ML20134F900

Forwards Request for Addl Info Re Reactor Protection Sys,Per 850802 Telcon.Response Requested by 850805

ML20134F900
Person / Time
Site:	River Bend
Issue date:	08/02/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:	William Cahill GULF STATES UTILITIES CO.
References
NUDOCS 8508210313
Download: ML20134F900 (4)

Text

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AUG 2 1985 Docket No.: 50-458 Mr. William J. Cahill, Jr.

Senior Vice President River Bend Nuclear Group Gulf States Utilities Company Post Office Box 2951 1 Beaumont, Texas 77704 ATTN: Mr. J. E. Booker

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - REACTOR PROTECTION SYSTEM Confirming a telphone conversation on August 2, 1985, between R. Bernero of the NRC and yourself, we are requesting additional information in the area of the reactor protection system. The request for information is detailed in the enclosure.

Pursuant to our agreement, please respond to this request by COB August 5, 1985. Please inform NRC Project Manager, Stephen Stern, of any request for clarification or further discussion on this topic.

Sincerely,

M 'ien1 siened by:

Walter Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

As stated cc w/ enclosure:

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l Mr. William J. Cahill, Jr. 1 Senior Vice President River Bend Nuclear Group Gulf States Utilities Company Post Office Box 2951 Beaumont, Texas' 77704 ATTN: Mr. J. E. Booker

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - REACTOR PROTECTION SYSTEM Confirming a telphone conversation on August 2, 1985, between R. Bernero of the NRC and yourself, we are requesting additional information in the -

area of the reactor protection system. The request for information is i detailed in the enclosure.

Pursuant to our agreement, please respond to this request by COB  !

August 5, 1985. Please inform NRC Project Manager, Stephen Stern, of '

any request for clarification or further discussion on this topic.  :

i.

Sincerely,  ;

Walter Butler, Chief Licensing Branch No. 2 Division of Licensing ,

Enclosure-As stated cc w/ enclosure:

See next page -

r I:r. Uilliam J. Cahill, Jr.

Gulf States Utilities Ccmpany River Send I;uclear Plant cc:

Troy B. Conner, Jr. , Esq. lis. Linca B. Watkins/Mr. Steven Irving Ccnner and lletterhahn Attorney at Law 1747 Pennsylvania Avenue,f411 355 hapoleon Street Washington, D.C. 20006 Batcn Rouge, Lcuisiana 70802 ilr. William J. Reed, Jr. Mr. David Zalcudek Director - Nuclear Licensing Nuclear Energy Division Gulf States Utilities Company Louisiana Department of P. O. Box ' 2951 Environmental Quality Beaumont, Texas 77704 P. O. Ecx 14690 Baton Rcuse, Louisiana 70898 Richard it. . Troy, Jr. , Esq.

Assistant Attorney General in Charce I;r. J. Davic McNeill, III State of Lcuisiana Department of Justice William G. Cavis, Esq.

234 Loyoia Avenue Department of Justice New Crleans, Louisiana 70112 Attorney Generai's Office 7434 Perkins Road Pesicent :nspector Baton Rouge, Lcuisiana 7 CEC 8 P. O. Box 1051 St. Francisville, Leutstana 70775 H. Anne Plettinge-3456 Villa Rose Drive Gretchen R. Rothschild Baton Rouge, Lcuisiana 70806 ~

Lcuisianians for Safe Enercy, :nc.

1659 Glenmore Avenue Baton Ecute, Lcuisiana 70775 Jaa:es W. Pierce, Jr., Esq.

P. O. Box 23571 Baton Rouce, Lcuisiana 7C893 Regicnal Adninistrator, Region IV U.S. Nuclear Regulatory Cucuission Office of Executive Director for Operations GI'. Ryan Plaza Drive, Suite 1000 Arlingtcn, Texas 76011 ,

/

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Enclosure 1 RIVER BEND REQUEST FOR ADDITIONAL INFORMATION_

GSU should provide adequate justification for using non-safety related equipment in the RPS downstream of the EPAs, or design, install, and classify these components as safety related. If justification for the existing design is provided, it should be demonstrated that all RPS bus loads are not required during or following any design basis event, in particular, seismic events.

Since the distribution panels and breakers are not seismically qualified, the staff is concerned that: (1) power cannot be restored to the RPS buses following a seismic event, and (2) faults resulting from a seismic event could degrade the RPS (if the MG sets remain on line during the event). The first concern is that loads powered from the RPS buses may be required to achieve, maintain, and monitor safe shutdown of the reactor following a seismic event.

The second concern is that a seismic event could cause a degraded voltage condition at the RPS distribution panels (e.g.,'Jndervoltage) that would not be detected by the EPAs, and could compromise the safety function of the RPS.

In addition, since the RPS distribution panels and breakers have been l

identified as non-safety related, the staff is concerned that they will not i ,

I receive the same treatment as safety related components (e.g., during i

i maintenance activities), which could lead to degradation of RPS performance.

1 Furthermore, since these non-safety related components are located downstream of the EPAs, the staff is concerned that the function of the EPAs (i.e., to ensure that adequate voltage is supplied to RPS components) could be compromised.