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Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 IR 05000261/20220022022-08-0909 August 2022 Integrated Inspection Report 05000261 2022002, 07200060 2022001 and Exercise of Enforcement Discretion ML22213A0682022-08-0505 August 2022 Request for Withholding Information from Public Disclosure for H. B. Robinson Steam Electric Plant, Unit 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves IR 05000261/20220112022-07-19019 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000261/2022011 ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22125A1942022-05-12012 May 2022 Request for Withholding Information from Public Disclosure for H.B. Robinson Steam Electric Plant, Unit 2 IR 05000261/20220012022-05-0202 May 2022 Integrated Inspection Report 05000261/2022001 IR 05000261/20224012022-04-19019 April 2022 Security Baseline Inspection Report 05000261/2022401 ML22098A2262022-04-11011 April 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22083A0032022-03-29029 March 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System IR 05000261/20210062022-03-0202 March 2022 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 (Report No. 05000261/2021006) 2024-01-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) 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) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 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 ML22222A1082022-08-10010 August 2022 NRR E-mail Capture - Request for Additional Information Regarding Duke'S Request to Remove 4.160 Kv Bus 2 from Surveillance Requirement 3.8.1.16 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ML22080A0042022-03-18018 March 2022 Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20353A1312020-12-18018 December 2020 2021 Hbr 50.59 Info Request 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) ML20191A2122020-07-0909 July 2020 012 FPTI Notification Letter ML20063L4562020-02-0404 February 2020 NRR E-mail Capture - RAI - Robinson Relief Req Rx Vessel Cold Leg Nozzle Dissimilar Meter Butt Weld Inspection Interval EPID L-2019-LLR-0072 ML20022A1942020-01-22022 January 2020 Emergency Preparedness Program Inspection Request for Information ML19365A0462019-12-18018 December 2019 Audit Documents Needed for the Robinson SPRA Review ML19288A2942019-10-15015 October 2019 NRR E-mail Capture - RAIs for Robinson Revision to RPV Surveillance Program Withdrawal Schedule ML19288A2462019-09-26026 September 2019 Request for Additional Information Regarding Change to Surveillance Requirement 3.8.2.1 H.B. Robinson Unit No. 2 ML19283A0372019-09-26026 September 2019 Draft Requests for Additional Information for H.B. Robinson LAR to Revise TS 3.8.2, AC Sources - Shutdown, SR 3.8.2.1 ML19072A0292019-03-13013 March 2019 50.69 LAR RAIs ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18291A6442018-10-17017 October 2018 NRR E-mail Capture - Robinson RAIs - Duke Energy 10 CFR 50.46 Annual Report ML18288A0192018-10-12012 October 2018 NRR E-mail Capture - Robinson RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 (EPID L 2018-LLA-0095) and LAR to Adopt TSTF-425 ML18274A2632018-09-28028 September 2018 NRR E-mail Capture - Robinson Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 (EPID L 2018-LLA-0095) and LAR to Adopt TSTF-425 ML18211A6042018-07-30030 July 2018 NRR E-mail Capture - Robinson Supplemental RAI - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L-2017-LLA-0308) ML18206B0612018-07-25025 July 2018 NRR E-mail Capture - Draft Robinson Supplemental RAI - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7592018-04-18018 April 2018 NRR E-mail Capture - Robinson RAIs - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18102B0812018-04-12012 April 2018 NRR E-mail Capture - Draft Robinson RAIs - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18074A0052018-03-15015 March 2018 Heat Sink Emailed Heat Sink RFI Request 2018 ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17248A0182017-08-31031 August 2017 NRR E-mail Capture - Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17235A2612017-08-22022 August 2017 NRR E-mail Capture - Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17114A0462017-04-21021 April 2017 Notification of Inspection and Request for Information ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16130A5982016-05-0505 May 2016 Notification of Inspection and Request for Information ML16048A3492016-03-0202 March 2016 RAI Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML16019A0532016-02-0808 February 2016 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals ML16026A0512016-01-25025 January 2016 Robinson EP RFI 2016-001 ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) ML15215A6512015-08-10010 August 2015 Duke Energy Progress, Inc., for H. B. Robinson, Unit 2 and Shearon Harris, Unit 1, Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 (TAC Nos. MF5872 ML15009A3352015-01-0808 January 2015 Requalification Program Inspection - H.B. Robinson Nuclear Plant RNP-RA/14-0118, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes2014-11-12012 November 2014 Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes ML14268A5162014-10-23023 October 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-evaluation Related to Southeastern Catalog Changes ML14057A6502014-02-26026 February 2014 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 2024-01-02
[Table view] |
Text
March 5, 2004 Mr. J. W. Moyer, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. MB7932)
Dear Mr. Moyer:
By letter dated February 11, 2003, as supplemented by letter dated December 30, 2003, Carolina Power & Light Company submitted Request for Relief No. 34 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the Code),Section XI, for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2). The request for relief is for the third 10-year inservice inspection interval, in which HBRSEP2 adopted the 1986 Edition of ASME Section XI as the Code of record, with the exception of Class 1, Examination Category B-J piping weld examinations, which are determined by the 1974 Edition through Summer 1975 Addenda of Section XI, as allowed by Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a.
