IR 05000219/1982003
| ML20053C974 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/17/1982 |
| From: | John Thomas, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20053C970 | List: |
| References | |
| 50-219-82-03, 50-219-82-3, NUDOCS 8206030235 | |
| Download: ML20053C974 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-219/82-03 Docket No. 50-219 Licoi;:: 30. DPR-16 Priority Category C
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Licensee:
GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Facility Name: Oyster Creek Nuclear Generating Station Inspection at: Forked River, New Jersey Inspection conducted:
March 2-April 5, 1982 Inspectors:
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5 Il!$1 QN.'50 mas, Resident Inspector
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date signed
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date signed Approved by:
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- L. E. TMhp, Chief, Reactor Projects Section
' da'te signed 2A I_nspection Summary: Inspection on March 2-April 5,1982 (Report No. 50-219/82-03)
Areas Inspected: Routine inspection by the resident area (32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />)
including review of plant operations, lop and record review, facility tours, surveillance observation, and review of periodic and special reports.
Results: Violations: None 8206030235 820517 PDR ADOCK 05000219 G
PDR Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted J. Carroll, Director, Station Operations P. Fiedler, Vice-President and Director, Oyster Creek K. Fickeissen, Plant Engineering Director M. Laggart, Supervisor, Oyster Creek Licensing R. McKeon, Manager, Rad Waste Operations W. Stewart, Plant Operations Manager J. Sullivan, Plant Operations Director D. Turner, Radiological Controls Manager The inspector also interviewed other licensee personnel during the inspection including management, clerical, maintenance and operations personnel.
2.
Review of Plant Operations 2.1 The inspector toured selected areas of the plant to examine compliance with Technical Specifications and the licensee's administrative and operating procedures. Areas toured included the following:
Control Room
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Turbine Building
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Augmented Off-Gas Building
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New Rad-Waste Buih.ing Cooling Water Intake and Dilution Plant Structure
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Monitoring Change Areas
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4160 Volt Switchgear, 460 Volt Switchgear, and Cable
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Spreading Rooms Diesel Generator Building
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Battery Rooms
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Maintenance Work Areas Yard Areas
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2.2 The following specific observations were made:
2.2.1 Through daily observation of Control Room instrumentation, annunciators, logs, and records the inspector verified compliance with Technical Specification Limiting Conditions for Operation (LCO) applicable while in cold shutdown.
Proper Control Room manning and implementation of Control Room access control requirements was verified.
The inspector periodically observed shift turnovers to confirm that they were conducted in an orderly manner and that sufficient information was exchanged to insure the continuity of system status. The inspector questioned Control Room Operators and Shift Supervisors on evolutions in progress, instrument parameters, and alamed annunciators to determine if they were aware of current plant conditions and that the reasons for abnormal indications and alamed conditions were understood and were being corrected if required. The inspector verified that evolutions in progress were being performed in accordance with approved procedures.
2.2.2 Local plant instrumentation was selectively examined to verify that instruments necessary to support safe plant operations and fulfill technical specification limiting conditions for operation were in service and that acceptable correlation between channels existed.
Actuation sensors for safety systems required in cold shutdown were examined to insure that activities in the area did not impair system operability.
2.2.3 Monitoring and Change Areas were observed to ensure that entrances to the radiation controlled area (RCA) were properly posted, personnel entering the RCA were wearing proper dosimetry, and that personnel and materials leaving the RCA were properly monitored for radioactive contamination. Monitoring instruments were observed to ensure that proper operational checks and calibrations had been perfomed. The inspector independently measured radiation levels at posted radiation and high radiation area boundaries to assure proper posting and barricading.
2.2.4 The inspector observed activities to verify that control point procedures were followed, that personnel complied with the requirements of applicable radiation work pemits, and that workers were aware of the radiological conditions in the work areas.
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2.2.5 Valves and components in safety related systems were observed to verify proper system alignment. Accessible major flow path valves in the Core Spray, Containment Spray, Control Rod Drive Hydraulic, Emergency Service Water, and Isolation Condenser systems were examined for proper alignment by direct observation and by observation of remote position indicators. All breakers in the 4160 Volt and selected breakers in the 460 Volt snd 125 Vdc electrical systems were examined for proper alignment.
Systems and components were examined for evidence of abnormal vibration and fluid leaks. Selected pipe hangers and seismic restraints were visually examined for indications of mechanical interference or fluid leaks.
2.2.6 Equipment Control procedures were examined for proper implementation by verifying that tags were properly filled out, posted, and removed as required, that jumpers were properly installed and removed, and that equipment control logs and records were complete.
During the conduct of inspection tours, the interiors of cabinets and control panels were examined for the presence of uncontrolled jumpers, lifted leads, or tags. Tags found on systems and components were examined to verify that the component was in the condition specified on the tags and that tags were properly filled out and authorized.
