ML18092A467
| ML18092A467 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 01/16/1985 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NFU-85-022, NFU-85-22, NUDOCS 8501240158 | |
| Download: ML18092A467 (4) | |
Text
e OPS~G e
NFU 85-022 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department January 16, 1985 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTENTION:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Gentlemen:
CYCLE 3 RADIAL PEAKING FACTOR LIMIT REPORT FACILITY OPERATING LICENSE DPR-75 UNIT NO. 2 SALEM GENERATING STATION DOCKET NO. 50-311 Attached is the Salem Unit 2 Cycle 3 Peaking Factor Limit Report.
It is provided in accordance with paragraph 6.9.1.10 of the Salem Unit 2 Technical Specifications.
The Radial Peaking Factor Limit Report has been prepared by Westinghouse in accordance with the Westinghouse Methodology, "Power Distribution Control and Load Following Procedure, WCAP-8385, September 1974".
PSE&G has reviewed this report and concurs with the proposed limits.
Attachments The Energy People Very truly yours, Manager - Nuclear Licensing and Regulation IJool
'I' 95-21 68 (75 M) 12-83
Mr. Steven A. Varga c
Mr. Donald C. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector 1/16/85
NFU 85-022 1/16/85 Radial Peaking Factor Limit Report This Radial Peaking Factor Limit Report ~s provided in accordance with Paragraph 6.9.1.10 of the Salem Unit 2 Nuclear Plant Technical Specifications.
The Fxy 1imits for RATED THERMAL POWER within specific c.ore planes for Cycle 3 sha11 be:
- 1.
For a11 core planes containing bank "D" control rods;
- F~~P !. 1.89 for core elevations up to 6.0 ft.,
F~~P !. 1.72 for core elevations fonn 6.0 to 12.0 ft., and
- 2.
For all unrodded planes; FRTP
< 1.61 for core elevations up to 6.0 ft., and xy *-
FRTP !. 1.66 for core elevations from 6.0to12.0 ft.
xy These Fxy(z) limits were* used to confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values of:
F0(z) ~ [
2 p 3~]
[K(z)]
F0(z) ~ [4.64]
[K(z)]
for P
> 0.5 and, for P
< 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control banks C and D during operation,
~-
including the accompanying variations* in the axial xenon and po~r distri-butions as described in the "Power Distribution Control and Load Following Procedures 11, WCAP-8385, September, 1974.
Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFRS0.46.
See Figure 1 for a plot of [F0T.pRel] vs. Axial Core Height.
i NFU BS-022
-STINGHOUSE PROPRIETARY CLASS 4t 1/16/85 FIGURE 1
MAXIM~~ [FQT.pRELJ VERSUS AXIAL CORE HEIGHT ouRrNG NORMAL OPERATION 2.20 t.80
- i.
ll l.00 o.o ll
- i.
.. I" Ill' " I JC I
J [JO -
'I",......
~
r-....,
"*'I.
A e.o Core Height (ft.)
~
.... i-i.....
lw ~ - ~
~
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J IA I
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l -
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