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| {{#Wiki_filter:* | | {{#Wiki_filter:NllC Form311 IM3) |
| * NllC Form311 IM3) U.I, NUCLEAll llEGULATOllY COflWllllON APl'AOVED OMI NO. 311111-4104 LICENSEE EVENT REPORT (LER) EXl'IRES:
| | * LICENSEE EVENT REPORT (LER) |
| 11/31115 I DOCKET NUM9Ell (2) I """"' I'll 0 I 5 I 0 I 0 I 0 I 2 17 I 2 1 I OF 0 I 5 FACILITY NAME 111 Sa1em Generating Station -Unit 1 TITLE l*I T. s. Survei11ance 4.7.11 Ron-Comp1iance | | * U.I, NUCLEAll llEGULATOllY COflWllllON APl'AOVED OMI NO. 311111-4104 EXl'IRES: 11/31115 I |
| -Fire Pampers Rot Survei11ed | | FACILITY NAME 111 DOCKET NUM9Ell (2) I """"' I'll Sa1em Generating Station - Unit 1 0 I 5 I 0 I 0 I 0 I 2 17 I 2 1 IOF 0 I 5 TITLE l*I T. s. Survei11ance 4.7.11 Ron-Comp1iance - Fire Pampers Rot Survei11ed - Inad. Admin. Con EVENT DATE (II) LEA NUMDEll Ill llEl'OAT DATE (7) OTHEll FACILITIES INVOLVED Ill MONTH QAY YEAR YEAR ]@ SE~~~~i~AL ft =~= MONTH DAY YEAR FACILITY NAMES DOCKET NUMllERISI Sa1em - Unit 2 o 1s Io I o I o 13 1 111 nlgolg a a ale -ol1IG-olo1lo ol4ala OPlRATING THll llEl'OAT II IUIMITTED l'UlllUANT TO THE REQUlllEMENTI OF 10 CFll §: (Ch<<:lt one or man of Ill* followln11J (11) |
| -Inad. Admin. Con EVENT DATE (II) LEA NUMDEll Ill llEl'OAT DATE (7) OTHEll FACILITIES INVOLVED Ill MONTH QAY YEAR YEAR ]@ | | MODE tel POWEii LEVEL I N/A 21U02(bl 20.G(1111 Ill) |
| ft MONTH DAY YEAR FACILITY NAMES DOCKET NUMllERISI Sa1em -Unit 2 o 1 s Io I o I o 13 1 111 nlgolg a a ale -ol1IG-olo1lo ol4ala OPlRATING MODE tel THll llEl'OAT II IUIMITTED l'UlllUANT TO THE REQUlllEMENTI OF 10 CFll §: (Ch<<:lt one or man of Ill* followln11J (11) ..,.. ______ ............ | | -- 20.-lcl I0.*1*1111 I0,7311oll2llM ll0.731oll21M -- 731.71lb) 73..71.lcl 1101 I I 20.ac.11111u1 1111.*Ccll21 llll.73(oll211wH) OTHEll ($/>>c/fymAb,,,.,r 11111=:::::::: |
| __. 21U02(bl 20.-lcl I0,7311oll2llM
| | .....-..~~~~~""""'..+--! "Y l>>low ond In Toxr, NRC Fann llll.73(ol(21(1J I0.7311oll211wlllllAI 366A) |
| ---I0.*1*1111 ll0.731oll21M LEVEL ----731.71lb) 73..71.lcl POWEii I N/A 20.G(1111 Ill) 1101 I I 20.ac.11111u1 11111=:::::::: | | - 1111.731(11121(111 1111.7:11(81121 (Ill) |
| 1111.*Ccll21 "Y llll.73(ol(21(1J llll.73(oll211wH) | | - I0.731Cell211wfllllll 1111.731(111211*1 LICENIEE CONTACT FOR THll LEI! (12) |
| -I0.7311oll211wlllllAI
| | NAME TELEPHONE NUMBER AREA CODE M. J. _Po11ack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll llEl'OAT (1311 CAUSE SYSTEM COMPONENT MANUFAC- MANUFAC-TURER SYSTEM COMPONENT TUR ER I I I I I I I I I I I I I I I I I I I - I I I I I I IUJIPLEMENTAL llEl'ORT EXl'ECTED 1141 MONTH DAY Y~AA EXPECTED n YES (If ya, comp- EXPECTED SU6MISSION DATE) kl NO SUllMISSION DATE (151 I I I On September 9, 1988, it was identified, by Site Protection personnel, that "twenty-nine ( 29) Air Balance Model #119 dampers, in several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11. The apparent root cause of this event has been attributed to inadequate administrative control. The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers. Consequently, the dampers were not identified on the equipment lists used as a reference to prepare surveillance procedures. Subsequently, -the damper surveillance requirement was missed. The surveillance for the subject dampers was completed. All dampers successfully passed. The Site Protection staff engineer(s) have been counseled on* the use of AP-6~ |
| -OTHEll ($/>>c/fymAb,,,.,r l>>low ond In Toxr, NRC Fann 366A) --1111.731(11121(111 I0.731Cell211wfllllll
| | "Incident Report/Licensee Event Report Program". Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected. As part of the Fire Protection Improvement -program, a design change will be made to have the appropriate P&ID- schematics identify and number (i.e., component I.D.) the dampers. |
| --1111.7:11(81121 (Ill) 1111.731(111211*1 LICENIEE CONTACT FOR THll LEI! (12) NAME AREA CODE M. J. _Po11ack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll llEl'OAT (1311 CAUSE SYSTEM COMPONENT I I I I I I I I TURER I I I SYSTEM I I -COMPONENT MANUFAC-TUR ER I I I I I I I I I I I I TELEPHONE NUMBER EXPECTED IUJIPLEMENTAL llEl'ORT EXl'ECTED 1141 MONTH DAY SUllMISSION DATE (151 kl NO n YES (If ya, comp-EXPECTED SU6MISSION DATE) I I On September 9, 1988, it was identified, by Site Protection personnel, that "twenty-nine ( 29) Air Balance Model #119 dampers, in several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11. The apparent root cause of this event has been attributed to inadequate administrative control. The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers. Consequently, the dampers were not identified on the equipment lists used as a reference to prepare surveillance procedures.
