ML20126B923

Notice of Violation from Insp on 841221-850430

ML20126B923
Person / Time
Site:	Dresden
Issue date:	06/06/1985
From:	Harrison J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20126B907	List: IR 05000237/1984027 ML20126B905 ML20126B923
References
50-237-84-27, 50-249-85-13, IEB-79-14, NUDOCS 8506140249
Download: ML20126B923 (2)

Text

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Appendix NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos.60-237; $0-249 l Dresden 2 and 3 Licenses No. OPR-19; DPR-25 l

l l As a result of the inspection conducted on December 21, 1984, through

! April 30, 1985, and in accordance with the General Policy and Procedures I

for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violations were identified:

1. 10 CFR 50, Appendix 8, Criterion X, as implemented by Ceco Topical Report CE-1-A,'" Quality Assurance Program for Nuclear Generating Stations," and Ceco Corporate Quality Assurance Manual, Nuclear Generating Stations, Quality Requirements, requires the licensee to establish and execute an inspection program to verify activities affecting quality are in conformance with documented instructions, procedures, and drawings.

l Contrary to the above, piping suspension system hardware r.iodifications that resulted from the Mark 1 program reviews, IE Bulletin 79 14 verifications, and the improvements in configuration made to the main steam safety relief valve discharge piping were not adequately inspected to verify that piping restraint component location, orientation, and configuration were in conformance with design documents (237/84027 01; 249/85013-01).

This is a Severity Level IV violation (Supplement !!).

2. 10 CFR 50, Appendix B, Criterion !!!, as implemented by Ceco Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating Stations," and Ceco Corporate Quality Assurance Manual, Nuclear Generating Stations, Quality Requirements, requires that design control measures provide for verifying or checking the adequacy of design, such as by the performance of design review.

Contrary to the above, the Nutech piping transient operability analysis performed for the Dresden 2 Low Pressure Coolant Injection System did notgiveproperconsiderationtodesignobjectives,justifythecriteria established and assumptions made, and correctly model the forces experienced during the transient. Nutech's recommendation to replace the failed snubber with a rigid restraint did not consider the potential adverse consequences on the piping. (237/84027 04).

This is a severity Level IV violation (Supplement !!).

l

Appendix 2 Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violation; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

JUN 6 1985 /)b Dated J.'J. Harrison, Chief Engineering Branch ,