Based on our review of the information provided by you, we have determined that additional information is required to complete our review. The details about the required information are provided in the enclosure. This information was discussed with your staff during a conference call on February 24, 2004. We request that you provide your response as soon as possible but no later than April 19, 2004.
Sincerely,
/RA/
Chandu P. Patel, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
Request for Additional Information cc w/encl: See next page
March 5, 2004 Mr. J. W. Moyer, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. MB7932)
Dear Mr. Moyer:
By letter dated February 11, 2003, as supplemented by letter dated December 30, 2003, Carolina Power & Light Company submitted Request for Relief No. 34 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the Code),Section XI, for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2). The request for relief is for the third 10-year inservice inspection interval, in which HBRSEP2 adopted the 1986 Edition of ASME Section XI as the Code of record, with the exception of Class 1, Examination Category B-J piping weld examinations, which are determined by the 1974 Edition through Summer 1975 Addenda of Section XI, as allowed by Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a.
Based on our review of the information provided by you, we have determined that additional information is required to complete our review. The details about the required information are provided in the enclosure. This information was discussed with your staff during a conference call on February 24, 2004. We request that you provide your response as soon as possible but no later than April 19, 2004.
Sincerely,
/RA/
Chandu P. Patel, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC AHowe EDunnington ACRS TChan PDII-2 R/F CPatel OGC PFredrickson, RII SCoffin Adams Accession No. ML040650140 OFFICE PM:PDII/S2 LA:PDII/S2 SC:PDII/S2 NAME CPatel EDunnington MLMarshall for:
WBurton (A)
DATE 3/4/04 3/4/04 3/4/04 COPY Yes/No Yes/No Yes/No OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION ON THIRD 10-YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF FOR CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NUMBER 50-261 1.0 SCOPE By letter dated February 11, 2003, Carolina Power & Light Company (CP&L, the licensee) submitted Request for Relief No. 34 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The request for relief is for the third 10-year inservice inspection (ISI) interval, in which H.B. Robinson adopted the 1986 Edition of ASME Section XI as the Code of record.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(g)(5)(iii), the licensee has submitted Relief Request 34 to address many components for which 100-percent coverage could not be obtained. For Class 1 and 2 welds, the Code requires that 100 percent of the examination volumes described in IWB-2500-1 be completed.
10 CFR 50.55a(g)(5)(iii) states that when licensees determine that conformance with Code requirements is impractical at their facility, they shall submit information to support this determination. The NRC will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to public safety and the burden imposed on the licensee.
In response to an NRC Request for Additional Information (RAI), the licensee revised the request and provided further information in a letter dated December 30, 2003. During review of the licensees RAI response, it was discovered that several welds had been omitted, and other relevant information was incomplete. The NRC staff, with assistance from its contractor, Pacific Northwest National Laboratory, has determined that the following information is required to complete the evaluation.
2.0 REQUEST FOR ADDITIONAL INFORMATION 2.1 Omitted Welds Several welds included in original Relief Request 34 were omitted in the revision. In one case, it was stated that, upon further review of examination reports, the licensee determined that greater than 90-percent coverage had been obtained for certain welds; therefore, relief was not required. These welds are listed in Table 1 below. Please clarify that greater than 90-percent volumetric and surface, as applicable, examination coverage was obtained for the welds in Table 1 and how the decision to list these welds in the original request was reached.
Other welds appear to have been omitted in revised Relief Request 34 with no explanation.
Please provide clarifying information as to why these welds listed in Table 2 were omitted.
Table 1 Welds Removed Based on Greater Than 90% Coverage in Revised Request Drawing/ ASME Description Item Exam Limitation/Comment Weld Category Coverage 101/14 B-A Reactor Vessel Upper B1.12 90% Proximity of the inlet Shell Longitudinal Weld nozzle inner radius section at 70° 101/15 B-A Reactor Vessel Upper B1.12 90% Proximity of the inlet Shell Longitudinal Weld nozzle inner radius section at 190° 101/16 B-A Reactor Vessel Upper B1.12 90% Proximity of the inlet Shell Longitudinal Weld nozzle inner radius section at 310° 101A/30 B-D Reactor Vessel Cold Leg B3.90 90% Proximity of the inlet Loop A Nozzle Weld at nozzle inner radius section 80° 101A/32 B-D Reactor Vessel Cold Leg B3.90 90% Proximity of the inlet Loop C Nozzle Weld at nozzle inner radius section 200° Table 2 Welds Missing in Revised Request With no Explanation Drawing/ ASME Description Item Exam Limitation/Comment Weld Category Coverage 202/01 C-A Boron Injection Tank C1.20 83% Vessel weld/component Shell to Upper Head configuration Weld 202/01 C-A Boron Injection Tank C1.20 83% Vessel weld/component Shell to Lower Head configuration Weld 204/A02 C-A Residual Heat C1.20 68% Inlet and outlet nozzles Exchanger A Shell to and vessel supports Lower Head Weld 231/30 C-F-1 Safety Injection System C5.21 50% Weld crown configuration Pipe to Elbow 239/12 C-F-1 Safety Injection System C5.21 52% Weld crown configuration Pipe to Elbow 239/13 C-F-1 Safety Injection System C5.21 42% Weld crown configuration Pipe to Elbow 239/14 C-F-1 Safety Injection System C5.21 41% Weld crown/component Pipe to Elbow configuration 240/13 C-F-1 Safety Injection Pipe to C5.21 86% Weld crown configuration Elbow
Finally, the welds listed in Table 3 below were omitted from the revised relief request with the following explanation:
During the review process performed on the subject welds, it was identified that the ISI Program description included steam generator nozzle safe end welds. After further review, it appears that the steam generators were provided with a stainless steel build-up on the hot leg and cold leg nozzles and that there is no weld in this location. Therefore, these welds are not included in this RAI response and have been deleted from the ISI Program description.
Please provide clarifying information on the weld configuration as the result of steam generator replacement and provide the dates for when the steam generators were replaced pertaining to these nozzle-to-piping welds. Please clarify that no new welds have been included in the ISI Program Plan. Also, provide any information related to limitations for examining these Category B-J welds or B-F welds.
Table 3 Welds in Original Relief Request That do not Exist Drawing/ Code Description Item Exam Limitation/Comment Weld Category Coverage 107/04 B-J Hot Leg Loop A Elbow B9.11 75% Weld/component to Safe End configuration 107/05 B-J Crossover Leg-Loop A B9.11 75% Weld/component Safe End to Elbow configuration 107A/04 B-J Hot Leg Loop B Elbow B9.11 75% Weld/component to Safe End configuration 107A/05 B-J Crossover Leg-Loop B B9.11 75% Weld/component Safe End to Elbow configuration 107B/04 B-J Hot Leg Loop C Elbow B9.11 75% Weld/component to Safe End configuration 107B/05 B-J Crossover Leg-Loop C B9.11 75% Weld/component Safe End to Elbow configuration 2.2 Request for Relief 34, Revision 1, Category B-D Examinations of Full-Penetration Welded Nozzles in Vessels Based upon the drawings and descriptions provided by the licensee for welds 101A/29, 101A/31, and 101A/33, it is not clear why only 10 percent of the subject nozzle weld can be examined when scanning transverse to the weld. In addition, the licensee does not state whether the subject weld was examined from the nozzle bore during the first period of the third inspection interval. Clearly explain why only 10 percent of the weld can be examined in the transverse direction and provide additional information to support a determination of reasonable assurance for continued structural integrity.
