ML24073A171: Difference between revisions

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Bob Coffey Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Bob Coffey Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408
Juno Beach, FL 33408


==SUBJECT:==
==SUBJECT:==
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 -
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 -
CORRECTION OF AMENDMENT NOS. 297 AND 290 REGARDING CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS (EPID L-2021-LLI-0002)
CORRECTION OF AMENDMENT NOS. 297 AND 290 REGARDING CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS (EPID L-2021-LLI-0002)


==Dear Bob Coffey:==
==Dear Bob Coffey:==
On September 26, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 297 to Subsequent Renewed Facility Operating License No. DPR-31 and Amendment No. 290 to Subsequent Renewed Facility Operating License No. DPR-41 to Florida Power and Light Company (the licensee) for to the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point), respectively (Agencyw ide Documents Access and Management System (ADAMS) Accession No. ML23234A192).


On September 26, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 297 to Subsequent Renewed Facility Operating License No. DPR-31 and Amendment No. 290 to Subsequent Renewed Facility Operating License No. DPR-41 to Florida Power and Light Company (the licensee) for to the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point), respectively (Agencyw  ide Documents Access and Management System (ADAMS) Accession No. ML23234A192).
These amendments convert the current technical specifications (TS) to the improved TS (ITS) and relocates certain requirements to other lic ensee-controlled documents. The ITS are based on:


These amendments convert the current technical specifications (TS) to the improved TS (ITS) and relocates certain requirements to other lic  ensee-controlled documents. The ITS are based on:
NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 5.0; Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132); and Title 10 of the Code of Federal Regulations, Part 50, Section 36, Technical specifications.
 
NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 5.0; Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132); and Title 10 of the Code of Federal Regulations , Part 50, Section 36, Technical specifications.


After issuance of the amendments, it was identified that there was an inadvertent error on ITS page 3.3.2-13. The trip setpoint of function 7b, ESFAS [Engineered Safety Feature Actuation System] Interlocks, T avg - Low of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, should state Nominal 543 °F [degrees Fahrenheit], however the page was issued as Nominal 543 psig [pounds per square in gauge]. In {{letter dated|date=May 24, 2023|text=letter dated May 24, 2023}} (enclosure 2) (ML23151A446), the licensee requested the trip setpoint of function 7b, ESFAS Interlocks, Tavg - Low of Table 3.3.2-1 to state Nominal 543 °F. The NRC staff reviewed ITS page 3.3.2-13, as requested, however during issuance, the error was introduced.
After issuance of the amendments, it was identified that there was an inadvertent error on ITS page 3.3.2-13. The trip setpoint of function 7b, ESFAS [Engineered Safety Feature Actuation System] Interlocks, T avg - Low of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, should state Nominal 543 °F [degrees Fahrenheit], however the page was issued as Nominal 543 psig [pounds per square in gauge]. In {{letter dated|date=May 24, 2023|text=letter dated May 24, 2023}} (enclosure 2) (ML23151A446), the licensee requested the trip setpoint of function 7b, ESFAS Interlocks, Tavg - Low of Table 3.3.2-1 to state Nominal 543 °F. The NRC staff reviewed ITS page 3.3.2-13, as requested, however during issuance, the error was introduced.


B. Coffey                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                      
B. Coffey  


The NRC concludes that this correction does not change the NRC staffs previous conclusions in the safety evaluation, nor do they affect the no significant hazards consideration, as published in the Federal Register on June 14, 2022 (87 FR 36003). The enclosure contains corrected page 3.3.2-13.
The NRC concludes that this correction does not change the NRC staffs previous conclusions in the safety evaluation, nor do they affect the no significant hazards consideration, as published in the Federal Register on June 14, 2022 (87 FR 36003). The enclosure contains corrected page 3.3.2-13.


If you have any questions regarding this matter, please contact me at (301) 415-3867 or by email at Michael.Mahoney@nrc.gov.
If you have any questions regarding this matter, please contact me at (301) 415-3867 or by email at Michael.Mahoney@nrc.gov.
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Sincerely,
Sincerely,


                                                                                /RA/
/RA/


Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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==Enclosure:==
==Enclosure:==
Corrected ITS page 3.3.2-13
Corrected ITS page 3.3.2-13


cc: Listserv ESFAS Instrumentation 3.3.2
cc: Listserv ESFAS Instrumentation 3.3.2


Table                     3.3.2-1 (page                                                                                       7 of 7)
Table 3.3.2-1 (page 7 of 7)
Engineered Safety Feature Actuation System Instrumentation
Engineered Safety Feature Actuation System Instrumentation


APPLICABLE MODES OR OTHER SPECIFIED                   REQUIRED                                             SURVEILLANCE                       ALLOWABLE FUNCTION                               CONDITIONS                   CHANNELS               CONDITIONS                 REQUIREMENTS                             VALUE                 TRIP SETPOINT
APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE TRIP SETPOINT
: 7.       ESFAS Interlocks
: 7. ESFAS Interlocks
: a.                               Pressurizer     1,2,3                           2                       K                 SR 3.3.2.3                         2018 psig                     Nominal Pressure, P-11                                                                                                         SR 3.3.2.6                                                         2000 psig
: a. Pressurizer 1,2,3 2 K SR 3.3.2.3 2018 psig Nominal Pressure, P-11 SR 3.3.2.6 2000 psig
: b.                               Tavg - Low       1,2,3                           2                       K                 SR 3.3.2.3                           542.5°F                     Nominal SR 3.3.2.6                                                         543°F
: b. Tavg - Low 1,2,3 2 K SR 3.3.2.3 542.5°F Nominal SR 3.3.2.6 543°F


Turkey Point Unit 3 and Unit 4                                                                                                                                                                                                                                       3.3.2-13                                                                                                                                                                                                                         Amendment Nos. 297 and 290
Turkey Point Unit 3 and Unit 4 3.3.2-13 Amendment Nos. 297 and 290


ML24073A171                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                             NRR-106 OFFICE NRR/DORL/LPL2-2/PM                                   NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NAME MMahoney                                               ABaxter                                                         DWrona DATE 03/19/2024 03/19/2024 03/25/2024 OFFICE NRR/DORL/LPL2-2/PM NAME MMahoney DATE 03/26/2024}}
ML24073A171 NRR-106 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NAME MMahoney ABaxter DWrona DATE 03/19/2024 03/19/2024 03/25/2024 OFFICE NRR/DORL/LPL2-2/PM NAME MMahoney DATE 03/26/2024}}

Latest revision as of 13:24, 5 October 2024

Correction of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications
ML24073A171
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/26/2024
From: Michael Mahoney
NRC/NRR/DORL/LPL2-2
To: Coffey B
Florida Power & Light Co
Mahoney M, NRR/DORL/LPL2-2
References
EPID L-2021-LLI-0002
Download: ML24073A171 (1)
v • d • e


Text

March 26, 2024

Bob Coffey Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.

Juno Beach, FL 33408

SUBJECT:

TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 -

CORRECTION OF AMENDMENT NOS. 297 AND 290 REGARDING CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS (EPID L-2021-LLI-0002)

Dear Bob Coffey:

On September 26, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 297 to Subsequent Renewed Facility Operating License No. DPR-31 and Amendment No. 290 to Subsequent Renewed Facility Operating License No. DPR-41 to Florida Power and Light Company (the licensee) for to the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point), respectively (Agencyw ide Documents Access and Management System (ADAMS) Accession No. ML23234A192).

These amendments convert the current technical specifications (TS) to the improved TS (ITS) and relocates certain requirements to other lic ensee-controlled documents. The ITS are based on:

NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 5.0; Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132); and Title 10 of the Code of Federal Regulations, Part 50, Section 36, Technical specifications.

After issuance of the amendments, it was identified that there was an inadvertent error on ITS page 3.3.2-13. The trip setpoint of function 7b, ESFAS [Engineered Safety Feature Actuation System] Interlocks, T avg - Low of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, should state Nominal 543 °F [degrees Fahrenheit], however the page was issued as Nominal 543 psig [pounds per square in gauge]. In letter dated May 24, 2023 (enclosure 2) (ML23151A446), the licensee requested the trip setpoint of function 7b, ESFAS Interlocks, Tavg - Low of Table 3.3.2-1 to state Nominal 543 °F. The NRC staff reviewed ITS page 3.3.2-13, as requested, however during issuance, the error was introduced.

B. Coffey

The NRC concludes that this correction does not change the NRC staffs previous conclusions in the safety evaluation, nor do they affect the no significant hazards consideration, as published in the Federal Register on June 14, 2022 (87 FR 36003). The enclosure contains corrected page 3.3.2-13.

If you have any questions regarding this matter, please contact me at (301) 415-3867 or by email at Michael.Mahoney@nrc.gov.

Sincerely,

/RA/

Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-250 and 50-251

Enclosure:

Corrected ITS page 3.3.2-13

cc: Listserv ESFAS Instrumentation 3.3.2

Table 3.3.2-1 (page 7 of 7)

Engineered Safety Feature Actuation System Instrumentation

APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE TRIP SETPOINT

7. ESFAS Interlocks
a. Pressurizer 1,2,3 2 K SR 3.3.2.3 2018 psig Nominal Pressure, P-11 SR 3.3.2.6 2000 psig
b. Tavg - Low 1,2,3 2 K SR 3.3.2.3 542.5°F Nominal SR 3.3.2.6 543°F

Turkey Point Unit 3 and Unit 4 3.3.2-13 Amendment Nos. 297 and 290

ML24073A171 NRR-106 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NAME MMahoney ABaxter DWrona DATE 03/19/2024 03/19/2024 03/25/2024 OFFICE NRR/DORL/LPL2-2/PM NAME MMahoney DATE 03/26/2024

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