| | 8810120307" 881004 *>s |
| Subsequently, -the damper surveillance requirement was missed. The surveillance for the subject dampers was completed. | | .PDR ADOCK 05000272 8 PNU NAC Form 311 (Ml) |
| All dampers successfully passed. The Site Protection staff engineer(s) have been counseled on* the use of "Incident Report/Licensee Event Report Program". | | |
| Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected. | | Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 88-016-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION: |
| As part of the Fire Protection Improvement -program, a design change will be made to have the appropriate P&ID-schematics identify and number (i.e., component I.D.) the dampers. NAC Form 311 (Ml) 8810120307" 881004 *>s .8 PDR ADOCK 05000272 PNU I | | Westinghouse - Pressu~ized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx} |
| *
| | IDENTIFICATION OF OCCURRENCE: |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 88-016-00 PAGE 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
| | Technical Specification Surveillance 4.7.11 Non-compliance; Fire Dampers Not Surveilled Due To Inadequate Design Review Event Date: 9/09/88 Report Date: 10/04/88 This report was initiated by Incident Report Nos. 88-379 and 88-380. |
| Westinghouse | | CONDITIONS PRIOR TO OCCURRENCE: |
| - | |
| Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE: | |
| Technical Specification Surveillance 4.7.11 Non-compliance; Fire Dampers Not Surveilled Due To Inadequate Design Review Event Date: 9/09/88 Report Date: 10/04/88 This report was initiated by Incident Report Nos. 88-379 and 88-380. CONDITIONS PRIOR TO OCCURRENCE: | |
| N/A DESCRIPTION OF OCCURRENCE: | | N/A DESCRIPTION OF OCCURRENCE: |
| On September 9, 1988, it was identified, by Site Protection personnel, that twenty-nine (29) Air Balance Model #119 dampers, 1n several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11. Technical Specification 3 .. 7 .11 states: "All fire penetrations (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting safety related areas shall be functional." Technical Specification Action Statement 3.7.11.a states: "With one or more of the above required fire barrier penetrations non-functional, within one hour either establish a continuous fire watch on at least one side of the affected penetration, or | | On September 9, 1988, it was identified, by Site Protection personnel, that twenty-nine (29) Air Balance Model #119 dampers, 1n several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11. |
| * verify* the OPERABILITY of fire detectors on at least one side of .the non-functional fire barrier and establish an hourly fire watch patrol. Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and s_ubmi t a Special Report to the Commission pursuant to Specification 6.9.2 within the next {30) days outlining the action taken, the cause of the 'non-functional penetration and . plans and schedule for restoring the fire barrier penetration (s) -; to functional status." Technical Specification Surveillance states: *"Each of the above required penetration fire barriers shall be | | Technical Specification 3 .. 7 .11 states: |
| *
| | "All fire penetrations (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting safety related areas shall be functional." |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 88-016-00 PAGE 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) verified to be functional:
| | Technical Specification Action Statement 3.7.11.a states: |
| : a. At least once per 18 months by a visual inspection, and b. Prior to returning a penetration fire barrier to functional status following repairs or maintenance by the performance of a visual inspection of the affected penetration fire barrier(s}." Note -Unit 1 Technical Specification 3.7.11 differs from Unit 2. The Unit 1 words "functional" and "non-functional" are replaced by the words "OPERABLE" and "inoperable" respectively. | | "With one or more of the above required fire barrier penetrations non-functional, within one hour either establish a continuous fire watch on at least one side of the affected penetration, or |
| The fire areas in which the dampers were not surveilled include: Unit Area Number of Dampers 1 Battery Rooms 8 1 84' El. Switchgear Room 7 1 #11 Diesel Fuel Oil Storage Tank Room 1 1 #12 Diesel Fuel Oil Storage Tank Room 1 2 Battery Rooms 9 2 84' El. Switchgear Room 1 .2 #21 Diesel Fuel Oil Storage Tank Room 1 2 #22 Diesel Fuel Oil Storage Tank Room 1 APPARENT CAUSE OF OCCURRENCE: | | * verify* the OPERABILITY of fire detectors on at least one side of |
