ML20138R196
| ML20138R196 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/26/1985 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512310040 | |
| Download: ML20138R196 (3) | |
Text
_.
s DuxE POWER GOMPAhT I
P.O. pox WM80 CIIAHLOTTE, N.C. 28242 "E";.EiEP AWA'fA
.m..__
December 26, 1985 Mr. Harold R. Denton, Director Office of Regulatory Reactor Regulation U.-S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr.
B. J. Youngblood, Project Director i
PWR Project Directorate No. 4 Re:
Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Proof and Review Technical Specifications
Dear Mr. Denton:
This letter supplements information regarding Figure 3.2-3,
" Reactor Coolant System Total Flow Rate Versus R" presented in my November 8, 1985 letter.
Section 3.2.3 of Revision 4 to the Standard Technical Specifications (STS) included an R2 factor.
R2, as defined in the STS, allowed for the inclusion of a penalty for. rod bow on DNBR only.
Thus, knowing the "as measured" values of FNAH and RCS flow allowed for " tradeoffs" in excess of R equal to 1.0 for the purpose of offsetting the rod bow DNBR penalty (see attached STS Rev. 4 Figure ~3.2-3 which clearly shows the operation region for R )*
2 Section 3.2.3 of Draft Revision 5 to the STS and the Catawba Technical Specifications have taken into account fuel rod bowing.
Credit is provided in Figure 3.2-3 to offset the reduction in the generic margin associated with rod bow.
The removal of the R2 factor has the effect of making operation outside the LOCA LIMIT line but~inside the DNB LIMIT line unacceptable no matter what the actual Rod Bow Penalty is.
Therefore,'the DNB LIMIT line no longer serves a purpose and should be deleted from'the Catawba Technical Specifications.
This line should also be removed from the Draft Rev. 5 STS.
.very truly yours,.
8512310040 851226 7"
PDR ADOCK 05000413 p
PDR Y
Hal B. Tucker
-RWO:slb
' Attachment
t a
~Mr. Harold R. Danton, Director December 26, 1985
- Page Two cc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory-Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station 4
^
k
.g.
t ll9.lD;tiFli T 1l;"ih
'i
! L
~ ~
j MEASUREMENT I
UNCERTAINTIES i
-a
,. OF 3.5% FOR FLOW
- d,.
'jAND 4% FOR INCOREl.
-ij
~
48 9 MEASUREMENT OF !~
h
~I "J" T E
iN ARE INCLUDED I
FAH ACCEPTABLE -
i IN THIS FIGURE.
't OPERATION REGION FOR l.R ONLY 44 j
THis FIGURE FOR ILI.USTRATION ONLY a.
DO NOT USE FOR OPERATION o
l bc ACCEPTABLE,
l 4
g OPERATION j
- l UNACCEPTABLE l
4 REGION FOR !
'. OPERATION E
R, AND R REGION i
g o
g (1.038, 39.8)
I a 40 T
+
o i
g j
j O
i E
+
i
.1-i 38 l
i-b 4
g..
'(1., 36.3) l i
36 i
l i
1 i
1 i
i.
?
I 34 1
I I
1 I
0.90 0.96 1.00 1.06 1.10 1.15 R, = F ll1.49 [1.0 + 0.2 (1.0 - P)]
3 R = RA1 - RBP(BU)]
FIGURE 3.2 3 RCS TOTAL FLOWRATE VERSUS R - FOUR LOOPS IN OPERATION PSTS 3/4 2-10 NOV 151979
. _... - - _ _... _ _ _. _ _.. - _ _ _ _ _, _ _ _ _.. _ _ _. _ _. _.