|
---|
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. 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. 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 ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition 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 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 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 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-19-040, 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 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 ... 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) ML17164A1432017-05-31031 May 2017 Enclosure 2C - EAL Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1412017-05-31031 May 2017 Enclosure 2A - EAL Comparison Matrix Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1422017-05-31031 May 2017 Enclosure 2B - EAL Red-Line 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 ML17087A3742017-03-28028 March 2017 License Amendment Request, Refueling Water Tank 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. ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System 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. ML16060A2232016-02-25025 February 2016 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. ML16035A2272016-02-0404 February 2016 License Amendment Request - Change to Surveillance Requirement 3.5.3.1 ML15310A0642015-11-0505 November 2015 License Amendment Request to Relocate Surveillance Frequency Requirements ML15212A9022015-07-30030 July 2015 Supplemental Information Regarding TSTF-425 License Amendment Request ML15210A3142015-07-29029 July 2015 License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel 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 ML14050A3742014-02-13013 February 2014 License Amendment Request Re Pressurizer Safety Valve Technical Specification Revision ML14050A3752014-02-13013 February 2014 Summary of Analysis Supporting Pressurizer Safety Valve Technical Change ML14015A1382014-01-13013 January 2014 License Amendment Request: Add Technical Specification for Atmospheric Dump Valves ML13308A3872013-10-31031 October 2013 Application for Technical Specification Improvement to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. 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 ML13030A1332013-01-28028 January 2013 License Amendment Request Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML13029A4562013-01-22022 January 2013 Emergency License Amendment Request: Revise Description of Operable Containment Air Cooling Train ML11222A0202011-08-0808 August 2011 License Amendment Request: Diesel Generator Surveillance Requirement 3.8.1.11 Revision 2023-08-21
[Table view] Category:Technical Specification
MONTHYEARML22298A0112022-10-25025 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. 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. RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin ML21278A2972021-09-0707 September 2021 6 to Technical Specification Bases ML21165A4062021-06-14014 June 2021 Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request 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 ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls 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 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. 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 ... ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... ML18262A0962018-03-0606 March 2018 Technical Specification Bases, Revisions 62 Through 63 ML17261A2342017-07-19019 July 2017 Bases 3.7, Plant Systems, Revisions; B 3.7.1-1 Through B 3.7.18-3 ML17261A2252017-07-19019 July 2017 Bases 3.2, Power Distribution Limits, Revisions; B 3.2.1-1 Through B 3.2.5-5 ML17261A2352017-07-19019 July 2017 Bases 3.8, Electric Power Systems, Revisions; B 3.8.1-1 Through B 3.8.10-5 ML17261A2272017-07-19019 July 2017 Bases 3.3, Instrumentation, Revisions; B 3.3.1-18 Through B 3.3.12-4 ML17261A2212017-07-19019 July 2017 Bases 2.0, Safety Limits, Revision 2; B 2.1.1-1 Through B 2.1.2-4 ML17261A2192017-07-19019 July 2017 Technical Specification Bases ML17261A2312017-07-19019 July 2017 Bases 3.5, Emergency Core Cooling System (Eccs), Revisions; B 3.5.1-1 Through B 3.5.5-5 ML17261A2232017-07-19019 July 2017 Bases 3.1, Reactivity Control Systems, Revisions; B 3.1.1-1 Through B 3.1.8-5 ML17261A2322017-07-19019 July 2017 Bases 3.0, Containment System, Revisions; B 3.0.1-1 Through B 3.0.8-4 ML17261A2292017-07-19019 July 2017 Bases 3.4, Reactor Coolant System(Rcs), Revisions; B 3.4.1-1 Through B 3.4318-8 ML17261A2382017-07-19019 July 2017 Bases 3.9, Refueling Operations, Revisions; B 3.9.1-1 Through B 3.9.6-2 ML17261A2222017-07-19019 July 2017 