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| {{#Wiki_filter:NRC FOJIM 3&& | | {{#Wiki_filter:NRC FOJIM 3&& U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OllB 110. 3150.0104 |
| * 14-951 FACILITY IAllE 111 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LEH) (See reverse for required numbar of digit1/char11:t11rs for 111ch block) SALEM GENERATING STATION, UNIT 1 TITU 141 APPROVED BY OllB 110. 3150.0104 EXPIRES D4/3D/H ESTlllATED 1U11DE1 PBI llDPlllSE 10 CIM'l.Y Wll1I lllS IUIDllOllY llFlllllUTIOI COwmDI llEllUEIT:
| | * 14-951 EXPIRES D4/3D/H ESTlllATED 1U11DE1 PBI llDPlllSE 10 CIM'l.Y Wll1I lllS IUIDllOllY llFlllllUTIOI COwmDI llEllUEIT: 51.11 1111. llEPOllTBI LIJSOD WlllEI llE lllCOllPOlllTED m1D m LICBllllll P110CE1S Am FID IACI 10 llllUSTIIY. FOllWAID COllllEllT1 IEllAllDlllll LICENSEE EVENT REPORT (LEH) IUllDO ESTlllATE 10 THE lllFOllllllATIOI AID llECOllllS lllllGEMEIT lllAICH IT.. F33I. |
| 51.11 1111. llEPOllTBI LIJSOD WlllEI llE lllCOllPOlllTED m1D m LICBllllll P110CE1S Am FID IACI 10 llllUSTIIY. | | U.S. 1UCW1 llEGULA11HIY CllMMISSIOI. WAIHllGTlll. DC 21555-llDDI, AID 10 THE Pll'lllWlllll llEDUCTIOI PllOJECT (315'"'1141. OFFICE OF llAIAllEllEIT AID IUDGET, (See reverse for required numbar of WlllllllllOI. DC 21513. |
| FOllWAID COllllEllT1 IEllAllDlllll IUllDO ESTlllATE 10 THE lllFOllllllATIOI AID llECOllllS lllllGEMEIT lllAICH IT .. F33I. U.S. 1UCW1 llEGULA11HIY CllMMISSIOI. | | digit1/char11:t11rs for 111ch block) |
| WAIHllGTlll. | | FACILITY IAllE 111 DOCIET IUlllEI 121 PAGE !JI SALEM GENERATING STATION, UNIT 1 05000272 1 of 4 TITU 141 Surveillance For Main Steam Isolation Valves Not Performed Prior To Entry Into Mode 3 As Required By Technical Specifications EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 llOITH DAY YEAI YEAI I IEQUEITW. |
| DC 21555-llDDI, AID 10 THE Pll'lllWlllll llEDUCTIOI PllOJECT (315'"'1141. | | IUlllEI I IEYlllOI lllWEI llOITH DAY YEAI FAcanYIWE SALEM UNIT 2 DOCIET IUlllEI 05000311 FAcanYIAllE 08 22 96 96 023 00 09 20 96 OPERATING N THIS REPORT IS SUBMITTED PURSUANT TD THE REQUIREMENTS OF 10 CFR I: (Checllon1armor1) (11) |
| OFFICE OF llAIAllEllEIT AID IUDGET, WlllllllllOI. | | MODEl91 20.22011111 20.2203(1HZ11vl X 5D.73(1H2Jlil 50.7311H2HviiiJ POWER 2D.2203(1K11 2D.22D311K311il 5D.73(1HZlliiJ 5D.7311H21W LEVEL 1101 000 20.220311HZllil 20.2203(1K311iiJ 50.73(1H2Jliii) 73.71 20.2203!1HZ11iil 20.2203(11141 5D.73(1HZJlivl 2D.22D311H211iiil 5D.3&1cH11 50.73(1H2Hvl 2D.2203(1H211ivl 50.3&1cH21 50.7311HZHviiJ LICENSEE CONTACT FOR THIS LER 1121 UllE TELEPHOIE IUl8El llodd1 Ano CMll Dennis V. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 11--~"-Ul-E~+-~n-ITE-ll~-+-~COllPO~-*-u~+--llA~IUF-A_CIU_U_*~+---*~_~_:_::_._E~~'>-~CA_*_E~+--n-ITE~ll~+--COllPG---*-u~-+--llA~*~_'_CTU~U-*---1~-*ri_a_:_=_~_E---11 SUPPLEMENTAL REPORT EXPECTED 1141 EXPECTED MONTH DAY YEAR YES SUBMISSION Pf yes, complete EXPECTED SUBMISSION DATE). DATE(151 ABSTRACT !Limit to 1400 spaces, i.11., 11pproximat11ly 151ingla-spac11d typawritten lines) 1161 |
| DC 21513. DOCIET IUlllEI 121 05000272 PAGE !JI 1 of 4 Surveillance For Main Steam Isolation Valves Not Performed Prior To Entry Into Mode 3 As Required By Technical Specifications EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 llOITH DAY YEAI YEAI I IEQUEITW. | | ' |
| I IEYlllOI IUlllEI lllWEI llOITH DAY DOCIET IUlllEI FAcanYIWE SALEM UNIT 2 YEAI 05000311 08 22 96 96 023 00 09 20 96 FAcanYIAllE OPERATING N THIS REPORT IS SUBMITTED PURSUANT TD THE REQUIREMENTS OF 10 CFR I: (Checllon1armor1) | | On August 22, 1996, a review identified that Salem Units 1 and 2 have transitioned from Mode 4 to Mode 3 with Main Steam Isolation Valve Surveillance Requirement 4.7.1.5 not met within the stated surveillance interval. This is a violation of Technical Specification 4.0.4. |
