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| | number = ML13155A140 | | | number = ML13155A140 |
| | issue date = 05/28/2013 | | | issue date = 05/28/2013 |
| | title = Millstone Power Station, Unit 2 - Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage | | | title = Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage |
| | author name = Grecheck E S | | | author name = Grecheck E S |
| | author affiliation = Dominion Nuclear Connecticut, Inc | | | author affiliation = Dominion Nuclear Connecticut, Inc |
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Technical Specifications
MONTHYEARML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21280A3282021-10-0707 October 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20261H5982020-09-17017 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18100A0552018-04-0404 April 2018 License Amendment Request to Revise Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML17038A0062017-02-0101 February 2017 Technical Specifications 2016 Annual Report ML17025A2182017-01-24024 January 2017 Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis ML16354A4242016-12-14014 December 2016 License Amendment Request to Revise Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 for the Remainder of Cycle 24 ML16208A0512016-07-26026 July 2016 Clean Technical Specifications (TS) Pages for Millstone Power Station 1 (Docket No. 05000245), Administrative Changes for TS (L53121) ML16068A3122016-03-31031 March 2016 Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing ML16011A4002016-01-29029 January 2016 Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15288A0042015-11-30030 November 2015 Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times ML15280A2422015-10-29029 October 2015 Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15225A0082015-08-26026 August 2015 Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML15187A3262015-07-29029 July 2015 Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C ML15187A1862015-07-28028 July 2015 Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692) ML15187A0112015-07-27027 July 2015 Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures ML15209A7292015-07-21021 July 2015 Response to Second Request for Additional Information Regarding Proposed Technical Specification Change for Spent Fuel Storage ML15098A0342015-05-20020 May 2015 Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A0022015-05-20020 May 2015 Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A4412015-05-18018 May 2015 Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies ML15044A0442015-02-0909 February 2015 Revised Response to Request for Additional Information Regarding License Amendment Request for Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14154A0912014-05-28028 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. ML14073A0552014-04-0808 April 2014 Issuance of Amendment Calculated Containment Internal Pressure ML13346A7672013-12-18018 December 2013 Correction Letter to License Amendment Nos. 256 and 257 ML13155A1402013-05-28028 May 2013 Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage ML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. ML13133A0332013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. ML12284A2132012-10-0404 October 2012 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML12250A6642012-08-28028 August 2012 Correction to Proposed Technical Specifications to Adopt TSTF-510 ML12220A0122012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12219A0732012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12202A0402012-07-17017 July 2012 License Amendment Request Regarding Removal of a License Condition, Proposed Technical Specifications Bases Change and FSAR Change for Ultimate Heat Sink Temperature Measurement ML12110A1142012-04-12012 April 2012 License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML12097A2002012-04-0202 April 2012 License Amendment Request to Revise Snubber Surveillance Requirements ML12032A2242012-01-25025 January 2012 License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3 ML11329A0032011-11-17017 November 2011 Proposed License Amendment and Exemption Request for Use of Optimized Zirlo Rod Cladding ML11193A2242011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages ML11193A2232011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 1 Through Attachment 3, Marked-up TS Page Changes 3/4 6-22 ML1102802082011-01-20020 January 2011 License Amendment Request to Revise Technical Specification (TS) 6.8.4.g, Steam Generator (SG) Program, and TS 6.9.1.7, Steam Generator Tube Inspection Report for Temporary Alternate Repair Criteria (H*) ML1022400642010-07-21021 July 2010 License Amendment Request to Revise Technical Specification 3/4.9.3.1, Decay Time 2024-01-12
[Table view] |
Text
Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com May 28, 2013 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT.
INC.FDomininn Serial No.13-283 NLOS/WDC RO Docket No. 50-336 License No. DPR-65 MILLSTONE POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATIONS CHANGES FOR SPENT FUEL STORAGE By letter dated December 17, 2012, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 2 (MPS2). The proposed amendment would revise Technical Specification (TS) 1.39 "Storage Pattern," TS 3.9.18,"Spent Fuel Pool -Storage," TS 3.9.19, "Spent Fuel Pool -Storage Patterns," TS 5.3.1 "Fuel Assemblies," TS 5.6.1, "Criticality," and TS 5.6.3, "Capacity" with conforming changes to Technical Specifications Bases (TSB) 3/4.9.18 and 3/4.9.19.
The proposed changes would reflect the results and constraints of a new criticality safety analysis for fuel assembly storage in the MPS2 fuel storage racks.In a letter dated February 11, 2013, the NRC provided DNC an opportunity to supplement the LAR identified above. The NRC requested the justification for the continued credit for Boraflex.
