ML20052G090

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Forwards Notification of 820520 Meeting W/Util in Bethesda, MD to Discuss Seismic Design Adequacy
ML20052G090
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 05/12/1982
From: Chandler L
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Udell R
Public Citizen's Critical Mass Energy Project
References
NUDOCS 8205140298
Download: ML20052G090 (1)


Text

1 O

May it,1982 Docket No. 50-206

-1 1

Mr. Richard Udell Critical Mass J

215 Pennsylvania Avenue, S.E.

Washington, D.C.

20003

Dear Mr. Udell:

In accordance with our phone conversation today, enclosed is a copy of the meeting notice and agenda for the forthcoming meeti,s g

concerning San Onofre Nuclear Generating Station Unit 1.-

ff RECEIVED Sincerely,

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MAy 131987,> ~._

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sa mm w mots u uc:

ro Lawrence J. Chandler co a

Deputy Assistant Chief Hearing Cou DISTRIBUTION:

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Miraglia S. Burns Rood Chron b $01 0FC

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DATE : S/ \\Y/82 :

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g NUCLEAR REGULATORY COMMISSION

.p WASHINGTON, D. C. 20555

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May 11, 1982

. Docket,No. 50-206 MEMORANDUM FOR:

Dennis M. Crutchfield, Chief Operating Reactors Branch #5, DL FROM:

Walter A. Paulson, Project Manager Operating Reactors Branch #5, DL

SUBJECT:

FORTHCOMING MEETING WITH SOUTHERN CALIFORNIA EDISON COMPANY - SAN ONOFRE UNIT NO. 1 Date & Time:

Thursday May 20,1982 1:00 PM Location:

Room P-118 Phillips Building 7920 Norfolk Avenue Bethesda, Maryland

Purpose:

To discuss San Onofre Unit No. 1 seismic design adequacy (seeattachedagenda).

Participants:

SCE K. Baskin, et al..

NRC W. Paulson, D. Crutchfield, W. Russell, G. Lainas, R. Purple, D. Eisenhut, E. Case. H. Denton, J. Knight, F. Schauer, R. Vollmer, S. Burns, R. Hoefling and L. Chandler h0W b-qu Walter A. Paulson, Project-Manager Operating Reactors Branch #5 8

Division of Licensing e

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d MEETING AGENDA SAN ONOFRE UNIT 1 4

SEISMIC DESIGN ADEQUACY 1.

Confirmation and demonstration by.the licensee that the original plant design and construction met the licensing basis described in the FSAR.

2.

Seismic capacity of the Reactor Coolant Pressure Boundry (RCPB) and systems and equipment necessary for safe shutdown (hot shutdown).

~

a.

Implication of lack of system availability following a postulated SSE (0.5g Housner) based upon the licensee's reanalysis (0.67g Housner) and the licensee's structural integrity criteria (April 30, 1982 su bnittal ),

b.

Non-conservatisms in the licensee's st.ructural integrity criteria which when considered would identify additional system or component availability concerns, c.

Identifb

' n of potentially serious deficiencies in the methods or reanalysis of RCPB branch lines which when considered could identify additional system availability Conc erns.

3.

Implication of Item 2 above for accident mitigation systems.

4.

Discussion of licensee's proposed program for corrective actions to be impl emented prior to startup.

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.