| -The apparent root cause of this event has been attributed to inadequate administrative control. The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers. Consequently, the dampers were not identified on the equipment lists used as a reference to surveillance'procedures.
| | .the non-functional fire barrier and establish an hourly fire watch patrol. Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and s_ubmi t a Special Report to the Commission pursuant to Specification 6.9.2 within the next {30) days outlining the action taken, the cause of the 'non-functional penetration and . |
| Subsequently,:the damper surveillance requirement was missed. ANALYSIS OF OCCURRENCE: | | plans and schedule for restoring the fire barrier penetration (s) -; |
| The fire barrier penetration visual surveillance ensures the functional integrity of barrier penetrations, including dampers, is not violated. | | to functional status." |
| The functional integrity of fire barriers ensures fires will be confined or adequately from spreading to adjacent portions of the facility. | | Technical Specification Surveillance 4.7~11 states: |
| *This design feature minimizes the ;,' | | *"Each of the above required penetration fire barriers shall be |
| *
| | |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE 88-016-00 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd) possibility of a single fire involving several areas of the facility prior to detection and extinguishment.
| | Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 88-016-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) verified to be functional: |
| The penetration fire barriers are a passive element in the facility fire protection program. However, because the fire barrier dampers have not been inspected within the 18 month period as per Technical Specification Surveillance 4.7.11 this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). An hourly fire watch patrol, for the fire barriers containing these dampers, had been previously established due to other fire protection and lOCFR 50, Appendix R concerns. | | : a. At least once per 18 months by a visual inspection, and |
| This fire watch complies with the action required per Technical Specification Action Statement 3.7.11.a. | | : b. Prior to returning a penetration fire barrier to functional status following repairs or maintenance by the performance of a visual inspection of the affected penetration fire barrier(s}." |
| Investigation of this event revealed that in August 1987, field walkdowns, conducted by engineering, were performed to evaluate fire area boundaries in support of revision to lOCFR 50 Appendix R exemption requests. | | Note - Unit 1 Technical Specification 3.7.11 differs from Unit 2. |
| One of the results of this walkdown recognized these dampers as being a component of the fire barrier(s). | | The Unit 1 words "functional" and "non-functional" are replaced by the words "OPERABLE" and "inoperable" respectively. |
| The scope of the review, however, did not include surveillance compliance thus the deficiency was not identified at that time. Coincidentally, in the spring of 1988 of procedure MlO-SST-031-1, "18 Month Fire Damper Visual Inspection", was initiated to address newly installed dampers. Other dampers (without a fusible link) have historically been functionally tested. The Site Protection staff engineer aware of the subject dampers through detailed review of the mechanical arrangement drawings. | | The fire areas in which the dampers were not surveilled include: |
| The Site Protection staff engineer, however, did not recognize the_ potential reportability. | | Unit Area Number of Dampers 1 Battery Rooms 8 1 84' El. Switchgear Room 7 1 #11 Diesel Fuel Oil Storage Tank Room 1 1 #12 Diesel Fuel Oil Storage Tank Room 1 2 Battery Rooms 9 2 84' El. Switchgear Room 1 |
| In August 1988, ,the procedure was approved by the Station Operations Review Committee At that SORC meeting, it was questioned whether these dampers have been surveilled historically*. | | .2 #21 Diesel Fuel Oil Storage Tank Room 1 2 #22 Diesel Fuel Oil Storage Tank Room 1 APPARENT CAUSE OF OCCURRENCE: |
| | The apparent root cause of this event has been attributed to inadequate administrative control. The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers. Consequently, the dampers were not identified on the equipment lists used as a reference to p~epare surveillance'procedures. Subsequently,:the damper surveillance requirement was missed. |
