IR 05000266/1987015

Insp Repts 50-266/87-15 & 50-301/87-14 on 870716-0831.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety,Maint,Surveillance,Physical Security, Radiological Protection & LER Followup

ML20235E833
Person / Time
Site:	Point Beach
Issue date:	09/17/1987
From:	Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20235E814	List: IR 05000266/1987015 ML20235E812
References
50-266-87-15, 50-301-87-14, IEIN-87-004, IEIN-87-008, IEIN-87-010, IEIN-87-012, IEIN-87-10, IEIN-87-12, IEIN-87-4, IEIN-87-8, NUDOCS 8709280289
Download: ML20235E833 (7)

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. U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-266/87015(DRP); 50-301/87014(DRP)

Docket Nos._50-266;'50-301 Licenses No. DPR-24; DPR-27 Licensee: Wisconsin Electric Company 231 West Michigan Milwaukee, WI 53203 Facility Name: Point Beach, Units 1 and 2 Inspection At: Two Creeks, Wisconsin Inspection Conducted: July 16, 1987 through August 31, 1987

' Inspectors: R. L. Hague-R. J.' Leemon-Approved By: R ayette, Reactor Projects Section 2B 7 /7 Date' :/

Inspection Summary Inspection from July 16, 1987 throuch August 31, 1987 (Reports No. 50-266/87015(DRP); No. 50-301/87014 (DRP))

Areas Inspected: Routine, unannounced inspection by resident _ inspectors of licensee actions on previous inspection. findings; operational safety; maintenance; surveillance; physical security; radiological protection; and licensee event report follow-u Results: No violations or deviations' were identified.

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DETAILS Persons Contacted

• J. J. Zach, Manager, PBNP

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T. J. Koehler, General Superintendent G. J. Maxfield, Superintendent - Operations

• J. C. Reisenbuechler, Superintendent - EQRS W. J. Herrman,. Superintendent - Maintenance & Construction D. F. Johnson, Superintendent - Health Physics R. Krukowski, Security Supervisor

• A. Flentje, Administrative Specialist

• J. E. Knorr, Regulatory Engineer T. L Fredrichs, Superintendent - Chemistry The inspectors also talked with and interviewed members of the Operation, Maintenance, Health Physics, Chemistry and Instrument and Control Section * Denotes personnel attending exit interview . Licensee Action on Previous Inspection Findings (92701) (92702)

(CLOSED) Open Item 266/87007-02; 301/87007-02 - Pending review of plant specific current transformer (CT) characteristic curve The licensee's CT analysis " Current Transformers as a Fire Hazard - Point Beach Nuclear Plant" NENE-87-44 determined the maximum C7 secondary potential-to be 400 volts. It was identified during the inspection, however, that this value of voltage was based on generic rather than plant specific CT characteristics. By letter, dated May 19, 1987, from R. Steve (Westinghouse Electric Corporation) to R. A, Newton (Wisconsin Electric Power Company) the licensee received, from the manufacturer, plant specific characteristics of the CT's of concern. A review of this information found this concern to be satisfied. This item is considered close The following IE Information Notices were reviewed by the licensee for applicability, distributed to the appropriate personnel at the corporate and site levels, and it was determined by the licensee that corrective actions were not necessar IN 87-04 " Diesel Generator Fails Test Because of Degraded Fuel" Fuel Oil Surveillance The licensee's technical specifications (TS 15.4.6A.4)

require that each fuel oil transfer pump shall be run monthl _ -_-_ . .

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. Maintenance Including Fuel Filter Cleaning RMP #43, " Diesel Annual Inspection" requires that the suction line strainer of the two fuel transfer pumps be cleaned and the fuel oil filters and fuel transfer filters be changed annually.

, Fuel Sampling Fuel oil is sampled monthly for each diesel and verified acceptable per table 1 of ASTM-D975, " Standard Specification for Diesel Fuel Oils" with respect to viscosity, water content and sedimen Fuel Oil Tank Cleaning The licensee does not perform fuel oil tank cleaning as a 1 part of a routine maintenance progra IN 87-08 " Degraded Leads in Limitorque DC Motor Operators" Licensee does not have DC motor operators with the referenced type of lead IN 87-10 " Potential for Water Hammer During Restart of Residual Heat Removal Pumps" This IN is applicable to BWRs and Point Beach Nuclear Power Plant is a PW IN 87-12 " Potential Problems with Metal Clad Circuit Breakers, General ^

Electric Type AKF-2-25"

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These breakers are not used at Point Beach Nuclear Power Plan . Operational Safety Verification and Engineered Safety Features System

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Walkdown (71707 and 71710)

The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the period of inspection. During these discussions and observations, the inspectors ascertained that the operators were alert, cognizant of plant conditions, attentive to changes in those conditions, and took prompt action when appropriate. The inspectors verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the Auxiliary and Turbine Buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.

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. The inspectors observed plant housekeeping / cleanliness conditions. During the period of inspection, the inspectors walked down the accessible portions of the Auxiliary Feedwater, Vital Electrical, Diesel Generating, Component Cooling, Safety Injection, and Containment Spray systems to verify operabilit These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications, 10 CFR and administrative procedure At 4:35 a.m. on July 18, 1987, Unit 1 was taken off line for a short  ;

maintenance outag Of primary concern was a steam generator level j transmitter isolation valve which had a significant packing leak. Other maintenance included leak repairs to the cylinder heating steamline and the manways on the 2A and 3B feedwater heater The unit was placed back on line at 12:47 p.m., July 18, 1987 and was at full power at 7:12 a.m.,

