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MONTHYEARML0729502252007-10-17017 October 2007 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process Project stage: Request ML0805303882008-03-24024 March 2008 Units, 1 and 2 - Tech Spec Pages for Amendments 285 and 262 Addition of Limiting Condition of Operation 3.0.8 for Inoperable Snubbers Project stage: Other ML0805303812008-03-24024 March 2008 Units, 1 and 2 - Amendments 285 and 262 Addition of Limiting Condition of Operation 3.0.8 for Inoperable Snubbers Project stage: Acceptance Review 2007-10-17
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Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program 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 RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 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 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 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 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) 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 ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary 2024-02-05
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23164A1702023-06-13013 June 2023 License Amendment Request to Adopt TSTF-59-A, Incorporate (Combustion Engineering) NPSD-994 Recommendations Into the (Safety Injection Tanks) Specification, Revision 1 ML23153A0982023-06-0202 June 2023 Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (CREVS) Technical Specification 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. ML23052A0632023-02-21021 February 2023 License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. 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 RS-22-017, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs2022-04-20020 April 2022 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs 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 ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition 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 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 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 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 ML20329A3342020-11-24024 November 2020 Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues 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 ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19346E5362019-12-11011 December 2019 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program 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 ML19127A0762019-05-0606 May 2019 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec 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 ML18333A0222018-11-28028 November 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. ML18235A1992018-08-23023 August 2018 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to ... ML18158A1292018-06-0505 June 2018 License Amendment Request: Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition ML18113A0902018-04-20020 April 2018 Administrative Change to Technical Specification 5.2.2, Unit Staff 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 ML17164A1512017-05-31031 May 2017 Enclosure 3E - Procedure Matrix for R.E. Ginna Nuclear Power Station ML17164A1432017-05-31031 May 2017 Enclosure 2C - EAL Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1452017-05-31031 May 2017 Enclosure 2E - Procedure Matrix for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1472017-05-31031 May 2017 Enclosure 3B - EAL Red-Line Basis Document for R.E. Ginna Nuclear Power Station ML17164A1482017-05-31031 May 2017 Enclosure 3C - EAL Basis Document for R.E. Ginna Nuclear Power Station ML17164A1422017-05-31031 May 2017 Enclosure 2B - EAL Red-Line Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1502017-05-31031 May 2017 Enclosure 3D - EAL Front Matter for R.E. Ginna Nuclear Power Station ML17164A1412017-05-31031 May 2017 Enclosure 2A - EAL Comparison Matrix Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 2023-08-21
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if.Y J. M. Heffley Constellation Energy Nuclear Generation Group, LLC Chief Nuclear Officer 1997 Annapolis Exchange Parkway Suite 310 Annapolis, MID 21401 410-897-5020 0Constellation Energy Nuclear Generation Group October 17, 2007 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk S ubject: Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2, Docket Nos. 50-317 & 50-3)18 R.E. Ginna Nuclear Power Plant Docket No. 50-244 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Itemn Improvement Process
Reference:
(a.) Notice of Availability of Model Application Concerning Technical Specification Improvement to Modify Requirements Regarding The Addition of Limiting Condition for Operation 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (70FR23252, May 4, 2005)
Pursuant to 10 CFR 50.90. Calvert Cliffs Nuclear Power Plant (Calvert Cliffs) and R.E. Ginna Nuclear Power Plant (Ginna) hereby request an amendment to Calvert Cliffs Renewed Operating Licenses DPR-53 and DPR-69 and Ginna. Renewed Operating License DPR-18. This proposed license amendment will modify Technical Specification requirements for inoperable snubbers by adding, Limiting Condition for Operation (LCO) 3.0.8, in accordance with Reference (a).
Attachment (1) provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications. A summary of regulatory commitments is contained in Attachment (2).
The proposed changes are shown in Attachments (3) and (4). The final Technical Specification pages will be renumbered to accommodate the insertion of this change.
We request approval of this change by April 1, 2008 to coincide with the Ginna spring outage. We also request an implementation period of 60 days.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the proper New York and Maryland state officials.
Document Control Desk October 17, 2007 Page 2 Should you have any questions regarding the information in this submittal, please contact Mr. L. S. Larragoite at (410) 897-5087 or Louis. S. Larragoite @constellation.com.
Very truly yours, JonM. Heffley ief Nuclear Of cejr STATE OF MARYLAND TO WIlT COUNTY OF ANNE ARUJNDEL 1, John M. Heffley, state that I am Chief Nuclear Officer, Constellation Energy Nuclear Generation Group, LLC, for Calvert Cliffs Nuclear Power Plant, Inc. and R. E. Ginna Nuclear Power Plant, LLC, and that I am duly authorized to execute and file this response on behalf of these companies. To the best of my knowledge and belief, the statements contained iii this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by employees and/or consultants of the companies. Such informnation has been reviewed in accordance with company practice, and I believe it to be reliable.
