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| | number = ML110610217 | | | number = ML110610217 |
| | issue date = 03/03/2011 | | | issue date = 03/03/2011 |
| | title = Fort Calhoun Station, Unit No. 1, Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval (TAC No. ME4541) | | | title = Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Bannister D J | | | addressee name = Bannister D |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, O.C. 20555-0001 March 3, 2011 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 SUB..FORT CALHOUN STATION, UNIT NO.1 -SECOND REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR RELIEF FROM CODE CASE N-722 VISUAL EXAMINATION OF THE REACTOR VESSEL HOT-LEG NOZZLE-TO-SAFE-END DISSIMILAR METAL WELDS (TAC NO. ME4541) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 March 3, 2011 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 SUB..IECT: FORT CALHOUN STATION, UNIT NO.1 - SECOND REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR RELIEF FROM CODE CASE N-722 VISUAL EXAMINATION OF THE REACTOR VESSEL HOT-LEG NOZZLE-TO-SAFE-END DISSIMILAR METAL WELDS (TAC NO. ME4541) |
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| ==Dear Mr. Bannister:== | | ==Dear Mr. Bannister:== |
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| By letter dated August 16, 2010, as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 102300679 and ML 110200205, respectively), Omaha Public Power District proposed an alternative to paragraph 50.55a(g)(6)(ii)(E), "Reactor coolant pressure boundary visual inspections," of Title 10 of the Code of Federal Regulations (10 CFR) for the Fort Calhoun Station, Unit No.1. This requirement defines the inservice inspection (lSI) frequency of visual examination of the reactor vessel hot leg nozzle-to-safe-end welds in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR [Pressurized-Water Reactor] Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with the U.S. Nuclear Regulatory Commission (NRC) conditions. | | By letter dated August 16, 2010, as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. |
| The duration of request is for the fourth 10-year lSI interval which ends on September 25, 2013. The NRC staff has reviewed your submittals and has determined that the information specified in the enclosed request for additional information (RAI) is needed for the staff to complete its evaluation. | | ML102300679 and ML110200205, respectively), Omaha Public Power District proposed an alternative to paragraph 50.55a(g)(6)(ii)(E), "Reactor coolant pressure boundary visual inspections," of Title 10 of the Code of Federal Regulations (10 CFR) for the Fort Calhoun Station, Unit No.1. This requirement defines the inservice inspection (lSI) frequency of visual examination of the reactor vessel hot leg nozzle-to-safe-end welds in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR [Pressurized-Water Reactor] Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with the U.S. Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year lSI interval which ends on September 25, 2013. |
| A draft copy of the enclosed RAI was provided to Mr. Bill Hansher of your staff via e-mail on February 23, 2011, and discussed with Mr. Hansher and others of your staff on February 24, 2011. Mr. Hansher indicated that the response would be provided within 7 days of receipt of this letter. | | The NRC staff has reviewed your submittals and has determined that the information specified in the enclosed request for additional information (RAI) is needed for the staff to complete its evaluation. A draft copy of the enclosed RAI was provided to Mr. Bill Hansher of your staff via e-mail on February 23, 2011, and discussed with Mr. Hansher and others of your staff on February 24, 2011. Mr. Hansher indicated that the response would be provided within 7 days of receipt of this letter. |
| D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov. Sincerely, ) | | |
| Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 | | D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov. |
| | Sincerely, |
| | ) '~f' |
| | ~~-M~- |
| | Lynnea E. Wilkins, 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:== |
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| As stated cc w/encl: Distribution via Listserv SECOND REQUEST FOR ADDITIONAL REQUEST FOR RELIEF FROM ASME CODE CASE N-722 REQUIREMENTS FOR VISUAL EXAMINATION OF REACTOR VESSEL HOT LEG NOZZLE TO SAFE END WELDS OMAHA PUBLIC POWER DISTRICT, FORT CALHOUN STATION, UNIT NO.1, DOCKET NO. 50-285 By letter dated August 16, 2010, as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 102300679 and ML 110200205, respectively), Omaha Public Power District proposed an alternative to paragraph 50.55a(g)(6)(ji)(E), "Reactor coolant pressure boundary visual inspections," of Title 10 of the Code of Federal Regulations (10 CFR) for the Fort Calhoun Station, Unit No.1. This requirement defines the inservice inspection (lSI) frequency of visual examination of the reactor vessel hot leg nozzle-to-safe-end welds in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR [Pressurized-Water Reactor] Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with the U.S. Nuclear Regulatory Commission (NRC) conditions. | | As stated cc w/encl: Distribution via Listserv |
