ML20149F022
| ML20149F022 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/17/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20149F020 | List: |
| References | |
| 50-373-97-08, 50-373-97-8, 50-374-97-08, 50-374-97-8, NUDOCS 9707220007 | |
| Download: ML20149F022 (1) | |
Text
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NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-373;50-374 LaSalle County Station License Nos. NPF-11; NPF-18 During an NRC inspection conducted on April 28,1997, through June 20,1997,a violation of NRC requirements was identified in accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
LaSalle Technical Specification 6.1.C.7 requires that the amount of overtime worked by unit staff members performing safety-related functions shall be limited and controlled in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).
Generic Letter 82-12, " Nuclear Power Plant Staff Working Hours," dated June 15, 1985, and LaSalle Administrative Procedure (LAP) 100-17, " Overtime Guidelines For Personnel That Perform Safety-Related Functions," Revision 10, dated June 19, 1996, state, in part, that a break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods (including shift turnover time), and in the event that very unusual circumstances arise which may require deviation from the above guidelines, such deviation shall be authorized by the plant manager or his deputy, or higher levels of I
management.
Contrary to the above, on April 29,1997, a test engineer conducting residual heat removal service water system post-modification testing, a safety-related function, returned to work without a break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> between work periods (including shift turnover time) without written approval, as required by Technical i
Specification 6.1.C.7 (50-373/97008-01; 50-374/97008-01).
This is a Severity Level IV violation (Supplement 1).
The inspection showed that steps have been taken to correct the identified violation to prevent recurrence. Consequently, no reply to the violation is required and we have no further questions regarding this matter.
Dated at Lisle, lilinois this 17th day of July 1997 5
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9707220007 970717 PDR ADOCK 05000373 G
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