ML19329C781
| ML19329C781 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/29/1975 |
| From: | Ferrell C Office of Nuclear Reactor Regulation |
| To: | Szukiewich A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002190894 | |
| Download: ML19329C781 (2) | |
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DISTRIBUTION:
h ral Files 50-346 NRR/ Reading OCT c e tg AAB/ Reading A. Szukiewicz, Electrical, Instrunentation & Control Systems Branch THRU: 3rian K. Grimes, Chief, Accident Analysis Branch, TR DAVIS DESSZ UNIT NO.1 MDDIFICATION TO THE SFENT FUEL BUILDING IS01ATION AND EMERCEiCY The Accident Analysis Branch requests the assistance of your bran h in reviewing the nodified desi:;n in the Davis 3 esse Unit No.1 Spent Fuel Building Energency Ventilation Filter System which was described to 52C staff by representatives of 3echtal in their meetin:; with us on Octo-ber 15, 1975, and in our phone conversation with Ted quay, of 3cchtel, on Occober 23, 1975. It is our undersmndin:; that the proposed nodification vill be submitted by the applicant in a later anendrent to the F3n. The basic schematic diagram of the proposed revisien is indicated on the at-tached sketch. The ductuork up to the safety,;rade charcoal filter train is not seisnically designed.
(',*e have accepted this on other GI.'s but requiro saismic design on current C? applicaticna.) Two dc=gers in parallel will be located upstream frca the outict to the normal dual train ventilation system. On each of the nomal ventilation systen train danpers vill be located on each side of the blowers. Dampers 1 and 2 on the ener;;ency filter train vill fail open on loss of power.
Cic recog-nize that a spurious signal causing closure could not be coped with 'cy this design.) The radiation detector all the way lovn to the actuators should be designed to 12HE-279 (1971) with the exceptien of the danpers which may be shown by analysis to coet this requirenent. Danpers A and 3 should meet 12EE-279 with exception of seisnic desi; n.
Thas revised dcaign is acceptable for Davis 3 ease Unit "o.1 oni-; and not for Unita 2 and 3.
T' tis was emphaaized by NRC staff to 3echtel repre-sentatives durin$ both the =cetin; and the phone conversation. W conclude that the proposed revision is a significant improvenent over the systes currently in the TSM and that while it.does not neat all current scienic and safety criteria, it is acceptable for this plant givna the current status of plant construction.
D S O D
Charlas Ferrell, Site Analyst i
d b $I Accident Analysis Branch r '. vision of Technical Review O
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- q1 g, q Of fice of Nuclear Reactor Regulation
Enclosure:
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