ML20106E183
| ML20106E183 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 10/29/1992 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-92-00134, GNRO-92-134, NUDOCS 9211060188 | |
| Download: ML20106E183 (2) | |
Text
%g.
.1
' CMergy Operations'inc.
~-
ENTERGY
~w ne m w :n.
if I 4 )
4
.n,~.-,-~.-----
m.<,-~
w.T. cotti.-
October 29, 1992
,y 1
U.S. Nuclear Regulatory Commission Mnfl Station Pl-137 Washington, D.C.
20555 Attention:
Document Control Desk
Subject:
Grand Gulf Nuclear Station Unit. 1 Docket No. 50-416 hicenan No. NPF-29 St nLion Blackout Conimitment Status GNko-92/00134 Gentlemen:
In a letter dated Fnbruary 6,1192 t he NRC t ronomittri the safety evaluat ion (SE) of Grand Gulr's initial response to the Station Blackout (SBO) Rule, 10(TR 50. 63, icluding several recommendations.
The NRC subsequentiv Issued a supplement al safet y evaluation (SSE) in a letter dated June 5, 1992, concluding t. hat F00 compliance was acceptable based on confirmations and commitment.s supplied in responsn t.o the initial safety ovaluation.
Additionally, the Staf f recp:ested writt en confirmation of the implementation of the comiritment s made regarding SBO.
In the resporse to the SE we committed, in part, to 1) perform the control room and control cabinet area heat-up analysis by September 30, 1992, n'nd
- 2) perform a tiew drywell heat-up calculation considering the hent ' loads -duc-to a postulated recirculet,
pump sea l lenk of 36 gom.
This letter confirms the impl w~.tation of thone two commitments.
A Station Blackout Calculation for drywell *.cmporature analvsis has been i
performed and is documented in Entergy Operations Calculation NEAD-SR-92/045 and NPE Engineerir.g Report No. GONS-92-0046, Pev. O.
-The 830 drywell temperature analysis shows that the peak drywell temperat.ure remains.less than t he des ign temperat ure of 336*F.
o 030000 88 921029
.k P
CK 05000416 PDR
/
)
n
.G9210091/SNhlCFhR - t e
i U
n a
V 4 --
- 0 tober 29, 1992 GNRO-92/00134 Page 2 of 3 A control room and cont n i cabinet area calculation has been pertor.ned and is documented in Calculation MC-QJZ10-92053, Rev. O.
The calculation shows that the control room and the control cabinet area peak temperatures remain less than 120'F.
9 These analyses art av111able on-site for review.
d additional information please contac. W. D. Brice at If you nee (601) 437-6556.
Yours truly, cp C~Ca w WTC/WBB/mtc cc:
Mr. R. 11. Be rnha rd Mr. D. C. Ilintz Mr. R. B. McGohee Mr. N. 9. Reynolds Mr.11. L. Thomas Mr. Stewart D. rnneter Regional Admfrtistrator U.S. Nuc? ear Regulatory Commission Region II 101 Marietta St.,
N.W., Suite '900
/
Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager (w/2) nr' ice of Nuclear Reactor -Rogulation
.S. Nuclear Regulatory Commission Mail Stop 13113 Washington, D.C.
20555 s
G9210091/SNhICFER - 2.
..