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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
[Table view] |
Text
REGUI ATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-244 REC: CASE F G ORG: LARSON L K DOCDATE: 05/08/78 NRC L DATE RCVD: 05/09/78 LBSaor-f ~
<ARS, LelBQ> PLACID'A6.
DOCTYPE: LETTER NOTARIZED: YES COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 40 FORWARDING LIC NO DPR-i8 APPL FOR AMEND: APPENDIX A TECH SPEC PROPOSED CHANGE CONCERNING MODIFICATION TO REQUIREMENTS FOR TESTING THE NUC PWR RANGE DETECTOR LOW PWR SETPGINT... NOTARIZED 05/05/78... W/ATT CERT'AFETY EVALUATION AND LIC FEES.
PLANT NAME: RE GINNA UNIT i REVIEWER INITIAL: X JM INITIAL:
DISTRIBUTOR
+++++w+>.l++>>~+~4~ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++++>>++>~>4+++~>+
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOOi)
FOR ACTION: BR CH 'N+<~W/7 ENCL INTERNAL: REG FILE4+W/ENCL NRC PDR4+W/ENCL E GELD>+LTR ONLY HAIMAUER++W/ENCL CHECK+<W/ENCL EI SENHUT++W/ENCL SHAO+wW/ENCL BAER4+W/ENCL BUTLER++W/ENCL EEB++W/ENCL J COLLINS+4W/ENCL J. MCGOUGH~+W/ENCL EXTERNAL: LPDR'S ROCHESTER'Y++W/ENCL TICKS< W/ENCL NS I C++W/ENCL ACRS CAT B++W/i6 ENCL 444%%4444f44444f4444444444444444%4%44%4%%4fff%$ %440 CHECK NBR: 46'95 AMOUNT: 4ii 200. 00 f CHECK AND,COPY GF TRANSMITTAL I TR ADVANCED TO W. MILLER (LFMB > (05/09/78) UPON RECIEPT f@444$ 5$ 4fff$ 4$ 440444%f44$ $ 44%f%4%%%444%%$ 44444f4%4 DISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 78i29003i SIZE: iP+2P+6P THE END
~1 LEBOEUFI LAMB, LEIBY, ac MACRAE l757 N STREET, N.W.
WAsHINGTQN> D. C. 20036 TELEPHONE 202 457 ~ 7500 CASLC ADDRESS LEON A ALLEN'R CAMERON F. MAcRAE 4 RANDALL J. I.TSOEUF,JR, I929 I97$
JOSEPH C.BACHELDER.III OAMERON F. MACRAElIIE I LCSWINe WASHINOTONs D C.
ERNEST S. BALLARD JR GCRARD A. MAHCR HORACE R,LAMB 1934 I977 G. S. PETER BERGCN 4 SHEILA H. MARSHALL TELCX: 440274 GCOFFRY O.C. BEST JAMES G. Mc CLROY ADRIAN C. LCISY l9$ 2 l978 DAVID P. DICKS JAMES P. McGRANERY, JR.~4 TCLECOPICFc TAYLOR R. BRIGGS PHILIP PALMER MCGVIGAN CHARLES N. BURGER HARVEY A.NAPICR 202 457 ~ 7543 THOMAS C.BURKE JAMES O'MALLCY UR. ~
ROGCR D.FELOMAN ~ 4 MICHAEL PARISH CVGCNE R. FIDCLL 4 WILLIAMW. ROSENBLATT JACOB FRICDLANDCR JOHN A. RVDY GERARO GIORDANO PAUL G. RVSSELL l40 BROADWAY DONALD J. GREENE PATRICK J SCOGNAMIGLIO
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JAM CS A. GREER, IZ I HAROLD M SCIDCL
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NCW YORK,N.Y. IOOOS JOHN L. GROSC 4 HALCYON Q. SKINNER DOUGLAS W. HAWCS JOSCPH S. STRAUSS CARI D. HOBCLMAN SAMUCL M. SVGDCN TCLCPHONC 2I2 289 IIOO MICHAEL IOVENKO EUQENC B. THOMAS. JR.
JAM CS F. JOHNSON, 4' LEONARD M. TROSTCN l CABLE ADDRESS RONALD D.JONES HARRY H. VOIGT 4 LCX K.LARSON H ~ RICHARD WACHTEL LE SW IN, IICW YORK Q RAN T S. LEWIS GERARD P WATSON KIMBA W. LOVEJOY THOMAS A. 2IERK TELLP: 4234IB May 8, 1978 cn~
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RCSIDCNT PARTNERS WASHINGTON OFFICE 4 ADMITTED TO THC DISTRICT OF COLUMBIA BAR 4Q3 Rm cn Yn Mr. Edson G. Case A C TXt Acting Director Office of Nuclear Reactor Regulation Cl U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket, No. 50-244
Dear Mr. Case:
As counsel for Rochester Gas and Electric Corpora-tion, I enclose the following:
(1) Three (3) originals and nineteen (19) copies of an Application for Amendment to Operating License; and
<<I7T, (2) Forty (40) copies each of three (3) documents designated Attachments A, B, and C which set forth the requested change in the Technical Specifications, its technical basis, and technical information asserting this change is of no safety or environmental significance.
