IR 05000266/1986015

Insp Repts 50-266/86-15 & 50-301/86-14 on 860801-0930.No Noncompliances or Deviations Noted.Major Areas Inspected: Maint,Surveillance,Ie Bulletin Followup & Followup on Temporary Instruction.Two Unresolved Items Noted

ML20215G065
Person / Time
Site:	Point Beach
Issue date:	10/08/1986
From:	Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20215G062	List: IR 05000266/1986015 ML20215G059
References
50-266-86-15, 50-301-86-14, IEB-86-002, IEB-86-2, NUDOCS 8610160470
Download: ML20215G065 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report Nos. 50-266/86015(DRP); 50-301/86014(DRP)

Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27 Licensee: Wisconsin Electric Company 231 West Michigan Milwaukee, WI 53203 Facility Name: Point Beach Unit 1 and 2 Inspection At: Two Creeks, WI Inspection Conducted: August 1 through September 30, 1986 Inspectors: R. L. Hague R. J. Leemon Approved By: I Reactor c h jects Section 2B

/4-/II Date Inspection Summary Inspection on August 1 through September 30, 1986 (Report Nos. 50-266/86015 (DRP); 50-301/86014(DRP))

Areas Inspected: Routine, unannounced inspection by resident inspectors of operational safety; surveillance; maintenance; IE bulletin follow-up; and followup on temporary instructio Results: No items of noncompliance or deviations were identifie Suo o

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DETAILS 1. Persons Contacted

• J. J. Zach, Manager, PBNP T. J. Koehler, General Superintendent G. J. Maxfield, Superintendent - Operation

• J. C. Reisenbucchler, Superintendent - EQR W. J. Herrman, Superintendent - Maintenance & Construction R. S. Bredvad, Health Physicist R. Krukowski, Security Supervisor

• F. A. Flentje, Staff Services Supervisor

• J. E. Knorr, Regulatory Engineer e The inspector also talked with and interviewed members of the Operation, Maintenance, Health Physics, and Instrument and Control Section * Denotes personnel attending exit interview . Operational Safety Verification and Engineered Safety Features System Walkdown (71707 and 71710)

The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the months of August and September. 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 maintenanc The inspectors, by observation and direct interview, verified that the physical security plant was being implemented in accordance with the station security pla The inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the months of August and September, 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 .

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During a review of the technical manual for the model 44F steam generators installed in Unit 1 during the 6-month outage ending in March of 1984, it was noted that the testing section for primary and secondary side hydrostatic testing listed a minimum test temperature of 120 degrees F. The technical manual for the steam generators that were removed from Unit 1 and for the steam generator presently being used in Unit 2 list a minimum temperature of 70 degrees F. The actual acceptance hydros done by the licensee were performed at a temperature of 147 degrees F. Technical Specification 15.3.1.B.2 states: The secondary side of the steam generator will not be pressurized above 200 psig if the temperature of the steam generator vessel shell is below 70 degrees F. The licensee is checking with the vendor to determine what the Technical Specification temperature value should be. This is an Unresolved Item (266/86015-01(DRP).

On August 6, the plant conducted an emergency preparedness drill in preparation for the September 9 emergency plan exercise. The drill was observed and critiqued by members of the Institute of Nuclear Power Operations (INP0), as well as the Nt; clear Power Departmen The Annual Emergency Preparedness Drill was conducted on September 9, 1986, and was successfu During a test of the emergency notification sirens in Manitowoc and Kewaunee Counties on September 13, 1986, the sirens in Manitowoc County could not be activated from the Sheriff's office as required. The sirens were then tested individually by local activation and they worked properly. The problem appears to be in the radio activation system. The licensee called in the manufacturer for further trouble-shootin It was demonstrated on September 15, 1986, that the sirens could be activated individually from the Sheriff's office. On September 25, 1986, the problem with this all-call signal was corrected and all sirens were tested satisfactorily from the Sheriff's offic On September 26, 1986, at 7:00 p.m., power rampdown commenced on Unit 2 for the annual refueling and maintenance outage (Refueling 12, a 7-week, outage). On September 27, 1986, at 2:22 a.m., the generator output breaker was opened, and at 7:10 a.m. the reactor was taken subcritica On September 28 both main steam stop valves failed to shut on a remote manual signal from the control room. The valves did shut after local attempts were made. These valves will be inspected to find out why they did not close in mid-October and will be tested before the unit is put back on line. This is an Unresolved Item (301/86014-01(DRP).

No violations or deviations were identifie . Monthly Surveillance Observation (61726)

The inspector observed technical specifications required surveillance testing on the Reactor Protection and Safeguards Analog Channels and Nuclear Instrumentation and verified that testing was performed in accordance with adequate procedures, the test instrumentation was calibrated, that limiting conditions for operation were met, that

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

The surveillance specimens of boraflex in the spent fuel pool have been exhibiting degradation presumably from absorption of spent fuel pit water. This absorption appears to increase with irradiation and is more prevalent at the cut edges of the specimens. The licensee has pulled two of the actual ~ sheets which are 8 inches wide by 12 feet long and found very littl degradation on the irradiated sheet and none on the unirradiated .

sheet. Despite this degradation neutron attenuation has remained unchanged. The licensee is preparing a special report on_this subject and will be submitting it to the NRC. This is an open item (266/86015-02(DRP).

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 in accordance with approved procedures, regulatory guides and industry 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 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 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 performance.

j The following maintenance activities were observed / reviewed:

In August the-load on Unit 1 and Unit 2 was reduced to allow

, cleaning biological fouling from the inside of condenser tubes.

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l Repair of the boric acid recirculation pump i

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Repairs to the IP2C charging pump CCW heat exchanger replacement Diesel generator 4D annual overhaul Repair of the white / yellow battery rooms cooling heat exchanger Repair of Valve FP-22, electric fire pump to test header No violations or deviations were identifie . IE Bulletin Followup (92701)

For the IE Bulletin listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action cor.initments based on information present in the bulletin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written respons , " Static-0-Ring Differential Pressure Switches" No violations or deviations were identifie . Temporary Instruction (25581)

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Temporary Instruction 2515/81, " Inspection Requirements for IE Bulletin 86-02, Static-O'-Ring Differential Pressure Switches'" is considered closed. In accordance with the requirements of IE Bulletin 86-02, the licensee has determined that S0R Model 102 or 103 differential pressure switches are not installed, or planned to be used, in safety-related applications at the Point Beach Nuclear Plan In conjunction with their evaluation of IE Information Notice 86-47, they further determined that these pressure switches are not utilized in any applications at Point Beac No violations or deviations were identifie . Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. Two unresolved items disclosed during the inspection are discussed in Paragraph _ __- . - . . - _ _ - .

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8. Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve 4 some action on the part of the NRC or licensee or both. An open item disclosed during the inspection is discussed in Paragraph . 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 discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspectors during the inspection. The licensee did not identify any such documents / processes as proprietary.

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