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| {{#Wiki_filter:May 5, 2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. | | {{#Wiki_filter:May 5, 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 | | Post Office Box 550 Fort Calhoun, NE 68023-0550 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPDATED SAFETY ANALYSIS REPORT CLARIFICATION OF OPERATOR ACTION DURING LOSS OF MAIN FEEDWATER EVENT (TAC NO. MC7524)Dear Mr. Ridenoure | | FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPDATED SAFETY ANALYSIS REPORT CLARIFICATION OF OPERATOR ACTION DURING LOSS OF MAIN FEEDWATER EVENT (TAC NO. MC7524) |
| :By letter dated July 1, 2005, Omaha Public Power District (OPPD) submitted a licenseamendment request for the Fort Calhoun Station, Unit 1. The license amendment proposed torevise the Updated Safety Analysis Report (USAR), Section 14.10, to credit operator action during the Loss of Main Feedwater Event. The proposed change will add a description of anexisting Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during a loss of main feedwater event to the USAR.The Nuclear Regulatory Commission (NRC) staff has reviewed OPPD's submittal and had ateleconference on April 24, 2006, with OPPD to discuss this submittal. The NRC staff hasdetermined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on May 1, 2006, and it was agreed that a response would be provided within 6 weeks 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 RegulationDocket No.
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| 50-285 | | ==Dear Mr. Ridenoure:== |
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| | By letter dated July 1, 2005, Omaha Public Power District (OPPD) submitted a license amendment request for the Fort Calhoun Station, Unit 1. The license amendment proposed to revise the Updated Safety Analysis Report (USAR), Section 14.10, to credit operator action during the Loss of Main Feedwater Event. The proposed change will add a description of an existing Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during a loss of main feedwater event to the USAR. |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and had a teleconference on April 24, 2006, with OPPD to discuss this submittal. The NRC staff has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on May 1, 2006, and it was agreed that a response would be provided within 6 weeks 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 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page May 5, 2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
| | RAI cc w/encl: See next page |
| Post Office Box 550 Fort Calhoun, NE 68023-0550 | | |
| | May 5, 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 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPDATED SAFETY ANALYSIS REPORT CLARIFICATION OF OPERATOR ACTION DURING LOSS OF MAIN FEEDWATER EVENT (TAC NO. MC7524)Dear Mr. Ridenoure | | FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPDATED SAFETY ANALYSIS REPORT CLARIFICATION OF OPERATOR ACTION DURING LOSS OF MAIN FEEDWATER EVENT (TAC NO. MC7524) |
| :By letter dated July 1, 2005, Omaha Public Power District (OPPD) submitted a licenseamendment request for the Fort Calhoun Station, Unit 1. The license amendment proposed torevise the Updated Safety Analysis Report (USAR), Section 14.10, to credit operator action during the Loss of Main Feedwater Event. The proposed change will add a description of anexisting Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during a loss of main feedwater event to the USAR.The Nuclear Regulatory Commission (NRC) staff has reviewed OPPD's submittal and had ateleconference on April 24, 2006, with OPPD to discuss this submittal. The NRC staff hasdetermined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on May 1, 2006, and it was agreed that a response would be provided within 6 weeks of receipt of this letter.If you have any questions, please contact me at (301) 415-1445.Sincerely,/RA/
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| Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No.
