ML17053A386

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Notification of 790122-24 Meeting in San Jose,Ca W/ Representatives of Mark I Owners Group to Discuss Mark I Long Term Program Load Definition Rept & Related Issues.W/ Encl Agenda
ML17053A386
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 01/08/1979
From: Charemagne Grimes
Office of Nuclear Reactor Regulation
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 7901250209
Download: ML17053A386 (4)


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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 8 1979 MEMORANDUM FOR:

D. G. Eisenhut, Acting Assistant Director for Systems and Projects, Division of Operating Reactors FROM:

SUBJECT:

C. I. Grimes, Task Manager A-7 FORTHCOMING MEETING WITH REPRESENTATIVES OF THE MARK I OWNERS GROUP DATE 5 TIME:

LOCATION:

PURPOSE:

ATTENDEES:

Monday, January 22, 1979 2:00 pm

Tuesday, January 23, 1979 8:30 am Wednesday, January 24, 1979 8:30 am San Jose, CA 1/22/79 GE Pruneyard Towers 1/23-24/79 Hyatt House To discuss the Mark I Long Term Program Load Definition Report and related issues.

A pro-posed agenda is attached.

NRC - C. Grimes, J. Fair, J. Kudrick, N.

Su BNL - G. Maise,'J.

Ranlet, R. Kosson, C. Tung, C. Economos,'A.

Sonin (MIT), G. Bienkowski (Princeton)

GE - B. Buchholz, L. Steinert, et. al.

Mar k I Owners - TRC Representatives EPRI - C. Sullivan, et. al.

LLL - E. McCauley, et. al.

Enclosure:

As stated C. Grimes Task Manager A-7 cc:

see page 2

>ppy 55p 40$

PROPOSED AGENDA Januar 22, 1979 2:00 - 7:00 pm Discuss l.

2.

3.

4, 5.

6.

ion of two and three dimensional pool swell test results 2D/3D data comparisons three dimensional effects test facility configurational differences effects of vent system orificing vent flow distributions pressure integration methodology Januar 23, 1979 I.

General Program Status Summary 1.

Schedule for submittal of outstanding reports.

2.

Implementation of LDR and plant-unique analysis content.

3.

Methods for resolution of NRC questions and comments.

II.

Ongoing program issues 1.

Downcomer submergence

-thermal stratification 2.

FSTF application methodology 3.

Fluid - structure interaction effects 4.

Load definition error and uncertainty III.

SRV Discharge Loads l.

quencher parametric testing a.

1/4 scale test results

b. scaling considerations (NEDC 23713) 2.

Monticello quencher test results 3.

Bubble phasing 4.

Pool temperature limits for quencher 5.

Monticello mixing test results.

IV.

Detailed discussion of NRC/consultant questions and comments on Mark I Load Definition Report (NEDO 21888).

~J24.

1978 I

Continuation of NRC/consultant questions and comments on Hark I Load Definition Report.