ML17321A917
| ML17321A917 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/16/1985 |
| From: | Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17321A916 | List: |
| References | |
| 50-315-85-26, 50-316-85-26, NUDOCS 8510210180 | |
| Download: ML17321A917 (4) | |
Text
~Aendix NOTICE OF VIOLATION American Electric Power Service Corporation Indiana and Michigan Electric Company Donald C.
Cook - Units I and 2
Docket No. 50-315 Docket No. 50-316 As a result of the inspection conducted on September 4-20,
- 1985, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violations were identified:
l.
10 CFR 50, Appendix B, Criterion XVII, as implemented by the D. C.
Cook Operations equality Assurance
- Program, requires that records be maintained to furnish evidence of activities affecting quality.
Contrary to the above, the licensee failed to provide for appropriate protection of special process records as required by PMI 2040, Revision 5, Paragraph 3.20.
This is a Severity Level V violation (Supplement I).
2.
10 CFR 50, Appendix B, Criterion XVI, as implemented by the D.
C.
Cook Operations equality Assurance
- Program, requires that measures be established to ensure that conditions adverse to quality are promptly identified and corrected.
Contrary to the above, the initial disposition of Condition Reports No. 12-12-83-1342 and No. 2-04-84-493 and the subsequent action by the Nuclear Safety and Design Review Committee to effect corrective action were incomplete, in that the resolutions did not address interim measures to preclude recur rence of the deficiencies prior to implementation of final corrective action.
This is a Severity Level IV violation (Supplement I).
3.
10 CFR 50, Appendix B, Criterion II, as implemented by the D. C.
Cook Operations equality Assurance
- Program, requires that control be provided over activities affecting the quality of identified structures, systems and components to an extent consistent with their importance to safety.
Contrary to the above, numerous inprocess design changes were not properly controlled to ensure timely completion of the required reviews, evaluations and other related activities.
This is a Severity Level IV violation (Supplement I).
asi02iOi80 50003i5 I';
. qDocv. 0 8
pt
~ I Appendix 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 expIanation in repIy, incIuding for each vioIation:
(1) corrective action taken and the resuIts achieved; (2) corrective action to be taken to avoid further noncompIiance; and (3) the date when fu11 compIiance wi11 be achieved.
Consideration may be given to extending your response time for good cause shown.
Date
/E ii/Z~
ap
)e o,
)e Division of Reactor Safety