ML20213G974
| ML20213G974 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/11/1987 |
| From: | Norelius C NRC |
| To: | |
| Shared Package | |
| ML20213G960 | List: |
| References | |
| 50-373-87-11, 50-374-87-12, NUDOCS 8705190069 | |
| Download: ML20213G974 (2) | |
Text
F I,
P NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-373 Docket No. 50-374 As a result of the inspection conducted on March 10 through April 20, 1987, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1985), the following violations were identified:
1.
Technical Specification 6.2.A states, in part, " Detailed written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:
The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, Revision 2 February 1978."
Appendix A of Regulatory Guide 1.33 includes procedures for operation of the Fuel Pool Cooling System.
Contrary to the above on March 18, 1987, procedure LOP-FC-03, " Fuel Pool Cooling System Startup, Operation, and Level Changes of the Fuel Pool Skimmer Surge Tank," was not reviewed or adhered to by personnel performing the evolution resulting in manipulation of a wrong valve which caused a loss of approximately 100 gallons of contaminated water into the Unit ? reactor building and reactor building ventilation.
This is a Severity Level IV violation (Supplement I).
2.
Technical Specification 3.3.la, Table 3.3.1-1(a), states that for the reactor protection system inrtrumentation chantels, with the number of operable channels less than required, place the inoperable channels in the tripped condition within two hours during the required surveillance.
Technical Specification 3.3.2b, Table 3.3.2-1(b), states that for the Primary and Secondary Containment isolation actuation instrumentation channels, with the number of operable channels less than required, place the operable chanw l in the tripped condition within two hours during required surveillaace.
Contrary to the above, on April 2, 1987, while performing surveillance LIS-RP-08, " Primary Containment High Pressure Scram and Secondary Containment Isolation Response Time Test," the High Primary Containment Pressure switch, IC71-N002A, was inoperable for 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (which made the number of operable channels less than required) without placing channel Al in the tripped condition within two hours.
This is a Severity Level IV violation (Supplement I).
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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) 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.
Modw S.M M Dated Charles E. Norelius, Director Division of Reactor Projects k