Letter Sequence Approval |
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TAC:MB6468, Missed Surveillance Requirements, Incorporate CEOG Topical Report to Eliminate Pressure Sensor Response Time Testing (Approved, Closed) |
Results
Other: ML021280278, ML022940186, ML030780605, ML031210545, ML031290602, ML031400506, ML031410096, ML031410107, ML031410212, ML031960625, ML032300003, ML032300305, ML032310200, ML032310213, ML032530228, ML032960189
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MONTHYEARML0205206542002-02-25025 February 2002 Order Attachment 1 - Addressee List - Order for Interim Safeguards and Security Compensatory Measures Project stage: Request ML0205002282002-02-25025 February 2002 Issuance of Order for Interim Safeguards and Compensatory Security Measures Project stage: Approval ML0212802782002-05-22022 May 2002 Reply to Response to Order for Interim Safeguards and Security Compensatory Measures Project stage: Other ML0229401862002-10-25025 October 2002 Biweekly Notice Memo, Notice of Consideration, Testing Prestressed Concrete Containment Tendons Project stage: Other ML0302201532003-01-16016 January 2003 Technical Specification Pages for Amendment 215 Missed Surveillances and Adoption of a Technical Specification Bases Control Program Project stage: Acceptance Review ML0229504532003-01-16016 January 2003 Issuance of License Amendment No. 215, Missed Surveillances & Adoption of Technical Specification Bases Control Program Project stage: Approval ML0305902712003-02-26026 February 2003 Technical Specifications, Relocation of TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report Project stage: Acceptance Review ML0306307272003-02-26026 February 2003 Issuance of Amendment No. 216, Relocating TS 3.5(5), Requirements for Testing Prestressed Concrete Containment Tendons to the Updated Safety Analysis Report Project stage: Approval ML0305803512003-02-27027 February 2003 Correction to Amendment No. 215 to Fort Calhoun, Station No. 1. Page 5-17 of Technical Specifications Omitted Reference to SR 3.0.5. Corrected TS Page Encl Project stage: Acceptance Review ML0307806052003-03-18018 March 2003 Pressure-Temperature Limit Report Submittal Project stage: Other ML0308402732003-03-24024 March 2003 RAI, Related to Integrated Leak Rate Test Surveillance Interval Project stage: RAI LIC-03-0052, Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request2003-04-10010 April 2003 Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request Project stage: Request LIC-03-0055, Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-04-11011 April 2003 Response to Request for Additional Information Integrated Leak Rate Testing Surveillance Interval Amendment Request Project stage: Response to RAI ML0312004872003-04-29029 April 2003 Issuance of Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days Project stage: Approval ML0312105452003-04-29029 April 2003 Tech Spec Pages for Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days Project stage: Other ML0312906022003-05-0808 May 2003 Tech Spec Pages for Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii Project stage: Other ML0312900812003-05-0808 May 2003 Issuance of Amendment No. 218, Administrative and Editorial Changes to FCS TS 1.3 Basis (1); 2.7 (1)a; 2.7 (1)b; 2.7 (1)d; 2.7 (1)i; 2.7 Basis; 3.0.2; Table 3-5, Item 11; and 3.5 (3)ii Project stage: Approval ML0314102122003-05-20020 May 2003 Thesis (Miscellaneous Report - 134 Pages), Fort Calhoun, S107100 Project stage: Other ML0314005062003-05-20020 May 2003 Ltr RELAP5/MOD3.3 Prediction and Model Simulation Project stage: Other ML0314100962003-05-20020 May 2003 Description/Model Simulation (Technical Paper - 5 Pages), Fort Calhoun, S107101 Project stage: Other ML0314101072003-05-20020 May 2003 Listing (Report, Technical - 3 Pages), Fort Calhoun, S107102 Project stage: Other ML0314103762003-05-21021 May 2003 Request for Additional Information Pressure-Temperature Limit Report Submittal (Tac. MB6468) Project stage: RAI LIC-03-0079, Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request2003-05-21021 May 2003 Supplemental Response to Request for Additional Information, Integrated Leak Rate Testing Surveillance Interval Amendment Request Project stage: Supplement ML0316800102003-06-17017 June 2003 Request for Additional Information, Use of the Gothic (Version 7.0) Computer Program Project stage: RAI ML0319606252003-07-11011 July 2003 Correction to Amd. 218 for the Fort Calhoun Station, Unit No. 1 (Tac. MB7498) Project stage: Other ML0320202182003-07-18018 July 2003 Ltr Environmental Assessment Relating to Exemption from the Requirements of Appendix G to 10 CFR Part 50 Project stage: Approval ML0320902422003-07-25025 July 2003 Unit 1, License Amendment 219 Modifying Technical Specification 2.1.6 Project stage: Approval ML0321004542003-07-25025 July 2003 Unit 1, Tech Spec Pages for License Amendment 219 Modifying Technical Specification 2.1.6 Project stage: Approval ML0323102002003-08-15015 August 2003 Tech Spec Pages for Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis Project stage: Other ML0323102132003-08-15015 August 2003 Tech Spec Page to License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing Project stage: Other ML0323003052003-08-15015 August 2003 License Amendment No. 221, Use of a Pressure Temperature Limits Report (Ptlr), Change the Minimum Boltup Temperature, Revise the Low Temperature Overpressure Protection (LTOP) Methodology and Analysis Project stage: Other ML0323000032003-08-15015 August 2003 License Amendment No. 220, Grants One-Time Five-Year Extension to Current Ten-Year Test Interval for Containment Integrated Leak Rate Testing Project stage: Other ML0325302282003-09-0404 September 2003 Ft.Calhoun, Closeout Letter - Response to Order for Compensatory Measures Related to Access Authorization Project stage: Other ML0329601892003-10-23023 October 2003 Reply to Response to Order for Fitness-For-Duty Enhancements for Nuclear Security Force Personnel Project stage: Other ML0331002902003-11-0505 November 2003 Unit #1, Issuance of Amendment 222, Authorizing Revisions to the Updated Safety Analysis Report to Incorporate the NRC Approval of the Gothic 7.0 Computer Program for Performing Containment Analysis, (Tac. MB7496) Project stage: Approval 2003-04-10
