ML20147B868

Summarizes 780103 Meeting Re Proposed Staff Responses to Questions Raised in ACRS Subcommittee Meeting of 771216

ML20147B868
Person / Time
Site:	Yellow Creek
Issue date:	10/05/1978
From:	Cox T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7810110209
Download: ML20147B868 (5)

Text

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L,HTED STATES

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p;d NUcLMR REGULATORY COMMISSION 4

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ef OCT 0 51978

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Decket Nos. STN 50-566

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and STN 50-567 APPLICANT: Tennessee Valley Authority (TVA)

FACILITY:

Yellow Creek Nuclear Plant

SUMMARY

OF MEETING HELD JANUARY 3,1978 The subject meeting was held at the U. S. Nuclear Regulatory Commission offices in Bethesda, Maryland.

The purpose was to discuss proposed staff responses to questions raised in the ACRS Subcommittee meeting of December 16, 1977.

The staff responses were expected to be requested again in the ACRS full committee review of the Yellow Creek project i

scheduled for January 5,1978.

e The topics discussed in the meeting were as outlined in a ".emorandum from D. B. Vassallo to R. J. Mattson dated December 21, 1977.

Subject:

"ACRS Full Committee Meeting - Yellow Creek Nuclear Plant".

This memorandum is included in this summary as Enclosure 1.

is a meeting attendance list.

Each of the potential discussion topics was briefly reviewed at this i

meeting.

Staff managers agreed that staff members qualified and prepared to address each of the issues or topics identified in the December 21 memorandum would be present at the ACRS meeting on January 5.

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In addition, Structural Engineering Branch representatives brought out that, in accordance with the SEB memorandum of December 23, 1977, from I. Sihweil to D. Vassallo, two new safety issues had been i,

identified and should be described to the ACRS.

The new issues 1

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concern (1) applicant's proposed method of calculating overturning moment on seismic Category 1 structures, and (2) applicant's proposed use of ACI 349 as the governing code for concrete construction.

It was agreed that the licensing project manager would cover these new issues in his remarks to the ACRS.

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M homas H. Cox, Project Manager Light llater Reactors Branch flo. 3 Division of Project Management

Enclosures:

1.

Memorandum from D. Vassallo to R. Mattson dated 12/21/77, "ACRS Full Committee Meeting -

Yellow Creek Nuclear Plant"

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Meeting Attendance List w

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DEC 211977 EilCLOSUREl j

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}tEl10RAllDUM FOR:

R. f tattson, Director, Division of Systems Safety FROM:

D. B. Vassallo, Assistant Director for Light 1!ater Reactors, Division of Project t'anagement 1

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SUBJECT:

ACRS FULL CCF2ilTTEE l'EETI!IG - YELLOW CREEK ftUCLEAR

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Reference:

,, ACP.S Subcocaittee Transcript, yellow Creek !!uclear Power Plant, Friday, Decenber 10, 1977 The subject full comittee nacting is currently scheduled to begin at 1 Pli on Thursday, January 5,1978 in our H Street offices.

At the Subcounittee neeting on Decer,ber 16, 1977 in Corinth, Mississippi, a number of questions were raised v hich we believe will be raised again at the full comittee meetino.

I ao requesting that appropriate

,nembers of your staff be present at the 01/05/78 ceeting to discuss the issues identified in this nemo.

The issues identified below were (1) the subject of a direct request for infornation from an ACRS conter, (2) were indicated t.o be of snecial importance to one or core ACRS morbers, or (3) were topics (.'sually outstan> Jing issues) which an ACRS nr.ber indicated the need for r. ore infornetion in order to better undarstand the bases behind the staff's position.

1.

?!r. Carbon's concern for the possible explosion of a barge at the shoreline by the plant, possibly due to sabotage (Transcript p. 39) 2.

ACRS interest in current interpretation of SSE acceleration versus intensity relationship for near and far-field si,tuations

-(Transcriptp.105,ff.)

3.

Dr. Kerr's interest in staf f's basis for requiring rebound and settlement records, particularly, where is an applicant to see this requirement in uriting (Transcript p.119, ff.)

4.

Design basis concrete strength for walls and roofs to withstand tornado missiles, (Transcript p. 125,126,142,143)

'5.

Itain stean line break analysis (Transcri p.131,ff.)

6.

Illninum containment pressure analysis (Transcript p.130, ff.)

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R. !!attson DEC 211977 7.

Plantmonitoringsystem(Transcriptp. 138, 144 ff.)

8.

Fire protection (Transcript p. 108,173 ff.)

9 9.

Mr. Carbon's concern for effects of very large fire external to plant (Transcript p. 177, 178) l l

10.

Containment leakage testing - fir. Carbon asks what'is current experience in actual testing (Transcript p.137, ifs)

In addition to the specific areas identified above, representatives from technical review areas which have outstandinc issues li.sted in, g

Section 1.9 of the st'aff's SER on Yellow Creek should be present.

This would include, in addition to the technical review areas associated i

with the items 1 to 10 above, the following branches:

f Outstandinq Issue Mo.

llydrology - iteteorology 1

4, 5, 18 Reactor Systems Accident Analysis 10, 12 Materials Engineering 16 Mechanical Engineering 16 06;in#@Mi i

rb.t.. hallo D. D. Vassallo, Assistant Director for Light !!ater Reactors Division of Project fianagement 5, cc:

R. Doyd D. Ross

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R. DeYoung T. flovak i

D. Vassallo P. Check l

T. Cox Z. Rosztoczy

!!. Denton R. Tedesco W. Garmill V. Beneroya i

L. Ilulman G. Lainas C. Stepp T. Ippolito D. Bunch F. Rosa 1

J. Knight R. Bosnak S. Pawlicki I. Sihweil s

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ENCLOSURE 2 i

l ATTENDANCE LIST 1

MEETING OF 01/03/78 i

YELLOW CREEK f

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T. Bennett S. Bhatt J. Burns g ~

C. Hofmayer H. Polk C. Moon M. Rubin T. Novak C. Tinkler T. Cox D. Vassallo R. Mattson F. Schroeder

0. Parr W. Bivins M. Fliegel G. Lainas C. Ferrell L. Soffer

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