The proposed amendment to the Provisional Operating License has been evaluated and determined to fall within the definition of Class II of 10 C.F.R. Section 170.22; therefore, a check for the required fee in the amount of $ 1,200.00 is also enclosed.
Very truly yours, LeBOEUF, LAMB, LEIBY 6 MacRAE 7SI29003i I By Lex K. Larson Enclosures
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of ROCHESTER GAS AND ELECTRIC CORPORATION Docket No. 50-244 (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,"
along with Attachments, by mailing copies thereof first class, postage prepaid to each of the following persons this 8th day of May, 1978:
Mr. Michael L. Slade 1250 Crown Point Drive Webster, New York 14580 Warren B. Rosenbaum, Esq.
One Main Street 707 Wilder Building Rochester, New York 14614 Edward G. Ketchen, Esp.
Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Robert N. Pinkney Supervisor Town of Ontario 107 Ridge Road West Ontario, New York 14519
1 L
r
Jeffrey L. Cohen, Esq.
New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza Albany, New York 12223 Edward Luton, Esq.
Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C. 20555, Dr. Dixon Callihan Union Carbide Corporation P. O. Box Y Oak Ridge, Tennessee 37830 Lex K. Larson LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
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 Specifica-tion 4.1 set forth in Appendix A to that license be amended to modify the reguirements for testing the nuclear power range detector low power setpoint.
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 ch'ange in the types or a significant, increase in the amounts of effluents or any change in the authorized power level of the facility. Justi-fication for classification of the amendment pursuant to 10 C.F.R. Section 170.22 is included as Attachment C. A check for the appropriate fee accompanies this Application.
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 By L.D. White, Jr.
Vice President, Electric and Steam Production Subscribed and sworn to before me on thi g~ day of May 1978 ST P H E N K 0 L'I EI A JIOTARY PUBLIC, Stete of N.Y, tl > ce C>,!r,ty Pily Commission Expires titerch "-0, 1950
Attachment A Replace Technical Specification page 4.1-5 with revised page 4.1-5.
TABLE 4.1-1 MINIMUM FREQUENCIES FOR CHECKS I CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Check Calibrate Test Remarks
- 1. Nuclear Power Range S D (1) B/W (2) (4) 1) Heat balance calculation**
M* (3) Q* (3) P(2) (5) 2) 3)
Signal to ST; bistable action (permissive, rod stop, trips)
Upper & lower chambers for
~
axial offset**
- 4) High setpoint (< 109% of rated power)
- 5) Low setpoint (< 25% of rated power)
- 2. Nuclear S (1) N.A. P (2) 1) Once/shift when in service Log level; bistable action Intermediate'ange, 2)
I (permissive, rod stop, trip)
U 3. Nuclear Source Range S (1) N.A. P (2) 1) Once/shift when in service
- 2) Bistable action (alarm, trip)
- 4. Reactor Coolant M(1) 1) Overtemperature-Delta T Temperature 2) Overpower Delta T
- 5. Reactor Coolant Flow S
- 6. Pressurizer Water Level
- 7. Pressurizer Pressure S
- 8. 4 Kv Voltage &
Frequency N.A. Reactor Protection circuits only
- 9. Analog Rod Position S (1,2) R 1) With step counters.
-2) Each six inches of rod motion when data logger is out of service by means of the movable in-core detector system.
- Not required during hot, cold, or refueling shutdown but as soon as possible after return to power DDQD'ACl. ~
Attachment B.
Technical Specifications Table 4.1-1 presently requires that the power range detectors be tested bi-weekly. These flux detectors have both high and low power setpoints (109% and 25% of rated power, respectively). The low power setpoint is used as a backup (to the intermediate range detectors) reactor protection means during startup. While at power, the Ginna safety analysis takes credit only for the high setpoint trip.
Thus, while the reactor is at power, the low power setpoint is not required to perform a safety function.
The proposal .to test the low power setpoint prior to startup, rather than bi-weekly, is consistent with the test schedule for the intermediate range detectors, which perform the same function.
This testing will provide sufficient assurance of the accuracy of the setpoint at the time it might be needed to perform its safety function.
Attachment C The proposed Amendment. to the Provisional Operating License has been evaluated and determined to fall within the definition of Class II of 10 C.F.R. Section 170.22 thereby requiring a fee of $ 1,200. The proposed amendment is a clarification of the Technical Specification requirement for testing of the power range detectors. The present, Technical Specification could be interpreted to mean that the low power setpoint, which provides a trip at 25% power, must be tested during normal power op'eration.
However, since this trip must be defeated during normal power operation in order to permit operation above 25% power, it is clear that such testing is superfluous. In addition, as described in Attachment B, since the low power trip will continue to be tested prior to startup so that, it would perform its intended safety function if required, it is clear that this change has no safety or environmental significance.
C