ML20034A666
| ML20034A666 | |
| Person / Time | |
|---|---|
| Site: | Clinton |
| Issue date: | 04/13/1990 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20034A663 | List: |
| References | |
| 50-461-90-02, NUDOCS 9004240078 | |
| Download: ML20034A666 (1) | |
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Docket No. 50-461 i
Illinois Power Company Clinton Power Station License No. NPF-62 l'
As a result of the inspection. conducted from February 26 through March 6,1990.
and in accordance with the " General Policy and Procedures for NRC Enforcement'.
Actions," 10 CFR Part 2, Appendix C'(1988), the following violation was identified:
10 CFR 50.59 (a)(1) allowed licensees to make changes to the facility as-described in the Safety Analysis Report without prior NRC approval, provided that the change did not require a change to the Technical Specification, or involve an unreviewed safety question.
A proposed change shall be deemed to involve an unreviewed safety question if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased.-
The Clinton Updated Safety Analysis Report, Sections 11.2.1.5.1 and 11.2.1.6 specified that all radwaste system tanks have both monitoring and high level annunciation which are used to control tank levels.
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CPS Procedure No. 3909.03, " Operating Waste Sludge System," Revision 11, dated December 19, 1988, describes methods for controlling the levels of radwaste sludge tanks.
Contrary to the above, on December 19, 1988, CPS Procedure No. 3909.03 was revised to allow the use of administrative methods for controlling liquid l-radwaste sludge tank levels, vice the installed level indicators and' l
annunciators, without performing a review to determine if the non utilization l
of these level indicators and annunciators constituted an unreviewed safety question.
This is a Severity Level IV violation (Supplement I).. (461/90002-01(DRP))
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 explanatioh in reply, including for each violation:
(1) corrective action.
I 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.
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Dated Edward G. Greenman, Director Division of Reactor Projects
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