| The duration of request is for the fourth 10-year lSI interval which ends on September 25, 2013. The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the relief request. In Reference 8.a of the Attachment to the letter dated August 16, 2010, the as-built dimension of the Nozzle Extension Forging (a.k.a. safe end) is not provided. | | |
| The drawing identifies a distance much larger than assumed in the analysis under References 9, 10, and 11. Please provide the basis for the distance between the dissimilar metal weld and stainless steel weld used in the analysis. It appears from Reference 6 of the Attachment to the letter dated August 16, 2010, that the post extended power uprate loads used in the analysis as documented in Table 3-3 were not conservative. | | SECOND REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF FROM ASME CODE CASE N-722 REQUIREMENTS FOR VISUAL EXAMINATION OF REACTOR VESSEL HOT LEG NOZZLE TO SAFE END WELDS OMAHA PUBLIC POWER DISTRICT, FORT CALHOUN STATION, UNIT NO.1, DOCKET NO. 50-285 By letter dated August 16, 2010, as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. |
| Loop 2 loads appear to be used for Deadweight | | ML102300679 and ML110200205, respectively), Omaha Public Power District proposed an alternative to paragraph 50.55a(g)(6)(ji)(E), "Reactor coolant pressure boundary visual inspections," of Title 10 of the Code of Federal Regulations (10 CFR) for the Fort Calhoun Station, Unit No.1. This requirement defines the inservice inspection (lSI) frequency of visual examination of the reactor vessel hot leg nozzle-to-safe-end welds in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR [Pressurized-Water Reactor] Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with the U.S. Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year lSI interval which ends on September 25, 2013. |
| + Normal Operating Thermal, and Loop 1 values were used for Operational Basis Earthquake and Safe Shutdown Earthquake. | | The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the relief request. |
| However, initial review of Reference 6 indicates the values calculated for the other Loop in each case were higher. Enclosure | | : 1. In Reference 8.a of the Attachment to the letter dated August 16, 2010, the as-built dimension of the Nozzle Extension Forging (a.k.a. safe end) is not provided. The drawing identifies a distance much larger than assumed in the analysis under References 9, 10, and 11. |
| -2 Please state the basis for using minimum loop loading values in Table 3-3 of the Attachment to the letter dated August 16, 2010. Figures 18 and 19 of Reference 11 of the Attachment to the letter dated August 16, 2010, appear to be the closest stress profiles to the one used to develop Figure 4-1 of the submittal. | | Please provide the basis for the distance between the dissimilar metal weld and stainless steel weld used in the analysis. |
| Figures 18 and 19 included post-weld heat treatment, a 25 percent weld repair, and a 5-13/32-inch safe-end length. Please provide the basis for the differences between the analysis and results between Figures 18,19, and 4-1. Specifically, please state the basis for the reduction in magnitude of the hoop and axial stresses in the inner half-thickness of the nozzle. Please describe the post-weld heat treatment procedure used after the dissimilar metal weld was fabricated. | | : 2. It appears from Reference 6 of the Attachment to the letter dated August 16, 2010, that the post extended power uprate loads used in the analysis as documented in Table 3-3 were not conservative. Loop 2 loads appear to be used for Deadweight + Normal Operating Thermal, and Loop 1 values were used for Operational Basis Earthquake and Safe Shutdown Earthquake. However, initial review of Reference 6 indicates the values calculated for the other Loop in each case were higher. |
| D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov. Docket No. 50-285 | | Enclosure |
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| | -2 Please state the basis for using minimum loop loading values in Table 3-3 of the Attachment to the letter dated August 16, 2010. |
| | : 3. Figures 18 and 19 of Reference 11 of the Attachment to the letter dated August 16, 2010, appear to be the closest stress profiles to the one used to develop Figure 4-1 of the submittal. Figures 18 and 19 included post-weld heat treatment, a 25 percent weld repair, and a 5-13/32-inch safe-end length. |
| | Please provide the basis for the differences between the analysis and results between Figures 18,19, and 4-1. Specifically, please state the basis for the reduction in magnitude of the hoop and axial stresses in the inner half-thickness of the nozzle. |
| | : 4. Please describe the post-weld heat treatment procedure used after the dissimilar metal weld was fabricated. |
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| | D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov. |
| | Sincerely, |
| | /RA! |
| | Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of !\Iuclear Reactor Regulation Docket No. 50-285 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDciCpnb Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLA...IBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JCollins, NRRIDCI/CPNB DRudland, RESIDE/CIB Sincerely, /RA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of !\Iuclear Reactor Regulation ADAMS Accession No. M L 110610217 | | PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDciCpnb Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLA...IBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JCollins, NRRIDCI/CPNB DRudland, RESIDE/CIB ADAMS Accession No. M L 110610217 *memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins JBurkhardt TLupold* MMarkley LWilkins DATE 3/2/11 3/2/11 2/17/11 3/3/11 3/3/11 OFFICIAL RECORD COpy}} |
| *memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins JBurkhardt TLupold* MMarkley LWilkins DATE 3/2/11 3/2/11 2/17/11 3/3/11 3/3/11 OFFICIAL RECORD COpy}} | |
Letter Sequence RAI |
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MONTHYEARML1023006412010-08-16016 August 2010
10 CFR 50.55a Request Number RR-12, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot Leg Nozzle to Safe End Dissimilar Metal Welds
Project stage: Request
ML1026500132010-09-21021 September 2010
Acceptance Review E-mail, Relief Request RR-12, from Requirements of ASME Code Case N-722 Visual Examination of Reactor Vessel Hot-Leg Nozzle to Safe End Dissimilar Metal Welds for 4th 10-Year Inservice Inspection Interval (ME4541)
Project stage: Acceptance Review
ML1027801882010-10-0404 October 2010
Email, Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541)
Project stage: Draft RAI
ML1027801902010-10-0404 October 2010
Draft Request for Additional Information, Relief Request RR-12, from Requirements of ASME Code Case N-722 for Fourth 10-Year Inservice Inspection Interval (ME4541)
Project stage: Draft RAI
ML1028600872010-10-25025 October 2010
Request for Additional Information, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
Project stage: RAI
ML1029101312010-10-25025 October 2010
Request for Withholding Information from Public Disclosure, 7/30/10 Affidavit Executed by J. Gresham, Westinghouse
Project stage: Withholding Request Acceptance
LIC-10-0095, Response to Request for Additional Information (RAI) Regarding Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle to Safe End Welds2010-11-0404 November 2010
Response to Request for Additional Information (RAI) Regarding Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle to Safe End Welds
Project stage: Response to RAI
ML1102001932011-01-14014 January 2011
Withdrawal of Response to Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds
Project stage: Withdrawal
ML1104705872011-02-16016 February 2011
Request for Additional Information LAR to Revise Technical Specification to Relocate Operating and Surveillance Requirements for the Power Operated Relief Valve
Project stage: RAI
ML1104705882011-02-16016 February 2011
Request for Additional Information
Project stage: RAI
ML1105404412011-02-23023 February 2011
Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
Project stage: RAI
ML1105404492011-02-23023 February 2011
Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
Project stage: RAI
ML1106102172011-03-0303 March 2011
Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
Project stage: RAI
LIC-11-0016, Response to Second NRC Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds2011-03-0404 March 2011
Response to Second NRC Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds
Project stage: Request
ML1109103272011-04-0505 April 2011
Verbal Authorization, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot-Leg Nozzle-to-Safe-End Dissimilar Metal Welds, 4th 10-Year Inservice Inspection Interval
Project stage: Other
ML1108309472011-05-17017 May 2011
Request for Withholding Information from Public Disclosure, Affidavit Dated 7/30/10, Executed by J. Gresham, Westinghouse, Report LTR-PAFM-10-123-P, Revision 0
Project stage: Withholding Request Acceptance
ML1122702902011-08-18018 August 2011
Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval
Project stage: Other
LIC-12-0004, Delay 2012 Refueling Outage and Extend In-service Inspection (ISI) and In-service Test (IST) Intervals2012-01-17017 January 2012
Delay 2012 Refueling Outage and Extend In-service Inspection (ISI) and In-service Test (IST) Intervals
Project stage: Other
2011-02-16
[Table View] |
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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]
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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 March 3, 2011 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 SUB..IECT: FORT CALHOUN STATION, UNIT NO.1 - SECOND REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR RELIEF FROM CODE CASE N-722 VISUAL EXAMINATION OF THE REACTOR VESSEL HOT-LEG NOZZLE-TO-SAFE-END DISSIMILAR METAL WELDS (TAC NO. ME4541)
Dear Mr. Bannister:
By letter dated August 16, 2010, as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML102300679 and ML110200205, respectively), Omaha Public Power District proposed an alternative to paragraph 50.55a(g)(6)(ii)(E), "Reactor coolant pressure boundary visual inspections," of Title 10 of the Code of Federal Regulations (10 CFR) for the Fort Calhoun Station, Unit No.1. This requirement defines the inservice inspection (lSI) frequency of visual examination of the reactor vessel hot leg nozzle-to-safe-end welds in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR [Pressurized-Water Reactor] Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with the U.S. Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year lSI interval which ends on September 25, 2013.
