ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
| ML19239A112 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/22/2019 |
| From: | Shawn Smith Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ET 19-0018 | |
| Download: ML19239A112 (5) | |
Text
..,
Stephen L. Smith August 22,2019 Vice President Engineering ET 19-0018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
Letter ET 19-0002, dated March 18, 2019, from S. L. Smith, WCNOC, to USNRC
Subject:
Docket No. 50-482:
Supplement to License Amendment Request to Revise Technical Specification 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation" To Whom It May Concern:
This letter is a supplement to the Reference, in which Wolf Creek Nuclear Operating Corporation's (WCNOC) submitted an application to revise Wolf Creek Generating Station (WCGS) Technical Specification (TS) 3.3.5. During the review of WCNOC documentation for the Safety Evaluation, the Nuclear Regulatory Commission (NRC) staff noted a discrepancy in Attachment I to the submittal. Specifically, the tables on page 17 and 19 were identical. The Enclosure to this letter replaces page 19 which contains the corrected Loss of Voltage Relay Setting table.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4093, or Ron Benham at (620) 364-4204.
SLS/rlt Sincerely, zj;gJ Stephen L. Smith P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 19-0018 Page 2 of 3
Enclosure:
Corrected Page 19 to Attachment I of ET 19-0002 cc:
S. A. Morris (NRC), w/e N. O'Keefe (NRC), w/e B. K. Singal (NRC), w/e K. S. Steves (KDHE), w/e Senior Resident Inspector (NRC), w/e
ET 19-0018 Page 3 of 3 STATE OF KANSAS
) ) ss COUNTY OF COFFEY )
Stephen L. Smith, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Z1 By _______ ~=:::..._...L.~---
Stephen L. Smith Vice President Engineering SUBSCRIBED and sworn to before me this c:2anfay of A L1Jlis+
, 2019.
RHONDA L. TIEMEYER Notary Public. State of Kansas My Appoimment Expires Notary Public Expiration Date~ /11 JOJ. J
Enclosure to ET 19-0018 Corrected Page 19 to Attachment I of ET 19-0002 (1 page)
~
Attachment I to ET 19-0002 Page 19 of 29 The maximum reset voltage 0/max reset) is calculated from the AF;; voltage and PU/DO ratio (relay pickup to dropout voltage ratio (in % of ATSP)). The PU is 110% of the dropout voltage for the LOV relay.
AFmax (
PU/DO )
(
10 ).
vmaxreset =
DO 1+
=92.3 1+- =101.53V 100 100 This translates to 101.53 x 35 x 1.003 =: 3564.3V at the 4.16kV buses when PT error is considered.
Results TS AV is~ 90.0V (3159.5V on the 4.16kV side).
TS nominal Trip Setpoint is 91.28V.
Analytical Limit/Safety Limit is 90.28V (90.28 x 35 x 0.997 = 3150.4Vac on the 4.16kV side).
The voltage element settings for the NB01
- and NB02 bus LOV relays are tabulated below.
Value SettinQ (Calculated SettinQs) (at 4kV)
Vmax (Reset) 101.52V 3864.3V Dropout Max As-Found 92.30V ATSP!foax 91.88V Dropout Max Allowable As-Left ATSPoo 91.28V TS nominal Trip Setpoint NTSPoo 90.69V Dropout Min As-Left Dropout Min As-Found 90.28V TS Allowable Value 90.0V(1>
3159.5V<2>
Analytical Limit/Safety Limit 3150.4V (1> The voltage at the relay with PT error excluded.
(2> The TS AV voltage at the 4.16 kV bus with PT error included