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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
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23151A0042023-06-0606 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) 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) ML17236A3462017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567) 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 ML13282A5362013-10-0909 October 2013 Request for Additional Information Email, Round 2, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) 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 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) ML13261A2122013-09-18018 September 2013 Request for Additional Information Email, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) ML13233A2482013-08-26026 August 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action; Request for Exemption, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage in Lieu of 10 CFR 26.205(d)(7) ML13235A1682013-08-23023 August 2013 Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13234A4352013-08-22022 August 2013 Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component Due to Inoperable Power Source 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 Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source ML13205A1252013-07-24024 July 2013 Request for Additional Information Email Round 2, Exigent Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact 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) ML13053A2262013-02-22022 February 2013 Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. ML13016A4322013-01-16016 January 2013 E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) 2023-06-06
[Table view] |
Text
November 16, 2005 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 NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATIONS FOR STEAM GENERATOR BLOWDOWN ISOLATION (TAC NO. MC7524)
Dear Mr. Ridenoure:
By letter dated July 1, 2005 (Agencywide Documents Access and Management System Accession No. ML051950401), Omaha Public Power District (OPPD/the licensee) requested a license amendment for changing the Updated Safety Analyses Report to credit operator action to isolate steam generator blowdown during a loss-of-main feedwater event. As a result of our review of OPPDs submittal, we have determined that additional information is needed to complete our review. The Nuclear Regulatory Commission staffs request for additional information (RAI) related to OPPDs request is attached. This request was discussed with Thomas Matthews of your staff and it was agreed that a response would be provided within 30 days of receipt of this letter.
Fort Calhoun has been selected to be part of the RAI Data Collection-Pilot Effort. As discussed previously, the RAIs have been assigned a category to be used in our pilot effort. If you have any questions or comments on the RAIs or their categorization 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
November 16, 2005 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 NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATIONS FOR STEAM GENERATOR BLOWDOWN ISOLATION (TAC NO. MC7524)
Dear Mr. Ridenoure:
By letter dated July 1, 2005 (Agencywide Documents Access and Management System Accession No. ML051950401), Omaha Public Power District (OPPD/the licensee) requested a license amendment for changing the Updated Safety Analyses Report to credit operator action to isolate steam generator blowdown during a loss-of-main feedwater event. As a result of our review of OPPDs submittal, we have determined that additional information is needed to complete our review. The Nuclear Regulatory Commission staffs request for additional information (RAI) related to OPPDs request is attached. This request was discussed with Thomas Matthews of your staff and it was agreed that a response would be provided within 30 days of receipt of this letter.
Fort Calhoun has been selected to be part of the RAI Data Collection-Pilot Effort. As discussed previously, the RAIs have been assigned a category to be used in our pilot effort. If you have any questions or comments on the RAIs or their categorization 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 Reading RidsNrrDorlLpliv (DTerao) RidsAcrsAcnwMailCenter RidsNrrLALFeizollahi RidsRegion4MailCenter (DGraves)
RidsNrrPMAWang RidsNrrDorlDpr RidsOgcRp ADAMS ACCESSION NO.: ML053050279 OFFICE LPLIV/PM LPLIV/LA LPLIV/BC NAME AWang LFeizollahi DTerao DATE 11/14/05 11/10/05 11/16/05 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION TECHNICAL SPECIFICATION RELATED TO STEAM GENERATOR BLOWDOWN ISOLATION PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 By letter dated July 1, 2005, Omaha Public Power District (OPPD) requested a license amendment for changing the Updated Safety Analyses Report (USAR) to credit operator action to isolate steam generator blowdown during a loss-of-main feedwater event (LMFW). As a result of our review of OPPDs submittal, we have determined that the following additional information is needed to complete our review:
(1) Steam Generator (SG) Blowdown Isolation Confirm that the SG blowdown isolation system is a safety grade system. If it is not a safety grade system, justify that its isolation function can be achieved on demand during the limiting transient for determining the required operator action for SG blowdown isolation. Does this function need to be included as a technical specification surveillance requirement to assure the reliability of the isolation system?
Also, confirm that taking credit of the operator action for SG blowdown isolation will not inadvertently affect the results of any loss-of-coolant accident (LOCA) and non-LOCA transients. (2a)
(2) SG Heat Transfer Model Discuss the SG heat transfer model in S-RELAP5 for events that experience SG dryout.
