ML20087B645

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Notifies That Addl Insp & Test of Reactor Trip Breakers Completed on 711221,in Response to 711208 Request.Attention Was Focused on Cleanliness of Exposed Linkages of Breaker Mechanisms.No Accumulation of Dirt Found
ML20087B645
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 12/21/1971
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Jennifer Davis
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20087B648 List:
References
NUDOCS 8403090309
Download: ML20087B645 (1)


Text

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Raleigh, North Carolina 27602 December 21, 1971 Mr. John G. Davis, Director .

U. S. Atomic Energy Commission Division of Conpliance Region 11 - Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303 H. B. ROBINSON STEAM ELECTRIC PLANT LICENSE DPR-23 REACTOR TRIP BREAKERS

Dear Mr. Davis:

Your letter C0:II:50-261 of December 8, 1971 concerning additional inspections and testing of the reactor trip breakers was received on December 15, 1971.

Carolina Power & Light Company letter of October 29, 1971 sum-marized the details of the reactor trip breaker difficulties experienced at our H. B. Robinson Plant to the Division of Reactor Licensing. In that letter it was reported that the undervoltage trip devices on the four reactor trip breakers had been replaced by Westinghouse with modified devices on October 12, 1971. Since this modification, periodic testing has demonstrated satisfactory operation of the reactor scram breakers in each instance.

As requested in your letter of December 8, 1971, an additional inspection and test of the breakcrs was completed on December 21, 1971.

Particular attention was focused on the cleanliness of the exposed linkages of the breaker mechanisms. No accumulation of dirt was found. On test, the breakers functioned normally and no corrective action was required.

It is believed that this additional inspection and test and continued formal, periodic testing of the breakers gives reasonable assurance that the breakers will function as designed in the event of a reactor trip signal. Careful surveillance of this vital, safety-related equipment will be continued.

Your interest in bringing the problems experienced at other plants to our attention is appreciated.

Yours very truly,

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D tley

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Manager Generation & System Operations NBB:me q-  ;^ #

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cc: Mr. C. D. Barham Mr. G. P. Beatty 3, ,

Mr. N. B. Bessac 8403090309 711221 PDR ADOCK 05000261 G PDR f