ML17090A428: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 20: | Line 20: | ||
No Significant Hazards Consideration Determination and Environmental Consideration Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No. 17-113 Docket No. 50-423 Page 2 of 2 Attachmenf Serial No. 17-113 Docket No. 50-423 No Significant Hazards Consideration Determination and Environmental Consideration DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3 No Significant Hazards Consideration Determination Serial No. 17-113 Docket No. 50-423 Attachment, Page 1 of 3 Dominion Nuclear Connecticut, Inc. (DNC) is requesting an exemption from certain requirements of 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," and Appendix K of 10 CFR 50, "ECCS Evaluation Models" for Millstone Power Station (MPS) Unit 3 (MPS3). DNC requested the exemption to allow up to eight lead test assemblies (L TAs) containing fuel rods fabricated with AXIOM cladding. The exemption request is required since the metallurgical content of the AXIOM material is outside the metallurgical content of cladding types approved for use at MPS3 (i.e., Zirc-4, ZIRLO, or Optimized ZIRLOŽ). The NRC has provided standards for determining whether a significant hazards consideration exists in 10 CFR 50.92(c). A determination that a proposed exemption involves no significant hazards consideration may be made if operation of the facility in accordance with the proposed exemption would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or 3) involve a significant reduction in a margin of safety. DNC has evaluated if a significant hazards consideration is involved with the proposed exemption request. A discussion of these standards as they relate to this exemption request is provided below. 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? No. The proposed exemption would allow DNC to insert up to eight L TAs with AXIOM fuel rod cladding at MPS3. The proposed exemption from the requirements of 10 CFR 50.46 and 10 CFR 50, Appendix K, to permit the use of the AXIOM cladding material in the MPS3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. AXIOM cladding material is not an accident initiator. The response of the fuel to an accident is analyzed using conservative techniques, and the results are compared to NRG-approved acceptance criteria. Reload specific analyses conducted by DNC and the fuel vendor demonstrate the design limits of the fuel cladding are met. Station operation and analysis will continue to be in compliance with NRC regulations. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Thus, the plant will continue to meet applicable design criteria and safety analysis acceptance criteria. Consequently, permitting the insertion of up, to eight L TAs with AXIOM fuel rod | No Significant Hazards Consideration Determination and Environmental Consideration Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No. 17-113 Docket No. 50-423 Page 2 of 2 Attachmenf Serial No. 17-113 Docket No. 50-423 No Significant Hazards Consideration Determination and Environmental Consideration DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3 No Significant Hazards Consideration Determination Serial No. 17-113 Docket No. 50-423 Attachment, Page 1 of 3 Dominion Nuclear Connecticut, Inc. (DNC) is requesting an exemption from certain requirements of 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," and Appendix K of 10 CFR 50, "ECCS Evaluation Models" for Millstone Power Station (MPS) Unit 3 (MPS3). DNC requested the exemption to allow up to eight lead test assemblies (L TAs) containing fuel rods fabricated with AXIOM cladding. The exemption request is required since the metallurgical content of the AXIOM material is outside the metallurgical content of cladding types approved for use at MPS3 (i.e., Zirc-4, ZIRLO, or Optimized ZIRLOŽ). The NRC has provided standards for determining whether a significant hazards consideration exists in 10 CFR 50.92(c). A determination that a proposed exemption involves no significant hazards consideration may be made if operation of the facility in accordance with the proposed exemption would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or 3) involve a significant reduction in a margin of safety. DNC has evaluated if a significant hazards consideration is involved with the proposed exemption request. A discussion of these standards as they relate to this exemption request is provided below. 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? No. The proposed exemption would allow DNC to insert up to eight L TAs with AXIOM fuel rod cladding at MPS3. The proposed exemption from the requirements of 10 CFR 50.46 and 10 CFR 50, Appendix K, to permit the use of the AXIOM cladding material in the MPS3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. AXIOM cladding material is not an accident initiator. The response of the fuel to an accident is analyzed using conservative techniques, and the results are compared to NRG-approved acceptance criteria. Reload specific analyses conducted by DNC and the fuel vendor demonstrate the design limits of the fuel cladding are met. Station operation and analysis will continue to be in compliance with NRC regulations. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Thus, the plant will continue to meet applicable design criteria and safety analysis acceptance criteria. Consequently, permitting the insertion of up, to eight L TAs with AXIOM fuel rod | ||
. ' Serial No. 17-113 Docket No. 50-423 Attachment, Page 2 of 3 cladding in the MPS3 core does not affect the probability of an accident or transient or the consequences thereof. Therefore, the proposed exemption does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different type of accident from any accident previously evaluated? No. The proposed exemption from the requirements of 10 CFR 50.46, and 10 CFR 50, Appendix K, does not impact the plant configuration or systeni performance. The proposed exemption does not modify any interfaces with existing equipment, change the equipment's function, or change the method of operating the equipment. Use of the AXIOM fuel rod cladding material in the MPS3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM L TAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current NRG-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the L TAs with AXIOM fuel rod cladding will not be inserted into the core. The proposed exemption assures there is adequate margin available to meet safety analysis criteria and does not introduce any failure modes, accident initiators, or equipment malfunctions that would cause a new or different kind of accident. Therefore, the proposed exemption does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? No. The proposed exemption from the requirements of 10 CFR 50.46, and 10 CFR 50, Appendix K, does not impact the plant configuration or system performance and use of the AXIOM cladding material in the MPS3 core does not adversely affect any fission product barrier. Current NRG-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior to ensure the plant continues to meet applicable design criteria and safety analysis acceptance criteria. The proposed exemption does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined, and the dose analysis | . ' Serial No. 17-113 Docket No. 50-423 Attachment, Page 2 of 3 cladding in the MPS3 core does not affect the probability of an accident or transient or the consequences thereof. Therefore, the proposed exemption does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different type of accident from any accident previously evaluated? No. The proposed exemption from the requirements of 10 CFR 50.46, and 10 CFR 50, Appendix K, does not impact the plant configuration or systeni performance. The proposed exemption does not modify any interfaces with existing equipment, change the equipment's function, or change the method of operating the equipment. Use of the AXIOM fuel rod cladding material in the MPS3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM L TAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current NRG-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the L TAs with AXIOM fuel rod cladding will not be inserted into the core. The proposed exemption assures there is adequate margin available to meet safety analysis criteria and does not introduce any failure modes, accident initiators, or equipment malfunctions that would cause a new or different kind of accident. Therefore, the proposed exemption does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? No. The proposed exemption from the requirements of 10 CFR 50.46, and 10 CFR 50, Appendix K, does not impact the plant configuration or system performance and use of the AXIOM cladding material in the MPS3 core does not adversely affect any fission product barrier. Current NRG-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior to ensure the plant continues to meet applicable design criteria and safety analysis acceptance criteria. The proposed exemption does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined, and the dose analysis | ||
. ,. Serial No. 17-113 Docket No. 50-423 Attachment, Page 3 of 3 acceptance criteria are not affected. The proposed exemption does not result in plant operation in a configuration outside the analyses or design basis and does not adversely affect systems that respond to safely shutdown the plant and maintain the plant in a safe shutdown condition. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM L TAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the AXIOM cladding LTAs will not be inserted into the core. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, Dominion concludes that the proposed change does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of "no significant hazards consideration" is justified. Environmental Consideration Dominion has reviewed the proposed exemption for environmental considerations. The proposed exemption does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed exemption meets the eligibility criterion for categorical exclusion from an environmental assessment as set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed exemption. | . ,. Serial No. 17-113 Docket No. 50-423 Attachment, Page 3 of 3 acceptance criteria are not affected. The proposed exemption does not result in plant operation in a configuration outside the analyses or design basis and does not adversely affect systems that respond to safely shutdown the plant and maintain the plant in a safe shutdown condition. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM L TAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the AXIOM cladding LTAs will not be inserted into the core. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, Dominion concludes that the proposed change does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of "no significant hazards consideration" is justified. Environmental Consideration Dominion has reviewed the proposed exemption for environmental considerations. The proposed exemption does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed exemption meets the eligibility criterion for categorical exclusion from an environmental assessment as set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed exemption.}} | ||
}} | |||
Revision as of 21:47, 18 May 2018
| ML17090A428 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/27/2017 |
| From: | Sartain M D Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17090A428 (6) | |
Text
Dominion Nuclear Connecticut, Inc. 5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 March 27, 2017 DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3 Dominion Serial No. NRA/WDC Docket No. License No.17-113 RO 50-423 NPF-49 SUPPLEMENT TO PROPOSED EXEMPTION REQUEST FOR THE USE OF AXIOM CLADDING MATERIAL IN LEAD TEST ASSEMBLIES In a letter dated June 30, 2016, Dominion Nuclear Connecticut, Inc. (DNC) requested an exemption from certain requirements of 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," and Appendix K of 10 CFR 50, "ECCS Evaluation Models" for Millstone Power Station (MPS) Unit 3 (MPS3). DNC requested the exemption to allow up to eight lead test assemblies containing fuel rods fabricated with AXIOM cladding. The exemption request is required since the metallurgical content of the AXIOM material is outside the metallurgical content of cladding types approved for use at MPS3 (i.e., Zirc-4, ZIRLO, or Optimized ZIRLO Ž). This letter supplements the June 30, 2016 exemption request with a no significant hazards consideration determination and a statement regarding categorical exclusion from an environmental assessment as set forth in 10 CFR 51.22(c)(9). Attachment 1 provides the supplemental information. DNC has reviewed the proposed exemption and determined the proposed exemption does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and meets the eligibility criterion for categorical exclusion from an environmental assessment. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for the proposed exemption. If you have any questions regarding this request, please contact Wanda Craft at (804) 273-4687. Sincerely, Mark D. Sartain Vice President -Nuclear Engineering and Fleet Support
