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Category:Code Relief or Alternative
MONTHYEARML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 NLS2020053, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR5-042020-08-26026 August 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR5-04 NLS2019034, 10 CFR 50.55a Relief Request RP5-02 and RI5-02, Revision 22019-06-28028 June 2019 10 CFR 50.55a Relief Request RP5-02 and RI5-02, Revision 2 ML19092A1402019-04-29029 April 2019 Proposed Inservice Inspection Alternative PR5-02 NLS2018029, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-032018-05-16016 May 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-03 NLS2017032, 10 CFR 50.55a Request Number RI-21, Revision 12017-03-29029 March 2017 10 CFR 50.55a Request Number RI-21, Revision 1 ML16034A4792016-02-17017 February 2016 Request for Relief RI5-02, Alternative to Use Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of Specific ASME Code Requirements ML16014A1742016-02-12012 February 2016 Request for Relief RP-01 Through RP-09, RV-01 Through RV-05, and RG-01 Alternative to ASME OM Code Requirements for Inservice Testing for the Fifth Ten-Year Program Interval (CAC Nos. MF5911, MF5913, MF5914, MF5915, MF5916, Etc.) ML16034A3032016-02-12012 February 2016 Request for Relief RC3-01 for Alignment of Inservice Inspection and Containment Inservice Inspection (CAC No. MF6333 ML15134A2422015-05-20020 May 2015 Relief Request RI-08, Revision 0, Relief from Reactor Vessel Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections, for the Fourth 10-Year Inservice Inspection Interval ML12313A1112013-01-22022 January 2013 Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval ML12233A1762012-08-28028 August 2012 Relief Request Nos. RV-07, Revision 0, and RV-01, Revision for Fourth 10-Day Inservice Inspection Interval Regarding Weld Overlay Repair NLS2011085, Relief Request from Certain Inservice Testing Code Requirements2011-08-24024 August 2011 Relief Request from Certain Inservice Testing Code Requirements ML1101205402011-02-18018 February 2011 Relief Request RI-36 for Alternative Weld Overlay Repairs for the Fourth 10-Year Inservice Inspection Interval ML1022204492010-10-0808 October 2010 Request for Relief No. RI-04 for the Fourth 10-Year Inservice Inspection Interval Regarding Inspection of Reactor Vessel Nozzle-to-Vessel Shell Welds ML1009703402010-04-26026 April 2010 Relief, Relief Request No. RV-06 from Certain Inservice Testing Requirements Related to Valves in the Control Rod Drive System, for Fourth 10-Year IST Interval NLS2010013, Request Relief from Certain Inservice Inspection (ISI) Code Requirements2010-02-0505 February 2010 Request Relief from Certain Inservice Inspection (ISI) Code Requirements NLS2010014, Request Relief from Certain Inservice Inspection Code Requirements2010-02-0505 February 2010 Request Relief from Certain Inservice Inspection Code Requirements NLS2009038, Relief Request from Certain Inservice Test Code Requirements, RV-06, Revision 02009-06-18018 June 2009 Relief Request from Certain Inservice Test Code Requirements, RV-06, Revision 0 ML0821304832008-08-15015 August 2008 Request for Relief No. Ri - 35 for Fourth Year Inservice Inspection Interval Regarding Weld Overlay Repair ML0802302882008-02-0606 February 2008 Request for Relief No. RI-29, Revision 1, for Fourth 10-Year Inservice Inspection Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds ML0631802502006-12-0505 December 2006 Request for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Vessel Code, Relief Request No. RI-06, Revision 3, for Weld HMC-BB-1 ML0630402412006-11-0303 November 2006 Correction to and Clarification on Safety Evaluation - Risk Informed Inservice Inspection Program for the Fourth 10-Year Interval; Relief Request No. RI-34 ML0628500512006-10-23023 October 2006 Risk-Informed Inservice Inspection Program for Fourth 10-Year Interval; Relief Request No. RI-34 ML0626202782006-10-13013 October 2006 Fourth 10-year Interval Inservice Inspection Request for Relief No. RI-15, Examination of Peripheral Control Rod Drive Housing Welds ML0625400642006-10-11011 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief RI-02 ML0622602032006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-04 ML0622601952006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-02 ML0622602172006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-06 ML0622602202006-10-0202 October 2006 Fourth 10-Year Interval Inservice Inspection Request for Relief No. PR-11 ML0623405482006-09-0808 September 2006 Relief, Request for Relief No. RI-13 Fourth 10-Year Interval Inservice Inspection ML0405603182004-02-25025 February 2004 Code Relief-RP-06-IST, Core Spray Pump CS-P-B, MB6821 NLS2003120, Inservice Testing Program Relief Request RP-06, Revision 22003-11-25025 November 2003 Inservice Testing Program Relief Request RP-06, Revision 2 ML0309003842003-03-31031 March 2003 Relief, Inservice Testing of All Pumps as Required by Asme/Ansi OMA-1988, Part 6, Paragraph 6.1, MB6822 2022-05-13
