ML17198A266

From kanterella
Jump to navigation Jump to search

Correction to Amendment No. 13 Regarding Surveillance Requirement Extensions
ML17198A266
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 07/18/2017
From: Robert Schaaf
Plant Licensing Branch II
To: James Shea
Tennessee Valley Authority
Schaaf R, NRR/DORL/LPLII-2
References
CAC MF8895
Download: ML17198A266 (5)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 18, 2017 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNIT 2 - CORRECTION TO AMENDMENT NO. 13 REGARDING SURVEILLANCE REQUIREMENT EXTENSIONS (CAC NO. MF8895)

Dear Mr. Shea:

By letter dated July 11, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17180A024), the U.S. Nuclear Regulatory Commission issued Amendment No. 13 for the Watts Bar Nuclear Plant, Unit 2, Facility Operating License (FOL)

No. NPF-96. This amendment revised Technical Specification (TS) Surveillance Requirement (SR) 3.0.2 to allow a one-time interval extension for SRs listed in Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17, to Enclosure 1 of your November 23, 2017, license amendment request, which was supplemented by letters dated February 16, 2017, and June 9, 2017.

Specifically, updated FOL No. NPF-96, page 3, was included with Amendment No. 13, as were TS pages 3.0-8 through 3.0-11, which included TS Table SR 3.0.2-1. Table 3.0.2-1 lists SRs that have been extended by Amendment No. 13 and previous amendments. Amendment No. 12 was issued on June 28, 2017 (ADAMS Accession No. ML17138A100), and included SR 3.8.1.19. One SR, being SR 3.8.1.19, was missing from Table 3.0.2-1 when Amendment No. 13 was issued on July 11, 2017.

Enclosed is the corrected TS page 3.0-11 for Amendment No. 13. Please use this page when making changes to FOL No. NPF-96 related to Amendment No. 13.

J. Shea If you have any questions regarding this matter, please contact me at (301) 415-1383 or Robert.Schaaf@nrc.gov.

Sincerely, 1£1{~ M Robert G. Schaaf, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391

Enclosure:

Corrected page 3.0-11 for Amendment No. 13 cc w/enclosure: Distribution via Listserv

ENCLOSURE CORRECTED WATTS BAR NUCLEAR PLANT, UNIT 2, RENEWED FACILITY OPERATING LICENSE NO. NPF-96, PAGE 3.0-11 FOR LICENSE AMENDMENT NO. 13 DATED JULY 11, 2017

SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

Table SR 3.0.2-1 Frequency Surveillance Requirement (SR) Description of SR Requirement Extension Limit Verify each DG:

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite 3.81.16 power; 11 /30/17
b. Transfers loads to offsite power source; and
c. Returns to ready-to-load operation Verify, DG 2A-A and 2B-B operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:

3.8.1.17 a. Returning DG to ready-to-load operation; and 11/30/17

b. Automatically energizing the emergency load from offsite power.

Verify the time delay setting for each sequenced load block 3.8.1.18 is within limits for each accident condition and non-accident 11/30/17 condition load sequence.

Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses;
b. Load shedding from emergency buses; and
c. DG auto-starts from standby condition and:
1. energizes permanently connected loads in s1 O seconds, 11/30/17 3.8.1.19 2. energizes auto-connected emergency loads through load sequencer,
3. achieves steady state voltage: ?>: 6800 V and s 7260 V,
4. achieves steady state frequency ?>: 59.8 Hz and s 60.1 Hz, and
5. supplies permanently connected and auto-connected emergency loads for?>: 5 minutes.

Perform integrated leak test for each system at least once 5.7.2.4b per 18 months. Specifically, only the centrifugal charging 10/31 /17 pump injection portion of the safety injection system (continued)

Watts Bar - Unit 2 3.0-11 Amendment No. 13

M17198A266 OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DORL/LPL2-2/BC DORL/LPL2-2/PM NAME PBuckberg BClayton UShoop BSchaaf (LRonewicz for)

DATE 7/18/2017 7/18/2017 7/18/2017 7/18/2017