| (11) MODEl91 20.22011111 20.2203(1HZ11vl X 5D.73(1H2Jlil 50.7311H2HviiiJ POWER 2D.2203(1K11 2D.22D311K311il 5D.73(1HZlliiJ 5D.7311H21W LEVEL 1101 000 20.220311HZllil 20.2203(1K311iiJ 50.73(1H2Jliii) 73.71 20.2203!1HZ11iil 20.2203(11141 5D.73(1HZJlivl 2D.22D311H211iiil 5D.3&1cH11 50.73(1H2Hvl 2D.2203(1H211ivl 50.3&1cH21 50.7311HZHviiJ LICENSEE CONTACT FOR THIS LER 1121 UllE TELEPHOIE IUl8El llodd1 Ano CMll Dennis V. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 SUPPLEMENTAL REPORT EXPECTED 1141 'YES Pf yes, complete EXPECTED SUBMISSION DATE). ABSTRACT !Limit to 1400 spaces, i.11., 11pproximat11ly 151ingla-spac11d typawritten lines) 1161 EXPECTED SUBMISSION DATE(151 MONTH DAY YEAR On August 22, 1996, a review identified that Salem Units 1 and 2 have transitioned from Mode 4 to Mode 3 with Main Steam Isolation Valve Surveillance Requirement 4.7.1.5 not met within the stated surveillance interval. | | The cause of this occurrence was determined to be inadequate review of the original Technical Specification 4.7.1.5 as compared to the Westinghouse Standard Technical Specification 4.7.1.5 in existence at the time. Corrective actions include submission of a License Change Request to revise the Technical Specifications. |
| This is a violation of Technical Specification 4.0.4. The cause of this occurrence was determined to be inadequate review of the original Technical Specification 4.7.1.5 as compared to the Westinghouse Standard Technical Specification 4.7.1.5 in existence at the time. Corrective actions include submission of a License Change Request to revise the Technical Specifications. | |
| This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications. | | This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications. |
| 9609270155 960920 PDR ADOCK 05000272 S PDR IRC FORM 316 14*95) | | 9609270155 960920 PDR ADOCK 05000272 S PDR IRC FORM 316 14*95) |
| * llRC FORM 3&&A 14-151 U.S. llUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1J DOCKET NUMBER 121 05000272 SALEM GENERATING STATION, UNIT 1 TEXT Of mare sp1c1 is required, use 1ddition1I copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse | | * llRC FORM 3&&A U.S. llUCLEAR REGULATORY COMMISSION 14-151 LICENSEE EVENT REPORT (LER) |
| -Pressurized Water Reactor Main Stearn/Main Stearn Isolation Valve {SB/V}* LER NUMBER 161 YEAI I IEDUEITIAL I -* IU*EI 11111m11 2 96 -023 -00 *Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC} CONDITIONS PRIOR TO OCCURRENCE PAGE 131 of At the time of identification, Salem Units 1 and 2 were shutdown and defueled. | | TEXT CONTINUATION FACILITY NAME (1J DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 05000272 YEAI I IEDUEITIAL IU*EI I -* |
| DESCRIPTION OF OCCURRENCE 4 On August 22, 1996, a review determined that Technical Specification Surveillance Requirement 4.7.1.5, Main Steam Isolation Valve (MSIV) Full Closure Time Test, had been performed in Mode 2. The surveillance requirement is applicable in Modes 1, 2 and 3. Entry into Mode 3, without the required surveillance completed, constitutes a violation of Technical Specification 4.0.4. The Technical Specifications do not include an exception to the provisions of Technical Specification 4.0.4 to allow entry into Modes 3 and 2 from Mode 4 for the MSIVs. Technical Specifications normally require completion of the specified surveillance test within the stated periodicity to prove operability of a safety system or component before entry into a Mode or operational condition that requires the system or component to be operable and capable of performing its required function. | | 11111m11 2 of 4 SALEM GENERATING STATION, UNIT 1 96 - 023 - 00 TEXT Of mare sp1c1 is required, use 1ddition1I copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Main Stearn/Main Stearn Isolation Valve {SB/V}* |
| However, some components cannot be adequately tested in a lower Mode or operating condition. | | *Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC} |
| Because of this, special provisions that allow entry into the applicable Mode (provided surveillances are promptly performed to verify operability) are inciuded in Technical Specifications. | | CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled. |
| This is accomplished by a specific exemption to Technical Specification 4.0.4 in the applicable Technical Specification. | | DESCRIPTION OF OCCURRENCE On August 22, 1996, a review determined that Technical Specification Surveillance Requirement 4.7.1.5, Main Steam Isolation Valve (MSIV) Full Closure Time Test, had been performed in Mode 2. The surveillance requirement is applicable in Modes 1, 2 and 3. Entry into Mode 3, without the required surveillance completed, constitutes a violation of Technical Specification 4.0.4. The Technical Specifications do not include an exception to the provisions of Technical Specification 4.0.4 to allow entry into Modes 3 and 2 from Mode 4 for the MSIVs. |
| Main Steam Isolation Valve operability testing at Salem is a specific example of the need for a provision to exempt compliance with Technical Specification 4.0.4. The steam pressure needed to properly test the valves is not available in* Mode 4, but the valves are required to be operable in Modes 1, 2 and 3. Therefore, entry into Mode 3 is necessary to test the valves. Section 10.3 of the UFSAR states that the surveillance test of the Main Stearn Isolation Valves is performed at or near 1000 psig steam pressure. | | Technical Specifications normally require completion of the specified surveillance test within the stated periodicity to prove operability of a safety system or component before entry into a Mode or operational condition that requires the system or component to be operable and capable of performing its required function. However, some components cannot be adequately tested in a lower Mode or operating condition. Because of this, special provisions that allow entry into the applicable Mode (provided surveillances are promptly performed to verify operability) are inciuded in Technical Specifications. This is accomplished by a specific exemption to Technical Specification 4.0.4 in the applicable Technical Specification. |
| The highest steam pressure available in Mode 4 is approximately 150 psig. Past practice at Salem has been to perform the test when in Mode 2 when adequate steam is available. | | Main Steam Isolation Valve operability testing at Salem is a specific example of the need for a provision to exempt compliance with Technical Specification 4.0.4. The steam pressure needed to properly test the valves is not available in* Mode 4, but the valves are required to be operable in Modes 1, 2 and 3. |
| | Therefore, entry into Mode 3 is necessary to test the valves. Section 10.3 of the UFSAR states that the surveillance test of the Main Stearn Isolation Valves is performed at or near 1000 psig steam pressure. The highest steam pressure available in Mode 4 is approximately 150 psig. Past practice at Salem has been to perform the test when in Mode 2 when adequate steam is available. |
| At present, Technical Specification 3/4.7.1.5 remains similar to its original wording which was based on Westinghouse Standard Technical Specifications. | | At present, Technical Specification 3/4.7.1.5 remains similar to its original wording which was based on Westinghouse Standard Technical Specifications. |
| Salem Specification 4.7.1.5, like the Standard Technical Specification, does not provide an exemption to Specification 4.0.4. NRC FORM 366A (4-95) lllRC FORM 366A U.S. lllUCLEAR REGULATORY COMMISSIOlll FACILITY lllAME 111 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER 121 05000272 SALEM. GENERATING STATION, UNIT 1 TEXT Pf mor111p1ce is required, use 1ddition1I copi111 of NRC Form 3&&AJ 1171 CAUSE OF OCCURRENCE LER IUMBER 161 PAGE 131 YEAI I 3 of 4 96 -023 00 The cause of this occurrence was determined to be a less than adequate review of the original Technical Specification with regard to differences from the Westinghouse Standard Technical Specifications and subsequent inadequate interpretation of Technical Specification 4.7.1.5. PRIOR' SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last .two years identified seven LERs (272/94-008, 272/95-004, 272/95-019, 272/95-028, 311/95-006, 311/95-008, .and 272/96-016) that were a result of missed surveillances due to inadequate implementation of Technical Specification requirements. | | Salem Specification 4.7.1.5, like the Standard Technical Specification, does not provide an exemption to Specification 4.0.4. |
| The corrective actions were specific to the missed surveillance issues addressed in each LER. The identification of programmatic issues related to the Technical Specification requirement
| |
| *implementation resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER 311/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Conditions for Operation.
| |
| SAFETY CONSEQUENCES AND IMPLICATIONS Although entry into Modes 3 and 2 is prohibited when the MSIV testing required by Technical Specification 4.7.1.5 had not been performed, subsequent performance of MSIV testing in Mode 2 is within the currently analyzed plant operation as discussed in UFSAR Sections 10.3 and 15.4. In the occurrences described in which Specification 4.0.4 was not met, while the Unit was in Modes 2 or 3, all of the MSIVs remained closed until testing began. During testing, only one valve is opened at any time, the other three valves remaining closed, already in the safe position, thus, had* a postulated steam line break or secondary system malfunction occurred that resulted in depressurization, isolation capability would have been maintained.
| |
| A postulated failure of the tested valve in the open position would have resulted in the blowdown of only a single steam generator since the remaining three MSIVs would have been in the closed position.
| |
| Failure of a single MSIV to close is consistent with the accident assumptions presented in UFSAR Section 15.4.2. Therefore, there was no safety significance to the improper entry into Modes 3 and 2, and the health and safety of the public remained unaffected.
| |
| NRC FORM 366A (4-95) | | NRC FORM 366A (4-95) |
| * llRC FORM 31i&A 14-151 -. . .. . FACILITY MAME 111 LICENSEE EVENT REPORT (LEH) TEXT CONTINUATION DOCKET llUMBER 121 05000272 SALEM GENERATING STATION, UNIT 1 TEXT Pf mar111p1c11 is required, use 1dditian1I copies of NRC Form 366AI 1171 CORRECTIVE ACTION U.S. llUCLEAR REGULATORY COMMISSIOll TEAi I LER llUMBER 161 IEQUEITIAl I IU*EI 96 .. 023 -* -00 PAGE 131 4 of 4 1. A License Change Request to include an exemption to the provisions of Specification 4.0.4 in Technical Specification 4.7.1.5 will be submitted to the NRC by October 4, 1996. . *-_ . 2. Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP .. program was described previously in LER 311/96-008-00.
| | |
| The TSSIP review is expected to be completed by December 31, 1997. 3. This LER will be issued to the Operations Department as required reading by September 30, 1996, to further emphasize the conservative understanding and implementation of Technical Specifications. | | lllRC FORM 366A U.S. lllUCLEAR REGULATORY COMMISSIOlll |
| | ~51 LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY lllAME 111 DOCKET NUMBER 121 LER IUMBER 161 PAGE 131 05000272 YEAI I 3 of 4 SALEM. GENERATING STATION, UNIT 1 96 - 023 00 TEXT Pf mor111p1ce is required, use 1ddition1I copi111 of NRC Form 3&&AJ 1171 CAUSE OF OCCURRENCE The cause of this occurrence was determined to be a less than adequate review of the original Technical Specification with regard to differences from the Westinghouse Standard Technical Specifications and subsequent inadequate interpretation of Technical Specification 4.7.1.5. |
| | PRIOR' SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last .two years identified seven LERs (272/94-008, 272/95-004, 272/95-019, 272/95-028, 311/95-006, 311/95-008, .and 272/96-016) that were a result of missed surveillances due to inadequate implementation of Technical Specification requirements. The corrective actions were specific to the missed surveillance issues addressed in each LER. |
| | The identification of programmatic issues related to the Technical Specification requirement *implementation resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER 311/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Conditions for Operation. |
| | SAFETY CONSEQUENCES AND IMPLICATIONS Although entry into Modes 3 and 2 is prohibited when the MSIV testing required by Technical Specification 4.7.1.5 had not been performed, subsequent performance of MSIV testing in Mode 2 is within the currently analyzed plant operation as discussed in UFSAR Sections 10.3 and 15.4. In the occurrences described in which Specification 4.0.4 was not met, while the Unit was in Modes 2 or 3, all of the MSIVs remained closed until testing began. |
| | During testing, only one valve is opened at any time, the other three valves remaining closed, already in the safe position, thus, had* a postulated steam line break or secondary system malfunction occurred that resulted in depressurization, isolation capability would have been maintained. A postulated failure of the tested valve in the open position would have resulted in the blowdown of only a single steam generator since the remaining three MSIVs would have been in the closed position. Failure of a single MSIV to close is consistent with the accident assumptions presented in UFSAR Section 15.4.2. |
| | Therefore, there was no safety significance to the improper entry into Modes 3 and 2, and the health and safety of the public remained unaffected. |
| | NRC FORM 366A (4-95) |
| | * llRC FORM 31i&A U.S. llUCLEAR REGULATORY COMMISSIOll 14-151 |
| | -. . . |
| | . LICENSEE EVENT REPORT (LEH) |
| | TEXT CONTINUATION |
| | -*- |
| | FACILITY MAME 111 DOCKET llUMBER 121 LER llUMBER 161 PAGE 131 05000272 TEAi I IEQUEITIAl IU*EI I 4 of 4 SALEM GENERATING STATION, UNIT 1 96 .. 023 00 TEXT Pf mar111p1c11 is required, use 1dditian1I copies of NRC Form 366AI 1171 CORRECTIVE ACTION |
| | : 1. A License Change Request to include an exemption to the provisions of Specification 4.0.4 in Technical Specification 4.7.1.5 will be submitted to the NRC by October 4, 1996. . *- _ . |
| | : 2. Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP .. |
| | program was described previously in LER 311/96-008-00. The TSSIP review is expected to be completed by December 31, 1997. |
| | : 3. This LER will be issued to the Operations Department as required reading by September 30, 1996, to further emphasize the conservative understanding and implementation of Technical Specifications. |
| NRC FORM 366A (4-95)}} | | NRC FORM 366A (4-95)}} |
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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: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
NRC FOJIM 3&& U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OllB 110. 3150.0104
- 14-951 EXPIRES D4/3D/H ESTlllATED 1U11DE1 PBI llDPlllSE 10 CIM'l.Y Wll1I lllS IUIDllOllY llFlllllUTIOI COwmDI llEllUEIT: 51.11 1111. llEPOllTBI LIJSOD WlllEI llE lllCOllPOlllTED m1D m LICBllllll P110CE1S Am FID IACI 10 llllUSTIIY. FOllWAID COllllEllT1 IEllAllDlllll LICENSEE EVENT REPORT (LEH) IUllDO ESTlllATE 10 THE lllFOllllllATIOI AID llECOllllS lllllGEMEIT lllAICH IT.. F33I.
U.S. 1UCW1 llEGULA11HIY CllMMISSIOI. WAIHllGTlll. DC 21555-llDDI, AID 10 THE Pll'lllWlllll llEDUCTIOI PllOJECT (315'"'1141. OFFICE OF llAIAllEllEIT AID IUDGET, (See reverse for required numbar of WlllllllllOI. DC 21513.
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FACILITY IAllE 111 DOCIET IUlllEI 121 PAGE !JI SALEM GENERATING STATION, UNIT 1 05000272 1 of 4 TITU 141 Surveillance For Main Steam Isolation Valves Not Performed Prior To Entry Into Mode 3 As Required By Technical Specifications EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 llOITH DAY YEAI YEAI I IEQUEITW.
IUlllEI I IEYlllOI lllWEI llOITH DAY YEAI FAcanYIWE SALEM UNIT 2 DOCIET IUlllEI 05000311 FAcanYIAllE 08 22 96 96 023 00 09 20 96 OPERATING N THIS REPORT IS SUBMITTED PURSUANT TD THE REQUIREMENTS OF 10 CFR I: (Checllon1armor1) (11)
MODEl91 20.22011111 20.2203(1HZ11vl X 5D.73(1H2Jlil 50.7311H2HviiiJ POWER 2D.2203(1K11 2D.22D311K311il 5D.73(1HZlliiJ 5D.7311H21W LEVEL 1101 000 20.220311HZllil 20.2203(1K311iiJ 50.73(1H2Jliii) 73.71 20.2203!1HZ11iil 20.2203(11141 5D.73(1HZJlivl 2D.22D311H211iiil 5D.3&1cH11 50.73(1H2Hvl 2D.2203(1H211ivl 50.3&1cH21 50.7311HZHviiJ LICENSEE CONTACT FOR THIS LER 1121 UllE TELEPHOIE IUl8El llodd1 Ano CMll Dennis V. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 11--~"-Ul-E~+-~n-ITE-ll~-+-~COllPO~-*-u~+--llA~IUF-A_CIU_U_*~+---*~_~_:_::_._E~~'>-~CA_*_E~+--n-ITE~ll~+--COllPG---*-u~-+--llA~*~_'_CTU~U-*---1~-*ri_a_:_=_~_E---11 SUPPLEMENTAL REPORT EXPECTED 1141 EXPECTED MONTH DAY YEAR YES SUBMISSION Pf yes, complete EXPECTED SUBMISSION DATE). DATE(151 ABSTRACT !Limit to 1400 spaces, i.11., 11pproximat11ly 151ingla-spac11d typawritten lines) 1161
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On August 22, 1996, a review identified that Salem Units 1 and 2 have transitioned from Mode 4 to Mode 3 with Main Steam Isolation Valve Surveillance Requirement 4.7.1.5 not met within the stated surveillance interval. This is a violation of Technical Specification 4.0.4.
The cause of this occurrence was determined to be inadequate review of the original Technical Specification 4.7.1.5 as compared to the Westinghouse Standard Technical Specification 4.7.1.5 in existence at the time. Corrective actions include submission of a License Change Request to revise the Technical Specifications.
This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
9609270155 960920 PDR ADOCK 05000272 S PDR IRC FORM 316 14*95)
- llRC FORM 3&&A U.S. llUCLEAR REGULATORY COMMISSION 14-151 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1J DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 05000272 YEAI I IEDUEITIAL IU*EI I -*
11111m11 2 of 4 SALEM GENERATING STATION, UNIT 1 96 - 023 - 00 TEXT Of mare sp1c1 is required, use 1ddition1I copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Main Stearn/Main Stearn Isolation Valve {SB/V}*
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC}
CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
DESCRIPTION OF OCCURRENCE On August 22, 1996, a review determined that Technical Specification Surveillance Requirement 4.7.1.5, Main Steam Isolation Valve (MSIV) Full Closure Time Test, had been performed in Mode 2. The surveillance requirement is applicable in Modes 1, 2 and 3. Entry into Mode 3, without the required surveillance completed, constitutes a violation of Technical Specification 4.0.4. The Technical Specifications do not include an exception to the provisions of Technical Specification 4.0.4 to allow entry into Modes 3 and 2 from Mode 4 for the MSIVs.
Technical Specifications normally require completion of the specified surveillance test within the stated periodicity to prove operability of a safety system or component before entry into a Mode or operational condition that requires the system or component to be operable and capable of performing its required function. However, some components cannot be adequately tested in a lower Mode or operating condition. Because of this, special provisions that allow entry into the applicable Mode (provided surveillances are promptly performed to verify operability) are inciuded in Technical Specifications. This is accomplished by a specific exemption to Technical Specification 4.0.4 in the applicable Technical Specification.
