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| | issue date = 03/13/1979 | | | issue date = 03/13/1979 |
| | title = Forwards Response to IE Bulletins 78-12 & 78-12A, Records Investigation Rept Re Off-Chemistry Welds in Matl Surveillance Specimens & Responses to Bulletin 78-12&78-12A Suppl. Concludes Crystal River 3 Isolated Event | | | title = Forwards Response to IE Bulletins 78-12 & 78-12A, Records Investigation Rept Re Off-Chemistry Welds in Matl Surveillance Specimens & Responses to Bulletin 78-12&78-12A Suppl. Concludes Crystal River 3 Isolated Event |
| | author name = TAYLOR J H | | | author name = Taylor J |
| | author affiliation = BABCOCK & WILCOX CO. | | | author affiliation = BABCOCK & WILCOX CO. |
| | addressee name = REINMUTH W G | | | addressee name = Reinmuth W |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| | docket = 05000244, 05000302 | | | docket = 05000244, 05000302 |
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| {{#Wiki_filter:Babcock~V~ilco"I!PowerGeneration GroUpP.O.Box1260,Lynchbur8,Va.24505Telephone: | | {{#Wiki_filter:I Babcock ~V~ilco" ! Power Generation GroUp P.O. Box 1260, Lynchbur 8, Va. 24505 Telephone: (804) 384-5111 |
| (804)384-5111~;)'b~%'l,~:.March13,1979Mr.PayneG.Re'inmu'th" | | ~;)'b ~ |
| ~.s.'-c,OfficeofInspection and'nforeementU.S;NuclearRegulatory Commission Nashington, D.C..2055$Subject-: | | %'l, ~ |
| ResponsetoIEBulletinNos.,78-12and78-12A'ear NrReinmuthEnclosedforyourinformation arethree(3)copiesof'urreportentitled, "RecordsInvestigation ReportRelated'o Off-Chemistry Neldsini~faterial Surveillance Specimens and.Resppnses toBulletin78-12.and.78-12ASupplement",
| | :.March 13, 1979 Mr. Payne G. Re'inmu'th" ~.s.'-c, f |
| whichwehavepreparedfor.ourcustomers inordertofacilitate their.responses tothebulletins.
| | Of ic e o f Inspection and 'n f ore ement U. S; Nuclear Regulatory Commission Nashington, D.C.. 2055$ |
| Thereportisbasically dividedintothree(3)parts:(1)anintroduction and.summaryofthe..............
| | Subject-: Response to IE Bulletin Nos., 78-12 and 78-12A'ear Nr Reinmuth Enclosed for your information are three (3) copies of'ur report entitled, "Records Investigation Report Related'o Off-Chemistry Nelds in i~faterial Surveillance Specimens and. |
| weld,wireissue;(2)'generalinformation tosupport.thecon-clusionswehavereached;and(3)specificresponses totheinformation requested bythebulletins. | | Resppnses to Bulletin 78-12. and. 78-12A Supplement", which we have prepared for. our customers in order to facilitate their . |
| Appendices containing copies.ofBINchemicalanalysisrequirements andweldfillerwirequalification testsareincludedassupporting information. | | responses to the bulletins. The report is basically divided into three (3) parts: (1) an introduction and. summary of the.............. |
| Theinformation intheappendices hasbeenselectedbasedonyourrequest.ataJanuary16,1979meetinginNt.Vernon,Indiana.Thisreport.describes theinvestigations thatveremadeasaresultofdiscovering anoff-chemistry condition inareactorvesselsurveillance specimenfortheCrystalRiver3(CR-3)Project.Thepurposeoftherecordsinvestigation wasto.determine thecauseandextentofthemixedweld.wireproblem..Theinvestigation alsoincludedareviewoftestresultsfrom.actualreactorvesselproduction weld.seamstotheextenttheseweldscouldbeinvestigated, andfromreactorvesselsurveillance materialtests.Theinvestigation coveredtheperiodfrom1966throughNovember1978.'naccordance withIEBulletin78-12A,ourresponseisgivenonagenericbasisandaoattemptwasmadetocorrelate specificweldments withheatsoffillerwire.~.I~5~QOVp3pgag~~~'Bah:ock ZWilcoxCompany/Estabhshed 1867
| | weld, wire issue; (2) 'general information to support. the con-clusions we have reached; and (3) specific responses to the information requested by the bulletins. Appendices containing copies. of BIN chemical analysis requirements and weld filler wire qualification tests are included as supporting information. |
| /~plf4fttyp,,5'lrl
| | The information in the appendices has been selected based on your request. at a January 16, 1979 meeting in Nt. Vernon, Indiana. |
| 'rbcock8.V/ilcox
| | This report. describes the investigations that vere made as a result of discovering an off-chemistry condition in a reactor vessel surveillance specimen for the Crystal River 3 (CR-3) |
| ~.r*Ir%QWHr.NayneG.ReinmuthMarch13,1979:0PTherecordsinvestigation,.provides considerable supportforthehypothesis that-the.presenceofatypicalchemistry condition intheCrystalRiver3surveillance'lock isanisolatedevent.involving asmall'amount.of.materialinoneheatofwire.~".Thegeneral:conclusion reached'as aresult'of theinvesti-gationoftheatypicalweldwirediscovery isthatitisvery~unlikelythatothersimil'arconditions:exist inanyreactorpressurevesselwelds.Furthermore, theshoppractices whichhaveevolvedovertheyearsandwhicharecurrently ineffectvirtually eliminate thepossibility thatavesselfabricated todaymight.containoff-chemistry weldmaterials.
