ML19340A174
| ML19340A174 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/22/1976 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19340A173 | List: |
| References | |
| NUDOCS 8001100661 | |
| Download: ML19340A174 (1) | |
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l.J' 4.2.10 For Unit 1, the provisions of Specification 4.2.9 will be revised prior to Cycle 4 operation due to operation during Cycle 3 with the reactor vessel surveillance specimens removed from the reactor vessel.
For Unit 3, the provisions of Specification 4.2.9 will be revised prior to Cycle 2 operation due to operation during a portion of Cycle 1 with the reactor vessel surveillance specimens removed from the reactor vessel.
4.2.11 During the first two refueling periods, two reactor coolant system piping elbows shall be ultrasonically inspected along their longitudinal welds (4 inches beyond each side) for clad bonding and for cracks in both the clad and base metal. The elbows to be inspected are identified in B&W Report 1364 dated December 1970.
Bases The surveillance program has been developed to comply with Section XI of the ASME Boiler and Pressure Vessel Code, Inservice Inspection of Nuclear Reactor Coolant Systems, 1970, including 1970 winter addenda, edition.
The program places major emphasis on the area of highest stress concentrations and on areas where fast neutron irradiation might be sufficient to change material properties.
The reactor vessel specimen surveillance program for Unit I and Unit 2 is based on equivalent exposure times of 1.8, 19.8, 30.6 and 39.6 years. The l
contents of the different type of capsules are defined below.
l A Type B Type Weld Material HAZ Material RAZ Material Baseline Material Baseline Material For Unit 3, the Reactor Vessel Surveillance Program is based on equivalent exposure times of 1.8, 13.3, 26.7, and 30.0 years.
The specimens have been selected and fabricated as specified in ASTM-E-185-72.
Early inspection of Reactor Coolant System piping elbows is considered desirable in order to reconfirm the integrity of the carbon steel base metal when explosively clad with sensitized itainless steel.
If no degradation is observed during the two annual inspections, surveillance requirements will revert to Section XI of the ASME Boiler and Pressure Vessel Code.
4.2-3 8001100 6 /