ML19290B826
| ML19290B826 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/03/1979 |
| From: | Tibbitts D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912140185 | |
| Download: ML19290B826 (7) | |
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UNITED STATES
'j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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- ,' G DOCKET NO. 50-395 APPLICANTS: SOUTH CAROLINA ELECTRIC AND GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY FACILITY:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT N0. 1
SUBJECT:
SUMMARY
OF MEETING HELD ON OCTOBER 25, 1979 WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY On October 25, 1979 we met with representatives of South Carolina Electric and Gas Company (SCE3G), Westinghouse Electric Corporation (Westinghouse), and Gilbert /Conmonwealth (Gilbert) to discuss seismic qualification of electrical and mechanical components. Personnel from the Naval Research Laboratory (NRL) also attended the meeting; NRL is under contract to the Nuclear Regulatory Conmission (NRC) to perform the review of mechanical and electrical equirment qualification for seismic and hydrodynamic loads. The persons attending the meeting are listed in Enclosure No.1.
We began the neeting by (1) describing the procedure that would be used in the staff audit of equipment dynamic qualification and (2) discussing the status of the review for the Summer facility. The procedure for the staff review is briefly outlined in.~nclosure No. 2.
For the Summer facility, SCE&G had previously sent in a listing of the seismic
~ Category I components. The next step was for the staff to prepare the list of selected equipment for audit. The staff estimated that this list would be issued to SCE&G by the end of November 1979.
We then discussed the criteria, standards and methods used in the qualification of components. The approach for the qualification of electrical equignent specified by Westinghouse varied significantly from the approach used for the equipment specified by Gilbert. While the FSAR cocmitment for electrical equip-ment is to IEEE Std. 344-1971, " Seismic Qualification of Class IE Equipment for Nuclear Generating Stations," the Gilbert design specification for seismic qualification incorporated many for the features of IEEE Std. 344-1975. Also for many of the components that were procured after 1975, IEEE Std. 344-1975 was used for qualification. Most of the specifications for the Westinghouse supplied equipment were prepared prior to 1973 and the qualification for the equipment was based only on IEEE Std. 344-1971. Westinghouse had a generic program to reevaluate the electrical equipment qualified to IEEE Std. 344-1971.
This generic program is applicable to the Summer facility.
1574 215
\\W 7912140 T
s
..G,N There were also differences between the qualification of mechanical components specified by Westinghouse and Gilbert. The principal difference was with the use of the recomendations of Regulatory Guide 1,48, " Design and Loading Com-binations for Seismic Category I Fluid System temponents," May 1973. Gilbet.
has incorporated portions of the recommendations of Regulatory Guide 1.48.
The Westinghouse equipment was designed to meet the fiRC recommendation thac was used prior to the development of Regulatory Guide 1.48.
We also discussed the status of the applicants' review and acceptance of qualification documents from equipment vendors. Westinghouse stated that their review was about 95 percent complete. Gilbert made available to us a detailed list of the reports for their components. Gilbert had identified 223 reports, of which 219 had been received and 168 had been reviewed and accepted. We stated that it appeared that we would issue our list of components by the end of fiovember 1979 and if we identified some components where the qualif1 cation reports were not complete, both Westinghouse and Gilbert could given the par-ticular reports a higher priority in their respective review process.
D wl. 0 Dean L. Tibbitts Light Water Reactors Branch No. 2 Division of Project Management
Enclosures:
1.
Attendance List 2.
Equipment Dynamic Qualification Review Procedures ces w/ enclosures:
See next pages 1574 216
DEC 0 31979 Mr. E. H. Crews, Jr., Vice President and Group Executive - Encinearino ir.a Construction htn r..olina El ec* 1r
- s. ' mNny
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P. u. co, 1,4 Co l umb -
'sa.tri.a r D<n<n[dcn}'#D'TIh o o N o
J u
, 2 It u cc:
Mr. H. T. Babb General Manager
' ens and Systen Plarring South Carolina Electric ?. a t Company P. O. Box 764 Columbia, Scuth Cicotirl 292 iP, G. H. Fischer, su.
V.ce President 5 2rc.
T<icative South Carolina Elec' ic ', 'ia s Ccopany P. O. Box 764 Col umbia, South Ca rel ina 29218 Mr. William C. :'escher President & Chief Executi.e Cfficer South Carolina Public Service Authority 223 North Live Oak Drive Marcks Corner, South Carolina 29461 Mr. William A. hiilianc, 'r.
Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South racolina 29461 Wallace S. Murphy, Esq.
General Counsel South Carolina Public Service Authority 223 North Live Cak Dri/e Moncks Corner, South Carolina 29461 Troy B. Conner, Jr., Esq.
Conner, Moore 3 Corber 1747 Pennsylvania Avenue, fl. W.
Washington, D. C.
20006 Mr. Mark B. Whitaker, Jr.
Fanager, Nuclear Licens f ng South Carolina Electric /. Gas Company 1574 2i7 P. O. Box 764 Columbia, South Carolina 29218 Fr. O. W. Dixon Group Manager, Production Engineering South Carolina Electric 7. Gas Caapany P. O. Box 764 Columbia, South Carolina 29218
Mr. E. H. Crews, Jr.
tt:.c.1979 cc:
Mr. Brett Allen Bursey Route 1 Box 93C Little Mountain, South Carclina 29076 Resident Inspector / Su' :er o..er Station c
c/c U. S. Nuclear Regulatory Comission P. O. Box 1047 Irmo, South Carolina
?o063 lD "l0'9' o o M o M J). X}f h D
.A 1574 218 O
DEC 0 01979 ENCLOSURE 1 ATTENDANCE LIST MEETING WITH SCE&G OCTOBER 25, 1979 NRC - STAFF S. Hou H. Daniels
- 0. Chopra R. Stephens D. Tibbitts E. Brown D. Reiff NRL R. Bart T. Kim SCE&G M. Whitaker R. Clary GILBERT / COMMONWEALTH D. Kelly C. Suh WESTINGHOUSE J. McInerney R. Kelly 1574 219
E&D PMENT JkkkiC GUALIFlCATION S'""
REVIEW PROCEDURES I. GENERAL IN FORMATION REVIEW C F5AR OR SEPAR ATE Doc 0MENTS)
QUA Lt FICATION
SUMMARY
(CRITERI A fr GUALIFICATION PROGR A M )
- LIST OF ALL ERUl?futENT INCLODE: 80? 4 NSSS ELEC. 4 MECH.
FOR EACH EGUIPMENT, S?EclFY N AM E, LOCATION ( B L p 6., E L E V..)
SAFETY FUNcTroR GOALIFicATidN NETHop At/AILA St LITY FOR INS ?ECTIOK 2
R R S ( 8 LD6. E L E V. )
C EdK. 4 HYPRODYNAMIC LdAD5j COMPLET10N 0 QUALIFICATION dR R E-E'!ALU ATidN se l
E SGLRT AUDIT c
e SELECT SAMPLE ITEMS FOR SGRT DATA SHEET D E TAI LS OF AN A LYSI S D ETAI LS OF TESTING RE PORT
- S &R-~ SITE \\/ISIT INSPECT SPECIFI ED ITE MS 03 SERVE OVERALL PER ':0RM ANCE
- DISCUSS OPEN ITEMS SPECl FY FOLL0tAl-U 3 ACTIONS ( IF Ah Y)
@3[.1 S E R 3'T STA17
[ TV.
ACRS N Y POST-ACRS REVIEW
(. IF ANY)
VT.
?iN A L AME N DM E NT TO FS E R.
.