IR 05000269/1979011

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IE Insp Repts 50-269/79-11,50-270/79-11 & 50-287/79-11 on 790301-29.No Noncompliance Noted.Major Areas Inspected:Plant Operations,Followup of Info Notices,Physical Security & LER
ML19269D883
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 04/28/1979
From: Cantrell F, Jape F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19269D874 List:
References
50-269-11, 50-269-79-11, 50-270-79-11, NUDOCS 7906200279
Download: ML19269D883 (6)


Text

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' UNITED STATE 3 tS NUCLEAR REGULATORY COMMISSION og . . REGION il g u 101 M ARIETTA STREET, N.W.

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'8 ATLANTA, GEORGIA 30303 ' %,...../ Report Nos. 50-269/79-11, 50-270/79-11 and 50-287/79-11 Licensee: Duke Power Company P. O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Oconee Nuclear Station Docket Nos.

50-269, 50-270 and 50-287 License Nos. DPR-38, DPR.47 and DPR-55 Inspection at Oconee Site near Seneca, South Carolina and Corporate Office in Charlotte, North Carolina.

Inspector: oo (<fn,, fys vw app F. Jape Date Signed 4 /? C'/ Cr Approved by: [[[ / tf F. S. Cant rell, Actitg Section Chief, RONS Date Signed " Branch SUMMARY Inspection on March 1-29, 1979.

Areas Inspected This routine, unannounced inspection involved 82 inspector-hours onsite in the areas of plant operations; followup of IEC's and IE Information Notices, ' physical security; licensee event reports and witness of selected periodic tests.

, Results Of the five areas inspected, no apparent items of noncompliance or deviations were identified.

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. . . . . DETAILS 1.

Persons Contacted Duke Power Company

  • J. E. Smith, Station Manager
  • J. N. Pope, Superintendent of Operations
  • R. M. Koehler, Superintendent of Technical Services
  • R. T. Bond, Licensing and Projects Engineer
  • D. J. Vito, Associate Engineer, Licensin; B. Carney, Assistant Engineer, Mechanical Maintenance
  • J. Brackett, Senior QA Engineer H. W. Morgan, Shif t Supervisor J. W. Herring, Shift Supervisor T. D. Patterson, Shift Supervisor G. B. Jones, Shift Supervisor D. W. Yoh, Shift Supervisor L. C. Evans, Assistant Shift Supervisor D. L. Gordan, Assistant Shift Supervisor R. T. Scott, Assistant Shif t Supervisor W. R. Pollard, Assistant Shift Supervisor D. F. Roth, Assistar t Shif t Supervisor W. A. Horton, Assistant Shift Supervisor F. F. Owens, Assistant Shift Supervisor D. J. Phillips, Assistant Shift Supervisor C. M. Sheridon, Assistant Shift Supervisor E. G. LeGette, Assistant Shift Supervisor O. C. Kohler, Assistant Shift Supervisor P. J. Chudzik, Assistant Shift Supervisor E. A. Force, Assistaot Shift Supervisor S. M. Pryor, Assistant Shif t Supervisor L. L. Howell, Assistant Shif t Supervisor

' Other licensee employees contacted included 4 technicians, 20 operators and 3 office personnel.

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  • Attended exit interview.

2.

Exit Interview i The inspection scope and fin 4ings were summarized on March 9, 16 and April 17, 1979, with those., persons indicated in paragraph I above. The inspection findings were acknowledged by licensee management without " significant comment.

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Licensee Action on Previous Inspection Findings Not inspected.

4.

Unresolved Items No unresolved items were identified during this inspection.

5.

Plant Operations The inspector reviewed plant operations to ascertain conformance with regulatory requirements, technical specifications and administrative directives. The control room logs, shift supervisors logs and the removal and restoration record books for all three units were reviewed.

Interviews with a number of plant operations personnel were held on the day and night shifts.

Supervisor and control room operator actions were observed during the shift and at shift change. The actions and activities were conducted as presciihed in Section 3.08 of the Station Directives. The number of licensed personnel on each shift met or exceeded the minimum required by Technical Specification C.1.1.3.

Operators were responsive to annunciator alarms and appeared to be cognizant of plant status.

Throughout the inspection period, the following areas were toured by the inspector: a.

Unit 3 Reactor Building b.

Unit 1 - 2 Spent Fuel Pool c.

Turbine Building , d.

Auxiliary Building e.

Rad Waste Treatment Facility - f.

Electrical Equipment Rooms g.

Cable Spreading Rooms s h.

Reactor Building Purge Rooms Observations were made during the tours of housekeeping and cleanliness, ongoing activities, security, equipment status and radiation control practices.

In general, housekeeping and cicanliness were found to be satisfactory. Security and radiation control practices were adhered to during the periods of observation. There were no fluid leaks, or 2251 115 .

. . .. . e . -3-excessive piping vibrations noted during the tour. Lock out tags on equipment required to be tagged were found as specified by Station Directive 3.1.1.

Within the areas inspected, no fire hazards were obse rved.

t 6.

Review of Licensee Event Reports The inspector performed an in-office review of nonroutine event reports to verify that the report details met license requirements, identified the cause of the event, described corrective actions appropriate for the , identified cause, adequately addressed the event and any generic implica-tions.

In addition, for those reports marked with an asterik, the inspector examined selected operating and maintenance logs and records and internal incident investigation reports. Personnel were interviewed to verify that the report accurately reflected the circumstances of the event, that the corrective action had been taken or responsibility assigned to assure completion and that the event was reviewed by the licensee as stipulated in the Technical Specifications. The following event reports were reviewed:

  • R0-269/79-4, Inoperable Hydraulic Suppressor
  • R0-269/79-5, CRD Breaker Failed to Trip During On-Line Test
  • R0-269/79-6, Radiation Monitors IRIA 47, 48 and 49 Inoperable

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  • R0-269/79-7, Failure to Verify Operability of Keowee Unit 1
  • R0-269/79-8, RB Narrow Range Pressure Transmitter Out of Calibration in Non-Conservative Direction
  • R0-270/79-1, RB Narrow Range Pressure Transmitter Out of Calibration in Non-Conservative Direction 7.

Witnessing Periodic Testing ' Performance of periodic tests were observed and reviewed throughout the inspection period to verify that the activities were accomplished using approved procedures and the work was done by qualified personnel.

Limiting conditions for operations were examined to ensure that while the equipment was removed from service, the appropriate conditions of technical specifications were followed.

The following were used as acceptance criteria: . a.

Administrative Policy Manual, Sections 2.3 and 3.2 2251 116

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Station Directives 3.2.1 and 3.2.2 Technical Specification, Section 4.0 c.

Within the areas inspected, no items of noncompliances or deviations were identified. The following periodic tests were witnessed: PT 1/A/203/06, LPI System Pump Performance PT 2/A/204/07, RBS Pump Performance Test PT 2/A/290/05, Main Turbine Trip Test PT 3/A/600/15, Control Rod Movement PT 1/A/150/15A, RB Spray Valves Functional - In each of the above tests, the test and measuring equipment used for data collection was verified through a records review, to be accurate and properly calibrated. Review of data revealed each test met the acceptance criteria.

8.

Physical Security Throughout the inspection period, implementation of the physical security program was observed. The areas inspected includes, physical security organizations, physical barriers, access and badge control and pat down searches.

No items of noncompliances or deviations were identified.

The review of the physical security organization was completed by verify-ing the presence of the physical security member who has the authority to direct shift activities. This item was verified on March 7, shifts 1 and 2; March 8, shifts 2 and 3; March 13, shifts 1, 2 and 3; and March 15, shifts 1, 2 and 3.

' Inspection of physical barriers consisted of walking the protected area fence on March 13, and observing that all gates were locked closed, and the isolation zone was free of objects. Within the building, vital area door barriers were noted to be locked closed throughout the inspection period.

. Access control was checked each time the inspector entered the protected Persons and packages were observed being searched. This review area.

also included observation that all persons within the protected area properly displayed their identification badge. Also throughout the inspection period, vehicles entering the protected area were observed t 2251 117 < ...,--m --. .,

' . - - - .. .. . . -5- . being searched in accordance with regulatory requirements. Unattended vehicles within the protected area were checked to verify if they were properly disabled. This check was conducted on the Number 3 shift on March 8 and 13.

To determine compliance with escorting procedures, the inspector spot . checked visitors and their escorts during the report period. The escort is required to remain with the visitor at all times and keep control of the visitor. The procedures and requiements were followed during the period of observation.

9.

IEC 79-02, Failure of 120 Volt Vital AC Power Supplies IEC 79-02, dated January 16, 1979, was received and reviewed by the licensee. No written response was requested to this circular, however, DPC prepared internal correspondence, dated February 23, 1979, docu-menting the review and followup of this item.

10.

IE Information Notices IE Information Notices, 79-1, 79-3, 79-4, and 79-5 have been received by the licensee. These items do not require a written response, the licensee treats these notices the same as IE circulars. That is, they are routed to the appropriate group within the company and an informal, internal written response is on file.

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