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| | page count = 6 | | | page count = 6 |
| | project = TAC:MA1202 | | | project = TAC:MA1202 |
| | stage = Approval | | | stage = RAI |
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| ==Dear Mr. Roche:== | | ==Dear Mr. Roche:== |
| Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity" was issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Reaulations (10 CFR Part 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits. | | Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity" was issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Reaulations (10 CFR Part 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits. |
| After reviewing your response, the NRC issued a letter dated August 6,1996 acknowledging receipt of your response and noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups' programs relative to your plant. We further indicated that a plant-specific TAC Number may be opened to review this material. Following issuance of these letters, the BWR Vessel and Intemals Project (BWRVIP) submitted the report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)." This report incluoed bounding assessments of new data from 1) the Combustion Engineering Owners Group (CEOG) database released in July 1997 which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are / | | After reviewing your response, the NRC issued a {{letter dated|date=August 6, 1996|text=letter dated August 6,1996}} acknowledging receipt of your response and noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups' programs relative to your plant. We further indicated that a plant-specific TAC Number may be opened to review this material. Following issuance of these letters, the BWR Vessel and Intemals Project (BWRVIP) submitted the report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)." This report incluoed bounding assessments of new data from 1) the Combustion Engineering Owners Group (CEOG) database released in July 1997 which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are / |
| documented in NRC Inspection Report 99901300/97-01 dated January 28,1998; 3) FTI's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September 20,1996; and 4) Chicago Bridge and Iron quality assurance records. ; | | documented in NRC Inspection Report 99901300/97-01 dated January 28,1998; 3) FTI's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September 20,1996; and 4) Chicago Bridge and Iron quality assurance records. ; |
| New data for one vessel fabricated by Hitachi was also included in the BWRVIP report. | | New data for one vessel fabricated by Hitachi was also included in the BWRVIP report. |
Letter Sequence RAI |
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MONTHYEARML20217K6421998-04-29029 April 1998 Forwards Request for Addl Info Re Response to GL 92-01,rev 1,suppl 1 Issued in May 1995 Requesting Licensees to Perform Review of RPV Structural Integrity Assessments to Identify, Collect & Report New Data Pertinent to Analysis Project stage: RAI ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 Project stage: Other 1998-04-29
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20206U3551999-02-0505 February 1999 Refers to Concerns Recipient Expressed to V Dricks on 990126 Related to Oyster Creek About Event Which Occurred on 970801 & About Administrative Control of EDG Vendor Manuals ML20199L2471999-01-22022 January 1999 Discusses GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 & Gpu Nuclear 960418 & 981202 Responses for Ocngs.Informs That Based on Confirming GL 96-01 Commitments Review Effort Closed ML20199G8241999-01-12012 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20199G8631999-01-0707 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20198B2121998-12-0909 December 1998 Advises of Planned Insp Efforts Resulting from Licensee Irpm Review.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20196C6001998-11-25025 November 1998 Forwards Insp Rept 50-219/98-09 on 980914-1025 & Notice of Violation.Inspector Identified That Security Force Member Left Running Unlocked Vehicle Unattended in Protected Area ML20195G8901998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9101998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G8801998-11-17017 November 1998 Responds to to Senator Lt Conners Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9181998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community IR 05000219/19980031998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/98-03 Issued on 980717.Corrective Actions Will Be Examined During Future Insp of Licensed Program ML20196D1431998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20195C4111998-11-0606 November 1998 Discusses 980825 Gpu Submittal of Proposed Mod for Ocnpp Core Support Plate Which Involved Installation of Wedges During 17R Outage.Licensee Intends to Use Recommendations of BWRVIP-25 & BWRVIP-50.SE Accepting Proposed Mod Encl ML20195B7981998-11-0505 November 1998 Discusses Alternative Evaluation of Flaws in Ferritic Piping.Core Spray Sys Test Line Was Concluded to Have Acceptable Level of Quality & Safety ML20155C6881998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7201998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7051998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7481998-10-29029 October 1998 Responds to Ltr to Assemblyman Morgan, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6241998-10-29029 October 1998 Responds to Ltr to Senator Connors,Dtd 980926,re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7021998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6661998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6841998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6721998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7251998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7371998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6981998-10-29029 October 1998 Responds to Recent Ltr to Senator Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6481998-10-29029 October 1998 Responds to Ltr to Sentor Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7091998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C8781998-10-29029 October 1998 Informs That Oyster Creek Generating Station Operating License,Paragraph 2.C.5 Re Evaluation of Core Spray Internals Insp Requires Authorization from NRC Before Plant Is Restarted from Refueling Outage.Plant Restart Authorized ML20155C7301998-10-29029 October 1998 Responds to Ltr to 9th District Legislative Offices, Re Possible Closure of Oyster Creek Nuclear Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155D2041998-10-26026 October 1998 Forwards Synopsis of 980604 Investigation Rept 1-98-027 Re Possible Discrimination Against Employee for Contacting NRC in Nov 1997 with Security & Safety Concerns ML20154Q9021998-10-20020 October 1998 Forwards Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted.Licensee Have Established & Implemented Effective Programs for Initial & Continuing Training of Workers, Especially Those Having Access to Controlled Areas ML20154L3001998-10-14014 October 1998 Forwards Safety Evaluation Re Reduced Scope of IGSCC Insp, During Refueling Outage 17 ML20154J8251998-10-0707 October 1998 Discusses Concerns Raised to NRC on 980913 Re Oyster Creek. Thoroughness of NRC Insps as Documented in NRC Integrated Insp Rept 50-219/98-03 Was of Concern 1999-09-30
[Table view] |
Text
JD 4 /7
- r j
2 NUCLEAR REGULATORY COMMISSION '
WASHINGTON, D.C. enmaa ann $
% , , , ,o April 29, 199G Mr. Michael B. Roche !
Vice President and Director '
GPU Nuclear, Inc.
Oyster Creek Nuclear Generating P.O. Box 388 Forked River, NJ 08731
SUBJECT:
REQUEST FOR ADCITiONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT OYSTER CREEK NUCLEAR GENERATING STATION (TAC NO. MA1202)
Dear Mr. Roche:
Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity" was issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Reaulations (10 CFR Part 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits.
After reviewing your response, the NRC issued a letter dated August 6,1996 acknowledging receipt of your response and noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups' programs relative to your plant. We further indicated that a plant-specific TAC Number may be opened to review this material. Following issuance of these letters, the BWR Vessel and Intemals Project (BWRVIP) submitted the report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)." This report incluoed bounding assessments of new data from 1) the Combustion Engineering Owners Group (CEOG) database released in July 1997 which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are /
documented in NRC Inspection Report 99901300/97-01 dated January 28,1998; 3) FTI's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September 20,1996; and 4) Chicago Bridge and Iron quality assurance records. ;
New data for one vessel fabricated by Hitachi was also included in the BWRVIP report.
The staff is requesting that you re-evaluate the RPV weld chemistry values that you have previously submitted as part of your licensing basis in light of the information presented in the 9M CEOG, FTl and BWRVIP reports. The staff expects that you will assess this new information to l
' determine whether any values of RPV weld chemistry need to be revised for your facility.
Therefore, in order to provide a complete response to items 2,3 and 4 of the GL, the NRC requests that you provide a response to the enclosed request for additional information within 90 da*,s of receipt of this letter, if a question does not apply to your situation, please indicate this in your RAI response along with your technical basis and, per GL 92-01, Rev.1, Supp.1, provide a certification that previously submitted evaluations remain valid.
,sosO4ooss95042, PDR ADOCK 0300o219 ME CENTER mov '
P PM ,
. l l
M. Roche 2 The information provided will be used in updating the Reactor Vessel integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identified data could result in the '
need for license amendments in order to maintain compliance with 10 CFR Part 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If additional license amendments or assessments are necessary, the attached requests that you provide a schedule for such submittels.
If you should have any questions regarding this request, please contact me at (301) 415-3041.
Sincerely, ORIGINAL SIGNED BY Ronald B. Eaton, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects - 1/11
{
Office of Nuclear Reactor Regulation i
Enclosure:
Request for AdditionalInformation cc w/ encl: See next page Distnbution:
Docket File PUBLIC PDl-3 Rdg. JZwolinski i TClark ACRS REaton CHehl OGC l
DOCUMENT NAME: G:WIA1202.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attichment/ enclosure "N" = No copy ,
OFFICE PDI-3/LA , jn l~ PDI-3/PR//// l PDI-3/PD ll j NAME TClark i hW REstorf P CThomas Ut%
DATE l
04/7/'/98 04/ # 1 /98 04/ M /98 ' l l OFFICIAL RECORD COPY i
I i
I
l.
i M. Roche GPU Nuclear, Inc.
cc:
Emest L Blake, Jr., Esquire
. Shaw, Pittman, Potts & Trowbridge t 2300 N Street, NW Washington, DC 20037 Regional Administrator, Region I l U.S. Nuclear Regulatory Commission i
475 Allendale Road King of Prussia, PA 19406-1415 BWR Licensing Manager
! GPU Nuclear Corporation i Upper Pond Road i
Parsippany, NJ 07054 i
Mayor Lacey Township l
818 West Lacey Road i
Forked River, NJ 08731 l Licensing Manager Oyster Creek Nuclear Generating Station l Mail Stop: Site Emergency Bldg.
j l P.O. Box 388 i l Forked River, NJ 08731 l
l Resident inspector l
clo U.S. Nuclear Regulatory Commission i P.O. Box 445 Forksd River, NJ 08731 Kent Tosch, Chief New Jersey Department of l Environmental Protection '
l Bureau of Nuclear Engineering l
CN 415 l
Trenton, NJ 08825 l.
I
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REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY Section 1.0: A=massment of Best-Enfimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2-6 Reacter Pressure Vessel integrity issues (BWRVIP-46)".
Based on this information, in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
~
An evaluation of the bounding assessment in the reference above and its applicability to the determination of the best-estimate chemistry for all of your RPV beltiine welds. Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table i for each RPV beltline weld material. If the limiting material for your vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.
With respect to your response to this question, the staff notes that some issues regarding the evaluation of the data were discussed in a public meeting between the staff, NEl, and industry representatives on November 12,1997. A summary of this meeting is documented in a meeting summary dated November 19,1997, " Meeting Summary for November 12,1997 Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses" (Reference 1). The information in Reference 1 may be useful in helping you to prepare your response.
In addition to the issues discussed in the referenced meeting, you should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. This is an important consideration when a mean-of-the-means or coil-weighted average approach is determined to be the appropriate method for determining the best-estimate chemistry. If a weld (or welds) were fabricated as weld qualification specimens by the same manufacturer, within a short time span, using similar welding input parameters, and using the same coil (or coils in the case of tandem arc welds) of weld consumables, it may be appropriate to consider all chemistry samples from that weld (or welds) as samples from "one weld" for the purposes of best-estimate chemistry determination, if information is not available to confgm the aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, the best-estimate chemistry should be evaluated both by assuming the data came from *one weld" and by assuming that the data came from an appropriate number of" multiple welds". A justification should then be provided for which assurrption was chosen when the best-estimate chemistry was determined.
Section 2.0: P-T Limit Evaluation if the limiting material for your plant changes or if the adjusted reference temperature for the limiting materialincreases as a result of the above evaluations, provide the revised RT,, value for the limiting material. In addition, if the adjusted RTa value increased, provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.
Enclosure
l 2
l Reference
.1.
Memorandum dated November 19,1997, from Keith R. Wichman to Edmund J. Sullivan
" Meeting Summary for November 12,1997 Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses."
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