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| | number = ML102780190 | | | number = ML102780190 |
| | issue date = 10/04/2010 | | | issue date = 10/04/2010 |
| | title = Fort Calhoun Unit 1 - 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) | | | title = 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) |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Hansher B R | | | addressee name = Hansher B |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
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| {{#Wiki_filter:ENCLOSURE 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, Omaha Public Power District (the licensee), proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(E) for Fort Calhoun Station, Unit 1. This requirement defines the inservice inspection frequency of visual examination of the reactor vessel hot leg nozzle to safe end welds in accordance with American Society of Mechanical Engineer's Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with NRC conditions. The duration of request is for the fourth 10-year ISI interval which ends on September 25, 2013. | | {{#Wiki_filter: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, Omaha Public Power District (the licensee), proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(E) for Fort Calhoun Station, Unit 1. This requirement defines the inservice inspection frequency of visual examination of the reactor vessel hot leg nozzle to safe end welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials, and with NRC conditions. The duration of request is for the fourth 10-year ISI 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. The NRC staff requests the licensee's basis for not performing a visual, volumetric or inside surface examination of each weld necessary to meet the inspection requirements of 10 CFR 50.55a(g)(6)(ii)(E). If visual, volumetric or inside surface examinations could be performed on each penetration nozzle to meet the current inspection requirements, the NRC staff finds insufficient basis to grant relief under 10 CFR 50.55a(a)(3)(i), as not performing the examination does not provide the same level of assurance as the current inspection requirements. However if there is a hardship, NRC staff requests the licensee's basis for relief to not perform the inspection under 10 CFR 50.55a(a)(3)(ii). 2. NRC staff requests the following references used in the Westinghouse calculation; numbers 3, 5, 6, 8, 9, 10 and 11. NRC staff will need these references quickly to have sufficient time to perform verification calculations and support the licensee's schedule. 3. NRC staff requests the 2003, 2008, and 2009 inspection data of welds designated Items 1 and 2 in Table 1 of the August 16, 2010 relief request. NRC staff requests the inspector's summary reports to verify previous inspection results, and verify basis for initial starting flaw size in flaw analysis calculations. For example, reports documentation the inspection stating "No Reportable" or "No Recordable" indications are requested. 4. In order to support the licensee's use of zinc as a mitigation method, NRC staff requires supporting technical basis documents for review. Specifically, NRC staff requests those documents that address the mitigation effectiveness of the zinc addition history at Fort Calhoun Station, Unit 1, at the current levels at 300 ppb-months, and the rate of addition of 6ppb/month. Also, provide projected rates of addition during the period of requested relief and projected accumulated concentration-time levels over the period of requested relief.}} | | 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. The NRC staff requests the licensees basis for not performing a visual, volumetric or inside surface examination of each weld necessary to meet the inspection requirements of 10 CFR 50.55a(g)(6)(ii)(E). If visual, volumetric or inside surface examinations could be performed on each penetration nozzle to meet the current inspection requirements, the NRC staff finds insufficient basis to grant relief under 10 CFR 50.55a(a)(3)(i), as not performing the examination does not provide the same level of assurance as the current inspection requirements. However if there is a hardship, NRC staff requests the licensees basis for relief to not perform the inspection under 10 CFR 50.55a(a)(3)(ii). |
| | : 2. NRC staff requests the following references used in the Westinghouse calculation; numbers 3, 5, 6, 8, 9, 10 and 11. NRC staff will need these references quickly to have sufficient time to perform verification calculations and support the licensees schedule. |
| | : 3. NRC staff requests the 2003, 2008, and 2009 inspection data of welds designated Items 1 and 2 in Table 1 of the August 16, 2010 relief request. NRC staff requests the inspectors summary reports to verify previous inspection results, and verify basis for initial starting flaw size in flaw analysis calculations. For example, reports documentation the inspection stating No Reportable or No Recordable indications are requested. |
| | : 4. In order to support the licensees use of zinc as a mitigation method, NRC staff requires supporting technical basis documents for review. Specifically, NRC staff requests those documents that address the mitigation effectiveness of the zinc addition history at Fort Calhoun Station, Unit 1, at the current levels at 300 ppb-months, and the rate of addition of 6ppb/month. Also, provide projected rates of addition during the period of requested relief and projected accumulated concentration-time levels over the period of requested relief. |
| | ENCLOSURE}} |
Letter Sequence Draft 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)
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
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)
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)
2024-09-12
[Table view] |
Text
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, Omaha Public Power District (the licensee), proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(E) for Fort Calhoun Station, Unit 1. This requirement defines the inservice inspection frequency of visual examination of the reactor vessel hot leg nozzle to safe end welds in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials, and with NRC conditions. The duration of request is for the fourth 10-year ISI 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. The NRC staff requests the licensees basis for not performing a visual, volumetric or inside surface examination of each weld necessary to meet the inspection requirements of 10 CFR 50.55a(g)(6)(ii)(E). If visual, volumetric or inside surface examinations could be performed on each penetration nozzle to meet the current inspection requirements, the NRC staff finds insufficient basis to grant relief under 10 CFR 50.55a(a)(3)(i), as not performing the examination does not provide the same level of assurance as the current inspection requirements. However if there is a hardship, NRC staff requests the licensees basis for relief to not perform the inspection under 10 CFR 50.55a(a)(3)(ii).
- 2. NRC staff requests the following references used in the Westinghouse calculation; numbers 3, 5, 6, 8, 9, 10 and 11. NRC staff will need these references quickly to have sufficient time to perform verification calculations and support the licensees schedule.
- 3. NRC staff requests the 2003, 2008, and 2009 inspection data of welds designated Items 1 and 2 in Table 1 of the August 16, 2010 relief request. NRC staff requests the inspectors summary reports to verify previous inspection results, and verify basis for initial starting flaw size in flaw analysis calculations. For example, reports documentation the inspection stating No Reportable or No Recordable indications are requested.
- 4. In order to support the licensees use of zinc as a mitigation method, NRC staff requires supporting technical basis documents for review. Specifically, NRC staff requests those documents that address the mitigation effectiveness of the zinc addition history at Fort Calhoun Station, Unit 1, at the current levels at 300 ppb-months, and the rate of addition of 6ppb/month. Also, provide projected rates of addition during the period of requested relief and projected accumulated concentration-time levels over the period of requested relief.
ENCLOSURE