Equipment control logs vere examined to verify that jumpering or tagging of system components did not remove redundant safety systems from service or violate technical specification limiting conditions for operation.
2.2.7 Plant housekeeping conditions including general cleanliness, control of material to prevent fire hazards, maintenance of fire barriers, and storage and preservation of equipment were examined. The inspector examined the placement of temporary hoses and extension cords, and the locations of scaffolding erected for maintenance or modification jobs to verify that safety related equipment operability was not impai red. The inspector noted a continuing improving i
trend in this area.
2.2.8 During daily entry and egress fmm the protected area, the inspector verified that access controls were in accordance with the security plan and that security posts were properly manned.
During facility tours, the inspector verified that
. protected area gates were locked or guarded and that isolation
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zones were free of obstructions. The inspector exavnined vital
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area access points to verify that they were properly kcked (
or guarded and that access control was in accordance with the j
security plan.
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2.3 Acceptance criteria for the above areas include the current revisions of the following:
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Technical Specifications
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Procedure 106, Conduct of Operations Procedure 108, Equipment Control
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Procedure 115, Standing Order Control
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Procedure 119, Housekeeping Procedure 120, Fire Hazards
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Procedure 122, Security Guidelines for Plant Personnel Procedure 903.2, Personnel Monitoring
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Procedure 903.6, Personnel Regulations
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Procedure 915.1, Restriction of Access into Radiation
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Control Areas Prccedure 915.4, Contamination Control
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Procedure 915.6, Radiation Work Permit
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Oyster Creek Physical Security Plan
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10 CFR 50.54(k)
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Inspector Judgment.
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3.
Shift Logs and Operating Records 3.1 The 1:ispector reviewed the current revisions of the following plant procedures to determine the licensee established requirements in this area in preparation for review of selected logs and records:'
Procedure 106, Conduct of Operations;
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Procedure 108, Equipment Control; and,
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Procedure 115, Standing Order Control.
The inspector had no questions in this area.
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3.2 Shift logs and operating records were reviewed to verify that:
Control Room logs were fillec out and signed;
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Equipment logs were filled out and signed;
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Log entries involving abnormal conditions provided
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sufficient detail to comunicate equipment status; Shift turnover sheets were filled out, signed, and
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reviewed; Operating orders did not conflict with Technical
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Specification requirements; and, Logs and records were maintained in accordance with
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the procedures in 3.1 above.
3.3 The review included the following plant shift logs and operating ecords as indicated, and discussions with licensee personnel.
Reviews were conducted on an intermittent selective basis:
Control Room Log, all entries;
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Group Shift Supervisors Log, all entries;
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Technical Specification Log;
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Control Room Turnover Check List;
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i Reactor Building Tour Sheets;
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Turbine Building Tour Sheets;
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i Equipment Tagging Log;
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Lifted Lead and Jumper Log;
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Defeated Alann Log; Standing Orders;
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i Operational Memos and Directives.
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No unacceptable conditions were identified.
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4.
Surveillance Testing Selected completed surveillance tests were reviewed to verify that the tests were completed as scheduled, test results were reviewed by supervisory staff and forwarded for management review, and that appropriate corrective actions were initiated as required for identified deficiencies.
Portions of selected ongoing surveillance activities were observed to verify that approved procedures were used, the work was performed by qualified personnel, that test instrumentation was calibrated, and that redundant systems for components were available for service if required. Activities reviewed included the following:
Procedure 636.4.003, Revision 12, October 28,1981, " Diesel
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Generator 20 percent Load Test", completed March 5,1982.
Special Procedure SP 82-024, " Core Spray Pipe Flush", completed
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March 8, 1982.
Procedure 619.3.016, Revision 5, September 23,1981, "High
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Drywell Pressure Scram Test and Calibration", completed March 9, 1982.
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Procedure 645.4.001, Revision 14, October 28,1981, " Fire Pump Operability Test", completed March 17, 1982.
5.
Review of Periodic and Special Reports Periodic and special reports submitted by the licensee pursuant to Technical Specification 6.9.1 were reviewed by the inspector. This review included the following considerations: the report includes the infonnation required to be reported to the NRC; planned corrective actions are adequate for resolution of identified problems; and that the reported infon':ation is valid. Within the scope of the above, the following periodic reports were reviewed by the inspector.
October 1981 Monthly Operating Data Report
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November 1981 Monthly Operating Data Report December 1981 Monthly Operating Data Report
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January 1982 Monthly Operating Data Report
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6.
Exit Interview l
At periodic intervals during the course of this inspection, meetings i
were held with senior facility management to discuss inspection scope and findings. A summary of inspection findings was presented to facility management at the conclusion of the inspection.
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