|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Miller, EdSent:Tuesday, June 10, 2014 11:02 AMTo:'Vu, Phong T (Phong.Vu@duke-energy.com)' | | {{#Wiki_filter:1NRR-PMDAPEm Resource From:Miller, Ed Sent:Tuesday, June 10, 2014 11:02 AM To:'Vu, Phong T (Phong.Vu@duke-energy.com)' |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Draft RAI for Relief Request 13-MN-003Attachments:Draft EPNB RAI.docxPT, The NRC staff's draft RAI for the subject relief request is attached to this e-mail. The draft RAI is not an official NRC staff request and is being provided to you to facilitate a subsequent conference call to determine: 1) If the questions clearly convey the NRC staff information needs; 2) Whether the regulatory basis for the questions is understood; 3) Whether the information is already available in existing, docketed, correspondence; and 4) To determine an appropriate response time-frame. After you've had a chance to review the draft information request, please contact me to schedule the conference call. | | Draft RAI for Relief Request 13-MN-003 Attachments:Draft EPNB RAI.docx PT, The NRC staff's draft RAI for the subject relief request is atta ched to this e-mail. The draft RAI is not an official NRC staff request and is being provided to you to facilitate a subsequent conference call to determine: 1) If the questions clearly convey the NRC staff information needs; 2) Whether the regulatory basis for the questions is understood; 3) Whether the information is already available in existing, docketed, correspondence; and 4) To determine an appropriate response time-frame. After you've had a chance to review the draft information request, please contact me to schedule the conference call. |
|
| |
|
| Ed Miller (301) 415-2481 Hearing Identifier: NRR_PMDA Email Number: 1352 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFD0D8A321D) | | Ed Miller |
| | |
| | (301) 415-2481 |
| | |
| | Hearing Identifier: NRR_PMDA Email Number: 1352 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFD0D8A321D) |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Draft RAI for Relief Request 13-MN-003 Sent Date: 6/10/2014 11:02:20 AM Received Date: 6/10/2014 11:02:00 AM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: "'Vu, Phong T (Phong.Vu@duke-energy.com)'" <Phong.Vu@duke-energy.com> Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 669 6/10/2014 11:02:00 AM Draft EPNB RAI.docx 27397 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | Draft RAI for Relief Request 13-MN-003 Sent Date: 6/10/2014 11:02:20 AM Received Date: 6/10/2014 11:02:00 AM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: "'Vu, Phong T (Phong.Vu@duke-energy.com)'" <Phong.Vu@duke-energy.com> Tracking Status: None |
| DRAFT REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 THIRD 10-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST NO. 13-MN-003 DOCKET NOS. 50-369 AND 50-370 By letter dated February 6, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14055A402), Duke Energy Carolinas (Duke) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI for the third 10-year Inservice Inspection (ISI) Program for McGuire Nuclear Station, Unit 2 (McGuire 2). In order for the NRC staff to complete its review of the relief request, the following additional information is requested. 1. What is the normal operating temperature and pressure for the subject welds (2ELDHX-HD-FLG & 2RCHPSS-OUT-1). 2. What environmental conditions are the subject welds, (2ELDHX-HD-FLG & 2RCHPSS-OUT-1), exposed to (e.g., system transients, vibration, flow)? 3. Describe the materials of construction for the stainless steel head, weld metal, and carbon steel flange in weld 2ELDHX-HD-FLG. 4. Describe the weld metal used in 2RCHPSS-OUT-1. 5. Has Duke performed a review of applicable operating experience for the subject welds? If so, did this review identify any industry operating experience of similar system welds developing service induced cracking or failure?}} | | |
| | Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 669 6/10/2014 11:02:00 AM Draft EPNB RAI.docx 27397 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: |
| | DRAFT REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 THIRD 10-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST NO. 13-MN-003 DOCKET NOS. 50-369 AND 50-370 |
| | |
| | By letter dated February 6, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14055A402) |
| | , Duke Energy Carolinas (Duke) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI for the third 10-year Inservice Inspection (ISI) Program for McGuire Nuclear Station, Unit 2 (McGuire 2). In order for the NRC staff to complete its review of the relief request, the following additional |
| | |
| | information is requested. |
| | : 1. What is the normal operating temperature and pressure for the subject welds (2ELDHX-HD-FLG & 2RCHPSS-OUT-1). |
| | : 2. What environmental conditions are the subject welds, (2ELDHX-HD-FLG & 2RCHPSS-OUT-1), exposed to (e.g., system transients, vibration, flow)? |
| | : 3. Describe the materials of construction for the stainless steel head, weld metal, and carbon steel flange in weld 2ELDHX-HD-FLG. |
| | : 4. Describe the weld metal used in 2RCHPSS-OUT-1. |
| | : 5. Has Duke performed a review of applicable operating experience for the subject welds? If so, did this review identify any industry operating experience of similar system welds developing service induced cracking or failure?}} |
|
|---|
Category:E-Mail
MONTHYEARML24207A0862024-07-24024 July 2024
Relief Request Acceptance Review Results - McGuire Units 1 and 2 Alternatives Component Cooling Pumps, RHR Pumps
ML24197A1702024-07-15015 July 2024
Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations
ML24179A1292024-06-24024 June 2024
Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1
ML24033A2372024-02-0202 February 2024
Acceptance of Requested Licensing Action Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations (Epids L-2024-LLR-0002 and L-2024-LLR-0003)
ML24029A1132024-01-16016 January 2024
Notification of Inspection and Request for Information (Email)
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
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)
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)
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)
ML23087A2492023-03-27027 March 2023
50.69 Acceptance Email
ML23087A0282023-03-27027 March 2023
Acceptance of Requested Licensing Action Amendment TSTF-505
ML23073A2282023-03-13013 March 2023
Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review
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)
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)
ML23017A2232023-01-13013 January 2023
Request for Additional Information (RAI) Issuance for McGuire Unit 1 Steam Generator Tube Inspection Report (Email)
ML22291A4602022-10-17017 October 2022
Relief Request Impractical RPV and Rx Coolant Sys. Welds
ML22242A1602022-08-30030 August 2022
Hardship Relief Request Pilot-Operated Relief Valve Acceptance Review Results
ML22115A1412022-04-25025 April 2022
NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information
ML22083A0702022-03-24024 March 2022
NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, and McGuire Nuclear Station, Units 1 and 2 - Acceptance Review for TSTF-569 LAR
ML22049B0152022-02-17017 February 2022
NRC RP Inspection Document Request Letter
ML22038A1572022-02-0707 February 2022
NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2
ML22024A3952022-01-24024 January 2022
Acceptance of Requested Licensing Action Amendment McGuire RCS PT Limits Change TS 3.4.3 and EFPY Changes
ML22018A0272022-01-18018 January 2022
2022 All RFI Responses - Exercise and Program Inspections - Revl
ML21361A0122021-12-23023 December 2021
NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility
ML21354A8612021-12-15015 December 2021
NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156)
ML21286A7812021-11-22022 November 2021
Acceptance of Requested Licensing Action Revision to the End of Cycle Moderator Temperature Coefficient Measurement Methodology
ML21295A0372021-10-0505 October 2021
NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-577 Revised Frequencies for Steam Generator Tube Inspections
ML21252A0532021-09-0808 September 2021
NRR E-mail Capture - Formal Release of Rais, 30 Day Response, Mcguire Relief Request, Ref: Later Edition Addenda ASME Code, Section XI, 50.55a(g)(4)(iv)
ML21195A2022021-07-14014 July 2021
NRR E-mail Capture - McGuire Relief Request Acceptance Review Results; McGuire Unit 1 RR, Later Edition Addenda ASME Code, Section XI, 50.55a(g)(4)(iv)
