IR 05000305/1982004
| ML20053A217 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 05/08/1982 |
| From: | Bob Fitzpatrick, Konklin J, Nelson R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20053A204 | List: |
| References | |
| 50-305-82-04, 50-305-82-4, NUDOCS 8205250093 | |
| Download: ML20053A217 (5) | |
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U.S. NUCLEAR REGULATORY CO.TfISSION
REGION III
Report No. 50-305/82-04(DPRP)
Docket No. 50-305 License No. DPR-43 Licensee: Wisconsin Public Service Corporation Post Office Box 1200 Green Bay, WI 54305 Facility Name: Kewaunee Nuclear Power Plant Inspection At: Kewaunee Site, Kewaunee, WI Inspection Conducted: February 1-28 and March 1-31, 1982 Inspectors:
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B itzpatrick I
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R.\\r L L v J
E. Konklin, Chief N
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Reactor Projects Section 2A J
Inspection Summary Inspection on Febri., 1-28 and March 1-31, 1982 (Report No. 50-305/82-04(DPRP))
Areas Inspected:
soutine, resident inspection of operational safety verifica-tion; monthly maintenance observation; monthly surveillance observation; licensee event report followup; independent inspection; followup on previous inspection findings; followup on regional request regarding TMI action items; participation in emergency drill observation. The inspection involved a total of 190 inspector-hours onsite by two NRC inspectors, including 37 inspector-hours onsite during off-shifts.
Results: No items of n'oncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
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C. Hintz, Plant Manager
- M. C. Marchi, Technical Supervisor R. W. Lange, Superintendent, Maintenance C. R. Steinhardt, Superintendent, Operations W. J. Richmond, Plant Services Superintendent D. W. McSwain,.',ssistant Superintendent, Instrument and Control K. H. Evers, Reactor Supervisor
- A. J. Ruego, Quality Control Supervisor
- D. J. Molzahn, Technical Services Engineer The inspectors also talked with and interviewed members of the Operations, Maintenance, Health Physics, Instrument and Control, and Security Groups.
- Denotes those attending one or more exit interviews.
2.
Followup on Previous Inspection Findings (Closed) Noncompliance (305/81-18-01 and 305/81-18-02): The licensee's actions appear to be adequate to prevent recurrences of these noncompli-ances.
3.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the months of February and March. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the containment, 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. The inspector, by observation and direct inter-view, verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector observed plant housekeeping and cleanliness conditions and verified implementation of radiation protection controls. During the months of February and March, the inspector walked down the accessible portions of the auxiliary feedwater, fire protection, service water, emergency diesel generator, high head safety injection, containment spray, residual heat removal, component cooling, spent fuel pit cooling and radiation monitoring systems to verify operability.
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 procedures.
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The inspector reviewed a licensee - identified fire protection item which was reported to the NRC in a letter dated March 15, 1982. The item relates to Technical Specification 3.15.d which requires that the CO system storage tank be maintained at a minimum pressure of 295 psig.
During recent maintenance on the system the licensee found that the compressor cycling points are 290 psig for stop and 310 psig for start.
This maintains the storage tank at an average pressure of 300 psig. The licensee's investigation has revealed that an apparent typographical error was made on the original Technical Specification submitted by the licensee which was then approved by NRR. The 295 psig should have been 275 psig based on the manufacturer's recommendations. The licensee plans to submit a Technical Specification amendment in the near future to reflect the manufacturer's recommendations. This item will remain open pending the licensee's amendment submittal and subsequent approval by NRR (305/82-04-01(DPRP)).
No items of noncompliance or deviations were identified.
4.
Monthly Maintenance Observation Station maintenance activities of safety related systems and components listed below were observed / reviewed to verify that they were conducted in accordance with approved procedures, regulatory guides and industry
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codes or standards, and were in conformance with technical specifications.
The following items were confirmed 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 to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire prevention controls were implemented.
Work requests were reviewed to determine the status of outstanding jobs and to assure that priority is assigned to safety related equipment main-tenance which may affect system performance.
The following maintenance activities were observed / reviewed:
MWR 33 19035 Replace Corroded Bolts in SI-2A MWR 33 18921 Repair Grease Leak on SI-209 Motor Operator MWR 55 19507 Replace Relay in Boric Acid Tank "B" Level Logic MWR 49 19526 Replace Conditioning Module on Control Rod K-7 IRPI PMP 24-1 Revision C Inspect, Lubricate, and Insulation Resistance Test Shield Building Vent System No items of noncompliance or deviations were identified.
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5.
Monthly Surveillance Observation The inspector verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements 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 personnel.
The inspector observed the following surveillance testing required by technical specifications:
SP-48-003 Nuclear Power Range Instrument Channel Test SP-48-004 Nuclear Power Range Channel Quarterly Calibration SP-49 Radiation Monitoring System SP-34-009 Residual Heat Removal and Valve Test SP-35-147 Boric Acid Tank Level Instrument Test No items of noncompliance or deviations were identified.
6.
Licensee Event Report Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specifications.
81-031/03L-0 Monitor Tank 1A Tritium High 81-032/01T-0 Discharge TDS Too High 81-033/01T-0 IB D/G and Component Cooling Heat Exchanger 1A Out of Service at Same Time 81-034/03L-0 IB Zone Special Ventilation Fan Solenoid Failure 81-035/03L-0 Monitor Tank 1A Tritium High 81-015/03X-2 Steam Flow Transmitter Out of Calibration (Update)
81-014/03X-1 Pressurizer Level Transmitter Out of Calibration (Update)
81-036/03L-0 Motor Driven Aux Feed Pump 1A Lube Oil Pump Failed to l
Stop 81-037/03L-0 Steam Flow Indication Transmitter Circuitry Failure 81-038/03L-0 SBVIOA Failed Shut 81-039/03L-0 CVC-101C Discharge Line Cracked Weld 81-039/03X-1 CVC-101C Discharge Line Cracked Weld (Update)
No items of noncompliance or deviations were identified.
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7.
Independent Inspection l
The inspector conducted a general inspection of operations, maintenance, l
health physics, security, quality assurance, and administrative activities.
No items of noncompliance or deviations were identified.
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8.
Regional Request a.
The inspector provided information to Region III concerning the status of several TMI action items.
b.
The inspector participated in the NRC observation of the plant emergency drill. The results of this inspection will be documented in Inspection Report No. 50-305/82-06.
9.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the inspection period and at the conclusion of the inspection on April 2, 1982, and summarized the scope and findings of the inspection.
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