ML20237D591

Notice of Violation from Insp on 871104-1201.Violation Noted:Capacitors Connected in Parallel W/Relay Coil Located in Both Unit 1 Emergency Diesel Generator Control Panels & Not Shown on Facility Electrical Drawings

ML20237D591
Person / Time
Site:	Comanche Peak
Issue date:	12/16/1987
From:	Warnick R NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20237D587	List: IR 05000445/1987030 ML20237D585 ML20237D591
References
50-445-87-30, 50-446-87-22, NUDOCS 8712240061
Download: ML20237D591 (2)

Text

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t.y APPENDIX A NOTICE-OF. VIOLATION. 1 TU Electric Dockets: 50-445/87-30 50-446/87-22 Comanche' Peak Steam Electric Station Permits: CPPR-126 Units l'and 2,1 Glen' Rose, Texas CPPR-127

.During an NRC inspection conducted on' November 4 through-December 1, 1987," violations of NRC requirements were identified.

In accordance with the'" General Statement of Policy and Procedure i for'NRC' Enforcement Actions," 10 CFR Part.'2, Appendix C.(1987), the' i

. violations are listed-below:

A.: Criterion III of Appendix B to 10 CFR Part 50- as implemented ,

by Section 3.0, Revision 3, dated July 31, 1984, of the j TU' Electric Quality Assurance Plan (QAP), requires in part, i that measures must be established to assure.that applicable j regulatory requirements and design bases, as defined in I Part 50i2.and as specified in the license application, for those structures, systems and components to which this appendix applies, are. correctly translated into specifica-tions, drawings, procedures, and instructions. The design control measures must provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by:the use of alternate or simplified calculational methods, or by the. performance of a suitable testing program.

In addition, design changes, including field changes, must be ,

subject to design control measures commensurate with those l applied'to the original design.

Contrary to the above, the NRC inspector identified two capacitors' connected in parallel with a relay coil located in both Unit 1 emergency diesel generator control panels that were not shown on facility electrical drawings nor described in any associated documents.

i This is a Severity Level IV violation (Supplement II)

(445/8730-V-06).

B.. Criterion V of Appendix B to 10 CFR Part 50, as implemented by Section 5.0, Revision.3 of the TU Electric QAP dated July 31, l- 1984, requires that activities affecting quality shall-be prescribed by and accomplished in accordance with documented instructions, procedures, or drawings of a type appropriate to the circumstances.

8712240061 871216 PDR ADDCK 05000445 Q POR b___ _ _ __ _

2 Paragraph 2.1.3 of TNE Procedure TNE-DC-7, Revision 16,-dated February 14, 1986, " Preparation and Review of Design Drawings," requires that completed drawings shall be checked for accuracy and compliance. Paragraph 2.1.4 also requires an engineering review for technical accuracy upon completion of the drafting / design check.

Contrary to the above, drawings were not appropriately reviewed / checked for accuracy as evidenced by the differences which existed between the two sets of electrical sc'aematic drawings for the emergency diesel generator control panels.

Examples of these differences were most evident in the circuitry for solenoids 6A and 6B and relay contact numbers and arrangements (i.e., RX/1B and 10X) on Drawings 09-500-76001, Sheet 3 and TNE-El-0067, Sheet 96.

This is a Severity Level IV violation (Supplement II)

(445-8730-V-07).

Pursuant to the provisions of 10 CFR 2.201, TU Electric is hereby s required to submit a written statement or explanation to the U. S. g Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Assistant Director for Inspection Programs, Comanche Peak Project Division, Office of  ;

Special Projects, within 30 days of the date of the letter I

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 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.

FOR THE NUCLEAR REGULATORY COMMISSION SYf OdAnt4$k',

Dated at Comanche Peak Site this 16th day of Dectnber, 1987

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