ML19232A379

Correction to Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3

ML19232A379
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/19/2019
From:	Thomas Wengert Plant Licensing Branch IV
To:	Entergy Operations
Wengert T, 415-4037
References
CAC MF7536, EPID L-2018-LLA-0063
Download: ML19232A379 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 19, 2019 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc.

N-TSB-58 1448 S.R. 333 Russellville, AR 72802

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT 1 - CORRECTION TO ISSUANCE OF AMENDMENT NO. 264 TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-425, REVISION 3, " RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL - RITSTF INITIATIVE Sb" (EPID L-2018-LLA-0063)

Dear Sir or Madam:

By letter dated May 22, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19098A955), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 264 to Renewed Facility Operating License No. DPR-51 for Arkansas Nuclear One, Unit 1 (AN0-1). The amendment adopted changes to the AN0-1 technical specifications (TSs) consistent with Technical Specifications Task Force (TSTF) Improved Standard Technical Specifications Change Traveler TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative Sb,"

dated March 18, 2009 (ADAMS Accession No. ML090850642).

After the issuance of the amendment, the NRC staff was notified by Entergy Operations, Inc.

(the licensee) of typographical errors unrelated to the license amendment that had been inadvertently included in revised TS page 3.4.14-2. Specifically, the two surveillance conditions in Surveillance Requirement 3.4.14.3 were incorrectly identified as items "c." and "d." They should have remained unchanged on TS page 3.4.14-2 as items "a." and "b.," as shown below:

a. <= 340 psig for one valve; and

b. <= 400 psig for the other valve Upon further review, the NRC staff determined that the errors had been previously introduced during the preparation of Amendment No. 257, which was issued on March 10, 2017 (ADAMS Accession No. ML16165A423), and inadvertently carried forward without correction in Amendment No. 264. The NRC staff determined that these errors were introduced during the preparation of the license amendments and are entirely typographical in nature. The corrections do not change any of the conclusions in the safety evaluations associated with the amendments and do not affect the associated notices to the public.

The enclosure to this letter contains the corrected TS page 3.4.14-2. Please replace the corresponding page issued by Amendment No. 264 for Arkansas Nuclear One, Unit 1.

We regret any inconvenience this may have caused. If you have any questions, please contact me at (301) 415-4037 or by e-mail at Thomas.Wengert@nrc.gov.

~~r---t-Sincerely,

-=FR Thomas J. Wengert, Senior ~oject Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

Corrected TS Page to Renewed Facility Operating License DPR-51 for Amendment No. 264 cc: Listserv

ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 3.4.14-2 FOR AMENDMENT NO. 264 ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET NO. 50-313

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------------------NOTE---------------------------

Not required to be performed in MODES 3 and 4.

Verify leakage from each RCS pressure isolation In accordance with check valve, or pair of check valves, as applicable, the INSERVICE is less than or equal to an equivalent of the TESTING Allowable Leakage Limit identified below at a PROGRAM differential test pressure ~ 150 psid.

Pressure Isolation Allowable Check Valve(s) Leakage Limit Once prior to entering MODE 2 DH-14A  :::; 5gpm whenever the unit DH-13A and DH-17  :::; 5 gpm total has been in DH-148  :::;5gpm MODE 5 for 7 days DH-138 and DH-18  :::; 5 gpm total or more, if leakage testing has not been performed in the previous 9 months SR 3.4.14.2 Verify OHR System autoclosure interlock prevents In accordance with the valves from being opened with a simulated or the Surveillance actual high RCS pressure signal. Frequency Control Program SR 3.4.14.3 Verify OHR System autoclosure interlock causes In accordance with the valves to close automatically with a simulated or the Surveillance actual high RCS pressure signal: Frequency Control Program

a. :::; 340 psig for one valve; and

b. :::; 400 psig for the other valve.

SR 3.4.14.4 Verify OHR System autoclosure interlock prevents In accordance with the valves from being opened with a simulated or the Surveillance actual Core Flood Tank isolation valve "not closed" Frequency Control signal. Program SR 3.4.14.5 Verify OHR System autoclosure interlock causes In accordance with the valves to close automatically with a simulated or the Surveillance actual Core Flood Tank isolation valve "not closed" Frequency Control signal. Program AN0-1 3.4.14-2 Amendment No. ~.~.264

ML19232A379 OFFICE NRR/D0RL/LPL4/PM NRR/D0RL/LPL4/LA NRR/D0RL/LPL4/8C NRR/D0RL/LPL4/PM NAME TWengert PBlechman RPascarelli TWengert DATE 9/17/19 9/17/19 9/18/19 9/19/19