ML17180A977

From kanterella
Revision as of 18:29, 8 January 2025 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Notice of Violation from Insp on 940815-0916.Violation Noted:Post Mod Test for Mod P12-3-93-614 Used Unverified Acceptance Criteria Greater than Limits Specified.Post Mod Test for Mod M12-0-90-025 Did Not Verify Relay Contacts
ML17180A977
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 10/21/1994
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17180A976 List:
References
50-237-94-16, 50-249-94-16, NUDOCS 9410260098
Download: ML17180A977 (1)


Text

.*

NOTICE OF VIOLATION Commonwealth.Edison Company Dresden Nuclear Power Station Units 2 and 3 Docket Nos. 50-237; 50-249 Licenses No. DPR-19; No. DPR-25 During an NRC inspection conducted August 15 through September 16, 1994, violations of NRC requirements were identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions, 11 10 CFR Part 2, Appendix C, the violation is listed below:

10 CFR 50, Appendix B, Criterion XI, states, in part, that a test program shall be established to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.

Contrary to the above, prior to September 16, 1994, the team noted that:

a.

The post modification test for Modification P12-3-93-614 used unverified acceptance criteria (+/- 6°F) that was greater than the limits specified in applicable design documents (+/- 5°F).

b.

The post modification test for Modification M12-0-90-025 did not verify j

four standby gas treatment relay contacts would perform satisfactorily in service, in that, other parallel relay contacts were actuated during

/ 1 the test.that performed the same fun~tion.

~

This is a Severity Level IV violation (Supplement 1).

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

Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, D.C.

20555 with a copy to the Regional Administrator, Region Ill, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (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, or, if contested, the basis for disputing the viol~tion, (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 or a Demand for Information 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.

Where good cause is shown, consideration will be given to extending the response time.

Dated at Lislel Illinois, this

?, / -~t day of October 1994 9410260098 941021 PDR ADOCK 05000237 G

"PDR