ML20024G963
| ML20024G963 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/09/1975 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Stuart I GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20024G638 | List: |
| References | |
| NUDOCS 9105030424 | |
| Download: ML20024G963 (2) | |
Text
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- R 0 375 Mr. Ivan Stuart, Manager Safety & Licensing Nuclear Energy Division General Electric Company 17$ Curtoer Avenue San Jose, California 95114
Dear Mr. Stuart:
Our review of the Gcueral Electric dompany topical repor*., NEDO-20626,
" Studies of BWR Designs for 111tigation of Anticipated Transients Without Scran," has revealed that we vil.1 require the additional Your iniwrmation listed in the enclosure to complete our evaluation.
response to this request is required within 30 days of your receipt of this letter.
Picose inform us within seven (7) days af ter receipt of this letter of your intention to provide the requested additional information within 30 dayt.. or previce the date you v 11 provide the information.
Sincerely,
-med by wicter EuGCf -
l Walter R. Butler, Chief Light Vater Reactors Branch 1-2 Division of Reactor Licensing
Enclosure:
As stated cc: lir. L. Gifford, Manager Regulatory Operations Unit General Elcetric Conpany 4720 Montgonery Lane Bethesda, Mr.ryland 20014 9105030424 780821 PDR ADOCK 05000263 P
ENCLOSURE ADDITIO"AL INFORMATION REQUIRED FOR NEDO-2062_6 l
Provide a detailed analysis ot' the radiological consequences due to an ATWS to demonstrate that Criterion 4.1 (p. 6) of 310.1 Provide and justify the assumptions made NEDO-20626 is met.
for the is11oving in the analysis.
lodine concentrations in the reactor coolant a.
b.
Iodine decontamination factors of iodine spikes during and following c.
The effect the transient i
The offeet of ivdine spiken prior to the transient d.
Provide the following information for each transient 310.3 considered in NEDO-20606:
Idre pres. core vs. time for each transient
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f.t e st Steam line temperature vs. time for the lonf term b.
Total reactor coolant mass c.
d.
Total suppression pool mat.:
Reactor coolant mass released to the suppression pool e.
Provide references for the information "by others" mentioned 310J in the third paragraph of page 8.
Complete the sentence iragment at the end of that paragraph.
Provide an analysis of a station blackout transient including A station blackout is defined 310.5 radiological consequences.
as the simultanefous loss of power from the unit generator and from the offsite transmission systcm. leaving the e. sit.c as the only source of cectrency diesel f.enerator sett.
electrical power.
l
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