ML20024C110
| ML20024C110 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/06/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 726C, NUDOCS 8307120268 | |
| Download: ML20024C110 (5) | |
Text
_..
e VIRGINIA ELECTRIC AND Powan COMPANY R Icnixoxn, VIRO INIA 202031 W. L. srmwuer weY.'d"*='."r"o..
July 6, 1983 Mr. Harold R. Denton, Director Serial No. 726C Office of Nuclear Reactor Regulation GLD/RWC:cdk:0556C Attn: Mr. Robert A. Clark, Chief Docket Nos. 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Comission NPF-7 Washington, D.C.
20555 Gentlemen:
SUPPLEMENT TO AMENDMENT TO OPERATING LICENSES NPF-4 AND NPF-7 NORTH ANNA POWER STATION UNIT NOS.1 AND 2 REACTOR COOLANT SYSTEM TEllPERATURE OF 587.8vF In our letter dated December 30,1982 (Serial No. 726), Yepco requested an amendment to Operating Licenses NPF-4 and NPF-7 to allow operation of-North Anna Unit Nos.1 and 2 at a reactor coolant system average temperature of 587.80F. This letter provides in Attachment 1 supplemental information in answer to questions discussed with members of the Staff's Core Performance Branch on May 9,1983 and June 15, 1983.
Should you have any questions, please contact us at your earliest convenience.
Very truly yours, w
W. L. Stewart Attachment (1) Response to Core Performance Branch Question for North Anna 7.50F Tavg Increase cc: Mr. James P. O'Reilly Mr. M. B. Shymiock Regional Administrator NRC Resident Inspector Region II North Anna Power Station Mr. George Schwenk Mr. Charlie Price Core Performance Branch Department of Health 109 Governor Street Richrmnd, VA 23219
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8307120268 830706
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PDR ADDCK 05000338 P
ATTACHMENT 1 RESPONSE TO CORE PERFORMANCE BRANCH QUESTION 0
FOR NORTH ANNA 7.5 F T-AVG INCREASE l
T ATTACHMENT 1 RESPONSE TO CORE PERFORMANCE BRANCH QUESTION FOR NORTH ANNA 7.5UF TAVG INCREASE I.
NRC Question
" Confirm that the applicable range for the key parameters in the W-3 DNBR correlation bounds the conditions expected after the 7.5 F in-crease in Tavg.
2.
Response
The Range of the key parameters associated with the W-3 correlation, the R-grid factor, the cold wall factor and the non-uniform heat flux multiplier are included in Table 1.
These are supported by the re-ferences also indicated in Table 1.
These ranges bound the operating conditions present in the Condition II and III DNB transients which were reanalyzed at the uprated conditions. Table 2 presents the 7.50 uprating design conditions, which are well within the W-3 correlation range of applicability.
I l
l l
4
TABLE 1: W-3 CORRELATION LIMITS REF.
PRESSURE MASS EQUIV.
LOCAL AXIAL INLET CORRELATION N0.$
RANGE VELOCITY DIAMETER QUALITY HEIGHT TEMP.
2 F
(psia)
(Mlb/h-f)
(in.)
(in.)
(O )
W-3 1,2 1000-1.0-0.2-5.0.15 10-
>400 2400 5.0 0.7 144 F-factor 1,2 1000-1.0-0.2-5.0.15 10-2400 3.0 0.7 144 Coldwall 1,2 1000-1.0-5,0.15
>10 Factor 3,4 2400 5.0 Spacer 3,4 1490-1.5-
-<0.15 96-404-Factor.
2440 3.7 168 624 0
TABLE 2:
CORE CONDITION WITH 7.5 F TAVG INCREASE core inlet temp. (O )
555.5 F
2 mass velocity (mlb/h-f )
2.442 pressure (psia) 2250 e
4 4
~
References:
1.
E. R. Rosal, J. O. Cermak, L. S. Tong, J. E. Casterline, S. Kokolis, and B. Matzer, "High Pressure Rod Bundle DNB Data with Axially Non-Uniform Heat Flux," Nuclear Engineering and Design Vol. 31(1974),
No. 1, pp. 1-20 (see Appendix B) 2.
L. S. Tong, " Boiling Crisis and Critical Heat Flux," U. S. AEC Critical Review Series,1972.
3.
F. F. Cadek, F. E. Motley, " Application of Modified Spacer Factor to L-Grid Typical and Cold Wall Cell DNB," WCAP-8030-A, January 1975.
4.
F. F. Cadek, F. E. Motley, "DilB Test Results for R-Grid Thimble Cold Wall Cells," WCAP-7958 Add.1, January 1975.
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