ML20062M456
| ML20062M456 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/18/1981 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19268A572 | List: |
| References | |
| NUDOCS 8112170246 | |
| Download: ML20062M456 (10) | |
Text
~'
Meiling Address Alocama Power Company 600 North 18th street Post Office Box 2641 Birmingham. Alabama 35291 s
Telephone 205 783-6081 F. L Clayton Jr.
b
- ZEC'$'"'
Alabama Power
~
November 18, 1981 Ap \\. - -Q g 4c Docket Nos. 50-348 50-364 p
?
rC{\\l%
J d-Y.W. - :. "
. Director of Nuclear Reactor Regulatirn 2
o $3F ^21 U. S. Nuclear Regulatory Comission
.% Neg u.sg' " Yw Q Washington, D. C.
20555
/
ue
- /
cg/
4 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Un' dEP'i i
ECCS Analysis /Fg Proposed Technical Specif1 tion' Change Dated Novemoer 16, 1981 Gentlemen: provides Alabama Power Company's response to the NRC Staff's request for supplemental information pertaining to the referenced submittal addressing the elevation dependent peaking factor versus core height graphs for Unit 1 Cycle-4 and Unit 2 Cycle-l. This information is being submitted in support of the requested Fg Technical Specification Change to the J. M. Farley Unit 1 Operating License No. NPF-2 and Unit 2 Operating License NPF-8.
As this submittal contains infomation proprietary to Westinghouse Electric Corporatica, it is supported by previously submitted affidavits signed by We:tinghouse, the owner of the information (Attachment 2).
The affidavits set forth the basis on which the information may be with-held from public disclosure by NRC and addresses with specificity the considerations listed in paragraph (b) (4) of Section 2.790 of the NRC regulations.
Accordingly, it is respectfully requested that the information, which is proprietary ;o Westinghouse, be withheld from public disclosure in accordance with 10CFR Section 2.790 of the NRC regulations. Correspon-dence with respect to the proprietary aspects of this application for withhalding or the supporting Westinghouse affidavit should reference CAW-81-83 and should be addressed to Mr. R. A. Wiesemann, Manager, Regulatory and Legislative Affairs Westinghouse Electric Corporation,
'P.O. Box 355, Pittsburgh, Pennsylvania 15230.
yApl$
Very truly yo m,
4 8112170246 811118 A
PDR ADOCK G5000348 g
r gR P
[
I F. L. C!ayton, Jr.
FLCJr/RLG:awm
//
Attachments cc: Page 2
I Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Page 2 cc: Mr. R. A. Thomas SWORN TO AND SUBSCRIBED BEFORE Mr. G. F. Trowbridge ME THIS
/2 ^
DAY OF Mr. J. P. O'Reilly Mr. E. A. Reeves A d m i r, 1981.
Mr. W. H. Bradford I
'^
Notary Public
.i l
My Comission Expires:
/c Z 7 B[
f f
I l
l i
l J
1 ATTACHMENT 1 NRC REQUEST FOR SUPPLEMENTAL INFORMATION Relating to APCo's 11-16-81 Request for F0 Change In Units 1 & 2 Technical Specifications
^
Please provide a graph of Maximum (F Subcase Analysis performed in suppork o. Pfbe)) prop.CoreHeightforthe vs osed FQ Technical Specification change for the Joseph M. Farley Nuclear Plant - Units 1 and 2.
APC RESPONSE T xp As requested by the NRC Staff, plots showing the maximum F versus axial height during normal operation for Farley Unik 1 CycT814 and Farley Unit 2 Cycle-1 are provided in Figures 1 and 2, respectively. contains the non proprietary version of Figures 1 and 2.T En-closure 2 contains the proprietary version of Figures 1 and 2.
FQ x
relative power was calculated as a function of height by imposing various load follow transients on the reactor through insertion and removal of Banks D and C considering the effects of the accompanying variation in axial xenon and power distributions as discussed in WCAP-8385 (Westing-house Proprietary) and WCAP-8403 (Non-Proprietary). Beginning and end of cycle conditions were assumed prior to calculating the effects of load follow transients on the axial power distributions. These different histories assumed base load operation and extensive load following without use of part length rods..In all cases the calculated values are maintained below the nuclear design operating envelope 2.31 x K(z) where K(z) is the normalized F (z) function shown on Figure 3.2-2 of both the Unit I and 2 Q
The F (z) envelope is verified for each reload Technical Specifications.
Q as part of the normal core design process.
The Unit 2 plot is based on 18 cases with the normal 3% and 5% engineering and measurement uncertainties applied. The limiting point (value slightly less than 2.31) at 4.5 feet eleveation is at return to power following a load follow transient at beginning of life case. The Unit 2 burnup is currently in excess of 4000 MWD /MTV. The Unit 1 plot is based on a 3 case subset with an additional 3% uncertainty applied. A new Westinghouse pro-cedure provides points at a greater number of axial locations than previously provided. Both Farley units operate base loaded, thus actual operating FQ values are significantly less than those shown on the plots.
Enclosures
g s
ENCLOSURE 1 Non-Proprietary Version; Figures 1 and 2 1
FIG
- _U._R.E 1
T
. lGXII.J:* (fQ*PR L.L ) YERSUS AX1 AL CORE liElGST DURI:!G i:0RGL CYCLE OPE!LATION i
CYCLE 4 J.M.Farley Uni t I h..
- S
h
- I h..-
t.
_.3 t y_ N ". ::. = :- :.:.-2.h
- =.::1: - -
7-h.::6
- -e--
t-.
.~
4:C;::.,
6.. -
.z.x'x
=:s t_i..is
=
a._.
'g gig j :: -
- J. ";
pC.
T--*...
I~-
I t
5-5
' - ~ ' -
.u.a e
i r_.m
- . =__
. _1_:..
2 t
me.m 4 f m
.e.-
A l"'-**'
-_. "e;.
J w g:.;_.
= =. -
g c,..
- rn n.
in:.-
>-- Cr =_._ __
~.-~:--
U.
~ ' ' _ ~
. =.
Zj g-f--r
- n.. -
M I ! -.T X
l---
f ;_-..
t-.
t' % ". :.1 L.i_==
1
- e e m d e4
.N
[*,*
LE__.
- ..=_-
=
.._.Se
.1:~
- 1"..._..
_-_ --- ::--.:r : :. _. 4
. ___ =:r :: : - :1_ :
= :; ;.::- _;.i;n.---;.-
- --. - ; f - -- :; _---
.:. :.:.:: u-- 2.7- - 9. i
- 4.un. g:
- - :. 2. =:t=-..;.:-.=.
J._-. = g.. -- -- - -- :--- f,- - : j = -, t_;._---
- _=.:-
2.:;--
BOTT0;4 CORE liEIG!!T (FEET)
TOP 1
l
.a I
(
o....., =
.a.-
&c..
.n n Nm.
w >=
~ - * - -
- "h
^
1 FIGURE 2 T
t%X?WM (Fq,pREL)
VERSUS AYl AL CORE HEIGHT DURING NORMAL CYCLE OPERATION J.M.Farley Unit 2, Cycle 1 2.6 e
2.4
+(a, c) 2.2 2.0 E 1.8 b
1.6 x
2 1.4 1.2 1.0 0.8 7 2
4 6
8 jo lj l
BOTTON CORE HEI6yr (FEET) l TOP
.. - - -,. ~... - ~.,,
m ATTACHMENT 2 Previously Submitted Westinghouse
, Proprietary Information Affidavits
,-y
,y p
-