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| * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 211991 LR-N97184 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/97-004-00 SALEM GENERATING STATION -UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen: | | t"}7 PS~G * |
| This Licensee Event Report (LER) entitled "Inadequate Surveillance Testing of Molded Case Circuit Breakers" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a) | | * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 211991 LR-N97184 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/97-004-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen: |
| (2) (i) (B). Attachment DVH C Distribution LER File _3. 7 9703280229 970321 PDR ADOCK 05000272 S PDR Sincerely, David F.- | | This Licensee Event Report (LER) entitled "Inadequate Surveillance Testing of Molded Case Circuit Breakers" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a) (2) (i) (B). |
| General Manager Salem Operations I If llll /11/11111111111111111111111111111111111111111111 St 1
| | Sincerely, |
| * ii & 3 I St | | ~O r-:QqJ!.c~oJ David F.- ~~chow General Manager Salem Operations Attachment DVH C Distribution LER File _3. 7 9703280229 970321 PDR ADOCK 05000272 S PDR IIfllll /11/11111111111111111111111111111111111111111111 St 1 |
| * 95-2168 REV. 6/94 | | * ii & ~ 3 I St |
| --NRC fORM 366 U.S. NUCL AR REGULATORY COMMISSION AP OVED BY OMB NO. 3150-0104 . ("'r95) EXPIRES 04/30/98 . ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
| | * 95-2168 REV. 6/94 |
| FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC. 20555-0001, AND TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAllE (1) DOCKET NUMBER (2) PAGE (3) SALEM GENERATING STATION UNIT 1 05000272 1 of 3 TITLE (4)' Inadequate Surveillance Testing of Molded Case Circuit Breakers. | | |
| EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) YEAR I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER Salem, Unit 2 05000311 02 21 97 97 004 00 03 97 FACILITY NAME DOCKET NUMBER --OPERATING NA THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) | | NRC fORM 366 U.S. NUCL AR REGULATORY COMMISSION AP OVED BY OMB NO. 3150-0104 |
| : 50. 73(a)(2)(viii)
| | . ("'r95) EXPIRES 04/30/98 . |
| POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) | | ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. |
| : 50. 73(a)(2)(ii) 50.73(a)(2)(x)
| | REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC. 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) | | FACILITY NAllE (1) DOCKET NUMBER (2) PAGE (3) |
| : 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4)
| | SALEM GENERATING STATION UNIT 1 05000272 1 of 3 TITLE (4)' |
| : 50. 73(a)(2)(iv)
| | Inadequate Surveillance Testing of Molded Case Circuit Breakers. |
| OTHER 20.2203(a)(2)(iii) 50.36(c)(1) | | EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| : 50. 73(a)(2)(v)
| | MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER IREVISION NUMBER MONTH DAY YEAR FACILITY NAME Salem, Unit 2 DOCKET NUMBER 05000311 FACILITY NAME DOCKET NUMBER 02 21 97 97 - 004 - 00 03 97 OPERATING NA THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) |
| Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) | | MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii) |
| : 50. 73(a)(2)(vii)
| | POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50.73(a)(2)(x) |
| LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Area Code) Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE I CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR 'YES xlNO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spac;:ed typewritten lines) (16) During NRC inspection activities, an inadequate performance of a surveillance requirement was identified. | | LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) Spec~in Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50. 73(a)(2)(vii) |
| Technical Specification (TS) Surveillance Requirement | | LICENSEE CONTACT FOR THIS LER (12) |
| : 4. 8. 3. 1. a .*2 requires that ten percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers) required to provide thermal protection of a penetration be verified operable every 18 months. In addition, TS 4.8.3.1.b requires.each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. Contrary to these requirements an adequate verification of the required overcurrent protection devices was not performed.
