ML17254A235
| ML17254A235 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/28/1985 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8503050425 | |
| Download: ML17254A235 (6) | |
Text
REGULATOR Y FORMA7 ION-DI8 TR IBUTION S Y H'R IDS)
ACCESSION( NBRe8503050ff25 DOC ~ OATEN 85/02/28 NOTARIZED'. NO DOCKET' FACIL!50 2ffff Robert" Emmet Ginna Nuclear Planti Unit ic Rochester G
050002ffff AUTH",NAME" AUTHOR AFFIL'I ATION KOBERiR xiii Rochester Gas
& Electric Corp.
RECIP ~ NAME, RECIPXENT AFFILIATION ZHOLINSKIiJ~,A, Operating Reactors Branch 5
r C'UBJECT:
Responds to 8ff1125"request for addi )nfo re Generic.,Ltr 83 28iItems ff,2'.1 8 ff.2',2',Br eaker~ maint will be performed-du>>ring.annual refueling outages-rather thin at 6~month inter val s.
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O'IA'I0'OCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649.0001 ROGER W. KOBER VICE PIIESIDSNT ELECTAIC6 STEAM PRODUCTION TSI.KPHONC ARKA CODS Tld 546-2700 February 28< l985 Director of Nuclear Reactor Regulation Attention:
Nr. John A. ZwolinskiT Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington>
D.C.
20555
Subject:
November 23, 1984 Request for Additional Information Concerning Generic Letter 83-28 R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Nr. Zwolinski:
The enclosure to this letter provides our response to the subject letter.
Reference paragraphs in the enclosure with this letter correspond to paragraph numbers in the enclosure to your November 23 letter.
V truly yoursT Ro r W. Kober Enclosure
~5 850228 8503050+~
05000+4+
PDR ADOGH
@DR P
J Al C!
Enclosure Paragraph 1.2< Issues Relating to Item 4.2.1 Procedures have been written and all will have been approved and implemented by the completion of the scheduled 1985 refueling outage.
These procedures will conform in intent to the Westinghouse Owners Group maintenance program (Revision 0 dated October 14< 1983) in the areas of concern listed in the attachment to your letter.
In most cases the Ginna procedure will use the reference procedure word for word.
We have renumbered the procedure steps and have used the Ginna procedure format rather than the reference procedure format.
In addition we> in some cases, require that data be logged in a data sheet which in some cases is not required in individual steps in the WOG procedure.
Further< in case of difficulty> the procedure does not specifically require that "Westinghouse Service Engineering" be called.
The Ginna experience with the Reactor Trip Switchgear is that when called upon to function< it has> without exception>
performed.
While our previous breaker maintenance'rogram has not been documented to the extent required by the latest NRC guidelines<
the lack of documentation has not diminished its effectiveness.
Unless future experience indicates unexpected degradation< it is our intention to perform'he maintenance only during'our annual refueling outages rather than at six month interv'als.
We do not believe that overtesting of any device enhances its reliabiliy.
Paragraph 2, Item 4.2.2> Trending of Reactor Trip Breaker Parameters to Forecast Degradation of Operability The parameters of undervoltage trip attachment dropout voltage< trip force>
and breaker insulation resistance will be trended as a way to detect degradation of the breakers and their ability to perform.
As a minimum~ response time testing of each RT breaker will be performed each refueling outage.
More frequent periodic online testing of breaker response time would be considered if life cycle testing shows that breaker trip response time degrades with operation.
The acceptance criteria will be consistent with the maximum value assumed in the Ginna Station accident analysis.
Specifically>
accident analysis requires that the breaker must function (i.e.> open after receiving the trip signal) within ten cycles.
Should the response time exceed 8
cycles< procedures require that the breaker be either repaired or that trending be accomplished by testing every six months.
Testing of the breaker response times for undervoltage trip has occurred during the 1983 and 1984 refueling outages.
In 1983, breakers AGB tripped in 5.0 and 5.5 cycles> respectively<
when actuation was initiated by loss of voltage to the undervoltage device.
In the 1984 tests the trip times were 5.2 and 5.0 cycles< respectively.
In testing the undervoltage trip attachment~
the dropout volta'ge will be measured and trended.
In addition< maintenance procedures will include inspecting the gap between the UVTA trip lever and the breaker trip bar.
This will be in addition to the response time testing listed above.
The shunt trip attachment will be tested to insure actuation of the tripping function when the applied voltage is only 70 VDC.
In addition< the clearance between the trip lever and the trip bar will be checked.
1
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