ML17201J375
| ML17201J375 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/29/1988 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17201J374 | List: |
| References | |
| 50-237-88-11, 50-249-88-13, NUDOCS 8808050223 | |
| Download: ML17201J375 (2) | |
Text
Appendix NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-237 Docket No. 50-249 As a result of the inspection conducted on May 10 through July 13, 1988, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, "10 CFR Part 2, Appendix C" (1987), the following violations were identified:
A.
10 CFR 50, Appendix B, Criterion XVI, as implemented by CECo Topical Report CE-1-A, "Quality Assurance Program for Nuclear Generating Stations", and CECo Corporate Quality Assurance Manual, Nuclear Generating Stations, "Quality Requirement Section 16.0", requires that corrective actions identified from nonconformances, incidents and deviations are verified for satisfactory completion to preclude repetition.
Contrary to the above, the corrective actions taken to resolve a previous violation involving the control of rigging activities were not timely enough or effective in preventing further chainfall rigging violations.
This is a Severity Level V violation (Supplement I).
B.
10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, requires, in part, that primary reactor containment leak tests for Type B and C tests be performed during reactor shutdown for refueling, but, in no case at intervals greater than two years.
Contrary to the above, Unit 3 reactor operated from September 27, 1987 to January 5, 1988, with approximately 41 Type B and C, Local Leak Rate Test surveillance intervals in excess of the two year Appendix J testing requirement.
Thus, the integrity of the primary containment was not adequately being demonstrated throughout this period, such that, the allowable operational primary containment leakage rate was verifiable to the technical specification acceptance criteria.
This is a Severity Level IV violation (Supplement I).
With respect to item B, the inspection showed that action had been taken to correct the identified violation and to prevent recurrence.
Consequently, no reply to the violation is required and we have no further questions regarding this matter.
With respect to item A, pursuant to the provisions of 10 CFR 8808050223 880729 PDR ADOCK 05000237 Q
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) corrective action 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.
Edwar
~reeman,o; rector Division of Reactor Projects
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