Letter Sequence Request |
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EPID:L-2020-LLR-0123, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR5-04 (Open) |
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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 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[Table view] |
Text
H Nebraska Public Power District "Always there when you need us" 10 CFR 50.55a NLS2020053 August 26, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code,Section XI, Relief Request RRS-04 Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46
Dear Sir or Maclain:
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv), and Nuclear Regulatory Commission (NRC) Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," dated July 28, 2004, Nebraska Public Power District (NPPD) requests NRC approval to use a specific provision of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for Cooper Nuclear Station (CNS). Specifically, NPPD requests approval to use IWA-4540(b) of the 2017 Edition of the ASME B&PV Code.
NPPD requests approval of this request by September 23, 2020, to support the upcoming CNS refueling outage scheduled in September 2020.
No formal licensee commitments are being made in this letter.
Should you have any questions concerning this matter, please contact Linda Dewhirst, Regulatory Affairs & Compliance Manager at (402) 825-5416.
Dent, Jr.
Vice President and Chief Nuclear Officer
/dv
Attachment:
Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv), Relief Request RRS-04
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COOPER NUCLEAR STATION 72676 648A Ave/ P.O. Box 98 / Brownville, NE 68321 http://www.nppd.com
NLS2020053 Page2 of2 cc: Regional Administrator w/ Attachment USNRC - Region IV Senior Project Manager w/ Attachment USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/ Attachment USNRC-CNS NPG Distribution w/o Attachment CNS Records w/ Attachment
NLS2020053 Attachment Page 1 of2 Attachment Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
Relief Request RRS-04 Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv) and the guidance provided in Reference 1, Nebraska Public Power District (NPPD) requests Nuclear Regulatory Commission (NRC) approval to use specific provisions of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for Cooper Nuclear Station (CNS). Specifically, NPPD requests approval to use IWA-4540(b) of the 2017 Edition of the ASME B&PV Code.
ASME Code Component(s) Affected:
All Class 1, 2, and 3 items located in the ASME Section XI boundaries.
Requested Date for Approval:
Approval is requested by September 23, 2020, to support the CNS refueling outage scheduled for September 2020.
Applicable Code Edition and Addenda
INTERVAL ISi INTERVAL PLANT EDITION SCHEDULED INTERVAL START END 2007 Edition, Cooper Nuclear 5 through 2008 04/01/2016 2/28/2026 Station Addenda Proposed Subsequent Code Edition and Addenda (or Portion):
CNS performs repair/replacement activities in accordance with a site program based on an edition of ASME Section XI which, at present, is the 2007 Edition through the 2008 Addenda.
Pursuant to 10 CFR 50.55a(g)(4)(iv), NPPD requests permission to utilize IWA-4540(b) from the 2017 Edition. This subparagraph outlines items that are exempt from pressure testing after repair/replacement activities.
Related Requirements:
10 CFR 50.55a(g)(4)(iv) states:
NLS2020053 Attachment Page 2 of2 "Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met. "
10 CFR 50.55a(b)(2) incorporates by reference Section XI, Division 1, of the ASME B&PV Code 2017 Edition as approved in Reference 3. NPPD is requesting to use IWA-4540(b) of the 2017 Edition of ASME Section XI to utilize the exemptions listed. There are no related requirements or applicable conditions associated with this subparagraph, IWA-4540(b).
Duration of Proposed Request:
The duration of this request will continue for the remainder of the site's current Inservice Inspection interval.
References:
- 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," dated July 28, 2004
- 2. U.S. Nuclear Regulatory Commission Memorandum from D. Rudland (Senior Level Advisor, Division of New and Renewed Licenses) to Anna H. Bradford (Director, Division of New and Renewed Licenses), "Summary of the June 25, 2020, Public Meeting with the Nuclear Industry to Discuss Title 10 of the Code of Federal Regulations Section 50.55a(b)(2)(xxvi) Condition on the Pressure Testing of Class 1, 2, and 3 Mechanical Joints," dated July 8, 2020 (ML20189A286)
- 3. Federal Register, 85 FR 26540, dated May 4, 2020, "American Society of Mechanical Engineers 2015-2017 Code Editions Incorporation by Reference - Final rule" Precedent:
Southern Nuclear letter to the U.S. Nuclear Regulatory Commission, "Vogtle Electric Generating Plant Units 1&2, VEGP-ISI-ALT-04-06, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code,Section XI," dated July 31, 2020 (ML20213C712).