ML20039F092

Requests Confirmation of B&W Contention That No Fuel Perforation Would Occur for Temp Excursion

ML20039F092
Person / Time
Site:	05000561
Issue date:	03/17/1977
From:	Mazetis G Office of Nuclear Reactor Regulation
To:	Check P Office of Nuclear Reactor Regulation
Shared Package
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References
FOIA-80-515, FOIA-80-555 NUDOCS 8201110845
Download: ML20039F092 (2)

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Docket No. 50-561 g g7 g MEMORANDUM FOR: Paul S. Check, Chief, Core Performance Branch, DSS THRU: Thomas M. Novak, Chief, Reactor Systems Branch, DSS FROM:

G. R. Mazetis, Section Leader, Reactor Systems Branch, DSS

SUBJECT:

FUEL DAMAGE ACCEPTANCE CRITERIA FOR B-SAR-205 MAIN STEAM LINE BREAK ANALYSIS The steam line break analysis for B-SAR-205 shows DNBR< l.3 (BAW-2) for a small percentage of rods (~1%).

Figure 15.1.14-3 shows DNBR and maximum clad surface temperature for the 42-inch main steamline break between the steam generator and MSIV. Babcock and Wilcox state in the SAR that even though the DNBR drops below 1.3 for the hot spot of the core during this transient, no fuel cladding failures are expected to occur because there is insignificant zirconium-water reaction in terms of the amount of wall thickness reduction that occurs as a reault of the reaction,1.e., 0.00035 inch out of a total wall thickness of 0.0235 inch, Although the staff could accept fuel damage during a main steam line rupture, providing the resultant doses do not exceed 10 CFR 100 limits, Babcock and Wilcox uses this ana'.ysis to bound several excessive heat removal events of moderate frequency for which fuel damage is not acceptable.

It is requested that CPB confirm B&W's contention that no fuel perforation would occur for this temperature excursion.

G. R. Mazet s, ection Leader Reactor Systems Branch Division of Systems Safety

Enclosures:

Fig. 15.1.14-3 cc:

D. Ross T. Novak S. Israel G. Mazetis T. Cox(#

S. Newberry D. Bunch

Contact:

S. Newberry, NRR x27911 8201110845 810403 PDR FOIA MADDEN 80-515 PDR

1300 1200 1100 Maximum 1000 Claa

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Surface

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Temperature.

F 800 700 N

600 1.8 i

ONR Ratio 1.7 1.6 1.5 1.4 1.3 0

1 2

3 4

5 6

7 8

9 10 Time After Ruoture, s Amendment 8 DOUBLE ENDED RUPTURE OF 42-INCH STEAM LINE DOWNSTREAM OF THE MAIN STEAM LINE ISOLATION VALVE (OFFSITE POWER AVAILABLE)

Figure 15.1.14 3 Sheet 5

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