| | Project. The purpose of the records investigation was to determine the cause and extent of the mixed weld. wire problem. |
| ESIyouhaveanyquestions concerning theenclosedmaterial, please.contactme(Ext.2817)orNilliamR.Speight(Ext.2902)oSmystaff-.I~~Verytruly.yoursJamesH.,Taylor1183Jlg'nclosures:
| | . The investigation also included a review of test results from |
| As.stated.ManagerLaceIIJET/ZN:cc:.R.,B;,Borsum-B4NRep.BethesdaOffice.~~;lI'~rI~~~~ri~i~rI~'Cwi,
| | .actual reactor vessel production weld. seams to the extent these welds could be investigated, and from reactor vessel surveillance through November 1978. 'n material tests. The investigation covered the period from 1966 accordance with IE Bulletin 78-12A, our response is given on a generic basis and ao attempt was made to correlate specific weldments with heats of filler wire. |
| | ~ . |
| | ~5 |
| | ~QOVp3 p gag I |
| | ~ ~ |
| | ~'Bah:ock Z Wilcox Company / Estabhshed 1867 |
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| 'Babcock:.wilcox PowerGeneration Group,P.O.Box1260,t.ynohburg, Va.24505Telephone: | | /~ pl f4fttyp, |
| (804)384-5111March'3,1979.(r1(westinghouse NuclearEner'gySystemsMonroeville NuclearCenter,NorthernPike.Road...';.:-.:*Yanroevil le,PennsylvanTa15146Attn:Hr.G..M.LarrbSub':ResponsetoNRCIEBulletinNo.78-.12&12A:.Gentlemen! | | ,5 'lrl |
| E'nclosed foryourinformation arethree(3)copiesofareportentitled, "RecordsInvestigation ReportRelatedtoOff-Chemistry MeldsinMaterialSurveillance Specimens andResponsetoNuclearRegulatory Corrmission IEBulletinNo.78-12&Supplement No.78-12A.." | | |
| 8&MContractNo.-MestinhousePurchaseOrderNo.610-0110Ro~><(craiba54-F"49758" SP610-0115-'pawr8~<~I54-g-55180-BP 610-0116f1)~~p.,~.54-g-61741-BP 6100116t2~""PaŽ~54g61742BP610-0144- | | 'r bcock8.V/ilcox |
| ..54-g-70140-BP
| | ~ .r |
| '10-0152'4-g-70141-SP 640-0001546-CVJ-150100-SP 640-0002546-CVD-150101-BP 640-0004546-CYJ-161057 640-0005546-CYQ-161058 640-0012,546-CYJ-195410-BP.640-0014546-CY0-195411-B P640-0016, 546-CY0-195412-BP 40-00617546CYJ161Q62BNplanstosubmitthereporttoNRCbyMarch23,1979.Theinformation, presented inthisreportre'presents anintensive recordsinvestigation whichincludesthefollowing reactorpressurevesselsandclosureheadsmanufactured specifically forMestinghouse. | | * I |
| 4(JHT:dsfEnclosures (3').';-.'.;:."cc:K.B.Stuckey-"fRt:Vernon | | %QW r Hr. Nayne G. Reinmuth March 13, 1979 |
| ~I(wgEncl.) | | :0 P |
| ,4r('(%~(I-Verytruly'yours, | | The records investigation,.provides considerable support for the hypothesis that- the. presence of atypical chemistry condition in the Crystal River 3 surveillance'lock is an isolated event. |
| ~yZ>,.~~r'P,r.+~~~JamesH..Tay1orPanager,.Licensing'(~~The83bcock8(%'itoog Con'.r.;.nv It'.(;tnhttrn( | | ~" |
| (tt.7 rllP}} | | involving a small 'amount. of. material in one heat of wire. |
| | . The general: conclusion reached'as a result'of the investi- |
| | ~ |
| | gation of the atypical weld wire discovery is that unlikely that other simil'ar conditions:exist in any reactor it is very pressure vessel welds. Furthermore, the shop practices which have evolved over the years and which are currently in effect virtually eliminate the possibility that a vessel fabricated today might. contain off-chemistry weld materials. |
| | ESIyou have any questions concerning the enclosed material, please. contact me (Ext. 2817) or Nilliam R. Speight (Ext. 2902) oS my staff-. |
| | I ~ ~ |
| | Very truly .yours James H., Taylor I I |
| | . Manager Lace JET/ZN |
| | :cc:. R., B;, Borsum - B4N Rep. Bethesda Office. 1183Jlg'nclosures: |
| | As. stated |
| | ~ ~ |
