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| {{#Wiki_filter:7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from the requirements of Section III.G.1.b of Appendix R to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, for Facility Operating License No. DPR-40, issued to Omaha Public Power District (OPPD, the licensee), for operation of the Fort Calhoun Station, Unit No. 1, located in Washington County, Nebraska. 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 | | {{#Wiki_filter:7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from the requirements of Section III.G.1.b of Appendix R to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, for Facility Operating License No. DPR-40, issued to Omaha Public Power District (OPPD, the licensee), for operation of the Fort Calhoun Station, Unit No. 1, located in Washington County, Nebraska. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact. |
| : The proposed action would provide an exemption from the provisions of 10 CFR Part 50, Appendix R, Section III.G.1.b, for the 72-hour requirement to provide repair procedures and materials for cold shutdown capability for redundant cold shutdown components. The proposed action is in accordance with the licensee
| | ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action: |
| =s application dated February 4, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080360106), as supplemented by letter dated October 13, 2008 (ADAMS No. ML082980018). | | The proposed action would provide an exemption from the provisions of 10 CFR Part 50, Appendix R, Section III.G.1.b, for the 72-hour requirement to provide repair procedures and materials for cold shutdown capability for redundant cold shutdown components. |
| The Need for the Proposed Action
| | The proposed action is in accordance with the licensee=s application dated February 4, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080360106), as supplemented by letter dated October 13, 2008 (ADAMS No. ML082980018). |
| : The proposed action is needed to provide notification and clarification of the exemption granted by the NRC by letter dated July 3, 1985 (ADAMS Legacy Library Accession No. 850724390), in which the NRC granted an exemption from the technical requirements of Section III.G.2 of Appendix R to 10 CFR Part 50, for Fire Area 31 (intake structure building) and for the pull box area of the auxiliary building. The NRC safety evaluation report (SER) dated July 3, 1985, incorrectly referenced Section III.G.2 and subsequently provided exemption from 10 CFR Part 50, Section III.G. Specifically, the original SER and exemption should have referenced 10 CFR 50, Appendix R, Section III.G.1.b. In addition, cables in the duct bank and manhole vaults numbers 5 and 31 that are routed between the pull boxes and intake structure were not discussed in the OPPD exemption request dated August 30, 1983 (ADAMS Legacy Library Accession No. 830909011). Therefore, OPPD needs exemption from 10 CFR Part 50, Appendix R, III.G.1.b, for the cables in the duct bank and manhole vaults numbers 5 and 31 that are routed between the pull boxes and the intake structure building. Environmental Impacts of the Proposed Action
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| : The NRC has completed its safety evaluation of the proposed action and concludes that the consequences of postulated accidents are not increased, because there is no credible fire hazard in the area of the cable duct bank or manhole, which would disable all the raw water pumps and prevent the cold shutdown capability. Furthermore, if all raw water pumps are lost, due to any condition, the abnormal operating procedure directs the operator to trip the reactor and enter emergency procedures based on observed plant conditions. Therefore, there is no undue risk, since neither the probability nor the consequences have been increased, to public health and safety.
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| On the basis of its review and evaluation of the information provided in the licensee's exemption request and response to NRC staff request for additional information questions, the NRC staff concludes that OPPD's request for exemption from the technical requirements of Section III.G.1.b of Appendix R to 10 CFR Part 50 has provided a thorough description of the proposed change and adequate safety assessment which address the issue. The details of the NRC staff
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| =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 released offsite. 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.
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| Environmental Impacts of the Alternatives to the Proposed Action
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| : As an alternative to the proposed action, the NRC staff considered denial of the proposed action (i.e., the Ano-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.
