Letter Sequence Request |
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TAC:MF6560, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Open) |
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Category:Letter type:L
MONTHYEARL-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports 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 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-2024-122, 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-2024-100, 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-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update 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-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 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-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports 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-2024-044, 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, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 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 Owners Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owners 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-2023-172, 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 Owners Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owners 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 2024-09-25
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L-2015-181 FPL, 10 CFR 50.90 July 7, 2015 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 Changes to License Amendment Request 229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
References:
- 1. Florida Power & Light Company letter L-2014-033, "License Amendment Request No.
229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program," April 9, 2014 [ML14105A042]
- 2. NRC letter "Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information on License Amendment Request to Revise Technical Specifications to Implement TSTF-425, Revision 3, 'Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specifications (RITSTF) Initiative 5B' (TAC Nos.
MF3931 and MF3932)," August 7, 2014 [ML14212A713]
- 3. Florida Power & Light Company letter L-2014-266 "Response to NRC Technical Specifications Branch Request for Additional Information Regarding License Amendment Request No. LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program," August 29, 2014
[ML14252A228]
- 4. Florida Power & Light Company letter L-2015-022, "Supplement to License Amendment Request 229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program," April 3, 2015 [ML15113A311]
In Reference 1 and supplemented by References 3 and 4, Florida Power & Light Company (FPL) submitted a request for an amendment to the Technical Specifications (TS) for Turkey Point Units 3 and 4. The proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." The changes are consistent with U.S. Nuclear Florida Power & Light Company "co 9760 SW 344 St Homestead, FL 33035 Lt4
L-2015-181 Page 2 of 3 Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control- RITSTF [Risk-Informed TS Task Force] Initiative 5b," Revision 3.
Subsequent to submission of the referenced documents, FPL identified that several of the proposed changes to the TS require modifications or corrections. This supplement to the license amendment request (LAR) modifies and corrects several of the proposed changes. The attachment provides revised markups of the affected TS pages showing the proposed changes to the Turkey Point TS. The TS markups in this supplement supersede the corresponding markups previously submitted in References 1, 3, and 4.
" Modifications to Surveillance Requirements (SRs) for Control Rod Position Indication In Reference 4, FPL proposed deleting TS Table 4.1-1, Rod Position Indicator Surveillance Requirements, and revising SR 4.1.3.2.2 for the analog rod position indication system and SR 4.1.3.3.2 for the group step counter demand position indicator. The changes proposed in Reference 4 are deleted and replaced with those originally provided in Reference 1 where Table 4.1-1 is retained in the TS. The attachment contains a markup of the TS showing the proposed changes.
- Modifications to SR 4.8.1.1.2i for the Diesel Generator Fuel Oil System In Reference 3, FPL revised its proposed changes so that items 1 and 2 under SR 4.8.1.1.2i have different frequencies. However, the numbering format was not adjusted to be consistent with the proposed change. To resolve this discrepancy, the attachment contains a markup of the TS showing the SRs renumbered from 4.8.1.1.2i.1 and 4.8.1.1.2i.2 to 4.8.1.1.2i and 4.8.1.1.2j, respectively.
- TS Index The proposed changes resulted in changes to the page numbers in section 6 of the TS. As a result, the attachment contains a revised TS index that incorporates the changes to the page numbers.
- Typographical Corrections Reference 4 discussed that it corrected two misspellings in SR 4.8.1.1.2.f. The corrections were made to SR 4.8.1.1.2.a.
The changes provided in this supplement are editorial in nature and do not alter the conclusion in the LAR that the proposed changes do not involve a significant hazards consideration.
This supplement to the LAR contains no new regulatory commitments and does not modify any existing commitments.
L-2015-181 Page 3 of 3 These changes have been reviewed by the Turkey Point Plant Nuclear Safety Committee.
Pursuant to 10 CFR 50.91 (b)(1), a copy of this submittal is being forwarded to the designated State of Florida official.
Should you have any questions regarding this submittal, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July 7, 2015.
Sincerely, "ZThomas Summers Site Vice President Turkey Point Nuclear Plant
Attachment:
Technical Specification Mark-ups cc: NRC Regional Administrator, Region II NRC Senior Resident Inspector NRC Project Manager Ms. Cindy Becker, Florida Department of Health
L-2015-181 Attachment ATTACHMENT Turkey Point Mark-ups of Technical Specification Pages (six pages follow)
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 DELETED 6.7 DELETED 6.8 PRO CEDURES AND PRO G RA MS ...................................................................................
