ML20141H262
| ML20141H262 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/18/1997 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20141H260 | List: |
| References | |
| NUDOCS 9705230255 | |
| Download: ML20141H262 (3) | |
Text
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 mainta's.ed in accordance with Specification 4.4.10.1.
APPLICABILITY: ALL MODES
)
ACTION:
With the structural integrity of any ASME Code Class 1 a.
componentis) 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.
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.*
i
- The ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway of the flywheels for all four reactor coolant pumps nay be extended through completion of the 2R13 refueling outage.
9705230255 970418 PDR ADOCK 05000368 P
PDR ARKANSAS - UNIT 2 3/4 4-26 Amendment No. M4,46,
e a
e e
s MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFORMATION ONLY) i
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 naintained 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 i
its limit or isolate the affected component (s) prior to j
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 I
1975.*
- For reactor ccolant pump 2P3J?., t-he-The ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway of the gywheels for all four reactor coolant pumps may be extended through goInpletion of the GRF2 2R13 refueling outage.
ARKANSAS - UNIT 2 3/4 4 26 Amendment No. -144,-146,