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| Alternative Use of Resources | | The Need for the Proposed Action: |
| : The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for the Fort Calhoun Station dated August 1972.
| | The proposed action is needed to provide notification and clarification of the exemption granted by the NRC by letter dated July 3, 1985 (ADAMS Legacy Library Accession No. |
| | 850724390), in which the NRC granted an exemption from the technical requirements of Section III.G.2 of Appendix R to 10 CFR Part 50, for Fire Area 31 (intake structure building) and for the pull box area of the auxiliary building. The NRC safety evaluation report (SER) dated July 3, 1985, incorrectly referenced Section III.G.2 and subsequently provided exemption from 10 CFR Part 50, Section III.G. Specifically, the original SER and exemption should have referenced 10 CFR 50, Appendix R, Section III.G.1.b. In addition, cables in the duct bank and manhole vaults numbers 5 and 31 that are routed between the pull boxes and intake structure were not discussed in the OPPD exemption request dated August 30, 1983 (ADAMS Legacy Library Accession No. 830909011). Therefore, OPPD needs exemption from 10 CFR Part 50, Appendix R, III.G.1.b, for the cables in the duct bank and manhole vaults numbers 5 and 31 that are routed between the pull boxes and the intake structure building. |
| | Environmental Impacts of the Proposed Action: |
| | The NRC has completed its safety evaluation of the proposed action and concludes that the consequences of postulated accidents are not increased, because there is no credible fire hazard in the area of the cable duct bank or manhole, which would disable all the raw water pumps and prevent the cold shutdown capability. Furthermore, if all raw water pumps are lost, due to any condition, the abnormal operating procedure directs the operator to trip the reactor and enter emergency procedures based on observed plant conditions. Therefore, there is no undue risk, since neither the probability nor the consequences have been increased, to public health and safety. |
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| | On the basis of its review and evaluation of the information provided in the licensees exemption request and response to NRC staff request for additional information questions, the NRC staff concludes that OPPDs request for exemption from the technical requirements of Section III.G.1.b of Appendix R to 10 CFR Part 50 has provided a thorough description of the proposed change and adequate safety assessment which address the issue. |
| | 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 released offsite. 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 NRC staff considered denial of the proposed action (i.e., the Ano-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 Fort Calhoun Station dated August 1972. |
| Agencies and Persons Consulted: | | Agencies and Persons Consulted: |
| In accordance with its stated policy, on November 26, 2008, the NRC staff consulted with the Nebraska State official, Julia Schmitt, of the Department of Health and Human Services Regulation and Licensure, 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 licensee | | In accordance with its stated policy, on November 26, 2008, the NRC staff consulted with the Nebraska State official, Julia Schmitt, of the Department of Health and Human Services Regulation and Licensure, regarding the environmental impact of the proposed action. The State official had no comments. |
| =s letter dated February 4, 2008, as supplemented by letter dated October 13, 2008. Documents may be examined, and/or copied for a fee, at the NRC | | 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. |
| =s 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 Internet at 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 by telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to pdr.resource@nrc.gov. | | For further details with respect to the proposed action, see the licensee=s letter dated February 4, 2008, as supplemented by letter dated October 13, 2008. Documents may be examined, and/or copied for a fee, at the NRC=s 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 Internet at 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 by telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to pdr.resource@nrc.gov. |
| Dated at Rockville, Maryland, this 23 rd day of December 2008.
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| FOR THE NUCLEAR REGULATORY COMMISSION
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| /RA/ Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation}}
| | Dated at Rockville, Maryland, this 23rd day of December 2008. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation}} |
Letter Sequence Approval |
