ML20214Q265

From kanterella
Jump to navigation Jump to search
Responds to Violations Noted in Insp Repts 50-369/87-11 & 50-370/87-11.Corrective Actions:All Previous Test Data Reviewed & Inspectors Provided W/Plot of Reactor Trip Breaker Response Trend Curves for All Breakers
ML20214Q265
Person / Time
Site: McGuire, Mcguire  
Issue date: 05/29/1987
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8706040320
Download: ML20214Q265 (3)


Text

,

Duxe POWER GOMPANY P.O. BOX 33189 CHAmLOrFE, N.C. 98948 HAL B. TUCKER -

"2"

== e en (704) 07t>4ast

.ma.

May 29 1987

.U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

Subject:

McGuire Nuclear Station Docket Nos. 50.-369, -370 NRC/0IE Inspection Report Nos.

50-369/87-11 and 50-370/87-11 Gentlemen:

Pursuant to 10CFR 2.201, please find attached the response to the violation identified in the above referenced inspection report.

Very truly yours,-

l Hal B. Tucker

{

SEL/63/jgm Attachment xc:

Dr. J. Nelson Grace Regicnal Administrator, Region II U.S. Nuclear Regulatory Connaission i

101 !farietta St., NW, Suite 2900

/

Atlanta, GA 30323 Mr. Darl Hood i

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation l

Washington, D.C.

20555

-Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station po\\

8706040320 870529 ADOCKOS00g9 DR

DUKE POWER COMPANY McGUIRE NUCLEAR STATION VIOLATION RESPONSE Violation 50-369/87-11-01 and 50-370/87-11-01 License Amendment No. 2 to McGuire Unit 2 facility operating license dated May 27, 1983, paragraph 2.c.12.c requires the licensee to implement the reactor trip breaker and reactor trip bypass breaker testing and reporting as described in Table 1, " Periodic Surveillance / Maintenance of Reactor Trip Breakers and Reactor Trip Bypass Breakers". Table 1, Column 3 delineates the six months surveillance and maintenance requirements for reactor trip and bypass breakers. Item 1 of Column 3 requires that the data obtained from response time testing of the UV/ breaker shall be trendad.

Contrary to the above, on March 16, 1987, UV/ Breaker response time test data was not being trended nor was there any evidence to show that this data has ever been trended.

This is a Severity Level V (Supplement I) Violation.

RESPONSE

1.

Admission or denial of violation:

Yes, we admit to the violation of not having a formal trending program for trending the UV/ breaker response time. However, we were at all times cognizant of the UV/ breaker response times both before and after the 6 month breaker maintenance. This is evident by our ability to produce plots of the previous UV/ breaker response times almost immediately which substantiated that a negative trend in UV/ breaker response time had not occurred.

2.

Reason for the violation if admitted:

We did not implement the trending requirement to the extent that it was intended. We interpreted the trending requirement to mean that we should require a cognizant engineer to evaluate the actual response times relative to the acceptance criteria and determine if the UV/ breaker response time was acceptable. This, to us, would insure that the breakers were capable of performing their intended safety function with the required time. We now know that the trending requirement must be implemented through a formal, defined program.

3.

Corrective steps which have been taken and the results achieved:

We were informed of the inspector's concern relative to trending UV/ breaker response time. We immediately reviewed all previous test data and provided the inspectors with a plot of Reactor Trip Breaker Response trend curves for all breakers, both main and bypass.

This data substantiated that a negative trend had not occurred which would have caused a need to take some corrective action.

e Page 2 4.

Corrective steps which will be'taken to avoid further violations:

A formal trending program will be established which will consist of adding steps to procedures PT/0/A/4601/07A (change #6) and PT/0/A/4601/07B (change #8) which will require the responsible engineer to review previous response time data for trends that may indicate breaker degradation. The' responsible engineer will also place a copy of the data sheets.into the Reactor Trip Breaker Time Response Data" logbook AND update computer data, if desired to graph the time response trends.

These steps will also require that 0.1 second be.the criteria for evaluating the need for corrective action before the next scheduled breaker PM.

5.

The date when full compliance will be achieved:

4 Full compliance will be achieved by August 7, 1987.

I i

1 a

i e

t

)

i i

i s

I i

I

. _.. _ _. -... _. _.., _ _ _ _ _. _ _ _ _... _ _ _ _ _ _ _ _ _ _,...... _ _.. _ _. _.