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| | issue date = 08/24/1998 | | | issue date = 08/24/1998 |
| | title = LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr | | | title = LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr |
| | author name = BAKKEN A C, NAGLE J C | | | author name = Bakken A, Nagle J |
| | 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:* | | {{#Wiki_filter:OPS~G * |
| * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Gentlemen: | | * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG 24 1998 LR-N980418 Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Gentlemen: |
| SPECIAL REPORT 311/98-009-00 | | SPECIAL REPORT 311/98-009-00 |
| * AUG 24 1998 LR-N980418 SALEM GENERATING STATION -UNIT 2 FACILITY OPERATING LICENSE NO DPR 75 DOCKET NO. 50-311 This Special Report entitled "Failure to Post Continuous Firewatch as Required by Fire Protection Program" is being submitted in accordance with the requirements of License Condition | | * SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO DPR 75 DOCKET NO. 50-311 This Special Report entitled "Failure to Post Continuous Firewatch as Required by Fire Protection Program" is being submitted in accordance with the requirements of License Condition 2.1 which requires that a 14 day report be submitted for cases where the provisions of the approved fire protection program are not maintained. Further, Technical Specification 6.9.3 states that "violations of the fire protection program ... which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted ... |
| | via the Licensee Event Report System within 30 days." This report satisfies both of these requirements. |
| | Sincerely, A. C. Bakken, Ill General Manager-Salem Operations Attachment |
| | : . .) |
| | /JCN .:.: .1. \_.. ......... \.) '* |
| | c U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 9809010154 980824 PDR ADOCK 05000311 S PDR Tht' ~~m' *t'r i~ in y( 1llr hands. |
| | 95-2168 REV 6194 |
|
| |
|
| ===2.1 which===
| | -..*~ |
| requires that a 14 day report be submitted for cases where the provisions of the approved fire protection program are not maintained. | | NRC FORM 366 U.S. NUCLEAR REGULA Y COMMISSION APPROVED B NO. 3150-0104 EXPIRES 06/3012001 (6-1998) Estimated burden per response to comply with this mandatory information |
| Further, Technical Specification | | ) |
| | v |
| | \ |
| | collection request 50 hrs. Reported leSsOns learned are incorporated into LICENSEE EVENT REPORT (LER) the licensing process and fed back to industry. Forward comments regarding burden estimate to the Records Management Branch (T-6 F33). U.S. |
| | Nuclear Regulatory Commission, Washington, DC 20555-0001, and to the (See reverse for required number of Paperwork Reduction Project (3150-0104), Office of Management and Budget. Washington, DC 20503. If an information collection does not display digits/characters for each block) a currently valid OMB control number. the NRC may not conduct or sponsor. |
| | and a person is not required to respond to, the information collection. |
| | FACILITY NAME (I) DOCKET NUMBER (l) PAGE (3) |
| | SALEM UNIT 2 05000311 1 OF 3 TITU(4) |
| | Failure.to Post Continuous Firewatch as required by Fire Protection Plan 08 10 98 OPERATING NAME John C. |
| | * CAUSE SYSTEM REPORTABLE TO EPIX EXPECTED MONm DAY YES (If yes, complete EXPECTED SUBMISSION DATE). |
| | ABSTRACJ (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
| | This Special Report is being made pursuant to the requirements of License Condition 2.I which requires that a 14 day report be submitted for cases where the provisions of the approved fire protection program are not maintained. Further, Tech Spec 6.9.3 states that "violations of the fire protection program -* which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted -* |
| | via the Licensee Event Report System within 30 days." This report satisfies both of these requirements. |
| | At 0945 hours on 8/9/98 the smoke detectors associated with the Salem Unit 2 chiller room were placed in bypass as a result of spurious alarms and an hourly fire watch was established. At approximately 0640 hours on 8/10/98 it was determined that the fire watch should have been provided on a continuous basis due to a pre-existing impairment affecting cable wrap in the same fire zone. This pre-existing condition was associated witn issues concerning qualification of fire barrier material that was used for the cable wrapping. |
| | Upon discovery a continuous fire watch was posted. The cause of this event was failure to recognize the concurrent conditions. This even~ was reported to the NRC by telephone at approximately 14:40 on 8/10/98. |
|
| |
|
| ====6.9.3 states====
| | J NRC FOR.'Yl 366A (6-1998) |
| that "violations of the fire protection program ... which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted
| | U,S, NUCLEAR REGULA TORY COMMISSION LICENSEE EVENT REPORT (LER) |
| ... via the Licensee Event Report System within 30 days." This report satisfies both of these requirements.
| | TEXT CONTINUATION FACILITY NAME (1) DOCKET(2) LER NUMBER (6) PAGE(3) |
| Attachment
| | NUMBER(2) |
| /JCN : . .) .:.: .1. \_.. .........
| | SALEM UNIT 2 05000311 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 2 OF 3 98 0 0 9 00 TEXT (If more space is required, use additional copies ofNRC Form 366A) (17) |
| \.) '* Sincerely, A. C. Bakken, Ill General Salem Operations c U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 9809010154 980824 PDR ADOCK 05000311 S PDR Tht'
| | PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Fire Detection {IC/-}* |
| *t'r in y( 1llr hands. 95-2168 REV 6194
| | * Energy Industry Identification System {EIIS} codes and component function identifier codes appear as (SS/CCC) |
| ) \ v NRC FORM 366 U.S. NUCLEAR REGULA (6-1998) LICENSEE EVENT REPORT (LER) (See reverse for required number of digits/characters for each block) FACILITY NAME (I) Y COMMISSION SALEM UNIT 2 TITU(4) APPROVED B NO. 3150-0104 EXPIRES 06/3012001 Estimated burden per response to comply with this mandatory information collection request 50 hrs. Reported leSsOns learned are incorporated into the licensing process and fed back to industry.
| | CONDITIONS PRIOR TO OCCURRENCE Salem Unit 2 was in the process of starting up following the completion of a maintenance shutdown. |
| Forward comments regarding burden estimate to the Records Management Branch (T-6 F33). U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and to the Paperwork Reduction Project (3150-0104), Office of Management and Budget. Washington, DC 20503. If an information collection does not display a currently valid OMB control number. the NRC may not conduct or sponsor. and a person is not required to respond to, the information collection.
| | DESCRIPTION OF OCCURRENCE On Friday 8/7/98 at 0650 hours a smoke detector in zone 122 (Salem Unit 2 Chiller area) alarmed for no apparent cause. The zone was reset and the alarm cleared. On Sunday 8/9/98 at 06~3 hrs, the same alarm came in and it was determined that there was no apparent cause for the alarm. As an immediate corrective action, all six detectors in this zone were accessed and cleaned. The zone was successfully reset, however, the alarm reflashed at 0945 hours. Because power ascension was in progress the Control Room Supervisor requested that no further troubleshooting be performed at that time. When this detector zone was locked into an alarm condition no other smoke detectors in the zone would cause a reflash alarm condition. A fire protection impairment was established for the loss of detection in accordance with procedures as well as an hourly firewatch. An action request was written to document this condition for further troubleshooting and repair. On 8/10/98, at approximately 0640 hours, during turnover from the off-going fire protection supervisor to the on-coming duty fire protection supervisor, a status review determined that a continuous firewatch should have been established because of the lack of smoke detection in the area combined with the previously existing impairment for potentially inoperable fire barriers in the area. An hourly firewatch was in place during the period of time the smoke detection zone was locked into the fire condition. |
| DOCKET NUMBER (l) 05000311 PAGE (3) 1 OF 3 Failure.to Post Continuous Firewatch as required by Fire Protection Plan 08 10 98 OPERATING NAME John C.
| | The lack of continuous f irewatch is a violation of the approved fire protection program. |
| * CAUSE SYSTEM YES (If yes, complete EXPECTED SUBMISSION DATE). ABSTRACJ (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) EXPECTED MONm DAY REPORTABLE TO EPIX This Special Report is being made pursuant to the requirements of License Condition 2.I which requires that a 14 day report be submitted for cases where the provisions of the approved fire protection program are not maintained.
