ML20040A443
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UNITED STATES
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3 p-NUCLEAR REGULATORY COMMISSION L b' O
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Docket No. S0-561 J. F. Stolz, Chief, Light Water Reactors Branch No. 1, DPM ROUND ONE QUESTIONS FOR B-SAR-205 f
PLANT NAME:
B-SAR-205 LICENSING STAGE: CP DOCKET NUMBER:
50-561 MILESTONE NUMBER:
03-01 i
RESPONSIBLE BRANCll:
LWR No. 1 l
PROJECT MANAGER:
T. Cox i
DESCRIPTION OF RESPONSE: Rour.d One Questions REQUESTED COMPLETION DATE: April 26, 1976 REVIEW STATUS:
Under Review l
We have reviewed Amendment I to B-SAR-205 and find that we need addi-tional information to complete our review. The applicant has not provided sufficient information or justification for the parameters used to calculate the gaseous and liquid radioactive waste source terms.
We will need the additional information by June 24, 1976 to meet our schedule.
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, John T. Collins, Chief Effluent Treatment Systems Branch Division of Site Safety and Environmental Analysis I
Enclosure:
Round One Questions cc:
S. llanauer
- 11. Denton D. Crutchfield J. Miller S. Varga R. Boyd R. DeYoung T. Cox R. Vollmer W. Kreger W. Mcdonald (w/o enc 1)
J. Panzarella (w/o enc 1) l M. Shuttleworth (w/o enc 1)
M. Bell J. Minns 8201210101 810403 PDR FOIA MADDENBO-SIS PDR
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010-1 i
'APR 2 0 576 010.0 EFFLUENT TREATMENT SYSTEMS BRANCH 010.S Your source terms for normal operation are based on para-(11.1.2) meters and calculational methods that are not consistent with Regulatory Guide 1.BB, " Calculation of Releases of Radioactive Materials in Liquid and Gaseous Effluents from Pressurized Water Reactors", dated September 9, 197S.
Provide operating data to justify the parameters used in your evaluation.
i 010.6
" Table 11.1-8 indicates that corrosion product activities (11.1.2.3) in the primary coolant are based on extrapolated data from similar operating reactors.
Provide these data for our -
review in accordance with the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, revision 1.
010.7 In your'expec'ted releases, you do not consider liquid (11.1. 5) effluents from the Boron Recovery System. Reactor operating experience does not justify this assumption.-
You should provide justification that:
1)
The plant water inventory can be maintained over the t
plant lifetime without discharge from these systems; 2) the tritium 1cycls in the plant can be controlled to maintain radiation exposure to operating personnel as low as practicable without discharge from these systems; and 3) there is sufficient capacity and flexibility or re-dundancy in the system that discharge from these systems will 'not be necessary as the result of anticipated operational occurrences and equipment downtime.
010.8 Provide the interface requirement reference 'for item 15(8)
(9.3.4.1) in figure 9.3-1, sheet 1.
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