Letter Sequence RAI |
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EPID:L-2017-LRR-0065, Inservice Inspection Program Fifth Ten-Year Interval 10 CFR 50.55a Relief Requests (Open) |
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Category:E-Mail
MONTHYEARML24157A0122024-06-0404 June 2024 NRR E-mail Capture - Cooper - Acceptance Review - License Amendment Request (LAR) to Revise TS Table 3.3.2.1-1 Minimum Critical Power Ratio (MCPR) ML24094A2462024-04-0303 April 2024 NRR E-mail Capture - Cooper Nuclear Station - RAI Emergency LAR Turbine Stop Valve Limit Switch TS 3.3.1.1 ML24081A0372024-03-21021 March 2024 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of LAR to Modify Allowable Value for HPCI Low Flow ML24124A0592024-02-22022 February 2024 May 2024 Emergency Preparedness Exercise Inspection - Request for Information ML24032A2382024-02-0101 February 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML24010A1172024-01-10010 January 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML23352A2472023-12-18018 December 2023 NRR E-mail Capture - Cooper Nuclear Station - Relief Request RC3-02 Drywell Head Inspection RAI Issuance ML23339A0892023-12-0505 December 2023 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of CLIIP LAR to Adopt TSTF-374 ML23318A5252023-11-0909 November 2023 NRR E-mail Capture - Cooper Nuclear Station - Relief Request RC3-02 Audit Agenda and Questions ML23257A2192023-09-14014 September 2023 NRR E-mail Capture - Cooper - Final RAI LAR to Adopt TSTF-551, Revision 3 ML23207A1742023-07-26026 July 2023 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of Relief Request RC3-02 Drywell Head Bolting ISI ML23153A1062023-06-0202 June 2023 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-551 ML23150A2492023-05-26026 May 2023 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-580 ML22192A0502022-07-0808 July 2022 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-554 ML22228A2572022-05-12012 May 2022 11 CNS-2022-06 Public Documents ML22055B1512022-02-22022 February 2022 CNS EP Exercise Inspection May 2022 RFI ML22010A2632022-01-10010 January 2022 NRR E-mail Capture - Cooper - Final RAI Relief Request RR5-01 Revision 1 ML21321A3742021-11-10010 November 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RI5-02 Revision 3 ML21258A2632021-09-15015 September 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RS-01 ML21253A0312021-09-0909 September 2021 Email 9-9-2021 - Request for Information - In-Office Inspection of Recent Cooper E-Plan Changes ML21232A2102021-08-20020 August 2021 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request Exception to Primary Containment Leakage Rate Program Requirement ML21203A3072021-07-21021 July 2021 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of Relief Request RI5-02 Revision 3 ML21202A1372021-07-20020 July 2021 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of Relief Request RR5-01 Revision 1 ML21165A0062021-06-11011 June 2021 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582 ML21109A2222021-04-15015 April 2021 Email with RFI Document for CNS PIR 2021012 ML21089A1682021-03-30030 March 2021 Email 3-30-2021-RFI for CNS EP Exercise Inspection (Week of 5-24-2021) ML20315A3922020-11-10010 November 2020 Email 11-10-2020 - Cooper EP Prog Insp RFI ML20260H4812020-09-0909 September 2020 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of Request to Use a Provision of a Later Edition of the ASME B&PV Code Section XI, Relief Request RR5-04 (L-2020-LLR-0123) ML20203M3692020-07-21021 July 2020 NRR E-mail Capture - Cooper - Final RAI License Amendment Request for Approval of EAL Scheme Change (EPID L-LLA-2020-0028) ML20175A5692020-06-22022 June 2020 (6-22-20 FEMA Hq Email) Cooper EP Biennial Exercise Exemption Request ML20139A0222020-05-15015 May 2020 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529 ML20126G4242020-05-0505 May 2020 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-566, ML20098G0872020-04-0707 April 2020 CNS Req RFI for NRC In-Office Inspection of Eplan EAL Changes ML20071G3522020-03-11011 March 2020 NRR E-mail Capture - Cooper Nuclear Station - Acceptance of Requested Licensing Action LAR to Adopt EAL Scheme Pursuant to NEI 99-01, Rev. 6 ML19269C1662019-09-26026 September 2019 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of LAR for Exception from Certain Leak Testing Interval Requirements of the Primary Containment Leakage Rate Testing Program (L-2019-LLA-0179) ML19218A3732019-08-0505 August 2019 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of Relief Requests RP5-02 and RI5-02 Rev. 2 (EPID Nos. L-2019-LLR-0063 and -0064) ML19200A0442019-07-19019 July 2019 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-564, Revision 2 ML19210D4342019-07-11011 July 2019 Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 ML19190A3042019-07-0808 July 2019 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-447, Revision 1 ML19190A0432019-06-28028 June 2019 Discusses Proprietary Information for Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19256D3372019-06-21021 June 2019 (050-00298) MC&A Wishlist 2019-405 ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19092A4812019-04-0202 April 2019 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3 ML18311A3192018-11-0606 November 2018 NRR E-mail Capture - Cooper Nuclear Station - Verbal Authorization of Relief Request PR5-02 ML18311A1862018-11-0505 November 2018 Email (11-5-18) RR RFI Responses for Review ML18198A5412018-07-17017 July 2018 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1 ML18166A1882018-06-14014 June 2018 NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of License Amendment Request to Revise TS Safety Limit Minimum Critical Power Ratio ML18171A1612018-06-12012 June 2018 NRR E-mail Capture - (External_Sender) TSTF-542 Implementation Change Request NRC-2017-0218, NRR E-mail Capture - (External Sender) Opportunity to Review and Comment on NRC Information Collection (10 CFR Part 73) - Response2018-05-0909 May 2018 NRR E-mail Capture - (External_Sender) Opportunity to Review and Comment on NRC Information Collection (10 CFR Part 73) - Response ML18241A3822018-03-23023 March 2018 CNS Email to Beaulieu, George, Kumana: Response to CNS Fan Coil Unit Questions 2024-06-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24094A2462024-04-0303 April 2024 NRR E-mail Capture - Cooper Nuclear Station - RAI Emergency LAR Turbine Stop Valve Limit Switch TS 3.3.1.1 ML24032A2382024-02-0101 February 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML24010A1172024-01-10010 January 2024 NRR E-mail Capture - Cooper Nuclear Station - LAR Dfo Tank Inspection RAI Issuance ML24010A0902024-01-0404 January 2024 RAI - 10120-R1 - Final Dfo Tank Inspections LAR ML23352A2472023-12-18018 December 2023 NRR E-mail Capture - Cooper Nuclear Station - Relief Request RC3-02 Drywell Head Inspection RAI Issuance ML23257A2192023-09-14014 September 2023 NRR E-mail Capture - Cooper - Final RAI LAR to Adopt TSTF-551, Revision 3 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information ML22208A0642022-07-26026 July 2022 Notification of Inspection and Request for Information for NRC Inspection Report 05000298/2022004 ML22179A3152022-06-28028 June 2022 Notification of Post-Approval Site Inspection for License Renewal (Phase 4) (NRC Inspection Report 05000298/2022011) and Request for Information ML22010A2632022-01-10010 January 2022 NRR E-mail Capture - Cooper - Final RAI Relief Request RR5-01 Revision 1 ML21321A3742021-11-10010 November 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RI5-02 Revision 3 ML21258A2632021-09-15015 September 2021 NRR E-mail Capture - Cooper - Final RAI Alternative Request RS-01 ML21109A2222021-04-15015 April 2021 Email with RFI Document for CNS PIR 2021012 ML21026A3112021-01-27027 January 2021 Notification of NRC Design Bases Assurance Inspection (Team) (NRC Inspection Report 05000298/2021010) and Initial Request for Information ML20315A3922020-11-10010 November 2020 Email 11-10-2020 - Cooper EP Prog Insp RFI ML20203M3692020-07-21021 July 2020 NRR E-mail Capture - Cooper - Final RAI License Amendment Request for Approval of EAL Scheme Change (EPID L-LLA-2020-0028) ML18306A5582018-10-30030 October 2018 Notification of Cyber Security Inspection(Nrc Inspection Report 05000298/2019410) and Request for Information ML18060A0272018-02-28028 February 2018 Enclosurequest for Additional Information (Letter to J. Shaw Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station