ML20099B260
| ML20099B260 | |
| Person / Time | |
|---|---|
| Site: | Crane, Arkansas Nuclear  |
| Issue date: | 04/13/1976 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20099A192 | List: |
| References | |
| FOIA-96-207 ORB-2-226, NUDOCS 8004300859 | |
| Download: ML20099B260 (2) | |
Text
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8004300 N 7 DISTRIBtTTION Rb Reading
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Subject File APR 1y Darrell G. Eisenhut, Assistant Director for Operations! Technology, DOR f
TECDi! CAL ASSISTANCE REQUEST NO. ORD-2-226 Plent Nace: Arkanses I;uclear Ono - Unit 1 (ANO-1)
Docket No:: S0-313 Sranch Code: ORL2 Project !Janagor:
"J. E. Converse Operational Technology Branches: Environmental Evaluation Branch (EEBOT)
Ret stor Safety Branch (RSBOT)
Plant Systems Branch (PSDCT)
Requested Coupletion Date: May 14, 1976 Description of Request: By letter dated May 8, 1973, Gabcock 4 Wilcox Company (54W) identified a deficiency in the design perforu.ance of the Reactor duilding Spray System (RDSS) of the Three Mile Island-1 and Arkansas Nuclear One-1 (ASO-1) nuclear facilities.
This letter (and the related report) is an-attachment to enclosure 2.
The report attached to that letter stated that a new analysis of the RSSS had been perforced which indicated the sodits:
hydroxide tank (S;1T), sodium thiosulfate tanke (51T) and borated water storage tank (MT) do not all draw down together under esiculatcJ accident conditions. This resul'tedin the emptying of the SHT and the STT up to 22 minutes before the DWST was depleted. Subsequently, Arkansas Power and.
Light Coopany-(APGL) subcitted thusuni Event Report (UER) 50-313/75-2,(enc 1. 1), dated June 25, 1975, based on the D4W report and indi-cated that a reanalysis would be performed based j
on the ANO-1 as-built piping configuration. By j
letter dated September 3,1975 (enc 1. 3), AP.5L subnitted UER S0-313/75-2A, the results of the reanalysis of the uneven tank draw-down problem.
P f
We request your revieu of the problem concomin; uneven dras-devn of tho ESS tan'as for the N;C-1 facility. Pl.ase supply a writcen evaluation j
g--,
-.. ~,
7 APR)i.:,q t
Darro11 C. Eisenhut,
I suitable for input into a safety evaluation l
addressing, at a ninimum. the following specific j
1 areas:
1.
The effcet on the RUSS and the ECCS of the uneven tank drau-da.cn.
(P5407,r.SRT).
2.
The effect of smovon tank draw-down on the offsite iodine doses following a LOCA.
(EE307) 3.
1he effect of the high pit atmosphere resulting from smovon tank draw-down on Reactor Building i
}
paints and cosmononts, l
(EESOT)
A TAR was issued on this matter to the Division i-of Technical Review (Containment Systems Branch and Accident Analysis Branch) on September 22, 1975.
CSB responded with a request of additional infor-mation (enc 1. 4), but AMs did not perform a review I
because of other workloads. Because the problem does appear to have safety signi'icance, I as i
reissuing the TAR to avoid further delays in obtaining needed technical assistance.
)
Nhe$ St Mskhfi.
eMW Operating Reactors Branch #2 "
Livision of Operating Reactors dnclosures:
1.
Unusual Event Report 50-313/75-2 (6/25/75) 2.
Transfer of Lead Responsioility (7/u/75) 3.
latusual Evont heport Su-313/75-2A ('J/3/75) 4.
CD acquest for Add'1 Information (11/3/75) cc v/unclosures.
cc w/o enclosures:
- 8. tirimes K. Goller W. Converse V. Stello R. Digrs i:. daer A. Schwencer T. Carter
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