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| | issue date = 03/31/1999 | | | issue date = 03/31/1999 |
| | title = LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr | | | title = LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr |
| | author name = MECREDY R C, ST MARTIN J T | | | author name = Mecredy R, St Martin J |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:'ATEGORYREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9904080027 DOC.DATE: | | {{#Wiki_filter:'ATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 99/03/31NOTARIZED: | | ACCESSION NBR:9904080027 DOC.DATE: 99/03/31 NOTARIZED: NO( DOCKET SCIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 |
| NO(SCIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G,'AUTH.NAME.AUTHORAFFILIATION | | ,'AUTH. NAME . AUTHOR AFFILIATION |
| .ST.MARTIN,J.T. | | .ST. MARTIN,J.T. Rochester Gas &, Electric Corp. |
| Rochester Gas&,ElectricCorp.MECREDY,R.C. | | MECREDY,R.C. Rochester Gas & Electric Corp. |
| Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000244VISSING,G.S. | | RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. |
| CAQ050002440NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | C |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER99-003-00:on 990301,two mainsteamnon-return checkvalvesweredeclaredinoperable duetoexceedance ofacceptance criteria.
| | LER 99-003-00:on 990301,two main steam non-return check valves were declared inoperable due to exceedance of A acceptance criteria. Caused by changes in m'ethodology & |
| Causedbychangesinm'ethodology
| | matls.Packing gland torque will be adjusted. With 990331 ltr. |
| &matls.Packing glandtorquewillbeadjusted.
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR I ENCL ( SIZE: |
| With990331ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| LTRIENCL(SIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.RECIPIENT IDCODE/NAME PD1-1PDINTERNAL:
| | Q NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 0 |
| AEODRAB~ENZNRR/DRCH/HQMB NRR/DSSA/SPLB RGN1FILE01EXTERNAL:
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 VISSING,G. ,1 1 INTERNAL: AEOD RAB 2 2 AEOD/SPD/RRAB RES/DET/EIB 1 1 |
| LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL112211111111111111RECIPIENT IDCODE/NAME VISSING,G.
| | ~ENZ 1 1 NRR/DRCH/HOHB 1 1 |
| AEOD/SPD/RRAB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB LMITCOMARSHALLNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL,1111111'11111111DNNOTETOALL"RZDS"RECIPZENTS: | | NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 NRR/DSSA/SPLB 1 1 1 1 RGN1 FILE 01 1 1 D |
| PLEASEHELPUSTOREDUCEHASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 N |
| LTTR18ENCL18 III ANDgM~giESTH CASli'gD".'E~ICRFC&Crv~89&54~=.S"E'C."$
| | NOTE TO ALL "RZDS" RECIPZENTS: |
| 5'.7V'Sa-'-.sg',i+CE.';6Ac-27KMarch31,1999U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirecto'rate I-1Washington, D.C.20555 | | PLEASE HELP US TO REDUCE HASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 18 |
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| | I I |
| | I |
| | |
| | AND gM~giESTH CAS li'gD ".'E~IC RFC& Crv ~ 89 &5 4~=.S"E'C."$ 5'. 7 V' Sa-'- .sg', i+CE.';6 Ac-27K March 31, 1999 U. S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directo'rate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| LER1999-003, TwoValvesDeclaredInoperable ResultsinCondition Prohibited byTechnical Specifications R.E.GinnaNuclearPowerPlantDocketNo.50-244
| | LER 1999-003, Two Valves Declared Inoperable Results in Condition Prohibited by Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Vissing:== |
| | |
| | The attached Licensee Event Report LER 1999-003 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (B), "Any operation or condition prohibited by the plant's Technical Specifications". |
| | Ver truly yours, Robert C. Mecred xc: Mr. Guy S. Vissing (Mail Stop SC2) |
| | Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector 9904080027 99033i PDR ADOCK 05000244 8 PDR |
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| | 0 I |
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| | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION IB ISSSI fN5lt'a Jeep r rVp Be'I'o'N'gAL(s%88P' information coaction request: 50 hrs. Reported lessons learned are incorporated into the licensing process and fed back to LICENSEE EVENT REPORT (LER) industry. Forward comments regarding burden estimate to the Records Management Branch (TA F33). U.S. Nudear Regulatory Commission, Washington, DC 205554001. and to (See reverse for required number of the Paperwork Reduction project (31504I04), Office of digits/characters for each block) Management and Budget, Washington, DC 20503. If an . |
| | information coBection does not display a cunently valid OMB control number, the NRC may not conduct or sponsor. and a FACILITY NAME I11 DocKET NUMBER I2I PAGE (3) |
| | R. E. Ginna Nuclear Power Plant 05000244 1 OF 6 TITLE (el Two Valves Declared Inoperable Results in Condition Prohibited by Technical Specifications EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| | SEOUENTIAL REYISION FACIUTY NAME DOCKET NUMBER MONTH OAY YEAR MONTH OAY NUMBER NUMBER 05000 03 01 1999 1999 - 003 00 03 31 1999 FACIUTY NAME DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED P URSUANT TO THE REQUIREMENTS OF 10 CFR E: (Check one or morel (11) |
| | MODE (9) 20.2201(b) 20.2203(a) (2) (v) X 50.73(a)(2)(i)(B) 50.73(a) (2)(viii) |
| | POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50 73(a)(2)(u) 50.73(a) (2) (x) |
| | LEVEL (10) 0 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) Specify ln Abstract below 20.2203(a) (2) (iv) 50.36(c)(2) 50.73(a)(2)(vii) or in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12) |
| | NAME TELEPHONE NUMBER (rneivde Aree Cadet John T. St. Martin - Technical Assistant (716) 771-3641 CAUSE REPORTABIE REPORTABlE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT TO EPIX MANUFACTURER TO EPIX SUPPLEMEIITAL REPORT EXPECTED (14) MONTH OAT EXPECTED YES SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). X No DATE (15) |
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
