ML14077A131

Special Inspection Charter to Evaluate the Abnormal Rotation of the Piston Crankshaft Bearings on the Catawba Unit 1 Diesel Generators

ML14077A131
Person / Time
Site:	Catawba
Issue date:	03/18/2014
From:	Mccree V Region 2 Administrator
To:	Joseph Austin NRC/RGN-II/DRP/RPB4
References
Download: ML14077A131 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 March 18, 2014 MEMORANDUM TO: Joseph Austin Senior Resident Inspector, Harris Division of Reactor Projects FROM: Victor M. McCree RA/

Regional Administrator

SUBJECT:

SPECIAL INSPECTION CHARTER TO EVALUATE THE ABNORMAL ROTATION OF THE PISTON CRANKSHAFT BEARINGS ON THE CATAWBA UNIT 1 DIESEL GENERATORS You have been selected to lead a Special Inspection to assess the circumstances surrounding the abnormal rotation of the piston crankshaft bearings on the Unit 1 diesel generators (DGs) at the Catawba Nuclear Station. Your onsite inspection should begin on March 25, 2014.

Alejandro Alen will be assisting you in this inspection. Robert Wolfgang, Senior Mechanical Engineer, NRR, will also be available to assist you in this inspection via telephone.

A. Basis During planned maintenance on March 4, 2014, Catawba discovered that the #7 connecting rod bearing had rotated from its normal horizontal orientation on the 1A DG. Subsequently, on March 10, 2014, during an extent of condition evaluation on the 1B DG, Catawba identified that the #1 connecting rod bearing had rotated. Both of these conditions necessitated bearing replacement for investigation and to assure continued operability of the engine. As stated in their written NOED request, the licensee has subsequently determined that the as-found condition of the bearing did not challenge the ability of the bearing to perform its function.

In accordance with Management Directive (MD) 8.3, NRC Incident Investigation Program, deterministic and conditional risk criteria were used to evaluate the level of NRC response for this operational event. Through review of the MD 8.3 deterministic criteria, the staff concluded that this event could involve possible adverse generic implications or repetitive events involving safety related equipment. The conditional core damage probability (CCDP) for this event was in the overlap region between a Special Inspection and an Augmented Inspection. In consultation with NRR, Region II determined that the appropriate level of NRC response is a Special Inspection.

This Special Inspection is chartered to identify the circumstances surrounding the rotated bearings on the 1A and 1B DGs, review the licensees actions following discovery of the condition, assess the licensees maintenance practices, evaluate the history of DG bearing failures at Catawba, assess the licensees conclusions on the operability of a diesel with a rotated bearing and evaluate operating experience.

CONTACT: Gerald McCoy, RII/DRP 404-997-4551

J. Austin 2 B. Scope The inspection is expected to perform data gathering and fact-finding in order to address the following:

1. Develop a history of bearing issues on the Catawba DGs including a detailed sequence of events from the 2006 bearing failure of the 1A DG until the 1B DG was returned to service after the replacement of the #1 piston crankshaft bearing.

2. Review and evaluate the licensees causal evaluation related to this event, including the dimensional tolerances between different bearings and the differences in bearings from different vendors.

3. Review and assess the licensees testing and maintenance practices for the DGs on both units.

4. Review and evaluate the licensees compliance with vendor recommendations regarding maintenance and operation of the DGs as it relates to bearing performance.

5. Assess licensee effectiveness in identifying previous bearing-related issues on the diesel generators at Catawba, evaluating the cause of these problems, and implementation of corrective actions to resolve identified problems.

6. Review and evaluate the licensees immediate corrective actions taken related to the issue and the extent of condition completed for the Unit 2 DGs.

7. Review and evaluate the licensees conclusion that the DG could remain operable but degraded with the bearing misaligned less than 45 degrees.

8. Assess the licensees actions resulting from vendor technical bulletins and industry operating experience concerning bearings on Delaval engines.

9. Collect data necessary to support completion of the significance determination process, if applicable.

10. Identify any potential generic safety issues and make recommendations for appropriate follow-up action (e.g., Information Notices, Generic Letters, and Bulletins).

C. Guidance Inspection Procedure 93812, "Special Inspection," provides additional guidance to be used during the conduct of the Special Inspection. Your duties will be as described in Inspection Procedure 93812. The inspection should emphasize fact-finding in its review of the circumstances surrounding the event. Safety or security concerns identified that are not directly related to the event should be reported to the Region II office for appropriate action.

J. Austin 3 You will report to the site, conduct an entrance, and begin inspection no later than March 25, 2014. A daily status briefing of Region II management will be provided beginning the second day on-site at approximately 4:00 p.m., Eastern Daylight Time (EDT). In accordance with IP 93812, you should promptly recommend a change in inspection scope or escalation if information indicates that the assumptions utilized in the MD 8.3 risk analysis were not accurate. A report documenting the results of the inspection should be issued within 45 days of the completion of the inspection. The report should address all applicable areas specified in section 3.02 of Inspection Procedure 93812. At the completion of the inspection you should provide recommendations for improving the Reactor Oversight Process baseline inspection procedures and the Special Inspection process based on any lessons learned.

This Charter may be modified should you develop significant new information that warrants review. Should you have any questions concerning this Charter, contact Gerald McCoy at 404-997-4551.

Docket No. 50-413 License No. NPF-35

_________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DRP RII:DRP RII:ORA RII:ORA SIGNATURE /VIA E-Mail/ /RA/ //RA/ /RA/ /RA/

NAME JAustin GMcCoy RCroteau LWert VMcCree DATE 3/14/2014 3/14/2014 3/14/2014 3/14/2014 3/18/2014 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO