ML20108A611
| ML20108A611 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/02/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8411150078 | |
| Download: ML20108A611 (3) | |
Text
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DUKE POWER GOMPANY P.O. EOx 33180 CHARLOTTE, N.C. 28242 1
HAL H. TUCKER TELEPHME (704) 373-4531 ms memmesr, November 2,'1984
=cos.o. -
Mr. Harold R. Denton,. Director Office of> Nuclear Reactor Regulation 1U. S. Nuclear. Regulatory Commission
- Washington,' D.. C. : 20555 -
Attention:
Ms.-E. G. Adensam, Chief Licensing Branch No. 4
'Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414.
Dear Mr. Denton:
My letter'of October 19,.1984 provided the status of specific commitments made in our response to Generic Letter 83-28 which was sent to you on November 4, 1983._ Please find attached supplementary'information outlining Duke _ Power Company's schedule for' implementation of'the requirements
.specified in Generic Letter 83-28.
Very truly yours, L
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Hal B. Tucker ROS:slb Attachment cc:
Mr. James P. O'Reilly, Regional Administrator Mr. Jesse L. Riley U. S. Nuclear Regulatory Commission Carolina Environmental Study Group Region II 854 Henley Place 101 Marietta Street, NW, Suite 2900 Charlotte, North Carolina 28207 Atlanta, Georgia 30323 IRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild,.Esq.
P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 213515 Devine Street Columbia,' South Carolina 29205 0
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-f CATAWBA NUCLEAR STATION GENERIC LETTER 83-28 Status of Requirements Item 1.1 Post Trip Review (Program Description and Review).
The Post Trip Review Program was' described in our' response, dated November 4, 1983. The program is in place and will be implemented upon initial criticality.
Item 1.2 Post Trip Review (Data and Information Capability).
The Post Trip Review data and information capability was described in our response, dated November 4, 1983.
It is part of our Post Trip Review Program which will be implemented upon initial criticality.
Item 2.1 Equipment Classificaticr. and Vendor Interface (Reactor Trip System Components).
The Equipment Classification program and the Vendor Interface Program for Reactor Trip System Components were described in our response dated November 4 1983. These programs have been implemented.
Item 2.2 Equipcent Classification and Vendor Interface (All Safety-Related Components).
The Equipment Classification Program was described in our November 4, 1983 response and is currently being implemented.
The Vendor Interface Programs for all Safety-Related components were described in our response of May 7,1984. This program will be fully implemented prior to December 31, 1986.
Item 3.1 Post-Maintenance Testing (Reactor Trip System Components).
Our review of vendor technical information for Reactor Trip System Components is in progress.
The results of this review will be submitted prior to December 31, 1984. Any Technical Specification changes will be submitted at that time.
The Post-Maintenance Testing Program for Reactor Trip System Components has been implemented.
Item 3.2 Post-Maintenance Testing (All other Safety-Related Components).
A review of vendor technical information is in progress. The results will be submitted by the end of the first refueling outage. Any Technical Specification changes will be submitted at that time.
The Post-Maintenance Testing Program has been implemented.
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sItem 4.1L !Reac, tor; Trip'SystemReliabilityj(Vendor-RelatedModifications)..
fRefer( to our response' dated' November' 4. - 1983.: IThis modification =
'was'coupleted prior-to fuel load.
- Itensi4!2.llReactor Trip System'RS11 ability:(Preventative Maintenance and and ' 4.2.2 : ;ParameteriTrending: Program'for.Re' actor Trip Breakers).
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The Preventative Maintenance' Program for Reactor Trip'
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Breakers and;the'; Parameter Trending-program, if needed,.
-will'beLimplemented by-December 31, 1984.- A' description-L
.of the Preventative Maintenance' Program for Reactor. Trip Breakers will:be submitted by December 31,:1984.
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- Items 4'2.3zReactor Trip System Reliability.(Life Testing andiReplacement.
and 4;2.4' Program for Reactor Trip' Breakers).
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The Reactor Trip' Breaker Trip' Attach' ment Life Testing and:
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- Replacement; programs'will be submitted prior to-startup from-the first refueling' outage. JThe^ Replacement program,' which
'is a.part of~the Preventative Maintenance program', will be
' implemented by December 31,:1984.
Itsa 4.'3
-Reactor Trip System Reliability (Automatic Actuation of c
Shunt Trip Attachment for W and B&W Plants).
i The Shunt trip attachment modification was described in ourl response-of November 4,.1983 and completed prior'to fuel-load.
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-Item 4.5 Reactor Trip System Reliability (System; Functional Testing).
We are awaiting NhtC review of: the Westinghouse. Owner's Group
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WCAP-1011 --Supplement 1.
Any changes.to the surveillance requirements of.the Standard Technical Specifications, will i'
be incorporated into the Catawba Technica1' Specifications.
These changes will be submitted prior to startup from.the.
.first refueling outage.
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