ML22004A132

Correction of Amendment Nos. 227 and 224 Issuance of Amendments Regarding Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition (EPID L-2019-LLA-027

ML22004A132
Person / Time
Site:	Farley
Issue date:	01/24/2022
From:	John Lamb Plant Licensing Branch II
To:	Gayheart C Southern Nuclear Operating Co
Lamb, J
References
EPID L-2019-LLA-0276
Download: ML22004A132 (4)

Text

January 24, 2022 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company 3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION OF AMENDMENT NOS. 227 AND 224 RE: ISSUANCE OF AMENDMENTS REGARDING APPLICATION TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-569, REVISE RESPONSE TIME TESTING DEFINITION (EPID L-2019-LLA-0276)

Dear Ms. Gayheart:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 227 and 224 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML20006E760) to Facility Operating Licenses NPF-2 and NPF-8 for the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, respectively.

The amendments adopted Technical Specifications Task Force (TSTF) traveler TSTF-569, Revise Response Time Testing Definition, which is an NRC-approved change to the Improved Standard Technical Specifications, into the Farley, Units 1 and 2, TSs. The amendments revised the TS Definitions for Engineered Safety Feature (ESF) Response Time and Reactor Trip System (RTS) Response Time.

The NRC staff has discovered an administrative error on TS page 1.1-3. The definition of E - AVERAGE DISINTEGRATION ENERGY was missing from TS page 1.1-3 on Amendment Nos. 227 and 224.

The NRC staff confirmed that Amendment Nos. 226 and 223 for Farley, Units 1 and 2, dated January 29, 2020 (ADAMS Accession No. ML19337C322), contained the E - AVERAGE DISINTEGRATION ENERGY on TS page 1.1-3.

Therefore, consistent with NRC staff guidance dated January 16, 1997 (ADAMS Accession No. ML103260096), based on the NRCs policy established by SECY-96-238, this error can be corrected by a letter to the licensee from the NRC staff.

Enclosed please find the corrected Farley, Units 1 and 2, TS page 1.1-3. This correction does not change any of the conclusions in the safety evaluation associated with Amendment Nos. 227 and 224.

If you have any questions, please contact me at 301-415-3100 or John.Lamb@nrc.gov.

Sincerely,

/RA/

John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-348 and 50-364

Enclosure:

As stated cc:

Listserv

Definitions 1.1 (continued)

Farley Units 1 and 2 1.1-3 Amendment No. 227 (Unit 1)

Amendment No. 224 (Unit 2) 1.1 Definitions AVERAGE shall be the average (weighted in proportion to the DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC, or the components have been evaluated in accordance with an NRC approved methodology.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

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 either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or

ML22004A132 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME JLamb KGoldstein (KEntz for)

MMarkley JLamb DATE 1/3/2022 1/5/2022 1/24/2022 1/24/2022