Similar Documents at Salem |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18093A8151988-04-21021 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 1988-04-21
[Table view] Category:LER)
MONTHYEARML18093A8151988-04-21021 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 1988-04-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARLR-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 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively 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 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 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-N99-0380, 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 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 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) 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 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 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 ML18107A3931999-06-23023 June 1999 Safety Evaluation Supporting Licensee Response to GL 95-07 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
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
ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 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
ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 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 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 ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18106B1461999-04-0101 April 1999 SER Accepting Util Proposed Request to Use 1992 Edition of ASME Boiler & Pressure Vessel Code,Section Xi,Article, IWA-4500,for Potential Repair of Feedwater Nozzles for Salem Nuclear Generating Station,Unit 2 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
05000272/LER-1999-001-01, :on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with
1999-09-30
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Text
- 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
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT Nb. 2 SPECIAL REPORT 92-2 . March 23, 1992 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.
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. MJP:pc Distribution
- Li . J-* '. [ *" ( ' * ,' I 9203300268 920323 PDR ADOCK 05000311 Since.rely yours, C. A. Vondra General Manager -Salem Operations 95-2189 (10M) 12-89 UNIT 2 SPECIAL REPORT *.
.--------*-*-----------------, Salem Generating Station -Units 1 and 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 . IDENTIFICATJON OF 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, and 92-183. Unit 1 -3/14/92: Unit 2 -2/24/92: Mode 1 Reactor Power 100% -Unit *Load 1160 MWe 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 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)
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 in support_of Service Water design modifications.
These penetrations are located as follows: Date of* No-. of *-------------------Penetrations
*--*--
*---. -2/24/92 1 1 3/14/92 1 Type A Test Support Location ------------#2 Relay Roon' 78' EJec. Pen. Area SW project support Unit 2 100' El. Floor Plate in the Boric Acid Transfer -Pump
- UNIT 2 SPECIAL REPORT Date of J_1!!12_ i rm 3/14/92 No. of ----1
- Location 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",
met. Salem Unit 2 Technical Specification states: "All fire (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
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 inoperable fire 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 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 .* ****
OF (
(7) days. Appropriate remedial actions were already in place in with the of Technical Specification Action Statement 3.7.11.a to establish an hourly fire watch patrol for the 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 safety of the public .. CORRECTIVE ACTION: The repair of the planned impaired penetrations was not accomplished within seven (7) days to the time required to 6omplete work. The penetrations will be sealed upon completion of associated work. The hourly'fire wat6h, as in the Description of Occurrence section, will continue until all fire protection concerns associated with these areas are resolved.
MJP:pc SORC Mtg.92-033 General Manager -Salem Operations