ML20245J281

Ack Receipt of 890413 & 0607 Ltrs Informing NRC of Actions Taken to Correct Violations Noted in Insp Rept 50-482/89-07

ML20245J281
Person / Time
Site:	Wolf Creek
Issue date:	06/20/1989
From:	Milhoan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
References
NUDOCS 8906300260
Download: ML20245J281 (2)

See also: IR 05000482/1989007

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In' Reply Refer To

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• , a Wolf Creek Nuclear Operating Corporation.

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ATTN: Bart-D. Withers

President and Chief Executive Officer

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P.O. Box 411. J

< Burlington. : Kansas 66839

Gentlemen:

Thank you' for your letters of April 13, 1989, and June 7, 1989,..in response.

to ou[ letters and Notice of Violation dated March 15 and May 10,J1989. We.

f , have reviewed your replies and find them responsive.to the concerns' raised in

our Notice of Violation. : We will review the implementation of your corrective

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actions.during;a : future inspection tc determine that full compliance has' been

achieved and $111.be maintained.

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Sincerely,

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, Drlginal Signed Bg

J. L Milhoan

James L. Milhoan, Director

Division of Reactor Projects

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' Wolf Creek Nuclear Operating Corporation

ATTN: Otto Maynard, Manager

of _icensing

P.O. Box 411

.Burlington, Kansas '66839

% Wolf Creek Nuclear.' Operating Corporation-

ATTN: Gary Boyer, Plant Manager

P.O. Box 411

Burlington, Kansas 66839 j

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Kansas' Radiation' Control Program Director:

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W$LF CREEK NUCLEAR OPERATING CORPORATION

Bart D. Withers

President and e

Chief Execut!ve Officer

June 7,1989

WM.89-0167 ,

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U. S. Nuclear Regulatory Commission 'b/s F

ATTN: Document Control Desk .\i JUN I 51989

Mail Station P1-137 U\' 1

Washington, D. C. 20555 d

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Reference: Letter dated May 10, 1989 from L. J. Callan, NRC to

B. D. Withers, WCNOC

Subject: Docket No. 50-482: Response to Request for Additional

Information on Violation 482/8907-01

Gentlemen

This letter provides Wolf Creek Nuclear Operating Corporation's (WCNOC)

response to the request for additional information documented in the

Reference. The request for additional information was in conjunction with

g Violation ,482/8907-01 involving the failure to provide a written safety

evaluation for a temporary modification.

If you have any questions concerning this matter, please contact me or

Mr. O. L. Maynard of my staff.

Very truly yours,

Bart D. Withers

President and i

Chief Executive Officer

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BDW/aem

Attachreent

cc: B. L. Bartlett (NRC), w/a

E. J. Holler (NRC), w/a

R. D. Martin (NRC), w/a

D. V. Pickett (NRC), w/a

P.O. Box 411/ Durlington, KS 60839 / Phone: (316) 364 8831

QQ) f An Equal Opportunity Employer M F!HC/ VET

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'3 . 8 ; Attachmtnt to WM 89-0167 .

'Page 1 of 2

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Response to Request for Additional Information

on Violation 482/8907-01

Reauest *

Provide additional information concerning instructions, _ guidance, and/or [

training that will be provided to individuals that prepare and review safety

evaluations and report responses to assure that they understand the revised-

procedure (ADM 01-022) and other measures you have. taken to prevent'

-recurrence of this type of issue.

-Response

As identified in letter dated April 13, A989 from B. D. Withers, WCNOC, to

the NRC, procedure ADM 01-022 "Autho.-ization of Changes, Tests and

Experiments (10 CFR 50.59)" was revised to provide additional guidance on

when a written safety evaluation should be leitiated. Specifically, the [

revision provides the guidance that when the Cpdated Safety Analysis Report I

(USAR) description is general in nature and the change cannot be easily-

determined to affect the 10 CFR 50.59 Section (a)(1) criteria, then a

written safety' evaluation should be initiated. A letter has been sent to

other WCNOC organizations identifying the need to review and revise, as

appropriate, their procedures governing the 10 CFR 50.59 safety evaluation

process to incorporate this guidance. Additionally, Violation 482/8907-01

). and the revised procedure ADM 01-022 have been explained in detail to those

individuals who assist in the review and preparation of safety evaluations

associate 3 with temporary modifications.

Reauest:

Provide additional information concerning the results of the reevaluation of

the Nuclear Safety Evaluation (S. E. Nc. 89-SE-021) considering the effects

of the decreased voltage of the battery bank with a cell jumpered as it is

being discharged under design accident conditions.

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Response: l

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Nuclear Safety Evaluation, S. E. No. 89-SE-021, was revised and reviewed by

the Plant Safety Review Committee on May 30, 1989. This revision to the

l Nuclear Safety Evaluation provides additional supporting information to the

original evaluation, and was determined to not constitute an unreviewed

safety question. The following provides the results of the re-evaluation:

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The removal (electrically) of a cell from the subject bank has been I

calculated to remove 2.7% of the rated capacity of the bank (reference

EER 89-NK-02). Therefore, the loss of a cell, which represents a 2.7%

capacity loss, is insignificant to the system's function because the ,

system's function only requires 37% of 100% total system capacity, j

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Attachment to WM 89-0167

Page 2 of 2

Response (cont.):

The calculation has also shown that it would require the removal of at

least five cells before voltage would drop below 105 volts (minimum i

required) during the worst case load, i.e., station blackout. During

a station blackout. AC and charger power are lost; thus, the fully

charged battery tenninal voltage with one jumpered out cell would be

expected to drop to an initial nominal terminal voltage on the order

of 120.95 volts verses 123 volts for 60 cells. This lower voltage

will not affect the functional requirements of the battery bank. At no

time during the station blackout will battery terminal voltage drop

below the overall minimum battery voltage of 105 volts. In addition,

the removal of one cell or 2.25 volts (if it were a good cell) from

the bank which floats between 132-135 volts will not have any

noticeable effect upon the system since this loss is within the

described float voltage range. To provide the same minimum battery

voltage of 105 volts with one cell jumpered out, it should be noted L

that the individual cell voltage has changed from 1.75 to 1.78 volts. )

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