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| {{#Wiki_filter:; I.* . NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB ND. 3150-0104 (4-95) EXPIRES 04130/98 ESTIMATED BURDEN PER RESPONSE TD COMPLY WITH THIS MANDATORY INFORMATION COUECTIOll REDDEST: 50.0 HRS. REPORTED LESSONS LEARNm ARE INCORPORATED INTO LICENSEE EVENT REPORT (LER) THE UCENSINS PROCESS AND Fm llACI TO INDUSTRY. | | {{#Wiki_filter:. |
| FORWARD COMMENTS REGARimoG BURDEN ESTIMATE TD THE INFORMATION AND RECORDS MANAGEMENT BRANCH ll-8 F331. U.S. NUCLEAR REGULATORY COMMISSllJN, WASHINGTON. | | ; I.* |
| DC 20555-0001, AllD TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT ANO BUDGET, (See reverse for required numiler of WASHINGTON. | | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB ND. 3150-0104 (4-95) EXPIRES 04130/98 ESTIMATED BURDEN PER RESPONSE TD COMPLY WITH THIS MANDATORY INFORMATION COUECTIOll REDDEST: 50.0 HRS. REPORTED LESSONS LEARNm ARE INCORPORATED INTO THE UCENSINS PROCESS AND Fm llACI TO INDUSTRY. FORWARD COMMENTS REGARimoG LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TD THE INFORMATION AND RECORDS MANAGEMENT BRANCH ll-8 F331. |
| Dt 20503. digits/characters for each block) FACILITY IAME 111 DOCKET IUMllH 121 PAGE 131 SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE 141 Inadequate Pressurizer Relief Tank Supports EVENT DATE 151 LER NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 I I FACllTY IAME DOCKET IUlllllER MOITH DAY YEAR YEH SEDUEITIAL ftEVISIOI l!OITH DAY YEAR IUlllEI I UMBER Salem, Unit 2 05000311 06 19 96 96 -010 00 07 16 96 FACll.ITYIAME DOCKET IUlllEn -OPERATING | | U.S. NUCLEAR REGULATORY COMMISSllJN, WASHINGTON. DC 20555-0001, AllD TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT ANO BUDGET, (See reverse for required numiler of WASHINGTON. Dt 20503. |
| * N THIS REPORT IS SUBMITTED PURSUANT TO THE REDUIREMENTS OF 10 CFR I: !Checkon11ormora) | | digits/characters for each block) |
| (11) MODEl91 20.22011bl 20.22031all2Jlv) 50.73(11112161 50.73(a)l2)(viii) | | FACILITY IAME 111 DOCKET IUMllH 121 PAGE 131 SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE 141 Inadequate Pressurizer Relief Tank Supports EVENT DATE 151 LER NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 FACllTY IAME DOCKET IUlllllER MOITH DAY YEAR YEH I SEDUEITIAL IUlllEI I ftEVISIOI I UMBER l!OITH DAY YEAR Salem, Unit 2 05000311 DOCKET IUlllEn 06 19 96 96 - 010 - 00 07 16 96 FACll.ITYIAME OPERATING |
| POWER 000 20.2203(11)(1) 20.2203(1Jl3llil x 50.73111J(2)6i) 50.73!all2Hxl LEVEL!1DI 20.220311112Jlil 20.2203la)(3Jfiil 50.73(1)(2Jfiiil 73.71 20.2203!all211iil 20.2203lull4J 50.73(1J(216vl x OTHER ::::::.o:.:: | | * N THIS REPORT IS SUBMITTED PURSUANT TO THE REDUIREMENTS OF 10 CFR I: !Checkon11ormora) (11) |
| 20.2203!all211iiil 50.3&1cll1J 50.731all2llvl Spm:lfy In Abstr1ct below or In :::::::::: | | MODEl91 20.22011bl 20.22031all2Jlv) 50.73(11112161 50.73(a)l2)(viii) |
| .*.*.*.w 20.2203(11)(2J6vl 50.361cll21 50.73111J(2Jlviil LICENSEE CONTACT FOR THIS LER 1121 IAME TELEPHOIE IUMIEft (llldlll1 Ano c.411 Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM COMPOIEIT MAIUFACTUREft REPORTABLE TO.IOI CAUSE IYmM COll'OIEIT MAIUFACTUIER REPORTABLE TO IPRDS ' : ;j :*. | | POWER 000 20.2203(11)(1) 20.2203(1Jl3llil x 50.73111J(2)6i) 50.73!all2Hxl LEVEL!1DI 20.220311112Jlil 20.2203la)(3Jfiil 50.73(1)(2Jfiiil 73.71 20.2203!all211iil 20.2203lull4J 50.73(1J(216vl x OTHER |
| SUPPLEMENTAL REPORT EXPECTED 1141 EXPECTED MONTH DAY YEAR IYES x IND SUBMISSION Pf yes, complete EXPECTED SUBMISSION DATE). DATE(151 ABSTRACT (Limitto 1400 spaces, i.11., approximately 15 single-spaced typBWl'itten lines) 1161 On June 19, 1996, an engineering review concluded that the pressurizer relief tank (PRT) supports are inadequate to preclude damage to the combined pressurizer safety valves discharge header. A reactor coolant system (RCS) over pressure event resulting inthe simultaneous lift of the three pressurizer safety valves.would cause the relief tank to move upward resulting in crimping the discharge header. The discharge header is the sole relief pathway for the safety valves, thus RCS overpressure protection could have reduced effectiveness. | | ::::::.o:.:: 20.2203!all211iiil 50.3&1cll1J 50.731all2llvl Spm:lfy In Abstr1ct below or In |
