ML19329A137
| ML19329A137 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 04/06/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| ORB-1-233, NUDOCS 7912300156 | |
| Download: ML19329A137 (2) | |
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April 6, 1976 4
D. G. Eisenhut, Assistant Director for Operational Technology, DOR TECIINICAL ASSISTANCE REQUEST NO. ORB-1-233 Your assistance'is requested for the following:
PLANT NAME: Oc Units 1,,2 and 3 DOCKET NOS.:
, 50-270 and 50-287 RESPONSIBLE BRANCH: ORB-1 CONTACT: Gary Zech (ext. 27433)
TEQiNICAL REVIEW BRANCIES: Engineering Branch Environmontal Evaluation Branch DESCRIPTION OF REQUEST: By the enclosed letters dated June 23, 1975 and December 16, 1975, Duke Power Company-(DPC) has identified the design objectives and criteria to be incorporated into the Oconee Station permanent waste r.anagement facility.
An interim facility was constructed'at Oconee after Units 1 and 2 were licensed and prior to fuel loading of Unit 3.
The interim facility was considered necessary after it was determined that the original facility, as described in the FSAP,, would not be adequate to process the expected volume of liquid wastes.
It should be noted that the licensee has inferred that the design of the permanent
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facility involves no unreviewed safety questions as defined in 10 CFR 50.59.
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addition, there are no changes to the operating licenses or techn3 cal specifications involved in this facility modification.
A review is presently in progress by ETSB: M.)
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regarding the basit: design capacities and
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process flows of the facility.
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determined that additional review is also necessaryn in the areas of occupational exposures and the 4
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structural design of the -facility building e' 'T a ~+~ m a
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b D.'risenhut APR 6 U/6 You are requested to review the enclosed letters and Safety Analysis Report (submitted with the June 23, 1975 letter) and determine if the proposed facility design has incorporated the appropriate' standards and codes as were applied in the original system design.
In addition, you are requested to evaluate the occupational exposure levels to be expected as a result of the proposed changes and detemine if they cre acceptable.
In conjunction with your review it is requested that a detemination be made whether we agree with the licensee that no unroviewed safety questions are irvolved as are defined in 10 CFR 50.59.
. TARGET DATE FOR COMPLETION: May 14, 1976 f t!gint! signed by Robert A. Purple, Chief Operating Reactors Branch #1 Division of Operating Reactors
Enclosures:
DISTRIBlTTION:
1.
Letter dtd. 6/23/75 Docket (3) from Duke Power ORB-1 Reading 2.
Letter dtd. 12/16/75 RAPurple from Duke Power cc:
L. Shao B. Grimes K. Goller T. Carter G. Zech S. Sheppard V. Stello
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