IR 05000269/1978008
| ML19316A191 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/13/1978 |
| From: | Jape F, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19316A185 | List: |
| References | |
| 50-269-78-08, 50-269-78-8, 50-270-78-08, 50-270-78-8, 50-287-78-08, NUDOCS 7911280726 | |
| Download: ML19316A191 (6) | |
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UNITED STATES
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Report Nos.:
50-269/78-8, 50-270/78-8 and 50-287/78-8 Docket Nos.:
50-269, 50-270 and 50-287 License Nos.: DPR-38, DPR-47 and DPR-55 Licensee:
Duke Power Company Box 2178 South Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee 1, 2 and 3 Inspection at:
Oconee Nuclear Station Inspection conducted:
April 4-7, 1978 Inspector:
F. Jape Accompanying Personnel:
None Reviewed by:
F. 0 -
/Mh6 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on April 4-7, 1978: (Report Nos. 50-269/78-8, 50-270/7.8-8 and 50-287/78-8)
Areas Inspected: Routine, unannounced inspection to followup on previous items of noncompliance, licensee event reports, unresolved items and IEB's, and review of plant operations, and organization and administration.
The inspection involved approximately 37 inspector-hours on site by one NRC inspector.
R_esults:
Of the six areas inspected, no items of noncompliance or deviations were identified.
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RII Rpt. Nos. 50-269/78-8, 50-270/78-8 and 50-287/78-8 I-1 DETAILS I Prepared by:
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F.VJape,Reactorfy6spe6 tor
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Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: April 4-7, 1978 Reviewedby:_[.6.
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R. C. Lesis, Chief Date
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Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
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1.
Persons Contacted
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Duke Power Company (DPC)
J. E. Smith, Station Manager
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- J. Davis, Superintendent of Maintenance R. M. Koehler, Superintendent of Technical Services
- W. M. Harris, Operating Engineer
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G. A. Ridgeway, Operating Engineer N. F. Edwards, Operating Engineer B. J. Earnhard, Operating Engineer D. W. Yoh, Fuel Handling Supervisor B. C. Moore, Operating Engineer R. Knoerr, Associate Engineer, I&E R. Gillespie, Associate Engineer, I&E D. Taylor, Associate Engineer, I&E
- R. T. Bond, Technical Services Engineer W. P. Deal, Associate Health Physicist K. W. May, Fuel Handling Utility Operator
- R. J. Brackett, Station Senior QA Engineer Four Control Operators Four Assistant Control Operators Two Shift Supervisors Four Assistant Shift Supervisors
- Denotes ettendance at the Management Exit Meeting
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RII Rpt. Nos. 50-269/78-8, 50-270/78-8 and 50-287/78-8 I-2 2.
_ Licensee Action on Previous Inspection Findings
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a.
Noncompliance Items (1)
(Closed)
77-24-01, Item A in Notice of Deviation.
Corrective action stated in licensee's response, dated
' January 20, 1978, was verified by the inspector. Procedure HP/0/B/1000/13 has been revised to require an annual communication check with outside agencies.
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(2)
(Closed)
77-24-02, Item B in Notice of Deviation.
Corrective action stated in licensee's response, dated January 20, 1978, was verified by the inspector.
Procedure
HP/0/B/1000/13 has been revised to require, so far as
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possible, participation by off-site agencies in emergency
drills.
(3)
(Closed)
77-24-03, Item A in Notice of Violation.
Corrective action stated in licensee's response, dated
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January 20, 1978, was verified by the inspector.
Procedure HP/0/B/1010/02 was revised to include a monthly inspection of the Scott Air Packs in Unit 1 and 2 Control Room, Unit 3 Control Room and the First Aid Room.
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(4)
(Closed)
77-24-04, Item B in Notice of Violation.
Corrective actions stated in licensee's response, dated January 20, 1978, were verified by the inspector.
Procedure HP/0/B/1009/01 was revised to require a monthly battery and response check, and Station Directive 3.2.2 was revised to assign responsibility for performing these checks.
(5)
(closed)
77-24-05, Item C in Notice of Deviation.
Corrective action stated in licensee response, dated January 20, 1978, was verified by the inspector.
Station Directive 3.8.5 was revised to delete the resuscitator as part of the required emergency equipment.
(6)
(Closed)
77-24-08, Item D in Notice of Deviaticn.
Corrective actions stated in licensee's response, dated January 20, 1978, were verified by the inspector. The distribution list for the Emergency Procedure, has been revised to include those off-site participating agencies previously not on the list, and records were reviewed to
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i verify that each outside agency has been mailed a current copy of,the Emergency Procedure.
