ML051390226

Enclosure, Amd MC3308, Extending the Inspection Interval for Reactor Coolant Pump Flywheels

ML051390226
Person / Time
Site:	Summer
Issue date:	05/09/2005
From:	Martin R NRC/NRR/DLPM/LPD2
To:	Archie J South Carolina Electric & Gas Co
Martin RE, NRR/DLPM, 415-1493
References
TAC MC3308
Download: ML051390226 (2)

Text

REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.

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 500 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 2001F.

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(s) to within its limit or isolate the affected component(s) from service.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.10 The requirements of Specification 4.0.5 are applicable.

SUMMER - UNIT 1 3t4 4-36 Amendment No.172

ADMINISTRATIVE CONTROLS Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

1. Changes to the Bases shall be made under appropriate administrative control and reviews.

2. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

a) A change in the TS Incorporated in the license or b) A change to the updated FSAR or bases that requires NRC approval pursuant to 10 CFR 50.59.

3. The Bases Control Program shall contain provisions to insure that the Bases are maintained consistent with the FSAR.

4. Proposed changes that meet the criteria of Specification 6.8.4.i.2.b above shall be reviewed and approved prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).

j. Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the Inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

In lieu of Positions C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the Inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.

SUMMER - UNIT 1 6-1 2d Amendment No. 468 172