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| | number = ML15210A780 | | | number = ML15210A780 |
| | issue date = 07/28/2015 | | | issue date = 07/28/2015 |
| | title = Draft RAI for Mur Flex Hose RR | | | title = NRR E-mail Capture - Draft RAI for Mur Flex Hose RR |
| | author name = Miller E | | | author name = Miller E |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Rudy L J | | | addressee name = Rudy L |
| | addressee affiliation = Duke Energy Corp | | | addressee affiliation = Duke Energy Corp |
| | docket = 05000413 | | | docket = 05000413 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Miller, Ed Sent: Tuesday, July 28, 2015 12:39 PM To: 'lawrence.rudy@duke-energy.com' | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Miller, Ed Sent: Tuesday, July 28, 2015 12:39 PM To: 'lawrence.rudy@duke-energy.com' |
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| ==Subject:== | | ==Subject:== |
| Draft RAI for MUR Flex Hose RR Attachments: | | Draft RAI for MUR Flex Hose RR Attachments: Draft RAI CN-15-001.docx |
| Draft RAI CN-15-001.docxLarry, 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. | | : Larry, The NRC staffs 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 youve had a chance to review the draft information request, please contact me to schedule the conference call. |
| | Also, I know its short notice, but do you think there would be any chance of having the draft RAI call between now and next Tuesday? The reviewer is going be out of the office for a while after next Tuesday. |
| | Ed Miller (301) 415-2481 1 |
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| Also, I know it's short notice, but do you think there would be any chance of having the draft RAI call between now and next Tuesday? The reviewer is going be out of the office for a while after next Tuesday.
| | Hearing Identifier: NRR_PMDA Email Number: 2257 Mail Envelope Properties (ecab4efa1fa64f2e8db3b3f3851d2638) |
| Ed Miller
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| (301) 415-2481
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| Hearing Identifier: NRR_PMDA Email Number: 2257 Mail Envelope Properties (ecab4efa1fa64f2e8db3b3f3851d2638) | |
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| ==Subject:== | | ==Subject:== |
| Draft RAI for MUR Flex Hose RR Sent Date: 7/28/2015 12:39:17 PM Received Date: 7/28/2015 12:39:00 PM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: "'lawrence.rudy@duke-energy.com'" <lawrence.rudy@duke-energy.com> Tracking Status: None | | Draft RAI for MUR Flex Hose RR Sent Date: 7/28/2015 12:39:17 PM Received Date: 7/28/2015 12:39:00 PM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: |
| | | "'lawrence.rudy@duke-energy.com'" <lawrence.rudy@duke-energy.com> |
| Post Office: HQPWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 877 7/28/2015 12:39:00 PM Draft RAI CN-15-001.docx 29127 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | Tracking Status: None Post Office: HQPWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 877 7/28/2015 12:39:00 PM Draft RAI CN-15-001.docx 29127 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| ENCLOSURE DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CATAWBA NUCLEAR STATION, UNIT 1 RELIEF REQUEST 15-CN-001 ALTERNATE REPAIR FOR FLEX HOSE STEAM LEAK DOCKET NO. 50-413
| | Recipients Received: |
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| By letter datedMarch 19,2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15082A074), Duke Energy Carolinas (Duke) submitted a relief request for the Catawba Nuclear Station, Unit 1. The proposed reliefwould allow the implementation of an alternate repair method for a steam leak. Duke has provided supplements to the submittal dated May 4, 2015, and July 16, 2015 (ADAMS Accession Nos. ML15127A170
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| and ML15201A499, respectively). In order for the NRC staff to complete its review of the relief request, the following additional information is requested.
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| : 1. The request stated that it is proposing an alternative the requirements of ASME Code Section XI, Appendix IX, Article IX-1000, General, (c) (2), in order to use a mechanical
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| clamping device on a system that forms part of the containment boundary. The licensee also stated that the clamping device will be designed to Appendix IX, Article IX-3000. The NRC requests that Duke verify that it will also meet all of the other requirements of Appendix IX. | | DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CATAWBA NUCLEAR STATION, UNIT 1 RELIEF REQUEST 15-CN-001 ALTERNATE REPAIR FOR FLEX HOSE STEAM LEAK DOCKET NO. 50-413 By letter datedMarch 19,2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15082A074), Duke Energy Carolinas (Duke) submitted a relief request for the Catawba Nuclear Station, Unit 1. The proposed reliefwould allow the implementation of an alternate repair method for a steam leak. Duke has provided supplements to the submittal dated May 4, 2015, and July 16, 2015 (ADAMS Accession Nos. ML15127A170 and ML15201A499, respectively). In order for the NRC staff to complete its review of the relief request, the following additional information is requested. |
| : 2. The request stated that the injection valve to be installed is ASME Code Class 1. The NRC requests that the applicant describe the code class of the other materials that will be used. | | : 1. The request stated that it is proposing an alternative the requirements of ASME Code Section XI, Appendix IX, Article IX-1000, General, (c) (2), in order to use a mechanical clamping device on a system that forms part of the containment boundary. The licensee also stated that the clamping device will be designed to Appendix IX, Article IX-3000. |
| : 3. The request stated that sealant will be injected into the piping between the root valves. The NRC requests that the licensee provide the temperature rating of the sealant and verify that the sealant does not contain contaminates, such as fluorides or chlorides, that could be detrimental to stainless steel pressure boundary components.}} | | The NRC requests that Duke verify that it will also meet all of the other requirements of Appendix IX. |
| | : 2. The request stated that the injection valve to be installed is ASME Code Class 1. The NRC requests that the applicant describe the code class of the other materials that will be used. |