Basis 3.0, Limiting Condition for Operation (LCO) Applicability, Revisions; B 3.0-1 Through B 3.0-25 ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System ML16258A0722016-09-0808 September 2016 Inc. - Technical Specification Bases, Unit Nos. 1 and 2 ML16258A0782016-09-0808 September 2016 Technical Specification Bases B 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ML16258A0732016-09-0808 September 2016 Technical Specification Bases B 2.1.1-1, Safety Limits ML16258A0762016-09-0808 September 2016 Technical Specification Bases B 3.2, Power Distribution Limits - Linear Heat Rate (Lhr) ML16258A0742016-09-0808 September 2016 Technical Specification Bases B 3.0-1, Limiting Condition for Operation (LCO) Applicability ML16258A0842016-09-0808 September 2016 Technical Specification Bases B 3.9.1, Refueling Operations, Boron Concentration ML16258A0802016-09-0808 September 2016 Technical Specification Bases B 3.5.1, Emergency Core Cooling System (Eccs), Safety Injection Tanks (Sits) ML16258A0812016-09-0808 September 2016 Technical Specification Bases B 3.6, Containment Systems ML16258A0752016-09-0808 September 2016 Technical Specification Bases B 3.1, Reactivity Control Systems ML16258A0832016-09-0808 September 2016 Technical Specification Bases B 3.8.1, Electrical Power Systems, AC Sources-Operating ML16258A0822016-09-0808 September 2016 Technical Specification Bases B 3.7.1, Plant Systems, Main Steam Safety Valves (Mssvs) ML16258A0772016-09-0808 September 2016 Technical Specification Bases B 3.3.1, Reactor Protective System (RPS) Instrumentation-Operating 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. ML15257A2022015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 10 of 12 ML15257A2042015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 12 of 12 ML15257A2012015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 9 of 12 ML15257A2002015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 8 of 12 ML15257A1992015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 7 of 12 ML15257A1982015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 6 of 12 ML15257A1972015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 5 of 12 ML15257A1962015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 4 of 12 ML15257A1952015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 3 of 12 ML15257A1942015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 2 of 12 ML15257A2032015-09-0404 September 2015 Technical Specification Bases, Revisions 49 Through 55. Part 11 of 12 2022-08-10
[Table view] Category:Amendment
MONTHYEARML22298A0112022-10-25025 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. 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. 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 ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls 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 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. 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 ... ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1003405862010-01-29029 January 2010 License Amendment Request: Pressurizer Safety Valve Technical Specification Revision ML0911700492009-04-23023 April 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from Technical Specification 5.2.2 to Support Compliance with 10 CFR Part 26 ML0821804962008-08-27027 August 2008 Technical Specifications, Amendment No. 288 ML0811601412008-04-23023 April 2008 Tech Spec Pages for Amendments 286 and 263 Modification of Technical Specification Definitions ML0731701802007-11-0808 November 2007 License Amendment Request: Modify Technical Specification Definitions ML0727007162007-09-27027 September 2007 Technical Specification Pages Re Unavailability of Barriers Using Consolidated Line Item Improvement Process ML0718403352007-06-29029 June 2007 License Amendment Request: Revise Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448 Using the Consolidated Line Item Improvement Process ML0516601952005-06-0707 June 2005 License Amendment Request: Technical Specification Changes to Modify Requirements Related to Positive Reactivity Additions ML0516602072005-06-0707 June 2005 License Amendment Request: Eliminate Use of the Term Core Alterations in the Technical Specifications ML0506002672005-02-24024 February 2005 Technical Specifications, Incorporating Core Operating Limits Analytical Methodology References Into Technical Specifications ML0503904972005-02-0303 February 2005 Technical Specification Pages to Calvert Cliffs, Unit 2 - Correction to Amendment No. 246 ML0503300972005-01-27027 January 2005 License Amendment Request: Change Regarding Mode Using the Consolidated Line Item Improvement Process ML0434400272004-12-0101 December 2004 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports ML0431001302004-11-0303 November 2004 Units 1 & 2; Technical Specification Bases, Revisions 15. 16, 17, 18, 19, 20. 21, and 22 ML0430001872004-10-21021 October 2004 Technical Specification Page for Corrected Amendment Nos. 268 and 244 ML0420200822004-07-15015 July 2004 Units, 1 and 2, License Amendment Request: Incorporate Methodology References for the Implementation of PHOENIX-P, Anc, Paragon, and Zirconium Diboride Into the Technical Specifications ML0416201102004-06-0707 June 2004 Units I & 2, License Amendment Request: Use of Alternate Decay Heat Removal in Mode 6 Refueling ML0416300782004-06-0303 June 2004 License Amendment, Technical Specification Pages Re Spent Fuel Pool Maximum Enrichment Limit ML0335102762003-12-12012 December 2003 License Amendment Request Regarding Elimination of Post-Accident Sampling System (PASS) Sampling Requirements ML0334504822003-12-0909 December 2003 Technical Specification for Calvert Cliff Units 1 & 2, Amendment Nos. 261 & 238 ML0331405792003-09-30030 September 2003 Letter Transmitting Calvert Cliffs, Units 1 and 2 - License Amendment Request: Increase the Unit 2 Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron and Burnup Credit ML0312702882003-05-0101 May 2003 License Amendment Request Re Increase to Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit ML0312803342003-05-0101 May 2003 License Amendment Request Re Increase to Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit, Attachment I Through F ML0312803252003-05-0101 May 2003 License Amendment Request Re Increase to Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit, Attachment H ML0312703002003-05-0101 May 2003 License Amendment Request Re Increase to Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit, Attachments 1 Through G ML0235100562002-12-13013 December 2002 License Amend Request: Removal of Charging Pumps from Emergency Core Cooling System Technical Specification ML0221302562002-07-17017 July 2002 Westinghouse Lead Fuel Assemblies - Temporary Exemption Request & License Amendment Request ML0209904332002-04-0808 April 2002 Technical Specification Pages for Amendments 251 & 228, Calvert Cliffs, Units 1 & 2 ML0209802212002-04-0404 April 2002 Technical Specification, Emergency Amendment 227 One-Time Extension of the Unit 2 Control Room Emergency Ventilation System Technical Specification ML0206406192002-03-0404 March 2002 Technical Specifications, for Amendment Nos. 250 & 256 ML0206302602002-03-0101 March 2002 Technical Specifications, Amendment Steam Generator Replacement (Tac Nos. MB0951 and MB0952) ML0204505342002-02-13013 February 2002 Technical Specifications, Amendment One-Time Extension of the Unit 2 Control Room Emergency Ventilation System Technical Specification 2022-08-10
[Table view] |
Text
Peter E. Katz 1650 Calvert Cliffs Parkway Vice President Lusby, Maryland 20657 Calvert Cliffs Nuclear Power Plant 410 495-4455 Constellation Generation Group, LLC 410 495-3500 Fax Energy Constellation Group December 13, 2002 U. S. Nuclear Regulatory Commission Washington, DC 20555
- ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 License Amendment Request: Removal of the Charging Pumps from the Emergency Core Cooling System Technical Specification
REFERENCES:
(a) Letter from Ms. D. Skay (NRC) to Mr. C. H. Cruse (CCNPP), dated April 8, 2002, "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Amendment Re: Implementation of ZIRLO Clad Fuel Rods (TAC Nos.
MB2540 and MB2541)"
(b) Letter from Mr. C. H. Cruse (CCNPP) to NRC Document Control Desk, dated May 9, 2002, "10 CFR 50.46 30-day Report for Changes to the Calvert Cliffs Nuclear Power Plant Emergency Core Cooling System Performance Analysis" (c) CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model," April 1998 Pursuant to 10 CFR 50.90, Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) hereby requests an amendment to Renewed Operating License Nos. DPR-53 and DPR-69 to incorporate the changes described below into the Technical Specifications for Calvert Cliffs Unit Nos. 1 and 2.
DESCRIPTION The proposed amendment revises Technical Specification 3.5.2, ECCS - Operating, by removing the Note that modifies the Limiting Condition for Operation. The proposed change will remove the requirement to have the charging pumps operable when thermal power is greater than 80% of rated thermal power (RTP). The proposed change will also remove Surveillance Requirement 3.5.2.4 for verifying the required charging pump flow rate. The proposed change to Technical Specification 3.5.2 does not modify any other charging pump requirements specified in the Technical Requirements Manual (e.g., requirements on charging pump availability for boration and cooldown remain in effect).
