ML20150E776

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Forwards Cycle 11 Radial Peaking Limit Rept Per Tech Spec 6.9.1.7.Results Applicable for Current Tech Spec Fq Limit of 2.32 & Proposed Limit of 2.50 Currently Under Review as Part of License Change Application 161
ML20150E776
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 03/24/1988
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8804040088
Download: ML20150E776 (3)


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David W. Cockfield Vice President, Nuclear March 24, 1988 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Comnission Attn:

Document Control Desk Washington, DC 20555

Dear Sirs:

Cycle 11 Radial Peaking Factor Limit Report Pursuant to Technical Sper,1fication 6.9.1.7, attached is a copy of Cycle 11 Radial Peaking Factor tirait Report for the Trojan Nuclear Plant. The results of this analysin are applicable for both the current Technical Specification Fg limit of 2.32 and the proposed Fg limit of 2.50 currently under review as part of License Change Application 161.

It is anticipated that License Change Application 161.;111 be approvao priue te Cycle 11 operation.

Sincerely, Attachment c:

Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. William Dixon State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant kDD 0 0080 080324 p

DOCK 05000344 PDR

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Trojan Nucisar Plant Docunsnt Control Dask Dockst 50-344 March 24, 1968 License NPF-1 Attachment Page 1 of 2 4

TROJAN UNIT 1, CYCLE 11 RADIAL PEAKING FACTOR LTMIT REPORT This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.7 of the Trojan Nuclear Plant Technical Specifications.

The F, limits for RATED THERMAL POWER within specific core planes shall be:

1.

less than or equal to 1.89 for all core planes containing bank "D" control rods, and 2.

less than or equal to 1.73 for all unrodded core planes.

These F (z) limits were used to confirm that the heat flux hot channel factor F (z) vill be limited to the Technical Specification q

values of:

f F (z) 5 [

] {E(z)) fr,r P > 0.5 and 9

F (z) $ [4.64) [K(z)) for P s 0.5*

9 assu=ing the most limiting axial power distribrtions 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 Load Following Procedures", VCAP 8403, September, 1974 Therefore, these F limits provide assurance that the initial conditions assumed in the IICA analysis are met along with the ECCS acceptance criteria of a

10C R50.46.

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K(z)

Figure 3,2 2 in Technical Specifications.

r' Trojan Nucleat Plant Document Control Dask

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Docket 50-344 March 24, 1988

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FIGURE 1 MAXIMUM F-Q VERSUS CORE HEIGHT FOR TROJAN CYCLE 11

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