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MONTHYEARLIC-05-0017, Day Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2005-03-0404 March 2005 Day Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request LIC-06-0067, Revised Request for an Extension to the Completion Date for Corrective Actions Taken in Response to Generic Letter 2004-022005-06-0909 June 2005 Revised Request for an Extension to the Completion Date for Corrective Actions Taken in Response to Generic Letter 2004-02 Project stage: Request LIC-05-0101, Follow-up Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2005-08-31031 August 2005 Follow-up Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0602605482006-01-19019 January 2006 Ft. Calhoun Unit 1 - Request for Additional Information Related to Extension Date for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0601802212006-02-0707 February 2006 Request for Additional Information Related to Extension Date for Corrective Actions Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized... Project stage: RAI ML0601001412006-04-10010 April 2006 Ft Calhoun, Letter, Response to Request for Extension to Completion Date for Corrective Action to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other 2005-08-31
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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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February 7, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXTENSION DATE FOR CORRECTIVE ACTIONS REGARDING GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS (TAC NO. MC9564)
Dear Mr. Ridenoure:
By letter dated November 18, 2005, Omaha Public Power District (OPPD/the licensee) submitted a response to Generic Letter (GL) 2004-02 for the Fort Calhoun Station, Unit 1 (FCS). The licensee requested an extension for the GL closure date of December 31, 2007, to the end of the refueling outage scheduled to start in March 2008. The NRC has reviewed OPPDs letter dated November 18, 2005, in which it also provided information regarding the FCS considerations of Information Notice 2005-26. In OPPDs November 18, 2005, letter OPPD listed five corrective measures to be completed in the FCS 2006 refueling outage (including removal of significant quantities of calcium silicate insulation material from containment). This letter also described existing procedural guidance: (1) to shutdown, under certain conditions, redundant high pressure safety injection (HPSI) and core spray pumps to minimize the strainer approach velocity; (2) to reduce the total sump flow when pump cavitation is detected; and (3) to refill the safety injection refueling water tank (SIRWT) with HPSI re-alignment to draw a suction on the SIRWT and inject into the reactor coolant system, if HPSI suction via the containment sump strainers in the recirculation mode is lost.
In addition, OPPD indicated that its strategy for compliance with GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, was provided in the FCS August 31, 2005, followup response to GL 2004-02.
This strategy has been to procure sump strainers with sufficient margin to accommodate any chemical effects that were identified by industry testing. OPPD concluded that: ... OPPD has
[now] determined that the chemical effects and potential downstream effects from the combination of trisodium phosphate (TSP) and calcium silicate insulation identified in Information Notice 2005-26 cannot be accommodated by this [current strainer sizing] strategy and will require additional testing (industry and plant-specific) and evaluation. OPPD described the envisioned testing and stated that such testing could not be completed in time to support design and installation of replacement sump strainers during the scheduled fall 2006 refueling outage. Therefore, OPPD stated that the implementation of the complete GSI-191 modifications by December 31, 2007, as required by GL 2004-02, could not be accomplished.
The Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and had a teleconference on January 13, 2006, with OPPD to discuss this submittal. OPPD has stated
R. Ridenoure that it has developed an option (item 3 above) to only inject as an interim corrective measure, which would allow them to comply with Section 50.46 of Title 10 of the Code of Federal Regulations until a permanent solution is implemented. The NRC staff has determined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on January 13, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Request for Additional Information cc w/encl: See next page
R. Ridenoure which would allow them to comply with Section 50.46 of Title 10 of the Code of Federal Regulations until a permanent solution is implemented. The NRC staff has determined that additional information is needed to complete our review. A request for additional information is enclosed. This request was discussed with Thomas Matthews of your staff on January 13, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIV R/F RidsRgn4MailCenter (DGraves)
RidsNrrDorlLplg (DTerao) RidsNrrPMAWang RidsAcrsAcnwMailCenter RidsNrrLALFeizollahi RidsNrrDorlDpr RidsOgcRp ADAMS ACCESSION NO.: ML060180221 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang LFeizollahi DTerao DATE 02/06/06 02/06/06 02/07/06 Official Record Copy
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02 EXTENSION REQUEST OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION DOCKET NO. 50-285 By letter dated November 18, 2005, Omaha Public Power District (OPPD/the licensee) submitted a response to Generic Letter (GL) 2004-02 for the Fort Calhoun Station, Unit 1 (FCS). The licensee requested an extension for the GL closure date of December 31, 2007, to the end of the refueling outage scheduled to start in March 2008. The Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and had a teleconference on January 13, 2006, with OPPD to discuss this submittal.
OPPD indicated that its strategy for compliance with Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," was provided in the FCS August 31, 2005, followup response to Generic Letter 2004-02. Its strategy has been to "procure sump strainers with sufficient margin to accommodate any chemical effects that were identified by industry testing." OPPD has stated that it has developed an option to only inject as an interim corrective measure that would allow them to comply with Section 50.46 of Title 10 of the Code of Federal Regulations until a permanent solution is implemented. The NRC has reviewed OPPD's letter dated November 18, 2005, with respect to filling the containment to the top of the hot leg using high pressure safety injection (HPSI) suction on the safety injection refueling water tank (SIRWT). Please address the following issues related to this approach:
- 1. What are the physical stresses on the containment building as a result of the higher containment water levels using this approach?
- 2. OPPD stated that it would "enhance procedures to identify equipment and instrumentation that could be affected by flooding the containment above the flood level assumed for equipment qualification," but did not list this equipment and instrumentation and any measures to preserve their functionality or deal with their malfunction,
- 3. OPPD should describe its systems or methods for measuring water level "above the maximum water level at the start of recirculation,"
- 4. List the hierarchy of water sources for SIRWT refill, or discuss the flow paths and flow rates which could be achieved in accomplishing refill, and
- 5. Discuss the actual refill flow rates versus the required refill flow rates, and resultant SIRWT water levels at the various times during which this direct injection lineup would be used in lieu of the recirculation mode (e.g., does OPPD show that the SIRWT does not go empty while HPSI pump suction is required?).
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 Lucas State Office Building, 5th Floor 321 East 12th Street Chairman Des Moines, IA 50319 Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission 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. 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 January 2006