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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
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL O-2SO <~ ./
REC: STELLO V ORG: UHRIG R E DOCDATE: 07/li/78 NRC FL PWR 4 LIGHT DATE 'RCVD: 07/17/78 DOCTYPE: LETTER NOTARIZED: YES COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 40 AMEND. TO LIC. NQS. DPR-31 5 DPR-41 CONSISTING OF PROPOSED CHANGES TO APPEND) X A TECl.l. SPECS. CONCERNING USE 8. SURVEIL'LANCE OF MOTOR OPERATED VALVES... NOTHER I ZED 07/1 1/78.
PLANT NANE:TURKEY PT e3 4-
++++4+++<f++++~~++ 'DISTRIBUTION OF TI..IIS MATERIAL IS'S REVIEWER INITIAL: XEF
'DISTRIBUTOR FOLLOWS INITIAL: ~
GENERAL DISTRIBUTION FOR AFTER ISSUANCE QF OPERATING LICEN E.
(DISTRIBUTION CODE AOOi )
FOR ACTION: B HIEF'RB81 BC++W/7 ENCL INTERNAL: REG FILE /ENCL NRC PDR+>W/ENCL I 8c E++W/2 ENCL OELD4%LTR ONLY IHANAUER~~W/ENCL CORE PERFORMANCE BR>wW/ENCL AD 'FOR SYS 8( PROJ%+W/ENCL ENGINEERING BR4~W/ENCI REACTOR SAFETY. BR+%W/ENCL PLANT SYSTEMS BR>+W/ENCL EEB~~W/ENCL EFFLUENT TREAT SYS<+W/ENCL J. MCGQUGH>sl W/ENCL EXTERNAL: LPDR S MIAMI. FL~~W/ENCL TERA4~W/ENCL NS I C~~W/ENCL ACRS CAT B++Wf16 ENCL 00000000000000000000%00%000000@0000%000000000000000 CHECK NBR: 63 590 AMOUNT: 04r 000. 00 CHECK AND COPY OF TRANSMITTAL LTR ADVANCED 0
- f. TO W. MILLER (LFMB) (07/18/78) 'UPON RECIEPT f 000000000000000000000%00000$ 0$ 000000$ 00000000000000 appP 2 DISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 781990298 SIZE: 2P+2P+1P
%%%%%%%% M%4'%%%%%4%%%%%%4%%%%8M+%%%0& TI.IE END
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FLORIDA POWER 5 LIGHT COMPANY July 11, 1978 L-78-233 Director of Nuclear Reactor Regulation Attention: Nr. Victor,Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555,
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Dear Nr. Stello:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 At the request of the Commission, and in accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.
The proposed amendment is described below and shown on the accompanying Technical Specification page bearing the date of this letter in the lower right hand corner.
Pa e 3.4-2 Technical Specification 3.4.1.a.7 is revised to include motor operated valves 863-A and 863-B. These valves are installed in parallel and,provide a crosstie from the discharge of the RHR, pumps to the SI system. The valves are closed during normal operation and "remain closed upon initial ECCS actuation.
To preclude spurious actuation during the ECCS injection phase, the valves will have power removed from their motor operators by locking open the ci rcuit breakers in the appropriate motor control centers. Power will be restored to the valve operators to accomplish the switchover from the ECCS injection mode to the recirculation mode.
Pa e 3.4-3 Technical Specification 3.4.1.b.7 is added to permit periodic surveillance of the valves specified in 3.4.1.a.7.
The proposed amendment has been reviewed by the Tu'rkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.
They have concluded that it does not involve an unreviewed safety question.
~i .8 82 99P298 P EOP LE... S E RV IN G P EOP LE
0 P pl 0
Director of Nuclear Reactor, Regulation July 11, 1978
'Page Two L-78-233 In accordance with the criteria stated'n 10 CFR 170.22, FPL has determined
.that this is a CLASS I-II amendment. 'A check in the amount of $ 4,000 to cover the requisi:te amendment fee is enclosed.
Very t yours, Robert E. Uhrig Vice President REU/MAS/cpc Enclosures cc: Mr. James P. O'Reilly, Region II Robert Lowenstein, Esquire
~E II
5., TtIO residual hea moval pumps shall be operable.
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- 6. 'TllO residual heat exchangers shall be operable.
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- 7. All valves, interlocks and piping associated with the above components and required for post accident operation, shall be operable, exce'pt valves that are positioned and locked. Valves 862-h&B; 863-A&B; 864-A&B; 865-A,B&C; 866-A&B shall have power removed from their motor operators by locking open the circuit breakers at the Motor Control Centers. The air supply to valve 758 shall be shut off to the valve operator..
- b. During power operation, the requirements of 3.4.la
'may be modified to allow one of the following com-.
ponents to be inoperable (including associated valves and piping) at any one time except for the cases stated
.in 3.4.1 b.2. ,Xf the system is not restored to meet the rcquixements of 3.4'.la within the time period specified; the reactor shall be placed in the hot .
shutdown condition. ,Tf the requirements of 3.4.la are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the reactor sha11 'be placed in the cold shutdown condition.
- l. ONE accumulator may be out of service for a period of up to 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />".
- 2. ONE of FOUR safety injection pumps may be out of service for 30 days. A second safety in-jection pump may be out of service, provided.
the pump is restored to operable status within 24 houxs. TWO of the FOUR safety injection pumps shall be 'tested to demonstrate operabi1ity before.
initiating maintenance of the inoperable pumps-
- 3. ONE channel of heat tracing on the flow path may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.4-2
ih Il
- 5. ONE residual heat exchanger may be out of
-.service for a p~d of'4 hours.
- 6. Any valve in the system may beI inoperablc pro-I vided xepaixs are complctcd wgthin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I Prior to initiating maintenance~ all valves that provide the duplicate function shall be tested to demonstrate operability
- 7. To facilitate surveillance of valve operability, the valves specified in 3.4.l.a.7 may be unloclccd and may have supplied air or electric power restored for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
.2 .EtKRGEHCY CONThLh~iKNT COOLXNG SYSTEHS a The reactor shall not bc made critical~ except for low power physics tests, unless the following conditions are met:
THREE emergency containment cooling unit
.are operablc.
7.. T< 0 containment spray, pumps arc operable All valves'and pij>ing associated with thc'bove com-.
ponent , and required .for post accident operation, arc operable.
'b. During power operation, thc requirements of B.~i.2a may be modified to allow one of the
~ Xollowing conponents to be inoperable (in-eluding associated valves'..nd piping) at any one time. Xf the system is not restored to meet the requirements of 3.4.2a within the time period pecified, the xcactor shall b placed in the hot shutdown condition. Xf the requirements of 3.4.2a are not satisfied within.an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the reactor shall bc placed in the cold shutdown condition.
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STATE OF FLORI DA )
) ss COUNTY OF DADE )
Robert 'E. Uhrig, being first, duly sworn, deposes and says:
That he is a Vice President of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the state-
'ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uh ig Subscribed and sworn to before me this
~/day of 19~/~
I .,
~x NOTA PUBLIC, xn an for he Co nty of Dade, State of Florida A,'W~p WOTASY PUBUC STATE OF FLORfDA It LA'ACC COMMiSSl0.1 EXPNES frAY Bi 'iN My commission expires:
-L Y B'OgPED ~glD fNYNABD BONO!NQ At,'IHEY
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