ML20234D248

Notice of Violation from Insp on 870810-17.Violation Noted: Licensee Failed to Apply QA Program to Provide Control Over Activities Affecting Quality of Sys Consistent W/Importance to Safety

ML20234D248
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	09/15/1987
From:	Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20234D179	List: ML20234D177 ML20234D248 ML20234D253
References
50-454-87-32, 50-455-87-30, 50-456-87-28, NUDOCS 8709220023
Download: ML20234D248 (1)

Text

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NOTICE OF VIOLATION Commonwealth Edison Company Byron, Unit 1 Docket No. 50-454 Byron, Unit 2 Docket No. 50-455 Braidwood, Unit 1 Docket No. 50-456 As a result of the inspection conducted on August 10-17,1987, and in l accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1985), the following violations were identified: ,

10 CFR 50, Appendix B, Criterion II, requires a quality assurance program be implemented to provide control over activities affecting the quality of systems (i.e. Emergency Operating Procedures) consistent with their importance  ;

to safety.

Contrary to the above, the licensee failed to apply a QA program to provide control over activities affecting the quality of systems (i.e. Emergency Operating Procedures) consistent with their importance to safety. . The Byron and Braidwood Generating Stations failed to ensure that the final printed revision of the E0Ps matched the approved draft document and that all of the l consequences of adding and deleting steps in the E0Ps had been fully examined.

Specific examples are as follows:

1. In 1BwFR-S.1, " Response to Nuclear Power Generation /ATWS," pages.9 and 10 were duplicates of pages 7 and 8. (Braidwood)

2. In step 14 of 18wFR-S.1 and BFR-S.1, the Response Not Obtained column returns the operator to step 6 (Steam Dump Isolation) vice step 4 i (Initiate Emergency Boration of RCS) as required by the Westinghouse. 4 Emergency Response Guidelines. (Byron and Braidwood). l This is a Severity Level IV violation (Supplement I)

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)correctiveaction taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.

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

hf) f g Dated Hubert J. Miller, Director Division of Reactor Safety

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hNOch G

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