ML20245E676

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Notice of Violation from Insp on 890326-0513.Violation Noted:Plant Entered Mode 2 During Scheduled Shutdown in Preparation for 1989 Refueling Outage,But Did Not Record Event in Control Room Log Until 890414
ML20245E676
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 06/05/1989
From: Mendonca M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20245E670 List:
References
50-344-89-10, NUDOCS 8906270379
Download: ML20245E676 (2)


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, APPENDIX A NOTICE OF VIOLATION Portland General Electric Company Docket No. 50-344 Trojan Nuclear Plant License No. NPF-1 D'uring an NRC inspection conducted from March 26, 1989 through May 13, 1989, two violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violations are listed below:

A. Technical Specification 4.0.5. requires, in part, inservice testing of ASME Code Class 1, 2, and 3 pumps in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda.

In implementation of this requirement, Licensee Topical Report PGE-1048 states that the requirements of the 1983 edition through Summer 1983 addenda of Section XI will be implemented.

Paragraph.IWP-4110 of Section XI, 1983 edition through Summer 1983 addenda, requires an instrument accuracy of plus or minus five percent of (uil scale for the measurement of vibration amplitude.

Contrary to the above, on March 23, 1989, measurement of vibration amplitude was performed for inservice. testing of the "A" Containment Spray Pump with instrument T-5410, which had an accuracy of less than plus or minus five percent of full scale.

l This is a Severity Level IV violation (Supplement I).

B. 10 CFR Part 50, Appendix B, Criterion V, states in part: " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."

Administrative Order A0-3-6, titled " Conduct of Operations-Shift Records," Revision 17, dated March 3, 1988, requires, in part, that control room log entries shall include entry into a different mode.

Contrary to .the above, on April 6,1989, the plant entered Mode 2 during l the scheduled shutdown in preparation for the 1989 Refueling Outage; i however, the entry into Mode 2 was not recorded in the control room log until April 14, 1989.

This is a Severity Level.V violation (Supplement I).

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1(1 ' Pursuant to the' provisions.of 10 CFR'2.201, Portland General Electric Company-Lis hereby required-to submit a written statement of explanation to .the U.S.'

a.." Nuclear Regulatory Commission, ATTN: . Document Control Desk, Washington, DC 20555.with a copy to theLRegional Administrator, Region V, and a copy to the NRC Senior Resident Inspector, Trojan, within-30. days of the date of the m

letter l transmitting this Notice. This reply should be clearly marked as:a-

" Reply to a Notir -of. Violation". and should include for each violation: '(1)'

e' .the reason for the violation if admitted, (2) the corrective; steps that have d-

'been taken.and the results achievsd, (3).the corrective steps that will be r taken to avoid further violations, and.(4) the date'when full compliance will id . 'be achieved. If'an' adequate' reply is not received within the time.specified

'1" 61n this Notice, an order ma be issued to show cause'why'the license should f Enot'be modified,' suspended,.or/ revoked or why such other action as may be proper should not be taken. , Con' sideration may be given to extending the 1 ,

. response time for good cause shown.

"'FOR THE NUCLEAR-REGULAT?RY COMMISSION

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3 M. M. Mendonca,' Acting Chief; Reactor Projects Branch o t Dated at Walnut Creek, California Lthis. d ay of June 1989 x

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