ML20010C304
| ML20010C304 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 08/04/1981 |
| From: | Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010C300 | List: |
| References | |
| 50-186-81-03, 50-186-81-3, NUDOCS 8108190334 | |
| Download: ML20010C304 (2) | |
Text
<3-Appendix A
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NOTICE OF VIOLATION Univirsity of Missouri Docket No. 50-186 As a result of the inspection conducted on May 18-22, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified:
1.
Technical Spe :ification 3.3.a requires that the si.gle instrument channel for Pressurizer High Pressure be operable to provide a safety system scram whenever the-reactor is operated.
-Contrary to the above, valve V599B was closed for a period of about 20 operating days isolating pressure switch PS939 which actuates the high pressure scram (Paragraph 9g).
This is a Severity Level IV violation (Supplement I).
2.
TechnicalSpecification4.2.crequireg/ min.
that the containment building leakage rate shall not exceed 16.3 ft (STP) with an overpressure of one pound per square inch gauge (psig) or 10% of contained volur.e over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period from an initial overpressure of 2 pounds per square inch gauge.
Contrary to the above, on February 23, 1981 a 3/4 inch containment l
test valve was found open and had been open for an undetermined period cf time, thus creating an open flow path from the containment building / min. at an overpressure of 1 psig (Paragraph 9e).
which wenld have caused the containment leak rate to exceed 16.3 ft This is a Severity Level IV violation (Supplement I).
3.
Technical Specification 5.4.a requires the semiannual calibration l
of all instruments required by the speci.gcations and Technical Specification 3.4.6 requires an operable cod run-in actuatica if the containment truck entry door is opened during reactor operation.
Contrary to the above, the test of the' truck entry door rod run-in function, Co.apliance Test CP-15, had not Lcen conducted since July 20, 1980 exceeding the semiannual test frequency.
This is a Severity Level VI violation (Supplement I).
810J190334 810808 PDR ADOCK 05000196 O
PDR o
A,pp.-ndix A *
'Tl e inspection showed that action had been taken to correct the identified i
items of noncompliance and 2o prevent recurrence.
Co'.sequently no reply to these items of noncompliance is required and we have no futher question regarding this matter.
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l, AugusL4, l981_____._
/A[L L-ate R. F. Ireishman, f(cting Director
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Division of Resident and
/g Project Inspection I
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