PA -
Subscribed and sworn before me, a Notary Public, in and for the State of Maryland and County of Anne Arundel, this 0i day of -OA6 ( -, 2007.
ah., ~JAMES E. RZEPKOWSKI Notary Public-Maryland Anne Arundel County ii MY Corn ironesx
-rt! Aan and Notarial Seal:
My Commission Expires: /0 1/0t Attachments: (1) Background and Analysis (2) Regulatory Commitments (3) Calvert Cliffs Nuclear Power Plant Technical Specification Markup (4) R.E. Ginna Nuclear Power Plant Technical Specification Markup
Document Control Desk October 17, 2007 Page 3 cc: D. V. Pickett, NRC R. 1. McLean, DNR S. J. Collins, NRC J. P. Spath, NYSERDA Resident Inspector, NRC P. Eddy, NYS Dept. of Public Services
ATTACHMENT (1)
BACKGROUND AND ANALYSIS Constellation Generation Group October 17, 2007
ATTACHMEENT 1 BACKGROUJND) AN]) ANALYSIS BACKGROUND The proposed amendment would modify Technical Specification requirements for inoperable snubbers by adding Limiting Condition for Operation (LCO) 3.0.8.
The changes are consistent with Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) Standard Technical Specification change, TSTF-3 72-A, Revision 4.
The availability of this Technical Specification improvement was published in the Federal Register on May 4, 2005 as part of the Consolidated Line Item Improvement Process (CLIIP).
ANALYSIS Applicability of Published Safety Evaluation We have reviewed the safety evaluation dated May 4, 2005 as part of the CLIIP. This review included a review of the NRC staffs evaluation, as well as the information provided to support TSTF-3 72-A. We have concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Calvert Cliffs Nuclear Power Plant (Calvert Cliffs), Units 1 and 2 and R.E. Ginna Nuclear Power Plant (Ginna) and justify this amendment for the incorporation of the changes to the Technical Specifications.
Optional Changes and Variations We are not proposing any variations or deviations from the Technical Specification changes described in TSTF-3 72-A, Revision 4 or the NRC staff's model safety evaluation dated April 26, 2005.
NO SIGNI]FICANT HAZARDS CONSIDERATION DETERMINATION We have reviewed the proposed no significant hazards consideration determination published in the Federal Register as part of the CLIIP. We have concluded that the proposed deten-nination is applicable to Calvert Cliffs and Ginna and is hereby incorporated by reference to satisfy the requirements of 10 CFR 5 0.9 1(a).
VERIEFICATION AND COMNIITAMNTS A Technical Specification basis for LCO 3.0.8 that provides guidance and details on how to use the new requirements will be established by Calvert Cliffs and Ginna. The basis will also state that, while the industry and NRC guidance on implementation of 10 CFR 50.65(a)(4) - the Maintenance Rule - does not address seismic risk, LCO 3.0.8 should be considered with respect to other plant maintenance activities and integrated into the existing Maintenance Rule process to the extent possible. The effect of this integration will be that maintenance on any unaffected train or subsystem is properly controlled and emergent issues are properly addressed. The basis will further state that the risk assessment need not be quantified, but may be a qualitative assessment of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.
Both Calvert Cliffs and Ginna have a Technical Specification Bases Control Program consistent with the Improved Standard Technical Specifications.
ENVIRONMIENTAL EVALUATION We have reviewed the environmental evaluation included in the model safety evaluation dated May 3, 2005 as part of the CLIIP. We have concluded that the staff's findings presented in that evaluation are applicable to Calvert Cliffs and Ginna and the evaluation is hereby incorporated by reference for this application.
1
ATTACHMENT (2)
REGULATORY COMMITMENTS Constellation Generation Group October 17, 2007
ATTACHMENT 2 REGULATORY COMMITMENTS The following table identifies those actions committed to by Calvert Cliffs Nuclear Power Plant and R.E. Ginna Nuclear Power Plant in this document. Any other statements in this submittal are provided for information purposes only and are not considered to be regulatory commitments.
REGULATORY COMMINTMIENTS ACTION COMPLETE BY Calvert Cliffs Nuclear Power Plant and R.E. Ginna Implemented with the approved amendment.
Nuclear Power Plant will establish the Technical Specification basis for LCO 3.0.8 as applicable to the approved license amendment.
I
ATTACHMENT (3)
Calvert Cliffs Nuclear Power Plant Technical Specification Markup Constellation Generation Group October 17, 2007
[CO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION ([GO) APPLICABILITY not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to
[CO 3.0.2 for the supported system. In this event, additional evaluations and limitations may be required in accordance with Specification 5.5.15, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.
LCO 3.0.7 Special test exception (STE) LCOs in each applicable [CO section allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with STE [COs is optional. When an STE [CO is desired to be met but is not met, the ACTIONS of the STE [CO shall be met. When an STE [CO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.
[CO 3.0.8 [Reo
[CO 3.0.9 When one or more required barriers are unable to perform their related support function(s), any supported system
[CO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support function(s), and risk is assessed and managed. This CA[VERT CLIFFS - UNIT 1 3.0-3 Amendment No. 282 CALVERT CLIFFS - UNIT 2 Amendment No. 259
INSERT LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:
- a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- b. the snubbers not able to perform their associated support funiction(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.
ATTACHMENT (4)
R.E. Ginna Nuclear Power Plant Technical Specification Markup Constellation Generation Group October 17, 2007
LCO Applicability 3.0 LCO 3.0.7 Test Exception LCO 3.1.8, "PHYSICS TEST Exceptions - MODE 2,"
allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.
R.E. Ginna Nuclear Power Plant 303Aedet8 3.0-3 Amendment 88
INSERT LCO 3.0.8 When one or more required snubbers are unable to performn their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:
- a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.