ML19256D697
| ML19256D697 | |
| Person / Time | |
|---|---|
| Site: | Crane, Arkansas Nuclear  |
| Issue date: | 07/23/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910220614 | |
| Download: ML19256D697 (3) | |
Text
f DISTRIBUTION:
Docket File July 23, 1976 ORS #4 Rdg Book File T
tk Docket ::o.:
50-289
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pact h e
D. G. Eisenhut, Assistant Director for Operational Tecnnolo;y, DOR TEC:C;ICAL ASSISTANCE REQUEST NO. 022-4-73 Your assistance is requested for the following:
PLANT NAME:
Three Mile Island Unit No. 1 (21-1)
DOCKET lio.:
50-289 RESPONSIBLE BRANCH:
ORBJ4 CONTACT:
G. B. Zwetzig (x27435)
OPERATIONAL TECEN0 LOGY REVIEW ERANCliES:
Environ = ental Evaluation Branch Reactor Safety Branch Plant Syste=s Branch TARGET DATE FOR COMPLETION:
September 1, 1976 DESCRIPTION OF REQUEST:
By letter dated May 8, 1973, Babcock
& Wilcox Company (E6*r!) identified a deficiency in the desi;;n performance of the Reactor Building Spray System (R3SS) of the TMI-l and Arkansas Nuclear One-1 (X;0-1) nuclear facilities.
This letter (and the related report) is an onclosure to attachrent 2.
The repcrt attached to that letter stated that a new analysis of the RBSS had been per-for:ed which indicated the sodir hydroxide tank (SHT), sedur thicsulfate tank (SIT) and borated water stora;c tank (E'..'ST) co no all draw deva torether under calculated accident conditicra This resulted in the enntyinc of the 5"T and the STT up to 22 minutes befor the 3WST was depleted.
1453 090 7910220 hN
a D. Lisenhut F
6 TAa 273 t h
o D
B 3y letter dated Septe ber 6,1975 (attachcent 1), :r.;C requested lietropolitan Edison Company (MetZe}
to analyze this problem with respec:
to the specific piping arrangenent TMI-1 and advise the staff of the at results of the analysis and to ad*ress the catter of potential punp dana;e due to cavitation. By letters dated October 13 and November 12, 1973, ye:Ed responded to these requests (attach-ments 3 and 4).
'Je request your revics of the probler concerning uneven draw-down of the R2SS tanks for the I'!I-1 facility.
Please supply a written evaluation suitable for input into a safety evaluation addressing, at a minimum, the following specific areas:
1.
The effect on the RBSS and the ECCS of the uneven tank (raw-down includ-ing the =atter of potential pump cavitation (PS3, RSS).
2.
The effect of uneven tank draw-down on the offsite iodine doses folicwir.
a LOCA (EE3).
3.
The effect of the hir.h pl. 2ttosphcre resulting, fron uneven tanu draw-de.c on Reactor Euilding paints and cc=penents (EZ2).
A TA2 was issued on this natter to the Division of Technical Review (Contain-cent Systers Branch a.d Accident Anal:r.n 2 Branch) on :ovceber 6, 1973.
CS? respeni _
with a request for additicnal infornatic.
(attachment 5), but AA3 diu not erf=
a review because of other workloads.
Because the problem appears to have safet,.
significance, I an reissuing the T.C tc.
avoid further delays in obtaining needet.
technical assistance.
1453 091
D. Eisenhut TA2 M3 Ly letter dated Tebr_a:/ 21. 1071,
'ictEd respended to tais requaat f;.
additional infor:2.tien (attach.ca: :.
E_ d Uotd H Robert U Reid, Chi;f Opert. ting Reacters uranch 4 Division of Operating Reactors Attachnents:
1.
NRC ler to Meted dtd 9/3/73 2.
Transfer of Lead Respen.21bility dtd 7/9/73 3.
Meted. 1tr GQL 1606 dtd 10/13/75 g
g D
4.
Meted ler GQL 1693 dtd 11/12/75 g
5.
NRC ltr to Meted dtd 1/20/76 6.
Meted ltr CQL 0249 dtd 2/21/76 ec w/o attachcents:
V. Stc11o K. Goller T. Carter R. Reid G. Zwetzig R. Ingra=
B. Grimes R. Baer
'n'. Butler 1453 092 l
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