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Category:Memoranda
MONTHYEARML22333B0922022-12-21021 December 2022
FY22 Nmss/Duwp Operating Experience Report
ML21271A5992021-08-0303 August 2021
License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2
ML21055A4022021-05-14014 May 2021
Memorandum: Final Environmental Assessment and Finding of No Significant Impact of Initial and Updated Decommissioning Funding Plans for the Cooper, Fort Calhoun and Virgil C. Summer Independent Spent Fuel Storage Installations
ML21271A1492021-04-13013 April 2021
License Amendment Request (LAR) 21-01, Chapter 1 9 Haley & Aldrich, Inc. Memorandum to Energysolutions, File No. 0127960-006, Fort Calhoun Nuclear Power Statio~1
ML20056E4872020-02-26026 February 2020
Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM)
ML18173A0082018-06-20020 June 2018
Cancelling Numerous Inspection Report Numbers
ML18108A1212018-04-11011 April 2018
American Nuclear Insurers - Notification of Change in the Number of Power Reactors in the Secondary Financial Protection (SFP) Program
ML17275A2642017-11-21021 November 2017
Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285
ML16057A1232016-02-26026 February 2016
Cy 2015 Baseline Completion
ML16007A4942016-01-11011 January 2016
Review of the Updated Final Safety Analysis Report for the Period June 14, 2014 Through December 4, 2015
ML14163A0022014-06-16016 June 2014
Summary of Audit Conducted March 5-9, 2012, Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML14129A4452014-05-12012 May 2014
5/13/2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1
ML14114A7012014-04-24024 April 2014
Task Interface Agreement - Concurrence on Fort Calhoun Tornado Missile Protection Licensing Basis (TIA 2013-07)
ML14085A1842014-03-28028 March 2014
Final Fort Calhoun Gothic TIA Response
ML14016A2602014-01-28028 January 2014
Fc Final Containment Structural TIA
ML13351A4762013-12-16016 December 2013
Recommendation for NRC to Close Confirmatory Action Letter EA-13-020 Supporting the Restart of Fort Calhoun Station and Recommendation to Issue Post-Restart Confirmatory Action Letter
ML13346A0822013-12-12012 December 2013
Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1
ML13312A8522013-11-0808 November 2013
Meeting Notice with Public to Discuss Fort Calhoun Station
ML13253A3542013-09-27027 September 2013
Letter to R. Morris Information Exchange Pertaining to Health Issues Related to Crow Butte Resources Uranium Mine and Ft. Calhoun Nuclear Generating Station
ML13102A1892013-04-15015 April 2013
4/22/12 Notice of Closed Meeting with Omaha Public Power District to Discuss Flooding Issues Associated with Fort Calhoun, Unit 1
ML13101A2232013-04-11011 April 2013
Meeting Notice with Omaha Public Power District - Potential License Amendment Requests for Fort Calhoun, Unit 1 Related to Flood Protection for Raw Water System, Tornado Missile Protection, Piping/Code Use, and Alternate Seismic Criteria
ML13066A8772013-03-0707 March 2013
Issuance of Revised U.S. Nuclear Regulatory Commission Manual Chapter 0350 Panel Fort Calhoun Station Restart Checklist Basis Document
ML13046A3212013-02-19019 February 2013
Notice of Closed Meeting with Fort Calhoun to Discuss Safeguards Information, Proprietary, or Other Sensitive Information
ML12345A2702012-11-30030 November 2012
Revised 12/12/2012 Notice of Forthcoming Meeting with Omaha Public Power District to Discuss Containment Internal Structures Issues to Support Restart of Fort Calhoun Station, Unit 1
ML12335A1652012-11-30030 November 2012
Forthcoming Meeting with Omaha Public Power District to Discuss Containment Internal Structures Issues to Support Restart of Fort Calhoun Station, Unit 1
ML12318A3192012-11-13013 November 2012
Issuance of U.S. Nuclear Regulatory Commission Manual Chapter 0350 Panel Fort Calhoun Station Restart Checklist Basis Document
ML12251A3172012-09-0707 September 2012
Manual Chapter 0350 Oversight Panel Charter - Revision
ML12066A0302012-03-29029 March 2012
Closure Memorandum: Issue for Resolution 2011-001 Fort Calhoun - Failure to Maintain External Flooding Procedures.
ML12229A1842012-03-0606 March 2012
Backfit Panel Regarding Fort Calhoun Flooding
ML1134707162011-12-13013 December 2011
Memo to M.S.Virgilio Notification of Change to Regulatory Oversight of Fort Calhoun Station
ML11293A1982011-10-19019 October 2011
Charter for Backfit Panel on Postulated Failure of Upstream Dams Affecting Fort Calhoun Station
ML1118811312011-07-0707 July 2011
Docketing of Nonproprietary Information Provided by Omaha Public Power District (OPPD) Personnel Following the June 2, 2011, Regulatory Conference
ML13106A1702011-07-0101 July 2011
Proposed Adequate Protection Backfit Exception
ML11174A2322011-06-21021 June 2011
for the Record-06-21-2011: NRC Ensures Public Safety Through Rigorous Oversight of Nuclear Power Plant Safety Standards
ML1113807322011-05-18018 May 2011
Regulatory Conference with Omaha Public Power
ML1113306432011-05-16016 May 2011
Notice of Forthcoming Prelicensing Teleconference on 5/26/11 with Omaha Public Power District Related to Fort Calhoun Station, Unit 1's License Amendment Submittal Related to Transition to Risk-Informed NFPA-805
ML1109103272011-04-0505 April 2011
Verbal Authorization, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot-Leg Nozzle-to-Safe-End Dissimilar Metal Welds, 4th 10-Year Inservice Inspection Interval
ML1108106952011-03-23023 March 2011
Notice of Forthcoming Pre-Licensing Meeting with Omaha Public Power District to Discuss Its Plans to Submit an Extended Power Uprate for Fort Calhoun Station and Issues Related to Equipment Environmental Qualification
ML1104808672011-02-18018 February 2011
03/2/2011 Notice of Forthcoming Closed Pre-Licensing Teleconference with Omaha Public Power District to Discuss Its Plans to Submit an Extended Power Uprate for Fort Calhoun Station and Issues Related to Control Rod Withdrawal at Power
ML1035605482010-12-23023 December 2010
Notice of Forthcoming Pre-Licensing Meeting with Omaha Public Power District to Discuss Fort Calhoun Station'S Extended Power Uprate, Spent Fuel Pool Criticality, and Proposed License Amendment Request Modeled After TSTF-493
ML1020701262010-08-30030 August 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of Fort Calhoun Station Unit 1, June 30, 2010 - Finding of No Potential Issues in Bank Statements
ML1016205062010-06-14014 June 2010
Notice of Forthcoming Teleconference Meeting with Omaha Public Power District to Discuss NRC Staff Request for Additional Information Dated 2/12/2010 on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1
ML1006010322010-03-0101 March 2010
Cy 2009 Baseline Inspection Completion
ML1004302742010-02-12012 February 2010
Notice of Forthcoming Teleconference with Omaha Public Power District to Discuss NRC Staff Request for Additional Information on Generic Letter 2004-02 for Fort Calhoun Station, Unit 1
ML0909607752009-04-0606 April 2009
Notice of End-of-Cycle Meeting with Omaha Public Power District - Fort Calhoun Station to Present and Discuss the Performance Results for the Fort Calhoun Station for the Period of January 1 Though December 31, 2008
ML0901603362009-01-16016 January 2009
Notice of Forthcoming Meeting with Omaha Public Power District, to Discuss the Fort Calhoun Station'S Transition to National Fire Protection Association (NFPA) 805
ML0901504382009-01-16016 January 2009
Notice of Forthcoming Meeting with Omaha Public Power District, to Discuss Oppd'S Plans to Submit an Extended Power Uprate Request for the Fort Calhoun Station, Unit 1
ML0814100052008-06-0303 June 2008
Summary of Conference Call with Omaha Public Power District (OPPD) Regarding OPPD Emergency Relief Request Submitted May 15, 2008 for Fort Calhoun Station (Tac No. MD8722)
ML0809404512008-04-18018 April 2008
Summary of 12/6/2006 Meeting with Omaha Public Power District, Regarding Water Management Strategies for Resolution of GSI-191 (Tac No MD5780)
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
2022-12-21
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July 19, 2006 NOTE TO: William H. Ruland, Deputy Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards THROUGH: Christopher M. Regan, Acting Chief /RA/
Licensing Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards FROM: Joseph M. Sebrosky, Senior Project Manager /RA/ by Stewart Brown for/
Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
SUBJECT:
CONCERNS REGARDING EXEMPTION FROM 10 CFR 72.48, 10 CFR 72.212 AND 72.214 FOR DRY SPENT FUEL STORAGE ACTIVITIES - FORT CALHOUN STATION The purpose of this note is to respond to the concerns identified in an anonymous letter dated June 20, 2006, regarding Omaha Public Power Districts (OPPDs) exemption request dated June 9, 2006. The anonymous letter is publicly available in the records component of NRCs Agencywide Documents Access and Management System (ADAMS). The ADAMS accession number for the anonymous letter is ML061800438. OPPD requested in its June 9, 2006, letter an exemption from NRC regulations to enable the use of a light-weight transfer cask (TC) and allow an earlier start time for vacuum drying. The June 20, 2006, anonymous letter requests that the NRC deny OPPDs exemption request, because in general: 1) there is no valid basis for OPPD to file the exemption request or for the NRC to grant the exemption, 2) it would lead to higher doses for the workers, and 3) the possibility that use of the TC with temporary shielding introduces a new type of accident.
The need for the exemption was identified during an NRC inspection of the licensees preparation for the dry cask storage campaign. Interactions with the NRC led OPPD management to the determination that submittal of an exemption request was the optimum path forward for use of the light weight TC at the Fort Calhoun Station. Regarding the basis for NRC granting the exemption, NRCs regulations permit licensees to seek exemptions in special circumstances which NRC may grant if it determines that the exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. NRCs basis for granting OPPD an exemption is documented in its safety evaluation report (SER) dated July 19, 2006 (ADAMS accession no. ML062000153).
