ML20154C884

Discusses Supplemental Request for Addl Info Re WCAP-14565, Rev 0, VIPRE-01 Modeling & Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis

ML20154C884
Person / Time
Issue date:	09/14/1998
From:	Wen P NRC (Affiliation Not Assigned)
To:	Sepp H WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
TAC-M98666, NUDOCS 9810070053
Download: ML20154C884 (4)

Text

'

September 14, 1998 4

Mr. Henry A. Sepp, Manager -

I Regulatory and Licensing Engineering ,ysC,,! $ n Westinghouse Electric Corporation e

~,.-,

3 Mail Stop ECE 4-07A * '2 !.!! lr): f;g Post Office Box 355 Pittsburgh, Pennsylvania 15230-0355 FUBuc OCUNagrggg;;

SUBJECT:

SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING WCAP-14565, REV. O,"VIPRE-01 MODELING AND QUALIFICATION FOR PRESSURIZED WATER REACTOR NON-LOCA THERMAL-HYDRAULIC ANALYSIS"(TAC No. M98666) l

REFERENCE:

Letter from H. A. Sepp (Westinghouse) to T. E. Collins (USNRC)" Responses to Request for Additional Information on WCAP-14565, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal Hydraulic Safety Analysis," August 7,1998. i

Dear Mr. Sepp:

l In the referenced letter to NRC, Westinghouse informed the staff that the VIPRE code will be used for analysis of main steam line break (MSLB) accidents. However, the referenced letter did not discuss how DNBR will be calculated by VIPRE at low reactor system pressure. The staff has determined a need for additional information in this regard. The enclosure to this letter identifies the information required. Please address your response to the NRC Document Control Desk.

If you have any questions, please contact me at 301/415-2832 (email, pxw@nrc. gov) or l Walt Jensen at 301/415-2856 (email, wij@nrc. gov).

Sincerely, I Original Signed By Peter C. Wen, Project Manager Generic Issues and Environmental NR T Offic f uclear eactor Regulation C PDR

Enclosure:

Supplemental RAI on topical report cc: See next page WCAP -14565, Rev 0 lf DISTRIBUTION:

PUBLIC TEssig FAkstulewicz TCollins RCaruso PGEB R/F PWen WJensen OGC ACRS 3

JRoe f

U(0

.s DOCUMENT NAME: G:\pxw\w14565.rai /

OFFICE PM:PGFB SC:PpE[ k NAME DATE PWen:sw pcd FAkstMdz' 09//4./ 98 r

bs ~ 6 ~ r)~

, WC S *.

• h6 09/ lll/98 ,

OFFICIAL OFFICE COPY r ; -]

taJc_

n rer:)

g i UNITED STATES g j 2

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001

+4***** $ September 14, 1998 Mr. Henry A. Sepp, Manager Regulatory and Licensing Engineering Westinghouse Electric Corporation Mail Stop ECE 4-07A Post Office Box 355 Pittsburgh, Pennsylvania 15230-0355

SUBJECT:

SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING WCAP-14565, REV. O,"VIPRE-01 MODELING AND QUALIFICATION FOR PRESSURIZED WATER REACTOR NON-LOCA THERMAL-HYDRAULIC ANALYSIS"(TAC No. M98666)

REFERENCE:

Letter from H. A. Sepp (Westinghouse) to T. E. Collins (USNRC) " Responses to Request fcr Additional information on WCAP-14565, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal Hydraulic Safely Analysis," August 7,1998.

Dear Mr. Sepp:

In the referenced letter to NRC, Westinghouse informed the staff that the VIPRE code will be used for analysis of main steam line break (MSLB) accidents. However, the referenced letter did not discuss how DNBR will be calculated by VIPRE at low reactor system pressure. The staff has determined a need for additionalinformation in this regard. The enclosure to this letter identifies the information required. Please address your response to the NRC Document Control Desk.

If you have any questions, please contact me at 301/415-2832 (email, pxw@nrc. gov) or Walt Jensen at 301/415-2856 (email, wij@nrc. gov).

Sincerely, 7tx c u s ,

Peter C. Wen, Project Manager Generic issues and Environmental Projects Branch Office of Nuclear Reactor Regulation

Enclosure:

Supplemental RAI on topical report WCAP -14565, Rev 0 cc: See next page

. - . . - - - ~. . - - ~ . . . . _ . _ _ . _ - _ . .. . _ . - . . - - -

o .

e s l cc:

Mr. Nicholas Liparulo, Manager

' Equipment Design and Regulatory Engineering ,

Westinghouse Electric Corporation i Mail Stop ECE 4-15 P.O. Box 355 -

Pittsburgh, PA 15230-0355

' Mr. Jack Bastin, Director Regulatory Affairs -

- Westinghouse Electric Corporation

. - 11921 Rockville Pike ,

Suite 107 Rockville, MD 20852 s

Mr. Sumit Ray, Manager Fuel Licensing Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 i

l I

l l

2

,u s

Supplemental Request for Information Regarding WCAP-14565 Rev. 0 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis

1. We understand that VIPRE will be used for analysis of main steam line breaks. As a consequence of a main steam line break the reactor core may experience recriticality leading to a retum to power at low reactor system pressure. For pressures outside the  ;

range of the WRB-1, WRB-2 and WRB-2M correlations that are programmed into the VIPRE code discuss how DNBR will be calculated. Provide the DNBR safety limits for the methods that will be used. Provide experimentaljustification that these methods are conservative for the Westinghouse nuclear fuel that will be analyzed using VIPRE.

1 1

h F

J j

I 1

i Enclosure l