Similar Documents at Ginna |
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Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23258A1382023-09-18018 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010 IR 05000244/20230052023-08-31031 August 2023 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report IR 05000244/20234012023-08-15015 August 2023 LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only) IR 05000244/20230022023-08-0303 August 2023 LLC - Integrated Inspection Report 05000244/2023002 ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 IR 05000244/20234022023-07-19019 July 2023 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only) RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23135A0412023-05-15015 May 2023 2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report ML23121A0482023-05-0101 May 2023 R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000244/20230012023-04-26026 April 2023 LLC - Integrated Inspection Report 05000244/2023001 ML23100A0302023-04-10010 April 2023 2023 10 CFR 50.46 Annual Report ML23114A1152023-03-29029 March 2023 Electronic Reporting of Exposure Data for 2022 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23075A0872023-03-15015 March 2023 R. E. Ginna Nuclear Power Plant - Project Manager Assignment ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000244/20220062023-03-0101 March 2023 Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006) ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23060A1622023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators ML22287A0692023-02-0808 February 2023 R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23031A2992023-02-0707 February 2023 R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request ML23010A0112023-02-0101 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000244/20223012023-01-20020 January 2023 Initial Operator Licensing Examination Report 05000244/2022301 IR 05000244/20220122023-01-12012 January 2023 LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012 ML22362A0382022-12-28028 December 2022 R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22348A2062022-12-14014 December 2022 Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator 2024-02-05
[Table view] Category:Technical Specification
MONTHYEARRS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin RS-21-082, Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC2021-08-13013 August 2021 Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC ML20339A2212020-11-20020 November 2020 Technical Specifications Bases, Rev 101 JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19150A5112019-05-10010 May 2019 Revision 90 to Technical Specification Bases ML18176A3272018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... ML15166A0752015-06-0404 June 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1212904852012-04-20020 April 2012 LAR File for Rod Indication/Attachment 1 Mrpi LAR ML11129A0132011-05-0303 May 2011 Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286) ML0908901912009-03-23023 March 2009 R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0835308062009-02-23023 February 2009 R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits ML0834600512008-12-0404 December 2008 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision of Tech Spec. 3.9.3 to Allow Refueling Operations Inside Containment with Both Personnel Hatch Air Lock Doors Open Under Administrative Control, and Obtain Regulatory Rev ML0723504322007-08-16016 August 2007 R. E. Ginna - Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0604802442006-02-15015 February 2006 Technical Specification Pages Re Relaxed Axial Offset Control ML0534702012005-12-0808 December 2005 R. E. Ginna Nuclear Power Plant, 5.5.1 Offsite Dose Calculation Manual (ODCM) ML0519501232005-07-0707 July 2005 License Amendment Request Regarding Extended Power Uprate ML0513003302005-04-29029 April 2005 License Amendment Request Regarding Adoption of Relaxed Axial Offset Control (RAOC) ML0507702042005-03-14014 March 2005 R. E. Ginna, Replacement Pages Associated with the Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0507603812005-03-10010 March 2005 R. E. Ginna - Application for Amendment to Facility Operating License Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension ML0506203062005-03-0101 March 2005 R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints ML0426800472004-09-22022 September 2004 Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints ML0402307292004-01-22022 January 2004 R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2 ML18142B9481977-12-22022 December 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18142B9501977-11-21021 November 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18143A2121977-01-0606 January 1977 R. E. Ginna - Forwards Copies of Application for Amendment to Operating License ML18142B9881976-01-21021 January 1976 R. E. Ginna - Forwards Copies of Proposed Change to Technical Specifications to Change Surveillance Requirements for Integrated Leakage Rate from Containment, and Copies of Application for Amendment to Operating License. ML18142C0271974-10-15015 October 1974 Transmittal of Rge Application for Amendment to Technical Specifications for Inspection Requirement for Hydraulic Snubbers ML18142C0281974-10-15015 October 1974 Letter Submitted Application for Amendment to Technical Specification, Consisting a Request for a Change to the License Maybe Amended to Add Inspection Requirement for Steam Generator Tubes ML18142C0291974-09-30030 September 1974 Letter Requesting a Proposed Change to the Technical Specification to Increase the Indicated Water Level to the Accumulators to Conform to Accident Analysis Assumptions ML18142C0321974-07-0909 July 1974 Submittal of Application for Amendment to Applicant'S Technical Specifications, Describing Duties and Responsibilities of the Plant Review and Audit Groups 2022-08-10
[Table view] Category:Amendment
MONTHYEARRS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML18176A3272018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML0908901912009-03-23023 March 2009 R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0835308062009-02-23023 February 2009 R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits ML0834600512008-12-0404 December 2008 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision of Tech Spec. 3.9.3 to Allow Refueling Operations Inside Containment with Both Personnel Hatch Air Lock Doors Open Under Administrative Control, and Obtain Regulatory Rev ML0723504322007-08-16016 August 2007 R. E. Ginna - Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0604802442006-02-15015 February 2006 Technical Specification Pages Re Relaxed Axial Offset Control ML0534702012005-12-0808 December 2005 R. E. Ginna Nuclear Power Plant, 5.5.1 Offsite Dose Calculation Manual (ODCM) ML0519501232005-07-0707 July 2005 License Amendment Request Regarding Extended Power Uprate ML0507603812005-03-10010 March 2005 R. E. Ginna - Application for Amendment to Facility Operating License Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension ML0506203062005-03-0101 March 2005 R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints ML0426800472004-09-22022 September 2004 Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints ML0402307292004-01-22022 January 2004 R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2 ML18142B9481977-12-22022 December 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18142B9501977-11-21021 November 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18143A2121977-01-0606 January 1977 R. E. Ginna - Forwards Copies of Application for Amendment to Operating License ML18142B9881976-01-21021 January 1976 R. E. Ginna - Forwards Copies of Proposed Change to Technical Specifications to Change Surveillance Requirements for Integrated Leakage Rate from Containment, and Copies of Application for Amendment to Operating License. ML18142C0271974-10-15015 October 1974 Transmittal of Rge Application for Amendment to Technical Specifications for Inspection Requirement for Hydraulic Snubbers ML18142C0281974-10-15015 October 1974 Letter Submitted Application for Amendment to Technical Specification, Consisting a Request for a Change to the License Maybe Amended to Add Inspection Requirement for Steam Generator Tubes ML18142C0291974-09-30030 September 1974 Letter Requesting a Proposed Change to the Technical Specification to Increase the Indicated Water Level to the Accumulators to Conform to Accident Analysis Assumptions ML18142C0321974-07-0909 July 1974 Submittal of Application for Amendment to Applicant'S Technical Specifications, Describing Duties and Responsibilities of the Plant Review and Audit Groups 2022-08-10
[Table view] |
Text
'EC DISTRIBUTION FOR PART 50 DOCI<ET MATERIAL (TCMPO BAR Y FO I)M)CONTROL NQ: FILE'".0j!:
Leooeuf, La->'o, Leiby E: llac";,ae Ifashin~ton, D.C.2003G 10-15-7(>10-15-76 DATE OF DOC DATE R EC'D LTR TWX RPT OTHER TO: Ilr.C."-.se ORIG CC OTHFR SENT AEC PDR SENT LOCAL PDR~r CI.ASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO: '50-gal)DESCRIPTION:
Ltr si v:-.iitted on behalf of the Dochester Gas 6 Blectric Cor~........re our 10-1-73 ltr......trans the folio~;inc:
ENCLOSURES:
Abel<<or t tldt to Tech Specs, notarized 10-i~i-7Jiy requestin~
that Appendix A be a-.end d to add'an inspection requires>ent fo: Hydra'ilic snubbers.PLANT NAME: PH Ginna Unit P, 1 (JiG cys rec'd)FOR ACTIOiU/liUFORMATION
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WASHINGTON, D.C.20036 ARVIN K.UPTON LEONARD" M.TROSTKN WILLIAM O.DOUB (AI)M.))AAYIA))I)I KUGKNK B.THOMAS)JR.HARRY H.VOIGT LKX K.LARSON WASHIHOTOH PA)ITNC)IS October 15, 1974 ONC CHASC MANHATTAN PLACA NEW YORK, N.Y.IOOOS WASHINGTON TCLCPHONC COC-BTC 8888~D CASLC ADDRCSS Mr.Edson G.Case Acting Director Directorate of Licensing U.S.Atomic Energy Commission Washington, D.C.20545 ef 7 l 5 197yg lQQI Otg~tw~~I~ON O.C./Re: Rochester Gas 6 Electric Corporation R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244
Dear Mr.Case:
Transmitted herewith are three (3)signed originals and nineteen (19)copies of Rochester Gas S Electric Cor-poration's Application for Amendment to Technical Specifi-cations and forty (40)copies of the proposed change.A safety evaluation of the proposed change is also transmit-ted.The proposed change will add to the technical speci-fications an inspection requirement for hydraulic snubbers in response to a letter from Donald J.Skovholt, dated October 1, 1973.A Certificate of Service is also enclosed.got;K~()gg Pg(Ill'ery truly yours, q l4RakuL LeBoeuf, Lamb, Leiby S MacRae Attorneys for Rochester Gas S Electric Corporation I Enclosures l II',~t' et'g)'CT LG lg74 TQ'fg pgt<rg~~+~Ulfggy"Culgggpg Gp">>>Sectlca C UNITED STATES OF AMERICA ATOMIC ENERGY COMMI S 0-c~o(.gyygQb~p+Qo aq4 (R.E.Ginna Nuclear Power Pla t-)>++Unit No.1)gS)APPLICATION FOR AMENDME TO TECHNICAL SPECIFICATIONS In the Matter of Rochester Gas 6 Electric Cor o io~);b+4 D et No.50-244 Pursuant to Section 50.90 of the regulations of the Atomic Energy Commission, Rochester Gas 6 Electric Cor-poration ("RGSE"), holder of Provisional Operating License No.DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that License be amended to add to the technical specifications an inspection requirement for hydraulic snubbers in response to a letter from Donald J.Skovholt, Assistant Director for Operating Reactors, dated October 1, 1973.The proposed technical specification change and a safety evaluation, which demonstrates that the proposed change does not involve a significant.
hazards consideration, are set forth in Attachment A.The proposed change would not authorize any change in the types or any increase in the amounts of effluents or any change in the authorized power level of the facility.WHEREFORE, Applicant respectfully requests that 1 3 Appendix A to Provisional Operating License No.DPR-18 be amended in the form attached hereto as Attachment.
