ML033250559

Tech Spec Pages for Amendment No. 171, Revising the Reporting Requirements for the Discovery of Defective or Degraded Steam Generator Tubes

ML033250559
Person / Time
Site:	Kewaunee
Issue date:	11/20/2003
From:	Anthony Mcmurtray NRC/NRR/DLPM/LPD3
To:	Coutu T Nuclear Management Co
References
TAC MB6993
Download: ML033250559 (2)

Text

c. Additional, unscheduled in-service inspections of each steam generator shall be performed using the criteria set forth in Table 4.2-2 foraulst SAMPLE INSPECTION" during shutdowns consequent to:

1. Primary-to-secondary tube leaks (not including leaks originating from tube-to-tubesheet welds) in excess of the limits of TS 3.1 .d and TS 3.4.d, or

2. A seismic event having a magnitude greater than the Operating Basis Earthquake, or

3. A loss-of-coolant accident requiring actuation of engineered safeguards, where the Reactor Coolant System cooldown rate exceeded 100°F/hr, or

4. A main steam line or feedwater line break, where the Reactor Coolant System cooldown rate exceeded 100 0F/hr.

d. If there is a significant change in steam generator chemistry control methodology, the steam generators shall be operated at power for three months while using the new treatment and shall then be inspected during the next outage of sufficient duration.-

4. Plugging Limit Criteria Any tube with tube wall degradation of 50% or more shall be plugged before returning the steam generator to service. If significant general tube thinning occurs, this criterion is reduced to 40% wall degradation.

5. Deleted

6. Deleted

7. Reports

a. Following each in-service inspection of steam generator tubes during which tubes are plugged, the number of tubes plugged shall be reported to the Commission within 60 days.

TS 4.2-5 Amendment No. 171

b. The results of each steam generator tube in-service inspection shall be included in the Annual Operating Report for the reporting period that included completion of the inspection. The report shall include:

1. Number of tubes inspected and extent of inspection.

2. Location of each tube wall degradation and its percent of wall penetration.

3. Identification of tubes plugged.

c. If a steam generator tube inspection result falls into Category C-3, the Commission shall be promptly notified according to requirements of 10 CFR 50.72(b)(3)(ii). A l Licensee Event Report shall then be filed with the Commission as described by Specification 4.2.b.7.a and as set forth in 10 CFR 50.73(a)(2)(ii).

TS 4.2-6 Amendment No. 171