IR 05000263/1978003
| ML20056B599 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/06/1978 |
| From: | Harpster T, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20056B595 | List: |
| References | |
| 50-263-78-03-MM, 50-263-78-3-MM, NUDOCS 9102070583 | |
| Download: ML20056B599 (4) | |
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t U.S. NUCLEAR REGUIATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMENT
REGION III
Report No. 50-263/78-03 Docket No. 50-263 License No. DPR-22 LicenseeY Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name: Monticello Nuclear Generating Plant Inspection At: Monticello Site, Monticello, MN Inspection Conducted: March 10 and March 21-23, 1978
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/18 Inspector:
T.L.Harpd V
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W P f.f ) & k Approved By:
R. F. Warnick, Chief 8-b78 f
Reactor Projects Section 2 Inspection Sumary Inspection on March 10 and March 21-23, 1978 (Rcport No. 50-263/78-03)
Areas Inspected:
Corporate management meeting on March 10, 1978.
Routine, unannounced inspection of design changes and modifications; and follovup of IE Bulletins, Circulars and Licensee Event Reports.
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The inspection' involved 16 inspector-hours onsite by one NRC inspector.
l Results: No items of noncompliance or deviations were identified in
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the areas inspected.
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9102070583 780406 CF ADOCK 0500026 M F i
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DETAILS
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1.
Persons Contacted
- M. Clarity, Superintendent, Plant Engineering and Radiation Protection
- W.
Shamla, Plant Engineer, Technical
- D.
Antony, Plant Engineer, Operations D. Nevinski, Engineer, Nuclear D.?Wegener, Engineer
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A. Myrabo Engineer R. Goranson, Engineer M. Voth, Corporate Engineer
- Denotee those attending the exit interview.
2.
Corporate Management Meeting
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A management meeting was held at the Northern States Power Company headquarters in Minneapolis on March 10, 1978. The purpose of the meeting was to review operating experiences and performance trends at the Monticello and Prairie Island Stetions. NRC representatives noted that the NSP nuclear stations had a good history with regard
to regulatory performance evaluation. Meeting attendees included:
NRC - Region III G. Roy, Deputy Director G. Fiorelli, Chief, Reactor Operations and Nuclear Support Branch R. Warnick, Chief, Reactor Projects Section 2 C. Feierabend, Reactor Inspector T. Harpster, Reactor Inspector NSP D. Gilbert, General Manager Power Production G. Neils, General Superintendent, Nuclear Power Plant Operation L. Mayer, Manager of Nuclear Support Services P. Tierney, Plant Manager, Prairie Island l
L. Eliason, Plant Manager, Monticello 3.
Design Changes and Modifications The inspector reviewed the following administrative control directives concerning design changes:
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3ACD 4.1 Desfgn Change Control
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3ACD 4.2 Des'ign Change Installation Procedure
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i 3ACD 4.3 Design Change Preoperational/ Operational j
Testing
i The inspector reviewed selected design changes to ascertain whether i
the changes were made in accordance with 10 CFA 50.59, Technical Speqilications and the above adminis'.rative control directives.
Modifications selected for review ircluded:
77 M005 Reactor Building H and V system modi-i fication i
77 M074 HpCI exhaust line sparger modification
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No items of noncompliance or deviations were disclosed.
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4.
Onsite Licensee Event Followup
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The inspector discussed Licensee Event Reports 77-25 and 78-02
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with the appropriate licensee personnel to ascertain whether the licensee's review, corrective actions, and reports of the iden-
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I tified events and associated conditions verts adequate and in i
i conformance with regulatory requirements, technical specifications,
l license conditions, and licensee procedures and controls.
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With regard to LER 78-02: The station is considoring replacing
the torus to drywell vacuum breaker teflon bushings with nickle l
l plated bronze sleeves.
If these are not replaced during the fall i
refueling outage, surveillance will be conducted to ensure that
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additional teflon growth and the resultant shaf t binding have not occurred.
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l No items of noncompliance were identified.
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IE Bulletin Followup i
The inspector verified that for IE Bulletins 78-01, 78-02, and i
78-04: The bulletins and responses were reviewed by appropriate
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onsite management representatives; information discussed in the l
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replies was accurate; any corrective actions taken were effected
as described in the replies; and the replies were prompt and i
within the time periods requested.
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With regard to Bulletin 78-02: In addition to the reviews already
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completed, a physical inspec' tion will be made no later than the
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fall refueling outage to verJfy that no unprotected terminal blocks I
exist.
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No items of noncompliance or deviations were disclosed.
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6.
IE Circular Followup
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The inspector verified that for IE Circulars 77-15 and 77-16:
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the, circulars were received by station management; a review for applicability was performed; and any actions taken or planned-l
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No items of noncompliance or deviations were disclosed.
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t 7.
Tip Shear Valve Explosive Squibs
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The inspector discussed the recent occurrence where a Region I
reactor was found to have the tip shear valve explosive squibs l
wired incorrectly due to an erroneous drawing. The inspector j
and licensee verified through review of the system preoperational
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l test and associated drawings that the system had been properly
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wired at Monticello.
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8.
Fuel Channel Box Measurements I I
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e The inspector observed licensee activities on the refueling floor
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f where fuel channel box neasurements were being taken with the new
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"in basin inspection station."
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9.
Containment Integrated Leak Rate Test Report i
j The inspector reviewed inoffice, the summary technical report of l
the Primary Containment Integrated Leak Rate Test - November 1977.
No items of noncompliance or deviations were disclosed.
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10.
Exit Interview l
i-At the conclusion of the inspection on March 23,.1978, the inspector-i met with station management personnel (denoted in Paragraph 1) and summarized the scope and findings of the inspection.
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