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| | issue date = 12/01/1995 | | | issue date = 12/01/1995 |
| | title = LER 95-007-00:on 900503,diesel Surveillance Required by TS Was Missed.Revised Process for Modifying EDG Surveillance frequency.W/951201 Ltr | | | title = LER 95-007-00:on 900503,diesel Surveillance Required by TS Was Missed.Revised Process for Modifying EDG Surveillance frequency.W/951201 Ltr |
| | author name = GREENLEE S, WARREN C C | | | author name = Greenlee S, Warren C |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:' ('i';t: $j * | | {{#Wiki_filter:' ( |
| * . Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit C*:=C 01 1995 LR-N95216 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
| | 'i';t: |
| LICENSEE EVENT REPORT 311/95-007-00 SALEM GENERATING STATION -UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed Diesel Surveillance Required by the Technical Specification'' | | ~ |
| is being submitted pursuant to the requirements of the Code of Federal Regulations 10 CFR5 0 . 7 3 (a) ( 2 ) ( i) . SORC Mtg. 95-141 Attachment DVH/tcp C Distribution LER File 9512050157 951201 PDR ADOCK 05000311 Sincerely, {! | | $j |
| C. Warren General Manager -Salem Operations 1-hl' F\t\\\T i--in \\11;r
| | ~~; PS~G * * |
| .. foJJ'' I 95-2168 REV. ,6/94 S PDR | | . Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit C*:=C 01 1995 LR-N95216 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: |
| *
| | LICENSEE EVENT REPORT 311/95-007-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed Diesel Surveillance Required by the Technical Specification'' is being submitted pursuant to the requirements of the Code of Federal Regulations 10 CFR5 0 . 7 3 (a) ( 2 ) ( i) . |
| * Attachment A PSE&G Commitments for LER 311/95-007-00 The following items represent
| | Sincerely, (J~ {! C-1././~ |
| *PSE&G commitments made to the Nuclear Regulatory Commission related to LER 272/95-027-00. | | c:~f/' C. Warren General Manager - |
| The commitments are as follows: A review of EDG failures since October 1992 will be performed to determine if any there were any further instances where increased EDG surveillance test frequency was required but not performed. | | Salem Operations SORC Mtg. 95-141 Attachment DVH/tcp C Distribution LER File 9512050157 951201 PDR ADOCK 05000311 S PDR 1-hl' F\t\\\T i-- in \\11;r 1r~.~: . ~*. foJJ'' I 95-2168 REV. ,6/94 |
| | |
| | Attachment A PSE&G Commitments for LER 311/95-007-00 The following items represent *PSE&G commitments made to the Nuclear Regulatory Commission related to LER 272/95-027-00. The commitments are as follows: |
| | A review of EDG failures since October 1992 will be performed to determine if any there were any further instances where increased EDG surveillance test frequency was required but not performed. |
| This review will be completed by January 31, 1996. A supplement to this LER will be provided if other EDG surveillance tests were determined to be missed. | | This review will be completed by January 31, 1996. A supplement to this LER will be provided if other EDG surveillance tests were determined to be missed. |
| NRC FORM 366 (4-95) U.S. llJCLEAR RElll.ATORY aMCISSICll LJ:CENSEE EVENT REPORT (LER) FACILITY NA1E (1) (See reverse for required nuiber of digits/characters for each block) SAUM GENERATING STATION UNIT 2 TITLE (4) | | |
| * APPROVED BY Oii NO. 3150-0104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
| | NRC FORM 366 (4-95) |
| FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33) U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON'-20555-0001, AND TO THE PAPERWORK REDUCTION DOCICET lllllER (2) PAGE (3) 05000311 1 OF 3 Missed Diesel Sm:veillan:E Required by the Technical Specifications EVENT DATE <5> MONTH DAY YEAR 05 03 90 LER lllltBER C6 , REPORT DATE C7) MONTH DAY YEAR 95 -007 -00 12 01 95 OTHER FACILITIES lllVOLVED C8l FACILITY NAME DOCKET NUMBER FACILITY NAME 05000 DOCKET NUMBER 05000 THIS REPORT JS SUBMITTED PURSUAJIT TO THE RECIJIREIEllTS OF 10 CFR §: (Check one or more) (11) G (9) 5 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(i) 50.73(a)(2)(viii P<IER LEVEL (10) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(3)(i) | | LJ:CENSEE EVENT REPORT (LER) |
| : 50. 73(a)(2)( ii) 20.2203(a)(3)(ii)
| | U.S. llJCLEAR RElll.ATORY aMCISSICll APPROVED BY Oii NO. 3150-0104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. |
| : 50. 73(a)(2)( iii) 20.2203(a)(2)(ii) 20.2203(a)(4)
| | REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD (See reverse for required nuiber of COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33) digits/characters for each block) U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON'- D~ |
| : 50. 73Ca)(2)( iv) 20.2203(a)(2)(iii) 50.36Cc)(1)
| | 20555-0001, AND TO THE PAPERWORK REDUCTION PROJE~T FACILITY NA1E (1) DOCICET lllllER (2) PAGE (3) |
| : 50. 73(a)(2)(v) 20.2203(a)(2)(iv) 50.36(c)(2) | | SAUM GENERATING STATION UNIT 2 05000311 1 OF 3 TITLE (4) |
| : 50. 73(a)(2)(vi i) LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Area Code) Mr. s. Greenlee, Operations Technical SUpport Manager 609 -339 -3500 *--C-AU_S_E | | Missed Diesel Sm:veillan:E Required by the Technical Specifications EVENT DATE <5> LER lllltBER C6 , REPORT DATE C7) OTHER FACILITIES lllVOLVED C8l FACILITY NAME DOCKET NUMBER MONTH DAY YEAR MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 05 03 90 95 - 007 - 00 12 01 95 05000 G THIS REPORT JS SUBMITTED PURSUAJIT TO THE RECIJIREIEllTS OF 10 CFR §: (Check one or more) (11) |
| __ S_Y_S_TE_M
| | (9) 5 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(i) 50.73(a)(2)(viii 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)( ii) |
| __
| | P<IER LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)( iii) 20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73Ca)(2)( iv) |
| ..... 1:--C-AU_S_E | | -::=:================:==:================::=:=================:,...~-ii:v:~~"" |
| __ S_Y_ST_E_M
| | 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 50.36Cc)(1) 50.36(c)(2) |
| __ C_OM_PON __
| | LICENSEE CONTACT FOR THIS LER (12) |
| ...... SUPPLEMENTAL REPORT EXPECTED <14l 'YES (If yes, c°""lete EXPECTED SUBMISSION DATE). EXPECTED SUBMJ SSICll DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten Lines) (16) MONTH DAY YEAR On November 1, 1995, it was detennine:i that: (1) surveillance tests for the 2A ErG were not perfonned as required on May 3 and 2_3, 1990; and (2) surveillance tests for the 2C ErG were not perfonned as required on May 7, 18, 21 and 24, 1990. '1hese surveillan:E tests were increased frequency tests required due to previous ErG valid test failures. | | : 50. 73(a)(2)(v) |
| '!he failure to perfonn these tests was discovered as a result of an ongoing Commi'bnent Verification Program. No llmoodiate ex>rrective actions were taken for this event *since the prcx:::ess for inplementin;J increased ErG surveillance test frequencies was nn:tified in October of 1992. A review of ErG failures since October 1992 will be perfonned to detennine if there were additional ErG surveillan:E tests missed. other surveillance test program; were evaluated for similar programmatic problems, and no additional problems were identified.
| | : 50. 73(a)(2)(vi i) |
| '!his event is reportable in accordance with 10 CFR 73(a)(2)(i)(B), any ex>mi.tion prohibited by the plant's Technical Specifications.
