ML19319D552
| ML19319D552 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/06/1973 |
| From: | Tedesco R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003170674 | |
| Download: ML19319D552 (2) | |
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Richard DeYoung, Assistant Director-for Pressurized Water Reactors, L LREQMST FOR ADDITIONAL INFOM'ATION FOR CESTAL RIVD. NUCLEAR CHERATING
_ PLANT, UNIT 3_'
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Os Responhibla Branch: PW O 4 O M D
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i Project Manager:
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Requested Completion Datet June 1, 1973 Description of Response: Additional Information Review Status: Awaiting Additional Information l
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2 Based on our review of tha radioactive vaste treatnant and radiation
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. protection systeus contained in the application and t.he reconsea to our request tfor. additional informati n, we have 1&stified three of the applicant'e positiens vidch are unm c.eptsble. We have also
. LJantified coa item fee which sufficient just!fication for us to evalua'te tha systems has not been provided. Enclooed are our c
coments on these four items.
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^ We will-need-the' applicg tt.% anavers to these item by July 13, 1973
- in order.tn complete our evaluation by septed.er 7,1973.
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REQUEST FOR ADDITIONAL INF0Fl!ATION FOR CRYSTAL RIVER NUCLEAR GENERATING PLANT, UNIT 3 l.
Section 11.1 states that the design objective of the radioactive waste treatment systems is to assure that the quantities of radio-active materials released from the plant uill not exceed a small fraction of 10 CFR Part 20 limits.
Sections 11.2.1.2 and 11.2.2.2 state that the release of liquid and gaseous radicactive wastes to unrestricted areas will be based on 10 CFR Part 20 limits.
It is our position that the design and operation of the radioactive vaste
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treatment systems shall be to reduce the quantities of liquid and j
gaseous radioactive materials expected to be released from the plant to as low as practicable in accordance with 10 CFR Part 50.
Accordingly, the design objective and release limits for liquid J
and gaseous radioaccive castes mus: ha based on keeping the latels of radioactive materials in effluents to unrestricted areas as low as practicable.
4 2.
Section 11.5 does not provide radiation zones that ulll be used to control in-plant personnel exposures, i.e.,
uncontrolled access, unlimited controlled access, limited controlled access.
Section 11.5-also does not discuss the design features that will be used i-to reduce in-plant personnel exposures during operation and maintenance of equipment; e.g.,
cubicles, location of equipment, valves and pipes, renote operation, angled shielding, labyrinths, etc.
We need these two items of information to complete our review of the health physics program.
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3.
Amendment 26 to the FSAR provided a revised Figure 11-13 that shows
.the-principal flow path for the chemical regenerant liquids as an untreated release to the discharge canal. The collection of these wastes and the criteria that will be used to process these wastas as radioactive must be described to complete our review of the radioactive. waste treatment systems.
It is our position that
. henever primary coolant to secondary coolant leakage is detected w
in the plant, the chemical regenerant liquids will be processed through the miscellaneous ~ waste evaporator and evaporator condensate demineralizer before release to unrestricted areas.
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