ML20236B656
| ML20236B656 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/21/1987 |
| From: | Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236B642 | List: |
| References | |
| 50-461-87-32, NUDOCS 8710260285 | |
| Download: ML20236B656 (2) | |
Text
1
.j l'
Illinois Power Company License No. NPF-62 i
As a result of the inspection conducted on August 31 through October 14, 1987, j
i and in accordance with the " General Policy and Procedure for NRC Enforcement Actions",10 CFR Part 2, Appendix C (1985), the following violation was ideotified:
j
(
Technical Specification 3.0.1 requires compliance with the Limiting Conditions l
for Operation - except that upon failure to meet the Limiting Conditions for 1
Operation, the associated ACTION requirements shall be met.
Technical Specification 4.0.3 states, in part, that failure to perform a surveillance 1
requirement within the specified time interval shall constitute a failure A
to meet the OPERABILITY requirements for a Limiting Condition for Operation.
I l
Contrary to the above:
i On August 17, August 28 and possibly July 18, 1987, control rods were withdrawn in OPERATING CONDITION 1 without a channel functional test of a
the Rod Pattern Control System Rod Withdrawal Limiter High Power Setpoint being :anducted within one hour prior to control rod movement unless perfotmed within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by Technical j
Specification Table 4.3.6-1 Item 1.b. Note (c) (461/87032-01A(DRP)).
On September 11 and 12, 1987, thermal overload protection for Valve 1FP079 was not bypassed continuously for a period in excess of eight hours and the affected valve was not declared inoperable in accordance with Technical Specification 3.8.4.2. (461/87032-01B(DRP)).
Between September 3 and 16, 1987, the weekly sample analysis of Process Radiation Monitor ORIX-PR001 required by Technical Specification Table 4.11.2-1 Item C was not performed and the channel was not declared inoperable (461/87032-01C(DRP)).
On September 23, 1987, both trains of main condenser offgas treatment system hydrogen monitors were inoperable for a period of more than four hours without a grab sample being taken in accordance with Technical i
Specification Table 3.3.7.12-1 Item 3.a ACTION 124 (461/87032-01D(DRP)).
On September 29, 1987, the AC offsite power sources were not demonstrated OPERABLE for a period of greater than eight hours j
with the 18 diesel generator inoperable as required by Technical J
Specification 3.8.1.1 ACTION b (461/87032-01E(DRP)).
i 87102602g5 973ng3s gDR ADOCK 05000461 PDR Id
1 l
1 p.
la Notice of Violation 2
g Between September 25 and 30, 1987, a period of greater than 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s-elapsed without verifying the seal leakage rate on primary containment Elevation 737' air lock doors as required by Technical f
Specification 4.6.1.3.a.1 (461/87032-01F(DRP)).
i This is a Severity Levei IV violation (Supplement I) (461/87032-01(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 i
explanation in yeply, including for each violation:
(1) corrective action 1
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.
I MI 2 I U" k
pb Dated W. T.
-orney, Chief "
l Reactor Projects Branch 1 s
l