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| | number = ML17037B871 | | | number = ML17037B871 |
| | issue date = 02/06/1978 | | | issue date = 02/06/1978 |
| | title = Nine Mile Point Unit 2 - Letter Regarding a Breakdown in the Graver Tank & Manufacturing Company'S QA Program and an Enclosed Report Providing a Description of the Deficiency, Analysis of the Safety Implications, and Corrective Action Taken | | | title = Letter Regarding a Breakdown in the Graver Tank & Manufacturing Company'S QA Program and an Enclosed Report Providing a Description of the Deficiency, Analysis of the Safety Implications, and Corrective Action Taken |
| | author name = Rhode G K | | | author name = Rhode G |
| | author affiliation = Niagara Mohawk Power Corp | | | author affiliation = Niagara Mohawk Power Corp |
| | addressee name = Carlson R T | | | addressee name = Carlson R |
| | addressee affiliation = NRC/IE, NRC/RGN-I | | | addressee affiliation = NRC/IE, NRC/RGN-I |
| | docket = 05000410 | | | docket = 05000410 |
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| =Text= | | =Text= |
| {{#Wiki_filter:REGULAT'ORYINFQRNATIQNDISTRIBUTI'QNSYSTEH(RIDS)DISTRI6UTIOh'OR INCOMINGMATERIAL50i410RECgCARLSONRTQRGSRHQOEGKDQCDATES02/06/78NRCNIAGARAMOHAWKPWRDATERCYDS02/13/78DQCTYPE!I.ETTERNOTARIZED INQCOPIESRECEIVEDSUBjlE('T iLTR0ENCI.1FINAl,DEFICIENCY REPTINCL.UDING CORRECTIVE ACTIONSREBREAKDOWN INTHEGRAVENlANK8MANUFACTURING CO'lSQUALITYASSURANCE PROGRAMCQNCEANING CONDITION 1NVOLYING FIELDERECTIONIOFUNXT2CONTAINVENT LINER~Pl.ANTNAMECANINENILEPOINT"UNIT'2REVIEWERINITIAL!5JHDISTRIBUTOR INITIALi*w**+4w**~*WAN*aw DISTRIBUTION OFTHISNATERIALISASFOLLOWS-*a4eew>*4*wAaa*4~a CONSTRUCTION DEFICIENCY REPORT(10CFR50,55(E), | | {{#Wiki_filter:REGULA T'OR Y INFQRNA TIQN DISTR I BUT I'QN SYSTEH (RIDS) 50i410 DISTRI6UTIOh'OR INCOMING MATERIAL RECg CARLSON R T QRGS RHQOE G K DQCDATES 02/06/78 NRC NIAGARA MOHAWK PWR DATE RCYDS 02/13/78 DQCTYPE ! I.ETTER NOTARIZED I NQ COPIES RECEIVED SUBjlE('T i LTR 0 ENCI. 1 FINAl, DEFICIENCY REPT INCL.UDING CORRECTIVE ACTIONS RE BREAKDOWN IN THE GRAVEN lANK 8 MANUFACTURING CO'lS QUALITY ASSURANCE PROGRAM CONDITION 1NVOLYING FIELD ERECTION IOF UNXT 2 CONTAINVENT CQNCEANING CANINE LINER ~ |
| (DISTRIBUTION CODEBOOED)FORACTIONSASSTDIR'VASSALLU+wLTR ONI.YBRANCHCHIEFVARGA+4LTR ONLYPRTRONLYLICAS8IiSERVICE0*L."TRlQNI'INTERNAL! | | Pl.ANT NAME NILE POINT " UNIT '2 REVIEWER INITIAL! 5 JH DISTRIBUTOR INITIALi |
| ,E)(TERNALI GFT-Br+WIS,E~~W/P.EACl.GQSSICK8STAFF<<LTR ONLYHQYD*ALTR
| | *w**+4w**~*WAN*awDISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS -*a4eew>*4*wAaa*4~a CONSTRUCTION DEFICIENCY REPORT (10CFR50,55(E), |
| 'ONLYHElTEVES*+W/ENCL KN?GHT**L.TR ON[,YTEDESCQ~*LTR IGNI,YSTANDARDS l)EYe<>4/ENCL LPPRI8,'OSWEGO'Yw~W/ENCL TICWAH/ENCL NSIC*ak/ENCl ACRSCATB*~b/16LTRSNRCPDRa*W/ENCL VELD~*LTR | | (DISTRIBUTION CODE BOOED) |
| ~ONLYHIPCa*y/ENCL DEYQUNG*A'W/ENCL R,NATTSQN**LTR ONLYROSSa+LTR ONLYEISENHUT~~LTR ONLYSEYFRIT/IEwwH/ENCL I.DISTRIBUTION!