Regarding doses to the workers, in the SER the staff evaluates the use of the light-weight TC and measures taken to compensate for the removal of the lead shielding in the TC (e.g., use of supplemental shielding, remote operation of the spent fuel pool building crane, and use of fuel with a minimum cooling time of 16.2 years to reduce the dose rate). In the SER the staff evaluated the exemption against the shielding and dose requirements in 10 CFR Part 72 and 10 CFR Part 20 and concludes that these requirements are met. Regarding the possibility of
introducing a new type of accident because of the introduction of the temporary shielding, the staff also evaluated this issue in the SER. The staffs determination is that the temporary shielding does not introduce the possibility of an accident that is not bounded by previously analyzed accidents.
The staff placed four conditions on the exemption which are:
- 1) OPPD will be limited to loading a total of four 32PT DSCs.
- 2) OPPD shall limit the decay heat level per DSC to 11 kW to ensure cask loadings are bounded by the analyses supporting the TN CoC No. 1004, Amendment No. 8.
- 3) OPPD shall limit the cooling time of the fuel that it intends to load to a minimum of 16.2 years to ensure that the radiological source term for fuel that is loaded in the light weight TC is kept as low as reasonably achievable.
- 4) The TS 1.2.11 dose rate limit/specification are substituted with the limit of 170 mrem/hr in the axial direction and 110 mrem/hr in the radial direction. The axial dose rate limit of 170 mrem/hr is to be taken under the conditions in Table 1 below. The radial dose rate limit of 110 mrem/hr is to be taken under the conditions in Table 2 below.
Table 1 Axial Dose Rate Measurement Configuration 32PT DSC inside the OS197L inside the decon sleeve/bell water drained from the DSC TC/DSC annulus full (within approximately 1 foot of the top)
TC neutron shield full top shield plug in place and included in axial shielding inner top cover plate in place and included in axial shielding automated welding system (AWS) with integral shield in place and included in axial shielding measurement taken at vertical centerline of DSC, 3 feet from AWS shield
Table 2 Radial Dose Rate Measurement Configuration 32PT DSC inside OS197L inside decon sleeve/bell water drained from the DSC TC/DSC annulus full (within approximately 1 foot of the top)
TC neutron shield full 6 inch nominal thickness carbon steel decon sleeve/bell in place and included in radial shielding measurement taken at outside surface (contact) of decon sleeve/bell Given the staffs safety determination and the limited nature of the exemption, the staff believes that the issuance of the exemption is warranted. The NRC considers public involvement in our activities to be a cornerstone of strong, effective, and fair regulation of the nuclear industry.
The staff appreciates the concern regarding OPPDs exemption request being identified to us.
If there are questions regarding this issue please contact Joe Sebrosky at (301) 415-8500.
Docket Nos. 72-54, 50-285 cc: Service List
Table 2 Radial Dose Rate Measurement Configuration 32PT DSC inside OS197L inside decon sleeve/bell water drained from the DSC TC/DSC annulus full (within approximately 1 foot of the top)
TC neutron shield full 6 inch nominal thickness carbon steel decon sleeve/bell in place and included in radial shielding measurement taken at outside surface (contact) of decon sleeve/bell Given the staffs safety determination and the limited nature of the exemption, the staff believes that the issuance of the exemption is warranted. The NRC considers public involvement in our activities to be a cornerstone of strong, effective, and fair regulation of the nuclear industry.
The staff appreciates the concern regarding OPPDs exemption request being identified to us.
If there are questions regarding this issue please contact Joe Sebrosky at (301) 415-8500.
Docket Nos. 72-54, 50-285 cc: Service List Distribution:
AWang, NRR BSpitzberg, RIV E:\Filenet\ML062010042.wpd OFC SFP E SFPO E OGC E SFPO E SFPO E O
NAME JSebrosky EZiegler STreby(NLO) CRegan WRuland DATE 7/12/06 7/3/06 7/13/06 7/19/06 7/19/06 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY
Ft. Calhoun Station, Unit 1 Service List cc:
Winston & Strawn Mr. Daniel K. McGhee ATTN: James R. Curtiss, Esq. Bureau of Radiological Health 1700 K Street, N.W. Iowa Department of Public Health Washington, DC 20006-3817 Lucas State Office Building, 5th Floor 321 East 12th Street Chairman Des Moines, IA 50319 Washington County Board of Supervisors P.O. Box 466 Mr. R. T. Ridenoure Blair, NE 68008 Vice President - Chief Nuclear Officer Omaha Public Power District Mr. John Hanna, Resident Inspector Fort Calhoun Station FC-2-4 Adm.
U.S. Nuclear Regulatory Commission Post Office Box 550 P.O. Box 310 Fort Calhoun, Nebraska 68023-0550 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial 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. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
