ML19326C681
| ML19326C681 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 02/17/1977 |
| From: | Rueter D ARKANSAS POWER & LIGHT CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004250496 | |
| Download: ML19326C681 (3) | |
Text
I NRC Pc:.u 195 UA NUCLEAR REGULATORY **.MMISslON DOCKET NUMCER a.7ei 50-313 NRC dlSTRIBUTION pen PART 50 DOCKET MATERIAL
/ '
FROM:
OATE OP OCCUMENT iTO:
l Arkansas Power & Light Company 2/17/77 Little Rock, Arkansas DATE RECEIVED Mr. D. L. Ziemann Mr. Donald A. Rueter 2/22/77 lj JfLETrun CNOTORIZED PROP INPiJT PORM NUMBER OF COPIES RECEIVED l
$ o R iclN Al.
%Nc LA333 pig o CCopy One signed l oEscr,tpTioN ENCLosu RE
)
i l
1 Ltr. re our 12/7/76 ltr.... furnishing information regarding re-evaluation of ECCS performance........
g r-v',T.e.~ ~ "T F J D
. v f
n n s - n -
i 2.i O V E
-, e 1/ v !.
t....
PLANT NAME:
(2-P)
Arkcasas Unit No. 1 SAFETY FOR ACTION /INFORMATION RmrTon 2/23/77 RJL ASSIGNED AD:
A M MTt"TFM AM+
XBRANCH CMTE?r Ziemann (6) nnAnt n t'nTvv.
M PROJECT MANAGER:
Snaider PROJECT MANAGER:
N LIC. ASST. ;
Diggs LIC. ASST. :
Y N,SmW W
//A$fA> > c INTERNAL DISTRIBUTION MM FIIM SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY _&
V NRC PDR _
HEINEMAN X TEDESCO ENVTRO ANALYSTS YI&E
(.3 -)
SCHROEDER BENAROYA DENTON & MUT T FR X OELD
~
X TA TNA M IX GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECR.
MIPC MACARRY KTRKWOOD ERNST VCASE BOSNAK_
BALLARD HANAUER SIRWEIL,
OPERATING REACTORS SPANGLER HARLESS PAWLICKI STELLO SITE TECH.
' PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH.
GAM!ILL
>d OYD X
ROSS X
EISENHUT STEPP P. COLLINS X
NOVAK SRA0 HULMN HOUSTON M
ROSZTOCZY 54 BAER CHECK
' l BIJrLER SITE ANALYS~
PETERSON IMELTZ l
CRIMES l
VOLLVIR HELTEMES AT & I l
BUNCH SKOVHOLT SALTZMAN J. COLI RUTBERG KREGET' EXTERNAL DISTRIBUTION COP
><LPDR Russellville.Ar c.' NAT. LAB:
BROOKHAVEN NAT. TAR.
XIIC:
X'NSIC:
LA PDR I
~'l k
[I 80 0425()
ASLBR,
CONSULTANTS:
/ M MACRS /6 CYS M6t:99&S/50T : & #4a.,6-4//7) l V
I I
W
, s s
~
H EL PIN G BUILO ARKANSAS ARK ANS AS POWER S LIGHT COMPANY P O. Box 551 LITTLE ACCK. A AK ANSAS 72203.(501)371-4000 February 17, K~. '
/\\
.i
.d 4 ~~~ %
,,.:.j N g
gg
- h '
Q-s
?.h' 0%
Y Q)."f'(N, '
y9 i
~ ~ "
1-027-10 y(
S g
Director of Nuclear Reactor Regulationh, Ii//
'Isagg/dfjl%[~
ATTN: !!r. D. L. Ziemann, Chief
('.
g;fj Operating Reactors Branch #2 6
mg U. S. Nuclear Regulatory Commission
/
Washington, D. C.
20555 U
lg\\
Subject:
Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Re-Evaluation of ECCS Performance (File:
0930, 1510)
Gentlemen:
Your letter of December 7,1976, requested that we submit a re-evaluation of ECCS performance using an NRC staff approved model that does not use a nucleate boiling heat transfer correlation during blowdown after the critical heat flux (CHF) has been predicted.
Per telecons with your F!r. Richard Snaider we informed you of our progress in this area.
This letter serves as documentation of that infomation transmitted by telecon.
Our ECCS evaluation model is based on the B6W Topical Report, BAW-10104 A, Rev. 1, March 1976.
In a December 2,1976 letter from Mr. D. F. Ross, Jr.,
Assistant Director for Reactor Safety, Division of System Safety, Office of Nuclear Reactor Regulation to Mr. K. E. Suhrke,.lanager, Licensing, NPGD, Babcock and Wilcox, the above mentioned modification to the B6W ECCS Evaluation Model was requested.
In a December 20, 1976 letter report from Mr. K. E. Suhrke to Mr. S. A. Varga, Chief, LWR Branch #4, Division of Project Management, Office of Nuclear Reactor Regulation, the requested revision to the model was proposed. Another letter from Mr. K. E. Suhrke to Mr. S. A. Varga, dated January 24, 1977, supplemented the previous transmittal.
Both are now being reviewed by the. NRC staff, and indications suggest that approval will be forthcoming in the near future.
The above referenced communications between your staff and R5N are appli-cable to the Arkansas Nuclear One-Unit 1 ECCS Evaluation.
Decisions made concerning the BGW Evaluation Model as contained in the topical should be.
T A X A AYING. IN VE S TOA CWNE O MEMDE A MtOOLE SOUTH UTILITIES SY.
.r,
?
1' Mr. D. L. ;Ziemann February 17.1977' 1,4f 7-10
.g
-and are,4 considered to be decisions made on'the ANO-1 Evaluation.
'Ihus,
upon receipt of your. approval of.B6W's revision to their model, this ques-tion on the ANO-1 docket will be closed.
Ifl you have any questions and/or comments, please contact us.
Very truly yours, I]w/Eth f
/DonaldA.Rueter -
- s. w
/
Manager, Licensing
.DAR:RMC:tw
'9
'4
}
k
%