ML23052A110

– Correction to Amendment Nos. 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements

ML23052A110
Person / Time
Site:	Watts Bar
Issue date:	03/03/2023
From:	Perry Buckberg NRC/NRR/DORL/LPL2-2
To:	Jim Barstow Tennessee Valley Authority
References
EPID L-2022-LLA-0100
Download: ML23052A110 (1)

Text

March 3, 2023

Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services 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 NOS. 159 AND 67 REGARDI NG ADOPTION OF TSTF-554, REVISE REACTOR COOLANT LEAKAGE REQUIREMENTS (EPID L-2022-LLA-0100)

Dear Mr. Barstow:

By letter dated January 25, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22348A005), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 159 to Renewed Facility Operating License (RFOL) No. NPF-90 and Amendment No. 67 to RFOL No. NPF-96 for the Watts Bar Nuclear Plant Unit Nos. 1 and 2.

The amendment revised the Technical Specifications (TSs) to adopt Technical Specifications Task Force (TSTF) traveler TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements, dated January 16, 2020, using the Consolidated Line Item Improvement Process (CLIIP).

An error was identified in these license amendments in that TS pages 1.1-4 for both RFOL No. NPF-90 and RFOL No. NPF-96 did not reflect updates included in the November 4, 2022, issuance of Watts Bar Nuclear Plant Unit Nos. 1 and 2 Amendment Nos. 156 and 64 (ML22257A051).

Enclosed with this letter are corrected TS pages 1.1-4 for RFOL Nos. NPF 90 and NPF-96 for License Amendment Nos. 159 and 67, respectively.

The error does not change any of the conclusions in the safety evaluation associated with the January 25, 2023, License Amendment Nos. 159 and 67.

J. Barstow

If you have any questions, please contact me at (301) 415-1383 or via e-mail at Perry.Buckberg@nrc.gov.

Sincerely,

/RA/

Perry H. Buckberg, 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:

1. Unit 1 - Corrected Technical Specification Page 1.1-4

2. Unit 2 - Corrected Technical Specification Page 1.1-4

cc: Listserv ENCLOSURE 1

CORRECTED TECHNICAL SPECIFICATION PAGE 1.1-4

RENEWED FACILITY OPERATING LICENSE NO. NPF-90

FOR LICENSE AMENDMENT NO. 159

TENNESSEE VALLEY AUTHORITY

WATTS BAR NUCLEAR PLANT, UNIT 1

DOCKET NO. 50-390 Definitions 1.1

1.1 Definitions

LEAKAGE 3. Reactor Coolant System (RCS)

(continued) LEAKAGE through a steam generator tothe Secondary System (primary-to-secondar y LEAKAGE).

b. Unidentified LEAKAGE

All LEAKAGE (except RCP seal water injectionor leakoff) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE

LEAKAGE (except primary-to-secondary LEAKAGE) through a fault in an RCS component body, pipe wall, or vessel wall. LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE.

MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing all master relays in the channel required for channel OPERABILITY and verifying the OEPRABILITY of each required master relay. The MASTER RELAY TEST shall include a continuity check of each associated required slave relay. The MASTER RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PDMS The Power Distribution Monitoring System (PDMS) is a real-time three dimensional core monitoring system. The system utilizes existing core instrumentation data and an on-line neutronics code to provide surveillance of core thermal limits.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

(continued)

Watts Bar-Unit 1 1.1-4 Amendment 65, 82, 156, 159 ENCLOSURE 2

CORRECTED TECHNICAL SPECIFICATION PAGE 1.1-4

RENEWED FACILITY OPERATING LICENSE NO. NPF-96

FOR LICENSE AMENDMENT NO. 67

TENNESSEE VALLEY AUTHORITY

WATTS BAR NUCLEAR PLANT, UNIT 2

DOCKET NO. 50-391 Definitions 1.1

1.1 Definitions (continued)

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary-to-secondary LEAKAGE).

b. Unidentified LEAKAGE

All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE

LEAKAGE (except primary-to-secondary LEAKAGE) through a fault in an RCS component body, pipe wall, or vessel wall. LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE.

MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing all master relays in the channel required for channel OPERABILITY and verifying the OPERABILITY of each required master relay. The MASTER RELAY TEST shall include a continuity check of each associated required slave relay. The MASTER RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

(continued)

Watts Bar - Unit 2 1.1-4 Amendment 64, 67

ML23052A110 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NRR/DORL/LPLII-2/BC NRR/DORL/LPLII-2/PM NAME PBuckberg RButler DWrona PBuckberg DATE 02/22/2023 02/22/2023 03/03/2023 03/03/2023