| | NAME TELEPHONE NUMBER (Include Area Code) |
| Certain elements of the. protective devices were not verified, because an acceptance criterion was not specified in the procedure. | | Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS |
| | 'YES SUPPLEMENTAL REPORT EXPECTED (14) |
| | (If yes, complete EXPECTED SUBMISSION DATE). |
| | I::::::::::::::::::::::::~:~:~ |
| | xlNO EXPECTED SUBMISSION DATE (15) |
| | MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spac;:ed typewritten lines) (16) |
| | During NRC inspection activities, an inadequate performance of a surveillance requirement was identified. Technical Specification (TS) Surveillance Requirement 4. 8. 3. 1. a .*2 requires that ten percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers) required to provide thermal protection of a penetration be verified operable every 18 months. In addition, TS 4.8.3.1.b requires.each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. Contrary to these requirements an adequate verification of the required overcurrent protection devices was not performed. Certain elements of the. protective devices were not verified, because an acceptance criterion was not specified in the procedure. |
| The protection devices were adequately tested, and the test procedures were clarified to better define the TS requirements. | | The protection devices were adequately tested, and the test procedures were clarified to better define the TS requirements. |
| This event is being submitted pursuant to 10 CFR 50. 73 (2),(i) (B)' any operation or condition prohibited by TS. NRC FORM 366 (4-95) | | This event is being submitted pursuant to 10 CFR 50. 73 (2),(i) (B)' any operation or condition prohibited by TS. |
| ,, NRC FORM 366A (4-95) U. . NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) SALEM GENERATING STATION UNIT 1 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 2 97 -004 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM ID.ENTIFICATION Westinghouse
| | NRC FORM 366 (4-95) |
| - | | |
| Water Reactor 460V/230V/120V Breakers {-/BKR} | | NRC FORM 366A U. . NUCLEAR REGULATORY COMMISSION (4-95) |
| * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC} CONDITIONS PRIOR TO OCCURRENCE OF 3 At the time of identification, Salem Unit 1 was defueled and Salem Unit 2 was in Mode 5. DESCRIPTION OF OCCURRENCE During NRC inspection activities, an inadequate performance of a surveillance requirement was identified. | | ,, LICENSEE EVENT REPORT (LER) |
| Specifically, Technical Specification (TS) Surveillance Requirement 4.8.3.1.a.2 requires that ten* percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers {-/BKR}) required to provide thermal protection of containment penetrations | | TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 2 OF 3 SALEM GENERATING STATION UNIT 1 97 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| *be verified operable every 18 months. In addition, TS 4.8.3.1.b states each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. Contrary to these requirements verification of the required overcurrent protection devices was not performed. | | PLANT AND SYSTEM ID.ENTIFICATION Westinghouse - Pressuriz~d Water Reactor 460V/230V/120V Breakers {-/BKR} |
| Three distinct types of molded case circuit breakers are used at Salem Generating Station to provide thermal protection for The first type of molded case circuit breaker has a thermal element and an adjustable instantaneous trip function. | | * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC} |
| The second type of molded case circuit. breakers has a thermal element and a fixed instantaneous trip funcition. | | CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Unit 1 was defueled and Salem Unit 2 was in Mode 5. |
| The third type of molded case circuit breaker has only an adjustable .instantaneous trip function (i.e., no thermal element in the circuit breaker.) | | DESCRIPTION OF OCCURRENCE During NRC inspection activities, an inadequate performance of a surveillance requirement was identified. Specifically, Technical Specification (TS) |
| The instantaneous trip function in the third type of molded case circuit breaker was tested during surveillance testing. The thermal element of the first and second type of molded case circuit breaker was tested during surveillance testing; however, the fixed instantaneous and adjustable instantaneous trip functions for the first and second type of *molded case circuit breakers was not by the. surveillance test. CAUSE OF OCCURRENCE The station procedures accurately identified that the thermal element and the instantaneous element required testing; however, the instantaneous element was not tested, because an acceptance criterion for the instantaneous function was not accurately specified in the NRC FORM 366A (4-95)) | | Surveillance Requirement 4.8.3.1.a.2 requires that ten* percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers {-/BKR}) required to provide thermal protection of containment penetrations *be verified operable every 18 months. In addition, TS 4.8.3.1.b states each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. |
| NRC FORM 366A (4-95) U. . NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (6) SALEM GENERATING STATION UNIT 1 0 5 0 0 0 2 7 2 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 97 -004 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PRIOR SIMILAR OCCURRENCES PAGE (3) 3 OF 3 A review of LERs for Salem Units 1 and 2 issued in the last two years identified ten LERs (272/95-019, 272/96-004, 272/96-006, 272/96-008, 272/96-016, 008, 311/96-003, 311/96-007, 311/96-010 and 311/96-011) where surveillance requirements were not performed because of procedure problems. | | Contrary to these requirements ad~quate verification of the required overcurrent protection devices was not performed. |
| The identification of this programmatic issue, along with other related issues, resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER Jll/95-008. | | Three distinct types of molded case circuit breakers are used at Salem Generating Station to provide thermal protection for con~ainment pe~etrations. |
| The TSSIP should ensure that Technical Specification surveillance requirements are adequately implemented. | | The first type of molded case circuit breaker has a thermal element and an adjustable instantaneous trip function. The second type of molded case circuit. |
