ML17174B139
| ML17174B139 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/11/1992 |
| From: | Greenman E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17174B138 | List: |
| References | |
| 50-237-91-39, 50-249-91-43, NUDOCS 9202180078 | |
| Download: ML17174B139 (2) | |
Text
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NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos.
50-237; 50-249 Dresden Nuclear Station Licenses No. DPR-1~; DPR-25 During an NRC inspection conducted on December 7, 1991, to January 17, 1992,
. violations of NRC requirements were identified.
In accordance with the "General S~atement.of Policy. and Procedure for NRC Enforcement Actions,"*
10 CFR Part 2, *Appen<fix C, (1991) the violations are *listed below:*
- 1.
Technical Specification 6.2.B.-requires that radiation conttol procedures* be maintained, made available to station personnel, and adhered.to.-
- -Procedure OAP 12-25, Revision I, "Radiation Work Permit-Program,"
- . states, in part,* that each worker. performing a job under. a Rad.iation Work Permit -(RWP) must follow the requirements of the RWP.
Contrary to the above, on December *s and 18, 1991,.workers did not follow the requirements of the RWP, as indicated by the examples listed below.
- a.
On December 5, 1991, a worker who was signed in on RWP 10559A,.
which only authorized operation of the turbine building overhead cranes, was found jogging in the reactor building.
- b.
On December 18, 1991, workers who were s*igned in on RWP 10609A; which only authorized work on control rod drive blades, shroud.
head bolts, and plugs for the recirculation suction line; moved fuel within the fuel pool.
This is a Severity Level IV violation (Supplement 1).
- 2.
Technical Specification 3.1.A.l requires that reactor protection system setpoints, and the minimum number of trip systems and minimum number of instrument*channels that must be operable shall be as given in Table 3.1.1. Table 3.1.l requires that two trip systems with two instrument channels each shall be operable for the main steam line high radiation trip function in all modes of operation and that the setpoint for this function be less than or equal to three times normal full power background.
Contrary to the above, on August 20, 1991, the setpoints in the "hydrogen addition on" mode were greater than three times normal full power background for both instrument channels of both trip systems, and the required actions were not performed.
This is a Severity Level IV violation (Supplement 1).
9202100078 92021-1-~.
PDR ADOCK 05000237.*
Cl PDR-.
With respect to item 1, the inspection showed that steps had been taken to correct the identified violation and to prevent recurrence. Consequently, no* * '
reply to this violation is required and we have no further questions regarding this matter. With re~pect to item 2, pursuant to the provisions.of 10 CFR 2.201, Conunonwealth Edison is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commhsion, ATTN:
Document Control Desk, Washington, D. C. 20555 with a copy to the U. S.
Nuclear Regulatory Conunission; Region III, 799 Roosevelt Road, Glen Ellyn, Illinois, 60137, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a AReply to a.. Notice of ViolationA and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Dated at Glen Ellyn, Illinois this //II.day of February, 1992 J:.,- Edward G. Greenman, Di rector,.
Division of Reactor Projects