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MONTHYEARML0318805582003-07-0909 July 2003 Request for Additional Information, Technical Specification Change to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit Project stage: RAI ML0319806092003-07-25025 July 2003 Second Request for Additional Information, Technical Specification Change to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit (Tac No. MB8896) Project stage: RAI ML0327401222003-09-25025 September 2003 Response to RAI Concerning the License Amendment Request to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit Project stage: Response to RAI ML0331400752003-11-0303 November 2003 Response to Second RAI Concerning the License Amendment Request to Increase the Spent Fuel Maximum Enrichment Limit with Soluble Boron Credit Project stage: Request ML0406106792004-02-25025 February 2004 Response to Third RAI Concerning the License Amendment to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit Project stage: Other ML0406505312004-04-0202 April 2004 Environmental Assessment, Finding of No Significant Impact Related to a Proposed Amendment to Increase Maximum Enrichment of Fuel Assemblies in Spent Fuel Pool Project stage: Other ML0410401292004-06-0303 June 2004 License Amendment Re Amendment to Increase the Spent Fuel Pool Maximum Enrichment Limit Project stage: Acceptance Review ML0418202322004-06-23023 June 2004 Correction to Technical Specifications for Amendment No. 267 (TAC MB8896). Table of Contents, Page III & Page 4 of Appendix C Updated to Correct Errors Project stage: Other ML0417402582004-06-23023 June 2004 Ltr, Correction to Amendment No. 267 (TAC MB8896). Table of Contents, Page III & Page 4 of Appendix C Updated to Correct Errors Project stage: Other 2003-09-25
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Category:Environmental Assessment
MONTHYEARML20212L5892020-11-20020 November 2020 Encl: Environmental Assessment Memo to File: Environmental Assessment & Finding of No Significant Impact for Exelon Generation Co. Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Calvert Cliffs ISFSI ML20114E2312020-05-21021 May 2020 Environmental Assessment and Finding of No Significant Impact for Exemption from Holtec International Certificate of Compliance No. 1032 Fuel Specification and Loading Conditions at Calvert Cliffs Nuclear Power Plant ML1017605232011-01-0303 January 2011 Issuance of Environmental Assessment for Use of M5 Cladding Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (TAC Nos. ME2831 and ME2832) ML1033700972011-01-0303 January 2011 Environmental Assessment and Finding of No Significant Impact ML0622601052006-10-30030 October 2006 Environmental Assessment and Finding of No Significant Impact Temporary Exemption from the Requirements of 10 CFR 50.46 and 10 CFR 50, Appendix K ML0521404972005-08-25025 August 2005 Environmental Assessment and Finding of No Significant Impact Exemption from Requirements of 10 CFR 50.68 ML0406505312004-04-0202 April 2004 Environmental Assessment, Finding of No Significant Impact Related to a Proposed Amendment to Increase Maximum Enrichment of Fuel Assemblies in Spent Fuel Pool ML0333200092003-12-16016 December 2003 Exemption, Environmental Assessment Related to Exemption to 10 CFR 50, Appendix E, Section IV.F.2.C ML0224002452002-12-0606 December 2002 Environmental Assessment, Calvert Cliffs Request for an Exemption Dated August 6, 2002 That Would Allow Up to Four Lead Fuel Assemblies Manufactured by Framatome Anp, Inc., with Fuel Rods Clad With... (Tac No. MB4064) ML0215703152002-07-30030 July 2002 Units, 1 and 2, Environmental Assessment, Finding of No Significant Impact That Would Correct Administrative Errors in Section 5.6.5, of the TSs and Section 2.0 of the Environmental Protection Program (TAC No. MB3928 and MB3931) ML0225500531991-03-31031 March 1991 Environmental Assessment Related to Construction and Operation of the Calvert Cliffs Independent Spent Fuel Storage Installation 2020-05-21
[Table view] Category:Finding of No Significant Impact
MONTHYEARML20212L5892020-11-20020 November 2020 Encl: Environmental Assessment Memo to File: Environmental Assessment & Finding of No Significant Impact for Exelon Generation Co. Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Calvert Cliffs ISFSI ML0406505312004-04-0202 April 2004 Environmental Assessment, Finding of No Significant Impact Related to a Proposed Amendment to Increase Maximum Enrichment of Fuel Assemblies in Spent Fuel Pool ML0333200092003-12-16016 December 2003 Exemption, Environmental Assessment Related to Exemption to 10 CFR 50, Appendix E, Section IV.F.2.C 2020-11-20
[Table view] Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations 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 ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
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Text
April 2, 2004 Mr. George Vanderheyden, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 -
ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT RELATED TO A PROPOSED AMENDMENT TO INCREASE MAXIMUM ENRICHMENT OF FUEL ASSEMBLIES IN SPENT FUEL POOL (TAC NO. MB8896)
Dear Mr. Vanderheyden:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendment dated May 1, 2003, as supplemented September 25, 2003, November 3, 2003, and February 25, 2004. The proposed amendment would allow for increased enrichment of U235 in fuel assemblies stored in the Calvert Cliffs Nuclear Power Plant, Unit 1, spent fuel pool while accounting for soluble boron credit. This action will modify Technical Specifications Section 4.3.1 Criticality, add a new Section 3.7.16, Spent Fuel Pool Boron Concentration, and add a license condition to require the development of a long-term coupon surveillance program for the carborundum samples.
