ML19241B277

Forwards Revision 1 to Rept on Reanalysis of Safety-Related Piping Sys. Seven Piping Supports Will Be Modified & Two New Supports Will Be Installed.Requests Authorization to Begin Interim Operation Until Refueling

ML19241B277
Person / Time
Site:	Beaver Valley
Issue date:	07/11/1979
From:	Woolever E DUQUESNE LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML19241B278	List: ML19241B277 ML19241B279
References
TAC-42636, NUDOCS 7907130410
Download: ML19241B277 (106)

Text

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Duquesne Udit , , , . _

.35 Sath Ai snue Pittsburgh, Pennsylvania 15219 July ll, 1979 Mr. Harold R. Denton Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attention: A. Schwencer, Chief Operating Reactors Branch .s'o. 1 Division of Operating Reactors Washington, DC 20555

Reference:

Be ver Valley Power Station, Unit No. 1 Docket No. 50-334 Request to Modify the Commission's March 13, 1979

" Order to Show Cause" Gentlemen:

Enclosed are tnree (3) signed , originals and thirty-seven (37) copies of Revision 1 to the " Report on the Reanalysis of Safety Related Piping Systems for Ecaver Valley No. 1 Unit". This revision consists of replacement pages to the original report submitted to you on June 19, 1979 and includes responses to certain questions received from the staff in a telephone ccaversation on June 28, 1979.

The status of the reanalysis ef fort has been updated, and a summary prcvided of the results of the reanalysis of safety related piping at Ecaver Valley Unit 1 performed to date.

As described in the revision to the report, a total of seven piping supports will be rodified and t,.:o new supports, consisting of a total of three techanical snubbers, will be installed. The completion of these nodifications will assure that the occurrence rf the safe shutdown earth-quake for Beaver Vallcy Unit 1 will not result in seismic loads on iping systems which Jill impair the fonctional capability of engineered t.,;fety features or the c=ergency core cooling systems, or prevent the raintenance of safe shutdown conditions, or result in irreparable damage to systems required to bring the plant to a cold shutdown condition.

As of this date, the Analysis of the Reactor Coolant Pressure Boundary is complete and acceptable with the modification of four supports. All other systems required for safe shutdown either have been found completely acceptable or have been judged to be acceptable based on short tern criteria.

541 037 L(( ()

7907130 44 l6

Beav-t 7. . . c , 7 3.'r Station, Unit No. 1 D . t No. 5 ^- 35s P.4 test ta Modify the Commission's March 13, 1979

er to Show Cauce" p- ,2-The Station Onsite Safety Committee and the Company Offsite Review Comnittee have determined that the facility may be safely operated once the identified modifications are c;_pleted and that no unreviewed safety question, as defined by 10CFR50.59, will exist.

We, therefore, request that so much of the Commission's March 13, 1979 Order which requires the plant to remain in a shutdown condition be modified at this time to permit interim operation of the unit until the time for refueling. We estimate that the reactor will be ready for refueling after operation for a period of six to seven weeks following startup.

The balance of the current reanalysis effort will continue during this interim operation in order to identify required modifications for the remaining piping systens analyzed with Shock II -- i.e., those piping systems which are not required for safe shutdown capability or not associated with the engineered safety features or the emergency core cooling systems -- and any additional modifications will be completed during the second refueling period.

Very truly yours, E. J. Uoolever Vice President, Engineering and Construction Enclosure 541 038

Uni ted St at es Nuclear Isegulatory Cormission Page 3 O

CO.NB10NWEALTH OF PENNSYlXANI A )

) SS:

COUNTY OF ALLEGHENY i On this 11th day of July, 1979 be fore me ,

P\UL 11 . MollI N , a Nc. t a ry Public in and for said Conunonwea l th and Coun ty , persoc;11y appeared E. J. Woolever who being duly sworn, disposed, and said that (1) he is Vice President of Duquesne Light Comp:iny , (2) he is duly authorized to execute and file the fo rego i ng i n fo rma t ion on behal f of said Conpany , and (3) the statements set forth in the Information are true and correct to the best of his knowledge, information and belief.

WITNESS my hand and seal the day and year fi rs t above wri t t en.

\, . _. 4 \'TN _

541 039

BEAVER VALLEY POWER STATION, UNIT 1 Revision 1 INSTRUCTIONS FOR ADDING REVISION 1 TO THE REPORT ON THE REANALYSIS OF SAFETY-RELATED PIPING SYSTEMS The following listing will serve as a checklist for entering the atcached pages into the report. The items listed in the " REMOVE" column should be removed from the report and replaced with the items in the " ENTER" column.

Vertical bars (change bars) have been placed in the outside margins of revised text pages and tables to show the location of any technical changes originating with this amendment. Some pages bear a new amendment designatien, but no change bars, because rev sions on other pages in that section caused a text shift. A few unrevised pages have been reprinted because they fa!!

within a run of closely spaced revised pages. No change bars are used on figures or on nau sections, appendices, questions and responses, etc. Change bars from previous amendments have been deleted on pages revised by this amendment. The instruction sheet and cover letter should be filed at the beginning of the report.

REMOVE ENTER Title page Title page

p. 1-2 p. 1-2 thru l-3 Table 1-1

p. 3-1 thru 3-19 p. 3-1 thru 3-27 Table 3-1 Table 3-1 Table 3-2 (4 pages)

p. 4-1 thru 4-3 p. 4-1 thru 4-3 Table 4-1 (7 pages) Table 4-1 (8 pages)

Table 4-2 (5 pages) Table 4-2 (6 pages)

p. 5-1 thru 5-3 p. 5-1 thru 5-3 Table 5-1 (5 pages) Table 5-1 (6 pages)

Table 5-2 (6 pages) Table 5-2 ( 3 pages)

p. 6-2 p. 6-2

p. 7-1 p. 7-1 and 7-2

p. 8-3 p. 8-3

p. 8-4 p. 8-4

p. 8-6 p. 8-6

p. A-1 thru A-8 p. A-1 thru A-9

p. 3-1 thru B-4 p. B-1 thru B-4 Table B-2 (3 pages) Table B-2 (1 page)

Table B-3 (3 pages) Table B-3 (4 pages)

p. C-1 p. C-1 Fig. 6.3-1 Fig. 6.3-1 Fig. 6.3-2 Fig. 6.3-2 Fig. 9.3-1 Fig. 9.3-1 Fig. RM-53A (after Fig. 10.3-5)

p. D-1 p. D-1 Fig. 4-2 -

Fig. 6.3-1 -

Fig. 6.3-2 -

Fig. 6.4-1 Fig. 6.4-1 Fig. 9.1-1 -

541 040

BEAVER VALLEY POWER STATION, UNIT 1 avision 1 REMOVE ENTER Fig. 9.3-1 -

Fig. 9.4-1 Fig. 9.4-1 Fig. 9.5-1 Fig. 9.5-1 Fig. 10.3-1 -

Fig. 10.3-6 -

Fig. RM-53A -

p. H-6 p. H-6

- p. H-15

p. H-16 541 041 2