ML18094A306
| ML18094A306 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/27/1989 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N89053, NUDOCS 8904060472 | |
| Download: ML18094A306 (4) | |
Text
Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer March 27, 1989 NLR-N89053 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
CYCLE 9 RADIAL PEAKING FACTOR LIMIT REPORT SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 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-8385, September 1974.
PSE&G has reviewed this report and concurs with the results.
Should you have any questions regarding this transmittal, please contact Mr. R. J. Gennone at (609) 339-5410.
Sincerely, Attachment
Document Control Desk NLR-N89053 2
c Mr. J. c. Stone Licensing Project Manager Ms.
K~ Halvey Gibson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 03-27-89
RADIAL PEAKING FACTOR LIMIT REPORT This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Salem Unit 1 Nuclear Plant Technical Specif'ications.
- The F limits for RATED THERMAL POYER within specific core planes for xy Cycle 9 shall be:
- 1.
For all core pla~es containing Bank "D" control rods:
_R.TP y--
< 2.18 for all core elevations xy -
1 through 61, inclusive).
(INCORE axial points
- 2.
For all unrodded planes:
_R.TP y--
< 1.67 for all core elevations (INCORE axial points xy -
1 through 61, inclusive).
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:
FQ(z) < [2p32 ]. [K(z)]
for P > 0.5 and, FQ(z) ~ [4.64]
[K(z)]
for P ~ 0.5 assuming the moat 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*, VCAP-8385, September, 1974.
Therefore, these F limit* provide assurance that the initial xy conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFR.50.46.
See Figure 1 for a plot of [FQT. PRel] versus Axial Core Height.
- _~
FIGURE _1 2.4 cc 2.2
- J 2.0 1.4 1.2...
MAX I MUM ( F~
- P"*' ) VERSUS AX I AL CORE HEIGHT DURING NORMAL CORE OPERATION I 6, 2. 32 I
-~
~
r""--
10.8,2.18 I cc c Cc
_, i"\\
t'l c l"'I n
1... c
~
c., c !'.!
- c-c o_
- Jc
-cc a \\
.. \\
\\
1 01
\\
\\
\\
12, 1.5 I r
2 4
6 8
10 12 CORE t£1GHT (FEET)