ML19326C257
| ML19326C257 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/07/1976 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326C251 | List: |
| References | |
| NUDOCS 8004220825 | |
| Download: ML19326C257 (1) | |
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IS-261 Item Component Exception 6.4 Bolting 29 Not Applicable 6.6 Integrally Welded Not Applicable 4.2.3 he structural integrity of the reactor coolant system boundary shall be maintaiced 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, *he 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. His will be verified by visual inspection to detemine 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.
He inspection of those core barrel to lower grid cylinder locking caps not readily visible (due to guide block interference) may be omitted provided the adjacent thermal shield to lower grid cylinder locking caps are inspected.
he core barrel to core support shield locking caps will be inspected each refueling shutdown.
4.2.5 Sufficient records of each inspection shall be kept to allow comparison and evaluation of f" tare inspections.
4.2.6 Complete surface and volumetric examination of the reactor coolant pump flywheels will be conducted coincident with refueling or maintenance shut' downs such that within a 10 year period after start-up all four reactor coolant pump flywheels will be examined.
4.2.7 Vessel specimens will be withdrawn according to a schedule which may_ be raodified to coincide with refueling or maintenance shutdowns.
As a minimum requirement the withdrawal schedule will comply with ASTM-E-185-70.
Bases he surveillance program has been developed to comply with Section XI of the ASVd Boiler and Pressure Vessel Code Inservice Inspection of Nuclear Reactor Coolant Systems,1971, including 1971 Winter Addenda edition.
The vessel specimen surveillance program will be based on equivalent exposure years which will assure that the first sample should be removed near the 500 NDIT shift point and the last sample should be removed near the end of the vessel design life.
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