Letter Sequence Acceptance Review |
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MONTHYEARML21271A1432021-08-0303 August 2021
License Amendment Request (LAR) 21-01, LIC-21-0005 LTP Cover Letter Final Fisher Signature
Project stage: Request
ML21350A0262021-12-16016 December 2021
Acceptance Review of License Amend Req. to Add License Condition to Include License Termination Plan Requirements, Req. for Supplemental Info
Project stage: Acceptance Review
LIC-22-0001, Well Water Results with River Stage2022-01-13013 January 2022
Well Water Results with River Stage
Project stage: Request
ML22038A6752022-02-10010 February 2022
Acceptance of Omaha Public Power District'S License Amendment Request to Add a License Condition to Include License Termination Plan Requirements
Project stage: Acceptance Review
ML22119A2472022-05-0303 May 2022
Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review
Project stage: RAI
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
Project stage: Request
ML22159A2152022-06-28028 June 2022
Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan
Project stage: Meeting
ML22357A0662022-12-30030 December 2022
Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan
Project stage: RAI
ML22357A0672022-12-30030 December 2022
Enclosure RAI Re Approval of License Termination Plan
Project stage: RAI
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
Project stage: Request
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
Project stage: RAI
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
Project stage: Request
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
Project stage: Request
ML24019A1682024-01-31031 January 2024
Safety Evaluation Report for Approval of License Termination Plan
Project stage: Approval
ML24019A1672024-01-31031 January 2024
Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements
Project stage: Approval
2022-06-15
[Table View] |
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Category:Acceptance Review Letter
MONTHYEARML22038A6752022-02-10010 February 2022
Acceptance of Omaha Public Power District'S License Amendment Request to Add a License Condition to Include License Termination Plan Requirements
ML21350A0262021-12-16016 December 2021
Acceptance Review of License Amend Req. to Add License Condition to Include License Termination Plan Requirements, Req. for Supplemental Info
ML17041A2382017-02-15015 February 2017
Acceptance Review Letter, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E to Allow Plant to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition
ML16007A3852016-01-15015 January 2016
Acceptance of Requested Licensing Action Following Supplement, Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML15341A2242015-12-15015 December 2015
Supplemental Information Needed for Acceptance of Requested Licensing Action Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML14178B3942014-06-27027 June 2014
NRC Acceptance Review of Fort Calhoun License Amendment Request 14-03
ML13267A1772013-09-24024 September 2013
Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood
ML13255A0072013-09-11011 September 2013
Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13249A3182013-09-0606 September 2013
Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis
ML12325A5782012-11-19019 November 2012
Acceptance Review Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup from Current Extended Outage
ML1215800432012-06-0505 June 2012
Acceptance Review Email, Amendment Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML1210706522012-04-16016 April 2012
Acceptance Review Email, Relocate Technical Specification Limiting Condition for Operation 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report
ML1208303282012-03-23023 March 2012
Email License Amendment Request to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
ML1203802312012-02-0707 February 2012
Acceptance Review Email, License Amendment Request to Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6)
ML1136300832011-12-29029 December 2011
Acceptance Review Email, License Amendment Request to Adopt National Fire Protection Standard NFPA -805 Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generation Plants,
ML1124501302011-09-0202 September 2011
Unit No.1 - Acceptance Review Email, Exemption Request from the Requirements of Appendix E, Sections IV.F.2.b and C of Section 50, Title 10 of the Code of Federal Regulations
ML1109605292011-04-0606 April 2011
Acceptance Review Email, License Amendment Request, Establish Ultimate Heat Sink LCOs in Technical Specification (TS) 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests.
ML1034001892010-12-14014 December 2010
Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
ML1026500132010-09-21021 September 2010
Acceptance Review E-mail, Relief Request RR-12, from Requirements of ASME Code Case N-722 Visual Examination of Reactor Vessel Hot-Leg Nozzle to Safe End Dissimilar Metal Welds for 4th 10-Year Inservice Inspection Interval (ME4541)
ML1023006762010-08-18018 August 2010
Acceptance Review Email, License Amendment Request to Revise License Condition and Approve Cyber Security Plan
ML1022406482010-08-12012 August 2010
Acceptance Review E-mail, LAR Regarding Revision to (1) TS LCO 2.15, Table 2-5, Item 1, (2) TS 3.1, Table 3-3, Items 1, 2, and 4 Control Element Assembly Position Indication and (3) TS LCO 2.10.2(7)c
ML1004707252010-02-16016 February 2010
Acceptance Review Email, Request for Exemption from 10 CFR Part 73 Physical Security Requirements
ML0932402402009-11-20020 November 2009
Acceptance Review Email, Request for Use of Alternate to Depth Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds
ML0918308972009-07-0202 July 2009
Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 2.0.1 and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source, Deletion of Diesel Generator SR 3.7(1)e
ML0905802252009-02-27027 February 2009
Acceptance Review Email, License Amendment Request to Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0905407952009-02-23023 February 2009
Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam .Generator Blowdown Isolation on a Reactor Trip
ML0833301062008-11-26026 November 2008
Acceptance Review Email, License Amendment Request to Revise TS 3.6(3), Containment Recirculating Air Cooling and Filtering System and License Conditions Replacement of Cacf System
2022-02-10
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Text
December 16, 2021 Mr. Troy Via, Chief Operation Officer and Vice President Utility Operations Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-4 9610 Power Lane Blair, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ACCEPTANCE REVIEW OF LICENSE AMENDMENT REQUEST TO ADD LICENSE CONDITION TO INCLUDE LICENSE TERMINATION PLAN REQUIREMENTS - REQUEST FOR SUPPLEMENTAL INFORMATION (EPID L-2021-LIT-0000)
Dear Mr. Via:
By letter dated August 3, 2021, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21271A178) Omaha Public Power District submitted a license amendment request for Fort Calhoun Station, Unit No. 1 (FCS). The proposed amendment would add License Condition 3.D to include License Termination Plan (LTP) requirements.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements.
