ML20248B241

Notice of Violation from Insp on 890409-29.Violation Noted: Temporary Plant Test (TPT)-235 Did Not Contain Sufficient Testing to Verify Interlocks & Permissives Associated W/Rhr Sys Suction Isolation Valve

ML20248B241
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/24/1989
From:	Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20248B238	List: IR 05000344/1989013 ML20248B232 ML20248B241
References
50-344-89-13, NUDOCS 8906080296
Download: ML20248B241 (2)

Text

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J n APPENDIX A NOTICE OF VIOLATION

, Portland General Electric Company Docket No. 50-344 Trojan Nuclear Plant License No. NPF-1 During an NRC inspection conducted from April 9 through April 29, 1989, a violation of NRC requirements was identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C (1987), the violation is listed below:

A. 10 CFR Part 50, Appendix B, Criterion XI, " Test. Control", states, in part: "A test program shall be established to assure that all testing required to demonstrate that systems and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained.in applicable design documents."

~ Contrary .to the above. . Temporary Plant Test (TPT)-235 " Remote Shutdown Station Input /0utput Verification", dated April 25, 1988, did not contain sufficient testing to verify the interlocks and permissives associated with M0-8702, Residual Heat Removal System suction isolation valve, functioned as designed subsequent to modification. Specifically, Temporary Plant Test (TPT)-235 stated, in part, " verify circuits >

interrupted by the RSS [ Remote Shutdown Station] installation will perform their control, indication, permissive and/or protective functions after restoration"~however, testing performed on May 22, 1988, did not verify the permissive and interlock features of M0-8702, and subsequently on April 9, 1989 the permissive and interlock features of M0-8702 were found to be inoperable.

This is a severity' level IV violation (Supplement 1).

Pursuant to the-provisions of 10 CFP, 2.201, Portland General Electric Company is hereby required to submit a written statement of explanation to the U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Senior Resident Inspector, Trojan, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "ReNy to a Notice of Violation" and should include for each violation: (1) the reason for the violation if admitted, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Consideration may be given to extending the response time for good cause shown.

8906080296 090524 PDR ADOCK 05000344 g PNU

f FOR THE NUCLEAR REGULATORY COMMISSION IS R. P. Zimmerman, Director Division of Reactor Safet9 and Projects Dated at ainut Creek, Californi.a this day of g /

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