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MONTHYEARML0833602642008-09-17017 September 2008 E-mail Request for Additional Information Re Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 Project stage: RAI LIC-08-0109, Response to Request for Additional Information Concerning Exemption from Requirements of 10 CFR 50, Appendix R, Section Iii.G.B. for Fire Area 312008-10-13013 October 2008 Response to Request for Additional Information Concerning Exemption from Requirements of 10 CFR 50, Appendix R, Section Iii.G.B. for Fire Area 31 Project stage: Response to RAI ML0833300362008-12-23023 December 2008 Environmental Assessment and Finding of No Significant Impact, Re Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 Project stage: Approval ML0833300262008-12-23023 December 2008 Environmental Assessment and Finding of No Significant Impact Project stage: Other ML0900504382009-02-0606 February 2009 Transmittal Letter, Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 Project stage: Approval ML0900504422009-02-0606 February 2009 Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 Project stage: Approval NRC-2008-0670, Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 312009-02-0606 February 2009 Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 Project stage: Approval 2008-12-23
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Category:Environmental Assessment
MONTHYEARML23333A0492023-12-31031 December 2023 Final Fort Calhoun License Termination Plan Environmental Assessment ML21053A2332021-05-14014 May 2021 Enclosure 3: Final Environmental Assessment and Finding of No Significant Impact of Omaha Public Power Districts Initial and Updated Decommissioning Funding Plans for Fort Calhoun Nuclear Generating Station ISFSI ML17261A4192017-11-21021 November 2017 Letter, Environmental Assessment and Finding of No Significant Impact Re Exemption Request from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition ML1003602182010-03-0202 March 2010 Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request ML1003601772010-03-0202 March 2010 Cover Letter, Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request ML0833300362008-12-23023 December 2008 Environmental Assessment and Finding of No Significant Impact, Re Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 ML0620000972006-08-0909 August 2006 Environmental Assessment for Use of M5 ML0324005292003-08-28028 August 2003 Ltr Environmental Assessment Relating to Exemption from 10 CFR Part 20 Definition of Total Effective Dose Equivalent ML0320202182003-07-18018 July 2003 Ltr Environmental Assessment Relating to Exemption from the Requirements of Appendix G to 10 CFR Part 50 ML0202303432002-02-21021 February 2002 Environmental Assessment and Finding of No Significant Impact for an Exemption from the Requirements of Appendix G to 10 CFR Part 50 2023-12-31
[Table view] Category:Federal Register Notice
MONTHYEARML23333A1092023-12-27027 December 2023 Federal Register Notice - Fort Calhoun Station, Unit 1, License Termination Plan Finding of No Significant Impact ML22178A0472022-07-0404 July 2022 Enclosure - Federal Register Notice - Fort Calhoun Station, Unit 1 - FRN on Public Meeting and Request for Comment on License Termination Plan (License No. DPR-40, Docket No. 50-285) ML21055A4002021-05-14014 May 2021 Enclosure 1: Environmental Assessments and Findings of No Significant Impact of Independent Spent Fuel Storage Facilities Decommissioning Funding Plans Federal Register Notice ML19179A1242019-07-11011 July 2019 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI & SGI & Order Imposing Procedures for Access to SUNSI & SGI: August 6, 2019 ML18318A3602018-11-19019 November 2018 FRN Document for Partial Site Release Requests (License DPR-40,Docket Nos. 50-285 and 72-54) NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 20182017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17353A1922017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 NRC-2017-0223, FRN, Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003)2017-12-19019 December 2017 FRN, Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17278A1782017-12-19019 December 2017 FRN, Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17261A3432017-11-21021 November 2017 FRN, Environmental Assessment and Finding of No Significant Impact Re Exemption Request from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition ML17172A7352017-10-0404 October 2017 FRN, Partial Exemption from 10 CFR 50, Appendix B, 10 CFR 50.59(d)(3), and 10 CFR 50.71(c) Regarding Record Retention Requirements NRC-2017-0202, FRN, Partial Exemption from 10 CFR 50, Appendix B, 10 CFR 50.59(d)(3), and 10 CFR 50.71(c) Regarding Record Retention Requirements2017-10-0404 October 2017 FRN, Partial Exemption from 10 CFR 50, Appendix B, 10 CFR 50.59(d)(3), and 10 CFR 50.71(c) Regarding Record Retention Requirements NRC-2017-0175, Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 20172017-08-0404 August 2017 Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 2017 ML17213A1842017-08-0404 August 2017 Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 2017 NRC-2017-0160, FRN, Request for Exemption from Specific Provisions in 10 CFR 73.55 Related to Suspension of Security Measures for Licensed Senior Operator or Certified Fuel Handler2017-07-0707 July 2017 FRN, Request for Exemption from Specific Provisions in 10 CFR 73.55 Related to Suspension of Security Measures for Licensed Senior Operator or Certified Fuel Handler ML17067A3422017-07-0707 July 2017 FRN, Request for Exemption from Specific Provisions in 10 CFR 73.55 Related to Suspension of Security Measures for Licensed Senior Operator or Certified Fuel Handler NRC-2017-0099, FRN, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate and Notice of Meeting to Discuss and Accept Comments2017-04-0707 April 2017 FRN, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate and Notice of Meeting to Discuss and Accept Comments ML17094A7952017-04-0707 April 2017 Letter, Notification of the Availability of Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate and Notice of Meeting to Discuss and Accept Comments ML17094A7972017-04-0707 April 2017 FRN, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate and Notice of Meeting to Discuss and Accept Comments ML16232A0892016-08-24024 August 2016 Letter, Withdrawal of an Amendment Request, Changes to Fire Protection License Condition Revised Commitment to Modify Plant Systems as Part of NFPA 805 Implementation ML16232A0882016-08-24024 August 2016 FRN, Withdrawal of an Amendment Request, Changes to Fire Protection License Condition Revised Commitment to Modify Plant Systems as Part of NFPA 805 Implementation NRC-2016-0096, FRN, Withdrawal of an Amendment Request, Changes to Fire Protection License Condition Revised Commitment to Modify Plant Systems as Part of NFPA 805 Implementation2016-08-24024 August 2016 FRN, Withdrawal of an Amendment Request, Changes to Fire Protection License Condition Revised Commitment to Modify Plant Systems as Part of NFPA 805 Implementation NRC-2016-0040, FRN, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements2016-08-0202 August 2016 FRN, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements ML16209A3692016-08-0202 August 2016 Letter, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements ML16209A3702016-08-0202 August 2016 FRN, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements ML16173A1222016-06-24024 June 2016 FRN, Withdrawal of Requested Licensing Action, Request to Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011 ML16061A3012016-03-0202 March 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 ML15356A5992015-12-29029 December 2015 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 5, 2016 NRC-2015-0269, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: December 8, 20152015-11-27027 November 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: December 8, 2015 ML15328A5502015-11-27027 November 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: December 8, 2015 ML15231A8382015-08-21021 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 2015 NRC-2015-0204, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 20152015-08-21021 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 2015 NRC-2012-0014, G20110506/LTR-11-0402/EDATS: SECY-2011-0402, G20110492/LTR-11-0382/EDATS: OEDO-2011-0387 - FRN, 2.206 Final Director'S Decision, Petitioner Thomas Saporito Related to Cooper Nuclear Station and Fort Calhoun Station (TAC Nos. ME6681 and2015-06-0303 June 2015 G20110506/LTR-11-0402/EDATS: SECY-2011-0402, G20110492/LTR-11-0382/EDATS: OEDO-2011-0387 - FRN, 2.206 Final Director'S Decision, Petitioner Thomas Saporito Related to Cooper Nuclear Station and Fort Calhoun Station (TAC Nos. ME6681 and ME66 ML15128A1432015-06-0303 June 2015 G20110506/LTR-11-0402/EDATS: SECY-2011-0402, G20110492/LTR-11-0382/EDATS: OEDO-2011-0387 - FRN, 2.206 Final Director'S Decision, Petitioner Thomas Saporito Related to Cooper Nuclear Station and Fort Calhoun Station ML15062A3732015-04-15015 April 2015 G20110506/LTR-11-0402 and G20110492/LTR-11-0382 - 2.206 Proposed Director'S Decision, Petitioner Thomas Saporito Related to Cooper Nuclear Station and Fort Calhoun Station ML15092A1842015-04-0606 April 2015 FRN, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra ML15092A1822015-04-0606 April 2015 Letter, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra NRC-2014-0159, FRN, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra2015-04-0606 April 2015 FRN, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra ML15022A6532015-01-26026 January 2015 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 3, 2015 ML14311A6612014-11-10010 November 2014 FRN, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months NRC-2014-0249, FRN, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months2014-11-10010 November 2014 FRN, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14311A6602014-11-10010 November 2014 Letter, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months NRC-2014-0193, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 20142014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 ML14233A2082014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 ML14204A5782014-07-25025 July 2014 Notice of Withdrawal of License Amendment Application, Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source ML14204A5922014-07-25025 July 2014 FRN, Notice of Withdrawal of License Amendment Application, Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source ML14177A6452014-06-27027 June 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations NRC-2014-0028, Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 20142014-02-10010 February 2014 Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014 ML14037A4142014-02-10010 February 2014 Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014 ML13274A0262013-10-28028 October 2013 FRN, Exemption Related to Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) Requirements 2023-12-27
