ML19329B360
| ML19329B360 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/18/1975 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002040780 | |
| Download: ML19329B360 (3) | |
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Ava I s E75 R. C. DeYoung. Assistant Director for Light Water Reactors, Group 1, RL DMIS4 ESSE SER IMPUT CDRRECTIGi PLAIT tiAME: Davis 4 esse Unit 1
' LICidSIiid STAGE: CL GCCKET liLHtiEP.: 50 -34c HILESTGiE iM2ER: 2.4 -31 P.ESPGtSISLE 3Rh4Cli: LWR 1-4; L. Engle, LPM REQUESTED COMPLETIGi DATE: il/A REVIEW STATLS: AAB Input Complete Tae enclosed pages should be sutstitutad for tne first page of cne enclosure to my August 14, 1575 memo.
Harold R. Centon, Assistant Director for Site Safety Division of Tecnnical Review Office of iluclear Reactor Regulation inclosure:
/s scated cc w/o enclosure:
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n 15.4 Steam Line Break, Steam Generator Tube Rupture, & Control Rod Ejection Accidents We have analyzed the radiological consequences of the steam line break, steam generator tube rupture, loss of offsite pour, and control rod ejection accidents.
In performing the dose calculations, it as assumed that the primarf and secondary coolant equilibrium activity concentrations are at the maximum levels permitted by the standard Technical Specifications, i.e.,
1.0 uCi/gm I-131 equivalent and 100/E uCi/gm for isotopes with half lives greater than 15 minutes for the primarf coolant, and 0.1 uC1/gm I-131 equivalent for the secondary coolant.
F accidents postulated to occur in coincidence with an iodine spike, the primary coolant concentration as assumed to be at the level pennitted by the standard Technical Specifications for 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> time periods; i.e., 60 uCi/gm I-131 equivalent at 100% pomr.
The dose results are shom in Table V and the assumptions employed in the analysis of these accidents are listed in Table VI. We find that the calculated doses are all within the guidelines of 10 CFR Part 100 and are acceptable.
15.5 Waste Gas Decay Tank Accident The maximum activity permitted in a mste gas decay tank at any given. time will te limited by appropriate technical specifications so that any single failure such as lifting or failure to close of
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-2 15.5 Waste Gas Decay Tank Accident (Cont'd.)
a relief valve will not result in doses that exceed small fractions of 10 CFR Part 100 guideline doses. The maximum allowble activity for any pressurized tank not containing charcoal will therefore be 14,200 curies of Xe-133 equivalent.
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