| | breakers has a thermal element and a fixed instantaneous trip funcition. The third type of molded case circuit breaker has only an adjustable .instantaneous trip function (i.e., no thermal element in the circuit breaker.) |
| | The instantaneous trip function in the third type of molded case circuit breaker was tested during surveillance testing. The thermal element of the first and second type of molded case circuit breaker was tested during surveillance testing; however, the fixed instantaneous and adjustable instantaneous trip functions for the first and second type of *molded case circuit breakers was not |
| | ~ested by the. surveillance test. |
| | CAUSE OF OCCURRENCE The station procedures accurately identified that the thermal element and the instantaneous element required testing; however, the instantaneous element was not tested, because an acceptance criterion for the instantaneous function was not accurately specified in the procedu~e. |
| | NRC FORM 366A (4-95)) |
| | |
| | NRC FORM 366A U. . NUCLEAR REGULATORY COMMISSION (4-95) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | SALEM GENERATING STATION UNIT 1 05 0 0 0 2 7 2 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 3 OF 3 97 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 issued in the last two years identified ten LERs (272/95-019, 272/96-004, 272/96-006, 272/96-008, 272/96-016, 311/95~ |
| | 008, 311/96-003, 311/96-007, 311/96-010 and 311/96-011) where surveillance requirements were not performed adequ~tely because of procedure problems. The identification of this programmatic issue, along with other related issues, resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER Jll/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately implemented. |
| SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences as a result of this event because the containment penetrations remained operable. | | SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences as a result of this event because the containment penetrations remained operable. |
| Redundant protection devices (e.g. fuses, circuit breakers) are installed on these circuits. | | Redundant protection devices (e.g. fuses, circuit breakers) are installed on these circuits. These redundant protection devices are reliable, therefore, a fault would likely have caused a l~ast one of the piotection devices to tiip. |
| These redundant protection devices are reliable, therefore, a fault would likely have caused a one of the piotection devices to tiip. This is supported by the testing that was performed on the devices after this event was discovered. | | This is supported by the testing that was performed on the devices after this event was discovered. The testing demonstrated that the tested circuit breaker instantaneous elements would have cleared the fault prior to exceeding the thermal capability of the penetration. |
| The testing demonstrated that the tested circuit breaker instantaneous elements would have cleared the fault prior to exceeding the thermal capability of the penetration. | | Further, the thermal element for both the fixed instantaneous trip and adjustable instantaneous trip circuit breakers were verified to be operable in accordance with the TS. The thermal element provides a measure of fault protection such that it is unlikely that a fault would have caused thermal damage to the ~lectrical penetration. |
| Further, the thermal element for both the fixed instantaneous trip and adjustable instantaneous trip circuit breakers were verified to be operable in accordance with the TS. The thermal element provides a measure of fault protection such that it is unlikely that a fault would have caused thermal damage to the penetration. | |
| The health and safety of the public was not affected. | | The health and safety of the public was not affected. |
| CORRECTIVE ACTIONS 1. For Salem Unit 2, the protection devices were adequately tested. 2. For Salem Unit 1, the protection devices will be tested prior to entry into Mode 4. 3. The common test procedure was revised to better clarify the TS requirements. | | CORRECTIVE ACTIONS |
| : 4. The Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was previously described in LER The TSSIP review is expected to be completed by December 31, 1997. NRC FORM 366A (4-95))}} | | : 1. For Salem Unit 2, the protection devices were adequately tested. |
| | : 2. For Salem Unit 1, the protection devices will be tested prior to entry into Mode 4. |
| | : 3. The common test procedure was revised to better clarify the TS requirements. |
| | : 4. The Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was previously described in LER 311/95~008-00. The TSSIP review is expected to be completed by December 31, 1997. |
| | NRC FORM 366A (4-95))}} |
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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
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- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 211991 LR-N97184 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/97-004-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen:
This Licensee Event Report (LER) entitled "Inadequate Surveillance Testing of Molded Case Circuit Breakers" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a) (2) (i) (B).
Sincerely,
~O r-:QqJ!.c~oJ David F.- ~~chow General Manager Salem Operations Attachment DVH C Distribution LER File _3. 7 9703280229 970321 PDR ADOCK 05000272 S PDR IIfllll /11/11111111111111111111111111111111111111111111 St 1
NRC fORM 366 U.S. NUCL AR REGULATORY COMMISSION AP OVED BY OMB NO. 3150-0104
. ("'r95) 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 LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC. 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAllE (1) DOCKET NUMBER (2) PAGE (3)
SALEM GENERATING STATION UNIT 1 05000272 1 of 3 TITLE (4)'
Inadequate Surveillance Testing of Molded Case Circuit Breakers.
EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER IREVISION NUMBER MONTH DAY YEAR FACILITY NAME Salem, Unit 2 DOCKET NUMBER 05000311 FACILITY NAME DOCKET NUMBER 02 21 97 97 - 004 - 00 03 97 OPERATING NA THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)
MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii)
POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) Spec~in Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50. 73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS
'YES SUPPLEMENTAL REPORT EXPECTED (14)
(If yes, complete EXPECTED SUBMISSION DATE).