| | ;l |
| | ~ r i~ir I' ~ |
| | ~ |
| | ' CI wi, I~ ~ ~ |
| | ~ r |
| | |
| | Babcock:.wilcox Power Generation Group |
| | , P.O. Box 1260, t.ynohburg, Va. 24505 Telephone: (804) 384-5111 March'3, 1979 . |
| | ( |
| | r 1 |
| | westinghouse Nuclear Ener'gy Systems ( |
| | Monroeville Nuclear Center, Northern Pike. Road ... '; .:- .: |
| | * Yanroevil le, Pennsyl vanTa 15146 Attn: Hr. G.. M. Larrb Sub': Response to NRC IE Bulletin No. 78-.12 & 12A |
| | :.Gentlemen! |
| | E'nclosed for your information are three (3) copies of a report entitled, "Records Investigation Report Related to Off-Chemistry Melds in Material Surveillance Specimens and Response to Nuclear Regulatory Corrmission IE Bulletin No. 78-12 & Supplement No. 78-12A.." |
| | The information, presented in this report re'presents an intensive records investigation which includes the following reactor pressure vessels and closure heads manufactured specifically for Mestinghouse. |
| | 8&M Contract No. -Mestin house Purchase Order No. |
| | 610-0110 Ro~> <( c r aiba 54-F"49758" SP 610-0115 'paw r 8~< ~ I 54-g-55180-BP t2 ~"" |
| | 610-0116 610 0116 f1) ~~ Pa'~p.,~. 54-g-61741-BP 54 g 61742 BP 610-0144- 54-g-70140-BP |
| | '10-0152 '4-g-70141-SP 640-0001 546-CVJ-150100-SP 640-0002 546-CVD-150101-BP 640-0004 546-CYJ-161057 640-0005 546-CYQ-161058 640-0012 , |
| | 546-CYJ-195410- BP |
| | . 640-0014 546-CY 0-195411-B P 640-0016, 6 40-00 17 546-CY0-195412-BP 546 CYJ 161Q62 BN plans to submit the report to NRC by March 23, 1979. |
| | Very truly'yours, |
| | ~yZ>, .~~ ror'P, r.+~~ |
| | ~ Panager, James H .. Tay1 |
| | .Li censing 4( |
| | JHT:dsf Enclosures (3').';- . '.;:." r( ' ( % ~ |
| | I |
| | ( |
| | cc: K. B. Stuckey -"fRt:Vernon |
| | ~ I (wgEncl.) |
| | ,4 |
| | ~ ~ |
| | ( |
| | The 83bcock 8(%'itoog Con'.r.;.nv I t'.(;tnhttrn( (t t .7 |
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| | r ll P}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999
Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
ML20217F9941999-10-15015 October 1999
Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review
IR 05000244/19990081999-10-14014 October 1999
Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy
ML20217J5171999-10-13013 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed
3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
ML20212L0771999-10-0404 October 1999
Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii)
ML20217D6551999-10-0101 October 1999
Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025
ML20212J8481999-10-0101 October 1999
Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
IR 05000244/19992011999-09-24024 September 1999
Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML20212F7251999-09-23023 September 1999
Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable
ML20212F7331999-09-23023 September 1999
Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition
ML20212E6741999-09-21021 September 1999
Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
ML20212F3141999-09-13013 September 1999
Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations
ML20211L9081999-09-0303 September 1999
Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3
ML20211Q7581999-09-0101 September 1999
Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML20211G7031999-08-30030 August 1999
Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval
ML20211G7111999-08-30030 August 1999
Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
ML20210Q4511999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006
ML20210P0741999-08-0505 August 1999
Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
ML20210G8551999-07-27027 July 1999
Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999
Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999
Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested
1999-09-30
[Table view]
Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20058A1421990-09-20020 September 1990
Forwards Application for Withholding Proprietary Info from Public Disclosure,Per 10CFR2.790(b)(4)
ML17262A2061990-09-0505 September 1990
Forwards Proprietary Presentation Overheads for Facility Feedwater Control Sys.Encl Withheld
ML19325E9001989-10-19019 October 1989
Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response
ML20245K4861989-06-0606 June 1989
Advises That Valves in Photographs & Mfg Records Forwarded to Licensee Identified as Mfg by Velan,Inc.Marking Info Provided by Florida Power Corp Matches Perfectly W/Licensee Mfg Records
ML17309A4001987-12-0303 December 1987
Requests Proprietary Status for LOFTTR2 Analysis of Potential Radiological Consequences Following Steam Generator Tube Rupture at Re Ginna Nuclear Power Plant, Per 10CFR2.790.Affidavit Encl
ML20137J4101985-07-12012 July 1985
Sanitized Version of EP Rahe Confirming 850711 Telcon Re Former Employee Allegations.Westinghouse Intends to Cooperate Fully.Internal Review in Progress.Preliminary Review Revealed No Actual Safety Deficiencies
ML17254A8811984-07-20020 July 1984
Requests Withholding of Proprietary Revised DNBR Licensing Basis for Steam Break Analysis at Reduced Pressure.Encl Withheld (Ref 10CFR2.790)
ML17255A7741984-04-10010 April 1984
Submits Application to Withhold Proprietary Info in Cook Apr 1984 Ltr to Denton (Ref 10CFR 2.790).Affidavit Encl
ML17255A7091984-03-16016 March 1984
Application for Withholding Proprietary Responses to Questions Re Applications for Amend to Tech Specs Dtd Dec 1983
ML19320C9681980-07-0909 July 1980
Responds to 800703 Inquiry Re Process Whereby Draft Evaluation Performed by Franklin Inst & Containing Possibly Proprietary Info Could Be Released to Rochester Gas & Electric.Westinghouse Has Proprietary Agreement W/Util
ML19305A8421980-03-11011 March 1980
Forwards Preliminary Rept,Transient Assessment Rept,Reactor Trip on 800226, in Partial Response to NRC 800304 Request for Info Re Power Upsets at B&W Plants
ML19296D3781980-02-26026 February 1980
Forwards Structural Effects of ATWS Overpressure Transients in Byron Jackson Primary Pumps, Addendum to Analysis of B&W Nuclear Steam Sys Response to ATWS Events.
ML17249A7171980-02-0505 February 1980
Advises of Authorization to Use Previously Furnished Affidavits for Current Reload Review Re Cycle 10. Same Proprietary Matl Being Used
ML19210D3021979-11-20020 November 1979
Responds to NRC 791114 Request Re Consideration of Effect of Employing NRC Ramp Rate Correlation as Contained in Draft NUREG-0630 to Determine Burst Temp Curve for Use in LOCA Analyses
ML19210D3551979-11-16016 November 1979
Submits Evaluation of Potential Impact of Heating Rate Dependent Burst Temp on C-E Licensing Calculations.Peak Cladding for C-E Operating Plants Would Not Be Significantly Affected by Heating Rate Dependent Rupture Temp Model
ML17244A6941979-03-13013 March 1979
Forwards Response to IE Bulletins 78-12 & 78-12A, Records Investigation Rept Re Off-Chemistry Welds in Matl Surveillance Specimens & Responses to Bulletin 78-12&78-12A Suppl. Concludes Crystal River 3 Isolated Event
ML19319D1441977-01-24024 January 1977
Forwards Proposed Revision to B&W ECCS Evaluation Model. Supersedes 761216 Revision.After NRC Approval,Change to Be Incorporated Into BAW-10104A,Revision 1, B&W ECCS Evaluation Model.
