ML17328A132
| ML17328A132 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/05/1989 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17328A131 | List: |
| References | |
| 50-315-89-22, 50-316-89-22, NUDOCS 8909120262 | |
| Download: ML17328A132 (2) | |
Text
NOTICE OF VIOLATION Indiana Michigan Power Company D.C.
Cook Nuclear Power Station Docket Nos.
50-315; 50-316 Licenses No.
DPR-58 DPR-74 As a result of the inspection conducted on July 10 through August 15, 1989, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy
'nd Procedure for NRC Enforcement Actions (1988),
the following violations were identified';
l.
10 CFR 50, Appendix B, Criterion V, as implemented by the D.C.
Cook Operations equality Assurance Program requires that activities affecting quality shall be accomplished in accordance with prescribed procedures.
Contrary to the above, as required by D.C.
Cook Procedure PMI-7030, Paragraph 4.5. 1, a Condition Report was not initiated when design deficiencies were discovered for pipe supports 1-GFW-L812, l-ACA-R911, 1-ACA-R910, l-ACCW-R924, and 1-GCCW-L181 (315/89002-01; 316/89022-01).
This is a Severity Level IV violation (Supplement 1) 2.
. 10 CFR 50, Appendix B, Criterion III, as implemented by the D.C.
Cook Operations equality Assurance Program requires that measures be established to check and verify the design.
Contrary to the above, the design was not adequa'tely checked and verified in that:
a.
For pipe support 1-CCW-L181, the bending stress in the redesigned support was not evaluated (315/89022-03A; 316/89022-03A).
b.
For pipe support 1-CS-R541, two of four load vectors on the support were not evaluated (315/89022-03B; 316/89022-03B).
This is a Severity Level IY violation (Supplement 1).
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) the corrective actions that have been taken and the results, achieved; (2) the corrective actions that will be taken to.avoid further viol.ations; and (3) the date when full compliance will'e achieved.
Consideration may be given to extending your response time for good cause shown.
Da ed ert s
er, erector Division of Reactor Safety
I