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MONTHYEARML0434802482004-12-13013 December 2004 Draft Request for Additional Information, Dominion Nuclear Connecticut, Inc. (DNC) Request for a Limited Exemption from Requirements of 10 CFR 50.68(b)(1). Project stage: Draft RAI ML0434905102004-12-14014 December 2004 Facsimile Transmission, Draft Request for Additional Information Project stage: Draft RAI ML0432202762005-02-0808 February 2005 Environmental Assessment and Finding of No Significant Impact Project stage: Other ML0504200582005-02-15015 February 2005 Exemption from the Requirements of 10 CFR Section 50.68(b)(1) Project stage: Approval 2004-12-14
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Category:Environmental Assessment
MONTHYEARML20332A1392020-12-0707 December 2020 Documentation of Completion of Required Actions Taken in Response to Lessons Learned from the Fukushima Dai-Ichi Accident ML19165A1202019-06-14014 June 2019 Enclosuenvironmental Assessment and Finding of No Significant Impact for the Virginia Electric and Power Company, Dominion Energy Kewaunee, Inc., and Dominion Nuclear Connecticut, Inc.'S Decommissioning Funding Plans Submitted ML17212A0012017-09-19019 September 2017 Letter Enclosing Environmental Assessment and Finding of No Significant Impact ML12212A2502012-08-13013 August 2012 Environmental Assessment and Finding of No Significant Impact Optimized Zirlo Fuel Rod Cladding Materials ML1213205742012-06-27027 June 2012 Environmental Assessment and Finding of No Significant Impact ML1213205762012-06-27027 June 2012 Environmental Assessment and Finding of No Significant Impact ML11138A0202011-08-22022 August 2011 Environmental Assessment and Finding of No Significant Impact ML1003304222010-03-19019 March 2010 Environmental Assessment and Finding of No Significant Impact ML1001311152010-01-12012 January 2010 Request for Exemptions from 10 CFR 73.55 Power Reactor Security Requirements Final Rule Additional Information ML0819300702008-07-30030 July 2008 Final Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate ML0808704572008-05-29029 May 2008 Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate ML0634902692007-01-11011 January 2007 Memo: K. Mcconnell to M. Lesar - Notice of Environmental Assessment and Finding of No Significant Impact Related to Partial Exemption from 10 CFR Part 50, Recordkeeping Requirements - Millstone Power Station, Unit 1 ML0432202762005-02-0808 February 2005 Environmental Assessment and Finding of No Significant Impact ML0332303792003-12-22022 December 2003 Environmental Assessment, Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of Title 10 of the Code of Federal Regulations, Section 54.17(c) ML0322000272003-10-0202 October 2003 Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of 10 CFR 50.44, 10 CFR 50.46, and 10 CFR Part 50, Appendix K ML0216800682002-07-10010 July 2002 Environmental Assessment Revised Final Safety Evaluation Report Licensing Basis for the Post-Accident Operation of the Supplementary Leakage Collection and Release System ML0205703072002-04-0808 April 2002 Environmental Assessment Revised Final Safety Evaluation Report Analysis of a Steam Generator Tube Rupture (Tac No. MB0866) ML0201802002002-01-18018 January 2002 Environmental Assessment, TAC Nos. MB2874, MB2875 and MB2876 Physical Protection License Condition and Site Name 2020-12-07
[Table view] Category:Finding of No Significant Impact
MONTHYEARML17212A0012017-09-19019 September 2017 Letter Enclosing Environmental Assessment and Finding of No Significant Impact ML12212A2502012-08-13013 August 2012 Environmental Assessment and Finding of No Significant Impact Optimized Zirlo Fuel Rod Cladding Materials ML1213205762012-06-27027 June 2012 Environmental Assessment and Finding of No Significant Impact ML11138A0202011-08-22022 August 2011 Environmental Assessment and Finding of No Significant Impact ML1003304222010-03-19019 March 2010 Environmental Assessment and Finding of No Significant Impact ML0808704572008-05-29029 May 2008 Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate ML0634902692007-01-11011 January 2007 Memo: K. Mcconnell to M. Lesar - Notice of Environmental Assessment and Finding of No Significant Impact Related to Partial Exemption from 10 CFR Part 50, Recordkeeping Requirements - Millstone Power Station, Unit 1 ML0432202762005-02-0808 February 2005 Environmental Assessment and Finding of No Significant Impact ML0332303792003-12-22022 December 2003 Environmental Assessment, Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of Title 10 of the Code of Federal Regulations, Section 54.17(c) ML0322000272003-10-0202 October 2003 Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of 10 CFR 50.44, 10 CFR 50.46, and 10 CFR Part 50, Appendix K ML0216800682002-07-10010 July 2002 Environmental Assessment Revised Final Safety Evaluation Report Licensing Basis for the Post-Accident Operation of the Supplementary Leakage Collection and Release System ML0201802002002-01-18018 January 2002 Environmental Assessment, TAC Nos. MB2874, MB2875 and MB2876 Physical Protection License Condition and Site Name 2017-09-19
[Table view] 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
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February 8, 2005 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 2 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT (TAC NO. MC5056)
Dear Mr. Christian:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application dated November 5, 2004, requesting an exemption from the requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 68, "Criticality Accident Requirements, Subsection (b)(1). The proposed exemption would allow the handling and storage of spent nuclear fuel in a 10 CFR Part 72 licensed spent fuel storage container in the Millstone Power Station, Unit 2 spent fuel pool with credit for soluble boron in the criticality analysis.