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RII Rpt. Nos. 50-269/78-8, l
50-270/78-8 and 50-287/78-8 I-3 i
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(Closed)
77-24-09, Item E in Notice of Deviation corrective
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action stated in licensee's response, dated January 20, 1978, was verified by the inspector.
Procedure HP/0/8/1000/13 was revised to require a program of various drill scenarios for different types of emergency situations.
3.
Unresolved Items No new unresolved items were identified during this inspection.
4.
Management Exit Meeting The inspector met with J. Davis, acting Station Manager, and those denoted in paragraph 1, on April 7, 1978, to discuss the inspection findings.
The finding were acknowledged by licensee management without significant comment.
5.
Review of Licensee Event Reports
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The inspector performed an in-office review of the nonroutine event reports listed below to verify that the report details met license requirements, identified the cause of the event, described corrective actions appropriate for the identified cause, adequately assessed actions appropriate for the identified cause and adequately assessed the event and any generic implications.
In addition, for those reports marked with an asterisk, 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:
RO-269/78-1, Keowee Hydro Uni-2, Field Flashing Breaker Inoperable
- RO-269/78-2, Keowee Hydro Unit 1 Not Verified Operable Within One Hour of Taking Unit 2 Out-of-Service
- RO-269/78-4, Two RBCU Simultaneously Inoperable RO-270/77-12 Primary-to-Secondary Leak BOTSG RO-270/78-1, CF Tank 2A Level Instruments Inoperable
- RO-270/78-2, RPS Channel D Flow Transmitters Inoperable R0-287/78-1, 3B DHR Cooler Outlet Valve Failed Partially Closed R0-287/78-2, FDW-108 Failed to Close Following Sample R0-287/78-3, 3 PR-9, Containment Isolation Valve Failure R0-287/78-4, 3 BS-3, BS Pump Suction Valve Inoperable t
- RO-287/78-7, 3 LPSW-123 Found Closed
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RII Rpt. Nos. 50-269/78-8,
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50-270/78-8 and 50-287/78-8 I-4 I
Followup on R0-287/77-17 was completed during this inspection.
Comments on this report were presented in Report No. 50-287/78-4.
Licensee management has decided to incorporate a precaution in the maintenance procedure for the emergency personnel hatch to require a visual check and cleaning of the sealing surfaces to aid in preventing recurrence of this event.
This item is considered resolved.
6.
IEB 78-1 and 78-2 The licensee's responses to IEB 78-1, dated February 20, 1978, and IEB 78-2, dated February 13, 1978, were reviewed and found to be responsive to the action requested.
In both cases, the proble=s described by the bulletin do not exist at the Oconee Nuclear Station.
The type relay discussed in IE Bulletin 78-1 is not utilized in safety-related systems, and there are no unprotected terminal blocks used for safety-related systems within containment as discussed in IEB 78-2.
No further action is planned for these items.
7.
Reactor System Decontamination Plans s
A discussion was held with the Superintendent of Technical Services concerning chemical decontamination of compcnents within the reactor coolant pressure boundary. He stated that, to date, chemical decontamination has not been attempted nor is planned for the near future.
8.
Organization and Administration The onsite organizational structure was reviewed and determined to be in compliance with the structure as described in the Technical Specifications (TS). Authorities and responsibilities are as delineated in the TS.
The offsite review committee membership and qualifications were reviewed and found to be in compliance with the
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applicable TS.
The Superintendent of Maintenance was recently replaced and the qualifications of the newly appointed replacement were examined and found to satisfy the position requirements as delineated by ANSI N18.1.
9.
Plant Operations The inspector reviewed plant operations to ascertain conformance with regulatory requirements, technical specifications, and administrative d irec t ives. Station logs, such as the unit supervisors log, control room operators log and the removal and restoration of station equipment records were reviewed. Interviews with a number of plant operations personnel were held on the day and night shifts.
In addition, a tour was conducted of the auxiliary building, turbine building and the Unit 1-2 Spent Fuel areas.
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RII Rpt. Nos. 50-269/78-8, 50-270/78-8 and 50-287/78-8 I-5 s
During the period of observation and inspection, all units were in power operation and while on tour of the plant accesible areas, i
observations were made regarding the plant housekeeping and cleanliness, ongoing activities, radiation control practices and security practices.
Housekeeping and cleanliness were found to be satisfactory within the radiation areas and non-radiation areas.
Security practices and radiation control practices were adhered to during the tour.
l Supervisor and control room operator actions were observed during the shift and at shift change.
The actions and activities were conducted as prescribed in Section 3.0 of the Station Directives.
Operators and shift supervisors were responsive to annunciator alarms and appeared to be aware of plant status.
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The number of licensed and non-licensed personnel on each shift was verified to meet the minimum required by TS 6.1.1.3.
Also, the 5 man fire brigade, required by TS, was verified to be met.
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