Main Steam Isolation Valve operability testing at Salem is a specific example of the need for a provision to exempt compliance with Technical Specification 4.0.4. The steam pressure needed to properly test the valves is not available in* Mode 4, but the valves are required to be operable in Modes 1, 2 and 3.
Therefore, entry into Mode 3 is necessary to test the valves. Section 10.3 of the UFSAR states that the surveillance test of the Main Stearn Isolation Valves is performed at or near 1000 psig steam pressure. The highest steam pressure available in Mode 4 is approximately 150 psig. Past practice at Salem has been to perform the test when in Mode 2 when adequate steam is available.
At present, Technical Specification 3/4.7.1.5 remains similar to its original wording which was based on Westinghouse Standard Technical Specifications.
Salem Specification 4.7.1.5, like the Standard Technical Specification, does not provide an exemption to Specification 4.0.4.
NRC FORM 366A (4-95)
lllRC FORM 366A U.S. lllUCLEAR REGULATORY COMMISSIOlll
~51 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY lllAME 111 DOCKET NUMBER 121 LER IUMBER 161 PAGE 131 05000272 YEAI I 3 of 4 SALEM. GENERATING STATION, UNIT 1 96 - 023 00 TEXT Pf mor111p1ce is required, use 1ddition1I copi111 of NRC Form 3&&AJ 1171 CAUSE OF OCCURRENCE The cause of this occurrence was determined to be a less than adequate review of the original Technical Specification with regard to differences from the Westinghouse Standard Technical Specifications and subsequent inadequate interpretation of Technical Specification 4.7.1.5.
PRIOR' SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last .two years identified seven LERs (272/94-008, 272/95-004, 272/95-019, 272/95-028, 311/95-006, 311/95-008, .and 272/96-016) that were a result of missed surveillances due to inadequate implementation of Technical Specification requirements. The corrective actions were specific to the missed surveillance issues addressed in each LER.
The identification of programmatic issues related to the Technical Specification requirement *implementation resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER 311/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Conditions for Operation.
SAFETY CONSEQUENCES AND IMPLICATIONS Although entry into Modes 3 and 2 is prohibited when the MSIV testing required by Technical Specification 4.7.1.5 had not been performed, subsequent performance of MSIV testing in Mode 2 is within the currently analyzed plant operation as discussed in UFSAR Sections 10.3 and 15.4. In the occurrences described in which Specification 4.0.4 was not met, while the Unit was in Modes 2 or 3, all of the MSIVs remained closed until testing began.
During testing, only one valve is opened at any time, the other three valves remaining closed, already in the safe position, thus, had* a postulated steam line break or secondary system malfunction occurred that resulted in depressurization, isolation capability would have been maintained. A postulated failure of the tested valve in the open position would have resulted in the blowdown of only a single steam generator since the remaining three MSIVs would have been in the closed position. Failure of a single MSIV to close is consistent with the accident assumptions presented in UFSAR Section 15.4.2.
Therefore, there was no safety significance to the improper entry into Modes 3 and 2, and the health and safety of the public remained unaffected.
NRC FORM 366A (4-95)
- llRC FORM 31i&A U.S. llUCLEAR REGULATORY COMMISSIOll 14-151
-. . .
. LICENSEE EVENT REPORT (LEH)
TEXT CONTINUATION
-*-
FACILITY MAME 111 DOCKET llUMBER 121 LER llUMBER 161 PAGE 131 05000272 TEAi I IEQUEITIAl IU*EI I 4 of 4 SALEM GENERATING STATION, UNIT 1 96 .. 023 00 TEXT Pf mar111p1c11 is required, use 1dditian1I copies of NRC Form 366AI 1171 CORRECTIVE ACTION
- 1. A License Change Request to include an exemption to the provisions of Specification 4.0.4 in Technical Specification 4.7.1.5 will be submitted to the NRC by October 4, 1996. . *- _ .
- 2. Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP ..
program was described previously in LER 311/96-008-00. The TSSIP review is expected to be completed by December 31, 1997.
- 3. This LER will be issued to the Operations Department as required reading by September 30, 1996, to further emphasize the conservative understanding and implementation of Technical Specifications.
NRC FORM 366A (4-95)