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| | number = ML17048A009 | | | number = ML17048A009 |
| | issue date = 02/28/2017 | | | issue date = 02/28/2017 |
| | title = St. Lucie Plant, Unit No. 2 - Withdrawal of Requested Licensing Action to Revise Period of Applicability of the Pressure-Temperature Limit Curves (CAC No. MF8968) | | | title = Withdrawal of Requested Licensing Action to Revise Period of Applicability of the Pressure-Temperature Limit Curves |
| | author name = Buckberg P H | | | author name = Buckberg P |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Nazar M | | | addressee name = Nazar M |
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| | docket = 05000335, 05000389 | | | docket = 05000335, 05000389 |
| | license number = DPR-067, NPF-016 | | | license number = DPR-067, NPF-016 |
| | contact person = Buckberg P H, NRR/DORL/LPL2-2, 415-1383 | | | contact person = Buckberg P, NRR/DORL/LPL2-2, 415-1383 |
| | case reference number = CAC MF8968 | | | case reference number = CAC MF8968 |
| | document type = Letter | | | document type = Letter |
| | page count = 3 | | | page count = 3 |
| | | project = CAC:MF8968 |
| | | stage = Withdrawal |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 28, 2017 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Co. |
| | Mail Stop NT3/JW 15430 Endeavor Drive Jupiter, FL 33478 |
| | |
| | ==SUBJECT:== |
| | ST. LUCIE PLANT, UNIT NO. 2 - WITHDRAWAL OF AMENDMENT REQUEST (CAC NO. MF8968) |
| | |
| | ==Dear Mr. Nazar:== |
| | |
| | By letter dated December 22, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17006A006), Florida Power & Light Company submitted a license amendment request (LAR) for the St. Lucie Plant, Unit No. 2, Renewed Facility Operating License No. NPF-16. The proposed amendment would have revised the Unit No. 2 period of applicability of the pressure-temperature (P-T) limit curves from 47 effective full power years (EFPY) to 31.98 EFPY and changed the low temperature overpressure protection requirements, which are based on the P-T limit curves, to 31.98 EFPY. Subsequently, by letter dated February 3, 2017 (ADAMS Accession No. ML17037A080), you withdrew the amendment request. |
| | The purpose of this letter is to advise that the above-cited application is being treated as withdrawn. Notice of Consideration of Issuance of the proposed amendment had not been published in the Federal Register. |
| | The results of the U.S. Nuclear Regulatory Commission (NRC) staff amendment request review that occurred prior to the February 3, 2017, withdrawal are as follows: |
| | * The proposed TS P-T limits provided in the LAR address the limiting RPV beltline shell material only. A LAR must address how the proposed TS P-T limits meet the requirements of 10 CFR Part 50, Appendix G for all beltline and non-beltline ferritic RPV materials, as identified in NRC Regulatory Issue Summary (RIS) 2014-11, "Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components," dated October 14, 2014 (ADAMS Accession No. ML14149A165). This includes non-beltline ferritic RPV components with structural discontinuities, such as RPV nozzles and nozzle welds, though these components may have a lesser degree of neutron embrittlement. |
| | |
| | M. Nazar If you have any questions, please contact me at (301) 415-1383 or Perry.Buckberg@nrc.gov. |
| | ~*~ ,/ |
| | Perry H. B ckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389 cc: Distribution via Listserv |
| | |
| | M. Nazar |
| | |
| | ==SUBJECT:== |
| | ST. LUCIE PLANT, UNIT NO. 2 - WITHDRAWAL OF AMENDMENT REQUEST (CAC NO. MF8968) |
| | DISTRIBUTION: |
| | Public RidsNrrLABClayton RidsNrrPMStLucie LPL2-2 R/F RidsNrrDorlLpl2-2 RidsRgn2MailCenter RidsACRS_MailCTR CSydnor, NRR CFairbanks, NRR RidsNrrDeEvib ADAMS Accession Number: ML17048A009 *by e-mail OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DE/EVIB/BC* DORL/LPL2-2/BC DORL/LPL2-2/PM BClayton NAME PBuckberg (LRonewicz for) DRudland BBeasley PBuckberg DATE 02/27/2017 02/27/2017 02/27/2017 02/28/2017 02/28/2017 OFFICIAL RECORD COPY}} |
Letter Sequence Withdrawal |
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Category:Letter
MONTHYEARML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000335/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000335/2024011 and 05000389/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024 Unplanned Reactor Scram L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24093A2612024-04-0202 April 2024 – Investigation Summary, Office of Investigations Case Number 2-2023-005 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes ML24078A2622024-03-26026 March 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24058A1572024-03-19019 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML24017A2092024-03-12012 March 2024 – Issuance of Amendment Nos. 254 and 209 to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage 2024-09-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 28, 2017 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division Florida Power & Light Co.
Mail Stop NT3/JW 15430 Endeavor Drive Jupiter, FL 33478
SUBJECT:
ST. LUCIE PLANT, UNIT NO. 2 - WITHDRAWAL OF AMENDMENT REQUEST (CAC NO. MF8968)
Dear Mr. Nazar:
By letter dated December 22, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17006A006), Florida Power & Light Company submitted a license amendment request (LAR) for the St. Lucie Plant, Unit No. 2, Renewed Facility Operating License No. NPF-16. The proposed amendment would have revised the Unit No. 2 period of applicability of the pressure-temperature (P-T) limit curves from 47 effective full power years (EFPY) to 31.98 EFPY and changed the low temperature overpressure protection requirements, which are based on the P-T limit curves, to 31.98 EFPY. Subsequently, by letter dated February 3, 2017 (ADAMS Accession No. ML17037A080), you withdrew the amendment request.
The purpose of this letter is to advise that the above-cited application is being treated as withdrawn. Notice of Consideration of Issuance of the proposed amendment had not been published in the Federal Register.
The results of the U.S. Nuclear Regulatory Commission (NRC) staff amendment request review that occurred prior to the February 3, 2017, withdrawal are as follows:
- The proposed TS P-T limits provided in the LAR address the limiting RPV beltline shell material only. A LAR must address how the proposed TS P-T limits meet the requirements of 10 CFR Part 50, Appendix G for all beltline and non-beltline ferritic RPV materials, as identified in NRC Regulatory Issue Summary (RIS) 2014-11, "Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components," dated October 14, 2014 (ADAMS Accession No. ML14149A165). This includes non-beltline ferritic RPV components with structural discontinuities, such as RPV nozzles and nozzle welds, though these components may have a lesser degree of neutron embrittlement.
M. Nazar If you have any questions, please contact me at (301) 415-1383 or Perry.Buckberg@nrc.gov.
~*~ ,/
Perry H. B ckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389 cc: Distribution via Listserv
M. Nazar
SUBJECT:
ST. LUCIE PLANT, UNIT NO. 2 - WITHDRAWAL OF AMENDMENT REQUEST (CAC NO. MF8968)
DISTRIBUTION:
Public RidsNrrLABClayton RidsNrrPMStLucie LPL2-2 R/F RidsNrrDorlLpl2-2 RidsRgn2MailCenter RidsACRS_MailCTR CSydnor, NRR CFairbanks, NRR RidsNrrDeEvib ADAMS Accession Number: ML17048A009 *by e-mail OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DE/EVIB/BC* DORL/LPL2-2/BC DORL/LPL2-2/PM BClayton NAME PBuckberg (LRonewicz for) DRudland BBeasley PBuckberg DATE 02/27/2017 02/27/2017 02/27/2017 02/28/2017 02/28/2017 OFFICIAL RECORD COPY