| | On March 1, 1999, at approximately 1707 EST, it was determined that the required torque to initiate valve disc closure for the two main steam non-return check valves was greater than the acceptance criteria specified in plant test procedures. |
| | Immediate corrective action was to declare both valves inoperable and enter Technical Specification Limiting Operation 3.0.3. Following an evaluation of the test data by Nuclear Engineering Services, it was determined that Condition'or the valves were oper'able. The plant exited Limiting Condition for Operation 3.0.3. |
| | The underlying cause of the event was changes in the methodology and materials for packing these valves, which resulted in a greater than anticipated shaft breakaway torque. |
| | Corrective action to prevent recurrence is outlined in Section V.B. |
| | |
| | 1 NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION IB 1999) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION |
| | 'ACILITYNAME I1) DOCKET l2) LER NUMBER I6I PAGE (3I SMUENTIAL RBBBIBN NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 1999 - 003 - 00 2 OF 6 TEXT (Ifmore space is required, use additional copies of NRC Form 366A/ I17) |
| | PRE-EVENT PLANT CONDITIONS: |
| | Since 1992, Performance Monitoring technicians have performed surveillance test procedure PT-2.10.15, "Main Steam Non-Return Check Valve Closure Verification", using the test methodology established by Nuclear Engineering Services (NES). Performance of test procedure PT-2.10.15 satisfies Ginna Station Improved Technical Specifications (ITS) Surveillance Requirement (SR) 3.7.2.2 and satisfies the requirements of Section XI of the ASME Code for these valves. The required torque to initiate valve disc closure (breakaway torque) for the main steam non-return check valves (CV-3518 and CV-3519) has consistently been measured significantly lower than the acceptance criteria specified within the test procedure (600 ft-lbs). |
| | On March 1, 1999, the plant was in Mode 3, cooling down to Mode 4 for a scheduled refueling outage. |
| | Both main steam isolation valves (MSIVs) were closed. At approximately 1707 EST, Performance Monitoring technicians were performing procedure PT-2.10.15. The technicians were utilizing a calibrated torque wrench with a range of 0 to 600 ft-lbs, as they had in previous years. The technicians could not initiate valve disc closure (achieve breakaway torque), even at the full range of the torque wrench. They consulted'with supervision, and initiated a plant ACTION'Report to document the inability to achieve check valve disc movement up to 600 ft-Ibs of torque. |
| | DESCRIPTIOA OF EVENT: |
| | A. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES: |
| | March 1, 1999, 1707 EST: Event Date and Time and Discovery Date and Time. |
| | March 1, 1999, .1 734 EST: Both main steam non-return check valves are declared inoperable. |
| | 0 March 1, 1999, 1930 EST: Engineering Technical Evaluation determines that both main steam non-return check valves are operable. |
| | March 1, 1999, 2018 EST: The Plant enters Mode 4, where ITS LCO 3.7.2 is not applicable. ITS LCO 3.0.3 for the main steam non-return check valves is exited. |
| | B. EVENT: |
| | On March 1, 1999, the plant was in Mode 3, cooling down to Mode 4 for a scheduled refueling outage. Both main steam isolation valves (MSIVs) were closed, as specified by the Initial Conditions for test procedure PT-2.10.15. The Performance Monitoring technicians notified the Shift Supervisor of the failure of the main steam non-return check valves to meet the closure torque acceptance criteria of test procedure PT-2.10.15. |
| | |
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6 IBBS) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION |
| | 'ACILITYNAME (1) DOCKET (2) LER NUMBER (6) PAGE (3) |
| | SEOUENTIAL RENSION TEAR NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 1999 - OO3 3 OF 6 TEXT llfmore spaceis required, use additional copies of NRC Form 366Al (17) |
| | The Shift Supervisor reviewed ITS Limiting Condition for Operation (LCO) 3.7.2, notified the NES staff of the 'event, and requested an engineering technical evaluation. At approximately 1734 EST the Shift Supervisor declared both valves CV-3518 and CV-3519 inoperable based on exceeding the acceptance criteria of test procedure PT-2.10.15. As specified in ITS LCO Required Action 3.7.2.E.1, with "one or more valves inoperable in flowpath from each steam generator (SG)", |
| | immediate entry into ITS LCO 3.0.3 is required. The Shift Supervisor directed entry into ITS LCO 3.0.3 at this time. |
| | Performance Monitoring technicians obtained a torque wrench of larger range and again attempted to achieve breakaway torque. At approximately 700 ft-Ibs torque, the valve d(sc for CV-3518 started to close, and at approximately 900 ft-Ibs torque the valve disc for CV-3519 started to close. |
| | These as-found breakaway torque values were provided to NES staff. |
| | NES staff performed an engineering technical evaluation of this event. At approximately 1930 EST, NES staffhadreviewed an engineering analysis (Design'Analysis DA-ME-92-147) that had been performed previously for these valves, and determined that the as-found breakaway torque was within the bounds of the analysis. This information was provided to the Shift Supervisor. |
| | While the valves were now capable of being declared operable, the plant continued the planned cooldown and entered Mode 4 at approximately 2018 EST on March 1, 1999. In Mode 4, ITS LCO 3.7.2 is not applicable, and ITS LCO 3.0.3 was formally exited at this time. |
| | The entry into ITS LCO 3.0.3 as a result of declaring both CV-3518 and CV-3519 inoperable is considered to be a condition prohibited by Technical Specifications. Entry into ITS LCO 3.0.3 for any reason or justification is considered reportable per the NRC guidance in NUREG-1022 Revision 1. |
| | INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: |
| | None D.,OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED: |
| | None E. METHOD OF DISCOVERY: |
| | This event was discovered by Performance Monitoring technicians who were performing a routine surveillance test during the plant cooldown. |
