|
---|
Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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 ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish 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, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 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 IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project 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 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 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal 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 IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) 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 IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 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 ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-2023-110, 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-2023-098, 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-2023-069, 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 ML23151A4362023-05-24024 May 2023 License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5 ML23151A4372023-05-24024 May 2023 Attachment 3: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database ML23095A0082023-04-0404 April 2023 Attachment 2 - Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-051, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information2022-03-29029 March 2022 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information L-2021-213, Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology2021-11-19019 November 2021 Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology L-2021-207, Response to Request for Additional Information for ISI Relief Request No. 102021-10-25025 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 L-2021-197, Response to Request for Additional Information for ISI Relief Request No. 102021-10-15015 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 ML21258A3792021-09-14014 September 2021 Response to Request for Additional Information, Relief Requests 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Extension of Inspection Interval for Turkey Point Unit 3 and Unit 4 Reactor. L-2020-111, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report2020-06-24024 June 2020 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report L-2020-081, Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor2020-06-0808 June 2020 Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor L-2020-083, Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re2020-05-21021 May 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re L-2020-071, Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2020-04-16016 April 2020 Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2020-064, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information2020-04-0909 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information L-2019-135, Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-07-22022 July 2019 Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications ML19158A5032019-06-0707 June 2019 NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Turkey Point ESA Section 7 Consultation L-2019-114, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response2019-06-0404 June 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response L-2019-048, Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 82019-03-15015 March 2019 Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 8 L-2019-037, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses2019-03-0606 March 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses2019-03-0101 March 2019 Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses ML19056A1252019-02-25025 February 2019 Turky Point SLRA RAIs 1 2 3 4 5 6 7 8 9 11 - Set 8 Rev 1 Irradiated Concrete-Steel Responses L-2019-012, Response to Follow-on NRC RAI No. B.2.3.9-1 a2019-02-13013 February 2019 Response to Follow-on NRC RAI No. B.2.3.9-1 a L-2019-023, Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals2019-01-31031 January 2019 Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals L-2018-234, Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision2018-12-21021 December 2018 Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision L-2018-223, Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses2018-12-14014 December 2018 Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses L-2018-222, Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses2018-12-12012 December 2018 Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses L-2018-218, Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review2018-11-28028 November 2018 Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review L-2018-191, Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review2018-11-28028 November 2018 Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review2018-11-0202 November 2018 Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review L-2018-166, WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings.2018-10-31031 October 2018 WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings. ML18299A1142018-10-24024 October 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 4 Responses L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items ML18296A0242018-10-16016 October 2018 Set 3 Response to Request for Additional Information to Subsequent License Renewal Application Safety Review ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal ML18299A1172018-10-12012 October 2018 Framatome Calculation No. 32-9280712, Rev. 002, Tp CRDM Lower Joint Environmentally Assisted Fatigue Dated October 12, 2018 (Non-Proprietary) L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 ML18283A3102018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application Environmental Review L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review L-2018-154, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses2018-09-14014 September 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses 2023-08-07
[Table view] |
Text
NRC FoAM 195 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER IZ 76)
~
FILE NUMBER NRC DISTRIBUTION FoA PART 60 DO CKET MATERIAL TO: Mr G iver ~ Florida Power & Light Co DATE OF DOCUMENT 3-)-77 Miami, Fla R E Uhrig DAT) Q(C)tvL- D QILETTE R 0 NOTOA IZ E D PAOP INPUT FOAM NUMBER OF COPIES RECEIVED Q ORIGINAL IHIUNc LAss IF I E D HfcoPY ~ 1 cc DESCRIPTION ENCLOSURE Ltr trans the following; Response to our 1-12-77 ltr.... furnishing add info re reactor vessel overpressurixration.....
lp 1Pp REACTOR VESSEL OVERPRESSURXZATXON PER G. EECH 10-21-76 'ISTRIBUTION E
PLANT NAME. Turkey Pt 3 & 4 SAFETY FOR ACTION/INFO RiU!ATION 3 7 77 A BRANCH CHXEF: 5 LXC, ASST:
Pl<OJECT MANAGER:
INTERNAL D IST Rl BUTION IH~XI F NR R
& E GOSSXCK & STAFF Mh'IQH ANIL
~~OK X~XBZbH SHAO MER BUTLER 2ECII.
EXTERNAL DISTRIBUTION CONTROL NUMBE R LPOI<: a ~i TIC:
NSIC.
