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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-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. ML22234A1692022-08-22022 August 2022 R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-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. ML22124A3162022-05-27027 May 2022 Summary of Combined Regulatory Audit in Support of Risk Informed Completion Times in Technical Specifications LAR and to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power ML22108A2482022-04-18018 April 2022 R.E.. Ginna Nuclear Power Plant - License Amendment Request to Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML22052A0132022-02-21021 February 2022 Application to Revise R. E. Ginna Technical Specification 3.1.8, Physics Tests Exception - Mode 2 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments ML21287A0062021-10-14014 October 2021 Supplemental Information No.1 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, - Risk-Informed Categorization and Treatment of Structu JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21140A3242021-05-20020 May 2021 R. E. Ginna Nuclear Power Plant - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML21141A0092021-05-20020 May 2021 R. E. Ginna Nuclear Power Plant - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments ML20056E9582020-02-25025 February 2020 R. E. Ginna Nuclear Power Plant, License Amendment Request to Add a One-Time Note for Use of Alternate Residual Heat Removal Methods RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions 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-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19045A2822019-02-15015 February 2019 R. E. Ginna Nuclear Power Plant - License Amendment Request (LAR) to Revise Technical Specification (TS) 5.5.15, Containment Leakage Rate Testing Program, for Permanent Extension of Type a Leak Rate Test Frequencies ML18158A1292018-06-0505 June 2018 License Amendment Request: Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML17321A1072017-11-16016 November 2017 R. E. Ginna, License Amendment Request to Revise Technical Specifications for Selected Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Channels to Incorporate Bypass Test Capability ML17304A9842017-10-31031 October 2017 R. E. Ginna Nuclear Power Plant - License Amendment Request to Revise Technical Specifications Surveillance Requirement SR 3.8.4.3, DC Sources - Modes 1, 2, 3, and 4, to Allow for a Modified Performance Discharge Test ML17186A2332017-06-30030 June 2017 License Amendment Request - Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition ML17164A1482017-05-31031 May 2017 Enclosure 3C - EAL Basis Document for R.E. Ginna Nuclear Power Station ML17164A1502017-05-31031 May 2017 Enclosure 3D - EAL Front Matter for R.E. Ginna Nuclear Power Station ML17164A1512017-05-31031 May 2017 Enclosure 3E - Procedure Matrix for R.E. Ginna Nuclear Power Station ML17164A1472017-05-31031 May 2017 Enclosure 3B - EAL Red-Line Basis Document for R.E. Ginna Nuclear Power Station RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16236A3002016-08-22022 August 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding 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).... ML16035A0152016-02-0404 February 2016 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. ML15210A3142015-07-29029 July 2015 License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel 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) RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 82014-08-29029 August 2014 License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8 ML13228A2652013-08-14014 August 2013 Independent Spent Fuel Storage Installations Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act & License Amendment Request ML13232A1562013-08-0606 August 2013 ISFSI, Nine Mile Point, Units 1, 2 and ISFSI and R.E. Ginna, and ISFSI, Application for Order Approving Transfer of Operating Authority and Conforming License Amendments. Part 1 of 2 ML13093A0642013-03-28028 March 2013 License Amendment Request Pursuant to 10 CFR 50.90: Adoption of NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML11138A1592011-05-12012 May 2011 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R.E. Ginna, Application for Approval of Indirect Transfer of Control of Licenses ML1020404732010-07-16016 July 2010 R. E. Ginna - Request for Approval of the Constellation Energy Nuclear Group Cyber Security Plan ML0926800602009-09-18018 September 2009 R. E. Ginna - License Amendment Request: Administrative Revision of Inservice Test Program Technical Specification ML0920905382009-07-23023 July 2009 R. E. Ginna - 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 ML0906304262009-02-26026 February 2009 R. E. Ginna and Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation - Supplement to Application for an Order Approving License Transfers and Conforming License Amendment Request 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 ML0903302752009-01-22022 January 2009 R. E. Ginna - Amendment to Application to Revise Technical Specification Limiting Conditions of Operation (Lcos) 3.3.2, 3.3.4, and 3.8.1 ML0902901012009-01-22022 January 2009 Application for an Order Approving License Transfers and Conforming License Amendment Request 2023-05-22
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Text
DISTRIBUTION AFTER ISSUANCE OF OPERATQfG LZCEVLSE NRCPOAM 19S VA NUCLSAR ASGULATORY COMMISSIO COOLEST NUMSSR IZ-Tgl o~
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! TO: FROM: OATS OP OOCVMSNT LeBoeuf, Lamb, Leiby & MacRae 11/28/77 Mr. Edson Go Case Washington, D C. C4LTS RSCSIVSO Leboeuf, Lamb Leiby & MacRae ill 29 77
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License No DPR-18 Appl for Amend: tech specs proposed chanse-concerning request for modification of reporting requirements and request for modification of tech spec tabi;e 3 '3-1 to add a shock suppressor to the list of safety related shock suppressors. ~ ~ ~ ~
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WAsHINGTQN, D. C. 20036 TELEPHONE 202 e67 7600 CASLE ADDRESS LEON A. ALLEN. JR. CAMERON F. MACRAE a RANDALL J. LaBDEVF,JR. I929 I976 CAMERON F. MACRAC 111 a LESWIN,WASHINGTON, D, C, JOSEPH C.BACHELDCR.IIE ADRIAN C. LEIBY I962 I976 ERNEST S. BALLARD.JR. OCRARD A.MAHCR TELEX: ee027e G. S. PETER BCROEN a SHCILA H. MARSHALL OEOFFRY D.C.BCST JAM CS G. Mc E LROY DAVID P. DICKS JAMES P. MCGRANCRY, JR ea OF COVNSCL TAYLOR R. BRIGGS PHILIP PALMER MCOVIOAN CHARLES N. BURGER JAMES O'ALLEY,JR.a ARVIN C. UPTON THOMAS C.BURKE J MICHAEL PARISH ROGER D.FCLDMAN ee
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JOHN A.RVDY EVOENC R. FIDELLa a PAUL G.RUSSELL JACOB FRIEDLANDER HAROLD M. SEIDEL Iso DONALD J.GREENE CHARLES Pi SIFTON BROADWAY JAMEs A.GREERo11a HALCYON O. SKINNER 10006 JoHN I.. OROSE a JOSEPH S.STRAUSS NEW YORK, N ~ Y.
