ML20236B656

Notice of Violation from Insp on 870831-1014.Violations Noted:Thermal Overload Protection for Valve 1FP079 Not Bypassed Continuously for Period in Excess of 8 H & Affected Valve Not Declared Inoperable

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: IR 05000461/1987032 ML20236B640 ML20236B656
References
50-461-87-32, NUDOCS 8710260285
Download: ML20236B656 (2)

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NOTICE OF VIOLATION l Illinois Power Company License No. NPF-62 i

As a result of the inspection conducted on August 31 through October 14, 1987, j and in accordance with the " General Policy and Procedure for NRC Enforcement i 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: ,

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• On August 17, August 28 and possibly July 18, 1987, control rods were withdrawn in OPERATING CONDITION 1 without a channel functional test of a the Rod Pattern Control System Rod Withdrawal Limiter High Power Setpoint being :anducted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 i hours without a grab sample being taken in accordance with Technical 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)).  !

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• 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

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