| | NAME TELEPHONE NUMBER (Include Area Code) |
| NRC FORM 366 (4-95)
| | Mr. s. Greenlee, Operations Technical SUpport Manager 609 - 339 - 3500 0 0 |
| *
| | *--C-AU_S_E_ _S_Y_S_TE_M_ _ C_OM_P_O_NE_N_T_M_A_N-UF_A_C_TU_R_ER- R~-~_ :i_:_g~-E.....1:--C-AU_S_E_ _S_Y_ST_E_M__C_OM_PON__ EN-T--MA_N_U_FA_C_T-UR_E_R_R_~_~_:_i_:g_~_E...... |
| * NRC FORM 366A (4-95) U.S. NUCLEAR REQILATORY COICISSl(JI LICENSEE EVENT REPORT (LER) '.I'filcr' aNI'INUATION FACILITY NAME C1) DOCKET LER IUtBER (6) YEAR I SEQUENTIAL I REV NUMBER NUMBER SAUM GENERATING STATION UNIT 2 05000311 95 -007 -00 TEXT Clf more space is required.
| | SUPPLEMENTAL REPORT EXPECTED <14l MONTH DAY YEAR EXPECTED YES SUBMJ SSICll (If yes, c°""lete EXPECTED SUBMISSION DATE). DATE (15) |
| use additional copies of NRC Form 366A) (17) PIAN!' AND SYSTEM IDENI'IFICATION Westir$ouse
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten Lines) (16) |
| -Pressurized Water Reactor Emergency Diesel Generator
| | On November 1, 1995, it was detennine:i that: (1) surveillance tests for the 2A ErG were not perfonned as required on May 3 and 2_3, 1990; and (2) surveillance tests for the 2C ErG were not perfonned as required on May 7, 18, 21 and 24, 1990. '1hese surveillan:E tests were increased frequency tests required due to previous ErG valid test failures. '!he failure to perfonn these tests was discovered as a result of an ongoing Commi'bnent Verification Program. |
| {EIV'I:.X;}
| | No llmoodiate ex>rrective actions were taken for this event *since the prcx:::ess for inplementin;J increased ErG surveillance test frequencies was nn:tified in October of 1992. |
| * PAGE (3) 2 OF 3 * . I e Energy Industcy Ident1f1cat1on System (EIIS) codes and component function identifier codes appear in the text as { SS/C'CC} . IDENTIFICATION OF OCClJRRENCE Event r:ates: May 3, 1990, May 7, 1990, May 18, 1990, May 21, 1990, May 23, 1990, and May 24, 1990 r:ate Dete:rmined to be Reportable:
| | A review of ErG failures since October 1992 will be perfonned to detennine if there were additional ErG surveillan:E tests missed. other surveillance test program; were evaluated for similar programmatic problems, and no additional problems were identified. |
| November 1, 1995 a::>NDITIONS PRIOR 'ID OCClJRRENCE Salem Unit 2: Mode 5, ooo % Reactor PcMer '!here were no sb:uctures, components, or systems that were inoperable at the start of the event that contributed to the event. DESCRIPITON OF OCClJRRENCE on November 1, 1995, it was dete:rmined that: (1) surveillance tests for the 2A Ea:; were not perfonned as required on May 3 and 23, 1990; and (2) sur:veillance tests for the 2C ED:; were not perfo:rm=d as required on Ma.y 7, 18, 21 and 24, 1990. 'Ihese sur:veillance tests were increased frequency tests required due to previous Ea:; valid test failures.