G/SENX eaaa NAC FOAM 196 IZ 7G)
P. O. BOX 013100, MIAMI, FL 33101 Fi((
(egulatory Docket 5
FLORIDA POWERS'CI'GHTCC4MPKAY March 1, 1977 L-77-74 Office of Nuclear Reactor Regulation pP Q)
Attn: George Lear, Chief Operating Reactors Branch 53 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.- C. 20555
'IKflr<>
Dear Mr. Lear:
Phf/QJS ~ fg~It P r "'Ion Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Ove ressurization Issue Your letter of January 12, 1977, requested that Florida Powe
& Light Company (1) identify the manner in which we plan to implement additional overpressure protection; and (2) supply additional information on interim measures being used to re-duce the likelihood of overpressurizat;ion events.
The hardware improvements. we plan to make to preclude ex-ceeding the limits of Appendix G to 10 CPR Part 50, including a schedule for implementation, are described in Attachment A.
Our response to your request for additional information is contained. in Attachment B. The procedural and administrative measures described therein will be continued wherever practical after long-term hardware improvements have been made.
Very truly yours, Robert E. Uhrig Vice President 3 ssgoii ta
~+~ass+~
REU/MAS/hlc .
Attachments (2) cc: Norman C. Moseley, Region IZ 2484 Robert Lowenstein, Esq.
PEQPLE... SERVING PEOPLE
ATTACHMENT A TURKEY POINT UNITS 3 and 4 DOCKET NOS. 50-250 and 50-251 OVERPRESSURIZATION ISSUE I. FPL PROPOSED OVERPRESSURE MITIGATING SYSTEM Our proposed "Overpressure Mitigating System" is an exten-sion of the "Reference Mitigating System" included in our December 10, 1976, submittal. Additional features have been included to be responsive to the design criteria pro-posed at the November 4, 1976, meeting between the NRC staff and utility representatives.
SYSTEM DESCRIPTION The power operated relief valves, equipped with a low set-point feature, will be used as the pressure relieving mechanism. The low setpoint feature is energized and de-energized by the operator by use of an administratively controlled key-lock switch in the control room. The pressure signal for the Overpressure Mitigating System will be obtained from redundant wide range pressure trans-mitters the same transmitters 'that control the RHR suction "valve. interlocks. An interlock with reactor coolant tem-
'perature is included to reduce the probability of inadver-tent actuation. Temperature indication for the interlock is obtained from-the RCS wide range temperature instrumen-tation. Figure 1 presents a functional representation of the proposed syst: em. The proposed low pressure feature parallels and does not override the existing actuation logic.
The power operated relief valves are spring loaded closed and require air to open. The air is presently supplied by a control air source. A redundant supply of air to the valves will be provided through the existing SlS accumula-tor nitrogen supply and pressure regulator with redundant check valves to ensure that backfeeding the air supply does not occur.
III. DESIGN BASES
- 1. OPERATOR ACTION This design will be verified by a detailed analysis
. currently being pursued by Westinghouse Electric Cor-poration. In this analysis, no credit is taken prior to 10 minutes after the operator should for'peration have been made aware of the occurrence.
- 2. SINGLE FAILURE CRITERIA The present power supply alignment of the solenoid valves controlling air flow to the power operated relief valves will be retained. The enable/disable switches on the control board will conform to the separation criteria requirements for the Turkey Point Plant. Utilization of the redundant wide range pressure transmitters completes mechanical and electrical separation of the two power operate'd re-lief valve actuation trains from sensor to valve, thus protecting against failure of one loop.
As outlined in the system description, a redundant air supply will be provided to protect against failure of instrument air.
It is our belief that results of analyses currently being performed by Westinghouse will confirm that.
the capacity of one power operated relief valve of the type installed at Turkey Point is sufficient to mitigate the most restrictive initiating event. In this case, the proposed system provides complete redundancy and protects against any .single failure in the mitigating system.
- 3. TESTABILITY Testability will be provided. Verification of oper-ability is possible prior to. solid-system, low-temperature operation by use of the remotely operated isolation valve, enable/disable switch, and normal electronics surveillance. Testing requirements could be incorporated in the operating procedures to assure performance prior to existence of plant con'ditions requiring operability of the mitigating system.
- 4. SEISMIC DESIGN AND IEEE-279 CRITERIA Seismic design of the electronic equipment. presently installed in the Turkey Point Plant will be retained.