Attachment:
No Significant Hazards Consideration Determination and Environmental Consideration Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No.17-113 Docket No. 50-423 Page 2 of 2 Attachmenf Serial No.17-113 Docket No. 50-423 No Significant Hazards Consideration Determination and Environmental Consideration DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3 No Significant Hazards Consideration Determination Serial No.17-113 Docket No. 50-423 Attachment, Page 1 of 3 Dominion Nuclear Connecticut, Inc. (DNC) is requesting an exemption from certain requirements of 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," and Appendix K of 10 CFR 50, "ECCS Evaluation Models" for Millstone Power Station (MPS) Unit 3 (MPS3). DNC requested the exemption to allow up to eight lead test assemblies (L TAs) containing fuel rods fabricated with AXIOM cladding. The exemption request is required since the metallurgical content of the AXIOM material is outside the metallurgical content of cladding types approved for use at MPS3 (i.e., Zirc-4, ZIRLO, or Optimized ZIRLOŽ). The NRC has provided standards for determining whether a significant hazards consideration exists in 10 CFR 50.92(c). A determination that a proposed exemption involves no significant hazards consideration may be made if operation of the facility in accordance with the proposed exemption would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or 3) involve a significant reduction in a margin of safety. DNC has evaluated if a significant hazards consideration is involved with the proposed exemption request. A discussion of these standards as they relate to this exemption request is provided below. 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? No. The proposed exemption would allow DNC to insert up to eight L TAs with AXIOM fuel rod cladding at MPS3. The proposed exemption from the requirements of 10 CFR 50.46 and 10 CFR 50, Appendix K, to permit the use of the AXIOM cladding material in the MPS3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. AXIOM cladding material is not an accident initiator. The response of the fuel to an accident is analyzed using conservative techniques, and the results are compared to NRG-approved acceptance criteria. Reload specific analyses conducted by DNC and the fuel vendor demonstrate the design limits of the fuel cladding are met. Station operation and analysis will continue to be in compliance with NRC regulations. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Thus, the plant will continue to meet applicable design criteria and safety analysis acceptance criteria. Consequently, permitting the insertion of up, to eight L TAs with AXIOM fuel rod
. ' Serial No.17-113 Docket No. 50-423 Attachment, Page 2 of 3 cladding in the MPS3 core does not affect the probability of an accident or transient or the consequences thereof. Therefore, the proposed exemption does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different type of accident from any accident previously evaluated? No. The proposed exemption from the requirements of 10 CFR 50.46, and 10 CFR 50, Appendix K, does not impact the plant configuration or systeni performance. The proposed exemption does not modify any interfaces with existing equipment, change the equipment's function, or change the method of operating the equipment. Use of the AXIOM fuel rod cladding material in the MPS3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM L TAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current NRG-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the L TAs with AXIOM fuel rod cladding will not be inserted into the core. The proposed exemption assures there is adequate margin available to meet safety analysis criteria and does not introduce any failure modes, accident initiators, or equipment malfunctions that would cause a new or different kind of accident. Therefore, the proposed exemption does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? No. The proposed exemption from the requirements of 10 CFR 50.46, and 10 CFR 50, Appendix K, does not impact the plant configuration or system performance and use of the AXIOM cladding material in the MPS3 core does not adversely affect any fission product barrier. Current NRG-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior to ensure the plant continues to meet applicable design criteria and safety analysis acceptance criteria. The proposed exemption does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined, and the dose analysis
. ,. Serial No.17-113 Docket No. 50-423 Attachment, Page 3 of 3 acceptance criteria are not affected. The proposed exemption does not result in plant operation in a configuration outside the analyses or design basis and does not adversely affect systems that respond to safely shutdown the plant and maintain the plant in a safe shutdown condition. Westinghouse will perform an evaluation of the MPS3 core using Loss of Coolant Accident (LOCA) methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM L TAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the AXIOM cladding LTAs will not be inserted into the core. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, Dominion concludes that the proposed change does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of "no significant hazards consideration" is justified. Environmental Consideration Dominion has reviewed the proposed exemption for environmental considerations. The proposed exemption does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed exemption meets the eligibility criterion for categorical exclusion from an environmental assessment as set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed exemption.