| | ANALYSIS OF OCCURRENCE: |
| | The fire barrier penetration visual surveillance ensures the functional integrity of barrier penetrations, including dampers, is not violated. The functional integrity of fire barriers ensures fires will be confined or adequately reta~ded from spreading to adjacent portions of the facility. *This design feature minimizes the |
| | |
| | Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION |
| | ~~~~~~~---:-~~~~~~~~~--~~~~~~~~~~~~~--~~~~~*---~~~- |
| | LER NUMBER PAGE U-'-=n=i~t-=1'--~~~~~~~~~~~~--=5000272 88-016-00 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd) possibility of a single fire involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program. |
| | However, because the fire barrier dampers have not been inspected within the 18 month period as per Technical Specification Surveillance 4.7.11 this event is reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B). |
| | An hourly fire watch patrol, for the fire barriers containing these dampers, had been previously established due to other fire protection and 10CFR 50, Appendix R concerns. This fire watch complies with the action required per Technical Specification Action Statement 3.7.11.a. |
| | Investigation of this event revealed that in August 1987, field walkdowns, conducted by engineering, were performed to evaluate fire area boundaries in support of revision to 10CFR 50 Appendix R exemption requests. One of the results of this walkdown recognized these dampers as being a component of the fire barrier(s). The scope of the review, however, did not include surveillance compliance thus the deficiency was not identified at that time. |
| | Coincidentally, in the spring of 1988 pr~paration of procedure MlO-SST-031-1, "18 Month Fire Damper Visual Inspection", was initiated to address newly installed dampers. Other dampers (without a fusible link) have historically been functionally tested. The Site Protection staff engineer becam~ aware of the subject dampers through detailed review of the mechanical arrangement drawings. The Site Protection staff engineer, however, did not recognize the_ potential reportability. |
| | In August 1988, ,the procedure was approved by the Station Operations Review Committee (SO~C). At that SORC meeting, it was questioned whether these dampers have been surveilled historically*. |
| Investigation of the historical records indicated that these dampers have not been surveilled historically. | | Investigation of the historical records indicated that these dampers have not been surveilled historically. |
| CORRECTIVE ACTION: The surveillance for the subject dampers was completed. | | CORRECTIVE ACTION: |
| All dampers successfully passed. The Site Protection staff engineers have been counseled on the use of AP-6, "Incident Report/Licensee Evept Report.Progra*". | | The surveillance for the subject dampers was completed. All dampers successfully passed. |
| Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected. | | The Site Protection staff engineers have been counseled on the use of AP-6, "Incident Report/Licensee Evept Report.Progra*". |
| *
| | Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected. |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: (cont'd) DOCKET NUMBER 5000272 LER NUMBER 88-016-00 PAGE 5 of 5 As part of the Fire Protection Improvement Program, a design change will be made to have the appropriate drawings revised to identify and number (i.e., component I.D.) the dampers. MJP:pc SORC Mtg. 88-082 General Manager -Salem Operations
| | |
| *
| | Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 88-016-00 5 of 5 CORRECTIVE ACTION: (cont'd) |
| * Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
| | As part of the Fire Protection Improvement Program, a design change will be made to have the appropriate drawings revised to identify and number (i.e., component I.D.) the dampers. |
| | ;It:~ |
| | General Manager - |
| | Salem Operations MJP:pc SORC Mtg. 88-082 |
| | |
| | OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 4, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
|
| |
|
| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 88-016-00 October 4, 1988 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations | | |
| *1ocFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of*discovery. | | SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 88-016-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations *1ocFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of*discovery. |
| MJP:pc Distribution The Energy People Sincerely yours, L. K. Miller General Salem Operations 95-2189 (11 M) 12-84}}
| | Sincerely yours, ff~ |
| | L. K. Miller General Manager-Salem Operations MJP:pc Distribution The Energy People 95-2189 (11 M) 12-84}} |
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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: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
NllC Form311 IM3)
- LICENSEE EVENT REPORT (LER)
- U.I, NUCLEAll llEGULATOllY COflWllllON APl'AOVED OMI NO. 311111-4104 EXl'IRES: 11/31115 I
FACILITY NAME 111 DOCKET NUM9Ell (2) I """"' I'll Sa1em Generating Station - Unit 1 0 I 5 I 0 I 0 I 0 I 2 17 I 2 1 IOF 0 I 5 TITLE l*I T. s. Survei11ance 4.7.11 Ron-Comp1iance - Fire Pampers Rot Survei11ed - Inad. Admin. Con EVENT DATE (II) LEA NUMDEll Ill llEl'OAT DATE (7) OTHEll FACILITIES INVOLVED Ill MONTH QAY YEAR YEAR ]@ SE~~~~i~AL ft =~= MONTH DAY YEAR FACILITY NAMES DOCKET NUMllERISI Sa1em - Unit 2 o 1s Io I o I o 13 1 111 nlgolg a a ale -ol1IG-olo1lo ol4ala OPlRATING THll llEl'OAT II IUIMITTED l'UlllUANT TO THE REQUlllEMENTI OF 10 CFll §: (Ch<<:lt one or man of Ill* followln11J (11)
MODE tel POWEii LEVEL I N/A 21U02(bl 20.G(1111 Ill)
-- 20.-lcl I0.*1*1111 I0,7311oll2llM ll0.731oll21M -- 731.71lb) 73..71.lcl 1101 I I 20.ac.11111u1 1111.*Ccll21 llll.73(oll211wH) OTHEll ($/>>c/fymAb,,,.,r 11111=::::::::
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- 1111.731(11121(111 1111.7:11(81121 (Ill)
- I0.731Cell211wfllllll 1111.731(111211*1 LICENIEE CONTACT FOR THll LEI! (12)
NAME TELEPHONE NUMBER AREA CODE M. J. _Po11ack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll llEl'OAT (1311 CAUSE SYSTEM COMPONENT MANUFAC- MANUFAC-TURER SYSTEM COMPONENT TUR ER I I I I I I I I I I I I I I I I I I I - I I I I I I IUJIPLEMENTAL llEl'ORT EXl'ECTED 1141 MONTH DAY Y~AA EXPECTED n YES (If ya, comp- EXPECTED SU6MISSION DATE) kl NO SUllMISSION DATE (151 I I I On September 9, 1988, it was identified, by Site Protection personnel, that "twenty-nine ( 29) Air Balance Model #119 dampers, in several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11. The apparent root cause of this event has been attributed to inadequate administrative control. The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers. Consequently, the dampers were not identified on the equipment lists used as a reference to prepare surveillance procedures. Subsequently, -the damper surveillance requirement was missed. The surveillance for the subject dampers was completed. All dampers successfully passed. The Site Protection staff engineer(s) have been counseled on* the use of AP-6~
"Incident Report/Licensee Event Report Program". Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected. As part of the Fire Protection Improvement -program, a design change will be made to have the appropriate P&ID- schematics identify and number (i.e., component I.D.) the dampers.
8810120307" 881004 *>s
.PDR ADOCK 05000272 8 PNU NAC Form 311 (Ml)
Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 88-016-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressu~ized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Technical Specification Surveillance 4.7.11 Non-compliance; Fire Dampers Not Surveilled Due To Inadequate Design Review Event Date: 9/09/88 Report Date: 10/04/88 This report was initiated by Incident Report Nos.88-379 and 88-380.
CONDITIONS PRIOR TO OCCURRENCE:
N/A DESCRIPTION OF OCCURRENCE:
On September 9, 1988, it was identified, by Site Protection personnel, that twenty-nine (29) Air Balance Model #119 dampers, 1n several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11.
Technical Specification 3 .. 7 .11 states:
"All fire penetrations (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting safety related areas shall be functional."
Technical Specification Action Statement 3.7.11.a states:
"With one or more of the above required fire barrier penetrations non-functional, within one hour either establish a continuous fire watch on at least one side of the affected penetration, or
- verify* the OPERABILITY of fire detectors on at least one side of
.the non-functional fire barrier and establish an hourly fire watch patrol. Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and s_ubmi t a Special Report to the Commission pursuant to Specification 6.9.2 within the next {30) days outlining the action taken, the cause of the 'non-functional penetration and .
plans and schedule for restoring the fire barrier penetration (s) -;
to functional status."
Technical Specification Surveillance 4.7~11 states:
Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 88-016-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) verified to be functional:
- a. At least once per 18 months by a visual inspection, and
- b. Prior to returning a penetration fire barrier to functional status following repairs or maintenance by the performance of a visual inspection of the affected penetration fire barrier(s}."
Note - Unit 1 Technical Specification 3.7.11 differs from Unit 2.
The Unit 1 words "functional" and "non-functional" are replaced by the words "OPERABLE" and "inoperable" respectively.
The fire areas in which the dampers were not surveilled include:
Unit Area Number of Dampers 1 Battery Rooms 8 1 84' El. Switchgear Room 7 1 #11 Diesel Fuel Oil Storage Tank Room 1 1 #12 Diesel Fuel Oil Storage Tank Room 1 2 Battery Rooms 9 2 84' El. Switchgear Room 1
.2 #21 Diesel Fuel Oil Storage Tank Room 1 2 #22 Diesel Fuel Oil Storage Tank Room 1 APPARENT CAUSE OF OCCURRENCE:
The apparent root cause of this event has been attributed to inadequate administrative control. The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers. Consequently, the dampers were not identified on the equipment lists used as a reference to p~epare surveillance'procedures. Subsequently,:the damper surveillance requirement was missed.
ANALYSIS OF OCCURRENCE:
The fire barrier penetration visual surveillance ensures the functional integrity of barrier penetrations, including dampers, is not violated. The functional integrity of fire barriers ensures fires will be confined or adequately reta~ded from spreading to adjacent portions of the facility. *This design feature minimizes the
Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
~~~~~~~---:-~~~~~~~~~--~~~~~~~~~~~~~--~~~~~*---~~~-
LER NUMBER PAGE U-'-=n=i~t-=1'--~~~~~~~~~~~~--=5000272 88-016-00 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd) possibility of a single fire involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program.
However, because the fire barrier dampers have not been inspected within the 18 month period as per Technical Specification Surveillance 4.7.11 this event is reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B).
An hourly fire watch patrol, for the fire barriers containing these dampers, had been previously established due to other fire protection and 10CFR 50, Appendix R concerns. This fire watch complies with the action required per Technical Specification Action Statement 3.7.11.a.
Investigation of this event revealed that in August 1987, field walkdowns, conducted by engineering, were performed to evaluate fire area boundaries in support of revision to 10CFR 50 Appendix R exemption requests. One of the results of this walkdown recognized these dampers as being a component of the fire barrier(s). The scope of the review, however, did not include surveillance compliance thus the deficiency was not identified at that time.
Coincidentally, in the spring of 1988 pr~paration of procedure MlO-SST-031-1, "18 Month Fire Damper Visual Inspection", was initiated to address newly installed dampers. Other dampers (without a fusible link) have historically been functionally tested. The Site Protection staff engineer becam~ aware of the subject dampers through detailed review of the mechanical arrangement drawings. The Site Protection staff engineer, however, did not recognize the_ potential reportability.
In August 1988, ,the procedure was approved by the Station Operations Review Committee (SO~C). At that SORC meeting, it was questioned whether these dampers have been surveilled historically*.
Investigation of the historical records indicated that these dampers have not been surveilled historically.
CORRECTIVE ACTION:
The surveillance for the subject dampers was completed. All dampers successfully passed.
The Site Protection staff engineers have been counseled on the use of AP-6, "Incident Report/Licensee Evept Report.Progra*".
Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected.
Salem Generating Station DOCKET NUMBER LICENSEE EVENT REPORT (LER) TEXT CONTINUATION LER NUMBER PAGE Unit 1 5000272 88-016-00 5 of 5 CORRECTIVE ACTION: (cont'd)
As part of the Fire Protection Improvement Program, a design change will be made to have the appropriate drawings revised to identify and number (i.e., component I.D.) the dampers.
- It
- ~
General Manager -
Salem Operations MJP:pc SORC Mtg.88-082
OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 4, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 88-016-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations *1ocFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of*discovery.
Sincerely yours, ff~
L. K. Miller General Manager-Salem Operations MJP:pc Distribution The Energy People 95-2189 (11 M) 12-84
