ML20039H113
| ML20039H113 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 09/23/1977 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201190567 | |
| Download: ML20039H113 (4) | |
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UNITED STATES 4
NUCLtiAR REGULATORY COMMISSION WASHINGTON, D. C. 20566 SEP 2 31977 MEMORANDUM FOR:
D. Vassallo, Assistant Director for Light Water Reactors, DPM
~
FROM:
R. Tedesco, Assistant Director for Plant Systems, DSS
SUBJECT:
REVISION TO REPORT TO ACRS IN THE MATTER OF BSAR-205 Plant Name: BSAR-205, Babcock & Wilcox Standard Steam System Docket Number: STN 50-561 Licensing Stage: PDA Responsible Branch: LWR-3 Project Manager:
T. Cox Requested Completion Date: September 2,1977 Review Status: Complete
References:
1.
" Draft Safety Evaluation Report for BSAR-205,"
memo from R. L. Tedesco to D. B. Vassallo, May 4, 1977.
2.
" Report to the Advisory Comittee on Reactor Safeguards," in the matter of BSAR-205, July,1977.
Our initial report on the review of BSAR-205 was provided in reference 1, and was incorporated in Reference 2.
The only open issue is discussed in Section 6.2.2 of Reference 2 and pertains to the environmental qualification of safety related equipment located inside containment. B&W addressed this issue in Amendments 16 and 17 to BSAR-205. We have evaluated the B&W response and conclude that our concerns are resolved. Enclosed is a suggested revision to the July, 1977 report to the ACRS, which will be used in developing the Safety Evaluation Report to be issued in conjunction with a decision on issuance of a Preliminary Design Approval.
This completes our scheduled review effort on the BSAR-205 project.
e<
- > cx:
Robert L. Tedesco, Assistant Director for Plant Systems Division of Systems Safety
Enclosure:
As Stated
'cc: See Page 2 i
Contact:
T. Greene, Ext. 27711 Q1gg67810403 NADDEN80-515 PDR 4
i
r 0 IS77 D. Yassallo cc:
S. Hanauer R. Mattson R. Boyd W. Mcdonald
- 0. Parr T. Cox J. Glynn G. Lainas J. Shapaker P. Baranowsky T. Greene
Enclosure Revision to Report to the Advisory Conmittee on Reactor Safeguards-Containment Systems Branch Change Section 6.2.2, Environmental Qualification Program, to read:
In Amendment 16 to BSAR-205, B&W presented temperature versus time curves for use in the qualification of safety related equipment. Peak temperatures of 410 degrees Fahrenheit and 285 degrees Fahrenheit are shown for the main steam line break accident and the loss-of-coolant accident in Figures 3.11-2 and 3.11-3 of BSAR 205, respectively; the environmental qualification temperature for safety related equipment was previously specified as 300 degrees Fahrenheit.
Babcock & Wilcox has committed to submit a topical report that will document the B&W qualification testing program for safety related equipment. The B&W topical report will be reviewed in conjunction with the staff's generic approach to evaluating the environmental qualification testing programs of the various NSSS suppliers, to develop a consistent set of requirements for the qualification of equipment that may be needed following an accident.
B&W has committed to adopt the generic resolution of issues regarding equipment qualification. We have concluded that B&W's connitments regarding equipment j
qualification are compatible with the staff's generic program for resolving this matter, and are, therefore, acceptable.
' We have concluded that the temperature profiles for the main steam line break and loss of coolant accidents are reasonably conservative. However, we will require applicants referencing BSAR-205 to show that the calculated containment atmosphere temperature profiles, when compared to those shown in Figures 3.11-2 and 3.11-3 of BSAR-205 for the respective accidents, are conservative.
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