The Environmental Assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
As stated cc w/encl: See next page
ML043220276 OFFICE PDI-2/PM PDI-2/LA RLEP-C/SC OGC PDI-2/SC NAME VNerses CRaynor JTappert DCummings DRoberts DATE 2/2/05 2/2/05 12/14/04 1/07/05 2/8/05 Millstone Power Station, Unit No. 2 cc:
Lillian M. Cuoco, Esquire Mr. John Markowicz Senior Counsel Co-Chair Dominion Resources Services, Inc. Nuclear Energy Advisory Council Building 475, 5th Floor 9 Susan Terrace Rope Ferry Road Waterford, CT 06385 Waterford, CT 06385 Mr. Evan W. Woollacott Edward L. Wilds, Jr., Ph.D. Co-Chair Director, Division of Radiation Nuclear Energy Advisory Council Department of Environmental Protection 128 Terry's Plain Road 79 Elm Street Simsbury, CT 06070 Hartford, CT 06106-5127 Ms. Nancy Burton Regional Administrator, Region I 147 Cross Highway U.S. Nuclear Regulatory Commission Redding Ridge, CT 00870 475 Allendale Road King of Prussia, PA 19406 Mr. Chris L. Funderburk Director, Nuclear Licensing and First Selectmen Operations Support Town of Waterford Dominion Resources Services, Inc.
15 Rope Ferry Road Innsbrook Technical Center Waterford, CT 06385 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Charles Brinkman, Director Washington Operations Nuclear Services Mr. David W. Dodson Westinghouse Electric Company Licensing Supervisor 12300 Twinbrook Pkwy, Suite 330 Dominion Nuclear Connecticut, Inc.
Rockville, MD 20852 Building 475, 5th Floor Rope Ferry Road Senior Resident Inspector Waterford, CT 06385 Millstone Power Station c/o U.S. Nuclear Regulatory Commission P.O. Box 513 Niantic, CT 06357 Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, CT 06385
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO. 2 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 68, "Criticality Accident Requirements," Subsection (b)(1) for Facility Operating License No. DPR-65, issued to Dominion Nuclear Connecticut, Inc. (the licensee), for operation of the Millstone Power Station, Unit No. 2 (MP2), located in New London County, Connecticut.
Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would exempt the licensee from the requirements of 10 CFR 50.68, "Criticality Accident Requirements," Subsection (b)(1) during the handling and storage of spent nuclear fuel in a 10 CFR Part 72 licensed spent fuel storage container that is in the MP2 spent fuel pool. The proposed action is in accordance with the licensees application dated November 5, 2004.
The Need for the Proposed Action:
Under 10 CFR 50.68(b)(1), the Commission sets forth the following requirement that must be met, in lieu of a monitoring system capable of detecting criticality events:
Plant procedures shall prohibit the handling and storage at any one time of more fuel assemblies than have been determined to
be safely subcritical under the most adverse moderation conditions feasible by unborated water.
Section 50.12(a) allows licensees to apply for an exemption from the requirements of 10 CFR Part 50 if the regulation is not necessary to achieve the underlying purpose of the rule and other conditions are met. The licensee stated that compliance with 10 CFR 50.68(b)(1) is not necessary for handling the 10 CFR Part 72 licensed contents of the cask system, which is designed to preclude conditions for accidental criticality events, to achieve the underlying purpose of the rule.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes that the exemption described above would continue to satisfy the underlying purpose of 10 CFR 50.68(b)(1). The details of the NRC staff's safety evaluation will be provided in the exemption that will be issued as part of the letter to the licensee approving the exemption to the regulation.
The proposed action will not significantly increase the probability or consequences of accidents. No changes are being made in the types of effluents that may be released offsite.
There is no significant increase in the amount of any effluent release off site. There is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential non-radiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the no-action alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for the MP2 dated June 1973.
Agencies and Persons Consulted:
On December 23, 2004, the staff consulted with the Connecticut State official, Michael Firsick, of the Department of Environmental Protection, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated November 5, 2004. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff at 1-800-397-4209 or 301-415-4737, or
send an e-mail to pdr@nrc.gov. (Note: As of the date of issuance of this letter, public access to ADAMS has been temporarily suspended so that security reviews of publicly available documents may be performed and potentially sensitive information removed. Please check the NRC Web site for updates on the resumption of ADAMS access.)
Dated at Rockville, Maryland, this 8th day of February 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation