ML20024C594
| ML20024C594 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1979 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Mattson R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20024C595 | List: |
| References | |
| TASK-07, TASK-7, TASK-GB GPU-2214, NUDOCS 8307120853 | |
| Download: ML20024C594 (2) | |
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g fp P.O. Box 1250 '.yr.c..m;rg, va. 2:5a5 Telechone:($34) 334 5:11 1
/M 7 May 12, 1979 1
Dr. R. J. Mattson, Director j
Division of Systa= Safety office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Co==ission Washi=ston, D.C.
20555 Refe:ence: "Ivaluation of Transie=t 3eha'vior and Sna11 Reactor Coolant i
Systen Breaks in the 177 Tual Assecbly Plant " May 7, 1979.
Dear Dr. Mattson:
The Stafi's review of the reference has'resulted in an NRC requast for additions.1 info:=ation on Section 6, "S all Break Analyses." Specifi-cally, the Staff requested the following analyses:
"S=a11' Break f~n the Pressurizer (PORV) With No Anvd m 7 l
Feedvater and One EPI Pt p"
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l 3&W has perfo =ed the requested analysis and concluded that the system is r.aintained in a safe conditien with the core re=aini=g covered out to at least 30 inutes. This calculation involves the conservative in-put asst prion of 1.2 x R:S decay heat. The results of the n miysis are attached to this letter and have been identified as Supple =ent 1 to
.Section 6 of the reference.
We also have ce=;1eted a s' 'lar calculation using 1.0 x M S decay heat.
'"his ennlysis was carried out to a;;;cr -*ttly 4700 seconds where the d
pressure turned around. The core remains covered throughout the tran-sient. The results of the analysis are attached to this letter and are designated as Supple =ent 2 to Section 6 of the reference.
If you have any additional questions, please call me at (804) 384-5111 Ixt. 2817 (office) or,(804) 3S4-3457 (home).
Y truly yours,
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J. E. Ta o":, Manager j
Licensing i
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JET /1t'
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cc:
I.A. Womack C.C. Schieck E.R. Kane C.O. Caissle R.E. Ea=
3.M. Du=n R.E. Davis
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