| | |
| | . ~ |
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (B IBBB) |
| | LICENSEE EVENT REPORT (LERj TEXT CONTINUATION FACILITY NAME (1) DOCKET (2) LER NUMBER (6) PAGE (3) |
| | SEOUENTIAE REVISION VEAR NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 1999 003 - 00 4 OF 6 TEXT ilfmore space is required, use additional copies of NRC Form 366Al (17) |
| | OPERATOR ACTION: |
| | The Shift Supervisor reviewed ITS LCO 3.7.2 and declared both valves CV-3518 and CV-3519 inoperable based on exceeding the acceptance criteria of test procedure PT-2.10.15. The Shift Supervisor directed entry into ITS LCO 3.0.3 at this time. The Shift Supervisor notified NES staff of the event, and requested an engineering technical evaluation. The operators continued the process of performing a plant cooldown per operating procedure 0-2.2, "Plant Shutdown from Hot Shutdown to Cold Conditions". |
| | After the plant was in Mode 4, ITS LCO 3.7.2 was not applicable and LCO 3.0.3 was exited for the main steam non-return check valves. |
| | G. SAFETY SYSTEM RESPONSES: |
| | None III. CAUSE OF EVENT: |
| | A. IMMEDIATECAUSE: |
| | The immediate cause of the condition prohibited by Technical Specifications was entering ITS LCO Required Action 3.7.2.E.1 for two valves inoperable, which required immediate entry into ITS LCO. |
| | 3.0.3. |
| | B. INTERMEDIATE CAUSE: |
| | The intermediate cause of entry into ITS LCO 3.7.2.E.1 was the decision to declare both main steam non-return check valves inoperable for exceeding the acceptance criteria of Steps 6.1.3 and 6.2.3 of test procedure PT-2.10.15. |
| | ROOT CAUSE: |
| | The underlying cause for exceeding the acceptance criteria was changes in the methodology and materials for packing these valves, instituted during the previous outage. These changes in methodology and vendor-recommended replacement shaft bushing materials were made in order to provide improved shaft sealability and vibration mitigation, and resulted in a greater than anticipated shaft breakaway torque. Over time, during the previous plant operating cycle, heat and moisture were absorbed by the packing, which caused the shaft friction to increase to the as-found values of 700 and 900 ft-lbs, which were higher than anticipated, based on testing results from previous years. |
| | |
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (B.IBBS) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME I1) DOCKET I2) LER NUMBER I6) PAGE I3) |
| | SEQUENTIAL REVISION YEAR NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 I 999 003 00 5 OF 6 TEXT (Ifmore spaceis required, use additional copies of ftlRC Form 366A/ I17) |
| | IV. ANALYSIS OF EVENT: |
| | This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) |
| | (8), "Any operation or condition prohibited by the plant's Technical Specifications". Declaring both main steam non-return check valves inoperable resulted in entry into ITS LCO 3.0.3. Since the plant entered ITS LCO 3.0.3, this condition is reportable. |
| | An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions: |
| | There were no operational or safety consequences attributed to not meeting the acceptance criteria specified in procedure PT-2.10.15 because: |
| | o The acceptance criteria in test procedure PT-2.10.15 was conservatively chosen in 1992 to be well below the value calculated in Design Analysis DA-ME-92-147. This conservative value had been utilized as the acceptance criteria in test procedure PT-2.10.15, prior to defining the operability requirements in ITS SR 3.7.2.2. The engineering technical evaluation performed on March 1, 1999, determined that the as-found breakaway torque values for the non-return check valves were within this previous analysis. |
| | o The two MSIVs isolate steam flow from the secondary side of the steam generators (SGs) following a Design Basis Accident (DBA). Both MSIVs were closed, as specified in the Initial Conditions of test procedure PT-2.10.15, prior to initiation of the surveillance test on March 1, 1999. The MSIVs are designed to work with the main steam non-return check valves, located immediately downstream of each MSIV, to preclude the blowdown of more than one SG following a steam line break (SLB). |
| | Based on the above, it can be concluded that the public's health and safety was assured at all times. |
| | V. CORRECTIVE ACTION: |
| | A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS: |
| | Immediate corrective action was to declare both valves inoperable and enter ITS LCO 3.0.3. |
| | Following an evaluation of the test data by NES, it was determined that the valves were operable. |
| | The plant exited ITS LCO 3.0.3. |
| | The plant is still in the 1999 refueling outage. |
|
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| ==DearMr.Vissing:==
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (61998) |
| TheattachedLicenseeEventReportLER1999-003issubmitted inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(i)(B),"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications".
| | LICENSEE EVENT REPORT (LER) |
| Vertrulyyours,RobertC.Mecredxc:Mr.GuyS.Vissing(MailStopSC2)ProjectDirectorate I-1DivisionofReactorProjects-I/IIOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555RegionalAdministrator, RegionIU.S.NuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector 9904080027 99033iPDRADOCK050002448PDR 0I NRCFORM366IBISSSIU.S.NUCLEARREGULATORY COMMISSION FACILITYNAMEI11R.E.GinnaNuclearPowerPlantLICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)PAGE(3)1OF6DocKETNUMBERI2I05000244fN5lt'aJeeprrVpBe'I'o'N'gAL(s%88P' information coactionrequest:50hrs.Reportedlessonslearnedareincorporated intothelicensing processandfedbacktoindustry.
| | TEXT CONTINUATION FACILITY NAME (1) DOCKET (2) LER NUMBER (6) PAGE (3) 9(RU(N(IAL RENSIOII IIUMBIR R.E. Ginna Nuclear Power Plant 05000244 1999 - 003 - 00 6 OF 6 TEXT llfmore space is required, use additional copies of NRC Form 366A/ (17) |
| Forwardcommentsregarding burdenestimatetotheRecordsManagement Branch(TAF33).U.S.NudearRegulatory Commission, Washington, DC205554001.
| | B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE o Packing gland torque for these check valves will be adjusted to a value specified by the IST Engineer. An as-found baseline breakaway torque value will be obtained for each valve during the 1999 outage. |
| andtothePaperwork Reduction project(31504I04),
| | 0 The design analysis will be revised to provide acceptance criteria, both for the ASME Code degradation value and for determination of valve operability. |
| OfficeofManagement andBudget,Washington, DC20503.Ifan.information coBection doesnotdisplayacunentlyvalidOMBcontrolnumber,theNRCmaynotconductorsponsor.andaTITLE(elTwoValvesDeclaredInoperable ResultsinCondition Prohibited byTechnical Specifications EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTHOAYYEARSEOUENTIAL REYISIONNUMBERNUMBERMONTHOAYFACIUTYNAMEDOCKETNUMBER050000301OPERATING MODE(9)POWERLEVEL(10)199901999-003-0003311999FACIUTYNAME20.2201(b) 20.2203(a)(1) 20.2203(a)(2)
| | I A "reference value" will be established in accordance with ASME/ANSI OM-1987 Part 10 for breakaway torque for these valves. This value will be included in a future revision to test procedure PT-2.10.1 5. |
| (i)20.2203(a)(2)(ii) 20.2203(a)(2) | | VI. ADDITIONALINFORMATION: |
| (iii)20.2203(a)
| | A. FAILED"COMPONENTS: |
| (2)(iv)20.2203(a)
| | None B. PREVIOUS LERs ON SIMILAR EVENTS: |
| (2)(v)20.2203(a)(3)(i) 20.2203(a)
| | A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Nuclear Power Plant could be identified. |
| (3)(ii)20.2203(a)(4) 50.36(c)(1) 50.36(c)(2) | | C. SPECIAL COMMENTS: |
| X50.73(a)(2)(i)(B) 5073(a)(2)(u) 50.73(a)(2)(iii)50.73(a)(2)(iv) 50.73(a)(2)
| | None |
| (v)50.73(a)(2)(vii)
| |
| THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFRE:(CheckDOCKETNUMBER05000oneormorel(11)50.73(a)(2)(viii) 50.73(a)(2)(x)73.71OTHERSpecifylnAbstractbeloworinNRCForm366ANAMEJohnT.St.Martin-Technical Assistant LICENSEECONTACTFORTHISLER(12)TELEPHONE NUMBER(rneivdeAreeCadet(716)771-3641CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABIE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABlE TOEPIXSUPPLEMEIITAL REPORTEXPECTED(14)YES(Ifyes,completeEXPECTEDSUBMISSION DATE).XNoEXPECTEDSUBMISSION DATE(15)MONTHOATABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnMarch1,1999,atapproximately 1707EST,itwasdetermined thattherequiredtorquetoinitiatevalvediscclosureforthetwomainsteamnon-return checkvalveswasgreaterthantheacceptance criteriaspecified inplanttestprocedures.
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| Immediate corrective actionwastodeclarebothvalvesinoperable andenterTechnical Specification LimitingCondition'or Operation 3.0.3.Following anevaluation ofthetestdatabyNuclearEngineering
| |
| : Services, itwasdetermined thatthevalveswereoper'able.
| |
| TheplantexitedLimitingCondition forOperation 3.0.3.Theunderlying causeoftheeventwaschangesinthemethodology andmaterials forpackingthesevalves,whichresultedinagreaterthananticipated shaftbreakaway torque.Corrective actiontopreventrecurrence isoutlinedinSectionV.B.
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| 1 NRCFORM366AIB1999)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION
| |
| 'ACILITYNAMEI1)R.E.GinnaNuclearPowerPlantDOCKETl2)05000244LERNUMBERI6ISMUENTIAL RBBBIBNNUMBERNUMBER1999-003-00PAGE(3I2OF6TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A/I17)PRE-EVENT PLANTCONDITIONS:
| |
| Since1992,Performance Monitoring technicians haveperformed surveillance testprocedure PT-2.10.15, "MainSteamNon-Return CheckValveClosureVerification",
| |
| usingthetestmethodology established byNuclearEngineering Services(NES).Performance oftestprocedure PT-2.10.15 satisfies GinnaStationImprovedTechnical Specifications (ITS)Surveillance Requirement (SR)3.7.2.2andsatisfies therequirements ofSectionXIoftheASMECodeforthesevalves.Therequiredtorquetoinitiatevalvediscclosure(breakaway torque)forthemainsteamnon-return checkvalves(CV-3518andCV-3519)hasconsistently beenmeasuredsignificantly lowerthantheacceptance criteriaspecified withinthetestprocedure (600ft-lbs).OnMarch1,1999,theplantwasinMode3,coolingdowntoMode4forascheduled refueling outage.Bothmainsteamisolation valves(MSIVs)wereclosed.Atapproximately 1707EST,Performance Monitoring technicians wereperforming procedure PT-2.10.15.
| |
| Thetechnicians wereutilizing acalibrated torquewrenchwitharangeof0to600ft-lbs,astheyhadinpreviousyears.Thetechnicians couldnotinitiatevalvediscclosure(achievebreakaway torque),evenatthefullrangeofthetorquewrench.Theyconsulted'with supervision, andinitiated aplantACTION'Report todocumenttheinability toachievecheckvalvediscmovementupto600ft-Ibsoftorque.DESCRIPTIOA OFEVENT:A.DATESANDAPPROXIMATE TIMESOFMAJOROCCURRENCES:
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| March1,1999,1707EST:EventDateandTimeandDiscovery DateandTime.March1,1999,.1734EST:Bothmainsteamnon-return checkvalvesaredeclaredinoperable.
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| 0March1,1999,1930EST:Engineering Technical Evaluation determines thatbothmainsteamnon-return checkvalvesareoperable.
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| March1,1999,2018EST:ThePlantentersMode4,whereITSLCO3.7.2isnotapplicable.
| |
| ITSLCO3.0.3forthemainsteamnon-return checkvalvesisexited.B.EVENT:OnMarch1,1999,theplantwasinMode3,coolingdowntoMode4forascheduled refueling outage.Bothmainsteamisolation valves(MSIVs)wereclosed,asspecified bytheInitialConditions fortestprocedure PT-2.10.15.
| |
| ThePerformance Monitoring technicians notifiedtheShiftSupervisor ofthefailureofthemainsteamnon-return checkvalvestomeettheclosuretorqueacceptance criteriaoftestprocedure PT-2.10.15.
| |
| NRCFORM366A(6IBBS)U.S.NUCLEARREGULATORY COMMISSION
| |
| 'ACILITYNAME(1)R.E.GinnaNuclearPowerPlantDOCKET(2)05000244LERNUMBER(6)TEARSEOUENTIAL RENSIONNUMBERNUMBER1999-OO3LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PAGE(3)3OF6TEXTllfmorespaceisrequired, useadditional copiesofNRCForm366Al(17)TheShiftSupervisor reviewedITSLimitingCondition forOperation (LCO)3.7.2,notifiedtheNESstaffofthe'event,andrequested anengineering technical evaluation.
| |
| Atapproximately 1734ESTtheShiftSupervisor declaredbothvalvesCV-3518andCV-3519inoperable basedonexceeding theacceptance criteriaoftestprocedure PT-2.10.15.
| |
| Asspecified inITSLCORequiredAction3.7.2.E.1, with"oneormorevalvesinoperable inflowpathfromeachsteamgenerator (SG)",immediate entryintoITSLCO3.0.3isrequired.
| |
| TheShiftSupervisor directedentryintoITSLCO3.0.3atthistime.Performance Monitoring technicians obtainedatorquewrenchoflargerrangeandagainattempted toachievebreakaway torque.Atapproximately 700ft-Ibstorque,thevalved(scforCV-3518startedtoclose,andatapproximately 900ft-IbstorquethevalvediscforCV-3519startedtoclose.Theseas-foundbreakaway torquevalueswereprovidedtoNESstaff.NESstaffperformed anengineering technical evaluation ofthisevent.Atapproximately 1930EST,NESstaffhadreviewed anengineering analysis(Design'Analysis DA-ME-92-147) thathadbeenperformed previously forthesevalves,anddetermined thattheas-foundbreakaway torquewaswithintheboundsoftheanalysis.
| |
| Thisinformation wasprovidedtotheShiftSupervisor.
| |
| Whilethevalveswerenowcapableofbeingdeclaredoperable, theplantcontinued theplannedcooldownandenteredMode4atapproximately 2018ESTonMarch1,1999.InMode4,ITSLCO3.7.2isnotapplicable, andITSLCO3.0.3wasformallyexitedatthistime.TheentryintoITSLCO3.0.3asaresultofdeclaring bothCV-3518andCV-3519inoperable isconsidered tobeacondition prohibited byTechnical Specifications.
| |
| EntryintoITSLCO3.0.3foranyreasonorjustification isconsidered reportable pertheNRCguidanceinNUREG-1022 Revision1.INOPERABLE STRUCTURES, COMPONENTS, ORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:NoneD.,OTHERSYSTEMSORSECONDARY FUNCTIONS AFFECTED:
| |
| NoneE.METHODOFDISCOVERY:
| |
| Thiseventwasdiscovered byPerformance Monitoring technicians whowereperforming aroutinesurveillance testduringtheplantcooldown.
| |
| .~
| |
| NRCFORM366A(BIBBB)LICENSEEEVENTREPORT(LERjTEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)DOCKET(2)LERNUMBER(6)PAGE(3)R.E.GinnaNuclearPowerPlant05000244VEARSEOUENTIAE REVISIONNUMBERNUMBER1999-003-004OF6TEXTilfmorespaceisrequired, useadditional copiesofNRCForm366Al(17)OPERATORACTION:TheShiftSupervisor reviewedITSLCO3.7.2anddeclaredbothvalvesCV-3518andCV-3519inoperable basedonexceeding theacceptance criteriaoftestprocedure PT-2.10.15.
| |
| TheShiftSupervisor directedentryintoITSLCO3.0.3atthistime.TheShiftSupervisor notifiedNESstaffoftheevent,andrequested anengineering technical evaluation.
| |
| Theoperators continued theprocessofperforming aplantcooldownperoperating procedure 0-2.2,"PlantShutdownfromHotShutdowntoColdConditions".
| |
| AftertheplantwasinMode4,ITSLCO3.7.2wasnotapplicable andLCO3.0.3wasexitedforthemainsteamnon-return checkvalves.G.SAFETYSYSTEMRESPONSES:
| |
| NoneIII.CAUSEOFEVENT:A.IMMEDIATE CAUSE:Theimmediate causeofthecondition prohibited byTechnical Specifications wasenteringITSLCORequiredAction3.7.2.E.1 fortwovalvesinoperable, whichrequiredimmediate entryintoITSLCO.3.0.3.B.INTERMEDIATE CAUSE:Theintermediate causeofentryintoITSLCO3.7.2.E.1 wasthedecisiontodeclarebothmainsteamnon-return checkvalvesinoperable forexceeding theacceptance criteriaofSteps6.1.3and6.2.3oftestprocedure PT-2.10.15.
| |
| ROOTCAUSE:Theunderlying causeforexceeding theacceptance criteriawaschangesinthemethodology andmaterials forpackingthesevalves,instituted duringthepreviousoutage.Thesechangesinmethodology andvendor-recommended replacement shaftbushingmaterials weremadeinordertoprovideimprovedshaftsealability andvibration mitigation, andresultedinagreaterthananticipated shaftbreakaway torque.Overtime,duringthepreviousplantoperating cycle,heatandmoisturewereabsorbedbythepacking,whichcausedtheshaftfrictiontoincreasetotheas-foundvaluesof700and900ft-lbs,whichwerehigherthananticipated, basedontestingresultsfrompreviousyears.
| |
|
| |
|
| NRCFORM366A(B.IBBS)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAMEI1)R.E.GinnaNuclearPowerPlantDOCKETI2)05000244LERNUMBERI6)YEARSEQUENTIAL REVISIONNUMBERNUMBERI999-003-00PAGEI3)5OF6TEXT(Ifmorespaceisrequired, useadditional copiesofftlRCForm366A/I17)IV.ANALYSISOFEVENT:Thiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(i)(8),"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications".
| | fi}} |
| Declaring bothmainsteamnon-return checkvalvesinoperable resultedinentryintoITSLCO3.0.3.SincetheplantenteredITSLCO3.0.3,thiscondition isreportable.
| |
| Anassessment wasperformed considering boththesafetyconsequences andimplications ofthiseventwiththefollowing resultsandconclusions:
| |
| Therewerenooperational orsafetyconsequences attributed tonotmeetingtheacceptance criteriaspecified inprocedure PT-2.10.15 because:oTheacceptance criteriaintestprocedure PT-2.10.15 wasconservatively chosenin1992tobewellbelowthevaluecalculated inDesignAnalysisDA-ME-92-147.
| |
| Thisconservative valuehadbeenutilizedastheacceptance criteriaintestprocedure PT-2.10.15, priortodefiningtheoperability requirements inITSSR3.7.2.2.Theengineering technical evaluation performed onMarch1,1999,determined thattheas-foundbreakaway torquevaluesforthenon-return checkvalveswerewithinthispreviousanalysis.
| |
| oThetwoMSIVsisolatesteamflowfromthesecondary sideofthesteamgenerators (SGs)following aDesignBasisAccident(DBA).BothMSIVswereclosed,asspecified intheInitialConditions oftestprocedure PT-2.10.15, priortoinitiation ofthesurveillance testonMarch1,1999.TheMSIVsaredesignedtoworkwiththemainsteamnon-return checkvalves,locatedimmediately downstream ofeachMSIV,toprecludetheblowdownofmorethanoneSGfollowing asteamlinebreak(SLB).Basedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTION:A.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUS:Immediate corrective actionwastodeclarebothvalvesinoperable andenterITSLCO3.0.3.Following anevaluation ofthetestdatabyNES,itwasdetermined thatthevalveswereoperable.
| |
| TheplantexitedITSLCO3.0.3.Theplantisstillinthe1999refueling outage.
| |
| NRCFORM366A(61998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)R.E.GinnaNuclearPowerPlantDOCKET(2)05000244LERNUMBER(6)9(RU(N(IAL RENSIOIIIIUMBIR1999-003-00PAGE(3)6OF6TEXTllfmorespaceisrequired, useadditional copiesofNRCForm366A/(17)B.ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE oPackingglandtorqueforthesecheckvalveswillbeadjustedtoavaluespecified bytheISTEngineer.
| |
| Anas-foundbaselinebreakaway torquevaluewillbeobtainedforeachvalveduringthe1999outage.0Thedesignanalysiswillberevisedtoprovideacceptance
| |
| : criteria, bothfortheASMECodedegradation valueandfordetermination ofvalveoperability.
| |
| IA"reference value"willbeestablished inaccordance withASME/ANSI OM-1987Part10forbreakaway torqueforthesevalves.Thisvaluewillbeincludedinafuturerevisiontotestprocedure PT-2.10.1 5.VI.ADDITIONAL INFORMATION:
| |
| A.FAILED"COMPONENTS:
| |
| NoneB.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:Nodocumentation ofsimilarLEReventswiththesamerootcauseatGinnaNuclearPowerPlantcouldbeidentified.
| |
| C.SPECIALCOMMENTS:
| |
| None fi}}
| |
Similar Documents at Ginna |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. 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W/960318 Ltr ML17264A2971995-12-14014 December 1995 LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr ML17264A1711995-09-25025 September 1995 LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr 1999-09-22
[Table view] Category:RO)
MONTHYEARML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr ML17309A6541999-05-27027 May 1999 LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr ML17265A6441999-05-13013 May 1999 LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed ML17265A6141999-03-31031 March 1999 LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A3671998-07-14014 July 1998 LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr ML17265A1921998-03-11011 March 1998 LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells ML17265A1641998-02-0606 February 1998 LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified ML17265A1601998-02-0606 February 1998 LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status ML17264B1441997-12-17017 December 1997 LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr ML17264B1291997-12-0303 December 1997 LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr ML17264B1271997-12-0101 December 1997 LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset ML17264B1211997-11-24024 November 1997 LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage ML17264B0461997-09-29029 September 1997 LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr ML17264B0111997-08-27027 August 1997 LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr ML17264A9941997-08-19019 August 1997 LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr ML17264A9911997-08-11011 August 1997 LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe ML17264A8271997-03-0303 March 1997 LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr ML17264A8071997-01-22022 January 1997 LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr ML17264A7471996-11-27027 November 1996 LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr ML17264A6051996-09-19019 September 1996 LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr ML17264A6061996-09-19019 September 1996 LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr ML17264A5911996-09-0505 September 1996 LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr ML17264A5921996-09-0505 September 1996 LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr ML17264A5891996-08-22022 August 1996 LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr ML17264A5781996-08-0606 August 1996 LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr ML17264A5561996-07-12012 July 1996 LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr ML17264A5421996-06-20020 June 1996 LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr ML17264A5411996-06-17017 June 1996 LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr ML17264A5051996-05-17017 May 1996 LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed ML17264A4481996-04-0808 April 1996 LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr ML17264A4471996-04-0808 April 1996 LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr ML17264A4101996-03-18018 March 1996 LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr ML17264A2971995-12-14014 December 1995 LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr ML17264A1711995-09-25025 September 1995 LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A7661999-06-30030 June 1999 1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 ML17309A6541999-05-27027 May 1999 LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested ML17265A6441999-05-13013 May 1999 LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6391999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6301999-04-18018 April 1999 Rev 1 to Cycle 28 COLR for Re Ginna Npp. ML17265A6251999-04-15015 April 1999 Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30
[Table view] |
Text
'ATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9904080027 DOC.DATE: 99/03/31 NOTARIZED: NO( DOCKET SCIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244
,'AUTH. NAME . AUTHOR AFFILIATION
.ST. MARTIN,J.T. Rochester Gas &, Electric Corp.
MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
C
SUBJECT:
LER 99-003-00:on 990301,two main steam non-return check valves were declared inoperable due to exceedance of A acceptance criteria. Caused by changes in m'ethodology &
matls.Packing gland torque will be adjusted. With 990331 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR I ENCL ( SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
Q NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 0
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 VISSING,G. ,1 1 INTERNAL: AEOD RAB 2 2 AEOD/SPD/RRAB RES/DET/EIB 1 1
~ENZ 1 1 NRR/DRCH/HOHB 1 1
NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 NRR/DSSA/SPLB 1 1 1 1 RGN1 FILE 01 1 1 D
EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 N
NOTE TO ALL "RZDS" RECIPZENTS:
PLEASE HELP US TO REDUCE HASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 18
I I
I
AND gM~giESTH CAS li'gD ".'E~IC RFC& Crv ~ 89 &5 4~=.S"E'C."$ 5'. 7 V' Sa-'- .sg', i+CE.';6 Ac-27K March 31, 1999 U. S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directo'rate I-1 Washington, D.C. 20555
Subject:
LER 1999-003, Two Valves Declared Inoperable Results in Condition Prohibited by Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
The attached Licensee Event Report LER 1999-003 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (B), "Any operation or condition prohibited by the plant's Technical Specifications".
Ver truly yours, Robert C. Mecred xc: Mr. Guy S. Vissing (Mail Stop SC2)
Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector 9904080027 99033i PDR ADOCK 05000244 8 PDR
0 I
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION IB ISSSI fN5lt'a Jeep r rVp Be'I'o'N'gAL(s%88P' information coaction request: 50 hrs. Reported lessons learned are incorporated into the licensing process and fed back to LICENSEE EVENT REPORT (LER) industry. Forward comments regarding burden estimate to the Records Management Branch (TA F33). U.S. Nudear Regulatory Commission, Washington, DC 205554001. and to (See reverse for required number of the Paperwork Reduction project (31504I04), Office of digits/characters for each block) Management and Budget, Washington, DC 20503. If an .
information coBection does not display a cunently valid OMB control number, the NRC may not conduct or sponsor. and a FACILITY NAME I11 DocKET NUMBER I2I PAGE (3)
R. E. Ginna Nuclear Power Plant 05000244 1 OF 6 TITLE (el Two Valves Declared Inoperable Results in Condition Prohibited by Technical Specifications EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
SEOUENTIAL REYISION FACIUTY NAME DOCKET NUMBER MONTH OAY YEAR MONTH OAY NUMBER NUMBER 05000 03 01 1999 1999 - 003 00 03 31 1999 FACIUTY NAME DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED P URSUANT TO THE REQUIREMENTS OF 10 CFR E: (Check one or morel (11)
MODE (9) 20.2201(b) 20.2203(a) (2) (v) X 50.73(a)(2)(i)(B) 50.73(a) (2)(viii)
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50 73(a)(2)(u) 50.73(a) (2) (x)
LEVEL (10) 0 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) Specify ln Abstract below 20.2203(a) (2) (iv) 50.36(c)(2) 50.73(a)(2)(vii) or in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (rneivde Aree Cadet John T. St. Martin - Technical Assistant (716) 771-3641 CAUSE REPORTABIE REPORTABlE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT TO EPIX MANUFACTURER TO EPIX SUPPLEMEIITAL REPORT EXPECTED (14) MONTH OAT EXPECTED YES SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). X No DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On March 1, 1999, at approximately 1707 EST, it was determined that the required torque to initiate valve disc closure for the two main steam non-return check valves was greater than the acceptance criteria specified in plant test procedures.
Immediate corrective action was to declare both valves inoperable and enter Technical Specification Limiting Operation 3.0.3. Following an evaluation of the test data by Nuclear Engineering Services, it was determined that Condition'or the valves were oper'able. The plant exited Limiting Condition for Operation 3.0.3.
The underlying cause of the event was changes in the methodology and materials for packing these valves, which resulted in a greater than anticipated shaft breakaway torque.
Corrective action to prevent recurrence is outlined in Section V.B.
1 NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION IB 1999)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
'ACILITYNAME I1) DOCKET l2) LER NUMBER I6I PAGE (3I SMUENTIAL RBBBIBN NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 1999 - 003 - 00 2 OF 6 TEXT (Ifmore space is required, use additional copies of NRC Form 366A/ I17)
PRE-EVENT PLANT CONDITIONS:
Since 1992, Performance Monitoring technicians have performed surveillance test procedure PT-2.10.15, "Main Steam Non-Return Check Valve Closure Verification", using the test methodology established by Nuclear Engineering Services (NES). Performance of test procedure PT-2.10.15 satisfies Ginna Station Improved Technical Specifications (ITS) Surveillance Requirement (SR) 3.7.2.2 and satisfies the requirements of Section XI of the ASME Code for these valves. The required torque to initiate valve disc closure (breakaway torque) for the main steam non-return check valves (CV-3518 and CV-3519) has consistently been measured significantly lower than the acceptance criteria specified within the test procedure (600 ft-lbs).
On March 1, 1999, the plant was in Mode 3, cooling down to Mode 4 for a scheduled refueling outage.
Both main steam isolation valves (MSIVs) were closed. At approximately 1707 EST, Performance Monitoring technicians were performing procedure PT-2.10.15. The technicians were utilizing a calibrated torque wrench with a range of 0 to 600 ft-lbs, as they had in previous years. The technicians could not initiate valve disc closure (achieve breakaway torque), even at the full range of the torque wrench. They consulted'with supervision, and initiated a plant ACTION'Report to document the inability to achieve check valve disc movement up to 600 ft-Ibs of torque.
DESCRIPTIOA OF EVENT:
A. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:
March 1, 1999, 1707 EST: Event Date and Time and Discovery Date and Time.
March 1, 1999, .1 734 EST: Both main steam non-return check valves are declared inoperable.
0 March 1, 1999, 1930 EST: Engineering Technical Evaluation determines that both main steam non-return check valves are operable.
March 1, 1999, 2018 EST: The Plant enters Mode 4, where ITS LCO 3.7.2 is not applicable. ITS LCO 3.0.3 for the main steam non-return check valves is exited.
B. EVENT:
On March 1, 1999, the plant was in Mode 3, cooling down to Mode 4 for a scheduled refueling outage. Both main steam isolation valves (MSIVs) were closed, as specified by the Initial Conditions for test procedure PT-2.10.15. The Performance Monitoring technicians notified the Shift Supervisor of the failure of the main steam non-return check valves to meet the closure torque acceptance criteria of test procedure PT-2.10.15.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6 IBBS)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
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SEOUENTIAL RENSION TEAR NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 1999 - OO3 3 OF 6 TEXT llfmore spaceis required, use additional copies of NRC Form 366Al (17)
The Shift Supervisor reviewed ITS Limiting Condition for Operation (LCO) 3.7.2, notified the NES staff of the 'event, and requested an engineering technical evaluation. At approximately 1734 EST the Shift Supervisor declared both valves CV-3518 and CV-3519 inoperable based on exceeding the acceptance criteria of test procedure PT-2.10.15. As specified in ITS LCO Required Action 3.7.2.E.1, with "one or more valves inoperable in flowpath from each steam generator (SG)",
immediate entry into ITS LCO 3.0.3 is required. The Shift Supervisor directed entry into ITS LCO 3.0.3 at this time.
Performance Monitoring technicians obtained a torque wrench of larger range and again attempted to achieve breakaway torque. At approximately 700 ft-Ibs torque, the valve d(sc for CV-3518 started to close, and at approximately 900 ft-Ibs torque the valve disc for CV-3519 started to close.
These as-found breakaway torque values were provided to NES staff.
NES staff performed an engineering technical evaluation of this event. At approximately 1930 EST, NES staffhadreviewed an engineering analysis (Design'Analysis DA-ME-92-147) that had been performed previously for these valves, and determined that the as-found breakaway torque was within the bounds of the analysis. This information was provided to the Shift Supervisor.
While the valves were now capable of being declared operable, the plant continued the planned cooldown and entered Mode 4 at approximately 2018 EST on March 1, 1999. In Mode 4, ITS LCO 3.7.2 is not applicable, and ITS LCO 3.0.3 was formally exited at this time.
The entry into ITS LCO 3.0.3 as a result of declaring both CV-3518 and CV-3519 inoperable is considered to be a condition prohibited by Technical Specifications. Entry into ITS LCO 3.0.3 for any reason or justification is considered reportable per the NRC guidance in NUREG-1022 Revision 1.
INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:
None D.,OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:
None E. METHOD OF DISCOVERY:
This event was discovered by Performance Monitoring technicians who were performing a routine surveillance test during the plant cooldown.
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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (B IBBB)
LICENSEE EVENT REPORT (LERj TEXT CONTINUATION FACILITY NAME (1) DOCKET (2) LER NUMBER (6) PAGE (3)
SEOUENTIAE REVISION VEAR NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 1999 003 - 00 4 OF 6 TEXT ilfmore space is required, use additional copies of NRC Form 366Al (17)
OPERATOR ACTION:
The Shift Supervisor reviewed ITS LCO 3.7.2 and declared both valves CV-3518 and CV-3519 inoperable based on exceeding the acceptance criteria of test procedure PT-2.10.15. The Shift Supervisor directed entry into ITS LCO 3.0.3 at this time. The Shift Supervisor notified NES staff of the event, and requested an engineering technical evaluation. The operators continued the process of performing a plant cooldown per operating procedure 0-2.2, "Plant Shutdown from Hot Shutdown to Cold Conditions".
After the plant was in Mode 4, ITS LCO 3.7.2 was not applicable and LCO 3.0.3 was exited for the main steam non-return check valves.
G. SAFETY SYSTEM RESPONSES:
None III. CAUSE OF EVENT:
A. IMMEDIATECAUSE:
The immediate cause of the condition prohibited by Technical Specifications was entering ITS LCO Required Action 3.7.2.E.1 for two valves inoperable, which required immediate entry into ITS LCO.
3.0.3.
B. INTERMEDIATE CAUSE:
The intermediate cause of entry into ITS LCO 3.7.2.E.1 was the decision to declare both main steam non-return check valves inoperable for exceeding the acceptance criteria of Steps 6.1.3 and 6.2.3 of test procedure PT-2.10.15.
ROOT CAUSE:
The underlying cause for exceeding the acceptance criteria was changes in the methodology and materials for packing these valves, instituted during the previous outage. These changes in methodology and vendor-recommended replacement shaft bushing materials were made in order to provide improved shaft sealability and vibration mitigation, and resulted in a greater than anticipated shaft breakaway torque. Over time, during the previous plant operating cycle, heat and moisture were absorbed by the packing, which caused the shaft friction to increase to the as-found values of 700 and 900 ft-lbs, which were higher than anticipated, based on testing results from previous years.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (B.IBBS)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME I1) DOCKET I2) LER NUMBER I6) PAGE I3)
SEQUENTIAL REVISION YEAR NUMBER NUMBER R.E. Ginna Nuclear Power Plant 05000244 I 999 003 00 5 OF 6 TEXT (Ifmore spaceis required, use additional copies of ftlRC Form 366A/ I17)
IV. ANALYSIS OF EVENT:
This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i)
(8), "Any operation or condition prohibited by the plant's Technical Specifications". Declaring both main steam non-return check valves inoperable resulted in entry into ITS LCO 3.0.3. Since the plant entered ITS LCO 3.0.3, this condition is reportable.
An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:
There were no operational or safety consequences attributed to not meeting the acceptance criteria specified in procedure PT-2.10.15 because:
o The acceptance criteria in test procedure PT-2.10.15 was conservatively chosen in 1992 to be well below the value calculated in Design Analysis DA-ME-92-147. This conservative value had been utilized as the acceptance criteria in test procedure PT-2.10.15, prior to defining the operability requirements in ITS SR 3.7.2.2. The engineering technical evaluation performed on March 1, 1999, determined that the as-found breakaway torque values for the non-return check valves were within this previous analysis.
o The two MSIVs isolate steam flow from the secondary side of the steam generators (SGs) following a Design Basis Accident (DBA). Both MSIVs were closed, as specified in the Initial Conditions of test procedure PT-2.10.15, prior to initiation of the surveillance test on March 1, 1999. The MSIVs are designed to work with the main steam non-return check valves, located immediately downstream of each MSIV, to preclude the blowdown of more than one SG following a steam line break (SLB).
Based on the above, it can be concluded that the public's health and safety was assured at all times.
V. CORRECTIVE ACTION:
A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:
Immediate corrective action was to declare both valves inoperable and enter ITS LCO 3.0.3.
Following an evaluation of the test data by NES, it was determined that the valves were operable.
The plant exited ITS LCO 3.0.3.
The plant is still in the 1999 refueling outage.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (61998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET (2) LER NUMBER (6) PAGE (3) 9(RU(N(IAL RENSIOII IIUMBIR R.E. Ginna Nuclear Power Plant 05000244 1999 - 003 - 00 6 OF 6 TEXT llfmore space is required, use additional copies of NRC Form 366A/ (17)
B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE o Packing gland torque for these check valves will be adjusted to a value specified by the IST Engineer. An as-found baseline breakaway torque value will be obtained for each valve during the 1999 outage.
0 The design analysis will be revised to provide acceptance criteria, both for the ASME Code degradation value and for determination of valve operability.
I A "reference value" will be established in accordance with ASME/ANSI OM-1987 Part 10 for breakaway torque for these valves. This value will be included in a future revision to test procedure PT-2.10.1 5.
VI. ADDITIONALINFORMATION:
A. FAILED"COMPONENTS:
None B. PREVIOUS LERs ON SIMILAR EVENTS:
A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Nuclear Power Plant could be identified.
C. SPECIAL COMMENTS:
None
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