IR 05000263/1985023

Insp Rept 50-263/85-23 on 850910-1125.No Violation Noted. Major Areas Inspected:Previous Insp Findings,Operational Safety Verification,Spent Fuel Shipments,Lers & IE Bulletins

ML20137W352
Person / Time
Site:	Monticello
Issue date:	12/05/1985
From:	Boyd D, Hartman P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20137W313	List: IR 05000263/1985023 ML20137W308
References
50-263-85-23, NUDOCS 8512100228
Download: ML20137W352 (5)

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D U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-263/85023(DRP) .

Docket No. 50-263 License No. DRP-22 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name: Monticello Nuclear Generating Station Inspection At: Monticello Site, Monticello, MN Inspection Conducted: Septe er 10 - November 25, 1985 Inspector:

[7b P. L. Hartman /2-5-E5 Date Approved By: D. oyd, C ief e2-5-S5 Reactor Projects Section 20 Date Inspection Summary Inspection on September 10 - November 25, 1985 (Report No. 50-263/85023(DRP)

Areas Inspected: A routine, unannounced inspection by the resident inspector of previous inspection findings; operational safety verification; spent fuel shipments; Licensee Event Reports; and IE Bulletins. The inspection involved a total of 176 inspector-hours onsite by one NRC inspector including 30 inspector-hours onsite during off-shift Results: No violations or safety concerns were identified in the five areas inspecte kDj ljpgCK28 851205 G 05000263 PDR

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DETAILS

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4 Persons' Contacted

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A.' Shamla, Plant Manager

- H. Clarity, Assistant to the Plant Manager D.' E. Nevinski, Plant Superintendent, Engineering & Radiation Protection

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H. M. Kendall, Plant Office Manager

! .D. D. Antony, Superintendent, Operations & Maintenance W. E. Anderson, Plant Superintendent, Operations & Maintenance

R. L. Scheinost, Superintendent, Quality Engineering J. R. Pasch, Superintendent, Security & Services

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L H. Waldinger, Superintendent, Radiation Protection

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W. J. Hill, Superintendent, Technical Engineering W. W. Albold, Superintendent of Maintenance

B. D. Day, Superintendent, Operations Engineering L. L. Nolan, Superintendent, Nucl, ear Technical Services The inspectors also contacted other licensee employees including members of the technical and engineering staffs and reactor and auxiliary

operators.

! '* Denotes the licensee representative attending the management exit interview ,

, Licensee Action on Previous Inspection Findings , (Closed) Open Item'(263/8301401(DRP)): HPCI Oil Sump Samplin The

'- licensee now samples.the sump oil on the bottom of the barrel during

. receipt inspection.

I (Closed) Open Item (263/84011-18(DRP)): Training Records. The

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licensee provided the classroom training records for ten fire brigade members to'the Senior Resident Inspecto . Operational Safety Verification The unit was operated at near full power during the majority of'the

' inspection period. On October 12, 1985, the reactor was shut down to allow replacement of a. safety relief valve (SRV). The SRV was replaced, l.'~ the reactor was made critical and the generator synchronized to the grid on October 13, 1985.

t iThe inspector observed control room operations, reviewed applicable logs

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and conducted discussions with control room operators'during the

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inspection period.- The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to f service of affected components. Tours of the reactor building and turbine building were conducted to observe plant equipment conditions,

-including potential fire hazards, fluid leaks, and excessive vibrations

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and to verify that maintenance requests had been initiated for equipment in need of maintenance,~ plant housekeeping / cleanliness conditions and verified implementation of radiation protection control No violations or deviations were identifie ts

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' Spent' Fuel Shipments During the inspection period, the licensee made two spent fuel shipments to the General Electric Company Morris Operation in Morris, Illinois. A shipment consisted of 36 BWR fuel assemblies in 2 IF-300 casks mounted on rail cars, 1 cask per ca On~one of.the shipments, before the rail cars with the casks IF-301 and IF-302 were shipped from the Monticello site, the inspector verified that shipping forms were completed, that the rail cars were properly

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placarded, and that the casks were correctly labeled. The radiation and contamination surveys.were noted to have been completed and to have been

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within departure limits requirements. The inspector also performed independent direct radiation and removable contamination surveys of the casks using NRC portable survey equipment and noted these readings and

. indications agreed with the licensee's survey records and information

presented in the radioactive materials shipment records.

l No violations or deviations were identified.

