ML18093A441
| ML18093A441 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/13/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87188, NUDOCS 8710190165 | |
| Download: ML18093A441 (4) | |
Text
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Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 October 13, 1987 NLR-N87188 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
CYCLE 8 RADIAL PEAKING FACTOR LIMIT REPORT SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272
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Q 0 g Public Service Electric and Gas Company (PSE&G) hereby submits the subject report for Salem Unit 1, in accordance with Technical Specification Section 6.9.1.9.
This report was prepared by Westinghouse Corporation in accordance with the Westinghouse methodology, "Power Distribution Control and Load Following Procedures", WCAP-8403, September 1974.
PSE&G has reviewed this report and concurs with the results.
Should you have any questions regarding this submittal, please contact Mr. Roger Blake at 609/339-4725.
Sincerely, Attachment C Mr. D. c. Fischer USNRC Licensing Project Manager -
Salem Mr. T. J. Kenny USNRC Senior Resident Inspector -
Salem Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 r--97-1019-oi65--e7iof3 ---- --- --;
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e WESTINGHOUSE PROPRIETARY CIAS.3 RADIAL PEAKING FACTOR LIMIT REPORT This Radial Peaking Factor Limit Report is provided in accordance with the Technical Specification change which replaces the radi~l peaking factor limits previously given in Section 4.2.2.2 of the Technical Specifications for Salem Unit 1 with those transmitted in a Peaking Factor Limit Report.
For Cycle 8 these are identical to the Technical Specification values, and are as follows at RATED THERMAL POWER within specific core planes:
- 1.
For all core planes containing bank "D" control rods;
~TP < 1.92 for core elevations up to 6.0 ft.,
xy
_RTP
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< 1.89 for core elevations from 6.0 to 12.0 ft., and xy
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For all unrodded planes;
~TP < 1.67 for core elevations to up 6.0 ft., and xy
~TP < 1.65 for core elevations from 6.0 to 12.0 ft.
xy These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of:
[K(z)]
for P > 0.5 and,
[K(z)]
for P < 0. 5
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WESTINGHOUSE PROPRIETARY CLAS~
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 power distributions as described in the "Power Distribution Control and Load Following Procedures", WCAP-8403, September, 1974.
Therefore, these F limits provide assurance that the initial xy conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFRS0.46.
See Figure 1 for a plot of [FQT
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W[ST141rousE PROPRIETARY CLASS 3 FIGURE 1
MAXIMUM [F0T.pREL) VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION
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