4351999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr
ML18107A4341999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18107A3951999-06-17017 June 1999
LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr
ML18107A3661999-06-0909 June 1999
LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr
ML18107A3551999-06-0202 June 1999
LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr
ML18107A3441999-06-0101 June 1999
Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716
ML18107A3541999-06-0101 June 1999
LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr
ML18107A3681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr
ML18107A3721999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr
ML18107A2931999-05-12012 May 1999
LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr
ML18107A2781999-05-10010 May 1999
LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr
ML18107A2791999-05-0404 May 1999
LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr
ML18107A2741999-05-0303 May 1999
LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr
ML18107A3711999-04-30030 April 1999
Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
ML18107A2991999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr
ML18107A2971999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr
ML18107A2351999-04-23023 April 1999
LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr
ML18107A2881999-04-0707 April 1999
Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11.
ML18107A1821999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr
ML18107A1831999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr
ML18106B1471999-03-29029 March 1999
LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr
ML18106B1021999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr
ML18106B1011999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr
ML18106B0931999-02-25025 February 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified
ML18106B0701999-02-16016 February 1999
LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr
ML18106B0551999-02-0101 February 1999
Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl
ML18106B0561999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr
ML18106B0571999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr
ML20205P1671999-01-31031 January 1999
a POST-PLUME Phase, Federal Participation Exercise
ML18106B0441999-01-29029 January 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables
ML18106B0491999-01-28028 January 1999
LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr
ML18106B0401999-01-18018 January 1999
LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr
ML18106B0251998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr
1999-09-30
[Table view] |
Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 11, 1992
- u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION
.LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO .. 1 SPECIAL REPORT 92-2-1 This supplemental report addresses additional fire barrier impairments which had not been restored to functional status within seven (7) days. This report has been prepared in accordance with the reporting requirements of Technical Specification Action Statement 3. -7. 11. a pursuant to Technical Specification 6. 9. 2. It is being submitted within thirty (30) days as required.
Sincerely yours,
- c. A. Vondra General Manager -
Salem Operations MJP:pc Distribution
.:. ~- . '
/{; 2i I \\/
9205190067 920511 ' ,/ 95*2189 (10/J,) 12*89 v
PDR ADOCK 05000272 S PDR
'. UNIT 1 SPECIAL REPORT 92-2-1 PLANT IDENTIFICATION:
Salem Generating Station - Unit 1 Pubiic Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Technical Specification 3.7.11; Fire Barriers Impaired For Greater*
Than Seven (7) Days in Support of Planned Work
- Event Dates: 3/24/92, 4/14/92,* 4/15/92 _and 4/25/92 .I R~~ort Date: *5/11/92 This report was initiated by Incident Report Nos.92-190, 92-229,92-233 and 92-257. It is a revision to Special Report 272/92-2 which.
includes additional Unit 1 penetration seals inoper?ble for greater than seven {7) .days in support of the tenth refueling outage.
CONDITIONS PRIOR TO OCCURRENCE:
3/17/92: Mode 1 Reactor Power 100% - Unit Load 1160 MWe 4/07/92: Mode 5 {Cold Shutdown); *10th Refueling Outage in progress 4/08/92: .Mode. 6 *{Refueling) 4/18/92: Mode 6 DESCRIPTION OF OCCURRENCE:
.Per Technical Specification Action Statement 3.7.11.a, a Special Report is required when fire barrier penetration seals are impaired for greater than seven (7) days~ This report satisfies this
. _requirement.
~he subject fire barrier impairments were initiated to support design changes and other Salem Unit 1 outage activities. Normally, the planning of penetration impairments includes repair within seven (7) .
I days. However, to support the work identified in this report, the penetrations could not be repaired within seven (?)days.
On March 17, 1992, two (2) fire barrier penetrations were impaired in support of Service Water System modifications . . on April 7, 1992, ten (10) fire barrier penetration seals were impaired a~so in support of Service Water System modifications. On April 8,:1992, thirty-four .