Additional electronic equipment will be installed so-as not to compromise the present seismic qualifica-tions of existing safety systems. The redundant air supply is from the seismic qualified SIS accumulator supply Since the pressure control and alarm instrumentation and electric equipment associated with the Oyerpres-sure Mitigating System are not designated as com-ponents of a "protection system," the requirements of IEEE 279 will not be blanketly applied.
As stated in III.2 above, the proposed system is redundant
and incorporates the separation criteria requirements for the Turkey Point Plant.
As stated in your November 17, 1976, letter documenting the November 4 meeting, the basic objection is that the system should not be vulnerable to an event which causes both a pressure transient and a. failure of equip'ment needed to terminate the transient. The proposed Overpressure Mitigating Syst: em meets and exceeds this requirement by being able to accommodate a single failure in the mitigat-ing system, as well as the initiating event. A more strict application of IEEE 279 and seismic criteria will not appreciably improve the design features of the proposed system, but. would lengthen lead times on materials, thereby lengthening the time before implementation can begin. A stricter interpretation of IEEE 279 would also result in a more extensive backfit program., A more extensive back-fit, just by its complexity, tends to decrease rather than increase the reliability as compared to a more simple back-fit.
IV. With the exception of the redundant air supply, it objective to install the Overpressure Mitigating System is our
. during the next scheduled refueling of each unit (4/77 for Unit 4, 10/77 for Unit 3) . Delivery of required components may preclude this early installation, but with the excep-tion of the redundant air supply, we plan to have the syst: em
.installed by the end of 1977. The redundant air supply is planned to be installed during the scheduled refuelings 'n 1978.
T+AIQ 7R Alki gvro Ci oA A g'cia/ 8 fO PoRVSci.wig pogy+l AstPgf 1 CL ~C Is/ g4)l>CJV 41cfrnR I'vlrCH LocP Hoo&f pgggg Ilies aYB RpR,@MOP Lag IC.
NI IYIQAY SV SY'ag 0iDl4 n /logy POPE'fl IA'PC Pc ms> Rrc il'F VH V4C Vg ~
ATTACHMENT B Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Over ressurization Issue The information in this Attachment is numbered to correspond, to the Additional Information Request enclosed with the Jan-uary 12, 1977, letter from George Lear,, NRC, to Robert E.
Uhrig, Florida Power 6 Light'Company.
- 1. a. Training will be held for all- licensed operators to review applicable overpress'urization events that have occurred at other PHR facilities. The training will be conducted in two ways: (1) A copy of this letter will be included in the weekly training information required to be reviewed by all licensed operators. This review will be com-pleted by June 1, 1977. (2) Formal training will be held as part of the normal operator requalifi-cation program conducted by the Training Depart-ment in discussions with off-shift operators.
This training will be completed for all operators by March 1, 1978.
- b. See l.a above.
- c. & d. The answers to the to these questions will be forwarded NRC by March 15, 1977.
2 ~ a~ A maximum temperature differential of 200'F be-tween the pressurizer and the reactor coolant loop is imposed by the technical specifications to limit the thermal shock which may be imposed upon the surge line connection to the hot leg.
limit, in combination with the pressure Itlimits is this*
for RCP operation, that act to limit operational flexi-bility. An RCS pressure of 325 to 350 psig is re-quired for operation of the RCP's. The associated saturation temperature in the pressurizer is from 406'F to 414'F. In order to maintain the required 200'F hT, it's necessary during plant heatup to run the reactor coolant pump while solid'o heat the RCS and pressurizer concurrently until satura-tion temperature is reached in the pressurizer.
During cooldown, the opposite situation is encoun-tered whereby the pressurizer bubble is collapsed and the, pressurizer circulated to maintain the required hT.
- b. The only pressure limitation associated with RCP operation is to maintain a pressure differential of at least 200 psia across the number one seal.
This condition is normally met if is maintained between 325 and 350 psig.
the RCS pressure The plant procedures that. specify this requirement are:.
1.
2.
O.P. 1001.1 (RCS fill and vent)
O.P. 202.1 (Cold condition to hot shutdown condition)
The reason for this requirement in the fill procedure is to properly vent the RCP's and to cir-and vent culate the RCS to ensure complete venting of the system.
The reason for this requirement in the heat up pro-cedure is to utilize RCP pump heat for system heat up and to ensure isothermal conditions are main-tained during system heat up.