DNC provided the supplement in a letter dated February 25, 2013.In a letter dated April 26, 2013, the NRC transmitted a request for additional information (RAI) to DNC related to the LAR. DNC agreed to respond to the RAI by June 10, 2013.Attachment 1 provides DNC's response to the NRC's RAI.Should you have any questions in regard to this submittal, please contact Wanda D. Craft at (804) 273-4687.Sincerely, Eugene S. Grecheck Vice President
-Nuclear Engineering and Development VICKI L. HULL Notary Public Commonwealth of Virginia 140542 My Commission Expires May 31, 2014 COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO)))The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Eugene S. Grecheck, who is Vice President
-Nuclear Engineering and Development of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.Acknowledged before me this 1ý/'ay of .2013.My Commission Expires: -31 Notary Public vt)t P-gp-Serial No.13-283 Docket No. 50-336 Page 2 of 2 Commitments made in this letter: None
Attachment:
- 1. Response to Request for Additional Information Regarding Proposed Technical Specifications Changes For Spent Fuel Storage cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Nadiyah S. Morgan Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No.13-283 Docket No. 50-336 Attachment 1 Response to RAI Regarding Proposed Technical Specifications Changes For Spent Fuel Storage DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 2 Serial No.13-283 Docket No. 50-336 Attachment 1, Page 1 of 2 By letter dated December 17, 2012, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 2 (MPS2). The proposed amendment would revise Technical Specification (TS) 1.39 "Storage Pattern," TS 3.9.18, "Spent Fuel Pool -Storage," TS 3.9.19, "Spent Fuel Pool -Storage Patterns," TS 5.3.1 "Fuel Assemblies," TS 5.6.1, "Criticality," and TS 5.6.3, "Capacity" with conforming changes to Technical Specifications Bases (TSB) 3/4.9.18 and 3/4.9.19.
The proposed changes would reflect the results and constraints of a new criticality safety analysis for fuel assembly storage in the MPS2 fuel storage racks. In a letter dated April 26, 2013, the NRC transmitted a request for additional information (RAI) to DNC related to the LAR. This attachment provides DNC's response to the NRC's RAI.Question I Discuss if the neutron absorbing capability of the borated stainless steel rodlets will be maintained such that degradation of the material does not exceed the assumptions made in the criticality analysis of record.a. Describe how long each borated stainless steel rodlet may be used in the spent fuel pool over the life of the spent fuel pool.b. Discuss whether a removed borated stainless steel rodlet can be reused in other fuel assemblies.
In addition, describe how there is reasonable assurance that the re-used rodlet maintains the criticality analysis' assumed boron content of 2 percent.Include in the discussion, the expected maximum calculated fluence over the life of the spent fuel pool which includes time after the reactor is decommissioned; and if there would be any significant change in the material properties at this calculated fluence.c. Is the program for surveillance and inspection of the poison rodlets described in the letter dated July 16, 1993, currently used at Millstone?
If so, discuss in more detail the visual inspection aspect of the program including the parameters to be monitored and acceptance criteria to ensure that there is no material degradation occurring and that the boron content in the rodlets remains at the criticality analysis'assumed boron content of 2 percent.DNC Response a. Borated stainless steel rodlets have been in continuous service since 1994 and are expected to be in use throughout the service life of the Millstone Power Station Unit 2 (MPS2) spent fuel pool.
Serial No.13-283 Docket No. 50-336 Attachment 1, Page 2 of 2 b. Rodlets are removed from assemblies that are stored in dry storage casks and are available for re-use in other fuel assemblies in the spent fuel pool. A 1992 Electric Power Research Institute (EPRI) study determined the maximum fluence over a 40-year service life in a spent fuel pool is 1 x 1012 neutron/cm 2.Extending the service life an additional 40 years to account for a 20-year plant operating license extension and an additional 20 years of storage could result in maximum fluence of less than 2 x 1012 neutrons/cm 2.The maximum fluence is equivalent to less than one second of in-reactor exposure, therefore, no measurable depletion of rodlet boron will occur over the lifetime of the rodlets. Tests performed by EPRI, to an upper bound of 1 x 1017 neutrons/cm 2 , determined that there was no significant change in borated stainless steel material properties.
No significant change in material properties is projected over the lifetime of the rodlets, providing high confidence that the material and neutronic characteristics of the rodlets will remain within the assumptions of the criticality analysis.c. DNC's current program for surveillance and inspection of the poison rodlets is consistent with that which was described in the July 16, 1993 letter (Reference 1).There are 2491 rodlets available for use, of which 27 rodlets installed in 9 selected fuel assemblies are designated as surveillance rodlets. These 27 rodlets, which have been in continuous use since installation, are representative of all rodlets installed in the spent fuel pool. Following initial selection as surveillance rodlets, the same rodlets are re-inspected during subsequent periods of inspections to permit trending of rodlet material condition.
Beginning in 1999, inspections have been performed at 5-year intervals.
Each surveillance rodlet is removed from the spent fuel pool and a detailed visual inspection is performed to identify any cracks, blisters, missing pieces of surface material, corrosion, or pitting. Any observed material abnormality would result in a more detailed assessment to evaluate the significance.
In 2004, a small nick was identified on one rodlet. The size of the indication was approximately 1/16" x 1/8".The assessment of this abnormality concluded that "minimal, if any, material has been removed" and it "does not affect the boron content of the rodlet." The 2009 inspection found no indication of degradation for any of the 27 rodlets. Therefore, the boron content in the rodlets remains at the criticality analysis assumed boron content of 2 percent.
References:
- 1. J. F. Opeka, Northeast Nuclear Energy Company to the Nuclear Regulatory Commission, "Millstone Nuclear Power Station Unit 2, Response to Request for Additional Information," July 16, 1993