ML20040A059
| ML20040A059 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 09/13/1976 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Happell J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200279 | |
| Download: ML20040A059 (4) | |
Text
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f op 3 REQUEST FOR ADDITIONAL INFORMATION C 35 o<asr B-SAR-205 m
Q-a.,
022.6 The response to Question 222.la is incomplete. Provide the mass and energy release data requested for the containment subcompartment analysis.
022.7 The response to Question 042.4 is incomplete. Justify that the double-ended rupture of a main steam line will result in the design basis main steam line break accident, or provide the mass and energy release data for a spectrum of main steam line breaks.
022.8 Provide the mass and energy release data for a postulated main feedwater line break.
022.9 The maximum environmental temperature that safety-related mechanical and electrical equipment will be designed and qualified to is given in Table 3.11-2 as 300 F.
Main steam line break accident analyses have indicated that the containment atmosphere temperature may 0
exceed 420 F.
Therefore, it is our position that Table 3.11-2 be revised to reflect a conservative upper bound on the maximum temperature expected inside the containment following a postulated main steam line break accident, or that a commitment be made to qualify the safety related equipment for the containment environmental conditions calculated by the B0P designer.
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8201200279 810403 PDR FOIA MADDEN 80-515 PDR
7 1of 3 022.10 The response to Question 022.3, which requested additional infomation about the containment isolation system within the B-SAR-205 scope of design, is unacceptable.
It is our position that the requested information should be included in B-SAR-205, and the interface requirements for the BOP designer should be identified.
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022.11 The Engineered Safety Features Actuation System (ESFAS) provides the signals for ESF actuation, including containment isolation.
For the containment isolation and cooling (CIC) signal, the ESFAS only monitors containment pressure.
It is our position that there should be diversity in the parameters sensed for the initiation of containment isolation. Therefore, propose other ESFAS signals that satisfy this position; e.g., safety injection signal.
022.12 Specify the maximum leakage rate and type of fluid for all containment isolation devices provided with the scope of B-SAR-205.
This information is needed by a B0P designer to determine the potential bypass leakage for a dual containment ~ plant.
'022.13 With regard to the combustible gas production and accumulation analysis, provide the following infomation:
1.
Specify the amount of hydrogen assumed to be in the primary coolant;
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. 2.
Provide a table of the aluminum and zine components in the B-SAR-205 scope of supply, including a description of the components, and their weight, thickness, and exposed surface area.
3.
Figure 6.2-2 shows the total hydrogen generated by the corrosion of aluminum. Provide an accompanying analysis, and justify the metal corrosion rates for the assumptions that were used.
4.
Specify the tenperature and pressure used to calculate standard cubic feet.
0^~ 14 Section 6.2.1 lists the criteria to assure that the structural integrity of the containment will be maintained.
Item 3 in this section implies that the only accident that must be considered is the LOCA.
It is our position that containment and interior structures be designed to withstand the effects of a postulated main steam line and feedwater line accident.
Include these accidents in your criteria.
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