ML19323E686

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Requests Forwarding of Encl Matl Re Steam Generator Refill to Board Members & Parties to Proceedings
ML19323E686
Person / Time
Site: Rancho Seco
Issue date: 05/08/1980
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Scott S
NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8005270130
Download: ML19323E686 (5)
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o UNITED STATES E

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NUCLEAR REGULATORY COMMISSION g

l WASHING TON, D. C. 20555

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May 8, 1980 s

E Docket No. 50-312 MEMORANDUM FOR:

Steve Scott, Chief, Distribution Services Branch, ADM e-I FROM:

Darrell G. Eisenhut, Director, Division of Licensing, NRR

SUBJECT:

BOARD NOTIFICATION - RANCHO SECO FACILITY Please forward the enclosed material to the Board members and parties to the proceedings.

IL -

Darrell G. Eisenh

, Director Division of Licensing Office of Nuclear Reactor Regulation cc w/ enclosures:

H. Denton E. Case E. Christenbury S. Varga D. Thompson S. Lewis D. Garner L. Nichols R. Capra T. Novak THIS DOCUMENT CONTAINS P00R QUAUTY PAGES 8005270@O.

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DISTRIBUTION OF BOARD NOTIFICATION (Steam Generator Refill) j RanchoSeco(DocketNo.50-312)

Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Board Panel l

Docketing and Service Section Thomas A. Baxter, Esq.

Elizabeth S. Bowers, Esq.

Herbert H. Brown, Esq.

Dr. Richard F. Cole i

Mr. Michael R. Eaton Christopher Ellison, Esq.

David S. Kaplan, Esq.

l Mr. Frederick J. Shon ACRS Members Mr. Myer Bender Dr. Max W. Carbon Mr. Jesse C. Ebersole Mr. Harold Etherington Dr. William Kerr 4

Dr. Stephen Lawroski Dr. Harold W. Lewis 1

Dr. J. Carson Mark l

Mr. William M. Mathis Dr. Dade W. Moeller Dr. David Okrent Dr. Milton S. Plesset Mr. Jeremiah J. Ray Dr. Paul G. Shewmon j

Dr. Chester P. Siess Mr. Roger Smith 1

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EVALUATION OF ENCLOSED MATERIAL Issues now before the Rancho Seco Licensing Board encompass control of auxiliary feedwater system flow rates.

The enclosed material appears to be relevant to these issues. The enclosure is a letter from Babcock

& Wilcox to the Sacramento Municipal Utility District pointing out the potential concerns associated with the overfilling of steam generators.

The letter requests that the utility undertake a review of the effect of overfill on the main steam line pipes.

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' 'T AE N. February.~19; 1980 B&W 177FA Plant' Owndis Group meeting a ptelimihary

./p.Mfety concu6..'(P.SC) concerning steam.geheretor overfill was discusse.d.

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M M:.> m..NNAIisiM$ted sihin!ssO and p EeNs OMeoncern;.thsI.~..Nphntia o

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Excess 1V,e' feetaler, eddit9on as 'used he6i. is defined as a condition which.

woutd ex1st if (main or euxiliary) 1s continually added to the

,ite m geherate. fee &ater16 an tmplanned fashion. At a rate greater, than the c6re hea id::nnatiM cipsbility for converting it to steam..~ Overf111 the condition

,. addressed in this PSC6 may be defined as a limiting case of excessive feedwater

' eddition.which allows liqui.d spillag'e into the steamlines...;

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.lt..h Estimated that ths tiime to overfill the Steam'Generatorii is ~a.pproximately.

- 2.to 4 minutes 91th main fee & vater and between17...to.15 'minutss'with' auxiliary'~

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.1., v 1.h.tG,ntia17. eiuI.ts. of ov.erfill hiuld bs:..,, f -

f ~ team li..,,.,..ne defor:matfori and. failure due to Water accumulatio, k.

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'.' I' St'das heidrator b' lowdown due to'steim'.line failure 8th he potential e, i. ' $ for. cord. return to power from a safe shutdown condition excessive y. steam generator tube stress, exceeding " reactor vessel. NDT ' limits or

/ E P. con.t.a.i.nment overpressurfration.

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  1. 3Votalstri the evaluation of the PSC.is the abili.t.

f plant steam lines to

'stirV1Veg With60t breakistgi'tfFitatTc and dynamic)y o effects of overfili.

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B&W has not specifRally analyTed a~ worst tase rssult from steam line break dde td ' Overfill potential.resulfs,it is our best engineering judgement faced witli the. above'that if the o

exists... Conversely, based on best engineeFing judgeinent and results of

, 86&lff,1f. dahe fof's. Consumer Power Co. for the recent operating plant show cause

'orded tih,the'stea t generators, if the stieam jines do not fail a reportable safetf

.S.-y,-;. concern does riot exist. C

'Thd iirrsniedhnt and:desiijn of de s' eondary systern is the responsibilit,y of c

the. licensee' 'and his A/E and is therefore plant specific.

In addition' the

. stress Analysiiof the steam lines is not done by Ball (in A/E's scope), thus

.ths Company is not prepared to do such analysis.

Considering these facts, it

,tc bu'r' judpe:nent.that we cannot complete the evaluation of this concern.

The re--

fore', purduant with Section 21 o_f 10CFR21, B&W is requesting each of.the plant

.Ticensees ic complete the evaluation and _ determine th_e reportability of the P$C.

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If B&N can be o/ ariy further assistance in this matter, please let us know.

1 We wouId appreciate being notified of tne results of your evaluation And any bo'r rect 1Ve etion plan that may be initiated.

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Yours truly, n.

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Service Manager 61 S }Vd' g

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R. J. Rodriguez

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33 WY r.c r, R. P. Dubre' R. A. Dieterich

5. 1. Anderson

'Ji R. Sheller J. II. Johnston s

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