[Table View] |
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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 District'S 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: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
[Table view] Category:Letter
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22159A2152022-06-28028 June 2022 Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report 2024-01-31
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Text
July 18, 2003 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station, FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT 1 - ENVIRONMENTAL ASSESSMENT RELATING TO EXEMPTION FROM THE REQUIREMENTS OF APPENDIX G TO 10 CFR PART 50 (TAC NO. MB6468)
Dear Mr. Ridenoure:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for exemption dated October 8, 2002. The proposed exemption would exempt Omaha Public Power District from certain requirements of Appendix G to 10 CFR Part 50 to allow the application of the methodology in CE NPSD-683-A, Revision 6, "Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP Requirements from the Technical Specifications," for the calculation of flaw stress intensity factors due to thermal stress loadings (KIt).
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Environmental Assessment cc w/encl: See next page
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G for Facility Operating License No. DPR-40, issued to Omaha Public Power District (the licensee),
for operation of the Fort Calhoun Station, Unit No. 1 (FCS), 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 exempt the licensee from certain requirements of Appendix G to 10 CFR Part 50 to allow the application of the methodology in Combustion Engineering (CE) Topical Report NPSD-683-A, Revision 6, "Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP Requirements from the Technical Specifications," for the calculation of flaw stress intensity factors due to thermal stress loadings (Klt).
The proposed action is in accordance with the licensees application dated October 8, 2002.
The Need for the Proposed Action:
In the associated exemption, the staff has determined that, pursuant to 10 CFR 50.12(a)(2)(ii), the underlying purpose of the regulation will continue to be served by the implementation of the alternative methodology. The proposed action would revise the currently-approved methodology for pressure temperature (P-T) limit calculations to incorporate the methodology approved for use in CE NPSD-683-A, Revision 6. CE NPSD-683-A, Revision 6, allows the use of an alternate methodology to calculate the flaw stress intensity factors due to thermal stress loadings (KIt). The exemption is needed because the methodology in CE NPSD-683-A, Revision 6, could not be shown to be conservative with respect to the methodology for the determination of KIt provided in Editions and Addenda of ASME Code,Section XI, Appendix G, through the 1995 Edition and 1996 Addenda (the latest Edition and Addenda of the ASME Code which had been incorporated into 10 CFR 50.55a at the time of the staffs review of CE NPSD-683-A, Revision 6). Therefore, in conjunction with the licensee's October 8, 2002, license amendment request, the licensee also submitted an exemption request, consistent with the requirements of 10 CFR 50.60, to apply the KIt calculational methodology of CE NPSD-683-A, Revision 6 as part of the FCS pressure temperature limit report (PTLR) methodology.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes that the exemption described above would provide an adequate margin of safety against brittle failure of the reactor pressure vessel at FCS. The details of the staff's evaluation will be provided in the exemption to Appendix G, which will allow the use of the methodology in Topical Report NPSD-683-A, Revision 6, to calculate the flaw stress intensity factors due to thermal stress loadings (Klt), that will be issued in a future letter to the licensee.
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 off site, and 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 nonradiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant nonradiological 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 resource than those previously considered in the Final Environmental Statement for the FCS dated August 1972.
Agencies and Persons Consulted:
On July 18, 2003, the staff consulted with the Nebraska State official, Howard Shuman of the Nebraska Consumer Health Services Agency, 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 letter dated October 8, 2002. 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 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 by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 18th day of July 2003.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
ML032020218
- W/Comment NRR-106 OFFICE PDIV-2/PM PDIV-2/LA RLEP:SC
- OGC - NLO PDIV-2/SC NAME JNDonohew EPeyton RLEmch for SCole SDembek for AWang JTappert DATE 7/1/2003 6/30/03 7/2/03 7/14/03 7/18/03 DOCUMENT NAME: G:\PDIV-2\FortCalhoun\mb6468ea.wpd Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn Mr. Daniel K. McGhee ATTN: James R. Curtiss, Esq. Bureau of Radiological Health 1400 L Street, N.W. Iowa Department of Public Health Washington, DC 20005-3502 401 SW 7th Street, Suite D Des Moines, IA 50309 Chairman Washington County Board of Supervisors Mr. Richard P. Clemens P.O. Box 466 Division Manager - Nuclear Assessments Blair, NE 68008 Omaha Public Power District Fort Calhoun Station Mr. John Kramer, Resident Inspector P.O. Box 550 U.S. Nuclear Regulatory Commission Fort Calhoun, NE 68023-0550 P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John B. Herman Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550