ML20040A447
| ML20040A447 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 04/27/1976 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201210110 | |
| Download: ML20040A447 (3) | |
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UNITED STATES 4
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Docket No:
50-561 John Stolz, Chief, LWR-1 ROUND ONE QUESTIONS B-SAR-205 i
I PLANT NAME: B-SAR-205 LICENSING STAGE:
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DOCKET NUMBER:
50-561 MILESTONE NUMBER: 03-33 RESPONSIBLE BRANCH: LWR-1 PROJECT MANAGER:
T. Cox DATE REQUESTED RECEIVED BY RAB: Per Blue Book REQUESTED COMPLETION DATE: 4-26-76 DESCRIPTION OF RESPONSE:
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REVIEW STATUS: dontinuing The Radiological Assessment Branch has reviewed the Babcock and Wilcox application for B-SAR-205 through Amendment 1.
Please use our draft round one questions sent to you on 4-13-76 for submittal to the applicant. We have attached a copy for your convenience.
This review is being performed by T. D. Murphy, Radiation Protection Section.
William E. Kreger, C ef Radiological Assessment Branch Division of Site Safety and Environmental Analysis
Enclosure:
As stated l
cc:
S. Hanauer T. Murphy H. Dentan W. Mcdonald (w/o encl.)
D. Crutchfield J. Panzarella (w/o encl.)
R. Vollmer P. Shuttleworth (w/o encl.)
J. Miller S. Varga R. Boyd i
R. DeYoung
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T. Cox W. Kreger 8201210110 810403 PDR FOIA MADDEN 80-515 PDR
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APR 2 7 B76 Docket No:
50-561 4
John Stolz, Chief, LUR-1 ROUND ONE QUESTIONS B-SAR-205 PLANT NAME:
B-SAR-205 LICENSING STAGE:
SP DOCKET NUMBER: 50-561 MILESTONE NUtiBER:
03-33 RESPONSIBLE BRANCH:
LWR-1 PROJECT MANAGER:
T. Cox DATE REQUESTED RECEIVED BY RAB:
Per Blue Book REQUESTED COMPLETION DATE: 4-26-76 l
t DESCRIPTION OF RESPONSE:
Q-l's REVIEW STATUS: Continuing t
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The Radiological Assessment Branch has reviewed the Babcock and Wilcox application for B-SAR-205 through Amendment 1.
Please use our draft round one questions sent to you on 4-13-76 for submittal to the applicant. We have attached a copy for your convenience.
I This review is being performed by T. D. Murphy, Radiation Protection l
Section.
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William E. Kreger, C ef Radiological Assessment Branch
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Division of Site Safety and i
I Environmental Analysis L
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Enclosure:
As stated I
cc:
S. llanauer T. Murphy l
- 11. Denton W. Mcdonald (w/o encl.)
D. Crutchfield J. Panzarella (w/o encl.)
R. Vollmer P. Shuttleworth (w/o encl.)
J. Miller
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S. Varga l l R. Boyd R. DeYo T. Cox i
m W. Kreger j
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331.0 RADIOLOGICALJSSESSMEllT BRAflCH 4
3 31.8 liith regard to the design review program described in Section (12.1.2) 12.1.2, describe the specific review functions and responsibilities of the person (s) who assures that features for assuring that occupational radiation exposures can be maintained as low as i.;
reasonably achievable are included in the design of the plaat.
331.9 Describe what specifications are used in the design and selection (12.3.1.1) of materials for the reactor coolant that are specifically directed toward the reduction of the production, transport and sa and Co60 j
redeposition of Co 331.10 The answer to acceptance review question 331.3 is unacceptable.
(9.3.4)
Describe the design considerations used in selecting a letdown range of 50-200 gpm. Discuss the effect on reactor coolant corrosion and fission product activity of increasing the letdown rate to 2000 c
gpm. Discuss your design considerations for the use of a high L
temperature, high flow filtration system to minimize the buildup of corrosion products in the reactor coolant and auxiliary sys tems.
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