IR 05000266/1987020
| ML20236R736 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/16/1987 |
| From: | Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236R723 | List: |
| References | |
| 50-266-87-20, 50-301-87-20, NUDOCS 8711230455 | |
| Download: ML20236R736 (6) | |
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U.S. NUCLEAR REGULATORY COMMISION
REGION III
Reports No. 50-266/87020(DRP); 50-301/87020(DRP)
Docket Nos. 50-266i 50-301 Licenses No. DPR-24; DPR-27 Licensee:
Wisconsin Electric Company 231 West Michigan l
Milwaukee, WI 53203
Facility Name:
Point Beach, Units 1 and 2 Inspection 't:
Two Creeks, Wisconsin Inspection Conducted:
October 1-31, 1987 Inspectors:
R. L. Hague R. J. Leemon i
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Approved By:
Rotiert De ayette,Cihief
// /h Reactor Projects Section 28 Date '
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Inspection Summary Inspection from October 1-31, 1987, (Reports No. 50-266/87020(DRP);
50-301/87020(DRP))
Areas Inspected:
Routine, unannounced inspection by resident inspectors of operational safety; maintenance; surveillance; physical security; radiological protection; and outages.
Results:
No violations or deviations were identified.
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DETAILS 1.
Persons Contacted
- J. J. Zach, Manager, PBNP T. J. Koehler, General Superintendent G. J. Maxfield, Superintendent - Operations i
- J. C. Reisenbuechler, Superintendent - EQRS W. J. Herrman, Superintendent - Maintenance & Construction D. F. Johnson, Superintendent - Health Physics R. Krukowski, Security Supervisor
- F. A. Flentje, Administrative Specialist
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- J. E. Knorr, Regulatory Engineer T. L. Fredrichs, Superintendent - Chemistry The inspectors also talked with and interviewed members of the Operation,
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Maintenance, Health Physics, Chemistry and Instrument and Control Sections.
- Denotes personnel attending exit interviews.
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Operational Safety Verification and Engineered Safety Features System
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Walkdown (71707 and 71710)
j 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 f
ascertained that the operators were alert, cognizant of plant conditions, j
attentive to changes in those conditions, and took prompt action when J
appropriate.
The inspectors verified the operability of selected
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emergency systems, reviewed tagout records and verified proper return to J
I service of affected components.
Tours of the Auxiliary and Turbine j
Buildings and Unit 2 containment were conducted to observe plant equipment
conditions, including potential fire hazards, fluid leaks, and excessive i
vibrations and to verify that maintenance requests had been initiated for
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equipment in need of maintenance.
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The inspectors observed plant housekeeping / cleanliness conditions.
During l
the period of inspection, the inspectors walked down the accessible
portions of the Auxiliary Feedwater, Vital Electrical, Diesel Generating, i
Component Cooling, Safety Injection, and Containment Spray systems to verify operability.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under
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Technical Specifications, 10 CFR and administrative procedures.
Unit 2 came off line on October 3, 1987, to begin refueling outage 13.
The outage is scheduled to be completed by November 14, 1987.
Major work items include:
eddy current and sleeving of steam generator tubes; reactor coolant pump seal package replacement; modification of steam driven auxiliary feedwater pump to replace coupling and thrust bearing; installation of moisture separator reheater (MSR) preseparators; low
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pressure turbine overhaul; and replacement of resistance temperature detector (RTD) manifolds.
On October 7,1987, a contract worker fainted while working on the Unit 2 B steam generator.
He was wearing a respirator and anti-contamination clothing.
The respirator and protective clothing were removed at the plant and he was taken by ambulance to a local-hospital.
The worker had slight amounts of radioactive contamination on his socks, face, and hair (9,000 - 15,000 disintegrations per minute over 100 square centimeters).
The contamination.apparently occurred when his respirator and protective clothing were removed.
He was accompanied to the hospital by plant health physics personnel.
He was decontaminated there by the health physicists and examined by medical personnel.
He was released and returned to work within several hours.
The ambulance and hospital treatment area were surveyed, and no detectable radioactive contamination was found.
The licensee received a letter from Westinghouse detailing the possible susceptibility of the Unit 2 steam generators to the type of failure which occurred at the North Anna plant.
The licensee was asked to perform inspections to determine if there was tube denting at the upper tube support plate and to what extent the antivibration bars penetrated the tube bundle.
The licensee performed these inspections and provided the results to Westinghouse for analysis.
Preliminary results indicate that the steam generators have no tubes at risk.
This information will also be presented to NRR in a meeting scheduled for the first week of November.
No violations or deviations were identified.
