ML063070225

2006/08/10-E-Mail: FW: Requested Information from Pilgrim License Renewal Program Document PRPD-06

ML063070225
Person / Time
Site:	Pilgrim
Issue date:	08/10/2006
From:	Douglas E Entergy Nuclear Operations
To:	Subbaratnam R NRC/NRR/ADRO
References
%dam200612, TAC MD2296
Download: ML063070225 (3)

Text

[Kent Howard -FW: Requesj~d Information from il rim License Renewal Program Document PRPD-06 Page__1 From: "Ellis, Douglas" <dellisl @entergy.com>

To: "Ram Subbaratnam" <RXS2@nrc.gov>

Date: 8/10/2006 12:11:59 PM

Subject:

FW: Requested Information from Pilgrim License Renewal Program Document PRPD-06 Doug Ellis, Pilgrim Licensing.

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Document PRPD-06 Creation Date From: Created By: FW: Requested Information from Pilgrim License Renewal Program 8/10/2006 12:11:42 PM"Ellis, Douglas" <dellisl @entergy.com>

dellisI @entergy.com Recipients nrc.gov TWGWPO02.HQGWDO01 RXS2 (Ram Subbaratnam)

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Security: Size 589 266912 1 None Standard No None No Standard Date & Time 8/10/2006 12:11:42 PM Junk Mail Handling Evaluation Results Message is eligible for Junk Mail handling This message was not classified as Junk Mail Junk Mail settings when this message was delivered Junk Mail handling disabled by User Junk Mail handling disabled by Administrator Junk List is not enabled Junk Mail using personal address books is not enabled Block List is not enabled Pilgrim NPS License Renewal Project LRevision 0 Time-Limited Aging Analyses -Mechanical Fatigue Page 19 of 33 ss ed 4 -year 1.3nt life was less han 0.5. Exnding plant life b an additional years rodue a usge facto below 0'5. Since th is less than 1.0, e fatigue critea are sh isi eTLAA bee rojecte through theeriod of exendefoperation ac ord cewi 1OCF 4.21(c)(i)"i).

2.4 PNPS Inservice Inspection

-Fracture Mechanics Analyses Plant Technical Specifications (Ref. 4.2.2, 3.6(G) and 4.6(G)) require an inservice inspection/testing program to verify the integrity of the reactor coolant pressure boundary.Specifically, 1OCFR50.55a(g) (Ref. 4.4.4) requires ISI per ASME Section Xl, and 1 OCFR50.36(c)(3) (Ref. 4.4.3) provides general surveillance requirements.

In accordance with 10CFR50.55a, the ISI Program Plan is reviewed every 120 months and revised, as necessary, to meet the latest NRC authorized edition of ASME Section XI. This revision is submitted to the NRC for approval.The examination categories defined in Table IWB-2500-1 require the use of nondestructive examination (NDE) techniques to detect and characterize flaws. The flaws may be service-induced (e.g., fatigue) or may be fabrication flaws that have grown due to service loads. Table IWB-2500-1 specifies the extent and frequency of inspection.

The Code does not restrict the inspection intervals to the current term of operation.

The inspection intervals are valid for any period of extended operation.

Flaws detected during examination are evaluated by comparing the examination results to acceptance standards established in ASME Section Xl. Unacceptable indications require detailed analysis (e.g., ASME Section Xl, Appendix A), repair, or replacement.

This section reviews analyses of flaws discovered during inservice inspections (ISI) at PNPS.Class 1, 2, or 3 components require evaluation in accordance with ASME Section Xl, Subsections IWB, IWC, or IWD, respectively.

For any indication discovered during ISI that exceeds acceptance standards, Section Xl requires that (1) repairs be made, (2) affected portions of the item be replaced, or (3) the indication be shown acceptable through fracture mechanics analysis (FMA).Acceptance through FMA requires prediction of flaw growth considering either a chosen evaluation period (i.e., no shorter than the time until the next inspection following discovery of the flaw), or the remaining service life of the component.

Flaw indications that are determined not to grow beyond acceptance limits during the evaluation period are justified for continued operation.

FMA evaluations performed for the current operating term may be TLAA. Below are results of the review of these potential TLAA.2.4.1 CRD Return Line Nozzle to End Cap Weld In 2003, PNPS discovered a crack on the inside diameter of the weld between the CRD return line nozzle and the end cap. PNPS relief request #36 (PRR-36) requested relief from the repair criteria of 10CFR50.55a(c)3 as it pertains to the control rod drive return nozzle cap (Refs. 4.2.19 and 4.2.20). This relief request cited code cases N-638 and N-504-2, but also requested exemptions to the code cases. The CRD nozzle cap was repaired using a weld overlay as opposed to grinding out the defect and re-welding.

There was no specific TLAA addressed in this relief request. Future acceptability of the weld is assured through inspections) per the guidelines of BWRVIP-75 (Ref. 4.5.15).