ML20034A200
| ML20034A200 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/12/1990 |
| From: | Walt T PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9004200403 | |
| Download: ML20034A200 (3) | |
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April 12, 1990 Trojan Nuclear Plant Docket 50-344 l
License NPF U.S. Nuclear Regulatory Commission Attn 1-Document Control Desk Washington DC 20555 5
Dear Sirst Trojan Cycle 13 Radial Peakinr. Factor Limit Report Pursuant to Technical Specification 6.9.1.7. " Radial Penking Factor Litait Report", attached is a copy of-the Trojan' Cycle'13 Radial Peaking Factor.-
Limit Report. The Fxy' limits'for rated thermal power'(RTP) are changed RTP values were 1.92 and.1.76 for-core-
'from Cycle 12;.the previous Fxy planos with control Bank "D" rods and unrodded planos.-respectively..
l Sincersly' O'b V
l T. D. Walt--
Acting Vice President,. Nuclear Attachment-c:
Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. David Stewart-Smith State of Oregon
. Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nucicar Plant
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W iTrojcnNuclCcrP1Cnt Document C:ntrol-De:k Dockqt 50-344 April 12, 1990 License NPF-1 Page 1 of 2 TROJAN CYCLE 13 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
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Nuclear Plant Technical Specifications, f
The F limits for RATED TIIERMAL POWER within specific core planes shall bet 1.
F less than or equal to 1.94 for all core planes containing bank "D" control rods, and 2.
F, less than or equal to 1.78 for all unrodded core planes.
i These Fgy(z) limits were used to confirm that the heat flux hot channel factor F (z) will be limited to the Technical Specification values'of:
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1 F (z) s [
] [K(z)] for P > 0.5 and*,
9 F (z) s (5.00] [K(z)] for P s 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 accompanying variations in the axial xenon and power distributions as described in the " Power Distribu'. ion Control and Load Following Procedures", WCAP-8403, September 1974.- Therefore, these F
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limits provide assurance that the initial conditions assumed in the Loss of Coolant Accident analysis are met, along wih the Emergency Core j
t Cooling System acceptance criteria of 10 CFR 50.46, " Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power.
Reactors".
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- K(z) - Figure 3.2-2 in Technical Specifications
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4330W.0490
Y Trojan Nuclear Plant Document, Control Desk
- h Docket 50-344 April-12, 1990 1.icense NPF-1 Attachment Page 2 of s FIGURE 1 L
MAXIMUM FQ VERSUS CORE HEIGHT FOR TROJAN CYCLE 13
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