ML20149G806
| ML20149G806 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/27/1994 |
| From: | Rehn D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-10, NUDOCS 9411070422 | |
| Download: ML20149G806 (2) | |
Text
..
- ? '
^
Duke [tnver Cornpany
.D. L Rrits
'y Catawba Nuclear Generation Departrnent VicePresident 4800ConcordRoad (303)8313205 Olhce York, $C29745.
(803)831-3426 Fax i ' DUKEPOWER October 27,1994 '
U. S. Nuclear Regulatory Commission Attention: Document Control Desk 4
Washington, D. C. 20555
Subject:
Catawba Nuclear Station Docket Nos. 50-413 and 50-414 NRC Generic letter No. 89-10 Safety-Related Motor-Operated Valve Testing and Surveillance Schedule Extension We appreciate the opportunity to have met with your staff on October 24,1994 to discuss the status of Duke Power's Generic 12tter (GL) 89-10 program and design basis verification closure requirements. This meeting was extremely helpful in providing us a better understanding of acceptable design basis verification methods.
i The current Catawba Group 1 population is 296 valves of which 250 have had a design basis verification completed. After applying the clarification provided by your staff during this meeting, it was determined that of the total population of Catawba's Group 1 valves, 46 valves (total for both'. units) require additional evaluation relative to the design basis verification requirements of GL 89-10. It is our initialimpression, following a quick check of the 46 valves, that we will'successfully complete the design basis verification for Catawba's Group 1 valves by the committed due date of December 28,1994 (reference Duke Power letter dated October 31, 1991).
Given that we have not completed verification of the forty-six (46) valves in a rigorous fashion, we recognize the potential for an unanticipated problem as we apply that rigor. Unanticipated problems could require field verification during a refueling outage. The next scheduled outage completion date for Unit 1 is April 9,1995 '1EOC8) and November 29, 1995 for Unit 2 (2EOC7). Given the reporting requirement of GL 89-10, Supplement 6 to post notice for an extension sixty (60) days in advance, we are providing notice, by this letter, of a schedule extension to December 31, 1995 or prior to startup following refueling outage 2EOC7 for Catawba's Group 1 valves. However, it is our intent to aggressively pursue completion of the requirements for closure for these Group 1 valves by the current committed due date.
0R00n7 9411070422 941027
,A q vyK PDR ADOCK 05000413
.h p
. na cmem.,
i
.l U. S. Nuclear Regulatory Commission detober 27,1994 Page 2 We will complete our evaluation for verification of the subject 46 valves by December 1,1994 and will forward either the supporting Supplement 6 schedule date extension information or provide notice of the intention to meet the current commitment date of December 28,1994 for the remaining Group 1 valves. We will also provide, via telecom by December 2,1994, a status of design basis verifications for the remaining Group 1 valves to the appropriate Region II staff.
The current Catawba Group 2 population has 178 valves. Our current schedule requires completion of Group 2 by December 28,1998. We agree to accelerate the schedule and commit to completing all Group 2 valves for Unit 1 by the end of refueling outage IEOC9 (currently scheduled to end October 23, 1996) and for Unit 2 by the end of refueling outage 2EOC8 (currently scheduled to end May 5,1997).
Upon completion of the design basis verification of GL 89-10 Group 1 valves, we plan to submit a request for closure, pursuant to the requirements of GL 89-10.
If there are any further questions, please contact Jeff Lowery at (803) 831-3414.
Very truly yours, b
A
/
D. L. Rehn, Site Vice-President Catawba Nuclear Station 1
xc:
S. D. Ebneter, Regional Administrator, Region II j
i R. E. Martin, ONRR R. J. Freudenberger, i
Senior Resident Inspector C. A. Casto, Engineering Branch, Region II l