[Table view] Category:Letter type:NLS
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023047, Licensee Guarantees of Payment of Deferred Premiums2023-07-26026 July 2023 Licensee Guarantees of Payment of Deferred Premiums NLS2023033, 10 CFR 50.55a Relief Request RC3-022023-06-27027 June 2023 10 CFR 50.55a Relief Request RC3-02 NLS2023039, Preparation and Scheduling of Operator Licensing Examinations2023-06-0101 June 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2023038, Nebraska Public Power District 2022 Financial Report2023-05-22022 May 2023 Nebraska Public Power District 2022 Financial Report NLS2023031, Annual Radiological Environmental Report2023-05-11011 May 2023 Annual Radiological Environmental Report NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023030, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2023027, Annual Report of Individual Exposure Monitoring2023-04-13013 April 2023 Annual Report of Individual Exposure Monitoring NLS2023021, Quality Assurance Program Changes2023-04-10010 April 2023 Quality Assurance Program Changes NLS2023020, Decommissioning Funding2023-03-29029 March 2023 Decommissioning Funding NLS2023019, Property Insurance Coverage2023-03-23023 March 2023 Property Insurance Coverage NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022054, Preparation and Scheduling of Operator Licensing Examinations2023-01-0505 January 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022053, CNS-2022-11 Post Exam Submittal2022-11-22022 November 2022 CNS-2022-11 Post Exam Submittal NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022048, Management Change and Correspondence Update2022-11-0101 November 2022 Management Change and Correspondence Update NLS2022047, Core Operating Limits Report, Cycle 33, Revision 02022-10-14014 October 2022 Core Operating Limits Report, Cycle 33, Revision 0 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses NLS2022035, Evacuation Time Estimate Report for Cooper Nuclear Station2022-08-16016 August 2022 Evacuation Time Estimate Report for Cooper Nuclear Station NLS2022031, Licensee Guarantees of Payment of Deferred Premiums2022-07-19019 July 2022 Licensee Guarantees of Payment of Deferred Premiums NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-06-16016 June 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements NLS2022025, Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring2022-06-0606 June 2022 Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring NLS2022016, Annual Radiological Environmental Report2022-05-10010 May 2022 Annual Radiological Environmental Report NLS2022020, Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report2022-05-0202 May 2022 Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report NLS2022014, Annual Radioactive Effluent Release Report2022-04-27027 April 2022 Annual Radioactive Effluent Release Report NLS2022010, Annual Report of Individual Exposure Monitoring2022-04-0505 April 2022 Annual Report of Individual Exposure Monitoring NLS2022009, Property Insurance Coverage2022-03-23023 March 2022 Property Insurance Coverage NLS2022011, Preparation and Scheduling of Operator Licensing Examinations2022-03-18018 March 2022 Preparation and Scheduling of Operator Licensing Examinations NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 NLS2021067, ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan2021-12-16016 December 2021 ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan NLS2021069, Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-12-15015 December 2021 Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements 2024-01-25
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Nebraska Public Power District"Always there when you need us" 10OCFR 50.55a NLS2010014 February 5, 2010 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555-0001
Subject:
10 CFR 50.55a Request Number RI-04, Revision 0 Cooper Nuclear Station, Docket No. 50-298, DPR-46
Dear Sir or Madam:
The purpose of this letter is to request that the Nuclear Regulatory Commission (NRC) grant Nebraska Public Power District (NPPD) relief from certain inservice inspection (ISI) code requirements for Cooper Nuclear Station (CNS) pursuant to 10 CFR 50.55a.10 CFR 50.55a Request Number RI-04, Revision 0 is applicable to the fourth ten-year ISI interval, which began March 1, 2006. NPPD requests NRC approval of the attached request by February 8, 2011, which represents a, standard twelve-month review period following tlle submittal.
Approval of this request is needed to support examinations scheduled for Refueling Outage 26.RI-04, Revision 0 is contained in the attachment to this letter.If you have any questions concerning this matter, please contact David Van Der Kamp, Licensing Manager, at (402) 825-2904.Sii Brian J. O'Grady Site Vice President/dm Attachment COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone:
(402) 825-3811 / Fax: (402) 825-5211 www.nppd.com 04ý NLS2010014 Page 2 of 2 cc: Regional Administrator w/ attachment USNRC -Region IV Cooper Project Manager w/ attachment USNRC -NRR Project Directorate IV-1 Senior Resident Inspector w/ attachment USNRC -CNS NPG Distribution w/ attachment CNS Records w/ attachment NLS2010014 Attachment Page 1 of 5 1OCFR 50.55a Request Number RI-04, Revision 0 Inspection of Reactor Vessel Nozzle-to-Vessel Shell Welds and Nozzle Inner-Radius Sections Cooper Nuclear Station Docket No. 50-298, DPR-46 Proposed Alternative in Accordance to 10CFR50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--COMPONENT IDENTIFICATION Code Class: Examination Category: Item Number:
Description:
Component Numbers: 1 B-D B3.90, B3.100 Inspection of Reactor Vessel Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Table RI-04-1 Specific Components that Relief is Requested Nozzle-to-Vessel Shell Welds that Relief is Requested ASME Item No. Component ID Item Description B3.90 NVE-BD-N1B 28" Recirculation Outlet B3.90 NVE-BD-N5B 10" Core Spray B3.90 NVE-BD-N6A 6" Instrumentation B3.90 NVE-BD-N8A 5" Jet Pump Instrumentation B3.90 NVE-BD-N3B 24" Main Steam B3.90 NVE-BD-N3C 24" Main Steam B3.90 NVE-BD-N3D 24" Main Steam Nozzle Inner Radius Sections that Relief is Requested ASME Item No. Component ID Item Description B3.100 NVIR-BD-N1B 28" Recirculation Outlet B3.100 NVIR-BD-N5B 10" Core Spray B3. 100 NVIR-BD-N6A 6" Instrumentation B3.100 NVIR-BD-N8A 5" Jet Pump Instrumentation B3. 100 NVIR-BD-N3B 24" Main Steam B3. 100 NVIR-BD-N3C 24" Main Steam B3.100 NVIR-BD-N3D 24" Main Steam NLS2010014 Attachment Page 2 of 5 Applicable Code Edition and Addenda The applicable Code Edition and Addenda for Cooper Nuclear Station (CNS) is American Society of Mechanical Engineers (ASME) Code Section XI, 2001 Edition, 2003 Addenda.Additionally for ultrasonic examinations,Section XI, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems," is implemented as required and subject to the limitations and modifications specified in lOCFR50.55a(b)(2)(xv).
Applicable Code Requirement ASME Section XI Code Class 1 nozzle-to-vessel shell weld and nozzle inner radius section examination requirements are provided in Subsection IWB, Table IWB-2500-1 "Examination Category B-D, Full Penetration Welded Nozzles in Vessels -Inspection Program B." Items B3.90 and B3. 100 require a volumetric examination of all the Reactor Vessel nozzle-to-vessel welds and associated nozzle inner radius sections, respectively.
Reason for Request The identified nozzles (see Table RI-04-1) are scheduled for examination prior to the end of the current inspection interval.
The proposed alternative provides an acceptable level of quality and safety, and the reduction in scope could provide a dose savings of as much as 15.5 Radiation Equivalent Man over the remainder of the interval.Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested from performing the required examinations on 100% of the identified nozzle assemblies (see Table below). As an alternative, for all welds and nozzle inner radius sections identified in Table RI-04-1, CNS proposes to examine a minimum of 25% of the nozzle-to-vessel shell welds and nozzle inner radius sections to include at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702 (Reference 3). For the nozzle assemblies identified this would mean one from each of the groups identified below: Table RI-04-2 Total Group/Component ID Number No. to be Examined Nozzles Recirculation Outlet (NI) 2 1 Recirculation Inlet (N2, does not pass criteria) 10 10 Main Steam (N3) 4 1 Feedwater (N4, not allowed by Code Case) 4 4 Core Spray (N5) 2 1 Head Instrument (N6) 2 1 Head Vent (N7) 1 1 NLS2010014 Attachment Page 3 of 5 Table RI-04-2 Total Group/Component ID Number No. to be Examined Nozzles Jet Pump (N8) 2 1 Control Rod Drive Return (N9, not allowed by Code Case)Code Case N-702 stipulates that Visual Test (VT) VT-I examination may be used in lieu of the volumetric examination for the nozzle inner radius sections (Item No. B3.100). CNS currently credits the enhanced magnification VT-I examination of the nozzle inner radius sections in accordance to Code Case N-648-1 (Reference
- 4) subject to the conditions placed upon the use of that Code Case by Regulatory Guide 1.147. The specific aspect of utilizing VT-I visual examinations as allowed by Code Case N-702 is not part of this request. Volumetric examinations of the nozzle inner radius sections of the selected core spray and jet pump instrumentation nozzles will still be performed, as their nozzle inner radius sections are not fully accessible from inside the vessel for enhanced magnification VT-I examination.
Electric Power Research Institute (EPRI) Technical Report 1003557 (Reference 1), "BWRVIP-108: Boiling Water Reactor Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," provides the basis for Code Case N-702. The evaluation found that failure probabilities at the nozzle blend radius region and nozzle-to-vessel shell welds due to a Low Temperature Overpressure event are very low (i.e., <1 x 10-6 for 40 years) with or without inservice inspection.
The report concludes that inspection of 25% of each nozzle type is technically justified.
The Nuclear Regulatory Commission issued a Safety Evaluation Report (SER) dated December 19, 2007 (Reference
- 2) approving the use of BWRVIP- 108 as a basis for using Code Case N-702. In the SER, Section 5.0 "Plant Specific Applicability" states that licensees who plan to request relief from the ASME Code,Section XI requirements for reactor pressure vessel (RPV)nozzle-to vessel shell welds and nozzle inner radius sections may reference the BWRVIP- 108 report as the technical basis for the use of ASME Code Case N-702 as an alternative.
However, each licensee should demonstrate the plant-specific applicability for the BWRVIP- 108 report to its units in the relief request by showing that all the general and nozzle specific criteria are satisfied:
Maximum RPV Heatup/Cooldown Rate (1) the maximum RPV heatup/cooldown rate is limited to less than 1 15'F per hour.This criterion is met by adherence to CNS Technical Specifications Surveillance Requirement 3.4.9.1 which requires verification that the Reactor Coolant System heatup and cooldown rates are <I00°F when averaged over a one hour period.
NLS2010014 Attachment Page 4 of 5 For recirculation inlet N2 nozzles, Criteria (2) and (3) of the SER apply: (2) (pr/t)/Ci-Rpv<
1.15 where: p = RPV normal operating pressure (p= 1020 psig per CNS Technical Specifications 3.4.10 for Reactor Steam Dome Pressure)r = RPV inner radius (r = 110.375 in.)t = RPV wall thickness (t = 6.875 in.)Ci-RPV = 19332 (based on the BWRVIP-108 recirculation inlet nozzle/RPV finite element method (FEM) model)The CNS result is 0.847, which is less than 1.15, therefore the CNS N2 nozzles meet criteria 2.(3) [p(ro2 +ri 2) / (ro 2-ri 2)] / Ci-NOZZLE
< 1.15 where: p = RPV normal operating pressure (p = 1020 psig)r0 = nozzle outer radius (ro = 10.219 in.)ri = nozzle inner radius (ri= 6.188 in.)Ci-NOZZLE
= 1637 based on the BWRVIP-108 recirculation inlet nozzle/RPV FEM model)The calculation result is 1.344, which is greater than 1.15, therefore the CNS N2 nozzles do not meet Criteria 3.For recirculation outlet NI nozzles, Criteria (4) and (5) of the SER apply: (4) (pr/t)/Co.yv<
1.15 where: p = RPV normal operating pressure (p = 1020 psig)r = RPV inner radius (r = 110.375 in.)t = RPV wall thickness (t = 6.875 in.)Co-RPV = 16171 (based on the BWRVIP- 108 recirculation outlet nozzle/RPV FEM model)The calculation result is 1.013, which is less than 1.15, therefore the CNS NI nozzles meet Criteria 4.(5) [p(r 0 2 +r, 2)/ (r 0 2_-r 2)] / Co-NOZZLE
< 1.15 where: p = RPV normal operating pressure (p = 1020 psig)r0 = nozzle outer radius (ro = 21.656 in.)ri = nozzle inner radius (ri= 12.875 in.)Co-NOZZLE
= 1977 (based on the BWRVIP- 108 recirculation outlet nozzle/RPV FEM model)The calculation result is 1.080, which is less than 1.15 therefore the CNS NI nozzles meet Criteria 5.Based upon the above information, all RPV nozzle-to-vessel shell welds and nozzle inner radius sections, with the exception of the Recirculation Inlet N2 Nozzles, meet the criteria.
Therefore, NLS2010014 Attachment Page 5 of 5 Code Case N-702 is applicable.
Since the Recirculation inlet nozzles do not meet all of the criteria, Code Case N-702 will not be applied to these nozzles.Therefore, use of Code Case N-702 provides an acceptable level of quality and safety pursuant to 10 CFR 50.55a(a)(3)(i) for all RPV nozzle-to-vessel shell welds and nozzle inner radius sections, with the exception of the Recirculation Inlet Nozzles.Duration of Proposed Alternative The proposed alternative is for the fourth ten-year interval of the Inservice Inspection Program for CNS that started on March 1, 2006 and ends in 2014, at the end of the current license.References
- 1. EPRI Technical Report 1003557, "BWRVIP-108:
Boiling Water Reactor Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," October 2002.2. Safety Evaluation of Proprietary EPRI Report, "BWR Vessel and Internals Project, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius (BWRVIP-108)," December 19, 2007.3. ASME Section XI Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell WeldsSection XI, Division 1," February 20, 2004.4. ASME Section XI Code Case N-648-1, "Alternative Requirements for Inner Radius Examination of Class I Reactor Vessel NozzlesSection XI, Division 1," September 7, 2001.
ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© 4 ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS©4 Correspondence Number: NLS2010014 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document.
Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments.
Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
'COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None N/A N/A t I f I I 4 PROCEDURE 0.42 REVISION 24 PAGE 18 OF 25