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| | ~rm;= ~*~&.n~~~f .*.*.*.w -~=~ 20.2203(11)(2J6vl 50.361cll21 50.73111J(2Jlviil ~~~~36~1 LICENSEE CONTACT FOR THIS LER 1121 IAME TELEPHOIE IUMIEft (llldlll1 Ano c.411 Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM COMPOIEIT MAIUFACTUREft REPORTABLE TO.IOI ~il~ CAUSE IYmM COll'OIEIT MAIUFACTUIER REPORTABLE TO IPRDS |
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| | : |
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| | SUPPLEMENTAL REPORT EXPECTED 1141 EXPECTED MONTH DAY YEAR x IND SUBMISSION IYES Pf yes, complete EXPECTED SUBMISSION DATE). DATE(151 ABSTRACT (Limitto 1400 spaces, i.11., approximately 15 single-spaced typBWl'itten lines) 1161 On June 19, 1996, an engineering review concluded that the pressurizer relief tank (PRT) supports are inadequate to preclude damage to the combined pressurizer safety valves discharge header. A reactor coolant system (RCS) over pressure event resulting inthe simultaneous lift of the three pressurizer safety valves.would cause the relief tank to move upward resulting in crimping the discharge header. The discharge header is the sole relief pathway for the safety valves, thus RCS overpressure protection could have reduced effectiveness. |
| The cause of this occurrence is that the original tank support design calculations failed to consider hydrodynamic loads on the PRT. These loads are caused by the discharge of water, bubble oscillation, and steam condensation. | | The cause of this occurrence is that the original tank support design calculations failed to consider hydrodynamic loads on the PRT. These loads are caused by the discharge of water, bubble oscillation, and steam condensation. |
| This event is reportable in accordance with 10 CFR 50.73(a) (2) (ii); any event or condition that resulted in the nuclear power plant being in a condition that was outside the basis of the plant and in accordance with 10 CFR 21. 2 ( c) . 9607230297 960716 -* --PDR ADOCK 05000272 .. s PDR NRC FORM 366 (4-951 | | This event is reportable in accordance with 10 CFR 50.73(a) (2) (ii); any event or condition that resulted in the nuclear power plant being in a condition that was outside the _d_~sig:n basis of the plant and in accordance with 10 CFR 21. 2 ( c) . |
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| * NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME ('I) SALEM GENERATING STATION UNIT 1 DOCKET NUMBER (2) LER NUMBER (6) 0 5 0 0 0 2 7 2 YEAR l SEQUENTIAL l REVISION NUMBER NUMBER 96 -010 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM IDENTIFICATION Westinghouse
| | 9607230297 960716 PDR ADOCK 05000272 |
| -Pressurized Water Reactor Reactor Coolant System Pressurizer Relief Tank Supports {RC/SPT}* | | .. |
| PAGE (3) 2 OF 3
| | NRC FORM 366 (4-951 s PDR |
| * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as (SS/CCC) CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled. | | |
| DESCRIPTION OF OCCURRENCE As a result of an unrelated review of the adequacy of support fasteners, a review of the supports for the Pressurizer Relief Tank (PRT) for both Salem units was undertaken. | | l |
| The review noted that the fastener arrangement was adequate for seismic response, however, the review identified that PRT hydrodynamic loads had not previously been considered in the PRT support design. A further review concluded that substantial upward loads could be expected during a simultaneous lift of all three safety relief valves, which could result in discharge line deformation. | | .. |
| The locked reactor coolant pump rotor and loss of turbine load accident analyses take credit for the safety relief valves operating at the same time. CAUSE OF OCCURRENCE The cause for the inadequate design of the PRT supports is a failure to consider hydrodynamic loads caused by water discharge, bubble oscillation and steam condensation. | | NRC FORM 366A (4-95) |
| Consideration of hydrodynamic loads was not incorporated in the design of Salem systems at the time of construction. | | * LICENSEE EVENT REPORT (LER) |
| PRIOR SIMILAR OCCURRENCES A review of LERs for the past two years identified one similar occurrence. | | U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION FACILITY NAME ('I) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05 00 027 2 YEAR l SEQUENTIAL NUMBER l REVISION NUMBER 2 OF 3 SALEM GENERATING STATION UNIT 1 96 - 010 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| LER 96-002 addressed an occurrence in which original plant design requirements for motor operated valves were found to be inadequate based on consideration of pressure locking and thermal binding. The corrective actions were specific to motor operated valves. NRC FORM 366A (4-95) *,:,.. ' ' | | PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Reactor Coolant System Pressurizer Relief Tank Supports {RC/SPT}* |