A plant procedure or situation other than those C~
discussed in 2.b that requires a water solid situa-tion is the. plant cool down procedures OP. 0205.2.
This procedure is performed to cool down the RCS if required by. technical specifications or .for maintenance on the system. There is no provision for maintaining a bubble in the pressurizer for the cold shutdown conditions.
- d. The use of a nitrogen br air bubble during these operations is not preferred. Nitrogen and air are non-condensable gases and have compressibility characteristics much "harder" than that of steam.
Large quantities of either gas would be required to provide significant mitigation of overpressure transients, particularly when operator action may not be assumed for ten minutes following initiation.
of the transient. Transition from gas to a steam bubble would necessitate spending additional time in a condition of undesirable pressure control. Holdup '.
and disposal of the required volume of gas is beyond the current capability of the plant.
3 ~ The answer to this question will be forwarded to the NRC by March 15, 1977.
- 4. a. All components and systems that receive a safety injection signal are tested during the emergency safeguards integrated test.'he test is conducted dufing the unit refueling outage.
ln addition, the SIS pumps are tested monthly, and the cold leg injection valves are cycled monthly.
4.b. Initial conditions for the integrated safeguards test specifiy which valves are to be closed to isolate the SIS pumps from the test unit RCS, See attached FSAR Figure 6.2-1 and list of isolation valves. .'OTE: The accumulator, MOV's are closed during'the integrated. test, but are later tested individually.) Normally, this test
'is run with the RCS depressurized.and the head re-moved. However, the procedures list. the necessary precautions for running this test with the system solid. These precautions include monitoring RCS pressure and taking action to ensure the RCS pres-sure does not go above 450 psig.
During the monthly SZS pump test, with one unit at..
cold shutdown, the isolation requirements of the cool down procedure will ensure no accidental in-jection to the shutdown unit during the test. The procedure for val've cycling precludes the possibility of accidental injection caused by cycling more thap one valve at a time. In addition, during cold shut-down conditions, the Nuclear Plant Supervisor is required by procedure to evaluate plant conditions prior to valve cycling.
- 5. a. An alarm will be provided. It will use signals from the redundant wide range pressure transmitters.
It will provide annunciation at the control board in the RCS annunciation panel.
Our objective is to have this alarm installed during the next refueling outage for each unit. Delivery isolation devices may preclude this early of'equired installation, but the alarm should be installed by the end of 1977.
- b. Isolation devices are being added to ensure isola-tion of the two redundant pressure instruments.
Pulling cable is the only additional modification.
c A fixed alarm setpoint of 450 psia is presently being considered. Final results of the analysis being performed by Nestinghouse may require a modi-fication to this setpoint. An audible alarm will be provided. Redundant wide range pressure trans-mitters will provide the signal.
- d. Either or both of the two redundant instrument loops-will initiate the alarm and clearing of the alarm in one loop will not remove the alarm signal,, thus protecting against failure of one loop. A discussion of alarm .surveillance will be forwarded to the NRC by March 15, 1977.
- 6. The answer to this question will be forwarded to the NRC by March 15, 1977..
7 0 'a ~ During the latter part of the cool down procedure, after the system is solid and pressurizer cooled down, the RCP ' are secured. The pressure is main-tained automatically by the charging: and letdown system until the system is depressurized prior to draining.
The system is again returned to the water solid con-dition during the fill and vent procedure. Pressure .
is controlled by the charging and letdown system during the system fill and vent and during system heat up until the pressurizer bubble is drawn.
The RCP's are started and stopped during the and vent, but are continuously running prior fill to drawing the bubble.
- b. See 2.d above.
c ~ There are no temperature limits associated with starting the RCP's in a water solid condition.
- d. See FSAR Figure 4.2-1 for location. of RCS temper--
ature elements.
- e. Prior to securing the RCP's, the RCS is brought to an isothermal condition by cooling down the RCS, removing the steam generators from service, collapsing the bubble, and cooling down the pressur-izer ~
In general, only one is started at a time, and it is allowed to come to second pump is started.
RCP rated speed before the During the fill and vent and heat up procedure, the RCP's are started se-quentially and in a controlled fashion so that thermal transients and pressure spikes will not produce an overpressure condition.
During the solid system pressure operation, the RCP operating procedures specify the following fox restarting an RCP after all pumps have tripped:
- 1. Reduce charging flow to 30 gpm.