DOUGLAS W HAWKS CARL D.HOBELMAN SAMUEL M.SUDDEN TELKPNDNL 2I2 269 II00 MICHAEL IOVCNKO AYw EUGENE B. THOMAS'R ea JAMES F. JOHNSON, LEONARD M. TROSTEN+ S CABLE ADDRESS RONALD D.JONES HARRY H. VOIOT' a LEX K.LARSON+a H RICHARD WACHTEL LCBWIN,NEW YORK ORANT S.LEWIS OERARD P. WATSON 1 November 28, 1977 TELEX: 423eIS n n
+RCSIDCNT PARTNERS WASHINGTON OFFICE S ADMITTED TO THC DISTRICT OF COLUMBIA BAR V gX/
Mr. Edson G. Case Acting Director ',',,l 'c'~',. 'OP+
6 p Office of Nuclear Reactor Regulation
~ fP U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Rochester Gas and Electri tion R. E. Ginna Nuclear Power Station, Unit No. 1 Docket No. 50-24'4'ear Mr. Case:
As counsel for Rochester Gas and Electric Corpora-tion, we hereby transmit three (3) signed originals and nineteen (19) copies of a document entitled, "Application for Amendment to Operating License," together with forty (40) copies of proposed changes to Technical Specifications and accompanying safety evaluation. This Application seeks to amend Technical Specification 6.9 set forth in Appendix A to Provisional Operating License No. DPR-18, by modifying the requirements for reporting information to the Commission and to modify Technical Specification Table 3.13-1 by adding a shock suppressor to the list of safety related shock suppres-sors ~
A Certificate of Service showing service of these documents upon the persons listed therein is also enclosed.
Enclosures
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )
)
ROCHESTER GAS AND ELECTRIC ) Docket No. 50-244 CORPORATION )
(R. E. Ginna Nuclear Power )
Station, Unit No. 1) )
CERTIFICATE OF SERVICE I hereby certify that I have served a document entitled, "Application for Amendment to Operating License" together with a copy of the proposed changes to Technical Specifications and accompanying safety evaluation by mailing copies thereof first. class, postage prepaid to each of the following persons this 28th day of November, 1977:
Chairman, Atomic Safety L. Dow Davis, IV, Esp.
and Licensing Board Panel Office of the Executive Legal U.S. Nuclear Regulatory Director Commission U.S. Nuclear Regulatory Washington, D. C. 20555 Commission Washington, D. C. 20555 Atomic Safety and Licensing Appeal Board Edward Luton, Esq.
U.S. Nuclear Regulatory Atomic Safety and Licensing Commission Board Washington, D. C. 20555 U.S. Nuclear Regulatory Commission Mr. Michael L. Slade Washington, D. C. 20555 1250 Crown Point Drive Webster, New York 14580 Dr. Emmeth A. Luebke Atomic Safety and Licensing Warren B. Rosenbaum, Esp. Board One Main Street East U.S. Nuclear Regulatory 707 Wilder Building Commission Rochester, New York 14614 Washington, D. C. 20555
Dr. A. Dixon Callihan Jeffrey L. Cohen, Esq.
Union Carbide Corporation New York State Energy P. O. Box Y Office Oak Ridge, Tennessee 37830 Swan Street Building Core I, Second Floor Mr. Robert N. Pinkney Empire State Plaza Supervisor Albany, New York 12223 Town of Ontario 107 Ridge Road West Ontario, New York 14519 Lex K. Larson LeBoeuf, Lamb; Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant, )
Unit No. 1) )
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RG&E"), holder of Provisional Operating License No. DPR-18, hereby requests that the Technical Specification 6.9 set forth in Appendix A to that license be amended to modify the requirements for reporting of information to the Commission. This request for a change in the Technical Specifications is submitted in accordance with a letter from A. Schwencer, Chief, Operating Reactors Branch 51, dated September 16, 1977. Additionally, a change is requested in Technical Specification Table 3.13-1 to add a shock suppressor to the list of safety related shock suppressors.
