ML20127N484

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Special Rept 85-007 Re Positive Moderator Temp Coefficient for Withdrawn Control Rods.Hot Zero Thermal Power Condition within Tech Spec 3.1.1.3a Limit.Control Rod Withdrawal Limits Incorporated Into Operating Procedures
ML20127N484
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/10/1985
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Martin R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
85-007, 85-7, KMLNRC-85-151, NUDOCS 8507010629
Download: ML20127N484 (3)


Text

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KANSAS GAS AND ELECTRIC COMPANY T>E ELECTAIC COMPANY GLENN L MOESTER vsCE Peasentar. asuctaan June 10, 1985 Mr. R.D. Martin, Regional Administrator T@M0MM A

[

U.S. Nuclear Regulatory Commission '

Region IV JUN I 41985 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 - I KMLNRC 85-151 Re: Docket No. STN 50-482 Subj: Special Report 85-007

Dear Mr. Martin:

The enclosed Special Report is submitted pursuant to Technical Specification 3.1.1.3.

If you have any questions concerning tivis matter, please contact me or Mr. Otto Maynard of my staff.

Ycurs very truly, hidGlenn L. Koester Vice President - Nuclear GLK: dab Enclosure xc: P0'Connor (2)

JCummins 8507010629 DR 850610 $

q g ADDCK 0500 2 C '

6 i 201 N. Market - Wichita, Kansas - Mail Address: RO. Box 208 i Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451

SPECIAL REPORr 85-007 POSITIVE MODERMOR TEMPFEATURE COEFFICIENT -

We moderator temperature coefficient for the all rods withdrawn, beginnirg of cycle life (pL), ho zero thennal power condition has been measured to be + 1.03 x 10- A F at a critical Boron concentration of 1353 ppn.

m is is more positive than the limit of Technical Specification 3.1.1.3a.

In accordance with Technical Specification 3.1.1.3 Action Statements, control rod withdrawal limits have been established and incorporated into the appropriate plant operating procedures to assure that the mod rator temperature coefficient is maintained less positive than 0 a F. (See Attached Typical Chart) .

We predicted average core burnup necessary for restoring the positive noderator tenperature coefficient to within its limit for the all rods withdrawn condition is 5400 MWD /MTU. W is is based on calculations for the all rods withdrawn, hot zero thennal power, Xenon and Samarium free condition at a critical Boron concentration of 1215 ppm.

l I

L.

ATTACHMENT TO ,

J SPECIAL REPORT 85-007 R00 WITHDRAWAL. LIMITS Moderator Temperature Coefficient (MTC) < 0 por TNe. I03 .202 302 40 W 50 2

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