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| 50-285
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| ==Enclosure:== | | ==Dear Mr. Ridenoure:== |
| RAIcc w/encl: See next page DISTRIBUTION
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| :PUBLICLPLIV R/FRidsNrrPMAWang DGuha, NRR/ADROSSun, NRR/ADESRidsNrrDorlLpl4 (DTerao)RidsRgn4MailCenter (DGraves)RidsOgcRpRidsAcrsAcnwMailCenterRidsNrrDorlDprRidsNrrDssSpwb (JNakowski)
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| RidsNrrLALFeizollahi RidsNrrPMBSingalADAMS ACCESSION NO.: ML061250341OFFICELPL4/PMLPL4/LALPL4/BCNAMEAWang; mxr4LFeizollahiDTeraoDATE5/5/065/5/065/5/06OFFICIAL RECORD COPY REQUEST FOR ADDITIONAL INFORMATIONREGARDING UPDATED SAFETY ANALYSIS REPORT (USAR) CLARIFICATIONOMAHA PUBLIC POWER DISTRICTFORT CALHOUN STATIONDOCKET NO. 50-285By letter dated July 1, 2005, Omaha Public Power District (OPPD), the licensee for the FortCalhoun Station, Unit 1 (FCS), requested a license amendment to permit FCS to revise the USAR, Section 14.10, to credit operator action during the Loss of Main Feedwater (LMFW)
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| Event. The proposed change will add a description of an existing Emergency OperatingProcedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during an LMFW event to the USAR. The operator action is intended to assist the auxiliaryfeedwater system in performing its design function of maintaining adequate steam generator(SG) water level for decay heat removal once the auxiliary feedwater actuation signal isactuated. OPPD requests approval of the proposed change to support plant operationsfollowing the 2006 outage during which the SGs, pressurizer, and reactor vessel head will bereplaced. The Nuclear Regulatory Commission (NRC) staff has performed a preliminary review of thehuman performance associated changes in the license amendment request. The licensee's responses to the following request for additional information with regard to containment analysis aspects of the license amendment are needed for the NRC staff to complete its review.1.Page 22 of Attachment 4 to the licensee's letter of July 1, 2005, stated that for thefeedwater line break (FLB) analysis that "SG blowdown flow is automatically and conservatively isolated at 49.03 sec...." The NRC staff has noted that in FCS TechnicalSpecification Table 2-1, a containment pressure high signal (CPHS) or a pressurizer pressure low signal (PPLS) would actuate a containment isolation actuation signal thatisolates SG blowdown flow. As such:a.Please indicate which signal (a CPHS or a PPLS) was credited to automaticallyisolate the SG in the analysis. Demonstrate that the FLB case with SGblowdown isolation occurring at 49.03 seconds is the limiting break case (considering full-break sizes of the FLB) with respect to the acceptance criterion of the peak post-trip hot-leg temperature of 600 degrees F.b.If OPPD credited a CPHS to isolate the SG blowdown flow, please discuss howthe CPHS time was determined for FLB cases with break sizes ranging from the maximum break size to the smallest credible size.c.Please provide a description of the containment model to show its adequacy forthe CPHS time determination (with respect to prediction of a lower containment pressure resulting in a high CPHS time).
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| d.For the small-size FLBs that would not result in a CPHS, please discuss theavailable Emergency Operating Procedures for the operator to manually isolate SG blowdown flow, and show that the proposed operation action (15 minutesafter a reactor trip) for the LMFW event is sufficient for the FLB event.
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| April 2006Ft. Calhoun Station, Unit 1 cc:Winston & Strawn ATTN: James R. Curtiss, Esq.
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| 1700 K Street, N.W.
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| Washington, DC 20006-3817ChairmanWashington County Board of Supervisors
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| P.O. Box 466 Blair, NE 68008Mr. John Hanna, Resident InspectorU.S. Nuclear Regulatory Commission
| | By letter dated July 1, 2005, Omaha Public Power District (OPPD) submitted a license amendment request for the Fort Calhoun Station, Unit 1. The license amendment proposed to revise the Updated Safety Analysis Report (USAR), Section 14.10, to credit operator action during the Loss of Main Feedwater Event. The proposed change will add a description of an existing Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during a loss of main feedwater event to the USAR. |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and had a teleconference on April 24, 2006, with OPPD to discuss this submittal. The NRC staff has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on May 1, 2006, and it was agreed that a response would be provided within 6 weeks 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 |
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| P.O. Box 310 Fort Calhoun, NE 68023Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Ms. 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 68509-5007Mr. David J. Bannister, ManagerFort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant
| | ==Enclosure:== |
| | RAI cc w/encl: See next page DISTRIBUTION: |
| | PUBLIC LPLIV R/F RidsNrrPMAWang DGuha, NRR/ADRO SSun, NRR/ADES RidsNrrDorlLpl4 (DTerao) |
| | RidsRgn4MailCenter (DGraves) RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrDssSpwb (JNakowski) |
| | RidsNrrLALFeizollahi RidsNrrPMBSingal ADAMS ACCESSION NO.: ML061250341 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang; mxr4 LFeizollahi DTerao DATE 5/5/06 5/5/06 5/5/06 OFFICIAL RECORD COPY |
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| P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Joe L. McManisManager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING UPDATED SAFETY ANALYSIS REPORT (USAR) CLARIFICATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION DOCKET NO. 50-285 By letter dated July 1, 2005, Omaha Public Power District (OPPD), the licensee for the Fort Calhoun Station, Unit 1 (FCS), requested a license amendment to permit FCS to revise the USAR, Section 14.10, to credit operator action during the Loss of Main Feedwater (LMFW) |
| | Event. The proposed change will add a description of an existing Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during an LMFW event to the USAR. The operator action is intended to assist the auxiliary feedwater system in performing its design function of maintaining adequate steam generator (SG) water level for decay heat removal once the auxiliary feedwater actuation signal is actuated. OPPD requests approval of the proposed change to support plant operations following the 2006 outage during which the SGs, pressurizer, and reactor vessel head will be replaced. |
| | The Nuclear Regulatory Commission (NRC) staff has performed a preliminary review of the human performance associated changes in the license amendment request. The licensees responses to the following request for additional information with regard to containment analysis aspects of the license amendment are needed for the NRC staff to complete its review. |
| | : 1. Page 22 of Attachment 4 to the licensee's letter of July 1, 2005, stated that for the feedwater line break (FLB) analysis that "SG blowdown flow is automatically and conservatively isolated at 49.03 sec...." The NRC staff has noted that in FCS Technical Specification Table 2-1, a containment pressure high signal (CPHS) or a pressurizer pressure low signal (PPLS) would actuate a containment isolation actuation signal that isolates SG blowdown flow. As such: |
| | : a. Please indicate which signal (a CPHS or a PPLS) was credited to automatically isolate the SG in the analysis. Demonstrate that the FLB case with SG blowdown isolation occurring at 49.03 seconds is the limiting break case (considering full-break sizes of the FLB) with respect to the acceptance criterion of the peak post-trip hot-leg temperature of 600 degrees F. |
| | : b. If OPPD credited a CPHS to isolate the SG blowdown flow, please discuss how the CPHS time was determined for FLB cases with break sizes ranging from the maximum break size to the smallest credible size. |
| | : c. Please provide a description of the containment model to show its adequacy for the CPHS time determination (with respect to prediction of a lower containment pressure resulting in a high CPHS time). |
| | : d. For the small-size FLBs that would not result in a CPHS, please discuss the available Emergency Operating Procedures for the operator to manually isolate SG blowdown flow, and show that the proposed operation action (15 minutes after a reactor trip) for the LMFW event is sufficient for the FLB event. |
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| P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Daniel K. McGheeBureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319}}
| | Ft. Calhoun Station, Unit 1 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 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 April 2006}} |
Letter Sequence RAI |
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MONTHYEARLIC-05-0001, License Amendment Request, Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event.2005-07-0101 July 2005
License Amendment Request, Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event.
Project stage: Request
ML0529101552005-10-31031 October 2005
RAI, Technical Specifications for Steam Generator Blowdown Isolation
Project stage: RAI
ML0530502792005-11-16016 November 2005
RAI, Related to Technical Specifications for Steam Generator Blowdown Isolation
Project stage: RAI
ML0603204812006-02-0707 February 2006
Request for Additional Information Related to License Amendment Request for Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event
Project stage: RAI
LIC-06-0016, Response to Human Factors Request for Additional Information on Fort Calhoun Station Unit No. 1 License Amendment Request, Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event.2006-02-16016 February 2006
Response to Human Factors Request for Additional Information on Fort Calhoun Station Unit No. 1 License Amendment Request, Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event.
Project stage: Request
ML0612503412006-05-0505 May 2006
Request for Additional Information Related to LAR for Updated SAR Clarification of Operator Action During Loss of Main Feedwater Event
Project stage: RAI
LIC-06-0038, Response to Fort Calhoun, Unit 1 - Request for Additional Information Related to License Amendment Request for Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event2006-07-0606 July 2006
Response to Fort Calhoun, Unit 1 - Request for Additional Information Related to License Amendment Request for Updated Safety Analysis Report Clarification of Operator Action During Loss of Main Feedwater Event
Project stage: Request
2006-02-16
[Table View] |
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Category:Letter
MONTHYEARLIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024
Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information
LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024
Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24255A0962024-09-12012 September 2024
License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285)
ML24243A1042024-09-12012 September 2024
Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256)
IR 05000285/20240022024-08-21021 August 2024
NRC Inspection Report 05000285/2024002
ML24235A0822024-08-10010 August 2024
Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024
ML24180A2082024-07-0808 July 2024
Phase 1 Final Status Survey Reports Request for Additional Information Letter
ML24183A3222024-07-0808 July 2024
Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review
LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024
License Amendment Request (LAR) to Revise License Termination Plan (LTP)
IR 05000285/20240012024-06-0505 June 2024
NRC Inspection Report 05000285/2024001
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024
Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI
LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024
Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report
LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024
(Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan
ML24079A1702024-03-10010 March 2024
ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe
LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024
Annual Decommissioning Funding / Irradiated Fuel Management Status Report
LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024
Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report
ML24019A1672024-01-31031 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
ML23234A2392023-08-18018 August 2023
Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf
ML23234A2412023-08-18018 August 2023
Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request
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
IR 05000285/20230022023-06-0505 June 2023
NRC Inspection Report 05000285/2023002
