Similar Documents at Salem |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18096A7351992-05-15015 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 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 ML18095A3601990-07-17017 July 1990 Special Rept 90-3:on 900611,fire Barrier Penetration Seal Impaired for More than 7 Days.Caused by Failure of Maint Supervision to Maintain Accountability of Fire Barrier Penetrations in Question.Event Reviewed by Maint Dept Mgt ML18095A2091990-05-16016 May 1990 Special Rept 90-2-1:on 900320,0410,12 & 16,fire Barrier Penetration Seals Impaired for More than 7 Days in Support of Design Change Work.Hourly Roving Fire Watch Patrol Established & Will Continue Until All Work Completed ML18094B3871990-04-0404 April 1990 Supplemental Special Rept 88-3-20:from 880720-900314 Addl Fire Penetration Seal Impairments Not Restored to Functional Status within 7 Days.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18094B3371990-02-0707 February 1990 Supplemental Special Rept 88-3-19:from 880720-900228,addl Fire Barrier Cable Penetrations & Penetration Seals Impaired for More than 7 Days.Hourly Fire Watch Patrol Will Continue Until Fire Protection Concerns Resolved ML18094A6541989-08-28028 August 1989 Special Rept:On 890805,06 & 08,sea Turtles Impinged on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration of Turtles & Boating & Commercial Fishing Operations.Bars Cleaned Once Per Day ML18094A5551989-07-0505 July 1989 Special Rept 89-4:on 890622,automatic Actuation Feature for Fire Pumps Deactivated & Sensing Line for Pressure Transmitter Isolated.Caused by Inadequate Administrative Control.Second Pressure Sensing Tap to Be Installed ML18094A5481989-06-22022 June 1989 Ro:On 890622,automatic Actuation Feature for Fire Pumps Found Deactivated.Caused by Sensing Line Between Fire Pump Cross 1FP10 & 2FP10 Being Isolated & Precluding Automatic Initiation.Jockey Pump & Isolation Valves Replaced ML18093B1991988-10-0404 October 1988 Supplemental Special Rept 88-3-2:on 880713,25,28 & Between 0802-30 & 31-0930,impairment of Fire Barriers Discovered. Cause Could Not Be Positively Determined.Fire Watches Will Continue Until All Fire Protection Concerns Resolved ML18093B0621988-09-0606 September 1988 Special Rept 88-5:on 880817,several Fire Barrier Penetrations in Support of Design Mods During Current Refueling Outage Impaired for Greater than 7 Days.Hourly Fire Watches Will Continue Until Concerns Resolved ML18093A9691988-07-21021 July 1988 Ro:On 880715,two Loggerhead Sea Turtles Stranded on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration Patterns.Trash Bar Observation Increased to at Least Once Per 2 H ML18093A8151988-04-21021 April 1988 Ro:On 880409,steam Generator Tube Plugged Due to Primary to Secondary Side Leakage & Leaking Explosive Plug Discovered on Hot Leg Side.Leaking Plug Drilled Out & Verified Intact ML18093A7471988-03-16016 March 1988 Special Rept 88-2:on 880217,reactor Trip Breaker Exceeded Time Requirement for Opening During Surveillance Testing. Caused by Equipment Problem.Undervoltage Trip Attachment Replaced & Breaker Maintained Per Breaker Maint Procedure ML18093A2571987-07-23023 July 1987 Special Rept 87-5:on 870713,automatic Actuation Feature for Fire Pumps Deactivated.Caused by Planned Equipment Upgrade. Fire Pumps Returned to Svc within 8 H ML19275A3131979-08-31031 August 1979 RO 79-56/01P:on 790830,noted Existence of Identical Configuration Re Excessive RHR Pump Flow During post-LOCA Recirculation Mode.Detailed Rept Will Be Submitted Per Tech Specs 1992-05-15
[Table view] Category:LER)
MONTHYEARML18096A7351992-05-15015 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 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 ML18095A3601990-07-17017 July 1990 Special Rept 90-3:on 900611,fire Barrier Penetration Seal Impaired for More than 7 Days.Caused by Failure of Maint Supervision to Maintain Accountability of Fire Barrier Penetrations in Question.Event Reviewed by Maint Dept Mgt ML18095A2091990-05-16016 May 1990 Special Rept 90-2-1:on 900320,0410,12 & 16,fire Barrier Penetration Seals Impaired for More than 7 Days in Support of Design Change Work.Hourly Roving Fire Watch Patrol Established & Will Continue Until All Work Completed ML18094B3871990-04-0404 April 1990 Supplemental Special Rept 88-3-20:from 880720-900314 Addl Fire Penetration Seal Impairments Not Restored to Functional Status within 7 Days.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18094B3371990-02-0707 February 1990 Supplemental Special Rept 88-3-19:from 880720-900228,addl Fire Barrier Cable Penetrations & Penetration Seals Impaired for More than 7 Days.Hourly Fire Watch Patrol Will Continue Until Fire Protection Concerns Resolved ML18094A6541989-08-28028 August 1989 Special Rept:On 890805,06 & 08,sea Turtles Impinged on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration of Turtles & Boating & Commercial Fishing Operations.Bars Cleaned Once Per Day ML18094A5551989-07-0505 July 1989 Special Rept 89-4:on 890622,automatic Actuation Feature for Fire Pumps Deactivated & Sensing Line for Pressure Transmitter Isolated.Caused by Inadequate Administrative Control.Second Pressure Sensing Tap to Be Installed ML18094A5481989-06-22022 June 1989 Ro:On 890622,automatic Actuation Feature for Fire Pumps Found Deactivated.Caused by Sensing Line Between Fire Pump Cross 1FP10 & 2FP10 Being Isolated & Precluding Automatic Initiation.Jockey Pump & Isolation Valves Replaced ML18093B1991988-10-0404 October 1988 Supplemental Special Rept 88-3-2:on 880713,25,28 & Between 0802-30 & 31-0930,impairment of Fire Barriers Discovered. Cause Could Not Be Positively Determined.Fire Watches Will Continue Until All Fire Protection Concerns Resolved ML18093B0621988-09-0606 September 1988 Special Rept 88-5:on 880817,several Fire Barrier Penetrations in Support of Design Mods During Current Refueling Outage Impaired for Greater than 7 Days.Hourly Fire Watches Will Continue Until Concerns Resolved ML18093A9691988-07-21021 July 1988 Ro:On 880715,two Loggerhead Sea Turtles Stranded on Circulating Water Sys Intake Trash Bars.Caused by Summer Migration Patterns.Trash Bar Observation Increased to at Least Once Per 2 H ML18093A8151988-04-21021 April 1988 Ro:On 880409,steam Generator Tube Plugged Due to Primary to Secondary Side Leakage & Leaking Explosive Plug Discovered on Hot Leg Side.Leaking Plug Drilled Out & Verified Intact ML18093A7471988-03-16016 March 1988 Special Rept 88-2:on 880217,reactor Trip Breaker Exceeded Time Requirement for Opening During Surveillance Testing. Caused by Equipment Problem.Undervoltage Trip Attachment Replaced & Breaker Maintained Per Breaker Maint Procedure ML18093A2571987-07-23023 July 1987 Special Rept 87-5:on 870713,automatic Actuation Feature for Fire Pumps Deactivated.Caused by Planned Equipment Upgrade. Fire Pumps Returned to Svc within 8 H ML19275A3131979-08-31031 August 1979 RO 79-56/01P:on 790830,noted Existence of Identical Configuration Re Excessive RHR Pump Flow During post-LOCA Recirculation Mode.Detailed Rept Will Be Submitted Per Tech Specs 1992-05-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With LR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 05000272/LER-1999-006-02, :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.With1999-08-26026 August 1999
- 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
ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 9) Second Interval,Second Period, First Outage (96RF) LR-N99-0379, Monthly Operating Rept for July 1999 for Salem,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With LR-N99-0380, Monthly Operating Rept for July 1999 for Salem,Unit 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr 05000311/LER-1999-008, :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.With1999-07-28028 July 1999
- 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
ML20210B7371999-07-21021 July 1999 Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively ML18107A4411999-07-0909 July 1999 SER Denying Licensee 980730 & 990222 Requests to Revise TS 3/4.7.6, Control Room Emergency Air Conditioning Sys, & Associated Bases to Change Acceptable Criteria for Control Room Emergency Air Conditioning System 05000311/LER-1999-007, :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.With1999-07-0606 July 1999
- 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
05000272/LER-1999-005-02, :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.With1999-07-0202 July 1999
- 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
05000311/LER-1999-006, :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.With1999-07-0101 July 1999
- 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
05000311/LER-1999-002, :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.With1999-07-0101 July 1999
- 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
ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr LR-N99-0325, Monthly Operating Rept for June 1999 for Salem,Unit 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With LR-N99-0324, Monthly Operating Rept for June 1999 for Salem,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With ML18107A4161999-06-23023 June 1999 Safety Evaluation Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000272/LER-1999-004-02, :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.With1999-06-17017 June 1999
- 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
ML18107A3751999-06-15015 June 1999 Safety Evaluation Accepting Licensee Request for Approval of Proposed Changes to Nuclear Business Unit EP for Hope Creek & Salem Generating Stations,Iaw 10CFR50.54(q) 05000272/LER-1999-003-02, :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).With1999-06-0909 June 1999
- 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
05000311/LER-1999-005-01, :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.With1999-06-0202 June 1999
- 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
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 LR-N99-0278, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With LR-N99-0275, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With ML18107A3111999-05-21021 May 1999 SER Accepting GL-88-20,suppl 4, IPEEEs for Severe Accident Vulnerabilities, for Plant,Units 1 & 2 05000272/LER-1999-002-02, :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.With1999-05-12012 May 1999
- 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
05000311/LER-1999-004-01, :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.With1999-05-10010 May 1999
- 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
ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 05000311/LER-1999-003-01, :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.With1999-05-0404 May 1999
- 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
05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- 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
LR-N99-0225, Monthly Operating Rept for Apr 1999 for Salem Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 LR-N99-0226, Monthly Operating Rept for Apr 1999 for Salem Unit 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML20206B4761999-04-26026 April 1999 Safety Evaluation Supporting Amends 220 & 202 to Licenses DPR-70 & DPR-75,respectively 05000311/LER-1999-001-03, :on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With1999-04-23023 April 1999
- 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
ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11 LR-N99-0176, Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With LR-N99-0177, Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 05000272/LER-1999-001-02, :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. with1999-03-29029 March 1999
- 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
1999-09-30
[Table view] |
Text
PS~G *
- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station
. March 23, 1992 U. S. Nuclear Regulatory Commission*
Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT Nb. 2 SPECIAL REPORT 92-2 This report addresses.Salem Unit 1 and.Salem Unit 2 fire barrier penetration seal impairments which have not been restored to functional status within seven {7) days. Th~se penetrations have been impaired in support of planned work. 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.
Since.rely yours, C. A. Vondra General Manager -
Salem Operations MJP:pc Distribution
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9203300268 920323 95-2189 (10M) 12-89 PDR ADOCK 05000311
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UNIT 2 SPECIAL REPORT * .
PLANT
IDENTIFICATION:
Salem Generating Station - Units 1 and 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038
. IDENTIFICATJON OF O~~lJRRE~CE_:_
Technical Specification 3.1.11; Fire Barriers Impaired For Greater Than Seven (7) Days in Support of Planned Work Event Dates: 3/02/92 and 3/21/92 Report Date: 3/23/92 This report was initiated by Incident Report Nos.92-128, 92~182, and 92-183.
