ML19330A840

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RO 80-2:on 800706,during Low Power Physics Testing at all- Control Rods Out Configuration,Moderator Temp Coefficient Found Out of Spec.Control Rod Withdrawal Limits Determined
ML19330A840
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 07/15/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8007290633
Download: ML19330A840 (3)


Text

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1750 Chestnut Street Tower II July 15, 1980 lir. Jaaes P. 0'2e1117, Director U.S. iluclear Regulatory Cocmission Office of Inspection and Enforeccent Region II 101 .iarietta Street, Suite 3100 atlanta, Georgia J0303

DearIr. O'Reilly:

Tc.iS2SS44 VALLEY AUT!!ORITY - SEQU0Y d .WCLCAR PLAWT UNIT 1 - DOCKET LO. 50-327 - FACILITY OPEMTUG LIC. NSE DP2 3P1;CIAL aZPGRT 00-2 Tha enclosed report provides details concerning a positive moderator temperatura coefficient walch was ncasured during low power physics testing at tae all-control rods out configuration. This report is aubmitted in accordance wita' Sequoyan unit 1 Iocnnical Specifications 6.9.2 and 3.1.1.3.

Very truly yours, TC.indSSEZ VALLZY AUTHORI~"I J. R. Calhoun Director of liuclear Power Enclosure (3) cc (Enclosure):

Director (3)

Office of ;Ianagement Information and Program Control U.S. Muclear Regulatory Coc: mission i Washin2 ton. DC 2Ei,5,5 ____ _ \

Director (40)

Office of Inspection and 2nforcement U.S. Uuclear Regulatory Cocenission Washington, DC 20535 lir. Bill Lavallee Wuclear Safety Analysis Center Palo Alto, California 94303 7

lir. W. T. Cottle, li2C Inspector, Sequoyah S

//

8007290633

SPECIAL REPORT 80-2 MODERATOR TDIPERATURE COEFFICIEhT The all .ontrol rods out, beginning of life, moderator temperature coeffi-cient (MTC) was determined on July 6 1980 to be 0.85 x 10-5 delta k/k/0F.

This does not meet the criteria of less positive than 0 delta k/k/0F established in the Sequoyah Nuclear Plant Unit 1 Technical Specifications.

Control rod withdrawallimits (See attached) have been determined. A conservatism of 1 x 10-0 delta k/k/ F has been included in the limits to ensure that the reactor is not operated with a positive MTC. The predicted burnup at which the MTC will be restored to within its limit is 1000 MWD /

MTU.

This report is submitted in accordance with Technical Specification 6.9.2 and 3.1.1.3 Action a.

Attachment

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