ML20202F872

Forwards Cycle 9 Radial Peaking Factor Rept,Per Tech Spec 6.9.1.7.F(xy) Unrodded Peaking Factor Changed from 1.66 (Cycle 8) to 1.70 for Cycle 9.Change to Tech Specs Section 5 Re Fuel Assembly Weight Will Be Submitted

ML20202F872
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/31/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8604140236
Download: ML20202F872 (3)

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Pbrtland General BectricCe@v I.~_~

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March 31, 1986 N '"

Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek CA 94596-5638

Dear Mr. Martin:

i TROJAN NUCLEAR PLANT Cycle 9 Radial Peakinr. Factor Report Pursuant to Technical Specification 6.9.1.7, attached is a copy of the Cycle 9 Radial Peaking Factor Limit Report for the Trojan Nuclear Plant.

l The F unrodded peaking factor has changed from 1.66 (Cycle 8) to 1.70 forChle9. The hot channel factor limits have not changed and no Sec-tion 2, 3, or 4 Technical Specification changes are required for Cycle 9 l

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operation. A change to Section 5, Design Features, of the Technical Specifications is prepared to cover a nominal change to the fuel assembly weight and will be submitted separately.

Sincerely, glh~

Bart D. Withers Vice President l

Nuclear Attachment c:

Mr. Lynn Frank, Director State of Oregon Department of Energy Director of Nuclear Reactor Regulation Attn: Chief PWR-A Reactor Systems Branch U.S. Nuclear Regulatory Commission Washington DC 20555 h

121 S V.' ".) tron 074:t. Put. vd Gepi 9 720 0 0

NkRER00 FROM MM08 TROJAN UNIT 1, CYCLE 9 RADIAL PEAKING FACTOR LIMIT REPORT is Radial Penking Factor Limit Report is provided in accordance with Para-3 aph 6.9.1.7 of the Trojan Nuclear Plant Technical Specifications.

I eF limits for RATED THERMAL POWER within specific core planes shall be:

RTP 1.

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

F less than or equal to 1.70 for all unrodded core planes.

xy i

[1pese F (z) 1:,mits were used to confirm that the heat flux hot channel factor F(z)wU1be'.im,Ited to the Technical Specification values'of :

g F (z) $

] [K(z)] for P > 0.5 and,*

q F (z) s

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

q ysuming the m ast, limiting axial power distributicns expected to result from the msertion and removal of Control Banks C and D during operation, including the

': companying variations in the axial xenon and power disbributions as described p the " Power Distribution Control and lead Following Procedures", WCAP 8403,

+. Therefore, these F limits provide assurance that the initial yptember,197(

ynditions ass'med in the IDCA analyUs are set, along with the ECCS acceptance riteria of 10;FR50.46.

j*Ps(z) - Figure 3.2 2 in Technical specifications I

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FROM MMOS WIRE ROOM (WED)03.26.'86 13804 NO.2 PAGE 4 t

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