| | '!his event is reportable in accordance with 10 CFR 73(a)(2)(i)(B), any ex>mi.tion prohibited by the plant's Technical Specifications. |
| '!he failure to perform these tests was discovered as a result of an ongoing Connnitrnent Verification Program. '!he version of Salem Technical Specification 4.8.1.1.2 that was in effect at the time of the missed sur:veillances required that the Ea:; test frequency be as specified in Table 4. 8-1. '!his table required that follCMing a third valid test failure, the sur:veillance test frequency was to be adjusted from once per 14 days to once per 7 days, on a unit basis. FollCMing a fourth valid failure, the table required that the sur:veillance test frequency be increased to once per 3 days, also on a unit basis. FollCMing a valid failure of the 2B Ea:; on May 2, 1990 (a third valid failure), a Special Report, SR 311/90-5, was issued stating that testing of the Effis had been increased to once per seven (7) days. Contrary to the special report and the Technical Specification requirements, the 7 day sur:veillance tests were missed for the 2A Ea:; on May 3, 1990, and the 2C Ea:; on May 7, 1990. NRC FORM 366A (4-95) | | NRC FORM 366 (4-95) |
| *
| | |
| * NRC FORM 366A (4-95) u_s_ llJCLEAR REQILATORY alltISSICll LICENSEE EVENT REPORT (LER) T.E>cr' CDN!'INUATION . FACILITY NAME (1) DOCKET LER lllllER (6) YEAR I SEQUENTIAL I REV NUMBER NUMBER SAUM GENERATING STATION UNIT 2 05000311 95 -007 -00 TEXT Cif more space is required.
| | NRC FORM 366A (4-95) |
| use additional copies of NRC Form 366A> (17) DESCRIP.I'ION OF oc::x::IJRRENCE (Cont'd) PAGE (3) 3 OF 3 On May 18, 1990, another valid failure was experienced with the 2A ED:;, followed by a valid failure of the 2B ED:; on May 21, 1990. Special Report 311/90-6 identified that the smveillance frequency had been increased to once per three (3) days. contrary to the special report arrl the Technical Specification requirements, the 3 day smveillance test of the 2A ED:; was not perfonned as required on May 23, 1990. Additionally, the 3 day smveillance tests for the 2C ED:; were not perfonned a8 required on May 18, 21, arrl 24, 1990. APPARENI' CAUSE OF oc::x::IJRRENCE | | * LICENSEE EVENT REPORT (LER) |
| | '.I'filcr' aNI'INUATION |
| | * U.S. NUCLEAR REQILATORY COICISSl(JI FACILITY NAME C1) DOCKET LER IUtBER (6) PAGE (3) |
| | YEAR I SEQUENTIAL NUMBER I NUMBER REV 05000311 2 OF 3 SAUM GENERATING STATION UNIT 2 95 - 007 - 00 TEXT Clf more space is required. use additional copies of NRC Form 366A) (17) |
| | PIAN!' AND SYSTEM IDENI'IFICATION Westir$ouse - Pressurized Water Reactor Emergency Diesel Generator {EIV'I:.X;} * |
| | * Energy Industcy Ident1f1cat1on . I e System (EIIS) codes and component function identifier codes appear in the text as {SS/C'CC} . |
| | IDENTIFICATION OF OCClJRRENCE Event r:ates: May 3, 1990, May 7, 1990, May 18, 1990, May 21, 1990, May 23, 1990, and May 24, 1990 r:ate Dete:rmined to be Reportable: November 1, 1995 a::>NDITIONS PRIOR 'ID OCClJRRENCE Salem Unit 2: Mode 5, ooo % Reactor PcMer |
| | '!here were no sb:uctures, components, or systems that were inoperable at the start of the event that contributed to the event. |
| | DESCRIPITON OF OCClJRRENCE on November 1, 1995, it was dete:rmined that: (1) surveillance tests for the 2A Ea:; were not perfonned as required on May 3 and 23, 1990; and (2) sur:veillance tests for the 2C ED:; |
| | were not perfo:rm=d as required on Ma.y 7, 18, 21 and 24, 1990. 'Ihese sur:veillance tests were increased frequency tests required due to previous Ea:; valid test failures. '!he failure to perform these tests was discovered as a result of an ongoing Connnitrnent Verification Program. |
| | '!he version of Salem Technical Specification 4.8.1.1.2 that was in effect at the time of the missed sur:veillances required that the Ea:; test frequency be as specified in Table |
| | : 4. 8-1. '!his table required that follCMing a third valid test failure, the sur:veillance test frequency was to be adjusted from once per 14 days to once per 7 days, on a unit basis. FollCMing a fourth valid failure, the table required that the sur:veillance test frequency be increased to once per 3 days, also on a unit basis. |
| | FollCMing a valid failure of the 2B Ea:; on May 2, 1990 (a third valid failure), a Special Report, SR 311/90-5, was issued stating that testing of the Effis had been increased to once per seven (7) days. Contrary to the special report and the Technical Specification requirements, the 7 day sur:veillance tests were missed for the 2A Ea:; on May 3, 1990, and the 2C Ea:; on May 7, 1990. |
| | NRC FORM 366A (4-95) |
| | |
| | NRC FORM 366A (4-95) |
| | * LICENSEE EVENT REPORT (LER) |
| | T.E>cr' CDN!'INUATION |
| | * u_s_ llJCLEAR REQILATORY alltISSICll FACILITY NAME (1) DOCKET LER lllllER (6) PAGE (3) |
| | YEAR I SEQUENTIAL NUMBER I NUMBER REV SAUM GENERATING STATION UNIT 2 05000311 3 OF 3 95 - 007 - 00 TEXT Cif more space is required. use additional copies of NRC Form 366A> (17) |
| | DESCRIP.I'ION OF oc::x::IJRRENCE (Cont'd) |
| | On May 18, 1990, another valid failure was experienced with the 2A ED:;, followed by a valid failure of the 2B ED:; on May 21, 1990. Special Report 311/90-6 identified that the smveillance frequency had been increased to once per three (3) days. contrary to the special report arrl the Technical Specification requirements, the 3 day smveillance test of the 2A ED:; was not perfonned as required on May 23, 1990. Additionally, the 3 day smveillance tests for the 2C ED:; were not perfonned a8 required on May 18, 21, arrl 24, 1990. |
| | APPARENI' CAUSE OF oc::x::IJRRENCE |
| '!he exact cause of the event was not detennined due to the age of the issue. However, it appears that there was a time lag in the planning arrl scheduling process between a recognized smveillance test failure arrl the inplementation.of increased test frequency. | | '!he exact cause of the event was not detennined due to the age of the issue. However, it appears that there was a time lag in the planning arrl scheduling process between a recognized smveillance test failure arrl the inplementation.of increased test frequency. |
| Additionally, this program weakness was not recognized, so canpensato:ry actions were not taken. mIOR SIMIIAR oc::x::IJRRENCES One similar occurrence, since 1990, was identified in IER 311/90-032-00. | | Additionally, this program weakness was not recognized, so canpensato:ry actions were not taken. |
| '!his event involved a failure to perfonn required increased frequency smveillance tests for three c::orrponent cooling punps arrl a sei:vice water p..nnp. SAFRlY SIGNIFICANCE Testing of the EOOs is required to ensure that they will operate as designed to mitigate the consequences of a loss of off-site J:X:Mer. '!he successful c::x::inpletion of subsequent smveillance tests demonstrated that the EI::Gs would have functioned as required. | | mIOR SIMIIAR oc::x::IJRRENCES One similar occurrence, since 1990, was identified in IER 311/90-032-00. '!his event involved a failure to perfonn required increased frequency smveillance tests for three c::orrponent cooling punps arrl a sei:vice water p..nnp. |
| 'lherefore, the safety significance of this event was low. CDRRECI'IVE ACI'IONS '!he process for IOOdifying ED:; smveillance frequency was revised in October 1992. '!his revision was the result of observations on potential problemS with the process by the onsite Safety cammi.ttee. | | SAFRlY SIGNIFICANCE Testing of the EOOs is required to ensure that they will operate as designed to mitigate the consequences of a loss of off-site J:X:Mer. '!he successful c::x::inpletion of subsequent smveillance tests demonstrated that the EI::Gs would have functioned as required. |
| '!he new process, which is :now part of the ED:; smveillance pro:edure, requires i.nnnecliate notification of appropriate personnel so that recurring tasks can be generated prior to the next required test. A review of ED:; failures since October 1992 will be perfonned to detennine if there were any further instances where increased mx; smveillance test frequency was required but not inplemented. | | 'lherefore, the safety significance of this event was low. |
| '!his review will be c::x::inpleted by Janua:ry 31, 1996. A supplement to this IER will be provided if other ED:; smveillance tests were detennined to be missed. other smveillance test programs were evaluated for similar programmatic problems. | | CDRRECI'IVE ACI'IONS |
