ML19340A160
| ML19340A160 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/24/1976 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19340A159 | List: |
| References | |
| NUDOCS 8001100628 | |
| Download: ML19340A160 (1) | |
Text
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e 4.2.10 For Unit 1, Cycle 3 operation, the surveillance capsules will-be' removed irom the reactor vessel and the provisions of Specification 4.2.9 will be revised prior to-Cycle 4 operation.
-For Unit 2, Cycle 2 operation, the surveillance capsules will be
. removed from the reactor vessel and the provisions of Specifica-tion 4.2.9 will be revised prior to Cycle 3 operation. For Unit 3, Cycle 2 operation, the surveillance capsules will be removed' from the reactor vessel and the provisions of Specification 4.2.9 will be revised prior to Cycle 3 operation.
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.
4.2.12 To assure that reactor internals vent valves are not opening during operation, all vent valves will be inspected during.each refueling i
outage to confirm that no vent valve is stuck open and that each valve operates freely.
i Bases j
r The surveillance program " - % en developed to comoly with Section XI of the ASME Boiler and Pressur 1 Code. Inservice
,ection of Nuclear Reactor 1
Coolant Systems, 1970,
_coing 1970 winter adde edition. The program places major emphasis on the area of highest strem. concentrations and on areas where fast neutron irradiation might be sufficient to change material properties.
l The reactor vessel specimen surveillance program for Unit 1 and Unit 2 is based on equivalent exposure times of 1.8, 19.8, 30.6 and 39.6 years.
The contents of the different type of capsules are defined below.
0 0
A Type B Tvoe es e.s J U Weld Material HAZ Material 7
g-HAZ Material Baseline Materi a 1]
_ h
_ k "A
a r
Baseline Material a
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 stainless 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.
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