ML19232A379
| 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
ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
N-TSB-58 1448 S.R. 333 Russellville, AR 72802 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 19, 2019
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.
Docket No. 50-313
Enclosure:
Sincerely,
-=FR ~~r---t-Thomas J. Wengert, Senior ~oject Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 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
SURVEILLANCE REQUIREMENTS SR 3.4.14.1 SR 3.4.14.2 SR 3.4.14.3 SR 3.4.14.4 SR 3.4.14.5 SURVEILLANCE
NO TE---------------------------
N ot required to be performed in MODES 3 and 4.
Verify leakage from each RCS pressure isolation check valve, or pair of check valves, as applicable, is less than or equal to an equivalent of the Allowable Leakage Limit identified below at a differential test pressure ~ 150 psid.
Pressure Isolation Check Valve(s)
DH-14A DH-13A and DH-17 DH-148 DH-138 and DH-18 Allowable Leakage Limit
- 5gpm
- 5 gpm total
- 5gpm
- 5 gpm total Verify OHR System autoclosure interlock prevents the valves from being opened with a simulated or actual high RCS pressure signal.
Verify OHR System autoclosure interlock causes the valves to close automatically with a simulated or actual high RCS pressure signal:
- a.
- 340 psig for one valve; and
- b.
- 400 psig for the other valve.
Verify OHR System autoclosure interlock prevents the valves from being opened with a simulated or actual Core Flood Tank isolation valve "not closed" signal.
Verify OHR System autoclosure interlock causes the valves to close automatically with a simulated or actual Core Flood Tank isolation valve "not closed" signal.
RCS PIV Leakage 3.4.14 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Once prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program AN0-1 3.4.14-2 Amendment No. ~.~.264
ML19232A379 OFFICE NRR/D0RL/LPL4/PM NRR/D0RL/LPL4/LA NAME TWengert PBlechman DATE 9/17/19 9/17/19 NRR/D0RL/LPL4/8C RPascarelli 9/18/19