July 19, 198 During a severe electrical storm, at 6:55 p.m. on August 16, 1987, the Unit 2 main transformer (2X01) was hit by a lightning strike. The lightning strike caused a lockout of the B and C phases of transformer 2X01. This in turn caused a lockout of the Unit 2 generator and a turbine f trip / reactor trip. No safeguards buses were lost, however, power was lost j to the reactor coolant' pumps. Operators verified natural circulation and

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were able to restore power to the reactor coolant pumps by 7:17 p.m. An Unusual Event was declared as required by the emergency plan. The Unusual Event was terminated at 8:05 p.m. The loss of power to the reactor i coolant pumps was a result of the failure of the automatic bus transfer to l occur. It is believed that this failure was due to the nature of the i power disruption and the fact that the synchronous relay which allows the transfer did not sense a synchronous condition at the time. Restart was delayed due to the necessity to completely check out the 2X01 transformer for physical damage and to perform repairs to the steam driven auxiliary feed pump which exhibited high outboard bearing temperatures while maintaining the unit in hot shutdown. The unit was placed back on line at 5:10 a.m. on August 18, 1987. During the startup the DC power to the main steam isolation valves was left tagged out. This is a potential ,

violation and will be discussed in special Inspection Report No. 301/8701 No violations or deviations were identified for this repor )

4. Monthly Surveillance Observation (61726)

The inspector observed technical specifications required surveillance testing on tre Reactor Protection and Safeguards Analog Channels and Nuclear Inst w mentation and verified that testing was performed in accordance with adequate procedures, the test instrumentation was calibrated, that limiting conditions for operation were met, that removal i and restoration of the affected components were accomplished, that test l results conformed with technical specifications and procedure requirements j and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne _ _ _-

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The inspector also witnessed or reviewed portions of the following test activities:

IT-07 Inservice Testing of Service Water Pumps & Valves (Monthly)

IT-09 Inservice Testing of Turbine-Driven Auxiliary Feed Pump (Monthly)

IT-72 Inservice Testing of Service Water Valves (Quarterly)

IT-295A Inservice Testing of Auxiliary Feedwater System Flow Indicators TS-9 Control Room Heating and Ventilation System Checks No violations or' deviations were identifie . Monthly Maintenance Observation (62703)

Station maintenance activities on safety related systems and components listed below were observed / reviewed to ascertain that they were conducted ,

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codes or standards and in conformance with technical specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as , applicable; functional testing and/or calibrations were performed prior i to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; i parts and materials used were properly certified; radiological controls H were implemented; and fire prevention controls were implemente Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performanc The following maintenance activities were observed / reviewed:

• Thrust bearing maintenance on 2P29 turbine-driven auxiliary feedwater pump

• Inspection of 2X01 transformer

• Installation of new instrument air compressor

• Repair of valve MOV 112B, RWST to VCT isolation

• Inspect bearings in boric acid transfer pump (

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During use of the Unit 2 steam driven auxiliary. feed'pu'mp, a high temperature alarm was received on'the' outboard turbine bearing. -Steam generator. feed-was. shifted to the electric driven auxiliary feed pumps and c .the~ steam driven pump was~ declared out of service. Maintenance personnel disassembled the bearing ~and found some. minor wiping of.the thrust bearing (one to two thousands of an inch). Normal' clearances are six to nine thousands'of an inch. This has been a recurring problem with the Terry turbine thrust bearings at Point Beach. A modification to replace the

. kingsbury type bearing with a roller type' thrust bearing has been delayed pending vendor support. . .The licensee expects to be able to complete the o

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modification during the next refueling, outage on'each uni No violations or deviations were identifie . Physical Security (71881)  !

.The inspectors, by observation and direct interview, verified that physical security.was being implemented in accordance with the station security pla During the inspection period, the inspectors verified that the security force compliment was as required by the security plan, that search

' equipment was operational, and that access control for personnel and packages was implemented in accordance with licensee procedures. Th inspectors verified that the protected and vital area barriers were being well maintained and, when required, appropriate compensatory measures were-take No violations or deviations were identifie . RadiologicalProtection(717091 During the inspection period, the inspectors verified that health physics supervision conducted plant tours and were aware of activities which may cause unusual radiological conditions. The inspectors verified that radiation work permits (RWP) contained required information and for selected RWPs the inspectors verified controls were being implemented as required at the work site. The inspectors observed personnel within radiation controlled areas and determined that personnel monitoring i equipment was properly worn and that the licensee's procedures for entry {

and. exit were followed. The inspectors observed the posting of radiation '

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areas, hot spots, contaminated areas, and labeling of containers holding radioactive material and verified postings using a calibrated beta gamma portable survey mete No violations or deviations were identified.

l Event Followup (92700)

Through direct observations, discussions with licensee personnel, and review of records, the following licensee event report (LER) was reviewed

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to' determine that deportability requirements.were fulfilled, immediate torrective1 action wcs_ accomplished, and corrective action to prevent g recurrenceihad been. accomplished in accordance with technical-E specifications.

I t'c 266/84006 ContainmentLIsolation Valve Leakage.in Excess of Technical l Specifications.

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In September 1984, this' valve leak rate was discussed between the Resident

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Inspector' staff and.the licensee and it was decided that this event was not reportable because the minimum pathway leakage of 410 standard cubic centimeters per minute (SCCM) passed the test. Recently, however, a review-of data indicates _that-it possibly should have been reported at-the time. This LER, therefore,'.was submitted for information purpose No violations or deviations were identifie . Exit Interview (30703)

The inspectors met with licensee representatives (denoted in Paragraph 1)

throughout the inspection period and at the conclusion of the inspection-period to summarize the scope and findings of the inspection activitie The licensee acknowledged the' inspectors' comments. The inspectors also

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discussed.the likely informational content of the inspection report with regard to documents.or processes reviewed by thel inspectors'during'the'

inspection. The;1icensee did not identify any such documents / processes as-proprietary.-

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