ML20215F598
| ML20215F598 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 06/10/1987 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8706220461 | |
| Download: ML20215F598 (4) | |
Text
- ___ - _..
3
~
June 10, 1987 i-
. Docket No. 50-601 APPLICANT:
Westinghouse Electric Corporation FACILITY:
RESAR SP/90
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS THE RESAR SP/90 APPLICATION On June 3, 1987, representatives of the NRC and Westinghouse met to discuss the general design features of RESAR SP/90. Attached is a list of attendees.
By letter dated June 1, 1987,. Westinghouse submitted the proprietary ~ version of this presentation. A non-proprietary version.will be submitted at a later
. time.
1 In summary, Westinghouse presented general design information regarding the RESAR SP/90 design.
Topics included a description of the advanced reactor i
design, steam generator design, the integrated safeguards systems, secondary side safeguards system, fluid. systems, the integrated protection systems, and the containment system. The applicant discussed how the design improved mitigation of LOCAs, and how it reduced the core melt frequency as compared to-current plant designs.
M Nigned By:
Thomas J. Kenyon, Project Manager Standardization 6nd Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects DISTRIBUTION:
CDocketJUa NRC & Local PDR PDSNP Reading HBerkow TKenyon EHylton OGC-BETH EJordan JPartlow NRC Participants ACRS (10)
'P PD 4 E'
ton Ts on:cw w
/87 06 0/87 06/ g87
/
7 8706220461 870610' DR ADOCK 05 61
d.
kQ QEC
=
h
[g UNITED STATES
[
-g.
NUCLEAR REGULATORY COMMISSION yj WASHINGTON, D. C. 20555 k
\\****'/
June 10, 1987 i
Docket No. 50-601 APPLICANT:
Westinghouse Electric Corporation FACILITY:
RESAR SP/90
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS THE RESAR SP/90 APFLICATION On June 3, 1987, representatives of the'NRC and Westinghou w met to discuss the general design features of RESAR SP/90.
Attached is a list of attendees.
By letter dated June.1, 1987, Westinghouse submitted the proprietary version of this presentation. A non-prop >ietary version will be submitted at a later time.
Insummary,Westinghousepresentedgeneraldesigninformationregardingthe i
RESAR SP/90 design. Topics included a description of the advanced reactor-design, steam generator design, the integrated safeguards systems, secondary 1
side safeguards system, fluid systems, the integrated protection systems, and the containment system. The applicant discussed how the design improved mitigation of LOCAs, and how it reduced the. core melt frequency as compared to-current plant designs.
)
l 72 Th as J.
yon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects I.
l q
d
J 9a RESAR SP/90 Briefing Meeting Attendees June 3, 1987 Name Organization T. Kenyon NRR/PDSNP H. Berkow NRR/PDSNP Faust Rosa NRR/ DST /SELB Jerry Swift NRR/DREP/RPB Brad Hardin RES/DRAA/PRAB James Wing NRR/ DEST /ECEB Sai P. Chan NRR/ DEST /ESGB Robert Jones NRR/ DEST /SRXB Steve Long NRR/DRPEP/RAB-C. D. Sellers NRR/EMTB j
Chang W. Kim NRR/ DEST /ICSB j
Fred Burrows NRR/ DEST /ICSB Jim Knight NRR/ DEST /SELB
~
Dom Tondi NRR/ DEST /SELB David Shum NRR/PSB.
Barry Mendelsohn NRR/DRIS/RSGB William Schivley W-APWR Licensing Program (NTSD/Nuc. Safety)
M. H. Shannon W-Nuclear Safety MGR-PSEL 1
(Licensing Prog MGR)
Theo van de Venne W-Engineering MGR APWR Development George Johnson NRR/ DEST /EMTB Gus Giese-Koch NRR/ DEST /ESGB I
Guy S. Vissing
'NRR/PDSNP Tom Dorian.
0GC.
C. Brinkman CE (Bethesda)
Mark Beaumont U (Bethesda)
)
Jack Spraul NRR/QAB j
i
E
.c.
., ;. Y Docket No. STN 50-601 -
RESAR-SP/90 -
cc: '
Dr. Robert Bari
' Brookhaven National Laboratory Building 130 Upton, New York. 11973 Mr. William Schivley Westinghouse Electric Corporation ECE-410 Mail Stop 4-08
- Box 355 Pittsburgh, Pennsylvania 15230
)
.m 1
1 G
i u