The NRC staff has reviewed your submittals and has determined that the information specified in the enclosed request for additional information (RAI) is needed for the staff to complete its evaluation. A draft copy of the enclosed RAI was provided to Mr. Bill Hansher of your staff via e-mail on February 23, 2011, and discussed with Mr. Hansher and others of your staff on February 24, 2011. Mr. Hansher indicated that the response would be provided within 7 days of receipt of this letter.
D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Sincerely,
) '~f'
~~-M~-
Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
As stated cc w/encl: Distribution via Listserv
SECOND REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF FROM ASME CODE CASE N-722 REQUIREMENTS FOR VISUAL EXAMINATION OF REACTOR VESSEL HOT LEG NOZZLE TO SAFE END WELDS OMAHA PUBLIC POWER DISTRICT, FORT CALHOUN STATION, UNIT NO.1, DOCKET NO. 50-285 By letter dated August 16, 2010, as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML102300679 and ML110200205, respectively), Omaha Public Power District proposed an alternative to paragraph 50.55a(g)(6)(ji)(E), "Reactor coolant pressure boundary visual inspections," of Title 10 of the Code of Federal Regulations (10 CFR) for the Fort Calhoun Station, Unit No.1. This requirement defines the inservice inspection (lSI) frequency of visual examination of the reactor vessel hot leg nozzle-to-safe-end welds in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR [Pressurized-Water Reactor] Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with the U.S. Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year lSI interval which ends on September 25, 2013.
The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the relief request.
- 1. In Reference 8.a of the Attachment to the letter dated August 16, 2010, the as-built dimension of the Nozzle Extension Forging (a.k.a. safe end) is not provided. The drawing identifies a distance much larger than assumed in the analysis under References 9, 10, and 11.
Please provide the basis for the distance between the dissimilar metal weld and stainless steel weld used in the analysis.
- 2. It appears from Reference 6 of the Attachment to the letter dated August 16, 2010, that the post extended power uprate loads used in the analysis as documented in Table 3-3 were not conservative. Loop 2 loads appear to be used for Deadweight + Normal Operating Thermal, and Loop 1 values were used for Operational Basis Earthquake and Safe Shutdown Earthquake. However, initial review of Reference 6 indicates the values calculated for the other Loop in each case were higher.
Enclosure
-2 Please state the basis for using minimum loop loading values in Table 3-3 of the Attachment to the letter dated August 16, 2010.
- 3. Figures 18 and 19 of Reference 11 of the Attachment to the letter dated August 16, 2010, appear to be the closest stress profiles to the one used to develop Figure 4-1 of the submittal. Figures 18 and 19 included post-weld heat treatment, a 25 percent weld repair, and a 5-13/32-inch safe-end length.
Please provide the basis for the differences between the analysis and results between Figures 18,19, and 4-1. Specifically, please state the basis for the reduction in magnitude of the hoop and axial stresses in the inner half-thickness of the nozzle.
- 4. Please describe the post-weld heat treatment procedure used after the dissimilar metal weld was fabricated.
D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Sincerely,
/RA!
Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of !\Iuclear Reactor Regulation Docket No. 50-285
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDciCpnb Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLA...IBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JCollins, NRRIDCI/CPNB DRudland, RESIDE/CIB ADAMS Accession No. M L 110610217 *memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins JBurkhardt TLupold* MMarkley LWilkins DATE 3/2/11 3/2/11 2/17/11 3/3/11 3/3/11 OFFICIAL RECORD COpy
