IR 05000269/1978032

IE Insp Repts 50-269/78-32,50-270/78-30 & 50-287/78-32 on 781127-30.No Noncompliance Noted.Major Areas Inspected: Licensee Event Repts,Licensee Actions on Open Items

ML15223A371
Person / Time
Site:	Oconee
Issue date:	12/06/1978
From:	Jape F, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML15223A368	List: IR 05000269/1978032
References
50-269-78-32, 50-270-78-30, 50-287-78-32, NUDOCS 7901100429
Download: ML15223A371 (4)

Text

tp'ftREG,,UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.:

50-269/78-32, 50-270/78-30 and 50-287/78-32 Docket Nos.:

50-269, 50-270 and 50-287 License Nos.:

DPR-38, DPR-47 and DPR-55 Licensee: Duke Power Company Post Office Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:

Oconee 1, 2 and 3 Inspection at:

Oconee Nuclear Station Inspection conducted:

November 27-30, 1978 Inspector: F. Jape Approved:

AF. o/24//

R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on November 27-30, 1978 (Report Nos. 50-269/78-32, 50-270/78-30 and 50-287/78-32)

Areas Inspected:

Routine, unannounced inspection of licensee event reports, licensee actions on IEC's and open item The inspection involved 36 man hours onsite by one NRC inspecto Results:

Of the three areas inspected, no items of noncompliance or devia tions were identifie z1A 9

RII Report Nos. 50-269/78-32, 50-270/78-30 and 50-287/78-32 I-1 DETAILS I Prepared by:

7 *

,4

/

F. Jape, Reactor Inspctor Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection:

November 27-30,-1978 Reviewed by: 4 __/

R. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Persons Contacted

• 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, Licensing T. D. Curtis, Reactor Engineer J. T. Campbell, Operating Engineer, Unit 2 W. M. McClain, Procedure Engineer H. W. Morgan, Shift Supervisor R. Gillespie, Assistant Engineer F. Siurua, Jr. Engineer

• H. R. Lowery, Operating Engineer

• Denotes those present at the exit intervie.

Licensee Action on Previous Inspection Findings Not inspecte.

Unresolved Items No new unresolved items were identifie.

Management Exit Meeting The inspector met with J. E. Smith and those denoted in-Paragraph I at the conclusion of the inspection on November 30, 1978. -The inspection findings were discussed. The findings were acknowledged by licensee management without significant commen The annual environmental reporting requirement, specified in Technical Specification 6.6.1.5, was discusse RII Report Nos. 50-269/78-32, 50-270/78-30 and 50-287/78-32 1-2 5. Review of Licensee Event Reports The inspector performed an in-office review of the non-routine 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 the event and any generic implications. In additioh, while at the site, 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 circum stances 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 Specification The following event reports were reviewed:

RO-269/78-15, Startup Transformer, CTI, Inoperable RO-269/78-19, Control Rod Stator, Inoperable RO-270/78-9, Control Rod 6, Group 4 RO-287/78-11, Instrumentation and Control Battery Inoperable In-Core Detector Uncertainty Values Duke Power Company was informed by B&W, NSSS vendor, that the uncertainty values associated with the in-core detectors were too small and should be increased. The in-core detectors are used to determine compliance with quadrant power tilt and imbalance limits. Follow-up on this item revealed the following:

a. DPC was informed by the NSSS vendor by letter dated May 1, 197 New, corrected uncertainty values were incorporated into procedure IP/1, 2 and 3/A/600/1, Periodic Instrument Surveil lance on May 11, 197 c. Implementation of the revised procedure began May 11, 197 The inspector verified the procedure change through examination of the master copy of the procedur. Reactor Protection System Ground Continuity A potential problem was identified by the NSSS vendor concerning loss of the ground connection for the NI/RPS system. Duke P r Company conducted an evaluation of the Oconee design and conel that a loss of ground could not occur without either causing a channel trip indica tion or being discovered during normal instrument surveillanc RII Report Nos. 50-269/78-32, 50-270/78-30 and 50-287/78-32 1-3 An examination of the RPS cabinets for Unit 2 was conducted by the inspector. The cabinets were found to be bonded together by means of multiple 3/8 inch bolts, and each channel is hard-wired to the instru ment ground. Thus, with multiple ground paths available, continuous grounding of the NI/RPS channels appears to be assured. The initial notification of the potential problem from the NSSS vendor was received on March 8, 1978 by telephone and by letter dated March 9, 1978. DPC notified NRC, Region II on March 8, 1978 of the problem and submitted their evaluation to NRC, Region II by letter dated April 11, 197. IE Circulars The inspector verified that appropriate action had been taken by licensee personnel on the following IE Circulars:

IEC 78-9, Arcing of GE Company, Size 2 Contractors IEC 78-13, Inoperability of Multiple Service Water Pumps IEC 78-16, Limitorque Valve Actuators IEC 78-18, UL Fire Test