1 Licensee Event Reports

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Through_ direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine i that reportability requirements were fulfilled,.immediate corrective action was accomplished, and corrective action to prevent recurrence ha been accomplished in accordance with technical specification (Closed) LER 83004: Low Flow on SBGT "B" Trai Procedure No. 1265

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was revised on May 21, 1985, to provide guidance and an action statement in the event the pressure differential ev.ceeds the given

, value.

i 1- .(Closed)'LER 83011: Leak in Moisture Separator Drain to 14B Heate D During normal operatior, routine inspection found a steam leak on a

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reducer at the D moisture separator drain valve. The cause was

determined to be from steam erosion. Further investigation revealed

, that the reducer was made of carbon steel instead of the design

required stainless steel. Since no stainless steel reducers were

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available, the leaking reducer was replaced by another carbon steel j, reducer which was to be replaced by stainless steel during the 1984

outage. This was completed on July 11, 1984, (WRA Nos. 83-3246 and 83-3247). (Closed) LER 83012: Mode Switch Relay Logic Failure. During surveillance testing, the mode switch scram bypass annunciator came on following energization of the "A" reactor protection logic. This was caused by a design deficiency which was corrected in accordance with GE Service Information Letter (SIL) No. 344, Revision 1.

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i (Closed) LER 83013: MSIV 2-800 Fast Closur During special

.. . surveillance testing, due to trend in valve timing, one of.the

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inboard MSIVs closed faster than technical specification values.

.This was caused by leakage of oil from the control valve -

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housing-to-body threaded connection due to inadequate maintenance and inspection. Thread sealant was applied and the MSIV closure time was readjusted. As part of the co rective action, a maintenance procedure was to be initiated to check these components. This was done as revisions to Procedure Nos. PM-4240 on July 20, 1984, and PM-4243 dated February 14, 198 e. (Closed) LER 83017: HPCI Isolation on High Steam Flo During normal operation while performing a surveillance test, HPCI isolated on high steam flow following replacement of a servo. The servo operation was stiff and sticky due to old oil residue. The servo was replaced and the HPCI satisfactorily teste f. (Closed) LER 83018: RHR Pump Minimum Flow Valve Failure to Ope During normal operation, using No. 11 RHR Pump for torus cooling, the minimum flow valve failed to open as required due to flow switch failure. An exact replacement part was installed and the valve then was tested satisfactoril g. (OPEN) LER 83020: No. 11 Diesel Generator Inoperable. During

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noreal plant operation, No.11 Diesel Generator became inoperable while in the standby condition because the turbocharger auxiliary lube oil pump motor bearing failed. After repairs were made, the diesel was functionally tested satisfactoril As part of-the corrective action, the Preventive Maintenance Procedures PM-4101-1 and PM-4101-2 were to be revised to include the pump motor assemblies. This action has not been completed and, therefore, this LER will remain open. The licensee stated this would be completed-early in 198 h. (Closed) LER 84007: No. 11 Reactor Recirculation Motor Generator

, Set Drive Motor Breaker Failure. Preliminary work involved cleaning, adjustment of the breaker trip mechanism and trip coil replacemen Final corrective action consisted of replacing Tuf-Loc sleeve bearings during the 1984 refueling outag i. (Closed) LER 85014: Trip of Reactor Building Exhaust Monito During a routine functional test of the resctor building exhaust plertum monitor, an isolation of the Reactor Building Ventilation and initiation of the Standby Gas Treatment System occurred. The cause was due to a spike actuating the upscale trip. The procedure was revised to prevent recurrenc j. (Closed) LER 85016: EFT Actuations Due to Chlorine Detector Trip k. (Closed) LER 85017: EFT Actuation Due to Tape Runou Corrective Action for the above two LERs was discussed in Inspection P,eport No. 263/85020(DRP).

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'e Exit Interview i

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The inspector met with licensee representative denoted in Paragraph 1 at the conclusion of the inspection on September 25, 1985. The inspector l discussed the purpose and scope of the inspection and the finding The inspector also discussed the likely informational content of the inspection report with regard to documents or processe! reviewed by the

. inspector during the inspection. The licensee did not' identify any documents / processes as proprietar '

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