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| | number = ML030300573 | | | number = ML030300573 |
| | issue date = 01/30/2003 | | | issue date = 01/30/2003 |
| | title = RAI, Request for Relief for Reactor Pressure Vessel Closure Head Penetration Welds. (TAC Nos. MB6379 and MB6380) | | | title = RAI, Request for Relief for Reactor Pressure Vessel Closure Head Penetration Welds. |
| | author name = Moroney B | | | author name = Moroney B |
| | author affiliation = NRC/NRR/DLPM/LPD2 | | | author affiliation = NRC/NRR/DLPM/LPD2 |
Letter Sequence RAI |
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MONTHYEARML0303005732003-01-30030 January 2003 RAI, Request for Relief for Reactor Pressure Vessel Closure Head Penetration Welds. Project stage: RAI ML0317001112003-06-17017 June 2003 Safety Evaluation for Relief Requests Nos. 20, 21, 30 and 31 Reactor Vessel Head Penetration Weld Repair and Flaw Evaluation Project stage: Approval 2003-01-30
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Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24192A2302024-07-10010 July 2024 003 Radiation Safety Baseline Inspection Information Request ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24177A2512024-02-12012 February 2024 Acceptance Review for RR 7-Proposed Alternative - Extension of Inspection Interval for St. Lucie Unit 1 Reactor Pressure Vessel Welds from 10 to 20 Years ML24177A2532024-02-12012 February 2024 Request for Additional Information Relief Request RR 7, Alternative Examination of Reactor Vessel Welds for Florida Power & Light Company, St. Lucie Nuclear Plant, Unit 1 ML23243A9862023-08-31031 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) ML22217A0032022-08-0404 August 2022 SLRA Second Round RAI Letter 1) ML22217A0022022-08-0404 August 2022 Email from Brian Harris (NRC) to Robert Coffey (FPL) - St. Lucie 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 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) 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) 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 2024-07-12
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January 30, 2003 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUESTS FOR RELIEF FOR REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATION WELDS (TAC NOS.
MB6379 AND MB6380)
Dear Mr. Stall:
By letter dated September 26, 2002, Florida Power and Light Company (FPL) submitted a request for relief to use an alternate repair method for control element drive mechanism penetration welds. In addition, FPL requested relief from the requirement to perform flaw characterization.
The U.S. Nuclear Regulatory Commission staff has reviewed your submittal and finds that a response to the enclosed request for additional information (RAI) is needed before we can complete the review. This request was discussed with your staff on January 14, 2003, and Mr. George Madden agreed that a response would be provided within 30 days of issuance.
If you have any questions, please feel free to contact Eva Brown at (301) 415-2315.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389
Enclosure:
RAI cc w/encl: See next page
ML030300573 OFFICE PDII-2/PM PDII-2/PM PDII-2/LA PDII-2/SC NAME BMoroney EBrown BClayton AHowe DATE 1/30/03 1/30/03 1/29/03 1/30/03 Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:
Senior Resident Inspector Mr. R. E. Rose St. Lucie Plant Plant General Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6351 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mr. J. T. Voorhees Division of Emergency Preparedness Acting Licensing Manager Department of Community Affairs St. Lucie Nuclear Plant 2740 Centerview Drive 6351 South Ocean Drive Tallahassee, Florida 32399-2100 Jensen Beach, Florida 34957 M. S. Ross, Attorney Mr. Don Mothena Florida Power & Light Company Manager, Nuclear Plant Support Services P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator Mr. Rajiv S. Kundalkar St. Lucie County Vice President - Nuclear Engineering 2300 Virginia Avenue Florida Power & Light Company Fort Pierce, Florida 34982 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. William A. Passetti, Chief Department of Health Mr. J. Kammel Bureau of Radiation Control Radiological Emergency 2020 Capital Circle, SE, Bin #C21 Planning Administrator Tallahassee, Florida 32399-1741 Department of Public Safety 6000 SE. Tower Drive Mr. Donald E. Jernigan, Site Vice President Stuart, Florida 34997 St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUESTS NOS. 20, 21, 30, AND 31 RELIEF FOR REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATION WELDS SAINT LUCIE PLANT, UNITS 1 AND 2 DOCKET NOS. 50-335 AND 50-389
- 1) Please comment on successive inspection plans for new Reactor Pressure Vessel (RPV) to control element drive mechanism (CEDM) tube pressure retaining welds, which are deposited approximately mid-wall of the RPV head. The discussion should include the types of nondestructive examination that are going to be performed and the frequency. If successive inspections are not going to be performed, provide the technical justification and basis for not performing a successive/repetitive inspection on the new pressure boundary welds.
- 2) Relief Requests Nos. 21 and 31 indicate that calculations, analyses and evaluations discussed within provide the technical basis why this repair methodology provides an acceptable level of quality and safety. Please submit the calculations, analyses and evaluations discussed below from Relief Requests Nos. 21 and 31:
a) American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, stress calculations will be performed to show the flaws are acceptable for a number of years.
b) An analysis of the new pressure boundary welds will be performed using a 3-dimensional model of a CEDM nozzle located at the most severe hillside orientation.
c) A primary stress analysis for design conditions will be performed. A maximum Primary General Membrane Stress Intensity (Pm) will be calculated and shown to be less than the maximum allowed by the ASME Code.
d) The maximum cumulative fatigue usage factor will be calculated, and allowable years of future plant operation will be based on the maximum allowed ASME Code usage factor criterion of 1.0.
e) A fracture mechanics evaluation will be performed to determine if degraded J-groove weld material could be left in the vessel, with no examination to size any flaws that might remain following the repair.
f) Residual stresses will not be included in the flaw evaluations since it will be demonstrated by analysis that these stresses are compressive in the low alloy steel base metal.
g) Flaw evaluations will be performed for a postulated radial corner crack on the uphill side of the RPV head penetration, where stresses are the highest and radial distance from the inside corner to the low alloy steel base metal (crack depth) is the greatest.
Enclosure
h) Fatigue crack growth, calculated for the remaining operational life, should be small, and the final flaw size will be shown to meet the fracture toughness requirements of the ASME Code using an upper shelf value of 200ksi/in for ferritic materials.