| | FOR ACTIONS ASST DIR 'VASSALLU+wLTR ONI.Y BRANCH CHIEF VARGA+4LTR ONLY I ' |
| LTR40ENCL,28SIX(~1Pt5PCONTROLNBRI780460032 t'I0~'hltttiIfN4II1Nlll~itI'utI)'4it-I2'NlltLI'NW4,';IINNy.''4~tgP4IIYIf4'IIIII\,Ig1r444Ifg1tt,dttll~o"ltII'At4',ttH*ltNN tlMll9mltIJatlÃB FNFgPLm'WNIAGAAPlUMOHAWKNIAGARAMOHAWKPOWERCORPORATION/300 ERIEBOULEVARD WEST,SYRACUSE, N.Y.13202/TELEPHONE (315)474-1511February6,1978OfficeofInspection andEnforcement RegionIAttention:
| | PR TR ONLY I L C A S 8 i S E R V I C E 0 |
| .Mr.,R.T.Garison,ChiefReactorConstruction andEngineering SupportBranchU.S.NuclearRegulatory Commission 631ParkAvenueKingofPrussia,Pennsylvania 19406'<~ling~~iS~p~i1918CI1O8Re:.NineMilePointUnit2DocketNo.50-410
| | * L." T R lQ N I INTERNAL! G FT -Br+W NRC PDRa*W/ENCL I S, E~~W/P. EACl. VELD~*LTR ~ONLY GQSSICK 8 STAFF<<LTR ONLY HIPCa*y/ENCL HQYD*ALTR 'ONLY DEYQUNG*A'W/ENCL HEl TEVES*+W/ENCL R, NATTSQN**LTR ONLY KN?GHT**L.TR ON[,Y ROSSa+LTR ONLY TEDESCQ~*LTR IGNI,Y EISENHUT~~LTR ONLY STANDARDS l)EYe<>4/ENCL SEYFRIT/IEwwH/ENCL |
| | , E)(TERNALI LPPR I8 |
| | , 'OSWEGO'Yw~W/ENCL TICWAH/ENCL NSIC*ak/ENCl ACRS CAT B*~b/16 LTRS I. |
| | DISTRIBUTION! LTR 40 ENCL, 28 CONTROL NBRI 780460032 SIX(~ 1Pt5P |
|
| |
|
| ==DearMr.Garison:== | | t |
| OnDecember.
| | 'I 0 ~ |
| 23,1977,yourstaffwas.advisedofabreakdown intheGraverTank&Manufacturing Company's QualityAssurance Program.Thiscondition involvedfielderectionoftheNine'ilePointUnit2containment liner.Asindicated in.ourJanuary24,1978letter,attachedisafinalreportproviding adescription ofthedeficiency, andanalysisofthesafetyimplications andthecorrective actiontaken.Thisreportissubmitted inaccordance withSection50.55(e)(3) oftheCommission's regulations.- | | 'h lt t ti I 4 II 1 |
| Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATION I7Geral.K.Rhod,VicePresident SystemPro)ctManagement PEF/szd~o46OO32Attachment Xc:.ErnstVolgenauInspection
| | ~ it Nl f N ll I' |
| &Enforcement BranchU.S.NuclearRegulatory Commission Washington, D.C.20555Boaq0/ | | u t I |
| I~~gog Stone.&Webster'.s FieldQualityControlgroupinaccordance withtheirQualityVerification ofGraver'sQualityProgramissuedsevenunsatis-factoryInspection ReportsandtwoNonconformance andDisposition ReportsduringafiveweekperiodendingDecember15,1977.Areviewofthesereportsrevealedthefollowing deficiencies: | | ) |
| A..Contraryto10CFR50AppendixBCriterion VI(DOCUMENT CONTROL)work,wasbeingperformed utilizing aprocedure, fortemporary attachment removalthat,hadnotbeenapprovedbyStoneandWebsterEngineering. | | 4 it 'N |
| B.Contraryto10CFR50AppendixB.Criterion IX-(CONTROL OFSPECIALPROCESSES) aweldingprocedure wasbeingusedthatwasnotqualified. | | -I 2 ll t |
| fortheapplication (i.e.,weldingwasbeingperformed oncladdingthinnerthanspecified intheprocedure).
| | LI' N W 4, ';I IN Ny |
| Inaddition,
| | .' '4 |
| : required, nondestructive testingwasnotbeingperformed toverifydefectremovalpriortowelding.C.Contraryto10CFR50AppendixBCriterion X(INSPECTION),
| | ~ tg P 4 II Y |
| Graver'sQualityControlgroupwasnotdocumenting theirinspection (reviewandacceptance) ofrepairweldsperformed asaresultofremovaloftemporary attachments. | | If 4 |
| D.Contraryto10CFR50AppendixB.Criterion XVI(CORRECTIVE ACTION),measureswerenotinitiated tocorrectconditions identified byStoneandWebsterFieldQualityControlaboveasbeingadversetoquality.After.theyhadbeeninstructed todosobyStoneand.Webster Engineering, Graverdid.notdocumenttheirinspection ofrepairwelds,usetheprocedure identified byStoneandWebsterasapplicable forclad'less than1/16"thick,andtheydidnotfollowtheirprocedure fortemporary attachment removalasapproved. | | 'I I I I I \, l~ |
| II.SAFETYANALYSISTheprimarycontainment cladmaterialanditsfunctionaredescribed inSection5.0ofthePreliminary SafetyAnalysisReport.Thecladformsanintegral, partofthebasematerialoftheprimarycontainment liner.Thecladsurfaceisdesignedto.providecorrosion protection ofthebasematerialandpreclude. | | Ig tt,dt tl 1r 4 44 I f g 1 o" lt I I' At 4 ',tt H |
| contamination. | | * lt NN |
| fromthesuppression poolwater.Thecladdingisnotrequiredfor.thedesignstrengthorleakintegrity oftheprimarycontainment liner.Theweldrepaircavitiesdidnotexposethecarbonsteelbasemetal.Therefore, this,doesnotresultinasafetyhazardtoNineMilePointUnit2.Theweldrepairsdonotjeopardize thecorrosion resistant performance ofthecladortheprimarycontainment linerdesignrequirements.
| | |
| E~f III.CORRECTIVE ACTIONThefollowing actionshavebeentakentocorrectthedeficiencies identified inSectionI:A.Aprocedure fortemporary attachment removalhasbeenreviewedandapprovedasofNovember22,1977.B.Stone.andWebsterhasreviewedtheapplicability ofweldingprocedures. | | Lm'W NIAGA A tlMll9mltIJatlÃB FNF gP Pl U MOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 February 6, 1978 Office of Inspection and Enforcement '<~ling ~ |
| forcladsurfaceweldrepairs.Theappropriate weldingprocedure inquestionwasfoundacceptable asitwasinaccordance withtheASMEcoderequiredbypurchasespecification.
| | Region I Attention: .Mr.,R. T. Garison, Chief ~i S~ p~ i 1918 CI1 Reactor Construction and Engineering Support Branch U. S. Nuclear Regulatory Commission O 631 Park Avenue King of Prussia, Pennsylvania 19406 8 Re:. Nine Mile Point Unit 2 Docket No. 50-410 |
| Also,cladsurfaceweldrepairswereallliquidpenetrant inspected andaccepted. | | |
| C.Theprocedure fortemporary attachment removalprovidesfortheinitiation ofatemporary welddatasheetto,document theweldprocedure usedandQualityAssurance sign-off. | | ==Dear Mr. Garison:== |
| D.OnJanuary4,.1978,ameetingwasheldatStoneandWebster'CherryHillOperations CenterwithGraverManagement. | | |
| todiscussthese'eficiencies.
| | On December. 23, 1977, your staff was. advised of a breakdown in the Graver Tank & Manufacturing Company's Quality Assurance Program. This condition involved field erection of the Nine'ile Point Unit 2 containment liner. |
| Asaresultofthismeeting,thefollowing actionshaveorwillbetaken:1.Graverhaspreparedasupplement totheNineMileQualityAssurance Manualwhich,has beenreviewedandaccepted.
