ML20237G964

Notice of Violation from Insp on 870615-25.Violation Noted: Failure to Perform Proper Insp of Location & Routing of Approx 1,110 safety-related Cables Installed During 1983- 1985

ML20237G964
Person / Time
Site:	Rancho Seco
Issue date:	07/30/1987
From:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20237G963	List: IR 05000312/1987021 ML20237G960 ML20237G964
References
50-312-87-21, NUDOCS 8708170003
Download: ML20237G964 (2)

Text

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, i APPENDIX A NOTICE OF VIOLATION Sacramento Municipal Utility District Docket No. 50-312 1 Rancho Seco Nuclear Generating Station License No. DPR-54 1

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During an NRC inspection conducted on June.15-25, 1987, a violation of NRC -

requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,'l 10 CFR Part 2, Appendix C (1987), the violation is listed below:

A. 10 CFR 50 Appendix,"B" Criterion X requires that a program for inspection of activities affecting quality shall be established and executed to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity and that the inspections shall be performed by individuals other than those who performed _the activity being inspected. NRC letter from R. W. Reid to J. J. Mattimoe.(SMUD) dated December 13, 1976, confirmed SMUD's September 23, 1976,' letter to the NRC stating that SMUD's Quality Assurance (QA) Program for plant operations at Rancho Seco complied with the guidance contained in the WASH document No. 1284, " Guidance on Quality Assurance Requirements During the Operation Phase of Nuclear Power Plants", dated October 26, 1973. WASH 1284 specifies NRC Safety Guide 30, August 11, 1972, and ANSI 3 N45.2.4-1972 (IEEE Std 336-1971),'" Installation,. Inspection, and Testing  !

Requirements for Instrumentation and Electric Equipment During the l l Construction of Nuclear Power Generating Stations" for QA requirement l l for the installation, inspection, and testing of instrumentation and -

l electric equipment. ANSI N45.2.4-1972 Paragraph 5.1.1 requires that d

" Inspections shall be made to verify that equipment is being located, installed, assembled, and/or connected to comply with latest approved-for-construction drawing, manufacturers instructions, and ~

installation specifications. Such inspections shall include, as l

appropriate, verification of: . . .. (3) proper location and routing of I

cables and sensing lines."

Contrary to these requirements, independent inspection for proper location and routing of approximately 1100 safety-related cables installed during the 1983 to 1985 timeframe was not performed. Of those cable:,, 10 power / control cables intermixed with instrumentation cables and 14 cables violating Appendix "R" separation criteria have been  ;

identified to date from a sample of approximately 247 cables. '

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

1 Pursuant to the provisions of 10 CFR 2.201, Sacramento Municipal Utility District is hereby required to submit a written statement or explanation to the U. S. Nuclear Regulatory Commission, ATTN: Doceaent Control Desk, Washington, DC 20555 with a copy to the Regional Administrator. Region V, and a copy to the @C Resident Inspector, Rancho Seco, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked -

as a " Reply tc a Notice of Violation" and should inc'lude for each violation:

(1) the reason for the violation if admitted, (2) the corrective steps that 8708170003 970730 PDR ADOCK 05000312 q PDR

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1 have been taken and the results achieved, (3) the corrective steps that will l be taken to avoid further violations, and (4) the date when full compliance i 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 l 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.

FOR THE NUCLEAR REGULATORY COMMISSION he D. F. Kirsch, Director Division of Reactor Safety and Projects )

, j Dated at Walnut Creek, California this '. day 'of - - - 1987 l

'JUL 3 01987

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