ML20137G124

Submits Info Re SER Open Item 1(c)i Identifying Pumps Affected by Static Shaft Analysis Where Rubbing Predicted & Item 1(c)ii Concerning How Mechanical Aging,Including Equipment in Mild Environ,Considered During Qualification

ML20137G124
Person / Time
Site:	Vogtle
Issue date:	08/23/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GN-694, NUDOCS 8508270182
Download: ML20137G124 (2)

Text

Georgi Power Company Rout 3 2. Box 299A Waynesborc. Georgia 30830

• Telephone 404 554 9%1 404 724-8114 Southern Company Services. Inc.

Post Office Box 2625 Birmingham, Alabama 35202 b

Telephone 205 870 6011 Vogtle Project August 23, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Ms. Elinor G. Adensam, Chief Log: GN-694 Licensing Branch #4 ,

Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 1: EQUIPMENT QUALIFICATION

Dear Mr. Denton:

The following information is offered concerning two outstanding items contained in the subject item:

e SER Item 1(c)1 Identify all pumps affected by static shaft analysis, where rubbing is predicted, and the test or documentation used to ensure operability.

GPC Response Of the BOP and NSSS pumps the RHR pump is the only pump assembly for which internal rubbing or contact during a seismic event has been analytically predicted as reported in Amendment 15. However, contact stresses have been determined analytically with results being well within allowable limits as documented in Westinghouse report ME-174. This report will be available for review during the site audit.

e SER Item 1(c)ii Clarify how mechanical aging, including equipment in mild environments, was considered during qualification. Indicate how these findings will be reflected in the maintenance and surveillance program. Indicate that mechanical aging of safety-related equipment was considered as recommended by IEEE 382-1980.

9 8508270182 850823 PDR ADOCK 05000424 E PDR

e Director of Nuclear Reactor Regulation File: X7BC35 August 23, 1985 Log: GN-694 Page 2 GPC Response Mechanical equipment qualification, including mild environments, involves a review of age sensitive critical parts for capabilities and life for incorporation into the maintenance and surveillance program. Mechanical aging of selected essential equipment is monitored through the Inservice Inspection (ISI) Program by measurement and evaluation of flow, leakage, and vibration. Results of the ISI Program will be evaluated for trends and the program will be modified as required. Concerning mechanical aging qualification for electric valve operators, Vogtle is committed to Regulatory Guide 1.73 (January 1974) which endorses IEEE 382-1972.

However, major actuator qualification programs which were performed after 1981 (MFIV and MSIV), used the IEEE 382-1980 standard for guidance.

If additional information is required on these items, we hope to provide the necessary information at the meeting scheduled with your staff on September 11, 1985.

Sincerely,

.b.

J. A. Bailey Project Licensing Manager JAB /sm xc: D. O. Foster G. Bockhold, Jr R. A. Thomas T. Johnson J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire L. Fowler M. A. Miller W. C. Ramsey B. Jones, Esquire L. T. Gucwa Vogle Project File 0053V