10 CFR 50.55a, Paragraph (f)(4)(ii) requires, in part, Inservice tests to verify operational readiness of pumps and valves, whose function is required for safety . . . must comply with the requirements of the latest edition and addenda of the Code
incorporated by reference in paragraph (b) of this section. . . . The applicable Code for the current Clinton Power Station Inservice Test Program interval for testing valves is the 1989 Edition of American Society of Mechanical Engineers (
ASME)
Section XI, Subsection IWV, Inservice Testing of Valves in Nuclear Power Plants, which references the ASME/ANSI Operations and Maintenance Code (OMa 1988, Part 10). OMa 1988, Part 10, Paragraph 4.1 requires, in part, that valves with remote position indicators shall be observed locally at least once every 2 years to verify that the valve operation is accurately indicated. In addition, OMa 1988, Part 10, Paragraph 4.3.2.2 requires, in part, that each
check valve shall be exercised or examined in a manner which verifies obturator travel to the closed, full-open or partially open position required to fulfill its function. Contrary to the above, the licensee incorrectly removed nine
excess flow check valves (1CM002A, 1CM002B, 1CM003A,
1E22-F330,
1E22-F332,
1E51-F377A,
1E51-F377B, 1SM008 and 1SM009) from its Inservice Testing Program in 2002 and subsequently failed to perform testing required by the Code. The licensee entered this violation into its
CAP as
AR 00846540. The finding was determined to be of very low safety significance (Green) because the finding was a design or qualification deficiency determined not to result in loss of operability or availability
