ML20040A445
| ML20040A445 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 11/18/1975 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201210105 | |
| Download: ML20040A445 (3) | |
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b UNITED STATES 6.
3 o;O NUCtEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 NOV 181975 Project No. STN P-566 A. Schwencer, Chief, Light Water Reactor Project Branch 2-3, RL B-SAR-205 ACCEPTANCE REVIEW Plant Name: Babcock-205 Standard Nuclear Sceam Supply System Licensing Stage: CP
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Project Number: STN P-566 t
Milestone Number: 01-01 Responsible Branch: LWR 2-3 Project Manager:
T. Cox Description of Response: Acceptance Review Requested Completion Date: November 18, 1975 Review Status: CcLplete We have completed our acceptance review of the PSAR for the B-SAR-205 NSSS and find its scope, in the areas we review, to be consistent with WASH-1341, Amendment 1.
Therefore, our review was limited to Section 11.1, " Source Terms" and the interfaces between the NSSS and the radio-active waste management, steam generator blowdown, and associated bal-ance of plant (BOP) systems.
g The PSAR identifies interface locations between NSSS and BOP systems on P&ID's and includes a listing of interface locations, temperatures
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and pressures. However, we will also need the flow rates and concen-trations of radioactive materials in the major streams input to the L
radwaste treatment system from the NSSS to complete our detailed review.
l We find the PSAR sufficiently complete to begin our review and, therefore, consider it acceptable for docketing. A list of additional information that is needed is enclosed.
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John T. Collins, Chief' j
Effluent Treatment Systems Branch Division of Technical Review f
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Enclosure:
I As stated cc:
R. Boyd W. Mcdonald S. Hanauer R. Heineman R. Tedesco
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8201210105 810403 PDR FOIA MADDEN 80-515 PDR
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4 (N
A. Schwencer !!OV 131975 cc:
(cont)
V. Moore D. Eisenhut H. Denton E. Conti S. Varga J. Glynn M. Bell W. Burke T. Cox J. Minns
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010-1 i
010.0 EFFLUENT T"EATMENT SYSTEMS BRANCil n
i 010.1 Provide a table listing all parameters used in the calculation (11.1) of reactor coolant fission and corrosion product activities.
Justify all assumptions and give a basis for the volume used in accordance with Regulatory Guide 1.70.27.
010.2 Provide the source term for carbon-14 in the reactor coolant (11.1) and the basis for the value used.
010.3 Provide the flow rates, batch volumes, and. concentrations of (NONE) radioactive materials during normal operation and anticipated operational occurrences, at each interface between the NSSS and the BOP radioactive waste management systems and for each
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leakage point f rom the NSSS to the building atmosphere and sumps.
010.4 For each interface between the chemical, volume control and (NONE) liquid poison systems and the BOP solid waste system, provide the flow rate, types of wastes, the maximum and expected batch volumes to be handled and the expected isotopic distribution and curie content.
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