ML21103A0542021-04-13013 April 2021
NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1
ML21096A3002021-04-0606 April 2021
E-mail for Approval of Proprietary Withholding for Duke Energy Exemptions for the Magnastor Storage Cask
ML21096A2512021-04-0505 April 2021
NRR E-mail Capture - McGuire Emergency Plan Submittal, Letter Dated March 31 2021
ML21067A6742021-03-0505 March 2021
NRR E-mail Capture - Final Request for Additional Information AMS Topical Report AMS-TR-0720R1
ML21049A2632021-02-0404 February 2021
NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan
ML21007A3722021-01-0707 January 2021
NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156)
ML21006A4302021-01-0606 January 2021
Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML20346A0212020-12-10010 December 2020
NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021
ML20323A4072020-11-18018 November 2020
NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180)
ML20297A3102020-10-13013 October 2020
NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126)
ML20297A3082020-10-0707 October 2020
NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124)
ML20297A3092020-10-0606 October 2020
NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125)
ML20216A3512020-08-0303 August 2020
Mcquire U-1 ISI RFI
ML20177A3792020-06-23023 June 2020
Email from L. Cox, North Carolina Department of Health and Human Services to NRC Regarding Exemption Request for Duke Energy'S McGuire Nuclear Station
ML20140A0852020-05-19019 May 2020
ADAMS 2D
ML20101L3132020-04-10010 April 2020
Notification of Inspection and Request for Information
2024-07-24
[Table view] |
Text
1NRR-PMDAPEm Resource From:Miller, Ed Sent:Tuesday, June 10, 2014 11:02 AM To:'Vu, Phong T (Phong.Vu@duke-energy.com)'
Subject:
Draft RAI for Relief Request 13-MN-003 Attachments:Draft EPNB RAI.docx PT, The NRC staff's draft RAI for the subject relief request is atta ched to this e-mail. The draft RAI is not an official NRC staff request and is being provided to you to facilitate a subsequent conference call to determine: 1) If the questions clearly convey the NRC staff information needs; 2) Whether the regulatory basis for the questions is understood; 3) Whether the information is already available in existing, docketed, correspondence; and 4) To determine an appropriate response time-frame. After you've had a chance to review the draft information request, please contact me to schedule the conference call.
Ed Miller
(301) 415-2481
Hearing Identifier: NRR_PMDA Email Number: 1352 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFD0D8A321D)
Subject:
Draft RAI for Relief Request 13-MN-003 Sent Date: 6/10/2014 11:02:20 AM Received Date: 6/10/2014 11:02:00 AM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: "'Vu, Phong T (Phong.Vu@duke-energy.com)'" <Phong.Vu@duke-energy.com> Tracking Status: None
Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 669 6/10/2014 11:02:00 AM Draft EPNB RAI.docx 27397 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
DRAFT REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 THIRD 10-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST NO. 13-MN-003 DOCKET NOS. 50-369 AND 50-370
By letter dated February 6, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14055A402)
, Duke Energy Carolinas (Duke) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for the third 10-year Inservice Inspection (ISI) Program for McGuire Nuclear Station, Unit 2 (McGuire 2). In order for the NRC staff to complete its review of the relief request, the following additional
information is requested.
- 1. What is the normal operating temperature and pressure for the subject welds (2ELDHX-HD-FLG & 2RCHPSS-OUT-1).
- 2. What environmental conditions are the subject welds, (2ELDHX-HD-FLG & 2RCHPSS-OUT-1), exposed to (e.g., system transients, vibration, flow)?
- 3. Describe the materials of construction for the stainless steel head, weld metal, and carbon steel flange in weld 2ELDHX-HD-FLG.
- 4. Describe the weld metal used in 2RCHPSS-OUT-1.
- 5. Has Duke performed a review of applicable operating experience for the subject welds? If so, did this review identify any industry operating experience of similar system welds developing service induced cracking or failure?
