ML20213F073

Forwards Request for Addl Info Re Multi-Plant Action B-81 & Items 4.2.1 & 4.2.2 Re Preventative Maint Program for Reactor Trip Breaker/Maint & Trending Described in Generic Ltr 83-28

ML20213F073
Person / Time
Site:	Diablo Canyon
Issue date:	11/08/1984
From:	Noonan V Office of Nuclear Reactor Regulation
To:	Knighton G Office of Nuclear Reactor Regulation
Shared Package
ML20213E750	List: ML20213E747 ML20213E752 ML20213E783 ML20213E788 ML20213F010 ML20213F018 ML20213F073 ML20213F078 ML20215A023 ML20215A063 ML20215A107 ML20215A144 ML20215A168 ML20215A234
References
CON-FIN-A-6814, FOIA-86-197 GL-83-28, TAC-53121, NUDOCS 8411260432
Download: ML20213F073 (4)

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o,, UNITED STATES

3 o NUCLEAR REGULATORY COMMISSION 3 p WASHINGTON, D. C. 20555

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NOV 8 1984

.; Docket Nos. 50-275/323

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MEMORANDUM FOR:

Licensing Branch No. 3 4 Division of Licensing FROM: Vincent S. Noonan, Chief

~f Equipment Qualification Branch Division of Engineering

SUBJECT:

REQUEST FCR ADDITIONAL INFORMATION FROM DIABLO CANYON UNITS 1 AND 2 (NRC DOCKET NOS. 50-275/323) REGARDING MPA B-81, ITEMS 4.2.1 AND 4.2.2 - PREVENTATIVE MAINTENANCE PROGRAM FOR REACTOR TRIP BREAKER / MAINTENANCE AND TRENDING The Equipment Qualification Branch (EQB) is responsible for the review of Items 4.2.1 and 4.2.2 in Generic Letter 83-28. These two items are also referred to as MPA B-81, Preventative Maintenance Program for Reactor Trip Breakers / Maintenance and Trending (TAC No. 53121 for Unit 1). The technical review is being performed by Idaho National Engineering Laboratory (INEL).

The initial submittal by the licensee has been reviewed. Based on that review we find that the licensee must address the attached request for additional information before we can complete our review.

t Vinc t S. Noonan, Chief

(

Equipment Qualification Branch Division of Engineering

Enclosure:

As stated cc: G. Bagchi R. Perch

R. Haroldson, INEL B. Buckley R. Wright N. Romney

Contact:

N. Romney, NRR

.'a Ext. 49-28115 3

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OIABLO CANYON UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION GL 83-28, ITEMS 4.2.1 AND 4.2.2, TASK A6814

.' INTRODUCTION Pacific Gas and Electric Company, the licensee ~ for'0f ablo Canyon Units 1 and 2, submitted their response to Generic Letter 83-28 on .

November 7,1983, December 20, 1983, and May 24, 1984. Those submittals have been reviewed with respect.to Items 4.2.1 and 4.2.2 of the Generic Letter. The licensee's response was not sufficiently detailed to permit an evaluation of'the adequacy of the periodic maintenance and trending programs for the breakers. The following additional information is

required to evaluate compliance with Itests 4.2.1 and 4.2.2.

Item 4.2.1 - Periodic Maintenance Program for Reactor Trip 1.

Breakers.

I 1.1 Criteria for Evaluating Compliance with I' tem 4.2.1

.. The Diablo Canyon Units 1 and 2 Reactor Trip Systems utilize

• Westinghouse 08-50 circuit breakers. The primary criteria for an acceptable maintenance program for this breaker are I contained in Maintenance Program for 08-50 Reactor Trip i Switchaear, Rev. O, dated October 14, 1983, by i Westinghouse. The NRC Staff, Equipment Qualification

.l Branch, has reviewed and endorsed the Westinghouse

! Maintenance Program for 08-50 Switchgear. Specifically, the 1 criteria used to evaluate compliance include those items in the Westinghouse program that relate to the safety function of the breaker, supplemented by those measures that must be taken to accumulate data for trending.

3 1.2 Issues Relatino to Item 4.2.1 l

l The licensee response states that a new maintenance

,-3 procedure, E-51.7, has been implemented which " incorporates

.the latest Westinghouse information and will be performed on-a yearly basis." The licensee's submittal did not include a copy of procedure E-51.7; also, the Westinghouse recommendations for a periodic maintenance program identify six-month and refueling outage maintenance intervals, rather than annual intervals.

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Uoes the Diablo Canyon Units 1 and 2 periodic maintenance program for the reactor trip breakers include, on a six month basis

. 1. Verification of trip bar freedom;

2. Verification of operating mechanism alignment and freedom, using the procedure identified in the Westinghouse program;

3. Retaining ring verification, 33 places;

4. Verification of nut and bolt tightness;

5. Verification of pole bases physical condition; j 6. Verification of arcing and main contacts physical

. condition, using the procedure identified in the Westinghouse program;

7. Verification of insulating link's physical condition;

8. Verification of wiring insulation and termination physical condition;

9. Verification of are chute physical condition;

10. Verification of breaker cleanliness;

,. 11. Undervoltage Trip Attachment (UVTA) dropout voltage 4 test and lubrication, using the procedure identified in the Westinghouse program;

12. Shunt Trip Attachment (STA) operation verification;

13. Verification of operation of auxiliary switches;

.'.. 14. Inspection of positioning lever condition, using the

> ' procedure identified in Westinghouse program; L

15. Functional test of the breaker prior to returning it to e'

service, using the procedure identified in the Westinghouse program.

Does the Otablo Canyon Units 1 and 2 periodic maintenance 2, program for the reactor trip breakers include, on a refueling interval basis:

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1. Verification of cell interlock operation; f,5 i

"; 2. Examination and cleaning of breaker enclosure; i

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3. Measurement of trip force required, using the procedure

]' identified in the Westinghouse program;

4. Breaker response time for undervoltage trip;

5. Functional test of the breaker prior to returning it to service, using the procedure identif.ied in the Westinghouse program.

The licensee is to confirm that the periodic maintenance program

, includes these 20 items at the soecified intervals or commit to their r inclusion.

2. Item 4.2.2 - Trending of Reactor Trip Breaker Parameters to

] i Forecast Degradation of Operability.

-} 2.1 Criteria for Evaluating Compliance with Items 4.2.2 d

Four parameters have been identified as trendable and are included in the criteria for evaluation. These are (1) undervoltage trip attachment dropout voltage,- (2) trip

, force, (3) breaker response time for undervoltage trip, and

, (4) breaker insulation resistance.

i 2.2 Issues Relatina to Item 4.2.2 The licensee indicates that development of a program to trend " parameters affecting operation to forecast degradation of operability" would be complete by December 1983.-

The licensee is to commit to inclusion of trip force, breaker response time and dropout voltage for undervoltage trip and breaker insulation resistance as trending parameters. The licensee should also identify the organization which will perform trend analysis, how often the analysis will be performed and how the information derived from the analysis will be used to affect periodic maintenance.

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