The proposed technical specification change is set forth in Attachment, A to this Application. A safety evaluation is set forth in Attachment B. This evaluation also demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.
I*
WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation L.D. White, Jr.
Vice President, Electric and Steam Production Subscribed and sworn to before me on this Jj 5ay of November 1977.
SHARON G. CAVALER(
NOTARY PUBLIC, State of N.Y. Monroe
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19+/
Coun'Ay Commission Expires March 30,
'1 P
Attachment A
- l. Replace pages 6.9-1, 6.9-2, 6.9-3 and 6.9-10 with the enclosed revised pages 6.9-1, 6.9-2, 6.9-3, and 6.9-10.
- 2. Replace page 3.13-.4 with enclosed revised page 3.13-4.
"I lf l II E
6.9 Re ortin Re uirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.
6.9.1 Routine Reports a ~ Startup Report. A summary report. of plant startup and power escalation testing shall be submitted following (1)'receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications, that may have signifi-cantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
Startup reports shall be submitted within (1) 90 days following. completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
Startup Report does not cover all three events (i.e, If the initial criticality, completion of startup test program, and resumption or, commencement of commercial power operation), supplementary reports shall be submitted at least every .three months until all three events have been completed.
- b. Mo'n'th'1 Opera't'in'e 'o'r't.'outine reports of operating statgstxcs and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 by the tenth of each month following the calendar month covered by the report.
The monthly report shall include a narrative summary of operating experience describing the operation of the facility, including'ajor safety related maintenance for the monthly period, except that safety related maintenance 6.9-1 PROPOSED
4 4 S l
performed during the refueling outage may be reported in the monthly report for thq month following the end,of the outage rather than each month during the outage.
6.9.2. Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
6,9-2 PROPOSED
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I N T E N T I 0 N A L L Y B L A N i<
6.9-3 PROPOSED
(2) Annually: A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according. to work and job functions, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket, dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose peed no/ be a@counted for. Xn the aggregate, at least 00% of the total whqle body dose received from external sources shall be assigned to specific major work functions.
(NOTE: This tabulation supplements the requirements of Section 20.407 of 10 'CFR Part 20.)
6.9-10 PROPOSED
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Table >.13-1 (Continued)
Safeu Nelahe5 Shock Su ressors S~nubbers-Accessi.ble or Esoecially Inaccessible High Radiation** Difficult to Snubber:hark No. Piping S stem (A or I) Zone Remove .
iMW-25 "A" Aux. Feedwater No No AFK-2 6 ".A" Aux. Feedwater No' AFW-27 "A" Aux. Feedwater No No "A"-Aux. Feedwater No AFW-28 No 4J "A" Aux. Feedwater No No AFW- 29 I
AFW-31 "A" Aux. Feedwater No No AFW-49 "A" Aux. Feedwater No No FW-9 "B" Feedwater No Yes FW-30 .
"B" Feedwater No No It FW-80 B II Feedwater No No FW-81 "B" Feedwater No No F'."-82 Fec."w; ter No No 0
'0 0
0
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ATTACHMENT B By letter dated September 16, 1977, the NRC requested that the Ginna Technical Specification requirements for the Annual Operating Report be revised. According to that letter, a review of reporting requirements had been performed and it had been determined that much of the information now included in the Annual Operating Report could be deleted and objectives.
still meet the desired NRC Accordingly, the proposed change would delete- the present requirements for an Annual Operating Report. Since the NRC has expressed a desire to continue receiving the tabulation of occu-pational exposure data presently required by paragraph 6.9.l.b.(3),
a requirement to submit such information is being retained as Specification 6.9.3.c.(2).
In accordance with the September 16 letter, the Monthly Operating Report, beginning with the report for January, 1978 will contain the requested information. It is proposed, however, that the safety re$ ated maintenance performed during the refueling outage be re-ported in the repoxt for the month following the end of the outage.
Because of the extensive maintenance which is performed during the
'pefueli,ng outage, due to the heavy manpower requirements to perform the rqaintenance, the reporting is deferred until. after the outage.
The proposed timing will allow plant personnel at least one month between the end of the outage and the report submittal. The proposed schedule pill, however, provide maintenance information more than is the case under the present 'Annual Operating Report. Afrequently separate, one-time-only, "Narrative Summary of Operating Experience" to cover the calendar year 1977 will be submitted. This summary will cover information presently required by Technical Specification 6.9.1.'b.(1) including safety related maintenance.
The proposed change will simplify reporting requirements and, will continue to provide to the NRC all information which the September 16, 1977 letter requests.
In addition, a change is proposed to the list of safety related shock suppressors in Technical Specification 3.13-1. This change would add a hydraulic snubber on the standby auxiliary feedwater to the table. This snubber is presently installed although the standby auxiliary feedwater system is presently under review at the NRC. The proposed revision is submitted pursuant to the footnote to Table 3.13-1.
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