| | NRC FORM 366A (6-1998) |
| Further, Tech Spec 6.9.3 states that "violations of the fire protection program -* which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted
| | |
| -* via the Licensee Event Report System within 30 days." This report satisfies both of these requirements.
| | NRC FORM 366A (6-1998) l'.S. SUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) |
| At 0945 hours on 8/9/98 the smoke detectors associated with the Salem Unit 2 chiller room were placed in bypass as a result of spurious alarms and an hourly fire watch was established.
| | TEXT CONTINUATION |
| At approximately 0640 hours on 8/10/98 it was determined that the fire watch should have been provided on a continuous basis due to a pre-existing impairment affecting cable wrap in the same fire zone. This pre-existing condition was associated witn issues concerning qualification of fire barrier material that was used for the cable wrapping.
| | .FACILITY NAME (I) DOCKET(2) LER NUMBER (6) PAGE(J) |
| Upon discovery a continuous fire watch was posted. The cause of this event was failure to recognize the concurrent conditions.
| | NUMBER(2) |
| This was reported to the NRC by telephone at approximately 14:40 on 8/10/98. ---------------
| | SALEM UNIT 2 05000311 SEQUENTIAL IREVISION 3 OF 3 I NUMBER NUMBER 98 0 0 9 00 TEXT (If more space is required, use additional copies of NRC Fonn 366A) (17) |
| ------..
| | CAUSE OF OCCURRENCE This was a human performance issue in which there was a failure to properly recognize the implications of the concurrent impairments and take the appropriate required compensatory actions. |
| ',' J *
| | Fire protection procedures clearly require the posting of a continuous firewatch in cases where there was a loss of a fire barrier and no detection was available. |
| * NRC FOR.'Yl 366A (6-1998) U,S, NUCLEAR REGULA TORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) SALEM UNIT 2 TEXT (If more space is required, use additional copies ofNRC Form 366A) (17) PLANT AND SYSTEM IDENTIFICATION DOCKET(2)
| |
| NUMBER(2) 05000311 Westinghouse
| |
| -Pressurized Water Reactor Fire Detection | |
| {IC/-}* LER NUMBER (6) YEAR I SEQUENTIAL I REVISION 2 NUMBER NUMBER 98 0 0 9 00 PAGE(3) OF 3 | |
| * Energy Industry Identification System {EIIS} codes and component function identifier codes appear as (SS/CCC) CONDITIONS PRIOR TO OCCURRENCE Salem Unit 2 was in the process of starting up following the completion of a maintenance shutdown. | |
| DESCRIPTION OF OCCURRENCE On Friday 8/7/98 at 0650 hours a smoke detector in zone 122 (Salem Unit 2 Chiller area) alarmed for no apparent cause. The zone was reset and the alarm cleared. On Sunday 8/9/98 at hrs, the same alarm came in and it was determined that there was no apparent cause for the alarm. As an immediate corrective action, all six detectors in this zone were accessed and cleaned. The zone was successfully reset, however, the alarm reflashed at 0945 hours. Because power ascension was in progress the Control Room Supervisor requested that no further troubleshooting be performed at that time. When this detector zone was locked into an alarm condition no other smoke detectors in the zone would cause a reflash alarm condition. | |
| A fire protection impairment was established for the loss of detection in accordance with procedures as well as an hourly firewatch. | |
| An action request was written to document this condition for further troubleshooting and repair. On 8/10/98, at approximately 0640 hours, during turnover from the off-going fire protection supervisor to the on-coming duty fire protection supervisor, a status review determined that a continuous firewatch should have been established because of the lack of smoke detection in the area combined with the previously existing impairment for potentially inoperable fire barriers in the area. An hourly firewatch was in place during the period of time the smoke detection zone was locked into the fire condition. | |
| The lack of continuous f irewatch is a violation of the approved fire protection program. NRC FORM 366A (6-1998) | |
| ,, ,.., *
| |
| * NRC FORM 366A (6-1998) l'.S. SUCLEAR REGULATORY COMMISSION .FACILITY NAME (I) SALEM UNIT 2 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET(2)
| |
| NUMBER(2) 05000311 TEXT (If more space is required, use additional copies of NRC Fonn 366A) (17) CAUSE OF OCCURRENCE 98 LER NUMBER (6) PAGE(J) I SEQUENTIAL I REVISION 3 NUMBER NUMBER OF 0 0 9 00 This was a human performance issue in which there was a failure to properly recognize the implications of the concurrent impairments and take the appropriate required compensatory actions. 3 Fire protection procedures clearly require the posting of a continuous firewatch in cases where there was a loss of a fire barrier and no detection was available. | |
| PRIOR SIMILAR OCCURRENCES LERs for 1995 to 1998 were reviewed and no similar occurrences were identified. | | PRIOR SIMILAR OCCURRENCES LERs for 1995 to 1998 were reviewed and no similar occurrences were identified. |
