ML20024G437
| ML20024G437 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/31/1972 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wachter L NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 9102120455 | |
| Download: ML20024G437 (3) | |
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I ATOMIC ENERGY COMMISSION i
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DIRCCTORATE OF REGULATORY OPERATIONS
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REGION 111
- 'Ur s O,4-799 ROOSEVELT ROAD yetg,goug GLEN ELLYN. ILLINOIS 6o137 Olt) 458-2660 July 31, 1972 c
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o Northern Statda Power Company Docktja,.50$63 C ATTN: Mr. Loo Wachter, Vico President peg g
Power Production and Systc.m yQ R
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o ninneapolis, Minnesota 55401 Centlemens This refers to the inspection conducted by l'essro. Ifaura and Johucon on July 12,1972, of operations at the Monticello plant authorized by AEC
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Operating Licenso No. DPR-22, and to the discuccion of our findings 1
held by the inspectors with Mosars. Scheinost, Larson, Clarity, and Dinvillo of your staff at the conclusion of the inspection.
/.rcas examined durinC this inspection included the reactor scrn:a of July 10, 1972, the equipnent performances during the sequence of eventa
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which followed, and corrective actions taken following the event. Within these arcas, the inspection consisted of selective examination of procedures and representativo records, intervievo with plant personnel, and observations by the inspector.
During this inspection it van found that one of your activitico arreared to bc in noncomplianco with AEC requiremento. The item and references to the pcrtinent requirmacnto are listed in the enclocure to this letter. Although we have confirmed that you have enken action to correct this iten, we requent that you provide us within 20 days, in writing, your corrents concerning the item, any steps that have bt m or will be taken to prevent recurrence, and tho dato all preventivo measures were or will be completed.
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2-July 31, 1972
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Horthorn States Power Company Should you have any questions concerning this inspection, we will be glad to discuss tlwm with you.
Sincerely yours.
I Boyce H. Crier Regional Director Enclocuro:
Dcocription of Item of 1*oncomplianca hect J..G. Keppler, RO R. H. Engelken, RO li. D. Thornburg, RD P. At Morrio, h0 A. Ciatibuneo, L R0 Files DR Contral File.a PDR
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ENCLOSURE Northern States Power Company Monticello Docket No. 50-263 '
Certain of the activities under your license appears to be in noncompliance with AEC licens,e requirements as indicated belows Sectiono 3.1A, 3.2A, 3.2B, and 3.2E.3, of the Technical Specifications require that four drywell pressure instrument channels be operable or operating when irradiated fuel is in the reactor vessel and the reactor water temperature is above 212*F.
Section 1.0 of the Technical Specif1-cations defines a component to be operable when it is capable of performing its intended function in its required manner.
Contrary to the above, two of the four drywell pressure sensing taps were found on July 11, 1972, to have been covered with tape. Although coergency core cooling system operation was properly initiated by re-dundant channels, failure of one of these redundant channels could i. ave resulted in a delay in the actuation of required safoguards. This is evidenced by the fact that the pressure indicated by the drywell precoure recorder, to which one of the taped scusing taps is connected, increased to 0.8 poig prior to conmencinE to decrease, even though drywell p. essure f
had increased to approximately 2 psig, as evidenced by the operation of pressure switches connected to the untaped sansing 2fnas.
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