Unit 1 - 3/14/92: Mode 1 Reactor Power 100% - Unit *Load 1160 MWe Unit 2 - 2/24/92: Mode 6 (Refueling); 6th Refueling Outage in progress Unit 2 - 3/14/92: Mode 5 (Cold Shutdown)
DESCRIPTION
-- ---------*--- -**- - ---**OF OCCURRENCE:
Per Technical Specification Action Statement 3.7.11.a {for both Salem Unit 1 and Salem Unit 2), a Special Report is required when fire barrier penetration seals are impaired for greater .than seven* {7) days. This report satisfies this requirem~nt.
The subject fire barrier impairments were initiated in support of design changes and other Salem Unit 2 outage activities. Normally, the planning of penetration impairments includes .their repair within seven (7) days. However, to fully support the work identified in this report, the penetrations could not be repaired within seven (7) days~
On February 24, 1992, two (2) fire barrier penetrations were impaired in support of Type A Containment Leak Rate Testing. On March 14, 1992, two (2) fire barrier penetrations were impaired to allow the routing of power c~bles in support_of Service Water design modifications. These penetrations are located as follows:
Date of*
No-.
- - - - of -- Location Penetrations 2/24/92 1 Type A Test #2 Relay Roon' Support 1 78' EJec. Pen. Area 3/14/92 1 SW project support Unit 2 100' El.
Floor Plate in the Boric Acid Transfer
- Pump Co!~-ridor
- - -of - Location J_1!!12_~ i rm ~I:!.t 3/14/92 1 SW project support Unit 1 100' El.
Floor Plate Boric Acid Transfer Pump Corridor An hourly roving fire watch had been previously established for the above fire areas due to other fire protection concerns. Therefore, the requirements of Technical Specification 3.7.11 Action "a", wer~
met.
Salem Unit 2 Technical Specification 3~7.11 states:
"All fire penetr~tions (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting safety related areas shall be OPERABLE."
Salem Unit 2 Action Statement 3.7.11.a states:
"With one (1) or more of the above required fire barrier penetrations inoperable, within one (1) hour either establish a co~tinuous fire watch on at least one (1) side of the affected penetration, or verify the OPERABIJLITY of fire detectors on at least one. (1} side of th~ inoperable fire barrie~ and establish an hourly fire watch patrol. Restore the inoperable fire barrier penetration(s) to OPERABLE 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 inoperable penetration and plans and schedule for restoring the fire barrier penetration(s) to OPERABLE status."
The Salem Unit 1 Technical Specifications_ are identical to the above Unit 2 Technical Specifications; however, the term functional" is used instead of the term "OPERABLE".
APPARENT CAUSE OF OCCURRENCE:
The cause of the fire barrier penetration impairments is to support outage related activities.
A_IJAJ,.iYS J;_S___Qlf _O_CCURRENC_E:
The functional integrity of fire barrier penetrations ensures that fires will be confined or ~dequately retarded from spreading to adjacent portions of the facility. This design 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 discovery antj eventual repair of the fire barrier impairments is greater than seven
UNIT 2 SPECIAL REPORT . * ****
ANALYSI~ OF OCCURRE~Cli_;__ ( co_~-t;~d)_
- (7) days. Appropriate remedial actions were already in place in accordanc~ with the requirem~nts of Technical Specification Action Statement 3.7.11.a to establish an hourly ~oving fire watch patrol for the impa~red fire barriers once the impairments were identified.
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 ho undue risk to the h~alth.or safety of the public ..
CORRECTIVE ACTION:
The repair of the planned impaired penetrations was not accomplished within seven (7) days d~e to the time required to 6omplete work. The penetrations will be sealed upon completion of associated work.
The hourly'fire wat6h, as addre~sed in the Description of Occurrence section, will continue until all fire protection concerns associated with these areas are resolved.
General Manager -
Salem Operations MJP:pc SORC Mtg.92-033