Date of No. of Purpose Location*
Impairment Penetrations 3/17/92 1 SW System* 122 1 El. Aux. Bldg.
Modifications Boric Acid Tank Room Floor Plate
UNIT 1 SPECIAL REPORT 92-2-1
- DESCRIPTION OF OCCURRENCE: (cont'd)
Date of No. of Purpose Location Impairment Penetrations 1 84' El. Aux. Bldg.
cont. spray Pump, Tank Area Floor Piate
- 4/7/92 10 SW project support 78' El. Mechanical Penetrations to containment.
4/8/92 1 SW pipe replacement #12 RHR Pump Room 4 Laundry, Shower, . &
Chemical Pump &
Tank Room 2 Nos. 11 & 12 Safet~
Injection Pump Room 1 Equipment Hatch -
122 1 El.
1 Equipment Hatch -
'100 1 El.
1 Equipment Hatch -
84 1 El.
1 Equipment Hatch -
64 I El.
2 #11 Comp. Cooling .
Heat Exch. & Pump Room 3 #11 & 12 Cont.
Spray-Pumps & Spray Add. *Tank 4 ~4' Valve Alley 7 * * #12 Comp. Cooling Heat Exch. & Pump Room 1 #11 & 12 Safety Injection Pump Room 2 64 1 Aisle #1 1 Water Recirculation Heater Room
. UNIT 1 SPECIAL REPORT 92-2-1 DESCRIPTION OF OCCURRENCE: (cont'd)
Date of No. of Purpose Location Impairment* Penetrations
- 1. 64 1 Lobby 1 84 1 Elevator Lobby 4/25/92 1 Room Cooler Work 100 1 Baling &
Storage Area An hourly roving fire watch was previously established for the
- above fire areas due to other fire.protection concerns.
Therefore, the requirements of *Technical Specification 3.7.11 Action "a", were met~
Technical Specification 3.7.11.states:
"All fire penetrati9ns (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting.
safety related areas shall be functional."
Action Statement 3.7.11.a states:
"With one (1) or more of the above required fire barrier penetrations nori-functional; within one (1) hour either establish a continuous fire watch on at least one (1) side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one (1) side. of the non-functional fire barrier and es~ablish an hourly fire watch patrol. Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification* 6.9.1, prepare and submit a Special Report to the Commission pursuant to.Specification 6.9.2 within the next (30) days outlining the action taken, the cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration(s) to functional status."
APPARENT CAUSE OF OCCURRENCE:
The cause of the fire barrier penetration impairments is to support o~tage r~lated activities~
ANALYSIS OF OCCURRENCE:
The functional integrity of fire barrier penetrations ensures that
'fires will. be confined or adequately retarded from spreading to adjacent portions of the facility.* This de~ign feature minimizes the possibility of a single fire involving several areas of the facility.
The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections. This report satisfies reporting requirements of Technical Specification Action statement 3.7.11.a, pursuant to Technical Specification 6.9.2 since the time between impairment and eventual repair of the fire barrier penetrations is greater than seven
'A **
UNIT 1 SPECIAL REPORT 92,..2-1 *
- J ' ANALYSIS OF OCCURRENCE: Ccont'dl (7) days. Appropriate remedial actions were already in place, in accordance with the requirements of Technical Specification Action Statement 3.7.11.a, to establish an hourly roving fire watch patrol
.for impaired fire barriers.
The subject fire areas contain detection devices in addition to the roving fire watch patrol. Therefore, a fire in the areas should be detected before it could involve an adjacent area. This occurrence therefore involved no undue risk to the health or safety of the public.
CORRECTIVE ACTION:
.The repair of the pranned impaired penetrations was not accompiished ,
within seven (7) days due to the time required to complete work. The penetrations will be sealed upon completion*of associated work.
The hourly fire watch, as addressed in the Description of Occurrence section~ will continue until all fire protection concerns associated with these areas are resolved.
IZ~
General Manager -
Salem Operations MJP:pc SORC Mtg.92-058
