ML24261C006
| ML24261C006 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/04/2024 |
| From: | Kimberly Green Plant Licensing Branch II |
| To: | Erb D Tennessee Valley Authority |
| Green K | |
| References | |
| Download: ML24261C006 (1) | |
Text
October 4, 2024 Delson Erb Vice President, OPS Support Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO AMENDMENT NO. 134 TO FACILITY OPERATING LICENSE NO. NPF-90 AND AMENDMENT NO. 38 TO FACILITY OPERATING LICENSE NO. NPF-96
Dear Delson Erb:
During the issuance of Amendment No. 134 to Facility Operating License (FOL) No. NPF-90, and Amendment No. 38 to FOL No. NPF-96, on April 30, 2020 (ADAMS Accession No. ML20076A194), the U.S. Nuclear Regulatory Commission (NRC) staff omitted the amendment numbers that should have been included in License Condition 2.C.(12)(a). The purpose of this letter is to issue corrected page 4b of FOL No. NPF-90, and corrected page 4 of FOL No. NPF-96. The NRC concludes that this omission does not change the staffs previous conclusion in the safety evaluation for issuance of Amendment Nos. 134 and 38, nor does it affect the NRC staffs no significant hazards consideration determination. The corrected pages also reflect minor formatting issues (e.g., spacing, missing hyphen) that occurred during the issuance of the amendments.
Enclosed, please find corrected page 4b of FOL No. NPF-90 for Amendment No. 134, and corrected page 4 of FOL No. NPF-96 for Amendment No. 38, as subsequently amended by Amendment No. 49.
If you have any questions regarding this matter, please contact me at (301) 415-1627 or by email at Kimberly.Green@nrc.gov.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391
Enclosures:
ENCLOSURE 1 WATTS BAR NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-390 CORRECTED PAGE 4b OF FACILITY OPERATING LICENSE NO. NPF-90
Facility License No. NPF-90 Amendment No. 107, 134 4b (10)
By May 31, 2018, TVA shall ensure that a listing organization acceptable to the NRC (as the Authority Having Jurisdiction) determines that the fire detection monitoring panel in the main control room either meets the appropriate designated standards or has been tested and found suitable for the specified purpose.
(11)
The licensee shall replace the WBN, Unit 1 upper compartment cooler cooling coils with safety-related cooling coils to eliminate a potential source of containment sump dilution during design basis events prior to increasing the number of Tritium Producing Burnable Absorber Rods (TPBARs) loaded in the reactor core above 704.
(12)
Adoption of 10 CFR 50.69, Risk-Informed categorization and treatment of structures, systems and components for nuclear power plants (a) TVA is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and seismic hazards; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards; fire hazards by use of the fire protection program (FPP) safe shutdown equipment list (SSEL), and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009, as specified in Unit 1 License Amendment 134.
(b) Prior to implementation of the provisions of 10 CFR 50.69, TVA shall complete the implementation items in Enclosure 2, Attachment 1, "List of Categorization Prerequisites," to TVA letter CNL-19-108, Response to NRC Second Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (WBN-TS-17-24) (EPID 2018-LLA-0493), dated October 28, 2019.
(13)
Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from using the FPP SSEL approach to an internal fire probabilistic risk assessment approach).
D.
The following exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Therefore, these exemptions are granted pursuant to 10 CFR 50.12.
(1)
Deleted
ENCLOSURE 2 WATTS BAR NUCLEAR PLANT, UNIT NO. 2 DOCKET NO. 50-391 CORRECTED PAGE 4 OF FACILITY OPERATING LICENSE NO. NPF-96 Unit 2 Amendment No. 19, 38, 49 Facility Operating License No. NPF-96 TVA may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(9)
By May 31, 2018, TVA shall report that a listing organization acceptable to the NRC (as the Authority Having Jurisdiction) has determined that the fire detection monitoring panel in the main control room either meets the appropriate designated standards or has been tested and found suitable for the specified purpose.
(10)
Deleted.
(11)
TVA will implement the compensatory measures described in Section 3.4, Additional Compensatory Measures, of TVA Letter CNL-18-012, dated January 17, 2018, during the timeframe the temperature indicator for RCS hot let 3 is not required to be operable for the remainder of Cycle 2. If the RCS hot leg 3 temperature indicator is returned to operable status prior to the end of Cycle 2, then these compensatory measures are no longer required.
(12)
Adoption of 10 CFR 50.69, Risk-Informed categorization and treatment of structures, systems and components for nuclear power plants (a) TVA is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and seismic hazards; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards; fire hazards by use of the fire protection program (FPP) safe shutdown equipment list (SSEL), and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009, as specified in Unit 2 License Amendment 38.
(b) Prior to implementation of the provisions of 10 CFR 50.69, TVA shall complete the implementation items in Enclosure 2,, "List of Categorization Prerequisites " to TVA letter CNL-19-108, Response to NRC Second Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (WBN-TS-17-24) (EPID L-2018-LLA-0493), dated October 28, 2019.
ML24261C006 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME KGreen ABaxter DWrona KGreen DATE 09/17/24 09/18/24 10/02/24 10/04/24