6.9 REPO RTING REQ UIREM ENTS ........................................................................................
6.9.1 RO UTINE REPO RTS ....................................................................................................
Startup Report .........................................................................................................
Annual Reports ........................................................................................................
Annual Radiological Environm ental O perating Report ............................................
Annual Radioactive Effl uent Release Report ..........................................................
Peaking Factor Lim it Report ....................................................................................
Core O perating Lim its Report ..................................................................................
Steam G enerator Tube Inspection Report ..............................................................
6.9.2 SPEC IAL REPO RTS ..................................................................................................... 6 6.10 DELETED TURKEY POINT - UNITS 3 & 4 xvi AMENDMENT NOS. 260 AND 2456
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.11 DELETED 6.12 HIG H RA D IATIO N AREA ............................................................................................... 6-20 6.13 DELETED 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) ................................................... 6-24 TURKEY POINT - UNITS 3 & 4 xvii AMENDMENT NOS. 269 AND 266
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.2.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the Demand 9.
Position Indication System and the Analog Rod Position Indication System agree within the Allowed Rod Misalignment of Specification 3.1.3.1 (allowing for one hour thermal soak after rod motion) -t 1 ..-- pc, 12 hews except during time intervals when the Rod Position Deviation Monitor is inoperable, then co pare the Demand Position Indication System and the Analog Rod Position Indication System at least once r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.2.2 Each of the above required analog rod position indicator(s) shall be determined to be OP RABLE .R by performance of a CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPE TIONAL TEST performed in accordance with Table 4.1-1.
Insert 1 TURKEY POINT - UNITS 3 & 4 3/4 1-21 AMENDMENT NOS. 2-*&AND 2
Replace each marked through Surveillance Frequency with "SFCP".
TABLE 4.1-1 ROD POSITION INDICATOR SURVEILLANCE REQUIREMENTS Functional Unit Check Calibration Operational Test Individual Rod Position -R- ----
-.6---
Demand Position N/A TURKEY POINT - UNITS 3 & 4 3/4 1-22 AMENDMENT NOS. 1-3-AND 4-32
REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 The group step counter demand position indicator shall be OPERABLE and capable of determining within
+/- 2 steps the demand position for each shutdown and control rod not fully inserted.
APPLICABILITY: MODES 3* **, 4* **, and 5***
ACTION:
With less than the above required group step counter demand position indicator(s) OPERABLE, open the reactor trip system breakers.
SURVEILLANCE REQUIREMENTS 4.1.3.3.1 Each of the above required group step counter demand position indicator(s) shall be determined to be OPERABLE by movement of the associated control rod at least 10 steps in any one direction Pat e*,e per 34
-day*g. lInsertl1 4.1.3.3.2 OPERABILITY of the group step counter demand position indicator shall be verified in accordance with-...
Table 4.1-1.
- With the Reactor Trip System breakers in the closed position.
See Special Test Exceptions Specification 3.10.5.
TURKEY POINT - UNITS 3 & 4 3/4 1-23 AMENDMENT NOS. 449 AND 444-
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued')
I*lnsert I
- h. At- loc o...pr.0 yar,* or after any modifications which could affect diesel generator interdependence by starting all required diesel generators simultaneously and verifying that all required diesel generators provide 60 +/- 0.6 Hz frequency and 3950-4350 volts in less than or equal to 15 seconds: and Iln accordance with the Surveillance
- 4. .A.t le -AStAc,*,cc Pe; !Frequency Control Program by draining
[-i.-4-I -+ each fuel oil storage tank, removing the accumulated sediment and cleaning the tank.* At least once per 10 years for Unit 4 only by F 7-]J 2H Ut 4 9,performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
4.8.1.1.3 Reports - (Not Used)
- A temporary Class III fuel storage system containing a minimum volume of 38,000 gallons of fuel oil may be used for up to 10 days during the performance of Surveillance Requirement 4.8.1.1.2i4 for the Unit 3 storage tank while Unit 3 is in Modes 5, 6, or defueled. If the diesel fuel oil storage tank is not returned to service within 10 days, Technical Specification 3.8.1.1 Action b and 3.8.1.2 Action apply to Unit 4 and Unit 3 respectively.
TURKEY POINT - UNITS 3 & 4 3/4 8-10 AMENDMENT NOS. 260 AND 26-,