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Category:Letter
MONTHYEARIR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages 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) ML23342A0972024-01-0909 January 2024 Connecticut Yankee Atomic Power Company - Independent Spent Fuel Storage Installation Security Inspection Plan 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 . ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal 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) ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations CY-23-014, Biennial Update of the CYAPCO Quality Assurance Program for the Haddam Neck ISFSI2023-12-0404 December 2023 Biennial Update of the CYAPCO Quality Assurance Program for the Haddam Neck ISFSI 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 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations 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 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 2024-01-09
[Table view] Category:Rulemaking-Comment
MONTHYEARCY-17-017, Comment (18) from the Connecticut Yankee Atomic Power Company Regarding Regulatory Improvements for Power Reactors Transitioning to Decommissioning2017-06-13013 June 2017 Comment (18) from the Connecticut Yankee Atomic Power Company Regarding Regulatory Improvements for Power Reactors Transitioning to Decommissioning CY-16-014, Comment (094) of Robert Mitchell on Behalf of Connecticut Yankee Atomic Power Co on ANPR-26, 50, 52, 73, and 140 - Regulatory Improvements for Decommissioning Power Reactors2016-03-17017 March 2016 Comment (094) of Robert Mitchell on Behalf of Connecticut Yankee Atomic Power Co on ANPR-26, 50, 52, 73, and 140 - Regulatory Improvements for Decommissioning Power Reactors CY-15-026, Comment (60) from Connecticut Yankee Atomic Power Company Regarding the Advance Notice of Proposed Rulemaking for 10 CFR Part 20 - Radiation Protection2015-06-16016 June 2015 Comment (60) from Connecticut Yankee Atomic Power Company Regarding the Advance Notice of Proposed Rulemaking for 10 CFR Part 20 - Radiation Protection CY-13-027, Comment (4) of Brantley Buerger on the Draft Regulatory Basis Document to Support Potential Amendment to Regulations Concerning Nuclear Power Plant Licenses' Station Blackout Mitigation Strategies (10 CFR Part 50 and 52), (NRC-2011-0299)2013-05-0202 May 2013 Comment (4) of Brantley Buerger on the Draft Regulatory Basis Document to Support Potential Amendment to Regulations Concerning Nuclear Power Plant Licenses' Station Blackout Mitigation Strategies (10 CFR Part 50 and 52), (NRC-2011-0299) CY-12-038, Comment (16) of Jim Lenois on Behalf of Connecticut Yankee Atomic Power Company, on ANPR 50 and ANPR 52, Regarding Onsite Emergency Response Capabilities2012-06-18018 June 2012 Comment (16) of Jim Lenois on Behalf of Connecticut Yankee Atomic Power Company, on ANPR 50 and ANPR 52, Regarding Onsite Emergency Response Capabilities ML11180A1832011-06-27027 June 2011 2011/06/27-Comment (54) of Mary Ellen Marucci, Supporting Petition for Rulemaking PRM-50-96, Regarding NRC Amend Its Regulations Regarding the Domestic Licensing of Special Material L-09-081, Comment (55) of C.L. Funderburk on Behalf of Dominion Resources Services, Inc., on Proposed Rule Pr 31, Regarding Limiting the Quantitiy of Byproduct Material in a Generally Licensed Device2009-10-28028 October 2009 Comment (55) of C.L. Funderburk on Behalf of Dominion Resources Services, Inc., on Proposed Rule Pr 31, Regarding Limiting the Quantitiy of Byproduct Material in a Generally Licensed Device ML0929309822009-10-19019 October 2009 2009/10/19-Comment (26) of Mary Lampert, Et. Al., on Behalf of Pilgrim Watch on Rules PR-50 and 50, Enhancements to Emergency Preparedness Regulations. ML0919003662009-06-23023 June 2009 Comment (36) of C.L. Funderburk on Behalf of Dominion on Draft Regulatory Guide DG-4014, Radiological Surveys and Monitoring During Operations. in Regards to Pr 20,30,40,50,70 and 72, Decommissioning Planning ML0904405572009-02-0303 February 2009 Comment (114) of Pam Mcdonald on Pr 51 Consideration of Environmental Impacts of Temporary Storage of Spent Fuel After Cessation of Reactor Operation, and Pr 51 Waste Confidence Decision Update ML0726705742007-09-24024 September 2007 Comment (13) of Lisa Rainwater on Behalf of Riverkeeper on Epstein'S PRM-50-85 Re to Extend the Minimum Distance from Five to Ten Miles for Host School Pick-up Points Beyond Plume Exposure Boundary Line ML0719201582007-06-27027 June 2007 Comment (23) of Charles A. Tomes on Proposed Rules Pr 50 Regarding Industry Codes and Standards; Amended Requirements ML0717601892007-06-25025 June 2007 Comment (2) of Chris L. Funderburk Submitted by Dominion on Ucs'S PRM-73-13 Re Amend to 10 CFR Part 7, Physical Protection of Plants and Materials ML0717702482007-06-15015 June 2007 Comment (16) Submitted by Charles A. Tomes on Proposed Rule Pr 50 Regarding Industry Codes and Standards; Amended Requirements ML0716404952007-06-13013 June 2007 Comment (11) Submitted by Dominion Energy Kewaunee, Inc. (Dek), Dominion Nuclear Connecticut, Inc. (Dnc), and Virginia Electric and Power Company (Dominion), Chris L. Funderburk on Pogo and Ucs PRM-50-83 Re Amend 10 CFR Part 50 Concerning D ML0707906742007-03-19019 March 2007 Comment (59) Submitted by Eleanor I. Gavin on Massachusetts Attorney General'S PRM-51-10 Re Amend of 10 CFR Part 51 - Spent Fuel ML0707303612007-03-14014 March 2007 Comment (37) Submitted by Connecticut Coalition Against Millstone, Nancy Burton on Petition for Rulemaking PRM-51-10 - Environmental Impacts of Spent Reactor Fuel Pool Storage ML0703705632007-02-0505 February 2007 Comment (66) Submitted by Nancy Burton on Behalf of the Connecticut Coalition Against Millstone on Shaw'S PRM-51-11 Re Application of National Academy of Science BEIR-VII Standard to Dose Radiation Calculation ML0606600282006-02-0303 February 2006 Comment (106) Submitted by the Assembly State of New York, Kenneth P. Lavalle & Fred W. Thiele on Proposed Rule PR-73, Regarding Deisgn Basis Threat ML0604405372006-01-23023 January 2006 Comment (82) Submitted by Dominion Resources Services, Inc., C. L. Funderburk on Proposed Rule PR-73 Regarding Design Basis Threat ML0407005072004-03-0404 March 2004 Comment (12) Submitted by Dominion Resources Services, Inc., Chris Funderburk on Proposed Rules PR-170 and PR-171 Re Revision of Fee Schedules; Fee Recovery for Fy 2004 ML0328203602003-10-0202 October 2003 Comment (2) Submitted by Dominion Resources Services, Inc., Chris L. Funderburk on Proposed Rule PR-50 Re Emergency Planning and Preparedness for Production and Utilization Facilities ML0226203322002-09-10010 September 2002 Comment of Stephen P. Sarver on Draft Document Environmental Review Guidance for Licensing Actions Associated with NMSS Programs. ML0404800311987-07-0202 July 1987 Comment (83) of E. J. Mroczka on Advance Notice of Proposed Rule Definition of High-Level Radioactive Waste 2017-06-13
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DOCKET NUMBER A PROPOSED RULE PR (gg b~e.3-qvz ( D NORTHEAST UTLITfIES~~~~ ~~Wcg'Im.
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' p :22 July 2, 1987 Docket Nos. 50-213 50-245 50-336 50423 B12580 Mr. Samuel 3. Chilk Secretary of the Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Docketing and Service Branch Gentlemen:
Haddam Neck Plant Millstone Nuclear Power'Station, Unit Nos. 1, 2 and 3 Comments on Advance Notice of Proposed Rule Definition of High-Level Radioactive Wastes On February 27, 1987,(1) the Nuclear Regulatory Commission (NRC) published for public comment an Advance Notice of Proposed Rulemaking (ANPR) which would modify the definition of high-level radioactive waste in order to follow more closely the statutory definition in the Nuclear Waste Policy Act (NWPA) of 1982. Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) respectfully submit the following comments on the ANPR.Our comments pertain to the "Activated Metals" section of the Appendix to the ANPR, in which it is stated: '1_j11 N. 1-.41. "Other than perhaps a few isolated casesi all of the spent fuel assemblies are being stored by licensees with the hardware still attached." 2. "Disposal responsibility Eof the activated hardware]
becomes less clear if licensees, seeking more efficient on-site storage, consolidated fuel themselves." NNECO and CYAPCO do not believe that It Is appropriate for the NRC to speculate in rulemaking proceedings related to the definition of a technical term either on: (a) statutory/contractual matters concerning implementation of the (0)52 Federal Register 5992, February 27, 1987 8707100290 970702 PDR PR PDR 1\0 60 52FR5992 D_4_QL__gjQ07
-_9W.... 7 .-:'. ... __ , , -rr Vrwr Mr. Samuel J. Chilk B12580/Page 2 3uly 2, 1987 NWPA or (b) the degree of success that a given technology will enjoy.Therefore, we respectfully request that the pertinent paragraphs containing the above quotations be deleted or revised to reflect the discussion below.The cited Appendix contains information that would suggest the antithesis of item (2) above. Specifically, the Appendix states that consolidation of fuel"enables more economical storage and easier handling for transport and disposal." Indeed the potential benefits of reduced fuel shipments resulting from a national at-reactor consolidation program can be substantial.