Provide the values of SG dryout heat transfer coefficients used in the analysis of non-LOCA transients, in particular, the LMFW and feedwater line break (FWLB) events.
The semiscale test data for FWLB (as discussed in Section 4.3.3.1 of NUREG/CR-4945, dated July 1987) demonstrate that SG heat transfer capacity remains unchanged until the SG liquid inventory is nearly deleted. This is followed by a rapid reduction to zero percent heat transfer with little further reduction in the SG water inventory. In light of these test data, OPPD is requested to verify that the heat transfer model used in the LMFW and FWLB events (that experience SG dryout) is conservative as compared to the semiscale test data. In addition, please provide:
a) a sketch of the four vertically stacked control volumes showing the volumes from top to bottom and associated void fractions, b) combine Figures 4 and 5 so that the conservatism can be readily apparent, and c) a justification for why S-RELAP5 is conservative with respect to semi-scale tests for FWLBs from 14 to 40 percent. (2b)
(3) Initial Conditions Discuss the effects of each parameter of the plant's initial conditions listed in Table 1 and 3 of to the July 1, 2005, letter on the LMFW and FWLB analyses, respectively. Justify that the values of the parameters used in the analysis are conservative in determination of the shortest required operator action time for SG blowdown isolation. The discussion should include all of the parameters of Table 1 (such as initial pressurizer pressure and level, initial SG pressure, and reactor protection system trip on a low SG level, etc.) and justify why the values used in the analysis are conservative with respect to the shortest time required for operator action to isolate blowdown. (2a)
(4) Non-Safety Grade Components and/or Systems Identify any non-safety grade systems and/or components that were credited for consequence mitigation in the LMFW and FWLB analysis, and justify that the use of identified non-safety systems and/or components for event mitigation is acceptable. Provide examples of non-safety grade systems that exacerbate the consequences of the LMFW and/or FWLB event. (2a)
(5) CESEC and S-RELAP5 Comparison Identify the differences of SG blowdown isolation models used in CESEC and S-RELAP5. (2b)
Both codes were approved by the Nuclear Regulatory Commission for use in the analysis of non-LOCA transients. Identify the fuel cycle number that started using S-RELAP5 to replace CESEC for the reload analysis. Explain why the need of operation action for SG blowdown was not identified in the current Cycle 23 reload analysis, instead, it was identified for Cycle 24 reload analysis that simulated the replacement SG, pressurizer, and reactor vessel head to be installed in 2006. Are there any effects on the LOCA and non-LOCA transient analyses (in particular, the LMFW and FWLB analysis) caused by the replacement SG, pressurizer, and reactor vessel? (3e)
Provide a statement discussing why Criterion 2 on page 8 of the auxiliary feedwater actuating system setpoint report is acceptable. In particular, justify that the conditions with Th < 600o F and reactor coolant system subcooling > 20o F will assure fuel cladding integrity in meeting the plant-specific departure from nucleate boiling safety limit and fuel centerline melting limit. (2b)
RAI CATEGORIES (Select only one, most dominant category for each RAI question)
- 1. More information is needed because of:
- a. complexity of request
- b. first-of-a-kind nature of request
- c. NRC change in regulatory significance or focus
- d. NRC questions on previously used methodology or guidance
- e. licensee change to previously used methodology
- f. licensee reduction in current safety margin
- 2. The review can not be completed without additional explanation or clarification of:
- a. input variables or analytical assumptions
- b. methodology used or results obtained
- c. applicability or bounding nature of third party analyses or data correlations
- d. differences from NRC guidance documents (SRP, RG, etc.)
- e. no significant hazards consideration discussion
- f. environmental considerations discussion
- g. applicable regulatory requirements discussion
- h. information that appears to be incorrect and needs to be corrected
- i. response to previous RAI appears inadequate
- 3. Reviewer requesting information even though the question is, or the question asks for:
- a. not directly related to the request
- b. inconsistent with applicable codes, standards, RGs, or SRP sections
- c. information accessible from readily available sources and was explicitly referenced
- d. Information does not appear needed given the precedent cases discussed in the request
- e. information that is not safety significant or pertinent to the regulatory finding
- f. information that is known to engineers who work in the general technical area
- g. going beyond the current licensing basis and doesn't need to be asked
- h. a formal commitment
- 4. Other (please specify)
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. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Centential 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 September 2005