I::::::::::::::::::::::::~:~:~
xlNO EXPECTED SUBMISSION DATE (15)
MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spac;:ed typewritten lines) (16)
During NRC inspection activities, an inadequate performance of a surveillance requirement was identified. Technical Specification (TS) Surveillance Requirement 4. 8. 3. 1. a .*2 requires that ten percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers) required to provide thermal protection of a penetration be verified operable every 18 months. In addition, TS 4.8.3.1.b requires.each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. Contrary to these requirements an adequate verification of the required overcurrent protection devices was not performed. Certain elements of the. protective devices were not verified, because an acceptance criterion was not specified in the procedure.
The protection devices were adequately tested, and the test procedures were clarified to better define the TS requirements.
This event is being submitted pursuant to 10 CFR 50. 73 (2),(i) (B)' any operation or condition prohibited by TS.
NRC FORM 366 (4-95)
NRC FORM 366A U. . NUCLEAR REGULATORY COMMISSION (4-95)
,, LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 2 OF 3 SALEM GENERATING STATION UNIT 1 97 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM ID.ENTIFICATION Westinghouse - Pressuriz~d Water Reactor 460V/230V/120V Breakers {-/BKR}
- 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 Unit 1 was defueled and Salem Unit 2 was in Mode 5.
DESCRIPTION OF OCCURRENCE During NRC inspection activities, an inadequate performance of a surveillance requirement was identified. Specifically, Technical Specification (TS)
Surveillance Requirement 4.8.3.1.a.2 requires that ten* percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers {-/BKR}) required to provide thermal protection of containment penetrations *be verified operable every 18 months. In addition, TS 4.8.3.1.b states each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months.
Contrary to these requirements ad~quate verification of the required overcurrent protection devices was not performed.
Three distinct types of molded case circuit breakers are used at Salem Generating Station to provide thermal protection for con~ainment pe~etrations.
The first type of molded case circuit breaker has a thermal element and an adjustable instantaneous trip function. The second type of molded case circuit.
breakers has a thermal element and a fixed instantaneous trip funcition. The third type of molded case circuit breaker has only an adjustable .instantaneous trip function (i.e., no thermal element in the circuit breaker.)
The instantaneous trip function in the third type of molded case circuit breaker was tested during surveillance testing. The thermal element of the first and second type of molded case circuit breaker was tested during surveillance testing; however, the fixed instantaneous and adjustable instantaneous trip functions for the first and second type of *molded case circuit breakers was not
~ested by the. surveillance test.
CAUSE OF OCCURRENCE The station procedures accurately identified that the thermal element and the instantaneous element required testing; however, the instantaneous element was not tested, because an acceptance criterion for the instantaneous function was not accurately specified in the procedu~e.
NRC FORM 366A (4-95))
NRC FORM 366A U. . NUCLEAR REGULATORY COMMISSION (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
SALEM GENERATING STATION UNIT 1 05 0 0 0 2 7 2 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 3 OF 3 97 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 issued in the last two years identified ten LERs (272/95-019, 272/96-004, 272/96-006, 272/96-008, 272/96-016, 311/95~
008, 311/96-003, 311/96-007, 311/96-010 and 311/96-011) where surveillance requirements were not performed adequ~tely because of procedure problems. The identification of this programmatic issue, along with other related issues, resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER Jll/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately implemented.
SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences as a result of this event because the containment penetrations remained operable.
Redundant protection devices (e.g. fuses, circuit breakers) are installed on these circuits. These redundant protection devices are reliable, therefore, a fault would likely have caused a l~ast one of the piotection devices to tiip.
This is supported by the testing that was performed on the devices after this event was discovered. The testing demonstrated that the tested circuit breaker instantaneous elements would have cleared the fault prior to exceeding the thermal capability of the penetration.
Further, the thermal element for both the fixed instantaneous trip and adjustable instantaneous trip circuit breakers were verified to be operable in accordance with the TS. The thermal element provides a measure of fault protection such that it is unlikely that a fault would have caused thermal damage to the ~lectrical penetration.
The health and safety of the public was not affected.
CORRECTIVE ACTIONS
- 1. For Salem Unit 2, the protection devices were adequately tested.
- 2. For Salem Unit 1, the protection devices will be tested prior to entry into Mode 4.
- 3. The common test procedure was revised to better clarify the TS requirements.
- 4. The Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was previously described in LER 311/95~008-00. The TSSIP review is expected to be completed by December 31, 1997.
NRC FORM 366A (4-95))
