ML19312C739

Summary of 670609 Meeting W/Util Re ACRS Questions to Applicant

ML19312C739
Person / Time
Site:	Oconee
Issue date:	06/20/1967
From:	Grimes B US ATOMIC ENERGY COMMISSION (AEC)
To:	Boyd R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7912190948
Download: ML19312C739 (4)

Text

__

M 20 Roger S. Boyd, AD/RP, DRL Charles G. Long:s Chief, RPB #3 ha Signed by THRU:

crf B. Grimes, Reactor Project Branch NE.yes G. Long h

Division of Reactor Licensing JUNEACRSMEETINGONOCONEESTATION-DOCKETNO.5(d269/270/287 on June 8, 1967, the ACES considered the Duke Power Company application for three units at its Oconee Nuclear Station in the first of two sche-duled nestings. At the close of the meeting the committee indicated that a list of questions would be issued; some to be orally answered and some to be answered in writing.

I discussed the following points with R. Wascher of B&W and W. Lee of Duke Power on June 9, 1967.

1.

Consider in more detail the transient loadings in the reactor cavities during a loss-of-coolant accident due to confinament of steam.

(The primary shield wall is as important as the secondary wall because of the engi-neared safeguards which might be affected by failure of the primary wall.)

2.

A commitment that any new mill-acceptance tests on vessel plate material will be submitted for regulatory review as

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well as Code committee review should be made.

1 3.

Justify ths use of a proof test on the containment liner which does not exert the same or greater stresses as would be experienced in an accident.

4.

Present the analysis of the thermal transient experienced by the reactor vessel as a result of safety injection after a loss of coolant accident. Assess the significance of portions of the vessel being below NDT + 600P.

Is the vessel designed with this transient in mind?

5.

Will bowing of fuel affect the transient analysis? A more general question is: What effect will displacement of fuel (in any direction) have on the reactivity of the core, (1) during a fast transient and (2) as a result of local flow blockage resulting in meltdown of a single element.

6.

How much reactivity insertion in a rod ejection accident would cause disruption of the core internals so that core cooling!might be afIacted.

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JUN 2 01967 In addition to the above points, the ACRS asked the staff to (1) make sure that safety systems shared between units are not affected by the sharing and (2) state whether the fix proposed for the "stesa bubble" problem is acceptable to the staff.

During the meeting the applicant stated that the personnel hatch has been redesigned to have double seals on the outer door.

The vent line to the penetration room will be run from between the outer seals.

Distribution:

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DRL Reading RPB #3 Reading S. Levine D. J. Skovholt D. R. Muller R. Tedesco C. G. Long 1

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ACRS MEETING OCONEE NUCLEAR STATION Agenda for June 8, 1967-1.

General Description of Oconee ------------------- W S Lee 2.

Site ---------------------------- C--------------

W S Lee 3.

Containment ------------------------------------- W S Lee 4.

Core Physics & Mechanical Design ---------------- R E Wascher 5.

Reactor Coolant System -------------------------- R E Wascher 6.

Engineered Safeguards and Emergency Power ------- W.S Lee 4

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ATTENDANCE - ACRS SUBCOMMITTEE MEETING 6/8/v/

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Babcock & Wilcox Company.

Duke Power. Company

' ". Donald W Montgomery

• William S Lee

• s.-

Linwood C Dail

• f.-T George E Kulynych

• Charles J Wylie *

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Alan H Lazar

• Edward C Fiss *

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Robert E Wascher*

James H Taylor

• Warren H Owen

• Melvin F Sankovich*

Bill M Rice

• Howard H Stevens,

. Carl A Price

. Herbert E Flora

• Thomas F Wyke *

. James F Mallay*

Charles A Dewey

• Robert L Dick Thomas M Schuler*

James C Carlton*

John C Rogers William H Grigg Raymond C Luken*

. Douglas M Collings*

John H Kreps*

W 3 Rowand*

Bennett B Cardwell*.

Dames & Moore Bechtel Corocration

. Pierre R Cassidy Y Francis'E Courtney John J Tkacik Robert C Williams Howard W Wahl Consulting. Attorney-s Edward J Simanek

. Jack I Reilly

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.;Roy B Snapp*

- Martin Malcom

.t John H Utegaard *

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