2.3 Request for Relief 34, Revision 1, Category B-G-1 Examinations of Pressure-Retaining Bolting The licensee has requested relief from the 100-percent Code-required examination volume for reactor coolant pump stud No. 7. The licensee states that the lower 8 inches of the stud cannot be examined due to a taper in the stud design. Further, the licensee states that the limitation equates to only 0.36 percent of the overall examination volume for all studs in aggregate. We understand that this relief is no longer required. Please clarify your position.
2.4 Confirm the end date for the H.B. Robinson third 10-year inspection interval was February 18, 2002.
2.5 Request for Relief 34, Revision 1, Examination Categories B-F, B-J, C-F-1, and C-F-2 Pressure-Retaining Welds in Piping Clarify that 100 percent, with the exception noted for socket Weld 133/10, of the Code-required surface examinations were completed for all Class 1 and 2 dissimilar metal, austenitic, and ferritic piping welds included in Request for Relief 34. Briefly discuss any relevant indication, if observed, during the volumetric and surface examinations.
2.6 Request for Relief 34, Revision 1, Examination Category C-C, Integral Attachments for Vessels, Piping, Pumps, and Valves Briefly discuss whether relevant indications have been detected on the subject integrally welded attachments, and describe other attachment welds that have received full Code examinations.
Mr. J. W. Moyer H. B. Robinson Steam Electric Plant, Carolina Power & Light Company Unit No. 2 cc:
Steven R. Carr Supervisor, Licensing/Regulatory Programs Associate General Counsel - Legal H. B. Robinson Steam Electric Plant, Department Unit No. 2 Progress Energy Service Company, LLC Carolina Power & Light Company Post Office Box 1551 3581 West Entrance Road Raleigh, North Carolina 27602-1551 Hartsville, South Carolina 29550 Ms. Margaret A. Force Ms. Beverly Hall, Section Chief Assistant Attorney General N.C. Department of Environment State of North Carolina and Natural Resources Post Office Box 629 Division of Radiation Protection Raleigh, North Carolina 27602 3825 Barrett Dr.
Raleigh, North Carolina 27609-7721 U. S. Nuclear Regulatory Commission Resident Inspectors Office Mr. Robert P. Gruber H. B. Robinson Steam Electric Plant Executive Director 2112 Old Camden Road Public Staff - NCUC Hartsville, South Carolina 29550 4326 Mail Service Center Raleigh, North Carolina 27699-4326 Mr. T. P. Cleary Plant General Manager Mr. Henry H. Porter, Assistant Director H. B. Robinson Steam Electric Plant, South Carolina Department of Health Unit No. 2 Bureau of Land & Waste Management Carolina Power & Light Company 2600 Bull Street 3581 West Entrance Road Columbia, South Carolina 29201 Hartsville, South Carolina 29550 Mr. James W. Holt Mr. Chris L. Burton Manager Director of Site Operations Performance Evaluation and H. B. Robinson Steam Electric Plant, Regulatory Affairs PEB 7 Unit No. 2 Progress Energy Carolina Power & Light Company Post Office Box 1551 3581 West Entrance Road Raleigh, North Carolina 27602-1551 Hartsville, South Carolina 29550 Mr. John H. ONeill, Jr.
Public Service Commission Shaw, Pittman, Potts, & Trowbridge State of South Carolina 2300 N Street NW.
Post Office Drawer 11649 Washington, DC 20037-1128 Columbia, South Carolina 29211 J. F. Lucas Manager - Support Services - Nuclear H. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550 Mr. C. T. Baucom