ML20041A790

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Responds to NRC Re Violations Noted in IE Insp Rept 50-302/81-19.Corrective Actions:Procedure SP-110 Revised to Actually Close Pressure Switch to Initiate Test Signal to Functionally Test Circuits
ML20041A790
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/20/1981
From: Baynard P
FLORIDA POWER CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20041A782 List:
References
3F-1181-30, NUDOCS 8202220521
Download: ML20041A790 (2)


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Powe.o.r November 20, 1981 co-o u r 3-0-3-a-2 CS-81-299 43F-1181 -30 Mr. J. P. O'Reilly, Director Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta St., Suite 3100 Atlanta, GA 30303

Subject:

Docket No. 50-302 Operating License No. DPR-72

Reference:

RII:TFS 50-302/81-19

Dear Mr. O'Reilly:

We offer the following response to the violation listed in the referenced inspection report.

NOTICE OF VIOLATION Technical Specification 4.3.1.1.1, Table 4.3-1, requires a monthly cali-bration functional test on the Reactor-Building (RB) pressure channel.

Technical Specification Definitions, Section 1, item 1.11.b requires a bistable channel functional test to consist of the injec. tion of a simulated signal into the channel sensor to verify operability including alarm and/or trip functions.

Contrary to the above, as of August 26, 1981, the Reactor Building pressure channel monthly functional test did not include injection of a simulated pressure signal at the pressure switches.

Response

Florida Power concurs that the monthly testing of the Reactor Building pressure circuitry was not in full compliance with Section 4.3.1.1.1 of Technical Specification requirements. The procedural method being used at that time failed to test the circuitry from the pressure switch to the buffer test device in the RPS cabinet. On the same day, action was initiated to correct the test method being used. [SP-110 was revised to actually close the pressure switch to initiate the test signal, to functionally :est the circuits. A per-manent revision to SP-110 was completed September 10, 1981 (Rev. 35).

This revision brings us into full compliance with the referenced Techni-cal Specification.

8202220521 B20209 PDR ADOCK 05030302 G

PDR General Office 3201 inety-fourtn street soutn. P O Box 14042, St. Petersburg, Flonda 33733 e 813-866-5151 -

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i Notice of Violation Response Ref: RII:TFS 81-19 Page 2 O

Should there be any further questions, please contact us.

Very truly yours, FLORIDA POWER CORPORATION "W /

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D. C. Poole fatsyY.Baynard, Manager Nuclear Plant Manager Nuclear Support Services JC/rc i

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