| | As indicated in.our January 24, 1978 letter, attached is a final report providing a description of the deficiency, and analysis of the safety implications and the corrective action taken. This report is submitted in accordance with Section 50.55(e)(3) of the Commission's regulations.- |
| Itisanticipated thatthissupple-mentwillbeissuedshortly.Thissupplement establishes asystemtoassurethatconditions adversetoqualitysuchasaudit,findings, deficiencies, deviations fromprocedures,
| | Very truly yours, NIAGARA MOHAWK POWER CORPORATION I 7 Geral. K. Rhod , Vice President System Pro) ct Management PEF/szd ~o46OO32 Attachment Xc: . Ernst Volgenau Inspection & Enforcement Branch U. S. Nuclear Regulatory Commission Boaq Washington, D. C. 20555 0 |
| : failures, malfunctions andnonconformances areidentified, corrected anddocumented.
| | / |
| Theprocedure willrequirearesponsefromtheaffectedpartyandwillalsorequireperiodicmanagement reviewofcorrective actions.
| | |
| zr 2.Graverwillbesupplementing itsgQuality Assurance activities byaddingapermanent QualityAssurance representative totheNineMilefieldcrew.InadditiontohisdefinedQualityAssurance responsibilities, hewillprovideanadditional~intertace>with<Stone andWebsterFieldQualityControl.~~~"<"~03.AsofJanuary16,1978,GraverhasassignedaQualityAssurance Management individual totheNineMilesiteonatemporary basis.Thisindividual willreviewtheactivities atthesiteand,reporttoGravermanagement ontheprogressofQualityAssurance andsiteactivities.
| | I |
| 4.Theappropriate Construction Interface Procedure willberevisedtoreflectaworkableInspection ReportandNonconformance | | ~ ~ |
| &Disposition Reportinterface betweenGraverandStoneandWebster.StoneandWebsterFieldQualityControlwillincreasetheirsurveillance oftheGraverQualityAssurance ProgramandreporttoStoneandWebsterProjectManagement andNiagaraMohawkontheprogress, andeffectiveness ofGraver'sQualityAssurance siteactivities. | | go g |
| RECEIVEOOOCOHEHTCONIROLGEST19tGFB15PQ200U.S.NRCOISTRIBUTION SERVICESBRANCH}}
| | |
| | Stone. & Webster'.s Field Quality Control group in accordance with their Quality Verification of Graver's Quality Program issued seven unsatis-factory Inspection Reports and two Nonconformance and Disposition Reports during a five week period ending December 15, 1977. A review of these reports revealed the following deficiencies: |
| | A.. Contrary to 10CFR50 Appendix B Criterion VI (DOCUMENT CONTROL) work,was being performed utilizing a procedure, for temporary attachment removal that,had not been approved by Stone and Webster Engineering. |
| | B. Contrary to 10CFR50 Appendix B .Criterion IX-(CONTROL OF SPECIAL PROCESSES) a welding procedure was being used that was not qualified. for the application (i.e., welding was being performed on cladding thinner than specified in the procedure). In addition, required, nondestructive testing was not being performed to verify defect removal prior to welding. |
| | C. Contrary to 10CFR50 Appendix B Criterion X (INSPECTION), Graver's Quality Control group was not documenting their inspection (review and acceptance) of repair welds performed as a result of removal of temporary attachments. |
| | D. Contrary to 10CFR50 Appendix B. Criterion XVI (CORRECTIVE ACTION), |
| | measures were not initiated to correct conditions identified by Stone and Webster Field Quality Control above as being adverse to quality. After. they had been instructed to do so by Stone and.Webster Engineering, Graver did. not document their inspection of repair welds, use the procedure identified by Stone and Webster as applicable for clad'less than 1/16" thick, and they did not follow their procedure for temporary attachment removal as approved. |
| | II. SAFETY ANALYSIS The primary containment clad material and its function are described in Section 5.0 of the Preliminary Safety Analysis Report. The clad forms an integral, part of the base material of the primary containment liner. |
| | The clad surface is designed to. provide corrosion protection of the base material and preclude. contamination. from the suppression pool water. |
| | The cladding is not required for. the design strength or leak integrity of the primary containment liner. |
| | The weld repair cavities did not expose the carbon steel base metal. |
| | Therefore, this, does not result in a safety hazard to Nine Mile Point Unit 2. The weld repairs do not jeopardize the corrosion resistant performance of the clad or the primary containment liner design requirements. |
| | |
| | E~ |
| | f |
| | |
| | III. CORRECTIVE ACTION The following actions have been taken to correct the deficiencies identified in Section I: |
| | A. A procedure for temporary attachment removal has been reviewed and approved as of November 22, 1977. |
| | B. Stone. and Webster has reviewed the applicability of welding procedures. for clad surface weld repairs. The appropriate welding procedure in question was found acceptable as in accordance with the ASME code required by purchase it was specification. Also, clad surface weld repairs were all liquid penetrant inspected and accepted. |
| | C. The procedure for temporary attachment removal provides for the initiation of a temporary weld data sheet to,document the weld procedure used and Quality Assurance sign-off. |
| | D. On January 4,. 1978, a meeting was held at Stone and Webster' Cherry Hill Operations Center with Graver Management. to discuss these'eficiencies. As a result of this meeting, the following actions have or will be taken: |
| | : 1. Graver has prepared a supplement to the Nine Mile Quality Assurance Manual which,has been reviewed and accepted. It is anticipated that this supple-ment will be issued shortly. This supplement establishes a system to assure that conditions adverse to quality such as audit, findings, deficiencies, deviations from procedures, failures, malfunctions and nonconformances are identified, corrected and documented. The procedure will require a response from the affected party and will also require periodic management review of corrective actions. |
| | |
| | z r |
| | : 2. Graver will be supplementing itsgQuality Assurance activities by adding a permanent Quality Assurance representative to the Nine Mile field crew. In addition to his defined Quality Assurance responsibilities, he will provide an additional~intertace>with<Stone and Webster Field Quality Control. ~~~"<"~0 |
| | : 3. As of January 16, 1978, Graver has assigned a Quality Assurance Management individual to the Nine Mile site on a temporary basis. This individual will review the activities at the site and, report to Graver management on the progress of Quality Assurance and site activities. |
| | : 4. The appropriate Construction Interface Procedure will be revised to reflect a workable Inspection Report and Nonconformance & Disposition Report interface between Graver and Stone and Webster. |
| | Stone and Webster Field Quality Control will increase their surveillance of the Graver Quality Assurance Program and report to Stone and Webster Project Management and Niagara Mohawk on the progress, and effectiveness of Graver's Quality Assurance site activities. |
| | |
| | RECEIVEO OOCOHEHT CON IROL GEST PQ 200 19tGFB 15 U.S. NRC OISTRIBUTION SERVICES BRANCH}} |
|
|---|
Category:Letter
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2024-09-04
[Table view]
Category:Report
MONTHYEARNMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023
Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023
Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-27027 March 2023
Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
ML20190A1482020-07-0808 July 2020
FAQ 20-01 NMP Scram Final Approved
ML20100F6822020-04-0909 April 2020
Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication
ML19228A0232019-08-15015 August 2019
Proposed Alternative to Utilize Code Case N-879
NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018
Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.
NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...
ML18018B2922018-01-18018 January 2018
Appendix a, Justification for Continued Operation, Component Review Summary Sheet
ML18018B2912018-01-18018 January 2018
Pipe Crack Task Force Report
ML18018A9652018-01-18018 January 2018
Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan
ML18018B0122018-01-18018 January 2018
Semi-Annual Radioactive Effluent Release Report July-December 1999
ML17251A0452017-09-20020 September 2017
- Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088)
ML17109A3652017-04-13013 April 2017
Pressure and Temperature Limits Report
ML17079A3842017-03-24024 March 2017
Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections
ML17037A6862017-02-0606 February 2017
Table 7.2-1
ML17037A7032017-02-0606 February 2017
Table 7.2-1 (Cont'D)
ML17027A0162017-01-27027 January 2017
10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors
RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016
High Frequency Supplement to Seismic Hazard Screening Report
ML16231A4522016-08-30030 August 2016
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events)
ML16223A8532016-08-25025 August 2016
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents)
RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016
Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML16160A0942016-06-0808 June 2016
ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004)
ML15153A6602015-06-16016 June 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re
ML15028A1492015-02-11011 February 2015
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014
Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML15022A6612014-07-31031 July 2014
Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version
ML14153A4102014-07-24024 July 2014
Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
ML14167A3492014-06-20020 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250)
ML15022A6622014-05-31031 May 2014
Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version
ML15023A0312014-04-30030 April 2014
Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version
ML14099A1962014-03-31031 March 2014
Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.
ML14064A3242014-02-28028 February 2014
000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics.
ML14071A4782014-02-21021 February 2014
Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments
ML14351A4272014-01-31031 January 2014
000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow).
ML14064A3222014-01-31031 January 2014
00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+).
ML14024A4422014-01-0707 January 2014
Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing
ML14064A3232013-12-31031 December 2013
000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15.
ML13225A5842013-12-19019 December 2013
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML13338A6632013-12-11011 December 2013
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129
ML13338A6642013-12-11011 December 2013
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130
ML13311A0542013-11-0404 November 2013
Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B)
ML13316B1102013-11-0101 November 2013
Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary)
ML13311A0552013-09-30030 September 2013
Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3
ML13197A2222013-07-12012 July 2013
Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic
2024-07-24
[Table view]
Category:Technical
MONTHYEARNMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023
Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
ML20100F6822020-04-0909 April 2020
Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication
ML19228A0232019-08-15015 August 2019
Proposed Alternative to Utilize Code Case N-879
NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018
Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.
NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...
ML18018B0122018-01-18018 January 2018
Semi-Annual Radioactive Effluent Release Report July-December 1999
ML18018A9652018-01-18018 January 2018
Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan
ML17109A3652017-04-13013 April 2017
Pressure and Temperature Limits Report
ML17037A7032017-02-0606 February 2017
Table 7.2-1 (Cont'D)
ML17037A6862017-02-0606 February 2017
Table 7.2-1
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014
Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML15022A6612014-07-31031 July 2014
Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
ML15022A6622014-05-31031 May 2014
Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version
ML15023A0312014-04-30030 April 2014
Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version
ML14064A3242014-02-28028 February 2014
000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics.
ML14071A4782014-02-21021 February 2014
Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments
ML14064A3222014-01-31031 January 2014
00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+).
ML14351A4272014-01-31031 January 2014
000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow).
ML14064A3232013-12-31031 December 2013
000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15.
ML13225A5842013-12-19019 December 2013
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML13338A6632013-12-11011 December 2013
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129
ML13338A6642013-12-11011 December 2013
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130
ML13311A0542013-11-0404 November 2013
Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B)
ML13316B1102013-11-0101 November 2013
Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary)
ML13311A0552013-09-30030 September 2013
Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3
ML13197A2222013-07-12012 July 2013
Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic
ML13078A3232013-02-28028 February 2013
XGEN-2012-25-NP, Revision 1, Westinghouse Engineering Report, Technical Basis for the Inspection Frequency of the Modified Alloy 718 Jet Pump Beam, Attachment 2
ML13066A1692013-02-28028 February 2013
Units I and 2, Overall Integrated Plan for Reliable Hardened Vents
ML12313A2032012-10-26026 October 2012
Attachment 1, NMP2 Extended Power Uprate, Power Ascension Test Report
ML12313A2042012-10-26026 October 2012
Attachment 2, Final Steam Dryer Stress Report, Continuum Dynamics, Incorporated Report No. 12-18NP, Attachment 3, Affidavit from CDI
ML12277A0902012-10-12012 October 2012
Technical Letter Report on Aging Management Program Audits at Ginna and Nine Mile Point 1
ML12284A1842012-09-30030 September 2012
Attachment 3, Final EPU Steam Dryer Load Definition CDI Report No. 12-20NP, Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point, Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1
ML12284A1852012-06-30030 June 2012
Attachment 4, Steam Dryer Limit Curves CDI Technical Note No. 12-13NP, Limit Curves with ACM Rev. 4.1 for the 100% Power Level Basis at Nine Mile Point, Unit 2, Revision 1
ML12170A8692012-06-30030 June 2012
Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition
ML11221A0132011-08-0505 August 2011
Attachment 3, Continuum Dynamics, Inc Technical Note No. 11-17NP, Limit Curve Analysis with ACM Rev. 4.1 for Power Ascension at Nine Mile Point Unit 2, Revision 1. (Non-Proprietary)
ML11208B7732011-07-0808 July 2011
Report No. 1100539.401, Rev. 1, Nine Mile Point Unit 1, Steam Dryer Support Bracket Flaw Evaluation.
