ML20149J462

Notice of Violation from Insp on 880104-22.Violation Noted: Auxiliary Feedwater Sys Test Data Sheet Filed W/O Engineer Signature & Applicable Inservice Testing Data Not Reviewed & Logged Appropriately

ML20149J462
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/05/1988
From:	Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20149J429	List: ML20149J425 ML20149J462 ML20149J475
References
50-344-88-01, 50-344-88-1, NUDOCS 8802230070
Download: ML20149J462 (2)

Text

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APPENDIX A NOTICE OF VIOLATION Portland General Electric Company Docket No. 50-344

. Trojan Nuclear Plant License No. NPF-1 As a result of the inspection conducted during the period of January 4 through 22, 1988, and in accordance with the NRC Enforcement Policy.10 CFR Part 2 ^

Appendix C, the following violation was identified:

Plant Technical Specification 4.0.5 provides requirements for periodic inservice testing and states in part that, "Inservice... testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME boiler and pressure vessel code..."

To meet the surveillance requirements of ASME Section XI, the fourth sentence of paragraph 6.1.4.2 (pumps) of PET-9-4 (Revision 7) states, ,

"The plant test engineer or designee shall review the test to determine the need for increased frequency of testing on the alert list," and the last sentence of paragraph 6.2 (valves) states, "IST-related parameters i shall be compared to the data (from the most recent, previous data) for each valve, and will be used to determine the ultimate operability of

that valve." l f

Contrary to the above, data sheet POT-5-1-DA for POT-5-1 auxiliary .

feedwater system testing performed on December 23, 1987, was filed in  !

the licensee's records vault without a plant test engineer signature and t M applicable IST data had not been reviewed and logged in the assouated 1987 IST pump and valve data log for procedure data sheet POT-5-1-DA/DB. Members of the ASME surveillance and testing group were unable to verify that they had reviewed data sheet POT-5-1-DA data to deterinine if increase testing was required or had compared the December 23, 1987, data to the most recent previous data.  ;

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

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

Nuclear Regulatory Comission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the ,

NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply 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 have been 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 1

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Notice, an order may be issued to show cause why the license should not be l modified, suspended, or revoked or why such action as may be proper should not be taken. Consideration may be given to extending your response time for

, good cause shown.

FOR THE NUCLEAR REGULATORY COPHISSION Vf obert J. Pa e Chief dY l Reactor Safety Branch e Dated at Walnut Creek, California this rf H day of(e vi och1988ys ,

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