| .. . , ; r.=N=R=c=F=o=R=M=36=6=A=========================u=.s=.=N=u=c=L=E=A=R=R=E=G=u=L=A=T=o=R=v=c=o=M=M=1s=s=1=o=N=;i (4-95) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) SALEM GENERATING STATION UNIT 1 DOCKET NUMBER-(2) | | * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as (SS/CCC) |
| LER NUMBER (6) 0 5 0 0 0 2 7 2 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 96 -010 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) SAFETY CONSEQUENCES AND IMPLICATIONS PAGE (3) 3 OF 3 There are no safety consequences for this occurrence since neither Salem unit had experienced a simultaneous lift of the three pressurizer safety valves and the units are in a defueled status. The pressurizer sprays and the power operated relief valves (PORVs) are available to mitigate an overpressure transient. | | CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled. |
| However, these pressurizer pressure control mechanisms have been conservatively excluded from the accident analyses. | | DESCRIPTION OF OCCURRENCE As a result of an unrelated review of the adequacy of support fasteners, a review of the supports for the Pressurizer Relief Tank (PRT) for both Salem units was undertaken. The review noted that the fastener arrangement was adequate for seismic response, however, the review identified that PRT hydrodynamic loads had not previously been considered in the PRT support design. |
| Thus, while the accident analyses do not credit pressure reduction through the pressurizer spray use and PORV opening, these mechanisms will reduce the challenge to the pressurizer safety valves. Therefore, the probability of simultaneous opening of the three pressurizer safety valves is reduced, minimizing the potential for deformation of the discharge header. The public health and safety were not affected. | | A further review concluded that substantial upward loads could be expected during a simultaneous lift of all three safety relief valves, which could result in discharge line deformation. The locked reactor coolant pump rotor and loss of turbine load accident analyses take credit for the safety relief valves operating at the same time. |
| CORRECTIVE ACTIONS Revise each unit's PRT support design to withstand hydrodynamic loads and complete any required modifications for each unit prior to that unit's entry into mode 3. 10CFR21 REPORTING 10CFR21 requirements are met by this LER. NRC FORM 366A (4-95)}} | | CAUSE OF OCCURRENCE The cause for the inadequate design of the PRT supports is a failure to consider hydrodynamic loads caused by water discharge, bubble oscillation and steam |
| | ' ' |
| | condensation. Consideration of hydrodynamic loads was not incorporated in the design of Salem systems at the time of construction. |
| | PRIOR SIMILAR OCCURRENCES A review of LERs for the past two years identified one similar occurrence. LER 96-002 addressed an occurrence in which original plant design requirements for motor operated valves were found to be inadequate based on consideration of pressure locking and thermal binding. The corrective actions were specific to motor operated valves. |
| | NRC FORM 366A (4-95) |
| | *,:,.. |
| | |
| | .. |
| | ., ; r.=N=R=c=F=o=R=M=36=6=A=========================u=.s=.=N=u=c=L=E=A=R=R=E=G=u=L=A=T=o=R=v=c=o=M=M=1s=s=1=o=N=;i (4-95) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER-(2) LER NUMBER (6) PAGE (3) 05 000 27 2 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 3 OF 3 SALEM GENERATING STATION UNIT 1 96 - 010 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | SAFETY CONSEQUENCES AND IMPLICATIONS There are no safety consequences for this occurrence since neither Salem unit had experienced a simultaneous lift of the three pressurizer safety valves and the units are in a defueled status. |
