ML20091P731
| ML20091P731 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/25/1995 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20091P725 | List: |
| References | |
| NUDOCS 9509010321 | |
| Download: ML20091P731 (3) | |
Text
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REACTOR COOLANT SYSTEM 3/4.4.~10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in-accordance with Specification 4.4.10.1.
APPLICABILITY: ALL MODES ACTION:
a.
With the structural integrity of any ASME Code Class 1-component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations, b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.
c.
With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.
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SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to'the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.*
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- For reactor coolant pump 2P32A, 'the ultrasonic volumetric examination of the
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areas of higher stress concentration at the bore and keyway may be extended through the 2R12 refueling outage.
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ARKANSAS - UNIT 2' 3/4 4-26 Amendment No. 14 4, 4
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6 MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFORMATION ONLY)
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REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY: ALL MODES ACTION:
a.
With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the af fected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations, b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.
c.
With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.
SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975 1 l
- for reactor coolant pump 2P32A. the ultrasonic volumetric examination of the areas of hicher stress concentration at the bore and keyway may be extended throuch the 2R12 refuelinc outage.
ARKANSAS - UNIT 2 3/4 4-26 Amendment No. 444,