ML19319A753
| ML19319A753 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/23/1976 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319A750 | List: |
| References | |
| NUDOCS 7912030390 | |
| Download: ML19319A753 (4) | |
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For Unit 1, Cycle 3 operation, the surveillance capsules will 4.2.10 be removed from the reactor vessel-and the provisions of Specification 4.2.9 vill be revised prior to Cycle 4 operarian.
Yor Unit 2, Cycle 2 operation, the surveillance capsules will be removed from the reactor vessel and the provisions of Specifica-tion 4.229 will be revisea,--ior.to Cycle 3 operation., Tor 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.
i 4.2.11 During the first two refueling periods, two reactor coolant system piping elbows shall be ultrasonically inspected.along their s
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 f
1970.
4.2.12 To assure that reactor internals vent valves are rot opening during operation, all vent valves will be inspected during each refueling
~ outage to confirm that no vent valve is stuck open and that each valva operates freely.
Bases i
I The surveillance program has been developed to comply with Section XI of the j
ASME Boiler and Pressure Vessel Code Inservice Inspection of Nuclear Reactor 1
Coolant Systems, 1970, including 1970 winter addenda, edition. The program places major emphasis on the area of highest stress concentrations and on areas where f ast neutron irradiation might be suf ficient to change material properties..
4 The reactor vessel specimen surveillance program for Unit 1 and Unit 2 is i
U 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.
A Type B Type I
Weld Material HAZ Material HAZ Material Baseline Material l
g Baseline Material
For Unit 3, the Reactor Vessel Surveillance Program is based on equivalent have.been exposure times of 'LS.13.J. 26.7. and 30.0 years. - The s=~4=a==
==1-r=d and fabrie; ALM w=== Wind'in AS129-E-ISS-72.
s Early.faspection of Beactor Coolant System piping elbous.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, surveit *= requiremmes will J
. - revert to Section XI of the ASME Boiler and-Pressure Vessel Code.
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l
.4.2-3
__penhentsNos. 35, 35 & 32
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