ML15160A430

NYS000559 - Indian Point Nuclear Generating Unit Nos. 2 and 3- License Renewal Application Pages 4.3-14 -15 (Excerpt)

ML15160A430
Person / Time
Site:	Indian Point
Issue date:	06/09/2015
From:	State of NY, Office of the Attorney General
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 27916, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML15160A430 (2)

Text

NYS000559 Submitted: June 9, 2015 Indian Point Energy Center License Renewal Application Technical Information operation, these TLAA remain valid through the period of extended operation per 10CFR54.21(c)(1)(i). Nonetheless, as the surge nozzles require environmental fatigue considerations, they will be reanalyzed for license renewal as discussed in Section 4.3.3.

4.3.1.4 Steam Generators Summary Description IP2 replaced steam generators during an outage completed in January 2001. IP3 replaced steam generators during an outage completed in June 1989. The IPEC replacement steam generators were analyzed for fatigue in their component stress reports. The replacement steam generators were re-evaluated with respect to fatigue for the power increase.

Cumulative usage factors for critical components, shown in Table 4.3-9 and 4.3-10, are from the power uprate analyses. Usage factors for additional, non-critical, components are available in the stress reports. The usage factor calculations are considered TLAA.

Table 4.3-9 Cumulative Usage Factors for the IP2 Steam Generators Location CUF Primary Side Divider plate 0.683 Tubesheet/shell junction 0.451 Tube/tubesheet weld 0.809 Tubes 0.484 Secondary Side Main feedwater nozzle 0.898 Secondary manway stud1 0.438 Steam nozzle 0.212 Steam nozzle support ring 0.220 Steam nozzle insert 0.212

1. The IP2 replacement steam generators use studs and nuts.

There are no longer any secondary manway bolts in use at IPEC.

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4.0 Time-Limited Aging Analyses Page 4.3-14

Indian Point Energy Center License Renewal Application Technical Information Table 4.3-10 Cumulative Usage Factors for the IP3 Steam Generators Location CUF Primary Side Divider plate 0.789 Tubesheet/shell junction 0.416 Tube/tubesheet weld 0.082 Tubes 0.161 Secondary Side Main feedwater nozzle 1.00 Secondary manway stud1 0.920 Steam nozzle 0.023 Steam nozzle support ring 0.894 Steam nozzle insert 0.208

1. The IP3 replacement steam generators use studs and nuts.

There are no longer any secondary manway bolts in use at IPEC.

Evaluation Section 4.3.1 projects that none of the design transients used for steam generator fatigue analysis will exceed their analyzed numbers during the period of extended operation. These usage factor calculations are based on the design transients discussed in Section 4.3.1 and will remain valid for the period of extended operation in accordance with 10CFR54.21(c)(1)(i).

4.3.1.5 Reactor Coolant Pump Fatigue Analysis The reactor coolant pumps were evaluated with respect to fatigue for the stretch power uprate.

Stresses in the reactor coolant pumps were reviewed and shown to remain within the ASME Code allowable stresses. These stress calculations have no time dependent assumptions and therefore are not TLAA.

Detailed fatigue analyses of RCP casings were not required because the conditions specified in the 1965 edition of the ASME code Sections N-415.1(a) through (f), Vessels Not Requiring Analysis for Cyclic Operation, were met. These fatigue waiver evaluations may be considered TLAA if they used the numbers of design cycles in the evaluation of items N-415.1(a) through (f).

IPEC has chosen to conservatively call the evaluations TLAA. These determinations were based on the numbers of design cycles. The projections in Tables 4.3-1 and 4.3-2 show that the numbers of significant cycles in 60 years will remain below the numbers of cycles used in these 4.0 Time-Limited Aging Analyses Page 4.3-15