The NRC staff has reviewed your application and concluded that it did not provide technical information in sufficient detail to enable the staff to complete its detailed review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements for the protection of public health and safety and the environment. This informational need was conveyed to your staff during the periodic licensing call on December 9, 2021. In that call, the NRC staff identified that the following information was needed to begin its technical review:
- 1. Document Request - LTP Chapter 6, Reference 1 Chapter 6, Reference 1 is cited as the source of summary information in the LTP for numerical modeling intended to provide support for concentration results from RESRAD-ONSITE for the Basement Fill Model. However, Reference 1 of Chapter 6 -
Haley & Aldrich, "Hydrogeological Conceptual Site Model, Revision 4, Fort Calhoun Station, Blair, NE," 2021, was not a document included in the LTP submittal. Revision 2 of Reference 1 is specifically listed in the text of early parts of Chapter 6 and was
T. Via 2 included in the LTP submittal. Revision 2 contains a brief description of the conceptual site model along with summaries and data from field tests but does not contain any information on the numerical modeling performed using the interface, Groundwater Vistas, for MODFLOW, MODPATH, and MT3DMS. A more complete description of the numerical modeling than provided in the LTP is needed for NRC staff to better understand the bounds and bases of the RESRAD-ONSITE results for the Basement Fill Model.
- 2. Document Request - LTP Chapter 6, Reference 6 Multiple similarly titled reports on radionuclides of concern are cited in the LTP, with an explanation provided on pages 6-9. Some of these documents were also cited in Chapters 2 and 5. Chapter 6 Reference 6, Omaha Public Power District, "FC-18-002, Potential Radionuclides of Concern During the Decommissioning of Fort Calhoun Nuclear Station," was not a document provided in the submittal. However, two other, more recent, documents were provided along with the LTP submittal:
Chapter 6, Reference 7: Omaha Public Power District, "FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern.
Chapter 6, Reference 8: Radiation Safety and Control Services, "FC-21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan," 2021.
Please provide Reference 6 for Chapter 6 or provide an explanation that the information in the latest report contains all the attributed information in the LTP (e.g., details on the suite of radionuclides for the initial sampling for decommissioning in Reference 6 are also included in Reference 8).
- 3. Clarification on Updated or Revised Documents As noted in the above specific examples, multiple revisions of, or similarly titled, reports are cited in the LTP. Clarification is requested on if there are other revisions or updates of referenced documents that the later revisions or updates contain cumulative information from the earlier reports, or only new information.
- 4. Data File Request - Subsurface Transport Modeling Please provide the input file sets used in Groundwater Vistas modeling to support results from RESRAD-ONSITE modeling for the Basement Backfill Model.
- 5. Data Request - Hydrologic Conditions NRC staff requests any historical groundwater level data and river stage measurements from the site that would reflect groundwater elevations near the river. Measurements of groundwater levels from June 2020 are stated in the LTP (pages 6-12) to be reflective of
T. Via 3 historical conditions at the site. The basis is stated to be the steady river stage levels typically between 10 and 15 feet over the past decade based on measurement stations upstream (Decatur) and downstream (Omaha) of the site. The groundwater levels at the site are also stated to be in intimate hydraulic connection with the river (e.g., LTP Section 1.3.6). The hydrologic conditions at the site are used to support the representative and conservative groundwater levels and gradients used in RESRAD-ONSITE model. In addition, hydrologic conditions at the site may impact decommissioning activities (e.g.., excavations, scans, and sampling) thus making the range of conditions expected at the site (e.g., seasonal) a concern given past flooding at the site and concurrent increases in groundwater levels with rising river stages.
In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs ADAMS. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
We request that the supplemental information requested above be provided within 30 days from the date of this letter. If you have any questions, please contact me at (301) 415-6634 or jack.parrott@nrc.gov.
Sincerely, Signed by Parrott, Jack on 12/16/21 Jack D. Parrott, Senior Project Manager Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery and Waste Projects Office of Nuclear Material Safety and Safeguards Docket No. 50-285 cc: Fort Calhoun Listserv Becki Harisis, Manager Office of Radiological Health Nebraska Department of Health & Human Services 301 Centennial Mall South P.O. Box 95026 Lincoln, NE 68509-5026 Becki.Harisis@nebraska.gov
ML21350A026 OFFICE NMSS/DUWP/RDB NMSS/DUWP/RDB NMSS/DUWP/RDB NMSS/DUWP/RDB NAME JParrott JP RFedors RF BWatson BW JParrott JP DATE Dec 16, 2021 Dec 16, 2021 Dec 16, 2021 Dec 16, 2021