ML11188A1952011-06-28028 June 2011
Calculation S0VESSELM035 (SIA File No. 1100566.301), Reactor Pressure Vessel Head Weld Flaw Evaluation, Rev. 00.00
ML11171A0602011-05-31031 May 2011
Attachment 3, CDI Report No. 11-04NP, Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Using ACM Rev. 4.1 Acoustic Loads, Revision 0. (Non-Proprietary), Attachment 4, Affidavit from Continuum Dynamics, Inc
ML1108803022011-03-31031 March 2011
NEDO-33636, Fuel Storage Criticality Safety Analysis of New Fuel Storage Racks - GE14, Attachment 3, (Non-Proprietary)
ML1104601602011-01-31031 January 2011
Attachment 1, CDI Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Revision 3
ML12135A6232011-01-14014 January 2011
Off-Site Dose Calculation Manual (Odcm), Revision 32
ML1035003652010-12-13013 December 2010
Holtec Report No. HI-2012621 (Non-Proprietary), Criticality Safety Evaluation for the Nine Mile Point 2 Rack Installation Project
ML1021702952010-07-30030 July 2010
Attachment 5, Continuum Dynamics, Inc., CDI Report No. 10-12NP, Design and Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Modifications for EPU Operation
ML1021701862010-07-28028 July 2010
Attachment 4, Structural Integrity Associates, Inc., Flaw Evaluation of Indications in the Nine Mile Point Unit 2 Steam Dryer Vertical Support Plates Considering Extended Power Uprate Flow Induced Vibration Loading
ML1019004492010-06-30030 June 2010
C.D.I. Report No. 10-10NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1, Rev. 1
ML1021701852010-06-30030 June 2010
Attachment 3, Global Nuclear Fuel - Americas, LLC, MCNP01A, Low Enriched UO2 Pin Lattice in Water Critical Benchmark Evaluations Using ENDF/B-V Nuclear Cross-Section Data, Revision 1
ML1019004482010-06-30030 June 2010
C.D.I. Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Rev. 1 (Non-Proprietary)
2023-08-04
[Table view] |
Text
REGULA T'OR Y INFQRNA TIQN DISTR I BUT I'QN SYSTEH (RIDS) 50i410 DISTRI6UTIOh'OR INCOMING MATERIAL RECg CARLSON R T QRGS RHQOE G K DQCDATES 02/06/78 NRC NIAGARA MOHAWK PWR DATE RCYDS 02/13/78 DQCTYPE ! I.ETTER NOTARIZED I NQ COPIES RECEIVED SUBjlE('T i LTR 0 ENCI. 1 FINAl, DEFICIENCY REPT INCL.UDING CORRECTIVE ACTIONS RE BREAKDOWN IN THE GRAVEN lANK 8 MANUFACTURING CO'lS QUALITY ASSURANCE PROGRAM CONDITION 1NVOLYING FIELD ERECTION IOF UNXT 2 CONTAINVENT CQNCEANING CANINE LINER ~
Pl.ANT NAME NILE POINT " UNIT '2 REVIEWER INITIAL! 5 JH DISTRIBUTOR INITIALi
- w**+4w**~*WAN*awDISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS -*a4eew>*4*wAaa*4~a CONSTRUCTION DEFICIENCY REPORT (10CFR50,55(E),
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Lm'W NIAGA A tlMll9mltIJatlÃB FNF gP Pl U MOHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 February 6, 1978 Office of Inspection and Enforcement '<~ling ~
Region I Attention: .Mr.,R. T. Garison, Chief ~i S~ p~ i 1918 CI1 Reactor Construction and Engineering Support Branch U. S. Nuclear Regulatory Commission O 631 Park Avenue King of Prussia, Pennsylvania 19406 8 Re:. Nine Mile Point Unit 2 Docket No. 50-410
Dear Mr. Garison:
On December. 23, 1977, your staff was. advised of a breakdown in the Graver Tank & Manufacturing Company's Quality Assurance Program. This condition involved field erection of the Nine'ile Point Unit 2 containment liner.
As indicated in.our January 24, 1978 letter, attached is a final report providing a description of the deficiency, and analysis of the safety implications and the corrective action taken. This report is submitted in accordance with Section 50.55(e)(3) of the Commission's regulations.-
Very truly yours, NIAGARA MOHAWK POWER CORPORATION I 7 Geral. K. Rhod , Vice President System Pro) ct Management PEF/szd ~o46OO32 Attachment Xc: . Ernst Volgenau Inspection & Enforcement Branch U. S. Nuclear Regulatory Commission Boaq Washington, D. C. 20555 0
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Stone. & Webster'.s Field Quality Control group in accordance with their Quality Verification of Graver's Quality Program issued seven unsatis-factory Inspection Reports and two Nonconformance and Disposition Reports during a five week period ending December 15, 1977. A review of these reports revealed the following deficiencies:
A.. Contrary to 10CFR50 Appendix B Criterion VI (DOCUMENT CONTROL) work,was being performed utilizing a procedure, for temporary attachment removal that,had not been approved by Stone and Webster Engineering.
