ML19256A861
| ML19256A861 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 01/10/1979 |
| From: | Brown S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901160243 | |
| Download: ML19256A861 (2) | |
Text
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Vin oINI A ELucTnIC ANI) POWEH C O h!PANY Hiciixoxn.VruarxrA 23009 January 10, 1979 Mr. Harold R. Denton, Director Serial No.
002 Office of fluclear Reactor Regulation LOA /RMN: Jab Attn: Mr. O. D. Parr, Chief Light Water Reactors Branch flo. 3 Docket flos. 50 304 Division of Project Management 50-405 U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
In response to a telephone request by Mr. R. P. Snaider, a member of your staff, we have attaciled to this letter a tabulation of the neutron flux levels at the inside surface of the neutron shield tank. These flux levels are based on the following general assumptions:
Power Level - 2763 MWt Power Distribution - Cycle 3, T=150 days, 6 x 6 PDQ model Model D ANISil (Slab)
Cross Section Data - DLC-47/ BUGLE Babcock & Wilcox recommends an axial peaking factor of 1.lb, an azimuthal peaking factor of 1.7 and an uncertainty factor of 1.25.
We believe that these flux levels are still too conservative and are inappropriate for computing damage to the neutron shield tank.
More realistic data will be available when detailed fuel cycle calcu-lations are made prior to operation.
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Senior Vice President-Power / Station Engineering and Construction Attachment 7 90116 0 2 h
i F]ux Levels at the Inside Surface of the Shield Tank
(
2 Group E upper (Mev)
& (n/cm
- sec)*
~
~
1 17.33 2.15(4) 2 14.92 5.98(4) 3 14.19 1.21(5) 4 13.50 6.88(6)-
5 10.00 4.95(6) 6 7.408 6.10(6) 7 6.065 7.22(6) 3 4.956 9.13(6) 9 4.066 5.44(6) 10 3.679 3.22(7) 11 2.725 3.00(7) 12 2.365 7.03(6) 13 2.307
~
1.30(7) 14 2.231 1.32(8) 15 1.653 1.33(8) 16 1.353 3.69(8) 17
.8629 3.46(8) 18
.8208 1.22(8) 19
.7427 8.64(8) 20
.6.081 5.05(8)
(
21
.4979 1.03(9) 22
.3688 1.00(9) 23
.2985 1.44(7) 24
.2972 9.93(8) 25
.1832 8.30(8) 26
.1111 7.87(8)
(.06738)
- Does not include 1.15 axial
~
1.7 azimuthal 1.25 uncertainty e
.