There would also be positive benefits for state traffic considerations, cask manufacturing costs and capacity requirements as well as system transportation and operation costs.Accordingly, the volume of activated materials resulting from spent fuel consolidation activities may come from more than a "few Isolated cases." The United States Department of Energy (DOE) has anticipated performing consolidation activities at a monitored retrievable storage (MRS) facility to achieve shipping and handling benefits relative to transportation to and disposal in a repository.
These benefits are of a similar nature to those which would also accrue for at-reactor consolidation prior to shipment to an MRS or a repository.
The Federal Government is responsible for disposal of the scrap derived from utilities' fuel that would be consolidated at an MRS or a repository, and must be similarly responsible for disposal of fuel hardware derived from at-reactor consolidation programs.Finally, the DOE, itself, has sought to clarify that it Intends to accept consolidated fuel assemblies, including the non-fuel components removed during consolidation for disposal (letter from R. H. Bauer, DOE, to 3. B. Hall, Utility Nuclear Waste Management Group, dated September 13, 1985, attached).
The NRC's rulemaking should be consistent with the DOE's stated intention.
We trust that these comments will be useful In finalization of the proposed rule.Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY SEn'.,iceroczka g Senior Vice President Mr. Samuel J. Chilk B12580/Page 3 3uly 2, 1987 cc: W. TP Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone -Unit No. I D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2 R. L. Ferguson, NRC Project Manager, Millstone Unit No. 3 F. M. Akstulewicz, NRC Project Manger, Haddam Neck Plant T. Rebelowski, Resident Inspector, Millstone Unit Nos. 1 and 2 3. T. Shedlosky, Resident Inspector, Millstone Unit No. 3 P. D. Swetland, Resident Inspector, Haddam Neck Plant B. C. Rushe, Director, DOE Office of Civilian Radioactive Waste Management Department of Energy Washington.
DC 2DSS SEP1 James B. Hall, Director Utility Nuclear Waste Management Group 11 l2th Street, N.W.Washington, D.C. 20036
Dear Mr. Hall:
This is in response to your letter of August 21, 1985 to Mr. Rusche, which requested clarification of two aspects of the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste.With regard to "other than standard fuel" -it is the Department's intent that all currently designed nuclear fuel, includirg that falling outside the maximum physical dimensions specifiled in Appendix E, will be subject to the same scheduling procedures.
It is also the Department's intent that consolidated fuel assemblies, including the non-fuel components removed during consolidation (control spiders, thimble plugs, neutron sources,-etc.), may be delivered for disposal in accordance with the Standard Contract subject to the same scheduling procedures as f~r otherv TueT. murther, such consolidated fuel-assemblies and associated non- fuel cmDDnenlts canned in a container provided by or approvea by the Department, will be treated as the equivalent of one fuel assembly for acceptance priority allocation purposes provided that this does not reduce the acceptance rate of other contract holGer."'
Failed fuel canned in a container provided by or approved by the tepartment also will be subject to the same scheduling procedures as other spent fuel.With regard to proof of ownership
-the following two statements supplied with Appendices C and D respectively will meet the proof of ownership requirements of the Standard Contract: Purchaser hereby certifies that the Spent Nuclear Fuel to be delivered pursuant to this Delivery Commitment Schedule has been discharged from a Civilian Nuclear Power Reactor covered by Purchaser's contract No. and that Purchaser has the legal right to deliver such Spent Nuclear Fuel to DOE for disposal.Purchaser hereby certifies that the Spent Nuclear Fuel to be delivered pursuant to this Final Delivery Schedule has been discharged from a Civilian Nuclear Power Reactor covered by Purchaser's contract No. and that Purchaser has the legal right to deliver such Spent Nuclear Fuel to DOE for disposal.
jI.-2 -If I can be of further assistance hesitate to contact me.in this regard, please do not Sincerely, Rert H. Sauer A sociate Director for Resource Management Office of Civilian Radioactive Waste Management 9.%.4...Jr U