The assessment is being forwarded to the Office of Federal Register for publication.
Sincerely,
/RA/
Guy S. Vissing, Senior Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-317
Enclosure:
Environmental Assessment cc: w/encl: See next page
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 cc:
President Patricia T. Birnie, Esquire Calvert County Board of Co-Director Commissioners Maryland Safe Energy Coalition 175 Main Street P.O. Box 33111 Prince Frederick, MD 20678 Baltimore, MD 21218 James M. Petro, Esquire Mr. Loren F. Donatell Counsel NRC Technical Training Center Constellation Energy Group, Inc. 5700 Brainerd Road 750 East Pratt Street, 5th floor Chattanooga, TN 37411-4017 Baltimore, MD 21202 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge 2300 N Street, NW Washington, DC 20037 Mark Geckle Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean, Manager Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Kristen A. Burger, Esquire Maryland People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631
ML040650531 *EA provoded - no significant changes made OFFICE PDI-1/PM PDI-1/LA RELP* OGC PDI-1/SC NAME GVissing SLIttle JTappert LZaccari RLaufer DATE 3/18/04 3/18/04 2/23/04 3/24/04 3/31/04 7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION CALVERT CLIFFS NUCLEAR POWER PLANT, INC DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. DPR-53, issued to Calvert Cliffs Nuclear Power Plant, Inc. (the licensee), for operation of the Calvert Cliffs Nuclear Power Plant, Unit No. 1 (CCNPP1), located in Calvert County, MD. 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 increase the maximum enrichment limit of fuel assemblies stored in the CCNPP1 spent fuel pool from 4.52 weight percent U235 to 5.00 weight percent U235.
This would be accomplished by the licensee taking credit for soluble boron in maintaining acceptable margins of subcriticality. The proposed action only relates to Unit 1 because the storage racks in the Unit 2 spent fuel pool are of a different design, and require different controls. The Unit 2 spent fuel pool will remain at the current enrichment level of 4.52 weight percent U235. The proposed action will result in modification of Technical Specification (TS) Section 4.3.1, Criticality, addition of a new Section 3.7.16, Spent Fuel Pool Boron Concentration, and addition of a license condition to require the development of a long-term coupon surveillance program for the Carborundum samples.
The proposed action is in accordance with the licensees application dated May 1, 2003, as supplemented September 25, 2003, November 3, 2003, and February 25, 2004.
The Need for the Proposed Action:
The proposed action would allow the number of fresh fuel assemblies per cycle to be decreased, through allowing the maximum enrichment for fresh fuel to be increased to 5.00 weight percent U235 and allowing credit for soluble boron in the spent fuel pool. Through decreasing the number of fresh fuel assemblies per cycle, Independent Spent Fuel Storage Installation storage requirements will decrease, permanent Department of Energy storage requirements will decrease, and fuel cycle costs will decrease. Currently, TS Section 4.3.1, Criticality, limits the maximum enrichment for fuel assemblies to 4.52 weight percent U235, and does not allow the licensee to take credit for soluble boron in the spent fuel pool. Thus, the proposed changes to the TSs were requested.
Environmental Impacts of the Proposed Action:
The NRC has completed its safety evaluation of the proposed action and concludes that the storage and use of fuel enriched with U235 up to 5.00 weight percent at CCNPP1, is acceptable. The staffs safety evaluation addresses safety considerations at the higher enrichment level, and the staff has concluded that the proposed action will not adversely effect plant safety.
The proposed action will not significantly increase the probability or consequences of accidents. Even though there will be a higher enrichment of U235 in the fuel rods, accident consequences will not increase. According to the TSs, the spent fuel pool will contain enough soluble boron to ensure both subcriticality in the event of a dropped rod or accidental misloading, and significant negative reactivity in the event of a loss of normal spent fuel pool cooling.
No changes are being made in the types of effluents that may be released off site.
Water and soluble boron will continue to be the materials used to ensure subcriticality in the spent fuel pool. There is no significant increase in the amount of any effluent released off site.
Due to the higher enrichment of fuel, the boron concentration in the spent fuel pool will increase from the current value of 300 ppm to 350 ppm to safely store the higher enrichment fuel in the spent fuel pool. The addition of 50 ppm boron is approximately a 15-percent increase in boron concentration, but this is not a significant increase in the amount of radioactive waste. Boron will continue to be collected on the spent fuel pool filters as the water in the spent fuel pool is purified. The filters are replaced periodically and treated as low-level waste. There is no significant increase in occupational or public radiation exposure. Doses to workers will not increase from their current level due to the increased soluble boron concentration absorbing neutrons from the higher enrichment fuel rods in the spent fuel pool. 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 Impact Statement for CCNPP1 dated April 1973, and the Final Supplemental Environmental Impact Statement (NUREG-1437, Supplement 1) dated October 1999.
Agencies and Persons Consulted:
On August 21, 2003, the staff consulted with the Maryland State official, Richard McLean of the Department of the Environment, 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 letters dated May 1, 2003, September 23, 2003, November 3, 2003, and February 25, 2004. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 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.
Dated at Rockville, Maryland, this 2nd day of April 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Guy S. Vissing, Senior Project Manager,Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation