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MONTHYEARML0826006582008-09-16016 September 2008 Draft Request for Additional Information - Relief Request 2 - Weld Overlay of Dissimilar Metal Welds Project stage: Draft RAI ML0826006252008-09-16016 September 2008 Draft Request for Additional Information on Relief Request No. 2 Regarding Structural Weld Overlays Project stage: Draft RAI ML0826105072008-09-18018 September 2008 Request for Additional Information on Relief Request for Structural Weld Overlays Project stage: RAI ML0829605462008-11-0303 November 2008 Safety Evaluation of Relief Request to Use Structural Weld Overlay and Alternative Examination Techniques on Safe End Dissimilar Metal Welds Project stage: Approval ML0831506402008-11-19019 November 2008 Corrected Page to Use Structural Weld Overlay and Alternative Examination Techniques on Safe End Dissimilar Metal Welds Project stage: Other ML0835406262008-12-24024 December 2008 Corrected Page to Safety Evaluation of Relief Request to Use Structural Weld Overlay and Alternative Examination Techniques on Safe End Dissimilar Metal Welds Project stage: Approval 2008-12-24
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 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 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23226A0762023-08-14014 August 2023 NRR E-mail Capture - Request for Additional Information - St. Lucie Plant, Units 1 and 2 - Adopt 10 CFR 50.69 (L-2022-LLA-0182) ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23254A4022023-01-24024 January 2023 RP Inspection_2023-001_Document Request ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22325A0692022-11-18018 November 2022 RAI Set 4 ML22270A1482022-09-26026 September 2022 SLRA Second Round RAI Letter 2 - Class 1 Fatigue (Final) ML22217A0022022-08-0404 August 2022 Email from Brian Harris (NRC) to Robert Coffey (FPL) - St. Lucie SLRA Second Round RAI Letter 1) ML22217A0032022-08-0404 August 2022 SLRA Second Round RAI Letter 1) ML22193A0872022-07-11011 July 2022 Letter RAI Set 3 (Final) ML22133A0032022-05-12012 May 2022 SLRA Rai'S Set 1 ML22101A2322022-05-0202 May 2022 Summary of the Environmental Remote Audit Related to the Review of the Subsequent License Renewal Application Enclosure RCIs and RAIs ML22094A1672022-04-0101 April 2022 2022 St. Lucie POV Inspection Information Request ML22075A1212022-03-16016 March 2022 Stl Problem Identification and Resolution (Pi&R) Information Request Final Report ML21350A4262021-12-21021 December 2021 Supplemental Information Needed for Acceptance of Licensing Amendment Request Concerning Technical Specification Conversion to NUREG-1432, Revision 5 ML21119A3142021-04-28028 April 2021 Requests for Additional Information Regarding License Amendment Requests to Apply Risk Informed Completion Times (RICT) for the 120-Volt AC (EPID L-2020-LLA-0283) (Email) ML21063A3192021-03-0404 March 2021 Request for Additional Information Regarding Relief Request RR 15 - Extension of RPV Welds from 10 to 20 Years ML20092G3442020-04-0101 April 2020 RAIs for LAR to Revise Technical Specifications 6.8.4.o, Reactor Coolant Pump Flywheel Inspection Program ML20094G2022020-03-30030 March 2020 Request for Additional Information Regarding License Amendment Request to Adopt EAL Schemes Pursuant to NEI 99-01 (L-2019-LLA-0210) ML19225D3152019-08-13013 August 2019 NRR E-mail Capture - St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Bypass Devices (L-2019-LLA-0106) ML19218A2742019-08-0606 August 2019 Notification of Inspection and Request for Information ML19193A1982019-07-12012 July 2019 Emailed St. Lucie Heat Sink RFI ML19192A1372019-07-11011 July 2019 NRR E-mail Capture - Request for Additional Information - St. Lucie Plant, Unit No. 2, Fall 2018 Refueling Outage Steam Generator Tube Inspection Report ML19192A1352019-06-25025 June 2019 NRR E-mail Capture - Draft Request for Additional Information - St. Lucie Plant, Unit No. 2, Fall 2018 Refueling Outage Steam Generator Tube Inspection Report ML19151A8312019-05-31031 May 2019 NRR E-mail Capture - St. Lucie Plant, Unit Nos. 1 and 2, Request for Additional Information Regarding Emergency Diesel Generator Surveillance Requirement Amendment Request ML19151A5092019-05-21021 May 2019 NRR E-mail Capture - Draft Request for Additional Information - St. Lucie Plant, Unit Nos. 1 and 2 Emergency Diesel Generator Surveillance Requirement Amendment Request ML19109A1392019-04-18018 April 2019 NRR E-mail Capture - St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding the License Amendment Request Pertaining to the Iodine Removal System ML19053A2242019-02-0101 February 2019 NRR E-mail Capture - St. Lucie Plant Unit No. 1 - Draft Request for Additional Information Related to Relief Request 6 Regarding the Refueling Water Tank Bottom Liner L-2018-018, St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181)2018-10-22022 October 2018 St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181) ML18296A2052018-10-22022 October 2018 NRR E-mail Capture - St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181) ML18197A4112018-08-0101 August 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Reduce the Number of Control Element Assemblies ML18019A0712018-01-18018 January 2018 NRR E-mail Capture - Request for Additional Information - St. Lucie Inop AFW Steam Supply LAR (L-2017-LLA-0296) ML17331B1532017-11-27027 November 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie IST Relief Request #5 - PR-01 (L-2017-LLR-0113) ML17277A3692017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie Rict LAR - MF5372/MF5373 ML17152A1842017-06-0101 June 2017 Request for Additional Information - RPS Rate of Change and LCO Change LAR (CACs MF9119 9120) ML16356A1432016-12-20020 December 2016 Notification of Inspection and Request for Information ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16308A3232016-11-0303 November 2016 NRR E-mail Capture - Request for Additional Information - St. Lucie EDG Day Tank LAR - MF8006 ML16292A8212016-10-14014 October 2016 Emergency Preparedness Inspection and Request for Information ML17003A0452016-10-11011 October 2016 NRR E-mail Capture - (External_Sender) FW: St. Lucie Response to RAI on SL2-22 SG Tube Inspection Report (MF7604) ML16244A2602016-08-26026 August 2016 Notification of Inspection and Request for Information ML16155A3502016-06-0303 June 2016 Notification of Inspection and Request for Information ML16089A0052016-03-28028 March 2016 NRR E-mail Capture - Request for Additional Information - St. Lucie Srxb Mtc Surv - MF7269 & MF7270 ML16077A1062016-03-17017 March 2016 NRR E-mail Capture - Request for Additional Information - St Lucie Vacuum Gothic LAR - MF6980/MF6981 ML16068A2612016-03-0808 March 2016 NRR E-mail Capture - Request for Additional Information - St Lucie TSTF-422 - MF6683/MF6684 ML16068A0412016-03-0808 March 2016 NRR E-mail Capture - Request for Additional Information - St Lucie Unit 1 Relief Request No. 10 - MF6685 ML16013A2152016-01-13013 January 2016 NRR E-mail Capture - St. Lucie RAIs (Rvi Aging Management Plan) MF6777 and MF6778 ML15336A8882015-12-16016 December 2015 Request for Additional Information Regarding License Amendment Request for Changes to the Snubber Surveillance Requirements ML15308A6152015-11-23023 November 2015 Request for Additional Information on License Amendment Request for Changes to the Required Actions for Inoperability of Auxiliary Feedwater Pumps ML15233A0362015-09-0404 September 2015 Redacted Request for Additional Information Regarding Proposed License Amendment Request and Exemption Request to Allow the Transition to Areva Fuel 2023-08-31
[Table view] |
Text
September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 - RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)
Dear Mr. Stall:
By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.
This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008. It was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.
Sincerely, /RA/ Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335
Enclosure:
Request for Additional Information cc: See next page
REQUEST FOR ADDITIONAL INFORMATION ST. LUCIE NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-335 By letter dated April 29, 2008, Florida Power & Light proposed an alternative Relief Request 2 (RR-2) to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, for mitigating primary water stress corrosion cracking on dissimilar metal welds using full structural weld overlays at St. Lucie, Unit 1 (SL-1). Currently, the U.S. Nuclear Regulatory Commission (NRC) staff has approved the use of ASME Section XI Code Cases N-504-3, "Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Section XI, Division 1,: and N-638-1, "Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique Section XI, Division 1." The NRC staff used the requirements of Code Cases N-504-3 and N-638-1 and NRC-approved criteria associated with similar full structural weld overlay (SWOL) applications to aid in the evaluation of the SL-1, RR-2, Attachment 2. To complete its review, the staff is requesting the following additional information: 1. Discuss whether the subject nozzles have been ultrasonically examined under the Inservice Inspection (ISI) program or Electric Power Research Institute report, MRP-139 in previous refueling outages. If so, discuss whether flaws have been detected in the subject nozzles. 2. In Section 1.1, page 1, the Examination Category for the subject welds is identified as R-A. This is a risk-informed ISI (RI-ISI) examination category. (A) Discuss whether after the weld overlay installation, will the ISI examinations be based on the RI-ISI program or the proposed Relief Request No. 2 (RR-2)? (B) Discuss whether the subject welds will be removed from the RI-ISI program after the weld overlay installation. 3. Paragraph 2(a) of Attachment 2 of RR-2 states that the size of all flaws detected or postulated in the original weldment shall be projected to the end of the expected life of the overlay. Provide/describe the expected life of the overlay. 4. Paragraphs g(2) and g(3) of American Society of Mechanical Engineers (ASME) Code Case N-504-3 require evaluations of residual stresses and flaw growth of the repaired weldments. Section 2 of Attachment 2 to RR-2 requires similar evaluations. Section 2(b)7 of Attachment 2 states that effects of any changes in applied loads, as a result of weld shrinkage from the entire structural weld overlay on other items in the piping system, shall be evaluated. (A) Confirm that the analysis will be performed to show that the requirements of Subarticles NB-3200 and NB-3600 of the ASME Code, Section Ill are satisfied. (B) Confirm that the analysis includes the crack-growth calculations to demonstrate that crack growth in the weld overlay or base metal is acceptable and residual stress distribution in the weld overlay and original weld demonstrate favorable stress distribution. (C) The staff requests that the licensee submit the preliminary results of the evaluations prior to entry into Mode 4 from the refueling outage and the final evaluations within 60 days of the plant restart.
- 5. Paragraph I-2.1(g)(2) of Mandatory Appendix I of Attachment 2 to RR-2 provides a means of determining an Adjustment Temperature for the welding procedure qualification. This Adjustment Temperature was not a part of Code Case N-638-1 and, therefore, has not been approved by the U.S. Nuclear Regulatory Commission (NRC) staff. Explain the technical basis of this requirement. 6. Section 5.2 of RR-2, states that a barrier layer of austenitic stainless steel filler metal across the austenitic stainless steel base metal will be used to reduce the risk of cracks.
(A) Discuss whether paragraph (e) of Code Case N-504-3 is applicable to the barrier layer if austenitic stainless steel filler metal is applied. Paragraph (e) requires existence of certain delta ferrite content in the welded metal when austenitic stainless steel weld metal is used. (B) Identify the austenitic stainless steel weld filler metal that will be used for the butter layer. (C) Confirm that the Certified Material Test Report (CMTR) for the austenitic stainless steel filler wire shows a minimum delta ferrite of a specified amount. Provide the maximum and minimum delta ferrite content for the heat of austenitic stainless steel filler wire to be used, as stated on the CMTR. 7. What are the beginning and end dates for the fourth 10-year ISI interval at SL-1? 8. The following typographical errors were identified in the proposed alternative and should be corrected: (A) On page 6, on the second line of the first full paragraph 2(b)(6) should be 2(b)(5), on the third line of the same paragraph 2(b)(7) should be 2(b)(6), on the eighth line of the paragraph 2(a)(2)(b) should be 2(a)(2)(a). (B) On page 25, Section 2(a)(2)(b) in the third line "(b) or (c) above" should be deleted. (C) On page 26, Section 2(b)(6) in the sixth line 2(b)(4), (5), or (6) should be 2(b)(3), (4), or (5). (D) On page 36, Section I-2.1(f) should be changed to I-2.1(f)(4). 9. Mandatory Appendix I to Attachment 2 of RR-2 Section I-3(e) lists a number of methods that can be used in the welding procedure to determine interpass temperature. The staff's position is that the temperature measurement in 1-3(e)(1) should be used. If 1-3(e)(1) cannot be performed, 1-3(e)(2) or 1-3(e)(3) may be used. Please describe the method that will be used at SL-1 and provide a discussion of its acceptability. 10. Section 3(c)2 of Attachment 2 of RR-2 states no credit can be given in any portion of the examination volume where the ultrasonic beam passes through the cast stainless steel material. (A) Provide the weld overlay thickness. (B) Provide reduction in ultrasonic testing (UT) volume coverage for the weld overlay locations that involve cast stainless steel safe-ends, including estimated total UT examination coverage for preservice and ISI per sections 3(b) and 3(c) of RR-2. Discuss why reduction in examination coverage is acceptable. (C) Discuss whether a phased-array UT technique will be used in the volumetric examination. 11. Attachment 2 of RR-2, page 23, first paragraph, states that, "All Section XI references are to the 2004 Edition with the 2006 Addenda . . . ." This statement is not applicable to SL-1 and should be eliminated because the code of record for the SL-1 fourth 10-year ISI interval in which RR-2 is applicable is the 2001 Edition through 2003 Addenda. In addition, Table 1 of Attachment 2 can be deleted since the additional code references do not apply. The staff notes that the NRC has not incorporated by reference the 2005 and 2006 Addenda of the ASME Code in Title 10, Code of Federal Regulations, Section 50.55a. 12. Section 2.0 of Attachment 2 of RR-2 states that the code of record for the current ISI 10-year interval is, "Section XI, 2001 Edition including Addenda through 2003 and 2001 with 2001 Addenda for Appendix VIII . . . ." Please clarify the ASME Code Edition and Addenda that will be used for performance demonstration initiative examination per the ASME Code,Section XI, Appendix VIII because the 2001 Addenda of the ASME Code do not exist.
September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 - RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)
Dear Mr. Stall:
By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.
This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008, it was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.
Sincerely, /RA/
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-335
Enclosure:
Request for Additional Information cc: See next page DISTRIBUTION
- PUBLIC RidsOgcRp RidsNrrDorlDpr LPL2-2 R/F RidsAcrsAcnwMailCenter RidsNrrDciCpnb RidsNrrPMBMozafari RidsRgn2MailCenter K. Hoffman RidsNrrLABClayton (Hard Copy) RidsNrrDorlLpl2-2 T. Chan ADAMS Accession Number: ML082610507 NRR-088 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA DCI/CPNB LPL2-2/BC NAME TOrf BMozafari BClayton TChan By memo dated TBoyce (BMoroney for) DATE 9/18/08 9/18/08 9/18/08 9/18/08 9/18/08 OFFICIAL RECORD COPY Florida Power and Light Company ST. LUCIE PLANT cc:Mr. Mano Nazar Senior Vice President and Nuclear Chief Operating Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408 Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Managing Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW. Suite 220 Washington, DC 20004 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Mr. Gordon L. Johnston Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000 Mr. Christopher R. Costanzo Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. Terry Patterson Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957
Don E. Grissette Vice President, Nuclear Operations, South Region Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Abdy Khanpour Vice President - Engineering Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 Southeast Tower Drive Stuart, Florida 34997
Mark E. Warner Vice President, Nuclear Plant support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Peter Wells, Acting VP, Nuclear Training and Performance Improvement Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Michael Page Acting Operations Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000