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
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
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
IR 05000285/20230012023-02-24024 February 2023
NRC Inspection Report 05000285/2023001
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
ML22138A1222022-08-0303 August 2022
Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, 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
ML22138A1242022-08-0303 August 2022
Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, 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
ML22138A1212022-08-0303 August 2022
Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106
2024-09-18
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24243A1042024-09-12012 September 2024
Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256)
ML24180A2062024-07-0808 July 2024
Phase 1 Final Status Survey Reports Request for Additional Information
ML23151A0042023-06-0606 June 2023
Second Set RAIs Rev 4
ML22357A0672022-12-30030 December 2022
Enclosure RAI Re Approval of License Termination Plan
ML22119A2472022-05-0303 May 2022
Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review
ML20111A2162020-05-20020 May 2020
Revised PSDAR Request for Additional Information - RAI
ML19241A1812019-08-21021 August 2019
Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status
ML18067A1432018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to M. J. Fisher Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station ISFSI)
ML17236A3462017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567)
ML17236A3442017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664)
ML17234A4692017-08-22022 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831)
ML17194A9732017-07-13013 July 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
ML17112A0362017-04-20020 April 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR
ML17090A3942017-03-31031 March 2017
NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437)
ML17082A0022017-03-22022 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption
ML17081A0192017-03-21021 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption
ML17067A3862017-03-15015 March 2017
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML17033A9692017-02-0202 February 2017
NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment
ML16263A0492016-09-20020 September 2016
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML16174A1502016-06-27027 June 2016
Request for Additional Information, Relief Request, Use of Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML16146A1782016-05-27027 May 2016
Request for Additional Information, Round 2, 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
ML16106A0232016-04-29029 April 2016
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML16104A2872016-04-25025 April 2016
Request for Additional Information, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML16048A1542016-02-23023 February 2016
Request for Additional Information, License Amendment Request, Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16048A0242016-02-23023 February 2016
Request for Additional Information, License Amendment Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML15343A1082015-12-15015 December 2015
Request for Additional Information, License Amendment Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition
ML15323A0362015-11-24024 November 2015
Request for Additional Information, Relief Requests P-1 - LPSI and CS Pumps and P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21, Fifth 10-Year Inservice Testing Interval
ML15194A2722015-07-14014 July 2015
Request for Additional Information, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML15057A0152015-03-0303 March 2015
Request for Additional Information, Materials Reliability Program (MRP)-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Implementation Review
ML15043A0612015-02-25025 February 2015
Request for Additional Information, Round 2, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14353A0512014-12-22022 December 2014
Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra
ML14259A3652014-09-24024 September 2014
Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14195A0862014-07-16016 July 2014
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
ML13317A5832013-11-25025 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13290A0022013-10-0909 October 2013
Request for Additional Information Email, License Amendment Request to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks
ML13282A5362013-10-0909 October 2013
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ML13270A2872013-09-27027 September 2013
Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
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ML13233A2482013-08-26026 August 2013
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ML13235A1682013-08-23023 August 2013
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ML13226A1222013-08-14014 August 2013
Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML13212A0092013-07-30030 July 2013
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ML13205A1252013-07-24024 July 2013
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ML13205A0182013-07-23023 July 2013
Request for Additional Information Email, Exigent License Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact
ML13144A4822013-05-23023 May 2013
Request for Additional Information Email, Decommissioning Funding Status Report
ML13100A1752013-04-10010 April 2013
Request for Additional Information 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
ML13086A4732013-03-27027 March 2013
Request for Additional Information Email, Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML13120A0842013-03-22022 March 2013
Request for Additional Information Email Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 20 (TAC No. D91660)
2024-09-12
[Table view] |
Text
May 5, 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 LICENSE AMENDMENT REQUEST FOR UPDATED SAFETY ANALYSIS REPORT CLARIFICATION OF OPERATOR ACTION DURING LOSS OF MAIN FEEDWATER EVENT (TAC NO. MC7524)
Dear Mr. Ridenoure:
By letter dated July 1, 2005, Omaha Public Power District (OPPD) submitted a license amendment request for the Fort Calhoun Station, Unit 1. The license amendment proposed to revise the Updated Safety Analysis Report (USAR), Section 14.10, to credit operator action during the Loss of Main Feedwater Event. The proposed change will add a description of an existing Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during a loss of main feedwater event to the USAR.
The Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and had a teleconference on April 24, 2006, with OPPD to discuss this submittal. The NRC staff has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on May 1, 2006, and it was agreed that a response would be provided within 6 weeks 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:
RAI cc w/encl: See next page
May 5, 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 LICENSE AMENDMENT REQUEST FOR UPDATED SAFETY ANALYSIS REPORT CLARIFICATION OF OPERATOR ACTION DURING LOSS OF MAIN FEEDWATER EVENT (TAC NO. MC7524)
Dear Mr. Ridenoure:
By letter dated July 1, 2005, Omaha Public Power District (OPPD) submitted a license amendment request for the Fort Calhoun Station, Unit 1. The license amendment proposed to revise the Updated Safety Analysis Report (USAR), Section 14.10, to credit operator action during the Loss of Main Feedwater Event. The proposed change will add a description of an existing Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during a loss of main feedwater event to the USAR.
The Nuclear Regulatory Commission (NRC) staff has reviewed OPPDs submittal and had a teleconference on April 24, 2006, with OPPD to discuss this submittal. The NRC staff has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on May 1, 2006, and it was agreed that a response would be provided within 6 weeks 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:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIV R/F RidsNrrPMAWang DGuha, NRR/ADRO SSun, NRR/ADES RidsNrrDorlLpl4 (DTerao)
RidsRgn4MailCenter (DGraves) RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrDssSpwb (JNakowski)
RidsNrrLALFeizollahi RidsNrrPMBSingal ADAMS ACCESSION NO.: ML061250341 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang; mxr4 LFeizollahi DTerao DATE 5/5/06 5/5/06 5/5/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION REGARDING UPDATED SAFETY ANALYSIS REPORT (USAR) CLARIFICATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION DOCKET NO. 50-285 By letter dated July 1, 2005, Omaha Public Power District (OPPD), the licensee for the Fort Calhoun Station, Unit 1 (FCS), requested a license amendment to permit FCS to revise the USAR, Section 14.10, to credit operator action during the Loss of Main Feedwater (LMFW)
Event. The proposed change will add a description of an existing Emergency Operating Procedure operator action to isolate steam generator blowdown within 15 minutes of reactor trip during an LMFW event to the USAR. The operator action is intended to assist the auxiliary feedwater system in performing its design function of maintaining adequate steam generator (SG) water level for decay heat removal once the auxiliary feedwater actuation signal is actuated. OPPD requests approval of the proposed change to support plant operations following the 2006 outage during which the SGs, pressurizer, and reactor vessel head will be replaced.
The Nuclear Regulatory Commission (NRC) staff has performed a preliminary review of the human performance associated changes in the license amendment request. The licensees responses to the following request for additional information with regard to containment analysis aspects of the license amendment are needed for the NRC staff to complete its review.
- 1. Page 22 of Attachment 4 to the licensee's letter of July 1, 2005, stated that for the feedwater line break (FLB) analysis that "SG blowdown flow is automatically and conservatively isolated at 49.03 sec...." The NRC staff has noted that in FCS Technical Specification Table 2-1, a containment pressure high signal (CPHS) or a pressurizer pressure low signal (PPLS) would actuate a containment isolation actuation signal that isolates SG blowdown flow. As such:
- a. Please indicate which signal (a CPHS or a PPLS) was credited to automatically isolate the SG in the analysis. Demonstrate that the FLB case with SG blowdown isolation occurring at 49.03 seconds is the limiting break case (considering full-break sizes of the FLB) with respect to the acceptance criterion of the peak post-trip hot-leg temperature of 600 degrees F.
- b. If OPPD credited a CPHS to isolate the SG blowdown flow, please discuss how the CPHS time was determined for FLB cases with break sizes ranging from the maximum break size to the smallest credible size.
- c. Please provide a description of the containment model to show its adequacy for the CPHS time determination (with respect to prediction of a lower containment pressure resulting in a high CPHS time).
- d. For the small-size FLBs that would not result in a CPHS, please discuss the available Emergency Operating Procedures for the operator to manually isolate SG blowdown flow, and show that the proposed operation action (15 minutes after a reactor trip) for the LMFW event is sufficient for the FLB event.
Ft. Calhoun Station, Unit 1 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 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 April 2006