| No additional problems were identified. | | '!he process for IOOdifying ED:; smveillance frequency was revised in October 1992. '!his revision was the result of observations on potential problemS with the process by the onsite Safety cammi.ttee. '!he new process, which is :now part of the ED:; smveillance pro:edure, requires i.nnnecliate notification of appropriate personnel so that recurring tasks can be generated prior to the next required test. |
| O'lan;Jes in the Isr program were already inplemented to prevent similar occurrences as a result of IER 311/90-032-00. | | A review of ED:; failures since October 1992 will be perfonned to detennine if there were any further instances where increased mx; smveillance test frequency was required but not inplemented. '!his review will be c::x::inpleted by Janua:ry 31, 1996. A supplement to this IER will be provided if other ED:; smveillance tests were detennined to be missed. |
| | other smveillance test programs were evaluated for similar programmatic problems. No additional problems were identified. O'lan;Jes in the Isr program were already inplemented to prevent similar occurrences as a result of IER 311/90-032-00. |
| NRC FORM 366A (4-95)}} | | NRC FORM 366A (4-95)}} |
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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: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] |
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. Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit C*:=C 01 1995 LR-N95216 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LICENSEE EVENT REPORT 311/95-007-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed Diesel Surveillance Required by the Technical Specification is being submitted pursuant to the requirements of the Code of Federal Regulations 10 CFR5 0 . 7 3 (a) ( 2 ) ( i) .
Sincerely, (J~ {! C-1././~
c:~f/' C. Warren General Manager -
Salem Operations SORC Mtg.95-141 Attachment DVH/tcp C Distribution LER File 9512050157 951201 PDR ADOCK 05000311 S PDR 1-hl' F\t\\\T i-- in \\11;r 1r~.~: . ~*. foJJ I 95-2168 REV. ,6/94
Attachment A PSE&G Commitments for LER 311/95-007-00 The following items represent *PSE&G commitments made to the Nuclear Regulatory Commission related to LER 272/95-027-00. The commitments are as follows:
A review of EDG failures since October 1992 will be performed to determine if any there were any further instances where increased EDG surveillance test frequency was required but not performed.
This review will be completed by January 31, 1996. A supplement to this LER will be provided if other EDG surveillance tests were determined to be missed.
NRC FORM 366 (4-95)
LJ:CENSEE EVENT REPORT (LER)
U.S. llJCLEAR RElll.ATORY aMCISSICll APPROVED BY Oii NO. 3150-0104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD (See reverse for required nuiber of COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33) digits/characters for each block) U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON'- D~
20555-0001, AND TO THE PAPERWORK REDUCTION PROJE~T FACILITY NA1E (1) DOCICET lllllER (2) PAGE (3)
SAUM GENERATING STATION UNIT 2 05000311 1 OF 3 TITLE (4)
Missed Diesel Sm:veillan:E Required by the Technical Specifications EVENT DATE <5> LER lllltBER C6 , REPORT DATE C7) OTHER FACILITIES lllVOLVED C8l FACILITY NAME DOCKET NUMBER MONTH DAY YEAR MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 05 03 90 95 - 007 - 00 12 01 95 05000 G THIS REPORT JS SUBMITTED PURSUAJIT TO THE RECIJIREIEllTS OF 10 CFR §: (Check one or more) (11)
(9) 5 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(i) 50.73(a)(2)(viii 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)( ii)
P<IER LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)( iii) 20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73Ca)(2)( iv)
-::=:================:==:================::=:=================:,...~-ii:v:~~""
20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 50.36Cc)(1) 50.36(c)(2)
LICENSEE CONTACT FOR THIS LER (12)
- 50. 73(a)(2)(v)
- 50. 73(a)(2)(vi i)
NAME TELEPHONE NUMBER (Include Area Code)
Mr. s. Greenlee, Operations Technical SUpport Manager 609 - 339 - 3500 0 0
- --C-AU_S_E_ _S_Y_S_TE_M_ _ C_OM_P_O_NE_N_T_M_A_N-UF_A_C_TU_R_ER- R~-~_ :i_:_g~-E.....1:--C-AU_S_E_ _S_Y_ST_E_M__C_OM_PON__ EN-T--MA_N_U_FA_C_T-UR_E_R_R_~_~_:_i_:g_~_E......
SUPPLEMENTAL REPORT EXPECTED <14l MONTH DAY YEAR EXPECTED YES SUBMJ SSICll (If yes, c°""lete EXPECTED SUBMISSION DATE). DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten Lines) (16)
On November 1, 1995, it was detennine:i that: (1) surveillance tests for the 2A ErG were not perfonned as required on May 3 and 2_3, 1990; and (2) surveillance tests for the 2C ErG were not perfonned as required on May 7, 18, 21 and 24, 1990. '1hese surveillan:E tests were increased frequency tests required due to previous ErG valid test failures. '!he failure to perfonn these tests was discovered as a result of an ongoing Commi'bnent Verification Program.
No llmoodiate ex>rrective actions were taken for this event *since the prcx:::ess for inplementin;J increased ErG surveillance test frequencies was nn:tified in October of 1992.
A review of ErG failures since October 1992 will be perfonned to detennine if there were additional ErG surveillan:E tests missed. other surveillance test program; were evaluated for similar programmatic problems, and no additional problems were identified.
'!his event is reportable in accordance with 10 CFR 73(a)(2)(i)(B), any ex>mi.tion prohibited by the plant's Technical Specifications.
NRC FORM 366 (4-95)
NRC FORM 366A (4-95)
- LICENSEE EVENT REPORT (LER)
'.I'filcr' aNI'INUATION
- U.S. NUCLEAR REQILATORY COICISSl(JI FACILITY NAME C1) DOCKET LER IUtBER (6) PAGE (3)
YEAR I SEQUENTIAL NUMBER I NUMBER REV 05000311 2 OF 3 SAUM GENERATING STATION UNIT 2 95 - 007 - 00 TEXT Clf more space is required. use additional copies of NRC Form 366A) (17)
PIAN!' AND SYSTEM IDENI'IFICATION Westir$ouse - Pressurized Water Reactor Emergency Diesel Generator {EIV'I:.X;} *
- Energy Industcy Ident1f1cat1on . I e System (EIIS) codes and component function identifier codes appear in the text as {SS/C'CC} .
IDENTIFICATION OF OCClJRRENCE Event r:ates: May 3, 1990, May 7, 1990, May 18, 1990, May 21, 1990, May 23, 1990, and May 24, 1990 r:ate Dete:rmined to be Reportable: November 1, 1995 a::>NDITIONS PRIOR 'ID OCClJRRENCE Salem Unit 2: Mode 5, ooo % Reactor PcMer
'!here were no sb:uctures, components, or systems that were inoperable at the start of the event that contributed to the event.
DESCRIPITON OF OCClJRRENCE on November 1, 1995, it was dete:rmined that: (1) surveillance tests for the 2A Ea:; were not perfonned as required on May 3 and 23, 1990; and (2) sur:veillance tests for the 2C ED:;
were not perfo:rm=d as required on Ma.y 7, 18, 21 and 24, 1990. 'Ihese sur:veillance tests were increased frequency tests required due to previous Ea:; valid test failures. '!he failure to perform these tests was discovered as a result of an ongoing Connnitrnent Verification Program.
'!he version of Salem Technical Specification 4.8.1.1.2 that was in effect at the time of the missed sur:veillances required that the Ea:; test frequency be as specified in Table
- 4. 8-1. '!his table required that follCMing a third valid test failure, the sur:veillance test frequency was to be adjusted from once per 14 days to once per 7 days, on a unit basis. FollCMing a fourth valid failure, the table required that the sur:veillance test frequency be increased to once per 3 days, also on a unit basis.
FollCMing a valid failure of the 2B Ea:; on May 2, 1990 (a third valid failure), a Special Report, SR 311/90-5, was issued stating that testing of the Effis had been increased to once per seven (7) days. Contrary to the special report and the Technical Specification requirements, the 7 day sur:veillance tests were missed for the 2A Ea:; on May 3, 1990, and the 2C Ea:; on May 7, 1990.
NRC FORM 366A (4-95)
NRC FORM 366A (4-95)
- LICENSEE EVENT REPORT (LER)
T.E>cr' CDN!'INUATION
- u_s_ llJCLEAR REQILATORY alltISSICll FACILITY NAME (1) DOCKET LER lllllER (6) PAGE (3)
YEAR I SEQUENTIAL NUMBER I NUMBER REV SAUM GENERATING STATION UNIT 2 05000311 3 OF 3 95 - 007 - 00 TEXT Cif more space is required. use additional copies of NRC Form 366A> (17)
DESCRIP.I'ION OF oc::x::IJRRENCE (Cont'd)
On May 18, 1990, another valid failure was experienced with the 2A ED:;, followed by a valid failure of the 2B ED:; on May 21, 1990. Special Report 311/90-6 identified that the smveillance frequency had been increased to once per three (3) days. contrary to the special report arrl the Technical Specification requirements, the 3 day smveillance test of the 2A ED:; was not perfonned as required on May 23, 1990. Additionally, the 3 day smveillance tests for the 2C ED:; were not perfonned a8 required on May 18, 21, arrl 24, 1990.
APPARENI' CAUSE OF oc::x::IJRRENCE
'!he exact cause of the event was not detennined due to the age of the issue. However, it appears that there was a time lag in the planning arrl scheduling process between a recognized smveillance test failure arrl the inplementation.of increased test frequency.
Additionally, this program weakness was not recognized, so canpensato:ry actions were not taken.
mIOR SIMIIAR oc::x::IJRRENCES One similar occurrence, since 1990, was identified in IER 311/90-032-00. '!his event involved a failure to perfonn required increased frequency smveillance tests for three c::orrponent cooling punps arrl a sei:vice water p..nnp.
SAFRlY SIGNIFICANCE Testing of the EOOs is required to ensure that they will operate as designed to mitigate the consequences of a loss of off-site J:X:Mer. '!he successful c::x::inpletion of subsequent smveillance tests demonstrated that the EI::Gs would have functioned as required.
'lherefore, the safety significance of this event was low.
CDRRECI'IVE ACI'IONS
'!he process for IOOdifying ED:; smveillance frequency was revised in October 1992. '!his revision was the result of observations on potential problemS with the process by the onsite Safety cammi.ttee. '!he new process, which is :now part of the ED:; smveillance pro:edure, requires i.nnnecliate notification of appropriate personnel so that recurring tasks can be generated prior to the next required test.
A review of ED:; failures since October 1992 will be perfonned to detennine if there were any further instances where increased mx; smveillance test frequency was required but not inplemented. '!his review will be c::x::inpleted by Janua:ry 31, 1996. A supplement to this IER will be provided if other ED:; smveillance tests were detennined to be missed.
other smveillance test programs were evaluated for similar programmatic problems. No additional problems were identified. O'lan;Jes in the Isr program were already inplemented to prevent similar occurrences as a result of IER 311/90-032-00.
NRC FORM 366A (4-95)