| | : 3. The request stated that sealant will be injected into the piping between the root valves. |
| | The NRC requests that the licensee provide the temperature rating of the sealant and verify that the sealant does not contain contaminates, such as fluorides or chlorides, that could be detrimental to stainless steel pressure boundary components. |
| | ENCLOSURE}} |
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Category:E-Mail
MONTHYEARRA-24-0276, EN 57402 - Catawba Nuclear Station Interim Part 21 Report2024-10-28028 October 2024 EN 57402 - Catawba Nuclear Station Interim Part 21 Report ML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML24192A3492024-07-10010 July 2024 Acceptance of Requested Licensing Action License Amendment Application to Revise Technical Specification 3.4.3, RCS Pressure and Temperature Limits ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24150A1662024-05-29029 May 2024 Document Request for Catawba Nuclear Station Units 1 & 2 - Radiation Protection Inspection - Inspection Report 2024-03 ML24066A0142024-03-0505 March 2024 Cat 2024-002 Radiation Safety Baseline Inspection Information Request 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) ML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 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 ML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications 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) 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 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) 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 NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22213A0472022-08-0101 August 2022 Document Request for Catawba Nuclear Station - Radiation Protection Inspection - Inspection Report 2022-03 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22174A0802022-06-0101 June 2022 Transmittal External Distribution Notification TR-NUC-CN-014344 - SLC Manual Revision to Loes and SLC 16.7-5 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 ML22041A5312022-02-10010 February 2022 NRR E-mail Capture - Catawba Nuclear Station Unit 2 - Acceptance of Requested Licensing Action Use of Alternative Requirements of ASME Code for Embedded Flaw Repair Method on Reactor Vessel Closure Head Penetration 74 EPID L-2022-LLR-0010 ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22024A1112022-01-0707 January 2022 E-mail Capture- Catawba POV Inspection Information Request (1) 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) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) 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 ML21189A2502021-07-0202 July 2021 NRR E-mail Capture - Acceptance Review: Duke Energy - Proposed Alternative to Use ASME Code Case N-885 for Catawba Nuclear Station Unit 2 - EPID: L-2021-LLR-0043 ML21117A1292021-04-26026 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request RA-21-0145 ML21117A1222021-04-23023 April 2021 NRR E-mail Capture - (External_Sender) Catawba Nuclear Station Relief Request RA-21-0133 ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21099A0742021-04-0909 April 2021 CAT_2021-02 Document Request for Upcoming RP Inspection ML21096A3002021-04-0606 April 2021 E-mail for Approval of Proprietary Withholding for Duke Energy Exemptions for the Magnastor Storage Cask ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 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 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information 2024-07-15
[Table view] |
Text
NRR-PMDAPEm Resource From: Miller, Ed Sent: Tuesday, July 28, 2015 12:39 PM To: 'lawrence.rudy@duke-energy.com'
Subject:
Draft RAI for MUR Flex Hose RR Attachments: Draft RAI CN-15-001.docx
- Larry, The NRC staffs 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 youve had a chance to review the draft information request, please contact me to schedule the conference call.
Also, I know its short notice, but do you think there would be any chance of having the draft RAI call between now and next Tuesday? The reviewer is going be out of the office for a while after next Tuesday.
Ed Miller (301) 415-2481 1
Hearing Identifier: NRR_PMDA Email Number: 2257 Mail Envelope Properties (ecab4efa1fa64f2e8db3b3f3851d2638)
Subject:
Draft RAI for MUR Flex Hose RR Sent Date: 7/28/2015 12:39:17 PM Received Date: 7/28/2015 12:39:00 PM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients:
"'lawrence.rudy@duke-energy.com'" <lawrence.rudy@duke-energy.com>
Tracking Status: None Post Office: HQPWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 877 7/28/2015 12:39:00 PM Draft RAI CN-15-001.docx 29127 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CATAWBA NUCLEAR STATION, UNIT 1 RELIEF REQUEST 15-CN-001 ALTERNATE REPAIR FOR FLEX HOSE STEAM LEAK DOCKET NO. 50-413 By letter datedMarch 19,2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15082A074), Duke Energy Carolinas (Duke) submitted a relief request for the Catawba Nuclear Station, Unit 1. The proposed reliefwould allow the implementation of an alternate repair method for a steam leak. Duke has provided supplements to the submittal dated May 4, 2015, and July 16, 2015 (ADAMS Accession Nos. ML15127A170 and ML15201A499, respectively). In order for the NRC staff to complete its review of the relief request, the following additional information is requested.
- 1. The request stated that it is proposing an alternative the requirements of ASME Code Section XI, Appendix IX, Article IX-1000, General, (c) (2), in order to use a mechanical clamping device on a system that forms part of the containment boundary. The licensee also stated that the clamping device will be designed to Appendix IX, Article IX-3000.
The NRC requests that Duke verify that it will also meet all of the other requirements of Appendix IX.
- 2. The request stated that the injection valve to be installed is ASME Code Class 1. The NRC requests that the applicant describe the code class of the other materials that will be used.
- 3. The request stated that sealant will be injected into the piping between the root valves.
The NRC requests that the licensee provide the temperature rating of the sealant and verify that the sealant does not contain contaminates, such as fluorides or chlorides, that could be detrimental to stainless steel pressure boundary components.
ENCLOSURE