ML20238A690

Notice of Violation from Insp on 870713-0806.Violation Noted:Failure to Identify Deficient Conditions,Failure to Evaluate Test Results & Failure to Perform Testing to Incorporate Requirements of Design Documents

ML20238A690
Person / Time
Site:	Braidwood
Issue date:	08/25/1987
From:	Hehl C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20238A682	List: IR 05000456/1987025 ML20238A679 ML20238A690
References
50-456-87-25, NUDOCS 8708310173
Download: ML20238A690 (1)

Text

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4 NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-456 ,

As a result of the inspection conducted on July 13 through August 6, 1987, and in accordance with the General Policy and Procedure for NRC Enforcement Action, (10 CFR Part 2, Appendix C), the following violations were identified:

1. N1. 10 CFR 50, Appendix B, Criterion XI, " Test Control," as implemented by the Commonwealth Edison Quality Assurance Manual and the Braidwood Startup Manual, requires that a testing program be established and that test results be documented and evaluated to ensure that the test requirements have been satisfied.

Contrary to the above, the test requirements of BwSU RC-33, " Reactor Coolant System Leak Test," were not accurately demonstrated to have been 1 l

satisfied because of an inaccurate startup test deficiency resolution which resulted in an incorrect calculation of the Reactor Coolant System leakage (456/87025-05).

This is a Severity Level V violation (Supplement II). l

2. 10 CFR 50, Appendix B, Criterion IX, " Test Control," as implemented by the Commonwealth Edison Quality Assurance Manual and the Braidwood Startup Manual, requires that a test program be established to assure that testing required to demonstrate that systems will perform satisfactorily in service is performed in accordance with written test procedures which incorporate the requirements of applicable design documents. I Contrary to the above, the licensee's test control program did not assure that the applicable design requirements of the Reactor Protection System were incorporated into startup test procedure BwSU RP-30. BwSU RP-30 as written and performed was not consistent with the basic design of the l Train 2 Undervoltage Diode and Output Module. As a result, BwSU RP-30 as originally performed did not demonstrate the proper performance of the i Reactor Protection System (456/87025-09). l This is a Severity Level V violation (Supplement II).

l Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this l office within thirty days of the date of this Notice a written statement or j explanation in reply, including for each item of violation: (1) corrective l

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. l Consideration may be given to extending your response time for good cause shown.

/fqpsd 3 Si l W 7 /

Dateo C. W. Wehl, Chief  ;

Operations Brane,n i 8708310173 870825 PDR ADOCK 05000456

.. G PDR

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