A()C
Document Control Desk December 13, 2002 Page 2 The requirement for the charging pumps was a result of the previous small-break loss-of-coolant accident (LOCA) analyses. Above 80% RTP, the small-break LOCA analyses assumed flow from a single charging pump, accounting for measurement uncertainties and flow mal-distribution effects, in calculating a conservative value of charging flow actually delivered to the Reactor Coolant System.
Credit was only taken for the water inventory. No credit was taken for any boration delivered by the charging pumps. At or below 80% RTP, there was a corresponding decrease in decay heat such that the injection of water from one charging pump was not required in order to achieve acceptable results in the small-break LOCA analyses.
The Nuclear Regulatory Commission approved the use of the new small-break LOCA evaluation models on April 8, 2002 (Reference a). In our letter dated May 9, 2002 (Reference b), we informed you that the analyses for the small-break LOCA Emergency Core Cooling System performance had been re-analyzed for the Unit 1 Cycle 16 and the upcoming Unit 2 Cycle 15. The re-analyses were performed using the newest Nuclear Regulatory Commission accepted versions of the Westinghouse evaluation models for Combustion Engineering designed pressurized water reactors (Reference c). In addition, the new analysis explicitly modeled the replacement steam generators, which were installed in Unit 1 prior to the startup of Cycle 16 and will be installed in Unit 2 prior to the startup of Cycle 15, and the new fuel design being introduced. The new fuel design implements ZIRLOTM cladding and mixing vane grids.
The new small-break LOCA analysis incorporated several changes to plant parameters used in the analysis, one of which was the elimination of the need to credit the charging pump flow above 80% RTP.
The charging pumps are not assumed to be operable to mitigate the consequences of a design basis accident or transient and are not an input assumption for any design basis accident analysis. Therefore, per 10 CFR 50.36(c)(2)(ii), this requirement can be removed from the Technical Specifications.
DETERMINATION OF SIGNIFICANT HAZARDS The proposed amendment revises the Unit Nos. 1 and 2 Technical Specification 3.5.2, Emergency Core Cooling System - Operating, by removing the requirement to have the charging pumps operable above 80% of rated thermal power. The proposed change will also remove Surveillance Requirement 3.5.2.4 for verifying the required charging pump flow rate.
These proposed changes have been evaluated against the standards in 10 CFR 50.92 and have been determined to not involve a significant hazards consideration, in that operation of the facility in accordance with the proposed amendment:
- 1. Would not involve a significantincrease in the probabilityor consequences of an accidentpreviously evaluated.
The charging pumps were credited in the previous analysis to mitigate the consequences of a small break loss-of-coolant accident (LOCA) above 80% of rated thermal power (RTP). The charging pumps were not considered to be an initiator of the accident. The new analysis for the small-break LOCA does not assume the charging pumps are initiators of the accident. Therefore, removing the requirement to maintain the charging pumps operable above 80% RTP and removing Surveillance Requirement 3.5.2.4 from the Technical Specification does not involve a significant increase in the probability of an accident previously evaluated.
The consequence of a small-break LOCA is the potential for inadequate core cooling and decreased negative reactivity such that the reactor core is not protected after the design basis event. The previous analysis for the small-break LOCA above 80% RTP assumed unborated flow from a single
Document Control Desk December 13, 2002 Page 3 charging pump to ensure there was adequate cooling flow delivered to the Reactor Coolant System.
The revised small-break LOCA analysis was performed such that flow from the charging pumps was not credited. Since the charging pump flow is no longer credited in the small-break LOCA analysis, the proposed changes do not involve a significant increase in the consequences of a small-break LOCA.
Therefore, the proposed Technical Specification changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Would not create the possibility of a new or different type of accidentfrom any accidentpreviously evaluated.
This request change does not involve a change in the operation of the plant and no new accident initiation mechanism is created by the proposed changes. Since the charging pump flow is no longer credited in the small-break LOCA analysis, the requirement to have the charging pumps operable above 80% RTP and the charging pump Surveillance Requirement 3.5.2.4 can be removed from the Technical Specification. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Would not involve a significant reduction in a margin of safety.
The safety function of the Emergency Core Cooling System is to provide core cooling and negative reactivity, to ensure that the reactor core is protected after design basis events. For a small-break LOCA, the previous analysis credited flow from the charging pumps above 80% RTP to supply supplemental cooling flow to the Reactor Coolant System. Credit for flow from a single charging pump was only taken for the water inventory.
The revised small-break LOCA analysis was performed using the newest Nuclear Regulatory Commission accepted versions of the Westinghouse evaluation models for Combustion Engineering designed pressurized water reactors. The revised small-break LOCA analysis incorporated several changes to plant parameters used in the analysis, one of which was the elimination of the need to credit the charging pump flow above 80% RTP. Since the charging pump flow is no longer credited in the small-break LOCA analysis, the requirement to have the charging pumps operable above 80%
RTP and charging pump Surveillance Requirement 3.5.2.4 can be removed from the Technical Specification.
The proposed change to Technical Specification 3.5.2 does not modify any other charging pump requirements specified in the Technical Requirements Manual (e.g., requirements on charging pump availability for boration and cooldown remain in effect).
Therefore, the safety function of the Emergency Core Cooling System is maintained and the margin of safety is not significantly reduced by the proposed changes ENVIRONMENTAL ASSESSMENT We have determined that operation with the proposed amendments will not result in any significant change in the types or significant increases in the amounts of any effluents that may be released offsite, and no significant increases in individual or cumulative occupational radiation exposure. Therefore, the
Document Control Desk December 13, 2002 Page 4 proposed amendments are eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact assessment is needed in connection with the approval of the proposed amendments.
SAFETY COMMITTEE REVIEW The Plant Operations and Safety Review Committee and the Offsite Safety Review Committee have reviewed this proposed amendment and concur that operation with the proposed amendment will not result in an undue risk to the health and safety of the public.
SCHEDULE Since the Unit 1 steam generators were replaced during the refueling outage for Unit 1 Cycle 16, this proposed change would apply to Unit 1 at the present time. However, Unit 2 has not yet replaced steam generators or installed the new fuel design. Those changes will take place in the 2003 Refueling Outage.
The proposed change will apply to Unit 2 upon completion of the 2003 Refueling Outage, which is currently scheduled to be completed in May 2003. Therefore, we request approval of the proposed changes by May 1, 2003.
Document Control Desk December 13, 2002 Page 5 Should you have questions regaiding this matter, we will be pleased to discuss them with you.
Very te lyours, STATE OF MARYLAND TO WIT:
COUNTY OF CALVERT I, Peter E. Katz, being duly sworn, state that I am Vice President - Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in 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 other CCNPP employees and/or consultants. Such information has been reviewed in accordance with company practice and I believ* t be reliable.
Subscrib.d and sworn before me, a Notary Public in and for the State of Maryland and County of
___o-_ _ , this day of U - -. ,2002.
WITNESS my Hand and Notarial Seal:
My Commission Expires: -711/o&
Date PEK/DJM/bjd -
- f
Attachment:
(1) Marked up Technical Specification Pages cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR D. M. Skay, NRC
ATTACHMENT (1)
MARKED-UP TECHNICAL SPECIFICATION PAGES 3.5.2-1 3.5.2-2 Calvert Cliffs Nuclear Power Plant, Inc.
December 13,2002
ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 with pressurizer pressure e 1750 psia.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Reduce pressurizer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> pressure to
< 1750 psia.
CALVERT CLIFFS - UNIT 1 3.5.2-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201
ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> listed position with power to the valve operator removed.
Valve Number Position Function MOV-659 Open Mini-flow Isolation MOV-660 Open Mini-flow Isolation CV-306 Open Low Pressure Safety Injection Flow Control SR 3.5.2.2 Verify each ECCS manual, power-operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.2.3 Verify each high pressure safety injection - In accordance and low pressure safety injection pump's with the developed head at the test flow point is Inservice greater than or equal to the required Testing Program developed head.
Testin _~or~
SR 3.5.2.5 Verify each ECCS automatic valve that is not 24 months locked, sealed, or otherwise secured in position, in the flow path actuates to the correct position on an actual or simulated actuation signal.
CALVERT CLIFFS - UNIT 1 3.5.2-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201