| SAFETY CONSEQUENCES AND IMPLICATIONS For approximately 21 hours the fire zone was subject to a one-hour fire watch rather than the continuous fire watch required by the Fire Protection Program. The need for a continuous firewatch was based upon loss of detection in conjunction with the degraded fire barrier. However, the fire barrier in question was not absent but is considered to be degraded and therefore impaired due to the concern regarding the ability of the insulating material to fully meet its design requirements. | | SAFETY CONSEQUENCES AND IMPLICATIONS For approximately 21 hours the fire zone was subject to a one-hour fire watch rather than the continuous fire watch required by the Fire Protection Program. The need for a continuous firewatch was based upon loss of detection in conjunction with the degraded fire barrier. However, the fire barrier in question was not absent but is considered to be degraded and therefore impaired due to the concern regarding the ability of the insulating material to fully meet its design requirements. A review of the Fire-Safe Shutdown analysis has determined that the there is minimal significance associated with this event because there is very limited amount of combustible material in this fire area and it is expected to self extinguish in the worst case within approximately four minutes. In addition, the cables are run in conduit and the fire wrap, although considered to be degraded, was not missing. These reasons, when coupled with the fact that there was a one-hour fire watch in place, significantly minimize the safety significance of this event. |
| A review of the Fire-Safe Shutdown analysis has determined that the there is minimal significance associated with this event because there is very limited amount of combustible material in this fire area and it is expected to self extinguish in the worst case within approximately four minutes. In addition, the cables are run in conduit and the fire wrap, although considered to be degraded, was not missing. These reasons, when coupled with the fact that there was a one-hour fire watch in place, significantly minimize the safety significance of this event. CORRECTIVE ACTIONS: 1. A continuous firewatch was posted immediately upon discovery of the error. 2. The smoke detectors were repaired and returned to service. 3. The individuals involved are being held accountable for their actions in accordance with company policy.}} | | CORRECTIVE ACTIONS: |
| | : 1. A continuous firewatch was posted immediately upon discovery of the error. |
| | : 2. The smoke detectors were repaired and returned to service. |
| | : 3. The individuals involved are being held accountable for their actions in accordance with company policy.}} |
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LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected
ML18106A6061998-04-0101 April 1998
Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences
ML18106A4451998-04-0101 April 1998
LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr
ML18106A4351998-03-30030 March 1998
LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr
ML18106A3961998-03-20020 March 1998
LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr
ML18106A5781998-03-20020 March 1998
Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs
ML18106A4021998-03-20020 March 1998
LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr
ML18106A4031998-03-20020 March 1998
LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr
1999-08-26
[Table view]
Category:RO)
MONTHYEARML18107A5031999-08-26026 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
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
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
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
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
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
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
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
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
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
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
ML18106B0081998-12-24024 December 1998
LER 97-001-01:on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With 981224 Ltr
ML18106B0021998-12-17017 December 1998
LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr
ML18106A9551998-11-0303 November 1998
LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr
ML18106A9451998-10-30030 October 1998
LER 97-004-01:on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With 981022 Ltr
ML18106A9491998-10-22022 October 1998
LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr
ML18106A9301998-10-21021 October 1998
LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr
ML18106A9071998-10-0101 October 1998
LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr
ML18106A8951998-09-28028 September 1998
LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr
ML18106A8821998-09-21021 September 1998
LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr
ML18106A8791998-09-16016 September 1998
LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr
ML18106A8801998-09-0808 September 1998
LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr
ML18106A8531998-08-27027 August 1998
LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr
ML18106A8521998-08-27027 August 1998
LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr
ML18106A8421998-08-24024 August 1998
LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr
ML18106A8431998-08-24024 August 1998
LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr
ML18106A8141998-08-13013 August 1998
LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr
ML18106A8201998-08-13013 August 1998
LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr
ML18106A6931998-06-29029 June 1998
LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged
ML18106A6471998-06-0404 June 1998
LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr
ML18106A6421998-06-0101 June 1998
LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr
ML18106A6431998-05-29029 May 1998
LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr
ML18106A6141998-05-18018 May 1998
LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr
ML18106A5901998-05-0101 May 1998
LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr
ML18106A5611998-04-20020 April 1998
LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected
ML18106A6061998-04-0101 April 1998
Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences
ML18106A4451998-04-0101 April 1998
LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr
ML18106A4351998-03-30030 March 1998
LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr
ML18106A3961998-03-20020 March 1998
LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr
ML18106A5781998-03-20020 March 1998
Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs
ML18106A4021998-03-20020 March 1998
LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr
ML18106A4031998-03-20020 March 1998
LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr
1999-08-26
[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
OPS~G *
- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG 24 1998 LR-N980418 Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Gentlemen:
SPECIAL REPORT 311/98-009-00
- SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO DPR 75 DOCKET NO. 50-311 This Special Report entitled "Failure to Post Continuous Firewatch as Required by Fire Protection Program" is being submitted in accordance with the requirements of License Condition 2.1 which requires that a 14 day report be submitted for cases where the provisions of the approved fire protection program are not maintained. Further, Technical Specification 6.9.3 states that "violations of the fire protection program ... which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted ...
via the Licensee Event Report System within 30 days." This report satisfies both of these requirements.
Sincerely, A. C. Bakken, Ill General Manager-Salem Operations Attachment
- . .)
/JCN .:.: .1. \_.. ......... \.) '*
c U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 9809010154 980824 PDR ADOCK 05000311 S PDR Tht' ~~m' *t'r i~ in y( 1llr hands.
95-2168 REV 6194
-..*~
NRC FORM 366 U.S. NUCLEAR REGULA Y COMMISSION APPROVED B NO. 3150-0104 EXPIRES 06/3012001 (6-1998) Estimated burden per response to comply with this mandatory information
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v
\
collection request 50 hrs. Reported leSsOns learned are incorporated into LICENSEE EVENT REPORT (LER) the licensing process and fed back to industry. Forward comments regarding burden estimate to the Records Management Branch (T-6 F33). U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, and to the (See reverse for required number of Paperwork Reduction Project (3150-0104), Office of Management and Budget. Washington, DC 20503. If an information collection does not display digits/characters for each block) a currently valid OMB control number. the NRC may not conduct or sponsor.
and a person is not required to respond to, the information collection.
FACILITY NAME (I) DOCKET NUMBER (l) PAGE (3)
SALEM UNIT 2 05000311 1 OF 3 TITU(4)
Failure.to Post Continuous Firewatch as required by Fire Protection Plan 08 10 98 OPERATING NAME John C.
- CAUSE SYSTEM REPORTABLE TO EPIX EXPECTED MONm DAY YES (If yes, complete EXPECTED SUBMISSION DATE).
ABSTRACJ (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
This Special Report is being made pursuant to the requirements of License Condition 2.I which requires that a 14 day report be submitted for cases where the provisions of the approved fire protection program are not maintained. Further, Tech Spec 6.9.3 states that "violations of the fire protection program -* which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted -*
via the Licensee Event Report System within 30 days." This report satisfies both of these requirements.
At 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> on 8/9/98 the smoke detectors associated with the Salem Unit 2 chiller room were placed in bypass as a result of spurious alarms and an hourly fire watch was established. At approximately 0640 hours0.00741 days <br />0.178 hours <br />0.00106 weeks <br />2.4352e-4 months <br /> on 8/10/98 it was determined that the fire watch should have been provided on a continuous basis due to a pre-existing impairment affecting cable wrap in the same fire zone. This pre-existing condition was associated witn issues concerning qualification of fire barrier material that was used for the cable wrapping.
Upon discovery a continuous fire watch was posted. The cause of this event was failure to recognize the concurrent conditions. This even~ was reported to the NRC by telephone at approximately 14:40 on 8/10/98.
J NRC FOR.'Yl 366A (6-1998)
U,S, NUCLEAR REGULA TORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET(2) LER NUMBER (6) PAGE(3)
NUMBER(2)
SALEM UNIT 2 05000311 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 2 OF 3 98 0 0 9 00 TEXT (If more space is required, use additional copies ofNRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Fire Detection {IC/-}*
- Energy Industry Identification System {EIIS} codes and component function identifier codes appear as (SS/CCC)
CONDITIONS PRIOR TO OCCURRENCE Salem Unit 2 was in the process of starting up following the completion of a maintenance shutdown.
DESCRIPTION OF OCCURRENCE On Friday 8/7/98 at 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> a smoke detector in zone 122 (Salem Unit 2 Chiller area) alarmed for no apparent cause. The zone was reset and the alarm cleared. On Sunday 8/9/98 at 06~3 hrs, the same alarm came in and it was determined that there was no apparent cause for the alarm. As an immediate corrective action, all six detectors in this zone were accessed and cleaned. The zone was successfully reset, however, the alarm reflashed at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />. Because power ascension was in progress the Control Room Supervisor requested that no further troubleshooting be performed at that time. When this detector zone was locked into an alarm condition no other smoke detectors in the zone would cause a reflash alarm condition. A fire protection impairment was established for the loss of detection in accordance with procedures as well as an hourly firewatch. An action request was written to document this condition for further troubleshooting and repair. On 8/10/98, at approximately 0640 hours0.00741 days <br />0.178 hours <br />0.00106 weeks <br />2.4352e-4 months <br />, during turnover from the off-going fire protection supervisor to the on-coming duty fire protection supervisor, a status review determined that a continuous firewatch should have been established because of the lack of smoke detection in the area combined with the previously existing impairment for potentially inoperable fire barriers in the area. An hourly firewatch was in place during the period of time the smoke detection zone was locked into the fire condition.
The lack of continuous f irewatch is a violation of the approved fire protection program.
NRC FORM 366A (6-1998)
NRC FORM 366A (6-1998) l'.S. SUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
.FACILITY NAME (I) DOCKET(2) LER NUMBER (6) PAGE(J)
NUMBER(2)
SALEM UNIT 2 05000311 SEQUENTIAL IREVISION 3 OF 3 I NUMBER NUMBER 98 0 0 9 00 TEXT (If more space is required, use additional copies of NRC Fonn 366A) (17)
CAUSE OF OCCURRENCE This was a human performance issue in which there was a failure to properly recognize the implications of the concurrent impairments and take the appropriate required compensatory actions.
Fire protection procedures clearly require the posting of a continuous firewatch in cases where there was a loss of a fire barrier and no detection was available.
PRIOR SIMILAR OCCURRENCES LERs for 1995 to 1998 were reviewed and no similar occurrences were identified.
SAFETY CONSEQUENCES AND IMPLICATIONS For approximately 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> the fire zone was subject to a one-hour fire watch rather than the continuous fire watch required by the Fire Protection Program. The need for a continuous firewatch was based upon loss of detection in conjunction with the degraded fire barrier. However, the fire barrier in question was not absent but is considered to be degraded and therefore impaired due to the concern regarding the ability of the insulating material to fully meet its design requirements. A review of the Fire-Safe Shutdown analysis has determined that the there is minimal significance associated with this event because there is very limited amount of combustible material in this fire area and it is expected to self extinguish in the worst case within approximately four minutes. In addition, the cables are run in conduit and the fire wrap, although considered to be degraded, was not missing. These reasons, when coupled with the fact that there was a one-hour fire watch in place, significantly minimize the safety significance of this event.
CORRECTIVE ACTIONS:
- 1. A continuous firewatch was posted immediately upon discovery of the error.
- 2. The smoke detectors were repaired and returned to service.
- 3. The individuals involved are being held accountable for their actions in accordance with company policy.
