ML20039H091
| ML20039H091 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 11/24/1975 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201190532 | |
| Download: ML20039H091 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMisslON W ASHINGTON. D. C. 20555 NOV 2 4 1975 Project flo. STN-566 Yoss A. Moore, Assistant Director, Light Water Reactors Group 2 ACCEPTAf!CE REVIEW 0F B-SAR-205 Plant Name:
Babcock & Uilcox Standard fluclear Steam Supply System B-SAR 1
Project flo.:
STN-566 Licensing Stage: N/A NSS Supplier:
Babcock & Hilcox Architect Engineer:
f!/A Containment Type; ilot Specified Responsible Branch & Project Manager: LWR, 2-3; T. Cox Requested Completion Date:
!!ovember 18, 1975 Review Status: Acceptance Review Complete As requested by your memorandum dated October 28, 1975, the Containment Systems Branch has performed an acceptance review of Section 6.2 and portions of Section 15.1 to the proposed Babcock & Hilcox B-SAR-205.
Based on cur review, we conclude that additional information, as indicated in the enclosure, is needed in Section 6.2 and Section 15.1.
Because of the extent of the deficiencies, ;;e cannot begin a meaningful review of B-SAR-205.
The principal deficiency is the lack of mass and energy release data to the containment resulting from LCCA.
This information is used by the 80P applicant to size the containment building, design the various containment subcompartments, and to size the containment heat removal systems.
B&U states that this infor-mation will be provided in a separate topical report which has not yet been submitted. He understand that the methods used to generate these mass and energy data will differ considerably from those which we have previously found acceptable, and there-fore, a censiderable review effort will be required.
i B&H has provided mass and energy release data for,the main steam C201190532 010403 PDR FOIA MADDEN 80-515 PDR 4
- NOV 2 41975 line break in B-SAP,-205, however, no discuss, ton of the calcula-tional method used was presented, Since a major portion of the necessary mass and energy release data has not been provided and a schedule for submittal of this information has not been established, we recommend that C-SAR-205 not be accepted for docketing.
QNEdLbW Robert L. Tedesco, Assistant Director for Containment Safety Diirision of Technical Review Enclosure As stated cc:
S. Hanauer R. Heineman R. Boyd W ficDonald R. DeYoung R. Denise K. Goller D. Skovholt D. Muller TR A/D's J. Glynn CS B/C's J. Kudrick J. Shapaker A. Schwencer T. Cox N. Anderson W. Jensen S. Varga
- 0. Parr I. Villaiva e
REQUEST FOR ADDITI0rlAL INFOR'MTIO!!
BABC0CK & ilILC0X B-SAR-205 PROJECT NO. STH-566 042.1 Provide the mass and energy release rates as a function of (6.2.1) time for a spectrum of hot and cold leg break sizes using methods and assunptions that are suitably conservative for containment analysis.
a.
Describe in detail the methods used and the input assunptions.
b.
Describe or reference the heat transfer correlations used to predict heat transfer from the core during blowdown.
Define the criteria that were used to establish the conservatism of these calculations.
c.
Provide and justify the heat transfer coefficient used in the steam generators for forward and reverse heat flow.
Discuss how these values are conservative
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for containment analysis. '
042.2 For the most severe hot and cold leg break sizes, provide a (6.2.1 )
list of the initial energy inventories in the core, primary coolant, piping, core internals, safety infection tanks, steam generator fluid and associated metal. A discussion on the justification for values used should be provided.
The mass of fluid contained in the pri; mary system,
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containment and safety injection tanks should also be listed.
(Include each inventory source at the end of blowdown and the end of the reflood period.)
042.3 Provide mass and energy data to be used by the con-(6.2.1 )
tainment designer for subcompartment analysis.
Describe the method used to generate this data and the input assumptions.
Include nass and energy re-lease rates in tabular form from time zero to about 1.5 seconds at approximately 0.05 second intervals for a spectrum of break sizes at various locations.
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i 042.4 (15.1.1.4. 2. 3. 2) Describe in detail the method used to generate the mass and energy release data in Table 15.1.1.4.2 for the 28 inch main steam line break.
Discuss how
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I this analysis is conservative for containment evaluation. Discuss possible singie failure modes i
in the main and auxiliary feedwater systems by I
which additional fluid could be added to the steam generators following a steam line break.
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042.5 Provide and justify the containment temperature and (6.2.1 )
pressure used in detennining the design of safety
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related equipment within the containment. Applicants f
a 0
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