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MONTHYEARML11264A0282011-09-13013 September 2011 Proposed Alternative Request Number 11-CN-002 for the Third Ten-Year Inservice Inspection Interval Project stage: Request ML12062A0142012-03-0101 March 2012 NRR E-mail Capture - Request for Additional Information for Relief Request 11-CN-002 Submitted September 13, 2011 Project stage: RAI ML12104A2672012-04-11011 April 2012 Proposed Alternative Request Number 11-CN-002 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information Project stage: Response to RAI ML12223A1972012-08-14014 August 2012 Alternative Requirements for Performing System Leakage Tests on the ASME Code Class 1 Piping and Component Segments Project stage: Other 2012-03-01
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Category:E-Mail
MONTHYEARML23271A1792023-09-28028 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 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) ML20260H4622020-09-0909 September 2020 NRR E-mail Capture - Acceptance Review for Mcguire/Catawba EDG Maximum Voltage TS Limit L-2019-014, NRR E-mail Capture - (External Sender) Request for State Comments - Regarding Proposed Amendment to Revise the Catawba, Unit 1, Technical Specification (TS) 3.4.3, RCS Pressure and Temperature (P/T) Limits - State Response2020-07-0707 July 2020 NRR E-mail Capture - (External_Sender) Request for State Comments - Regarding Proposed Amendment to Revise the Catawba, Unit 1, Technical Specification (TS) 3.4.3, RCS Pressure and Temperature (P/T) Limits - State Response ML20191A0242020-07-0707 July 2020 NRR E-mail Capture - Request for State Comments - Regarding Proposed Amendment to Revise the Catawba, Unit 1, Technical Specification (TS) 3.4.3, RCS Pressure and Temperature (P/T) Limits - Staff Solicitation 2023-09-28
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NRR-PMDAPEm Resource From: Thompson, Jon Sent: Thursday, March 01, 2012 1:09 PM To: Hart, Randy; Rudy, Lawrence J Cc: Rezai, Ali; Lupold, Timothy; Salgado, Nancy
Subject:
Request for Additional Information for Relief Request 11-CN-002 submitted September 13, 2011
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (CATAWBA 1 AND 2), REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RELIEF REQUEST (RR) 11-CN-002, PROPOSED ALTERNATIVE REQUEST NUMBER 11-CN-002 FOR THE THIRD TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NOS. ME7182 THROUGH ME7187)
By letter dated September 13, 2011, Duke Energy Carolinas, LLC (the licensee), submitted the subject RR for Catawba 1 and 2. The U.S. Nuclear Regulatory Commission staff has reviewed the licensees submittal and determined that an RAI is needed in order to complete our review. The enclosed document describes this RAI. A written response should be provided to the NRC staff for these RAI questions within 30 days in order to support our timely review of this request. Please inform me as soon as possible if you are unable to support this response timeframe.
If you have any questions, please call me at 301-415-1119.
Sincerely, Jon Thompson, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosure:
As stated OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 11-CN-002 PROPOSED ALTERNATIVE REQUEST NUMBER 11-CN-002 FOR THE THIRD TEN-YEAR INSERVICE INSPECTION INTERVAL DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 By letter dated September 13, 2011, Duke Energy Carolina, LLC (the licensee) submitted Relief Request (RR) 11-CN-002, Proposed Alternative Request Number 11-CN-002 for the Third Ten-Year Inservice Inspection Interval (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11264A028) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. In the subject RR, the licensee proposed alternative pressure testing for the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Class 1 piping and component segments connected to (or part of) the reactor coolant system (RCS) in lieu of requirements of the ASME Code,Section XI, pressure testing. The proposed alternative is requested for the remainder of the third 10-year in service inspection (ISI) interval of Catawba 1 1
(which commenced on June 29, 2005, and will end on July 14, 2014) and Catawba 2 (which commenced on October 15, 2005, and will end on August 19, 2016).
The NRC staff has reviewed the information provided by the licensee in RR 11-CN-002 and finds the following additional information is needed to complete its review.
- 1. RR 11-CN-002 documented that the design pressure for piping and components in Segments 1, 2, 3, 4, and 5 is 2500 psig, while the section titled Proposed Alternative states that a system leakage test will be performed at a pressure not less than 300 psig for Segments 1, 2, and 5 and not less than 42 psig for Segment 3. The NRC staff notes that the section titled Bases for the Proposed Alternative states, The proposed system leakage test conducted at a pressure of at least 300 psig (Segments 1, 2 and 5) and at least 42 psig (Segment 3) is acceptable because leakage (if it were to occur) would still be detectable at this reduced pressure, although at a reduced rate.
- a. Provide the maximum pressure that the subject piping and piping components for Segments 1, 2, 3, 4, and 5 would experience during normal operating, stagnant, accident, and fault conditions.
- b. In light of the documented design pressure of 2500 psig for Segments 1, 2, 3, 4, and 5, and maximum pressures (identified in the response to RAI question 1a), provide justification for performing a system leakage test at such a reduced pressure to ensure the structural integrity of the system.
- 2. On pages 8 and 9 of the subject RR, several related industry RRs are cited. Discuss whether during the second (previous) 10-year ISI interval of Catawba 1 and 2, a RR for pressure testing requirements was submitted to the NRC staff for the same piping and piping components of Segments 1, 2, 3, 4, and 5.
- 3. Are there any welded connections in piping and components for Segments 1, 2, 3, 4, and 5? If the answer is yes, provide number and type (e.g., full penetration butt weld and fillet weld) of welds.
Discuss any nondestructive examinations (NDEs) that were performed on the welded connections.
Discuss any industry or plant-specific operating experience regarding potential degradation (e.g, fatigue, stress corrosion cracking, overloading, and corrosion) of welds in piping and components for the subject segments.
- 4. NRC Information Notice (IN) 2011-04, Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking [SCC] in Stainless Steel Piping in Pressurized water Reactors, (ADAMS Accession No. ML103410363), discusses potential SCC in stainless steel piping. Discuss the potential for SCC in piping and piping components for Segments 1, 2, 3, 4, and 5.
- 5. ASME Code Case N-731, Alternative Class 1 System Leakage Test Pressure Requirements, approved for use in Regulatory Guide (RG) 1.147, Rev. 16 (ADAMS Accession No. ML101800536),
provides an acceptable alternative to existing provisions of the ASME Code,Section XI. Discuss whether piping and piping components for Segments 1, 2, 3, 4, and 5 for which relief is requested, meet the requirements of ASME Code Case N-731.
Enclosure 2
Hearing Identifier: NRR_PMDA Email Number: 283 Mail Envelope Properties (Jon.Thompson@nrc.gov20120301130800)
Subject:
Request for Additional Information for Relief Request 11-CN-002 submitted September 13, 2011 Sent Date: 3/1/2012 1:08:31 PM Received Date: 3/1/2012 1:08:00 PM From: Thompson, Jon Created By: Jon.Thompson@nrc.gov Recipients:
"Rezai, Ali" <Ali.Rezai@nrc.gov>
Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>
Tracking Status: None "Salgado, Nancy" <Nancy.Salgado@nrc.gov>
Tracking Status: None "Hart, Randy" <Randy.Hart@duke-energy.com>
Tracking Status: None "Rudy, Lawrence J" <Lawrence.Rudy@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 5598 3/1/2012 1:08:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: