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| {{#Wiki_filter:RIORITY1CCELERATED RIDSPl(OCESSliG) | | {{#Wiki_filter:RIORITY 1 CCELERATED RIDS Pl(OCESSliG) |
| REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9505300226 DOC.DATE: | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9505300226 DOC.DATE: 95/05/22 NOTARIZED: |
| 95/05/22NOTARIZED: | | YES FACIL:50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva AUTH.NAME AUTHOR AFFILIATION BYRAM,R.G. |
| YESFACIL:50-388 Susquehanna SteamElectricStation,Unit2,Pennsylva AUTH.NAMEAUTHORAFFILIATION BYRAM,R.G.
| | Pennsylvania Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET 05000388 P |
| Pennsylvania Power&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000388P | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Providescoreshroudinspscope6scheduleforSSESUnit2Rinresponsetorequirements ofGL94-03Eascommitted toinutil941219ltr.IDISTRIBUTION CODE:A018DCOPIESRECEIVED:LTR QENCLLSIZE:g>'g~0NOTES:RECIPIENT IDCODE/NAME PM'INTERNA.&3m01NRR/DE/EMEB NRR/DSSA/SRXB EXTERNAL:
| | Provides core shroud insp scope 6 schedule for SSES Unit 2 R in response to requirements of GL 94-03 E as committed to in util 941219 ltr.I DISTRIBUTION CODE: A018D COPIES RECEIVED:LTR Q ENCL L SIZE: g>'g~0 NOTES: RECIPIENT ID CODE/NAME PM'INTERNA.&3m 01 NRR/DE/EMEB NRR/DSSA/SRXB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PM/CARPENTERPG |
| NRCPDRCOPIESLTTRENCL1111111111RECIPIENT IDCODE/NAME PM/CARPENTERPG
| | ~NRR/DE/EMCB NRR/DOPS/OECB COPIES LTTR ENCL 1 1 1 1 1 1 D C U VOTE TO ALL"RIDS" RECIPIENT'TS: |
| ~NRR/DE/EMCB NRR/DOPS/OECB COPIESLTTRENCL111111DCUVOTETOALL"RIDS"RECIPIENT'TS: | | PLEASE HELP US TO REDUCE iVKSTE!CONTACT TIIE DOCL'ifEYT COA'TROL DESk, ROO!1f Pl-37 (EXT.504-0033)TO ELIMINATE YOl'R iAifi P!IOif DISTRIBUTIOY LIS'I'S I'OR DOCL'8 I Ei'I'S YOL'OY" I'!TED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8 Pennsylvania Power&Light Company Two North Ninth Street~Allentown, PA 18101-1179 |
| PLEASEHELPUSTOREDUCEiVKSTE!CONTACTTIIEDOCL'ifEYT COA'TROLDESk,ROO!1fPl-37(EXT.504-0033)TOELIMINATE YOl'RiAifiP!IOifDISTRIBUTIOY LIS'I'SI'ORDOCL'8IEi'I'SYOL'OY"I'!TED!TOTALNUMBEROFCOPIESREQUIRED:
| | ~610/774-5151 Robert G.Byram Senior Vice President-Nuclear 610/774-7502 Fax: 610/774-5019 MAY 22 1995'.S.Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-136 Washington, DC 20555 SUSQUEHANNA STEAM E<LECTRIC STATION UNIT 2 7TH REFUEL AND INSPECTION OUTAGE CORE<SHROUD INSPECTION SCOPE AND SCHEDULE Docket No.50-388 |
| LTTR8ENCL8 Pennsylvania Power&LightCompanyTwoNorthNinthStreet~Allentown, PA18101-1179
| |
| ~610/774-5151 RobertG.ByramSeniorVicePresident | |
| -Nuclear610/774-7502 Fax:610/774-5019 MAY221995'.S.NuclearRegulatory Commission Attn.:DocumentControlDeskMailStationP1-136Washington, DC20555SUSQUEHANNA STEAME<LECTRIC STATIONUNIT27THREFUELANDINSPECTION OUTAGECORE<SHROUDINSPECTION SCOPEANDSCHEDULEDocketNo.50-388 | |
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| ==Reference:== | | ==Reference:== |
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| 1)PLA-4233fromMr.RG.ByramtoUSNRC,"InlerimResponsetoGenericLelter94-03,"datedDecember19,1995.2)USNRCLetterpornMr.C.PoslusnytoMr.RG.Byrarn,GenericLetter94-03,GenericLetter94-03,"Intergranular StressCorrosion CrackingofCoreShroudsinBP'Rs,"Pennsylvania PowerandLightCompany,Susquehanna SteamElectricStation,Units1and2(TAC¹s.M90112andM90113)datedMarch23,1995.ThisletterprovidesPPEcL'scoreshroudinspection scopeandscheduleforSusquehanna SteamElectricStation(SSES)Unit2inresponsetotherequirements ofGenericLetter94-03andascommitted tointhereferenced PLA-4233. | | 1)PLA-4233 from Mr.RG.Byram to USNRC,"Inlerim Response to Generic Lelter 94-03,"dated December 19, 1995.2)USNRC Letter porn Mr.C.Poslusny to Mr.RG.Byrarn, Generic Letter 94-03, Generic Letter 94-03,"Intergranular Stress Corrosion Cracking of Core Shrouds in BP'Rs," Pennsylvania Power and Light Company, Susquehanna Steam Electric Station, Units 1 and 2 (TAC¹s.M90112 and M90113)dated March 23, 1995.This letter provides PPEcL's core shroud inspection scope and schedule for Susquehanna Steam Electric Station (SSES)Unit 2 in response to the requirements of Generic Letter 94-03 and as committed to in the referenced PLA-4233.PPEcL commits to perform the scope of inspections as defined in the BWR Core Shroud Inspection and Flaw Evaluation Guidelines prepared by General Electric Nuclear Energy for the BWROG Vessel Internals Inspection Project, GENE-523-113-0S94 for Category B plants.For SSES Unit 2, this inspection will consist of ultrasonic inspection of all accessible areas of welds H3, H4, H5, H6B, and H7.The inspections will be conducted during the Unit 2-7th Refueling and Inspection Outage scheduled to begin in September, 1995.In the case where no significant cracking (defined as greater than 10%of the weld length)is found in any of the above five welds, PP&L will scan the remaining three welds (H1, H2, and H6A)as permitted by the outage schedule.In the case where significant cracking is found, the 9505300226 950522, PDR ADOCK;,<05000338 |
| PPEcLcommitstoperformthescopeofinspections asdefinedintheBWRCoreShroudInspection andFlawEvaluation Guidelines preparedbyGeneralElectricNuclearEnergyfortheBWROGVesselInternals Inspection Project,GENE-523-113-0S94 forCategoryBplants.ForSSESUnit2,thisinspection willconsistofultrasonic inspection ofallaccessible areasofweldsH3,H4,H5,H6B,andH7.Theinspections willbeconducted duringtheUnit2-7thRefueling andInspection Outagescheduled tobegininSeptember, 1995.Inthecasewherenosignificant cracking(definedasgreaterthan10%oftheweldlength)isfoundinanyoftheabovefivewelds,PP&Lwillscantheremaining threewelds(H1,H2,andH6A)aspermitted bytheoutageschedule.
| | ..P,~'''PDR P1$ FILE R41-2 PLA-4317 Document Control Desk scope of inspection will be increased to include all accessible areas of welds Hl, H2, and H6A as shown in the Attachment to this PLA.We plan to use the BWR Core Shroud Distributed Ligament Length Computer Program, as we did for Unit 1, to assess structural integrity if any cracking is discovered. |
| Inthecasewheresignificant crackingisfound,the9505300226 950522,PDRADOCK;,<05000338
| | This program will be used to help determine if any repairs are necessary to ensure the structural integrity of the Unit 2 shroud.If repairs are necessary, they will be performed in accordance with the BWR Core Shroud Repair Design Criteria and Flaw Evaluation Guidelines prepared by General Electric Nuclear Energy for the BWROG Vessel Internals Project.We will submit results from the Unit 2 core shroud inspection to the NRC within 30 days following the completion of all inspections accomplished during the Unit 2 outage.Please call our Mr.James B.Wesner if you have any questions. |
| ..P,~'''PDRP1$ FILER41-2PLA-4317DocumentControlDeskscopeofinspection willbeincreased toincludeallaccessible areasofweldsHl,H2,andH6AasshownintheAttachment tothisPLA.WeplantousetheBWRCoreShroudDistributed LigamentLengthComputerProgram,aswedidforUnit1,toassessstructural integrity ifanycrackingisdiscovered. | | Very truly yours, R..am At nt copy: NRC Region I Ms.M.Banerjee NRC Sr.Resident Inspector Mr.C.Poslusny, Jr.NRC Sr.Project Manager AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA |
| Thisprogramwillbeusedtohelpdetermine ifanyrepairsarenecessary toensurethestructural integrity oftheUnit2shroud.Ifrepairsarenecessary, theywillbeperformed inaccordance withtheBWRCoreShroudRepairDesignCriteriaandFlawEvaluation Guidelines preparedbyGeneralElectricNuclearEnergyfortheBWROGVesselInternals Project.WewillsubmitresultsfromtheUnit2coreshroudinspection totheNRCwithin30daysfollowing thecompletion ofallinspections accomplished duringtheUnit2outage.PleasecallourMr.JamesB.Wesnerifyouhaveanyquestions.
| | ): SS)I, ROBERT C.BYRAM, being duly sworn according to law, state that I am Sr.Vice President-Nuclear of Pennsylvania Power 8r Light Company and that the facts set forth on the attached PLAP317 regarding the Unit 2 7th Refuel and Inspection Outage Core Shroud Inspection Scope and Schedule are true and correct to the best of my knowledge, information and belief.Ro C.Byram Sr.Vi Pr sident-Nuclear ls Q/beor met of ay , 1995 Sworn to and subscribed Nota Public Notarial Seal Martha C.Sedora, Notary Public Atlontown, Lehioh County My Cornmlsslon Expirea Jan.16, 1998 Member, P |
| Verytrulyyours,R..amAtntcopy:NRCRegionIMs.M.BanerjeeNRCSr.ResidentInspector Mr.C.Poslusny, Jr.NRCSr.ProjectManager AFFIDAVIT COMMONWEALTH OFPENNSYLVANIA
| | ~J l/P J'I ATTAOIMENt TO FLAHJI 7 Hl TO OJZDE QPPI&t RDC TYPICAL SAPLING&ALL CPOSS SECTION SUSQUEHANNA SHROUD gQRf,C,SHIT,OO I,lPO.I CHMENT TO PLA-4317 O4 TOP GUIOE SUPPORT RING 0-S Hl ANSTEC APERTURE CARD H4 Atso Available on Aperture Card INSIDE%SOLE 9p, CORE PLATE SLPPORT RING H6-8 H9 VESSEL ltALL RPV QQOLQ QPPORT CYLINDER SI TYPICAL SHROUO&ALL CROSS SECTION SUSQUEHANNA |
| ):SS)I,ROBERTC.BYRAM,beingdulyswornaccording tolaw,statethatIamSr.VicePresident-NuclearofPennsylvania Power8rLightCompanyandthatthefactssetforthontheattachedPLAP317regarding theUnit27thRefuelandInspection OutageCoreShroudInspection ScopeandSchedulearetrueandcorrecttothebestofmyknowledge, information andbelief.RoC.ByramSr.ViPrsident-NuclearlsQ/beormetofay,1995Sworntoandsubscribed NotaPublicNotarialSealMarthaC.Sedora,NotaryPublicAtlontown, LehiohCountyMyCornmlsslon ExpireaJan.16,1998Member,P | | ~ HFPOUD CORE.C, RSOUO 40OI<ANG4A S g\ 1 N I'I'C.~ U 0 0 I I v (}} |
| ~Jl/PJ'I ATTAOIMENt TOFLAHJI7HlTOOJZDEQPPI&tRDCTYPICALSAPLING&ALLCPOSSSECTIONSUSQUEHANNA SHROUDgQRf,C,SHIT,OO I,lPO.I CHMENTTOPLA-4317O4TOPGUIOESUPPORTRING0-SHlANSTECAPERTURECARDH4AtsoAvailable onApertureCardINSIDE%SOLE9p,COREPLATESLPPORTRINGH6-8H9VESSELltALLRPVQQOLQQPPORTCYLINDERSITYPICALSHROUO&ALLCROSSSECTIONSUSQUEHANNA | |
| ~ HFPOUDCORE.C, RSOUO40OI<ANG4A Sg\ 1NI'I'C.~ U00IIv(}} | |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999
Forwards Change J to SSES Security Training & Qualification Plan.Without Encl
ML20217K4391999-10-18018 October 1999
Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl
ML20217H3301999-10-14014 October 1999
Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr
ML18152B3541999-10-12012 October 1999
Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info
ML20216K1681999-10-0101 October 1999
Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein
ML20212J9101999-10-0101 October 1999
Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date
ML18152B3391999-09-27027 September 1999
Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC
ML20212G5091999-09-22022 September 1999
Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6)
ML18152B3331999-09-17017 September 1999
Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves.
ML18152B6671999-09-17017 September 1999
Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03
ML18152B3341999-09-16016 September 1999
Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations
ML18040B2951999-09-0808 September 1999
Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early
ML20211N2531999-09-0808 September 1999
Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl
ML20211L9151999-09-0101 September 1999
Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
ML18152B4471999-09-0101 September 1999
Requests That NRC Remove Listed Labels from Distribution
ML20211J2211999-08-31031 August 1999
Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl
ML20211H4131999-08-27027 August 1999
Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint
PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999
Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl
ML20138B3241999-08-23023 August 1999
Forwards Draft Response to Question 1 Re NAPS USI A-46
ML20211D9041999-08-20020 August 1999
Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal
ML20211B3871999-08-17017 August 1999
Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project
ML20210T0671999-08-13013 August 1999
Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation
ML20210Q9841999-08-12012 August 1999
Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13
ML20210Q7661999-08-0606 August 1999
Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas
ML18152B4081999-08-0606 August 1999
Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves.
ML18152B4091999-08-0505 August 1999
Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d)
ML20210N2921999-08-0505 August 1999
Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits
ML20210J8861999-08-0202 August 1999
Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate
ML20210F6121999-07-28028 July 1999
Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal
ML18152B3971999-07-26026 July 1999
Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02
ML20209E7621999-07-0909 July 1999
Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines
05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999
Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl
ML18040A9741999-07-0808 July 1999
Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant
ML20209E3711999-07-0202 July 1999
Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations
ML18152B4401999-07-0101 July 1999
Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co
ML18152B4371999-06-24024 June 1999
Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections
ML20196G2581999-06-23023 June 1999
Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity
ML20212J2951999-06-22022 June 1999
Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS
ML20196F1151999-06-22022 June 1999
Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program
ML18152B4361999-06-22022 June 1999
Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06
ML20196G2211999-06-21021 June 1999
Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included
ML20195J7011999-06-15015 June 1999
Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP
ML20195J1391999-06-11011 June 1999
Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit
ML20207G5051999-06-0707 June 1999
Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created
PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999
Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21
ML18152B4301999-06-0303 June 1999
Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002
ML20195C6601999-06-0101 June 1999
Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program
ML20207C9851999-05-28028 May 1999
Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted
ML18152B4261999-05-28028 May 1999
Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request
ML18152B4221999-05-27027 May 1999
Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999
Forwards Change J to SSES Security Training & Qualification Plan.Without Encl
ML20217K4391999-10-18018 October 1999
Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl
ML20217H3301999-10-14014 October 1999
Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr
ML18152B3541999-10-12012 October 1999
Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info
ML20216K1681999-10-0101 October 1999
Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein
ML18152B3391999-09-27027 September 1999
Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC
ML20212G5091999-09-22022 September 1999
Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6)
ML18152B3331999-09-17017 September 1999
Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves.
ML18152B6671999-09-17017 September 1999
Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03
ML18152B3341999-09-16016 September 1999
Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations
ML18040B2951999-09-0808 September 1999
Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early
ML18152B4471999-09-0101 September 1999
Requests That NRC Remove Listed Labels from Distribution
ML20211L9151999-09-0101 September 1999
Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
ML20211H4131999-08-27027 August 1999
Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint
PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999
Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl
ML20138B3241999-08-23023 August 1999
Forwards Draft Response to Question 1 Re NAPS USI A-46
ML20211D9041999-08-20020 August 1999
Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal
ML20210Q9841999-08-12012 August 1999
Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13
ML20210Q7661999-08-0606 August 1999
Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas
ML18152B4081999-08-0606 August 1999
Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves.
ML18152B4091999-08-0505 August 1999
Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d)
ML20210J8861999-08-0202 August 1999
Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate
ML20210F6121999-07-28028 July 1999
Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal
ML18152B3971999-07-26026 July 1999
Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02
ML20209E7621999-07-0909 July 1999
Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines
05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999
Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl
ML18040A9741999-07-0808 July 1999
Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant
ML18152B4401999-07-0101 July 1999
Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co
ML18152B4371999-06-24024 June 1999
Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections
ML18152B4361999-06-22022 June 1999
Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06
ML20196F1151999-06-22022 June 1999
Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program
ML20212J2951999-06-22022 June 1999
Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS
ML20195J7011999-06-15015 June 1999
Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP
PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999
Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21
ML18152B4301999-06-0303 June 1999
Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002
ML20195C6601999-06-0101 June 1999
Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program
ML20207C9851999-05-28028 May 1999
Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted
ML18152B4261999-05-28028 May 1999
Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request
ML18152B4221999-05-27027 May 1999
Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2
ML18152B4231999-05-26026 May 1999
Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable
ML18040A9731999-05-24024 May 1999
Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant
ML20195B2181999-05-20020 May 1999
Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790
ML20195B5381999-05-14014 May 1999
Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs
ML18152A3701999-05-13013 May 1999
Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion
ML20206G9481999-05-0303 May 1999
Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp
ML20206H0221999-05-0303 May 1999
Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl
ML18040B2901999-04-30030 April 1999
Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed
ML20205T1181999-04-16016 April 1999
Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999
ML20205P1891999-04-0808 April 1999
Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included
ML20205K3631999-04-0505 April 1999
Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1
1999-09-08
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Text
RIORITY 1 CCELERATED RIDS Pl(OCESSliG)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9505300226 DOC.DATE: 95/05/22 NOTARIZED:
YES FACIL:50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva AUTH.NAME AUTHOR AFFILIATION BYRAM,R.G.
Pennsylvania Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET 05000388 P
SUBJECT:
Provides core shroud insp scope 6 schedule for SSES Unit 2 R in response to requirements of GL 94-03 E as committed to in util 941219 ltr.I DISTRIBUTION CODE: A018D COPIES RECEIVED:LTR Q ENCL L SIZE: g>'g~0 NOTES: RECIPIENT ID CODE/NAME PM'INTERNA.&3m 01 NRR/DE/EMEB NRR/DSSA/SRXB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PM/CARPENTERPG
~NRR/DE/EMCB NRR/DOPS/OECB COPIES LTTR ENCL 1 1 1 1 1 1 D C U VOTE TO ALL"RIDS" RECIPIENT'TS:
PLEASE HELP US TO REDUCE iVKSTE!CONTACT TIIE DOCL'ifEYT COA'TROL DESk, ROO!1f Pl-37 (EXT.504-0033)TO ELIMINATE YOl'R iAifi P!IOif DISTRIBUTIOY LIS'I'S I'OR DOCL'8 I Ei'I'S YOL'OY" I'!TED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8 Pennsylvania Power&Light Company Two North Ninth Street~Allentown, PA 18101-1179
~610/774-5151 Robert G.Byram Senior Vice President-Nuclear 610/774-7502 Fax: 610/774-5019 MAY 22 1995'.S.Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-136 Washington, DC 20555 SUSQUEHANNA STEAM E<LECTRIC STATION UNIT 2 7TH REFUEL AND INSPECTION OUTAGE CORE<SHROUD INSPECTION SCOPE AND SCHEDULE Docket No.50-388
Reference:
1)PLA-4233 from Mr.RG.Byram to USNRC,"Inlerim Response to Generic Lelter 94-03,"dated December 19, 1995.2)USNRC Letter porn Mr.C.Poslusny to Mr.RG.Byrarn, Generic Letter 94-03, Generic Letter 94-03,"Intergranular Stress Corrosion Cracking of Core Shrouds in BP'Rs," Pennsylvania Power and Light Company, Susquehanna Steam Electric Station, Units 1 and 2 (TAC¹s.M90112 and M90113)dated March 23, 1995.This letter provides PPEcL's core shroud inspection scope and schedule for Susquehanna Steam Electric Station (SSES)Unit 2 in response to the requirements of Generic Letter 94-03 and as committed to in the referenced PLA-4233.PPEcL commits to perform the scope of inspections as defined in the BWR Core Shroud Inspection and Flaw Evaluation Guidelines prepared by General Electric Nuclear Energy for the BWROG Vessel Internals Inspection Project, GENE-523-113-0S94 for Category B plants.For SSES Unit 2, this inspection will consist of ultrasonic inspection of all accessible areas of welds H3, H4, H5, H6B, and H7.The inspections will be conducted during the Unit 2-7th Refueling and Inspection Outage scheduled to begin in September, 1995.In the case where no significant cracking (defined as greater than 10%of the weld length)is found in any of the above five welds, PP&L will scan the remaining three welds (H1, H2, and H6A)as permitted by the outage schedule.In the case where significant cracking is found, the 9505300226 950522, PDR ADOCK;,<05000338
..P,~PDR P1$ FILE R41-2 PLA-4317 Document Control Desk scope of inspection will be increased to include all accessible areas of welds Hl, H2, and H6A as shown in the Attachment to this PLA.We plan to use the BWR Core Shroud Distributed Ligament Length Computer Program, as we did for Unit 1, to assess structural integrity if any cracking is discovered.
This program will be used to help determine if any repairs are necessary to ensure the structural integrity of the Unit 2 shroud.If repairs are necessary, they will be performed in accordance with the BWR Core Shroud Repair Design Criteria and Flaw Evaluation Guidelines prepared by General Electric Nuclear Energy for the BWROG Vessel Internals Project.We will submit results from the Unit 2 core shroud inspection to the NRC within 30 days following the completion of all inspections accomplished during the Unit 2 outage.Please call our Mr.James B.Wesner if you have any questions.
Very truly yours, R..am At nt copy: NRC Region I Ms.M.Banerjee NRC Sr.Resident Inspector Mr.C.Poslusny, Jr.NRC Sr.Project Manager AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA
): SS)I, ROBERT C.BYRAM, being duly sworn according to law, state that I am Sr.Vice President-Nuclear of Pennsylvania Power 8r Light Company and that the facts set forth on the attached PLAP317 regarding the Unit 2 7th Refuel and Inspection Outage Core Shroud Inspection Scope and Schedule are true and correct to the best of my knowledge, information and belief.Ro C.Byram Sr.Vi Pr sident-Nuclear ls Q/beor met of ay , 1995 Sworn to and subscribed Nota Public Notarial Seal Martha C.Sedora, Notary Public Atlontown, Lehioh County My Cornmlsslon Expirea Jan.16, 1998 Member, P
~J l/P J'I ATTAOIMENt TO FLAHJI 7 Hl TO OJZDE QPPI&t RDC TYPICAL SAPLING&ALL CPOSS SECTION SUSQUEHANNA SHROUD gQRf,C,SHIT,OO I,lPO.I CHMENT TO PLA-4317 O4 TOP GUIOE SUPPORT RING 0-S Hl ANSTEC APERTURE CARD H4 Atso Available on Aperture Card INSIDE%SOLE 9p, CORE PLATE SLPPORT RING H6-8 H9 VESSEL ltALL RPV QQOLQ QPPORT CYLINDER SI TYPICAL SHROUO&ALL CROSS SECTION SUSQUEHANNA
~HFPOUD CORE.C,RSOUO 40OI<ANG4A S g\1 N I'I'C.~U 0 0 I I v (