B. Contrary to 10CFR50 Appendix B .Criterion IX-(CONTROL OF SPECIAL PROCESSES) a welding procedure was being used that was not qualified. for the application (i.e., welding was being performed on cladding thinner than specified in the procedure). In addition, required, nondestructive testing was not being performed to verify defect removal prior to welding.
C. Contrary to 10CFR50 Appendix B Criterion X (INSPECTION), Graver's Quality Control group was not documenting their inspection (review and acceptance) of repair welds performed as a result of removal of temporary attachments.
D. Contrary to 10CFR50 Appendix B. Criterion XVI (CORRECTIVE ACTION),
measures were not initiated to correct conditions identified by Stone and Webster Field Quality Control above as being adverse to quality. After. they had been instructed to do so by Stone and.Webster Engineering, Graver did. not document their inspection of repair welds, use the procedure identified by Stone and Webster as applicable for clad'less than 1/16" thick, and they did not follow their procedure for temporary attachment removal as approved.
II. SAFETY ANALYSIS The primary containment clad material and its function are described in Section 5.0 of the Preliminary Safety Analysis Report. The clad forms an integral, part of the base material of the primary containment liner.
The clad surface is designed to. provide corrosion protection of the base material and preclude. contamination. from the suppression pool water.
The cladding is not required for. the design strength or leak integrity of the primary containment liner.
The weld repair cavities did not expose the carbon steel base metal.
Therefore, this, does not result in a safety hazard to Nine Mile Point Unit 2. The weld repairs do not jeopardize the corrosion resistant performance of the clad or the primary containment liner design requirements.
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III. CORRECTIVE ACTION The following actions have been taken to correct the deficiencies identified in Section I:
A. A procedure for temporary attachment removal has been reviewed and approved as of November 22, 1977.
B. Stone. and Webster has reviewed the applicability of welding procedures. for clad surface weld repairs. The appropriate welding procedure in question was found acceptable as in accordance with the ASME code required by purchase it was specification. Also, clad surface weld repairs were all liquid penetrant inspected and accepted.
C. The procedure for temporary attachment removal provides for the initiation of a temporary weld data sheet to,document the weld procedure used and Quality Assurance sign-off.
D. On January 4,. 1978, a meeting was held at Stone and Webster' Cherry Hill Operations Center with Graver Management. to discuss these'eficiencies. As a result of this meeting, the following actions have or will be taken:
- 1. Graver has prepared a supplement to the Nine Mile Quality Assurance Manual which,has been reviewed and accepted. It is anticipated that this supple-ment will be issued shortly. This supplement establishes a system to assure that conditions adverse to quality such as audit, findings, deficiencies, deviations from procedures, failures, malfunctions and nonconformances are identified, corrected and documented. The procedure will require a response from the affected party and will also require periodic management review of corrective actions.
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- 2. Graver will be supplementing itsgQuality Assurance activities by adding a permanent Quality Assurance representative to the Nine Mile field crew. In addition to his defined Quality Assurance responsibilities, he will provide an additional~intertace>with<Stone and Webster Field Quality Control. ~~~"<"~0
- 3. As of January 16, 1978, Graver has assigned a Quality Assurance Management individual to the Nine Mile site on a temporary basis. This individual will review the activities at the site and, report to Graver management on the progress of Quality Assurance and site activities.
- 4. The appropriate Construction Interface Procedure will be revised to reflect a workable Inspection Report and Nonconformance & Disposition Report interface between Graver and Stone and Webster.
Stone and Webster Field Quality Control will increase their surveillance of the Graver Quality Assurance Program and report to Stone and Webster Project Management and Niagara Mohawk on the progress, and effectiveness of Graver's Quality Assurance site activities.
RECEIVEO OOCOHEHT CON IROL GEST PQ 200 19tGFB 15 U.S. NRC OISTRIBUTION SERVICES BRANCH