- 2. Open all letdown orifice isolation valves.
- 3. Adjust charging and letdown to approxi-mately 325 psig.
- 4. Then restart the RCP ' ~sing the normal starting procedure.
'I
If an RCP is lost after establishing bubble, ensure either the B a pressuiizer or C RCP is started first to establish pressurizer spray flow.
(-'ll'(I'tg""S I NN00 e(tm A 14w 0>> 'f l' 1
~
e Deca ~ 0>>
~ I
) ~
sN~j
~ ot" Ng II ~
I L>> L.>> "J I N I>>
~
~
~
t>>l I 4>> ~
I ev I. ~ ~
~ ~ 4401 ~I N ~~
>>I
~a ~
I llv
~ I ~
I
>>) 1CL".).
I~
~
~>>
N<<l 4 N>> N CI ~
Net 0N 0+4
~
~ ~
0< N>>0 It<0 I ~ ) ~ >> :J
~0 I~ '%(IN
' <>IN
~ I'IJ ~ Vl I>> SIN I
~ ~ ~<
~ ~
~ Il ~ 4 N ~ 4 av 4 I
~ ~
lv>>4 ~ NN
~ N 01
)lo>> I~ I>> NI ~
I<4 ~I ~ 004N te>> ~~
~ ~ ~ ~ 4 N a >><I<44 0.4 ~ llt 4
~ 04 ala<lee <tall<<<vv ~
~ t ~ ~
I lIoe
~
wl ~ I IN 00'0 >>IN ~
$ 00 \4
~
we al ala<4<
l<<t ~a
~ Ie
~ 4 - .'gr:-::- ~ IN
~
I>> >>4 <<N M
~
~ ~ ~
E>>0 ~ 0~ VN/
gi 0004< I va< ~~ ~
He 0 0)40 ~K't<40>>
~ IN 0 <N I~
g' 0 ~ >>>> lea 0>>N N>>>>av ~ I> I Nl>> ~ 0<
4 I<>>4 aa I ~ NSW"
~
'I>> II NW tt>>
~
'l
~
l4 4 44Na
~
~
~ 0 44< <0<01 ~
I I>> IN ~ W ~ I Y
l4LI'I ~ Nl ~ IVN ~
I 40000 ~
I\ II ~ I <<I<< IQ
~ >>
~
0' I It
P' N
~
NI<fle t Il" ta 0 NN << I ~ >>t el <
'iJ-
~
4<0 ~ VN
'~'I(tt >>IV 00 4<1 4N
~ 4<
4 Q>>e I lat
~ ~IN h I 4<< l>>1 IIII
<tool I 4 <ill ~ ~
It'g ~
4 ) 400 ~ jI t>> INN lot I ~I ""Z tfl 4~
~ ~
/ <<I ~
a<a>> N
~ I+i+
IP Jlk >>4 0<< tl Y
.l~ I g<<0 KIIII N A
~
~
>> a<<>>a >>4
~ N>>>><INN ~
~~ ~ l>>I IN I ~ N No>> NW
)>> I<01<+0
~
e 0>> .<0-1 ~ NN l' I, lvl , 10041 I N)<JII
~ > ~ ~ ~ ~ ~ ~ ~0 ~ ~0~0~ ~ ~ 00 ~ 0 ~
~~
k'I<e ~ >> Sl'>>
I walt~ ~ I<001 ~
I I ~ la ~
Ie I>>NN ~ 4 I
'r., ~ 00 I(
(1 tt ~~ ~ ~ ~ ~ 0000 ' ~ ~ 00 0 00000W ~ F 000 ~ 00000 0 0 ~~ ottteo<ot ~ ~ ~~0~ tt F 00 00 ~ ~ tttoe 000 ~ ~ II Ile low<I I ~
wee ~ ~
444J) 4 ~ ~, +44I JS)4 01 VAI.'l(()S CI oSCD 'fa lSot.grf SXS FROH VAI.VCS CI.oSKb la ISal.g+FSX5 Fgog + Fag uaIy Ogham TS.SV'HI.)
gc$ DuRILtg col D sHu~bausN comb)l lode R('S PIIRI4l IsIT'F(4R TCb SAFE uAII.bS fkSl e~W <O SaSA e ke eggs)s ~88BA,S,C, 5D
~ ~