Letter Sequence RAI |
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EPID:L-2021-LLR-0014, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) (Approved, Closed) |
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Category:Letter
MONTHYEARIR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections 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 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 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 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20243012023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 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 IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 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 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) ML22230D0692022-08-22022 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident IR 05000324/20220022022-08-0505 August 2022 Integrated Inspection Report 05000324/2022002 and 05000325/2022002 IR 05000324/20220102022-06-27027 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000324 2022010 and 05000325 2022010 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 IR 05000324/20220012022-05-10010 May 2022 Integrated Inspection Report 05000324/2022001 and 05000325/2022001 ML22119A1352022-05-0909 May 2022 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000325/2022403; 05000324/2022403 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22102A0502022-04-11011 April 2022 301 Corporate Notification Letter IR 05000324/20224012022-03-16016 March 2022 Security Baseline Inspection Report 05000324/2022401 and 05000325/2022401 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications IR 05000324/20210062022-03-0202 March 2022 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 (Reports No. 05000324/2021006 and 05000325/2021006) IR 05000324/20210042022-02-14014 February 2022 Integrated Inspection Report 05000324/2021004 and 05000325/2021004 ML22035A1262022-02-0909 February 2022 Withdrawal of Exemption Request from the Requirements of 10 CFR Part 50, Appendix E, Section IV.F.2.d (EPID L-2021-LLE-0055 (COVID-19)) ML21354A5032022-01-24024 January 2022 Requested Exemption from 10 CFR 50, Appendix E, Section IV.F.2.D Not Required (EPID L-2021-LLE-0055 (COVID-19)) ML22018A1842022-01-18018 January 2022 Notification of Brunswick Steam Electric Plant, Units 1 & 2 - Design Bases Assurance Inspection - U.S. Nuclear Regulatory Inspection Report 05000324/2022010 and 05000325/2022010 ML21348A7192021-12-21021 December 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times 2023-09-25
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23202A0652023-07-19019 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) 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) 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 ML22192A0862022-07-12012 July 2022 RQ Inspection Notification Letter ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information 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) ML21277A0952021-10-0101 October 2021 NRR E-mail Capture - Request for Additional Information - Brunswick Exemption Request from 10CFR 55.47 License Operator Exam Two-year Waiver Limit ML21239A0652021-09-0808 September 2021 Request for Additional Information Regarding Proposed Alternative to ASME Section XI Requirements for Repair - Replacement of Buried Service Water Piping (EPID L-021-LLR-0014) - Public 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 ML21019A3772021-01-13013 January 2021 002 Radiation Safety Baseline Inspection Information 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) ML20309A5212020-10-29029 October 2020 Request for Additional Information - Brunswick License Amendment Request to Modify Its Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSC Categorization Process ML20275A2972020-10-0101 October 2020 NRR E-mail Capture - Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19283C5532019-10-18018 October 2019 Redacted - Brunswick Steam Electric Plant, Units 1 and 2 - Request for Additional Information ML19283D0852019-10-0909 October 2019 Request for Additional Information - Brunswick Atrium 11 LAR ML19179A1312019-06-27027 June 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19177A0122019-06-25025 June 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19081A0722019-03-21021 March 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19065A0962019-03-0606 March 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19058A0742019-02-26026 February 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19015A0302019-01-14014 January 2019 NRR E-mail Capture - Brunswick 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19010A3872019-01-10010 January 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TSs to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML18360A0352018-12-21021 December 2018 NRR E-mail Capture - Brunswick Draft 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML18360A0362018-12-21021 December 2018 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TSs to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML18282A1492018-10-0909 October 2018 NRR E-mail Capture - Brunswick RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML18263A3042018-09-20020 September 2018 NRR E-mail Capture - Brunswick Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML18250A3082018-08-31031 August 2018 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report ML18225A0122018-08-10010 August 2018 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18130A8262018-05-15015 May 2018 Supplemental Information Needed for Acceptance. Amendment Request to Revise the Technical Specifications to Relocate the Pressure Temperature Limit Curves to a Pressure and Temperature Limits Report ML18088A0072018-03-27027 March 2018 NRR E-mail Capture - Brunswick Units 1 & 2 Request for Additional Information - Relief Request for RPV Shell Circumferential Weld Examination (L-2018-LLR-0001) ML18071A3732018-03-12012 March 2018 NRR E-mail Capture - Correction: Brunswick Unit 1 and Unit 2 Request for Additional Information Related Human Factors in the Mellla+ LAR (CACs MF8864 and MF8865, EPID: L-2016-LLA-0009) ML18067A1032018-03-0808 March 2018 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related Human Factors in the Mellla+ LAR (CACs MF8864 and MF8865, EPID: L-2016-LLA-0009) ML18010A0502018-01-0505 January 2018 E-mail Re. Brunswick Units 1 and Unit 2 - Request for Additional Information Related to the Mellla+ LAR (CACs MF8864 and MF8865) ML18010A0512018-01-0505 January 2018 Unit 2 - Request for Additional Information Related to the Mellla+ LAR (CACs MF8864 and MF8865) (Nonproprietary) ML17339A9132017-12-0505 December 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related the Exigent Amendment Request for One-Time Extension of EDG Completions Time - Human Factors (EPID: L- 2017- LLA- 0398) ML17339A0702017-12-0404 December 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related the Exigent Amendment Request for One-Time Extension of EDG Completions Time - Electrical Engineering (EPID: L- 2017- LLA- 0398) ML17317B0022017-12-0404 December 2017 Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MF9905 and MF9906; EPID L-2017-LLA-0242) ML17339A0732017-12-0404 December 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related the Exigent Amendment Request for One-Time Extension of EDG Completions Time - PRA (EPID: L- 2017- LLA- 0398) ML17328A4872017-11-24024 November 2017 Unit 2 - Request for Additional Information Related the Emergency Amendment Request for One-Time Extension of EDG Completions Time ML17275A2772017-10-0202 October 2017 E-mail, Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CAC Nos. MF8864 and MF8865) (Non-Proprietary) ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17082A3042017-03-0909 March 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CACs MF8864 and MF8865) ML17037A0022017-02-0303 February 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related to LAR to Modify the TS Requirements for End States Associated with the Implementation of the Approved TSTF Traveler TSTF-423-A (MF8466 and MF8467) ML16020A2632016-01-20020 January 2016 Brunswick Steam Electric Plant - Notification Of Inspection And Request For Information 2023-07-19
[Table view] |
Text
OFFICIAL USE ONLY PROPRIETARY INFORMATION September 8, 2021 Mr. John A. Krakuszeski Site Vice President Brunswick Steam Electric Plant Duke Energy Progress, LLC 8470 River Rd. SE (M/C BNP001)
Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE TO ASME SECTION XI REQUIREMENTS FOR REPAIR/REPLACEMENT OF BUIRED SERVICE WATER PIPING (EPID L-2021-LLR-0014)
Dear Mr. Krakuszeski:
By letter dated February 24, 2021, as supplemented by letters dated May 3, 2021, and June 22, 2021 (Agencywide Documents Access and Management System Accession Nos.
ML21055A797, ML21123A293, and ML21173A253), Duke Energy Carolinas, LLC (Duke Energy, or the licensee) submitted a request pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), to use an alternative to certain requirements of the American Society for Mechanical Engineers Boiler & Pressure Vessel Code,Section XI.
Specifically, the licensee requested approval to allow the use of Carbon Fiber Reinforced Polymer Composite System for the internal repair of the buried service water piping at Brunswick Steam Electric Plant, Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed as discussed in the Enclosure. During a clarification call on September 7 2021, Mr. Arthur Zaremba of your staff agreed that Duke Energy would respond within 30 days of the date of this letter.
The NRC staffs request for additional information (RAI) contains proprietary information as originally submitted in the letter dated February 24, 2021. Proprietary information withheld under 10 CFR 2.390 is identified by text enclosed within double brackets as shown here (( )).
A non-proprietary version of the RAI is provided as Enclosure 2.
Enclosure 1 to this letter contains proprietary information. When separated from Enclosure 1, this document is DECONTROLLED.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION J. Krakuszeski If you have any questions, please contact me at 301-415-0615 or via e-mail at Zackary.Stone@nrc.gov.
Sincerely,
/RA/
Zackary R. Stone, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-324 and 50-325
Enclosures:
- 1. Request for Additional Information (Proprietary)
- 2. Request for Additional Information (Non-Proprietary) cc: w/o Enclosure 1: Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION ENCLOSURE 2 NON-PROPRIETARY VERSION REQUEST FOR ADDITIONAL INFORMATION BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DUKE ENERGY CAROLINAS, LLC PROPOSED ALTERNATIVE TO ASME SECTION XI REQUIRMENTS FOR REPAIR/REPLACEMENT OF BURIED SERVICE WATER PIPING DOCKET NOS. 50-324 AND 50-325 OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DUKE ENERGY CAROLINAS, LLC PROPOSED ALTERNATIVE TO ASME SECTION XI REQUIRMENTS FOR REPAIR/REPLACEMENT OF BURIED SERVICE WATER PIPING DOCKET NOS. 50-324 AND 50-325 By letter dated February 24, 2021, as supplemented by letters dated May 3, 2021, and June 22, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML21055A797, ML21123A293, and ML21173A253), Duke Energy Carolinas, LLC (Duke Energy, or the licensee) submitted a request pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), to use an alternative to certain requirements of the American Society for Mechanical Engineers (ASME) Boiler & Pressure Vessel Code,Section XI.
Specifically, the licensee requested approval to allow the use of Carbon Fiber Reinforced Polymer (CFRP) Composite System for the internal repair of the buried service water piping at Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick).
Regulatory Basis:
Pursuant to 10 CFR 50.55a(z)(1), the applicant shall demonstrate that proposed alternatives to Code requirements would provide an acceptable level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) staffs request for additional information (RAI) contains proprietary information as originally submitted in the letter dated February 24, 2021.
Proprietary information withheld under 10 CFR 2.390 is identified by text enclosed within double brackets as shown here (( )). A non-proprietary version of the RAI is provided as .
EMIB RAI-1:
The scope section of Attachment A in Enclosure 2 of the submittal mentions that it has not been determined whether the cement mortar lining will be removed or remain in place for upgrade of Brunswick service water piping using CFRP composite lining. Attachment B, Table 1 of provides a minimum average requirement for shear bond strength between CFRP and steel of (( )). Section 5A.3.1 of Attachment A in Enclosure 5 lists shear bond strength of CFRP on host pipe of (( )), which is also used in calculations in Attachment C of Enclosure 5.
(a) Discuss the applicability of the above noted shear bond strength values for the following situations:
- a. Between CFRP and host steel pipe when the cement lining is removed, and
- b. Between CFRP and host steel pipe when cement lining remains in place.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION (b) Discuss the acceptability of shear bond strength of ((
)).
EMIB RAI-2:
Figures S-7 and S-8 in Attachment D to Enclosure 5 of the submittal provide illustrations of CFRP composite system termination detail at straight ends, and repair terminations, where a certain length of host pipe is required to act compositely with the CFRP system. At the ends of the repair, a good bond with host pipe substrate is critical to maintain structural integrity so that the CFRP composite system can transfer loads to the host pipe. Provide additional discussion to address the following related to the intact or non-repaired side of the terminations.
(a) Whether the intact piping on the non-repaired side of terminations is buried, or whether all non-repaired side is above ground.
(b) The distance from the termination end to the end of buried portion of pipe or to the beginning of aboveground piping in the building penetrations or valve pits.
(c) The distance from termination end to the piping supports or anchors in the vicinity for the aboveground piping.
(d) Repair terminations interface with the repaired and the non-repaired sides of the piping. It appears that the loads from the repaired side are considered. Provide a discussion on structural integrity of the repair terminations from consideration of any dead weight, thermal, seismic, and any other applicable loadings from the non-repaired side for the terminations at Reactor Building wall, radwaste tunnel, and service water pumphouse. Address the structural integrity of the terminations for combined loads from repaired side and non-repaired or above ground continuation piping.
(e) Attachment C of Enclosure 5 lists a stress of (( )) of maximum longitudinal demand from non-repair side. Discuss if this stress represents the effect from all loadings from nonrepaired side combined with the effects from loads from repaired side to verify the structural integrity of the termination interfaces.
EMIB RAI-3:
Attachment F in Enclosure 5 discusses seismic analysis for the design basis earthquake (DBE) combined with emergency operating conditions for service water piping. The seismic analysis of the piping is performed using the analytical software ABAQUS. Attachment F to Enclosure 5 states that seismic ground strain analysis is based on 100-40-40 combination rule described in American Society of Civil Engineers, ASCE/SEI 4-16, Seismic Analysis of Safety-Related Nuclear Structures. Discuss how this seismic analysis compares with the original design criteria. 100-40-40 combination refers to three orthogonal directions. Eight load cases were considered but included only two horizontal directions. The third orthogonal direction (vertical) appears to be not considered. Please provide rationale to justify the approach used.
EMIB RAI-4:
Some recent limited testing data indicates that the glass transition temperature (Tg) is also dependent on the cure temperature. If the actual cure temperature in the field is not high OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION enough, the glass transition temperature, as listed in Enclosure 4, Attachment B, Table 3, of Tg max (( )) may not be achieved. When Tg is very close to Tmax with no
(( )), the epoxy may become rubbery and the CFRP system may lose its structural integrity and therefore capability to support the applied loads.
(a) Provide discussion and any test data on field cure temperature effect, and realistic glass transition temperature achievable with curing temperatures attainable during actual CFRP repair field installation conditions at Brunswick.
(b) Include a detailed discussion to provide assurance that the epoxy will not become rubbery, and the CFRP system will be capable of supporting the applied loading at the maximum operating temperature of (( )). Provide a discussion on how much will be the margin between realistic Tg achievable for curing and installation at Brunswick and maximum operating temperature of (( )).
(c) It appears that Enclosure 6 Attachment C and Enclosure 7 address tension testing and degree of cure testing of witness panels. However, the submittal does not discuss testing for glass transition temperature of the as-installed field cured CFRP repair. The licensee is requested to address testing of witness panels representing the as installed field cured conditions for Tg to demonstrate that Tg Tmax + margin.
(d) The following cautionary note is provided in in Section 401-VIII-4 CURE of ASME PCC 2018 standard.
Caution: Each polymer in the repair system can be cured to a range of glass transition temperatures. Repair systems will not achieve the ultimate glass transition temperature determined by the qualification testing specified in this Standard unless they experience the same temperature for the same period of time as the sample tested. Repairs designed for elevated temperature service will not meet the requirements of this Article unless they are subject to a post-cure (heating) cycle that matches the thermal history of the sample tested during qualification.
Please provide a discussion on whether the Brunswick CFRP piping repair installation will satisfy the above cautionary note.
EMIB RAI-5:
Attachment A to Enclosure 9 discusses operating experience and provides a list of successful applications of CFRP composite systems in piping.
(a) Clarify if any of those listed in Enclosure 9 include similar cure at elevated temperatures, and whether the epoxy used is the same as that planned for use at Brunswick.
(b) Also, clarify if any of those in Enclosure 9 include CFRP repair of steel piping with cement mortar lining.
EMIB RAI-6:
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Attachment C to Enclosure 5 summarizes that the CFRP system design for Brunswick consists of the ((
)).
EMIB-RAI 7:
In Enclosure 5 it is mentioned that the minimum expected ((
)).
((
))
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION EMIB RAI-8:
Attachment C in Enclosure 5 of the submittal provides a summary table of computed
((
)) and for 3 separate soil covers of 12.25 ft, 19.5 ft, and 6.75 ft. The table also provides factor of safety limits for the 9 limit states. Unlike metallic materials, there are many unknown uncertainties associated with CFRP composite materials which are non-isotropic, and the analytical methods. Further, CFRP materials have significant variation in material properties. A-Basis properties are more appropriate for use in safety related ASME Section III design. A review of the table indicates that ((
)). Discuss design improvements or modifications required to satisfy the required factor of safety.
NPHP RAI-1: , Attachment B, Table 2 discusses the ((
)) Enclosure 5, Attachment B provided the ((
))
Clarify whether the ((
))
NPHP RAI-2: , Attachment A, Section 17, page 15 of 36 stated, in part, that:
((
))
Discuss how the CFRP composite system that [
.))
NPHP RAI-3: , Attachment B, page 16 of 17 stated, in part, that:
(( ))
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Clarify whether the ((
))
NPHP RAI-4: , Attachment A, page 3 of 11 stated, in part, that:
It has not been determined whether the cement mortar lining will be removed or remain in place. Hydraulic and structural analysis will be performed to justify either condition, (1) cement mortar lining removed or (2) cement mortar lining remains.
Furthermore, Enclosure 5, Attachment D, page 83 of 122 stated, in part, that:
((
))
(a) For terminal ends, clarify whether the CFRP will be installed on host pipes bare metal or on the concrete mortar lining. If the answer is on the concrete mortar lining, provide justification.
(b) ((
]
(c) ((
))
(d) Clarify whether the pipe metallic substate is catholically protected to minimize the corrosion and loss of metal from outside of the pipe.
(e) RA-20-0353 referenced ASME Code Case N-871, Repair of Class 2 & 3 Piping Using Carbon Fiber Reinforced Polymer Composites, that was approved by the ASME Code.
Clarify why the CFRP composite system and the terminal ends of metallic substrate will not be inspected (e.g., visually, acoustically, or both) following installation at the second period of the current 10-year ISI interval to monitor the soundness of the installed CFRP composite system.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
Package: ML21239A072 Proprietary: ML21239A053 Non-Proprietary: ML21239A065 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-2/LA NRR/DEX/EMIB/BC NAME ZStone RButler ITseng (Acting)
DATE 08/31/2021 08/31/2021 08/25/2021 OFFICE NRR/DNRL/NPHP/BC NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-1/PM NAME MMitchell DWrona ZStone DATE 08/26/2021 08/31/2021 09/08/2021