ISFSI) ML18037B0002018-02-0606 February 2018 NRR E-mail Capture - Cooper Nuclear Station - Final RAI Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066) ML18025C0042018-01-25025 January 2018 Notification of NRC Design Bases Assurance Inspection (Teams) (05000298/2018011) and Initial Request for Information ML18024A3752018-01-24024 January 2018 NRR E-mail Capture - Cooper Nuclear Station - Final RAI LAR to Adopt TSTF-542 (CAC MG0138; EPID L-2017-LLA-0290) IR 05000298/20170032017-11-13013 November 2017 NRC Integrated Inspection Report 05000298/2017003 and Independent Spent Fuel Storage Installation Inspection Report 07200066/2017001 ML17177A2432017-06-26026 June 2017 Notification of NRC Design Bases Assurance Inspection (Programs) (05000298/2017007) and Initial Request for Information ML17024A3292016-12-15015 December 2016 NRR E-mail Capture - Rec 2.1 Seismic: Cooper'S SFP Evaluation ML16335A0152016-11-29029 November 2016 NRR E-mail Capture - Cooper Nuclear Station - Formal Request for Additional Information Concerning License Amendment Request to Adopt TSTF-425 Revision 3 ML16112A2732016-04-21021 April 2016 Notification of NRC Triennial Fire Protection Baseline Inspection (05000298/2016008) and Request for Information ML15107A2542015-05-0404 May 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML15051A4872015-02-20020 February 2015 Notification of NRC Component Design Bases Inspection 05000298/2015007 and Initial Request for Information ML13323A1052013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13256A0822013-09-12012 September 2013 Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13246A3482013-08-29029 August 2013 Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/12 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NLS2013082, Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding2013-08-22022 August 2013 Letter Requesting Information from the United States Army Corps of Engineers to Provide Response to March 12, 2012 Letter Regarding Enclosure 2, Recommendation 2.1, Flooding ML13155A0112013-06-0303 June 2013 Request for Additional Information Email, 2013 Decommissioning Funding Status Report ML13133A0802013-05-24024 May 2013 (Redacted) - Request for Additional Information, Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts ML13144A5202013-05-24024 May 2013 Request for Additional Information Email, Decommissioning Funding Status Report ML13095A1602013-04-0404 April 2013 Email, Draft Request for Additional Information - Review of License Renewal Commitment NLS2009100-1 - Core Rim Plate Bolts ML13059A3452013-03-0808 March 2013 Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML13053A3422013-02-22022 February 2013 E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML12338A2642012-12-0303 December 2012 Email, Round 3, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and SRs ML12312A2812012-11-14014 November 2012 Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12283A4002012-10-0909 October 2012 Email, Draft Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12251A0582012-09-0606 September 2012 Request for Additional Information, License Amendment Request, Round 2, Revise Technical Specifications to Implement a 24-Month Fuel Cycle and Adopt TSTF-493, Revision 4, Option a ML12235A2522012-09-0505 September 2012 Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML12205A2162012-08-10010 August 2012 Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML1217400512012-06-21021 June 2012 List of Questions for Supplement to Complete Acceptance Review, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML12159A2992012-06-11011 June 2012 Request for Additional Information, 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 ML12157A5412012-06-11011 June 2012 Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program ML12153A0642012-05-31031 May 2012 Notification of Inspection (NRC Inspection Report 05000298/2012005) and Request for Information ML1213905092012-05-18018 May 2012 Email, Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval 2024-04-03
[Table view] |
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NRR-DMPSPEm Resource From: Wengert, Thomas Sent: Tuesday, February 06, 2018 12:04 PM To: Shaw, Jim D.
Cc: Van Der Kamp, David W.; Pascarelli, Robert
Subject:
Cooper Nuclear Station - Final RAI RE: Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066)
Attachments: Cooper RR5-02 and RR5-03 Final RAI.pdf On January 22, 2018, the U.S. Nuclear Regulatory Commission (NRC) staff sent Nebraska Public Power District (NPPD or licensee) the draft Request for Additional Information (RAI) identified below. This RAI relates to the licensees request for relief from certain inservice inspection requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI at Cooper Nuclear Station (CNS), as described below On January 29, 2018, the NRC staff and the licensee held a conference call to clarify the request. A publicly available version of this final RAI (attached with Draft removed and corrections to minor typographical errors) will be placed in the NRCs Agencywide Documents Access and Management System (ADAMS).
Subsequently, the licensee agreed to respond to this request within 30 days of the date of this email (i.e., by March 8, 2018).
Note that the NRC staff is still reviewing Relief Requests RI-01, RI-02, and RI-03, which were also included in the August 17, 2017 letter. We will notify you at a later date if additional information is needed for those reviews.
Tom Wengert Project Manager - Cooper Nuclear Station NRR/DORL/LPL4 (301) 415-4037 From: Wengert, Thomas Sent: Monday, January 22, 2018 3:02 PM To: Shaw, Jim D.
Cc: Van Der Kamp, David W. ; Pascarelli, Robert
Subject:
Cooper Nuclear Station - Draft RAI RE: Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066)
By letter dated August 17, 2017 (Agencywide Documents and Access Management System (ADAMS)
Accession No. ML17241A048), Nebraska Public Power District (the licensee) requested relief from certain inservice inspection requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI at Cooper Nuclear Station (CNS). The licensee submitted Relief Requests RR5-02 and RR5-03 for U.S. Nuclear Regulatory Commission (NRC) approval to use to implement repairs to certain degraded CNS piping using ASME Code Case N-513-4.
RR-02 applies to all ASME,Section XI, Class 2 and 3 piping components that meet certain operational and configuration limitations of the Code Case. RR-03 applies to all ASME,Section XI, Class 3 residual heat removal service water booster (RHRSWB) system piping with a maximum operating pressure less than or equal to 490 pounds per square inch - gauge (psig) and a maximum operating temperature less than 200 degrees Fahrenheit (F).
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information, as described in the attached request for additional information (RAI), is required for the staff to complete its review of these 1
relief requests. This RAI is identified as draft at this time to confirm your understanding of the information that the NRC staff needs to complete the evaluations. If the request for information is understood, please respond to this request for additional information within 30 days of the date of this request. Please contact me if you would like to set up a conference call to clarify this request for information.
Note that the NRC staff is still reviewing Relief Requests RI-01, RI-02, and RI-03, which were also included in the August 17, 2017 letter. We will notify you later if additional information is needed for those reviews.
Tom Wengert Project Manager - Cooper Nuclear Station NRR/DORL/LPL4 (301) 415-4037 2
Hearing Identifier: NRR_DMPS Email Number: 146 Mail Envelope Properties (Thomas.Wengert@nrc.gov20180206120400)
Subject:
Cooper Nuclear Station - Final RAI RE: Relief Requests RR-02 and RR-03 (EPIDs L-2017-LRR-065 and -066)
Sent Date: 2/6/2018 12:04:00 PM Received Date: 2/6/2018 12:04:00 PM From: Wengert, Thomas Created By: Thomas.Wengert@nrc.gov Recipients:
"Van Der Kamp, David W." <dwvande@nppd.com>
Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>
Tracking Status: None "Shaw, Jim D." <jdshaw@nppd.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3442 2/6/2018 12:04:00 PM Cooper RR5-02 and RR5-03 Final RAI.pdf 135373 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION (RAI)
RELIEF REQUESTS RR5-02 AND RR5-03 APPLICATION OF ASME CODE CASE N-513-4 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated August 17, 2017 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML17241A048), Nebraska Public Power District (the licensee) requested relief from certain inservice inspection requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI at Cooper Nuclear Station (CNS). The licensee submitted Relief Requests RR5-02 and RR5-03 for U.S.
Nuclear Regulatory Commission (NRC) approval to repair certain degraded CNS piping using ASME Code Case N-513-4. RR5-02 applies to all ASME,Section XI, Class 2 and 3 piping components that meet certain operational and configuration limitations of the Code Case.
RR5-03 applies to all ASME,Section XI, Class 3 residual heat removal service water booster (RHRSWB) system piping with a maximum operating pressure less than or equal to 490 pounds per square inch - gauge (psig) and a maximum operating temperature less than 200 degrees Fahrenheit (F). To complete its review, the NRC staff requests the following additional information.
RAIs for Relief Request RR5-02 RAI RR5-02-1 Code Case N-513-4, Paragraph 5(a) requires, in part, that A sample size of at least five of the most susceptible and accessible locations, or, if fewer than five, all susceptible and accessible locations shall be examined within 30 days of detecting the flaw Paragraph 5(b) requires that When a flaw is detected, an additional sample of the same size as defined in paragraph 5(a) shall be examined On Page 61 of the attachment to the August 17, 2017 submittal, the licensee states the following, in part:
CNS will follow all requirements of Code Case N-513-4. With regard to augmented examination process as described in Section 5 of the Code Case, a sample size of at least five of the most susceptible and accessible locations shall be examined within 30 days of detecting the original flaw. The intent of this requirement is to identify the extent of condition that exists within similar system piping that could also be susceptible to similar flaws.
Specific to the CNS SW Class 3 piping, if a single flaw is identified within 30 days of scheduled volumetric examinations, CNS may take credit for any previous examination if performed prior to identification of the flaw, as a part of the same set of inspections. Credit will be taken for these examinations to
2 meet the requirements of Code Case N-513-4 paragraph 5(a), provided that the examination meets the inspection method requirements of the Code Case and was performed on SW Class 3 piping components, the inspected segments are of the same design and operation, and the inspected segments are considered to be of the most susceptible and accessible locations determined from the engineering evaluation. This is consistent with the augmented examination approach in [Generic Letter (GL)] 90-05 as well as previous NRC approved versions of N-513.
In the submittal the licensee appears to convey that if a single flaw is identified, the licensee will examine a fewer number of pipe locations than required by paragraphs 5(a) and 5(b) of Code Case N-513-4, because the licensee proposes to take credit for examinations performed within 30 days prior to identification of the flaw. The NRC staffs understanding of paragraph 5(a) is that within 30 days after a flaw is identified, augmented examinations must be performed. The Code Case does not imply that credit may be taken for previously performed examinations. In addition, GL 90-05, does not imply that previously performed examinations may be credited toward augmented examinations performed after a flaw is identified.
(a) Clarify whether the proposed use of Code Case N-513-4 will examine the same number of pipe locations as required by paragraph 5(a). If not, provide justification.
(b) Clarify whether the above proposed use of Code Case N-513-4 will meet paragraph 5(b). If not, provide justification.
RAI RR5-02-2 On Page 61 of the attachment to the August 17, 2017 submittal, the licensee states the following, in part:
NPPD will apply ASME Code Case N-513-4 in its entirety along with RG 1.147, Revision 17 (or later NRC defined revision as applicable) for evaluation of Class 2 and 3 piping flaws at CNS if Code repairs cannot reasonably be completed within the Technical Specifications required time limit.
(underline added)
The NRC staff notes that Regulatory Guide (RG) 1.147, Revision 17 does not reference Code Case N-513-4. Code Case N-513-3 is listed in RG 1.147 with one condition. However, this condition has been addressed in Code Case N-513-4. Clarify if the intent of the statement above is that when Code Case N-513-4 is listed in a subsequent revision of RG 1.147, the licensee intends to utilize the Code Case in accordance with RG 1.147, including any conditions that may be placed on the Code Case by the NRC.
RAIs for Relief Request RR5-03 RAI RR5-03-1 In the ASME Code Component(s) Affected Section of the relief request on page 63 of the attachment to the August 17, 2017 submittal, the licensee discusses the RHR and RHRSWB systems. However, in other sections of the relief request, the licensee discusses only the RHRSWB piping. Confirm that the relief request covers only RHRSWB piping, not RHR piping.
3 RAI RR5-03-2 Provide the following:
(a) All RHRSWB pipe outside diameters (or nominal pipe sizes) and schedules (i.e., wall thicknesses),
(b) Specific maximum operating pressures in the various RHRSWB pipe segments with associated pipe outside diameters and thicknesses, and (c) RHRSWB piping isometric drawings showing the pipe support locations and piping routing.
RAI RR5-03-3 Code Case N-513-4, Paragraph 5(a) requires, in part, that A sample size of at least five of the most susceptible and accessible locations, or, if fewer than five, all susceptible and accessible locations shall be examined within 30 days of detecting the flaw Paragraph 5(b) requires that When a flaw is detected, an additional sample of the same size as defined in [paragraph 5](a) shall be examined On Page 67 of the attachment to the August 17, 2017 submittal, the licensee proposes the following two deviations from Code Case N-513-4:
Deviation No. 1: If a single flaw is identified during scheduled volumetric examinations, CNS may take credit for any previous examination if performed within 30 days prior to identification of the flaw, as a part of the same set of inspections. Credit will be taken for these examinations to meet the requirements of Code Case N-513-4 paragraph 5(a).
This exception appears to convey that if a single flaw is identified, the licensee will examine a fewer number of pipe locations than required by paragraphs 5(a) and 5(b) of Code Case N-513-4, because the licensee proposes to take credit for examinations performed within 30 days prior to identification of the flaw.
(a) Clarify whether the proposed deviation will require the licensee to examine the same number of pipe locations as required by paragraph 5(a). (i.e., if a flaw is detected, a sample size of at least five of the most susceptible and accessible locations, or, if fewer than five, all susceptible and accessible locations shall be examined within 30 days of detecting the flaw.) If not, provide justification.
(b) Clarify whether the above proposed deviation will meet the requirement of paragraph 5(b). If not, provide justification.
Deviation No. 2. The licensee proposes to increase the number of augmented examinations from 5 to 10 pipe locations.
(c) This is an enhancement and improvement to the sample size as specified in paragraph 5(a) of Code Case N-513-4, however, this may introduce unintended requirements. For example, if a flaw is detected, paragraph 5(b) requires the licensee to increase the number of additional samples of the same size, i.e., from a sample of 10 pipe locations
4 to 20 locations. Clarify if this is the intent of Deviation No. 2. If not, explain the intent of Deviation No. 2 with respect to the requirements of paragraphs 5(a) and 5(b).
RAI RR5-03-4 Page 67 of the attachment to the August 17, 2017 submittal states that, if the Code Case is applied to a leaking flaw in the RHRSWB system, for leakage greater than 5 gallons per minute (gpm), the leakage will be stopped by use of a mechanical clamping device.
(a) A leak rate of 5 gpm is not insignificant because it may cause flooding in a room if the sump drainage system does not have adequate capacity to drain the fluid, may affect safety-related components, and may impact personnel safety. Discuss the actions that the licensee will take before the leakage reaches 5 gpm.
(b) Provide the allowable leakage rate beyond which the relief request will no longer be valid.
(c) Discuss the minimum leakage rate that would prevent the RHRSWB from performing its intended function, the flow rate in the RHRSWB pipe that is needed to satisfy its designed function, and the average normal flow rate in the RHRSWB piping.
(d) Discuss how the leakage rate in the RHRSWB piping can be detected and how the operators in the control room are notified. Discuss the minimum leakage rate that can be detected.
RAI RR5-03-5 The Duration of Proposed Alternative Section of the relief request on Page 68 of the attachment to the August 17, 2017 submittal states, in part, that A Section XI compliant repair/replacement will be completed prior to exceeding the next scheduled refueling outage or allowable flaw size, whichever comes first. The NRC staff notes that Table 4, Allowable Axial and Circumferential Flaw Size Comparison, in Enclosure 2, Attachment 3 of the submittal provides allowable flaw sizes. However, it appears that the allowable flaw size calculations are generic and not specific to CNS.
(a) Provide the plant-specific allowable flaw sizes and associated calculations for the RHRSWB piping.
(b) Discuss why the allowable leakage rate is not identified as a criterion to determine repair/replacement in the above statement as a condition on the use of the relief request.