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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
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STATE OF WASHINGTON DEPARTMENT OF HEALTH DIVISION OF RADIATION PROTECTION 7171 Cleanwater Lane, Bldg. 5 @P.O. Bov 47827 - Olympia, Washington 98504-7827 TDD Relay 1-800-833-6388 25 February 2003 Christepher McKenney System Performance Analyst Environmental and Performance Assessment Branch Office of Nuclear Material Safety and Safeguards Mail Stop T-7J8 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Dear Mr. McKenney:
This letter is in response to the Nuclear Regulatory Commission's (NRC) request for comments on its Safety Analysis Report (SAR) concerning Long-Term Hazard of Millstone Unit 1 's Missing Spent Fuel Rods Potentially Disposedat the Hanford Commercial Low-Level Radioactive Waste DisposalFacility. This report was published in the January 6, 2003 Federal Register (Volume 68, Number 3, page 588-589).
The SAR states that the rods may have been unintentionally disposed of at the Hanford, Washington commercial low-level radioactive waste (LLRW) disposal facility, but most likely were inadvertently shipped to the Barnwell LLRW site. The NRC's SAR concluded that if the rods were shipped to Hanford, they would not constitute a present or future risk to the public health and safety of the environment.
The Washington State Department of Health staff have considered the source term of the Millstone fuel rods in its dose assessment portion of the Environmental Impact Statement (EIS) being prepared for the US Ecology facility, and have determined that the fuel rods present negligible additional risk. However, we cannot concur with the NRC's conclusions until the Final Environmental Impact Statement is completed and the public has an opportunity to comment. The Final EIS is estimated to be completed by mid-2003.
The department also has the following comments regarding the SAR:
The statement on page 3 "This includes some other spent fuel that was legally disposed in Hanford during the 1970's" should be clarified. It should be made clear that any fuel waste legally disposed during the 1970's was accepted and authorized under the U.S. Nuclear Regulatory Commission's Special Nuclear Materials license. Although the source term tIsý
Christepher McKenney Page 2 of 2 February 25, 2003 from these wastes were included in the state of Washington's dose assessment for the EIS that is being prepared for the facility, it is requested that all fuel waste disposed at the facility under the U.S. NRC license be accounted for and quantified.
On page 3, the EIS source term for Tc-99 is 50 Ci, rather than 60 Ci.
We would like assurance that the presence of both the legally disposed fuel waste and the potential disposal of the Millstone fuel rods at the Hanford facility will not affect the transfer of the facility to the federal government custodian (US DOE) after site closure.
If you have any questions, please feel free to contact me at (360) 236-3210.
Sincerely, Gary Rcbfrtson, Director Divisio6f Radiation Protection cc: Lilia Lopez, Assistant Attorney General Radiation Protection, Richland Larry Goldstein, Department of Ecology Mike Garner, Department of Ecology