A.ROCHESTER GAS 6 ELECTRIC CORPORATION Leon D.White, Jra Vice President, Electric and Steam Production Subscribed and sworn to before me this gpss~day of October, 1974.pt tary P lic GARY L.REISS<',NOTAIIY PUBLIC, State of N.Y.h'lonroe Co.Mir'Commission Expires hiarch 30, 19.p~
'I)!I eW h~'/i'z~g ATTACHMENT A Add the following to Table 4.1-2,"Minimum Frequencies for Equip-ment and Sampling Tests": TEST FREQUENCY 19.Hydraulic Snubber s Fluid Level Check Each refueling for Class II Components and Visual Inspection shutdown Saf e Evaluation A program of hydraulic shock suppressor (snubber)inspection and upgrading was instituted at Ginna in September 1973 to insure the proper operation of the units.Several units fabricated by Bergen-Paterson had been found at other facilities to have experienced seal deterioration.
It has been determined by Bergen-Paterson that acceptable seal performance will be obtained if ethylene-propolene seals are used instead of the originally supplied polyurethane seals.Bergen-Paterson has also recommended inspection at each refueling interval to insure acceptable performance.
Based on the surveillance results of the past twelve months, inspection at each refueling interval will insure acceptable performance for Bergen-Paterson hydraulic snubbers with ethylene-propolene seals and for the hydraulic snubbers fabricated by other manufacturers.
All Bergen-Paterson units inside:containment and six of the thirteen Bergen-Paterson units outside containment now have the ethylene-propolene seals.The remaining seven Bergen-Paterson units outside containment still contain polyurethane material and will be inspected at monthly intervals until such time as the polyurethene is replaced.by ethylene-propolene Of these smen units, two have been, in,.service
,...for approximately one year and exhibit no signs of leakage and five do not exhibit significant leakage.No failure is expected in these units since they are in low radiation and low temperature areas.
~'1 hS\
BEFORE THE UNXTED STATES ATOMIC ENERGY COMMXSSION OCT lS>SSC 9."~4'RUIC Etl.RCY 7 COHQ j$5 f QRcgllia)"py
~ALII Sedlau A Xn the Matter of))Rochester Gas 6 Electric Corporation
)(R.E.Ginna Nuclear Power Plant,)Unit No.1))Docket No.50-244 CERTIFICATE OF SERVICE I hereby certify that I have served a document entitled"Application for Amendment to Technical Specifications" by mailing copies thereof first.class, postage prepaid, to each of the following persons this 15th day of October,,:1974.
Chairman, Atomic Safety and Licensing Board Panel U.S.Atomic Energy Commission Washington, D.C.20545 Atomic Safety and Licensing Appeal Board U.S.Atomic Energy Commission Washington, D.C.20545 Mr.Michael Slade 1250 Crown Point.Drive Webster, New York 14580 Warren B.Rosenbaum, Esq.One Main Street East 707 Wilder Building Rochester, New York 14614 C.John Clemente, Esp.New York State Department.
of Commerce 99 Washington Avenue Albany, New York 12210 Howard M.Wilchins, Esp.Counsel, Regulatory Staff U.S.Atomic Energy Commission Washington, D.C.20545 Edward Luton, Esp.Atomic Safety and Licensing Board Panel U.S.Atomic Energy Commission Washington, D.C.20545 j.0660 I k I'I 4 S I~~k 4 Thomas W.Reilly, Esq.Atomic Safety and Licensing Board Panel U.S.Atomic Energy Commission Washington, D.C.20545 Dr.Franklin C.Daiber Department of Biological Sciences University of Delaware Newark, Delaware 19711 Dr.A.Dixon Callihan , Union Carbide Corporation P.O.Box Y Oak Ridge, Tennessee 37830 Mr.Bruce E.Thompson Supervisor, Town of Ontario 528 Furnace Road Ontario, New York 14519 Dr.Emmeth A.Luebke Atomic Safety and Licensing Board Panel U.S.Atomic Energy Commission Washington, D.C.20545 Hope M.Babcock LeBoeuf, Lamb, Leiby&MacRae Attorneys for Rochester Gas S Electric Corporation I5 A.1~I lj f II V1 I 1 1'J II R I I y',-'I'II'I I