1990-09-05
[Table view] |
Text
I Babcock ~V~ilco" ! Power Generation GroUp P.O. Box 1260, Lynchbur 8, Va. 24505 Telephone: (804) 384-5111
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- .March 13, 1979 Mr. Payne G. Re'inmu'th" ~.s.'-c, f
Of ic e o f Inspection and 'n f ore ement U. S; Nuclear Regulatory Commission Nashington, D.C.. 2055$
Subject-: Response to IE Bulletin Nos., 78-12 and 78-12A'ear Nr Reinmuth Enclosed for your information are three (3) copies of'ur report entitled, "Records Investigation Report Related'o Off-Chemistry Nelds in i~faterial Surveillance Specimens and.
Resppnses to Bulletin 78-12. and.78-12A Supplement", which we have prepared for. our customers in order to facilitate their .
responses to the bulletins. The report is basically divided into three (3) parts: (1) an introduction and. summary of the..............
weld, wire issue; (2) 'general information to support. the con-clusions we have reached; and (3) specific responses to the information requested by the bulletins. Appendices containing copies. of BIN chemical analysis requirements and weld filler wire qualification tests are included as supporting information.
The information in the appendices has been selected based on your request. at a January 16, 1979 meeting in Nt. Vernon, Indiana.
This report. describes the investigations that vere made as a result of discovering an off-chemistry condition in a reactor vessel surveillance specimen for the Crystal River 3 (CR-3)
Project. The purpose of the records investigation was to determine the cause and extent of the mixed weld. wire problem.
. The investigation also included a review of test results from
.actual reactor vessel production weld. seams to the extent these welds could be investigated, and from reactor vessel surveillance through November 1978. 'n material tests. The investigation covered the period from 1966 accordance with IE Bulletin 78-12A, our response is given on a generic basis and ao attempt was made to correlate specific weldments with heats of filler wire.
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The records investigation,.provides considerable support for the hypothesis that- the. presence of atypical chemistry condition in the Crystal River 3 surveillance'lock is an isolated event.
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involving a small 'amount. of. material in one heat of wire.
. The general: conclusion reached'as a result'of the investi-
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gation of the atypical weld wire discovery is that unlikely that other simil'ar conditions:exist in any reactor it is very pressure vessel welds. Furthermore, the shop practices which have evolved over the years and which are currently in effect virtually eliminate the possibility that a vessel fabricated today might. contain off-chemistry weld materials.
ESIyou have any questions concerning the enclosed material, please. contact me (Ext. 2817) or Nilliam R. Speight (Ext. 2902) oS my staff-.
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Very truly .yours James H., Taylor I I
. Manager Lace JET/ZN
- cc:. R., B;, Borsum - B4N Rep. Bethesda Office. 1183Jlg'nclosures:
As. stated
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Babcock:.wilcox Power Generation Group
, P.O. Box 1260, t.ynohburg, Va. 24505 Telephone: (804) 384-5111 March'3, 1979 .
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westinghouse Nuclear Ener'gy Systems (
Monroeville Nuclear Center, Northern Pike. Road ... '; .:- .:
- Yanroevil le, Pennsyl vanTa 15146 Attn: Hr. G.. M. Larrb Sub': Response to NRC IE Bulletin No. 78-.12 & 12A
- .Gentlemen!
E'nclosed for your information are three (3) copies of a report entitled, "Records Investigation Report Related to Off-Chemistry Melds in Material Surveillance Specimens and Response to Nuclear Regulatory Corrmission IE Bulletin No. 78-12 & Supplement No.78-12A.."
The information, presented in this report re'presents an intensive records investigation which includes the following reactor pressure vessels and closure heads manufactured specifically for Mestinghouse.
8&M Contract No. -Mestin house Purchase Order No.
610-0110 Ro~> <( c r aiba 54-F"49758" SP 610-0115 'paw r 8~< ~ I 54-g-55180-BP t2 ~""
610-0116 610 0116 f1) ~~ Pa'~p.,~. 54-g-61741-BP 54 g 61742 BP 610-0144- 54-g-70140-BP
'10-0152 '4-g-70141-SP 640-0001 546-CVJ-150100-SP 640-0002 546-CVD-150101-BP 640-0004 546-CYJ-161057 640-0005 546-CYQ-161058 640-0012 ,
546-CYJ-195410- BP
. 640-0014 546-CY 0-195411-B P 640-0016, 6 40-00 17 546-CY0-195412-BP 546 CYJ 161Q62 BN plans to submit the report to NRC by March 23, 1979.
Very truly'yours,
~yZ>, .~~ ror'P, r.+~~
~ Panager, James H .. Tay1
.Li censing 4(
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