ML20199G238
| ML20199G238 | |
| Person / Time | |
|---|---|
| Issue date: | 10/14/1976 |
| From: | Lafleur J NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP) |
| To: | Heineman R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20199G207 | List: |
| References | |
| FOIA-85-665 NUDOCS 8604090094 | |
| Download: ML20199G238 (3) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMIS810N y
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R. E. Beineman, Director, Division of Systems Safety, Intr SWISS VISIT.. REQUEST (0CTOBER 27-28, 1976) e.
The fo11oving 4-man Swiss team has requested a series of appointmen;;s at NRC on October 27-28, 1976,.to address the attached discussion topics (Enclosure 1),
whiEh I believe all f all within the responsibility of DSS:
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- Mr., F. W. Weehuizen, Head of the Nuclear Engineering Section, Nuclear Safety Division, Swiss Federal Office of Energy Economics (ASK) s
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[Dr.M.J. Lewis,AnalyticalGroup,NuclearEngineeringSection,ASK Mr. P. Krebs, Head of the Ndclear Division, Swiss Boiler Association (SVDd)
(Responsible for quality control of all ASK mochtnical equipment)
Mr. Kusemodel, Head of the Heavy Imactor Component Group, SVDB They have requested.that items 2.2.3 thran=h 2.2.7 he =ri A.. tad on October 27, 1976, when the full delegation will be present. (The SVDs representatives will attend only the first da 's meetings.) Grenhar 28 could then be devoted gw 4g j,fg, gV A _,1,al, ((,4,so @
(See Enclosure 2 for additional detai s on to iter.s 2.2.1. 2.2.2. ans'2,2.8.
2.2.1 and 2.2.2.)
I wuld appreciate your designation of sonronriate contacts for each of areas listed. I hope to schedule the meetings in Room 7414 wuna r m. o,1 u g o, both days, with a two hour lunch break. Ple'ase advise Donna Chenier (X27788)
'of your nominations as soon as' M e.
As further backgrou.d. the group will be en route from (a) discussions at GE-San Jose on transient analysis, Mark Il containment dynamic behavior, and l
-4 other questions on the status of Mark I and Mark II containments sad ICCS, particularly core spray effectiveness, and (b) a visit to GE-Wilmington, North Carolina, for on-site checks of the quality control organisation and effective-ness. Following their NRC appointments, the will travel to the LaSalle nuclear station, and then return home.
h9604090094e60212 PDR FOIA FIRESTOSS-665 PDR Joe D.
r, Jr.
Dep y Director i
Off ce of International Programs Enclosures 1.
Main Discussion Topics 2.
^$upplemental List ect E. G. Case, NRR o
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NHC-AUK $.WDD-Mecting Nr. II. Praferably October 27-28
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ASK:
Dr. M. Lewis, Mr. F. Weehuizet.
Mr. P. Krebs, Mr. KXsemodel SVDB:
Since Dr. Lewis is at present on holiday, possibly more detailed items regarding containment will be submitted '
in about 10 days.
Present status of BWR-pressure suppression containment *
- (I 2.2.1 dynamic behaviour for LOCA (Mark I, II and III) and S/R valve actuation.
2.,2.2 Present status of BWR-ECCS-computer models We have been informed by GE that their proposals for modifying present computer models - which e.g. give a
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Tclad max. of 24000F at DBA-LOCA with one or two spray lf systems on BWR/6 - ip being checked by NRC and that final decisions are expected for this fall. Since Mr.Njo was absent during detailed discussions in our house with
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GE this spring, it may.be advisable to restrict dis-cussions on this subject to Trip No. II, see 2.2.2).
2.2.3 Criteria for considering plant stationary and transient
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loads / earthquake loads and combinations of these for reactor coolant pressure boundary, containment, supports and pipe whip provisions for r.c.p.b.. and main steam / feed f,/2) water piping. (Refers to NRC Reg. Guide 1.48/1 57) Special f
questions are e.g. (1) consideration of earthquake causing LOCA causing broken loop still being subjected to earth-quake following break; (2) considerations on loading conditions.for r.c.p.b. supports, LOCA load " normal" condition as for containment?; (3) same as (2) for pipe whip provisions.
2.2.4 Codes and Standards for load carrying steel / concrete structures like BWR pedestal and biological shield.
2.2 5 Basic philosophy underlying pipe whip protection criteria like Reg. Guide 1.46, e.g. interference with Inservice-Inspection requirements; similar considerations for pipe penetrations with guard pipe, such as in Mark III Contair ment.
2.2.6 Backfitting considerations regarding component supports and pipe whip protection.
2.2 7 Pressure Vescel Internals Integrity
_ g, We would liket to have % broad general discussion on loadirs renditions, allowable stresses,and code conside-rat 10ne 3r the design and stress analysis of vessel "h % nt' < with due consideration of loadings considered
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for both PWR and BWR vessel internals.
2.2.8 Plant general layout, redundancy considerations, external events.
During Mr.' Lafleur's visit to the ASK on Febr. 26, 1976, he suggested a*round table talk between NRC-and ASK-specialists on plant general layout and redundancy 2I considerations in view -of discrepancies between US and european (also swiss) philosophy, the latter being based on the german concept.' We would be willing to give an introduction by describing the layout concepts
'of the new Swiss pl' ants 05sgen (KWU-PWR), Leibstadt and Graben (both GE-BWR with BBC conventional part).
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