ML20247G205
| ML20247G205 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/31/1989 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8904040156 | |
| Download: ML20247G205 (3) | |
Text
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j David W. Cockfield Vice President, Nuclear March 31, 1989 Trojan Nucicar Plant l
Docket 50-344-License NPF-1 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555
Dear Sirs:
Cycle 12 Radial Peaking Factor Limit Report Pursuant to Technical Specification 6.9.1.7, " Radial Peaking Factor Limit Report", attached is a copy of Cycle 12 Radial-Peaking Factor Limit Report I
for the Trojan Nuc1 car Plant. The results of this analysis are applicable for the Technical Specifications which we expect to be approved as part of License Change Appilcation (LCA) 161, " Nuclear Fuel Upgrade".
It is our understanding that LCA 161 will be approved prior to the scheduled initial criticality of cyclo 12 operation.
1 Sincerely, Attachment c:
Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. William T. Dixon State of Oregon Department of Energy Mr. R. C. Bare q
i NRC Resident Inspector Trojan Nuclear Plant 8904040156 890331
(
PDR ADOCK 05000344 P
PDC 121 S.W. Salmon Street, Portland, Oregon 97204,503/404-8897 c
I Trojen Nuclear Plent Docum nt Control D2sk j
. 4 Docket 50-344 March 31, 1989 License NPF-1 Attachment Page 1 of 2 TROJAN CYCLE 12 RADIAL PEAKING FACTOR LIMIT REPORT This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1. 7, " Radial Peaking Factor Limit Report", of the Trojan Nuclear Plant Technical Specifications.
The F limits for RATED THERMAL POWER within specific core planes shall be:
RTP 1.
F less than or equal to 1.92 for all core planes containing xy bank "D" control rods, and RTP 2.
F less than or equal to 1.76 for all unrodded core planes.
limits were used to confirm that the heat flux hot channel l
These F y(z) factor F (z) will be limited to the Technical Specification values of:
F (z) S [2.50] [K(z)] for P > 0.5 and*,
9 P
F (z) s [5.00] [K(z)) for P s 0.5*
1 1
assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Lm.d Following Procedures", WCAP-8403, September, 1974.
Therefore, these F
limits provide assurance that the initial conditions assumed in the y
Loss-of-Coolant-Accident analysis are met, along with the Emergency Core Cooling System acceptance criteria of 10 CFR 50.46. " Acceptance Criteria
'or Emergency Core Cooling Systems for Light Water Nuclear Power Reactors".
~
- K(z) - [5gure 3.2-2 in Technical Specifications.
v.
Trofan Nuclear Plant Document Control Desk D9cket 50-344 March 31, 1989 License NPF-1 Attachment Page 2 of 2
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FIGURE 1
MAXIMUM FQ VERSUS COi4E HEIGHT FOR TROJAN CYCLE 12
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