[Table view] Category:Finding of No Significant Impact
MONTHYEARML1127700102011-10-0505 October 2011 Exemption to Extend Compliance Date to 11/5/2013 for One Specific Requirement of 10 CFR 73.55(a)(1) ML1003602182010-03-0202 March 2010 Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request ML1003601772010-03-0202 March 2010 Cover Letter, Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request ML0833300362008-12-23023 December 2008 Environmental Assessment and Finding of No Significant Impact, Re Exemption from Requirements of 10 CFR Part 50, Appendix R, Section III.G.1.b for Fire Area 31 ML0620000972006-08-0909 August 2006 Environmental Assessment for Use of M5 ML0320202182003-07-18018 July 2003 Ltr Environmental Assessment Relating to Exemption from the Requirements of Appendix G to 10 CFR Part 50 2011-10-05
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7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from the requirements of Section III.G.1.b of Appendix R to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, for Facility Operating License No. DPR-40, issued to Omaha Public Power District (OPPD, the licensee), for operation of the Fort Calhoun Station, Unit No. 1, located in Washington County, Nebraska. 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 provide an exemption from the provisions of 10 CFR Part 50, Appendix R, Section III.G.1.b, for the 72-hour requirement to provide repair procedures and materials for cold shutdown capability for redundant cold shutdown components.
The proposed action is in accordance with the licensee=s application dated February 4, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080360106), as supplemented by letter dated October 13, 2008 (ADAMS No. ML082980018).
The Need for the Proposed Action:
The proposed action is needed to provide notification and clarification of the exemption granted by the NRC by letter dated July 3, 1985 (ADAMS Legacy Library Accession No.
850724390), in which the NRC granted an exemption from the technical requirements of Section III.G.2 of Appendix R to 10 CFR Part 50, for Fire Area 31 (intake structure building) and for the pull box area of the auxiliary building. The NRC safety evaluation report (SER) dated July 3, 1985, incorrectly referenced Section III.G.2 and subsequently provided exemption from 10 CFR Part 50, Section III.G. Specifically, the original SER and exemption should have referenced 10 CFR 50, Appendix R, Section III.G.1.b. In addition, cables in the duct bank and manhole vaults numbers 5 and 31 that are routed between the pull boxes and intake structure were not discussed in the OPPD exemption request dated August 30, 1983 (ADAMS Legacy Library Accession No. 830909011). Therefore, OPPD needs exemption from 10 CFR Part 50, Appendix R, III.G.1.b, for the cables in the duct bank and manhole vaults numbers 5 and 31 that are routed between the pull boxes and the intake structure building.
Environmental Impacts of the Proposed Action:
The NRC has completed its safety evaluation of the proposed action and concludes that the consequences of postulated accidents are not increased, because there is no credible fire hazard in the area of the cable duct bank or manhole, which would disable all the raw water pumps and prevent the cold shutdown capability. Furthermore, if all raw water pumps are lost, due to any condition, the abnormal operating procedure directs the operator to trip the reactor and enter emergency procedures based on observed plant conditions. Therefore, there is no undue risk, since neither the probability nor the consequences have been increased, to public health and safety.
On the basis of its review and evaluation of the information provided in the licensees exemption request and response to NRC staff request for additional information questions, the NRC staff concludes that OPPDs request for exemption from the technical requirements of Section III.G.1.b of Appendix R to 10 CFR Part 50 has provided a thorough description of the proposed change and adequate safety assessment which address the issue.
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 released offsite. 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 NRC staff considered denial of the proposed action (i.e., the Ano-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 Fort Calhoun Station dated August 1972.
Agencies and Persons Consulted:
In accordance with its stated policy, on November 26, 2008, the NRC staff consulted with the Nebraska State official, Julia Schmitt, of the Department of Health and Human Services Regulation and Licensure, 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 licensee=s letter dated February 4, 2008, as supplemented by letter dated October 13, 2008. Documents may be examined, and/or copied for a fee, at the NRC=s 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 Internet at 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 by telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to pdr.resource@nrc.gov.
Dated at Rockville, Maryland, this 23rd day of December 2008.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation