ML20213D160
| ML20213D160 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/29/1986 |
| From: | Guldemond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20213D150 | List: |
| References | |
| 50-374-86-36, NUDOCS 8611100446 | |
| Download: ML20213D160 (2) | |
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NOTICE OF VIOLATION Conmonwealth Edison Company Docket No. 50-374 As a result of the inspection conducted on September 3 through October 7, 1986, 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 3.3.7.4 requires remote shutdown instrumentation to be operable with readouts displayed in the remote shutdown panel external to the control room. The reouired Instrumentation included the Residual Heat Removal (RHR) service water temperature. With any of the required monitoring instrumentation inoperable, the instrumentation shall be restored to operable status within seven days or the plant shall be in at least hot shutdown within the next twelve hours.
Contrary to the above, on September 16, 1986, the reactor was not in at least hot shutdown nor was the RHR service water temperature indicator on the remote shutdown panel operable, seven days after the indicator had been made inoperable on September 9,1986.
This is considered a Severity Level IV violation (Supplement I).
2.
10 CFR 50 Appendix B, Criteria V, Instructions, Procedures, and Drawings requires that activities affecting quality shall be prescribed by... procedures... appropriate to the circumstances.
Contrary to the above, on September 17, 1986, the control room annun'ciator alarm procedure LOA 2H13-P601 C301, " Residual Heat Removal Heat Exchanger Discharge Cooling Water Heat Exchanger A/8 1
f Temperature Hi," was found not to be appropriate in that, it did not include.i reference to Technical Specification 3.3.7.4 Limiting l
Condition for Ooeration for remote shutdown monitoring instrumentation, of which the RHA Hx service water discharge temperature indication is a part.
This is a Severity Level IV violation (Supplement I).
3.
Technical Specification 6.2.A.1 states, " Detailed written procedures shall be prepared, approved and adhered to for applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978." Regulatory Guide 1.33, Appendix A, includes procedures for the control of equipment.
LaSalle's administrative' procedures for the control of equipment includes procedure lap 1300-1, " Work Request," which states, "The Shift Engineer shall review Technical Specification requirements and verify that equipment can be removed from service and is not required to be operable."
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Contrary to the above, on September 9,1986, the Shift Engineer failed to review the Technical Specification requirements section of the work request before removing the equipment from service.
The related Tecnnical Specification, section 3.3.7.4, had a seven day Limiting Condition for Operation time clock which was exceeded.
This is a Severity Level IV violation (Supplement I).
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.
OCT 2 91986
{0 -2 f-f6 Dated W&'Gf Gd146mond, Chief Reactor Projects Branch 2 1
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