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Category:Letter type:L
MONTHYEARL-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 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 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-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 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-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports 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 L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2024-02-0909 February 2024 Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles 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) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule 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, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-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 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. 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-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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 L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, 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 Applications2023-03-27027 March 2023 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 2024-08-12
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REGULATORY INFORMATION DISTRIBUTION YSTEM (RIDS>
DISTRIBUTION FOR INCOMING MATERIAL 50-250 2 1 REC: STELLO V ORG: UHRIG R E DOCDATE." 07/20/78 NRC FL PWR 8. LIGHT DATE RCVD: 07/28/7".
DOCTYPE: LETTER NOTARIZED: NO COP I E RECEIVED
SUBJECT:
LTR 3 ENCL 40 FORWARDING SUPPLEMENT TO APPLICANT"S 07/10/78 PROPOSED AMEND TO LIC NOS DPR-31 4 41 RE FULL PWR OPERATION WITH UP TO 25/. OF STEAM GENERATOR TUEWES PLUGGED'ONSISTING OF NON LOCA ACCIDENTS SAFETY EVALUATION FOR HIGHER LEVELS OF STEAM GENERATOR TUBE PLUGS /<4 PLANT NAME: TURKEY PT 03 REVIEWER INITIAL: X JM TURKEY PT 04 DISTRIBUTER INITIAL: ~
DISTRIBUTION QF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION: BR CHIEF ORB01 BC4+W/7 ENCL INTERNAL: R G F L~M W/ENCL NRC PDR+4W/ENCL E~~W/2 ENCL OELD++'LTR ONLY HANAUER++W/ENCL CORE PERFORMANCE BR>+W/ENCL AD FOR SYS 8( PROJ+4W/ENCL ENGINEERING BR++A/ENCL REACTOR SAFETY BR44W/ENCL PLANT SYSTEMS BR+>W/ENCL EEB~~W/ENCL 'EFFLUENT TREAT SYS+4W/ENCL J. MCGOUGH+4W/ENCL EXTERNAL: LPDR S MIAMIi FL++W/ENCL TERA++W/ENCL NSIC4+WfENCL ACRS CAT B>+W/16 ENCL DISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 7820~0005 S I ZE: 3P+43P THE END %4 4 +%4%%4 %%%44 %0%%%%%4 %4%%%%%%4%4 4
r"LQF!1D* pGSVHR ~o s lo'iti COiVipAAY July 20, l978 L-78-242 Office of Nuclear Reactor Regulation Attention: Hr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Coranission Washington, D. C. 20555
Dear Nr. Stello:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Supplement to Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 Florida Power & Light Company (FPL) letter L-78-230 of July 10, 1978, con-tained proposed amendments to the Turkey Point Units 3 and 4 Operating Licenses to allow full power operation with up to 25K of the steam generator tubes plugged. The proposed amendments resulted from an evaluation of non-LOCA transients. An analysis of the LOCA transients, which could lead to further proposed amendments, is scheduled to be submitted by August 10, 1978.
On July 12, after receipt of the FPL July 10 submittal, the NRC staff initiated a telephone conference call to discuss the FPL safety evaluation submitted in support of the proposed amendments. During the phone call, FPL representatives and the NRC staff scheduled a meeting for the purpose of continuing the discussi on. The meeting was held on July 13, 1978. As a result of the meeting, it was agreed that FPL would submit a supplement to the July 10 lette~ containing a corresponding evaluation developed by the NSSS vendor . The NSSS vendor analysis is attached. The difference between it and the FPI analysis is as follows:
a) Section 3.2 - Evaluation The NSSS vendor did not consider the effects of fuel rod bow in the evaluation and recommended that the generic rod bow penalty on F~H be applied. Where appropriate, FPL modified the evalua-tion such that it included the effects of a rod bow penalty, consistent with a previous submittal (FPL letter L-77-106 of April 4, 1977) and showed that the rod bow penalty could be ab-sorbed ~iithout a reduction in F~H. Any other differences are edi tori al in nature.
b) Section 3.3.1 -, Uncontrolled Control Rod Assembl Mithdrawal at Power
/
The NSSS vendor reanalysis did not include the development of new transient curves. Instead the NSSS vendor examined the setpoints and concluded that there was substantial margin in the current toe~
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Office o f Nuclear Reactor Regulation Page Three Please call if you have further questions regarding this or previous submittals ~
Very truly yours, Robert E. Uhrig Vice President REU/MAS/RDH/cpc Attachment cc: Mr. James P. O'Reilly, Region EI Robert Lowenstein, Esquire
Office of Nuclear Reactor Regulation Page Two (FSAR) Overtemperature dT setpoint and that the Overpower aT setpoint should be changed. FPL performed a reanalysis of the transients with the setpoints developed by the NSSS vendor with the rod bow penalty included and showed that the DNBR limits were not violated. The Overpower aT and Overtemperature aT setpoints resulting from the two reanalyses are therefore identical.
c) Section 3.3.2 - Loss of'eactor Coolant Flow Flow Coast-Down ccident The NSSS vendor reanalysis did not consider the effects of fuel rod bow. FPL modified the reanalysis to include a rod bow penalty.
Although the vendor reanalysis did not consider rod bow, the minimum DNBR obtained by the vendor during the transient is 1.48. This value shows that the effect of rod bowing can be accommodated wi thout penalizing any operating parameter.
d) Section 4.0 Technical S ecifications The only difference between the Technical Specifications proposed by the NSSS vendor and FPL are the Reactor Core Thermal and Hydraulic Safety Limits curves, Figure F 1-lb. In generating these curves the vendor did not include the effects of rod bow penalty, but FPL did. The FPL curves were developed using the COBRA code exclusively, in conformance wi th the methods used to generate the companion curves, submitted in FPL letter L-78-217 on June 22, 1978, for lesser amounts of steam generator tube plugging. As the rod bow penalty is already included in these curves, there is no need for any further penalty to the F<H limit or to any other operating parameter.
e) Section 6.0 - References FPL requests a timely review of their Safety and Fuel Management Analysis Methods (Reference 6) and of the DYNODE-P Code (Reference 7),
as these methods and codes are to be used in future analyses to be submitted by FPL in support of licensing actions .
A question was raised at the J'uly 13 meeting concerning the NSSS vendor's use of a modified FLARE code on the Unit 4, Cycle 5 design (refer to Unit 4, Cycle 5 Reload Safety Evaluation, FPL letter L-78-210, dated June 19, 1978).
Me have discussed the use of this code with NSSS vendor representatives, and they have verified that all uses of the FLARE model for the cycle 5 design
,.were backed up (confi rmed) with the use of their standard methods.