ML14191B118

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Notice of Violation from Insp on 890311-0417.Violation Noted:Step 7.2.30.3 of Written Procedure OST-202 Not Properly Implemented in That,Main Steamline Isolation Valve MS-V1-3A Closed Instead of MS-V1-8C,resulting in Scram
ML14191B118
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 05/18/1989
From: Verrelli D
NRC Office of Inspection & Enforcement (IE Region II)
To:
Shared Package
ML14191B115 List:
References
50-261-89-08, 50-261-89-8, NUDOCS 8906050299
Download: ML14191B118 (1)


Text

ENCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket No. 50-261 H. B. Robinson License No. DPR-23 During the NRC inspection conducted on March 11

- April 17, 1989, a violation of NRC requirements was identified.

In accordance with "General Statement of Policy and Procedure For NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violation is listed below:

Technical Specification 6.5.1.1.1.c requires written procedures be implemented for surveillance and test activities of safety-related equipment. Written procedure OST-202, Steam Driven Auxiliary Feedwater System Component Test, provides instructions for testing the safety-related steam driven auxiliary feedwater (SDAFW) pump.

Step 7.2.30.3 of OST-202 requires SDAFW pump steam supply isolation valve MS-V1-8C to be closed.

Contrary to the above, step 7.2.30.3 was not properly implemented, in that, main steamline isolation valve MS-V1-3A was closed instead of MS-V1-8C, resulting in a reactor scram.

This is a Severity Level IV Violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light is hereby required to submit to this office within.30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including:

(1) admission or denial of the violation, (2) the reason for the violation if

admitted, (3) the corrective steps which have been taken and the results
achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION David M. Verrelli, Chief Reactor Projects Branch 1 Division of Reactor Projects Dated at Atlanta, Georgia this l(tday of May 1989 8906050299 890518 PDR ADOCK 05000261 Q

PNU