ML20065A883

Revised Tech Spec Change Re Acoustic Emission Exam Methodology to Test Reactor Coolant Pump Flywheels

ML20065A883
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/15/1983
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20065A881	List: 1CAN028313, Application to Amend License DPR-51,updating 790222 Request to Change Tech Specs Re Acoustic Emission Exam of Reactor Coolant Pump Flywheel ML20065A883
References
NUDOCS 8302220280
Download: ML20065A883 (1)

Text

o IS-261 Item Component Exception 6.4 Bolting 20 Not Applicable 6.6 Integrally Welded Not Applicable Valve Supports 4.2.3 The structural integrity of the reactor coolant system boundary shall be maintained at the level required by the original acceptance standards throughout the life of the station. Any evidence, as a result of the tests outlined in Table 15-261 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 throughout 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 inspected after hot functional testing and whenever the internals are removed from the vessel during a refueling or maintenance shutdown. The 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 Surface and volumetric examination of the reactor coolant pump flywheels will be conducted coincident with refueling or

( maintenance shutdowns such that during 10 year intervals all four

, reactor coolant pump flywheels will be examined. Such l

examinations will be performed to the extent possible through the access ports, i.e., those areas of the flywheel accessible without motor disassembly. The surface and volumetric examination may be accomplished by Acoustic Emission Examination as an initial examination method. Should the results of the Acoustic Emission Examination indicate that additional examination is necessary to ensure the structural integrity of the flywheel, then other appropriate NDE methods will be performed on the area of concern.

4.2.7 The reactor vessel material irradiation surveillance specimens removed from the reactor versel in 1976 shall be installed, irradiated in and withdrawn from the Davis-Besse Unit No. 1 reactor vessel in accordance with the schedule shown in Table 4.2-1. Following withdrawal of each capsule listed in l

' Table 4.2-1, Arkansas Power & Light Company shall be responsible for testing the specimens and submitting a report of test results in accordance with 10CFR50, Appendix H.

77 R3022202BO 030215 PDR ADOCK 05000313 p PDR

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