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Monthly Surveillance Observation (61726)
The inspector observed technical specifications required surveillance i
testing on the Reactor Protection and Safeguards Analog Channels and j
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 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 also witnessed or reviewed portions of the following test activities:
ICP 2.7 Power Range Nuclear Instrumentation, Unit 1
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ICP 2.13 4160 Volt Undervoltage, Unit'l ICP 4.15 Boric Acid Tank Level Transmitters, Unit 1
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ICP 4.25 Nuclear Instrumentation System Intermediate Range Channels
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Unit 2 l
ICP 4.38 Intermediate Range Compensating Voltages, Unit 2
IT-03 Inservice Testing of Low Head Safety Injection Pumps & Valves
Unit 1 IT-04 Inservice Testing of Low Head Safety Injection Pumps & Valves l
Unit 2 j
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IT-05 Inservice Testing of Containment Spray Pumps, Eductor Supply l
Check Valves & Sodium Hydroxide Addition Valves, Unit 1 I
IT-08 Inservice Testing of Turbine Driven Auxiliary Feed Pumps Unit 1 l
TS-36 Local Leak Test of Containment Purge Valves i
l No violations or deviations were identified.
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4.
Monthly Maintenance Observation (62703)
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Station maintenance activities on safety related systems and components i
listed below were observed / reviewed to ascertain that they were conducted j
in accordance with approved procedures, regulatory guides and industry j
codes or standards and in conformance with technical specifications.
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The following items were considered during this review:
the limiting I
conditions for operation were met while components or systems were removed I
from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected j
as applicable; functional testing and/or calibrations were performed prior
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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 i
were implemented; and fire prevention controls were implemented.
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.
The following maintenance activities were observed / reviewed:
Installation of new RTD manifolds Steam driven auxiliary feedpump modification
"A" reactor coolant pump seal replacement
Unit 2 steam generator tube sleeving
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o Installation of MSR preseparators
Replacement of unqualified solenoid valve pigtails
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Installation of alarm for main steam isolation valve DC control power i
Modification of instrument air system j
i No violations or deviations were identified.
5.
Physical Security (71881)
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The inspectors, by observation and direct interview, verified that physical security was being implemented in accordance with the station security plan.
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During the inspection period, the inspectors verified that the security
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force compliment was as required by the security plan, that search
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equipment was operational, and that access control for personnel and
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packages was implemented in accordance with licensee procedures.
The i
inspectors verified that the protected and vital area barriers were being well maintained and, when required, appropriate compensatory measures were taken.
No violations or deviations were identified.
6.
Radiological Protection (71709)
During the inspection period, the inspectors verified that health physics i
supervisory personnel conducted plant tours and were aware of activities l
which may cause unusual radiological conditions.
The inspectors verified
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that radiation work permits (RWP) contained required information and for selected RWPs the inspectors verified controls were being implemented as i
required at the work site.
The inspectors observed personnel within i
radiation controlled areas and determined that personnel monitoring I
equipment was properly worn and that the licensee's procedures for entry j
and exit were followed.
The inspectors observed the posting of radiation i
areas, hot spots, contaminated areas, and labeling of containers holding radioactive material and verified postings using a calibrated beta gamma portable survey meter.
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Two hot particle contaminations occurred during the inspection period.
These events were referred to the Region III Division of Radiation Safety and Safeguards for resolution and are described in Inspection Reports 266/87019; 301/87019.
No violations or deviations were identified.
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Outages (60710, 61701, 86700)
The inspectors verified that prior to the handling of fuel in the core, all surveillance testing required by the Technical specifications and the licensee's procedures had been completed; verified that during the outage the periodic testing of refueling related equipment was performed as required by Technical Specifications; observed 5 shifts of the fuel handling operations (removal, inspection and insertion) and verified that activities were performed in accordance with the Technical Specifications and approved procedures; verified that containment integrity was maintained as required by Technical Specifications; verified that housekeeping was maintained in the refueling area; and, verified that staffing during refueling was in accordance with Technical Specifications and approved procedures.
The major modifications performed on Unit 2 during the refueling outage were:
repiping the resistance temperature detectors' by pass manifolds to reduce future exposure while doing loop maintenance; sleeving of 89 steam i
generator tubes which indicated 36% or more through wall defects; and moisture preseparator installation.
The licensee also used the newly acquired ultrasonic fuel assembly defect detection equipment to inspect all assemblies which were to be reused in the core reload.
The equipment was installed on the floor of the refueling cavity which eliminated the need to send each assembly to the spent fuel pool for inspection.
This saved a significant amount of time and reduced assembly manipulations to a minimum.
The inspectors observed the following refueling outage related surveillance testing on Unit 2 to verify that the tests were covered by properly approved procedures; that the procedures used were consistent j
with regulatory requirements, licensee commitments, and administrative
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controls; that minimum crew requirements were met, test prerequisites were completed, special test equipment was calibrated and in service, and required data was recorded for final review and analysis; that the qualifications of personnel conducting the test were adequate; and that the test results were adequate.
- WMTP 9.1.A Rod Drop Tests
ORT 1 Flow Test of Safety Injection Pumps
ORT 2 Flow Test of Residual Heat Removal Pumps
ORT 3 Safety Injection Actuation with Loss of Engineered j
Safeguards AC i
ORT 11 Check Valve Stroke Test 6