| | The pressurizer sprays and the power operated relief valves (PORVs) are available to mitigate an overpressure transient. However, these pressurizer pressure control mechanisms have been conservatively excluded from the accident analyses. Thus, while the accident analyses do not credit pressure reduction through the pressurizer spray use and PORV opening, these mechanisms will reduce the challenge to the pressurizer safety valves. Therefore, the probability of simultaneous opening of the three pressurizer safety valves is reduced, minimizing the potential for deformation of the discharge header. The public health and safety were not affected. |
| | CORRECTIVE ACTIONS Revise each unit's PRT support design to withstand hydrodynamic loads and complete any required modifications for each unit prior to that unit's entry into mode 3. |
| | 10CFR21 REPORTING 10CFR21 r~porting requirements are met by this LER. |
| | NRC FORM 366A (4-95)}} |
LER 96-010-00:on 960619,identified Pressurizer Relief Tank Hydrodynamic Loads Had Not Previously Been Considered in Support Design.Caused by Failure to Consider Hydrodynamic Loads Caused by Water Discharge.Supports RevisedML18102A264 |
Person / Time |
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Site: |
Salem ![PSEG icon.png](/w/images/c/cc/PSEG_icon.png) |
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Issue date: |
07/16/1996 |
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From: |
Hassler D Public Service Enterprise Group |
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To: |
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Shared Package |
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ML18102A263 |
List: |
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References |
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LER-96-010-01, LER-96-10-1, NUDOCS 9607230297 |
Download: ML18102A264 (3) |
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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
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB ND. 3150-0104 (4-95) EXPIRES 04130/98 ESTIMATED BURDEN PER RESPONSE TD COMPLY WITH THIS MANDATORY INFORMATION COUECTIOll REDDEST: 50.0 HRS. REPORTED LESSONS LEARNm ARE INCORPORATED INTO THE UCENSINS PROCESS AND Fm llACI TO INDUSTRY. FORWARD COMMENTS REGARimoG LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TD THE INFORMATION AND RECORDS MANAGEMENT BRANCH ll-8 F331.
U.S. NUCLEAR REGULATORY COMMISSllJN, WASHINGTON. DC 20555-0001, AllD TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT ANO BUDGET, (See reverse for required numiler of WASHINGTON. Dt 20503.
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FACILITY IAME 111 DOCKET IUMllH 121 PAGE 131 SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE 141 Inadequate Pressurizer Relief Tank Supports EVENT DATE 151 LER NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 FACllTY IAME DOCKET IUlllllER MOITH DAY YEAR YEH I SEDUEITIAL IUlllEI I ftEVISIOI I UMBER l!OITH DAY YEAR Salem, Unit 2 05000311 DOCKET IUlllEn 06 19 96 96 - 010 - 00 07 16 96 FACll.ITYIAME OPERATING
- N THIS REPORT IS SUBMITTED PURSUANT TO THE REDUIREMENTS OF 10 CFR I: !Checkon11ormora) (11)
MODEl91 20.22011bl 20.22031all2Jlv) 50.73(11112161 50.73(a)l2)(viii)
POWER 000 20.2203(11)(1) 20.2203(1Jl3llil x 50.73111J(2)6i) 50.73!all2Hxl LEVEL!1DI 20.220311112Jlil 20.2203la)(3Jfiil 50.73(1)(2Jfiiil 73.71 20.2203!all211iil 20.2203lull4J 50.73(1J(216vl x OTHER
- .o:.:: 20.2203!all211iiil 50.3&1cll1J 50.731all2llvl Spm:lfy In Abstr1ct below or In
~rm;= ~*~&.n~~~f .*.*.*.w -~=~ 20.2203(11)(2J6vl 50.361cll21 50.73111J(2Jlviil ~~~~36~1 LICENSEE CONTACT FOR THIS LER 1121 IAME TELEPHOIE IUMIEft (llldlll1 Ano c.411 Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM COMPOIEIT MAIUFACTUREft REPORTABLE TO.IOI ~il~ CAUSE IYmM COll'OIEIT MAIUFACTUIER REPORTABLE TO IPRDS
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SUPPLEMENTAL REPORT EXPECTED 1141 EXPECTED MONTH DAY YEAR x IND SUBMISSION IYES Pf yes, complete EXPECTED SUBMISSION DATE). DATE(151 ABSTRACT (Limitto 1400 spaces, i.11., approximately 15 single-spaced typBWl'itten lines) 1161 On June 19, 1996, an engineering review concluded that the pressurizer relief tank (PRT) supports are inadequate to preclude damage to the combined pressurizer safety valves discharge header. A reactor coolant system (RCS) over pressure event resulting inthe simultaneous lift of the three pressurizer safety valves.would cause the relief tank to move upward resulting in crimping the discharge header. The discharge header is the sole relief pathway for the safety valves, thus RCS overpressure protection could have reduced effectiveness.
The cause of this occurrence is that the original tank support design calculations failed to consider hydrodynamic loads on the PRT. These loads are caused by the discharge of water, bubble oscillation, and steam condensation.
This event is reportable in accordance with 10 CFR 50.73(a) (2) (ii); any event or condition that resulted in the nuclear power plant being in a condition that was outside the _d_~sig:n basis of the plant and in accordance with 10 CFR 21. 2 ( c) .
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9607230297 960716 PDR ADOCK 05000272
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NRC FORM 366 (4-951 s PDR
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NRC FORM 366A (4-95)
- LICENSEE EVENT REPORT (LER)
U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION FACILITY NAME ('I) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05 00 027 2 YEAR l SEQUENTIAL NUMBER l REVISION NUMBER 2 OF 3 SALEM GENERATING STATION UNIT 1 96 - 010 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Reactor Coolant System Pressurizer Relief Tank Supports {RC/SPT}*
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear as (SS/CCC)
CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
DESCRIPTION OF OCCURRENCE As a result of an unrelated review of the adequacy of support fasteners, a review of the supports for the Pressurizer Relief Tank (PRT) for both Salem units was undertaken. The review noted that the fastener arrangement was adequate for seismic response, however, the review identified that PRT hydrodynamic loads had not previously been considered in the PRT support design.
A further review concluded that substantial upward loads could be expected during a simultaneous lift of all three safety relief valves, which could result in discharge line deformation. The locked reactor coolant pump rotor and loss of turbine load accident analyses take credit for the safety relief valves operating at the same time.
CAUSE OF OCCURRENCE The cause for the inadequate design of the PRT supports is a failure to consider hydrodynamic loads caused by water discharge, bubble oscillation and steam
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condensation. Consideration of hydrodynamic loads was not incorporated in the design of Salem systems at the time of construction.
PRIOR SIMILAR OCCURRENCES A review of LERs for the past two years identified one similar occurrence. LER 96-002 addressed an occurrence in which original plant design requirements for motor operated valves were found to be inadequate based on consideration of pressure locking and thermal binding. The corrective actions were specific to motor operated valves.
NRC FORM 366A (4-95)
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., ; r.=N=R=c=F=o=R=M=36=6=A=========================u=.s=.=N=u=c=L=E=A=R=R=E=G=u=L=A=T=o=R=v=c=o=M=M=1s=s=1=o=N=;i (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER-(2) LER NUMBER (6) PAGE (3) 05 000 27 2 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 3 OF 3 SALEM GENERATING STATION UNIT 1 96 - 010 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY CONSEQUENCES AND IMPLICATIONS There are no safety consequences for this occurrence since neither Salem unit had experienced a simultaneous lift of the three pressurizer safety valves and the units are in a defueled status.
The pressurizer sprays and the power operated relief valves (PORVs) are available to mitigate an overpressure transient. However, these pressurizer pressure control mechanisms have been conservatively excluded from the accident analyses. Thus, while the accident analyses do not credit pressure reduction through the pressurizer spray use and PORV opening, these mechanisms will reduce the challenge to the pressurizer safety valves. Therefore, the probability of simultaneous opening of the three pressurizer safety valves is reduced, minimizing the potential for deformation of the discharge header. The public health and safety were not affected.
CORRECTIVE ACTIONS Revise each unit's PRT support design to withstand hydrodynamic loads and complete any required modifications for each unit prior to that unit's entry into mode 3.
10CFR21 REPORTING 10CFR21 r~porting requirements are met by this LER.
NRC FORM 366A (4-95)