ML19312B899

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Conformance W/Asme Section Xi:Inservice Exam.
ML19312B899
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 10/01/1976
From:
DUKE POWER CO.
To:
Shared Package
ML19312B898 List:
References
PROC-761001, NUDOCS 7911250085
Download: ML19312B899 (2)


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O-Attachment 1 OCONEE NUCLEAR STATION UNIT 1 CONFORMANCE WITH ASME SECTION XI INSERVICE EXAMINATION 9

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7 911250 OI

3 OCONEE NUCLEAR STATION UNIT 1 CONFORMANCE WITH ASME SECTION XI INSERVICE EXAMINATION The Oconee 1 inservice examination of Duke Power Class A, B, and C piping and components (corresponding to ASME Boiler and Pressure Vessel Code Section III Class 1, 2, and 3, respectively) will be conducted in accordance with 10CFR 50.55 a as amended February, 1976 with the following exceptions:

(1) The design and access provisions for inservice examination of Oconee 1 considered principally the code requirements for inspection of the reactor coolant pressure boundary since the ASME Code,Section XI, 1970 edition did not address Class B and Class C piping and components at the time engineering design was completed. Therefore, Class B and C piping and components will be examined as accessibility permits. Inaccessible piping and components include, but are not limited to, those components permanently insulated; those components located in trenches, chases or other areas to which access would necessitate the removal of structures and/or other piping or components; and piping welds located within penetrations. Visual examinations performed during the code required system pressure tests will serve to detect degradation, if any, of the structural integrity of components with limited access for direct examination.

(2) Class B and C piping and components whose pressurization or pressure measurement is impractical will be examined under conditions as closely approximating Code requirements as possible. Visual examinations will be conducted as accessibility permits.

(3) The examination of Class B and C piping and components whose operation is not necessary for the safe shutdown and cooldown of the Reactor Coolant System and whose inspection would create excessive radiation exposure will be considered to be impracticable.

(4) Since South Carolina is not an ASME Code state, the inservice examination will not be witnessed by an Authorized Inspector.

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