NRR E-mail Capture - Duke Energy Fleet Request for an Alternative to Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. 9513-9521)ML17109A239 |
Person / Time |
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Site: |
Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire |
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Issue date: |
04/19/2017 |
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From: |
Dennis Galvin Plant Licensing Branch II |
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To: |
Zaremba A Duke Energy Corp |
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References |
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MF9513, MF9514, MF9515, MF9516, MF9517, MF9518, MF9519, MF9520, MF9521 |
Download: ML17109A239 (3) |
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Category:E-Mail
MONTHYEARML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML24029A1132024-01-16016 January 2024 Notification of Inspection and Request for Information (Email) ML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23349A0272023-12-15015 December 2023 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 5.5.2 ML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) ML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 ML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards ML23267A0032023-09-21021 September 2023 RP Inspection Document Request ML23262B4502023-09-19019 September 2023 NRR E-mail Capture - H. B. Robinson Steam Electric Plant, Unit 2 - Acceptance of License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures Based on Leak-Before-Break Methodology ML23248A2612023-09-0505 September 2023 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise the 10 CFR 50.69 Categorization Process ML23269A0412023-08-22022 August 2023 Code Case N-752 Audit; August 22, 2023, E-mail Providing Additional Information Regarding Design and Quality Program Requirements ML23220A2342023-08-0808 August 2023 NRR E-mail Capture - Robinson, Unit 2 - Acceptance Review Results for Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23202A0652023-07-19019 July 2023 NRR E-mail Capture - Request for Additional Information - Brunswick Steam Electric Plant, Units 1 and 2, Torus Liner Inspection Alternative Request (L-2022-LLR-0089) ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23192A0552023-07-11011 July 2023 Relief Request Later Edition of ASME Code for ISI ML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications ML23177A1992023-06-26026 June 2023 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-23-0005 - LAR to Align Certain TSs with ISTS (L-2023-LLA-0078) ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23144A0862023-05-24024 May 2023 Acceptance of Requested Licensing Action Proposed Relief Request (RA-23-0018) to Use ASME Code Case 853 ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23131A4192023-05-10010 May 2023 003 Radiation Safety Baseline Inspection Information Request ML23125A1452023-05-0505 May 2023 Change in Estimated Review Schedule and Level of Effort for Proposed Alternative to Use Code Case N-752 ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23095A0052023-04-0404 April 2023 002 Radiation Safety Baseline Inspection Information Request ML23087A0282023-03-27027 March 2023 Acceptance of Requested Licensing Action Amendment TSTF-505 ML23087A2492023-03-27027 March 2023 50.69 Acceptance Email ML23086C0362023-03-27027 March 2023 Request for Additional Information Steam Generator Tube Inspection Report (03R31) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23080A1892023-03-20020 March 2023 RP Inspection Document Request ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23065A0942023-03-0606 March 2023 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-22-0081 - LAR to Address Administrative Changes to the Operating License and Technical Specifications (L-2023-LLA-0020) ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 ML23030B9032023-01-30030 January 2023 Formal Release of RAIs for McGuire Unit 1, Relief Request Impractical RPV Rx Coolant System Welds, Due March 1, 2023 (Email) ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML23031A1552023-01-17017 January 2023 1/17/2023 Email from John Moses, Deputy Director, Division of Rulemaking, Environmental, and Financial Support, to Diane Curran, Counsel to Beyond Nuclear and the Sierra Club, Request for Extension of Scoping Comment Period for Oconee EIS ML23017A2232023-01-13013 January 2023 Request for Additional Information (RAI) Issuance for McGuire Unit 1 Steam Generator Tube Inspection Report (Email) ML23011A0152023-01-11011 January 2023 NRR E-mail Capture - Request for Additional Information to Duke'S Request for Robinson to Add Feedwater Isolation Function to TS 3.3.2 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23006A1892023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 ML23006A0642023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22294A0812022-10-21021 October 2022 Nrc/Duke Steam Generator Inspection Call for November 8, 2022 ML22291A4602022-10-17017 October 2022 Relief Request Impractical RPV and Rx Coolant Sys. Welds ML22285A1552022-10-12012 October 2022 NRR E-mail Capture - H. B. Robinson, Unit 2 - Acceptance of License Amendment Request Regarding the Addition of Feedwater Isolation Function to TS 3.3.2 and Removal of Obsolete Content from TS 2.1.1.1 and TS 5.6.5.b 2024-01-25
[Table view] |
Text
NRR-PMDAPEm Resource From: Galvin, Dennis Sent: Wednesday, April 19, 2017 12:06 PM To: Arthur.Zaremba@duke-energy.com Cc: Joshua.Duc@duke-energy.com; Beasley, Benjamin; Markley, Michael; Rudland, David; Dijamco, David; Poehler, Jeffrey; Barillas, Martha; Hon, Andrew; Wentzel, Michael; Koenick, Stephen; Mahoney, Michael
Subject:
Duke Energy Fleet Request for an Alternative to Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. 9513-9521)
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1; CATAWBA NUCLEAR STATION, UNIT NO. 2; SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1; MCGUIRE NUCLEAR STATION, UNIT NOS. 1 AND 2; OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3; AND H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 ACCEPTANCE OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST (CAC NOS. MF9513-MF9521)
- Art, By letter dated March 29, 2017, Duke Energy Carolinas, LLC and Duke Energy Progress, LLC (the licensee) (Agencywide Documents Access and Management System Accession No. ML17088A846) submitted a request in accordance with Paragraph 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME B&PV Code) for Brunswick Steam Electric Plant, Unit No. 1; Catawba Nuclear Station, Unit No. 2; Shearon Harris Nuclear Power Plant, Unit 1; McGuire Nuclear Station, Unit Nos. 1 and 2; Oconee Nuclear Station, Unit Nos. 1, 2 and 3; and H. B. Robinson Steam Electric Plant, Unit No. 2. The proposed alternative would allow the licensee to eliminate the reactor pressure vessel threads in the flange volumetric examination requirement ASME B&PV Code,Section XI, Examination Category B-G-1, Item Number B6.40.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed alternative. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to 10 CFR 50.55a(z), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of 10 CFR 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the staffs detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 200 hours8.333 days <br />1.19 weeks <br />0.274 months <br /> to complete. The NRC staff expects to complete this review in approximately 11 months, which is March 1, 2018. If there are emergent complexities or challenges in our review that would cause changes to the initial 1
forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager.
These estimates are based on the NRC staffs initial review of the application and they could change, due to several factors including requests for additional information, and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
If you have any questions, please contact me at (301) 415-6256.
Sincerely, Dennis Galvin Project Manager U.S Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Licensing Project Branch 2-2 Docket Nos. 50-325, 50-414, 50-400, 50-369, 50-370, 50-269, 50-270, 50-287, and 50-261 2
Hearing Identifier: NRR_PMDA Email Number: 3447 Mail Envelope Properties (Dennis.Galvin@nrc.gov20170419120500)
Subject:
Duke Energy Fleet Request for an Alternative to Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. 9513-9521)
Sent Date: 4/19/2017 12:05:51 PM Received Date: 4/19/2017 12:05:00 PM From: Galvin, Dennis Created By: Dennis.Galvin@nrc.gov Recipients:
"Joshua.Duc@duke-energy.com" <Joshua.Duc@duke-energy.com>
Tracking Status: None "Beasley, Benjamin" <Benjamin.Beasley@nrc.gov>
Tracking Status: None "Markley, Michael" <Michael.Markley@nrc.gov>
Tracking Status: None "Rudland, David" <David.Rudland@nrc.gov>
Tracking Status: None "Dijamco, David" <David.Dijamco@nrc.gov>
Tracking Status: None "Poehler, Jeffrey" <Jeffrey.Poehler@nrc.gov>
Tracking Status: None "Barillas, Martha" <Martha.Barillas@nrc.gov>
Tracking Status: None "Hon, Andrew" <Andrew.Hon@nrc.gov>
Tracking Status: None "Wentzel, Michael" <Michael.Wentzel@nrc.gov>
Tracking Status: None "Koenick, Stephen" <Stephen.Koenick@nrc.gov>
Tracking Status: None "Mahoney, Michael" <Michael.Mahoney@nrc.gov>
Tracking Status: None "Arthur.Zaremba@duke-energy.com" <Arthur.Zaremba@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 4357 4/19/2017 12:05:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: