ML19326C418
| ML19326C418 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/19/1976 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326C416 | List: |
| References | |
| NUDOCS 8004230548 | |
| Download: ML19326C418 (1) | |
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.IS-261 Item Component Exception 6.4 Bolting 20 Not Applicable 6.6 Integrally Welded Not Applicable Valve Supports 4.2.3 Le structural integrity of the reaccor coofant system boundary shall be maintained at the level required by the original accep-tance standards throughout the life of the station. Any evidence, as a result of the tests outlined in Table IS-261 of Section XI of the code, that defects have developed or grown, shall be investigated.
4.2.4 To assure the structural integrity of the reactor internals through-out the life of the unit, the two sets of main internals bolts (connecting the core barrel to the core support shield and to the lower grid cylinder) shall remain in place and under tension. This will be verified by visual inspection to determine that the welded bolt locking caps remain in place. All locking caps will be inspect-ed after hot functional testing and whenever the internals are removed from the vessel during a refueling or maintenance shutdown.
'Ihe core barrel to core support shield caps will be inspected each refueling shutdown.
4.2.5 Sufficient records of each inspection shall be kept to allow comparison and evaluation of future inspections.
4.2.6 Complete surface and volumetric examination of the reactor coolant pump flywheels will be conducted coincident with refueling or maintenance shutdowns such that within a 10 year period after start-up all four reactor coolant pump flywheels will be examined.
4.2.7 Reactor vessel specimens shall be removed and examined, to deter-mine changes in material properties, at speumen exposures (E>1Mev) equivalent to 3, 9.5, 16 and 22.5 Effective Full Power Years (EFPY) of operation. This withotawal schedule may be modified to coincide with those refueling outages or plant shutdowns, when the reactor head is removed, most closely approaching the withdrawal schedule.
Results of these examinations shall be used to update Technical 1
Specification 3.1.2.
Specimens not subjected to destructive testing after the first 0.93 EFPY of Cycle 1 may be removed and stored during the remainder of Cycle 1, but shall be re-installed prior to Cycle 2.
Bases The su7eillance program has been developed to comply with Section XI of the ASME boiler and Pressure Vessel Code Inservice Inspection of Nuclear Reactor Coolaat Systems, 1971. including 1971 Winter Addenda Edition.
The number of reactor vessel specimens and the frequencies for removing and testing these specimens are'provided to assure compliance with the i
requirements of Appendix H to.10CFR Part 50.
77 8004230 N 8