ML080840082

ACRS Fitzparick Lr Presentation

ML080840082
Person / Time
Site:	FitzPatrick
Issue date:	03/06/2008
From:	Le N, Roy Mathew, Meyer G NRC/NRR/ADRO/DLR, Division of Nuclear Materials Safety I
To:
Le N. B., NRR/DLR/RLRB, 415-1458
Shared Package
ML080840057	List: ML080800034 ML080840048 ML080840082
References
Download: ML080840082 (19)

Text

1 Advisory Committee on Reactor Safeguards (ACRS) License Renewal Full Committee James A. Fitzpatrick Nuclear Power PlantLicense Renewal Safety Evaluation ReportTommy Le, Sr. Project Manager, NRRRoy Mathew, Audit Team Leader, NRRGlenn Meyer, Inspection Team Leader, RI March 6, 2008 2 Introduction*Overview*License Renewal Inspections

• Section 2: Scoping and Screening Review*Section 3: Aging Management Review Results*Section 4: Time-Limited Aging Analyses (TLAAs) 3 Overview Recap of September 2007 sub-committee meeting*346Audit Questions *118 RAIsIssued

• Safety Evaluation Report (SER) With Open Items was issued July 31, 2007Two (2) Open ItemsZero (0) Confirmatory ItemsThree (3) Standard License Conditions 4License Renewal Inspections Glenn Meyer Inspection Team Leader, Region I 5 Regional Inspection*54.4(a)(2) -non-safety SSCs whose failure could affect safety SSCs*Spatial and Structural Interactions

• LRA Drawings and procedures reviewed*Plant walkdowns performed*Some components or portions of systems needed to be added to scope 6RegionalInspection*Spatial interaction*Structural interaction*Scoping and screening 7 Regional InspectionAging Management*Reviewed program implementation for 22 AMPs*Reviewed programs, evaluations, and records*Program procedures *Operational experience information *Corrective actions on prior plant issues*Interviewed cognizant personnel*Performed plant walk downs 8 Regional InspectionAging Management

• Aging Management Programs support conclusion that aging effects will be managed*Regional Administrator's Letter To NRR Director issued January 25, 2008 9 Section 2 Conclusion*The applicant's scoping and screening methodology consistent with the requirements of 10 CFR 54.4 and 54.21(a)(1) *SSCs within the scope of license renewal and subject to AMR are consistent with the requirements of 10 CFR 54.4 and 54.21(a)(1) 10 Section 3: Aging Management Review ResultsAging Management Programs (AMPs)

• Total 36 AMPs

-26 existing AMPs

-10 new AMPs

• GALL Report Consistency

-10 Consistent

-20 Consistent with exceptions/enhancements

-6 Plant Specific 11 Section 3: Aging Management Review Results*346 Audit Questions

• All Questions except two (2) were resolved

• 2 Questions Converted to RAIs

• Fifty-five of the Questions Resulted in Revisions to the LRA

• 25 Commitments at the End of the Audit 12 Section 3 Conclusion*Based on its review of the AMRsand AMPs, the staff concludes that the

applicant has demonstrated that the effects of aging will be adequately managed so that the intended function(s)

will be maintained consistent with the

CLB for the period of extended operation 13Section 4 -TLAAs

• OI 4.2.1-1 -Reactor Vessel Fluence(Resolved)ºNew (RegGuide 1.190-based) calculationsubmitted on November 5, 2007ºMethodology acceptable and new value is bounded by initial value

• OI 4.3.3-1 -Environmentally-Assisted Fatigue (Resolved)

ºThe applicant submitted Commitment #20

ºWill comply with 10 CFR 54.21(c)(1)(iii) 14 Section 4 Conclusion*TLAAs-10 CFR 54.3: TLAA lis t adequate, as amended-10 CFR 54.21(c)(1)(i): analyses remain valid for Period of Extended Operation (PEO), (ii): analyses projected to the end of PEO, and (iii): aging effects will be adequately managed for PEO-10 CFR 54.21(d): Sufficie nt supplements to FSAR -10 CFR 54.21(c)(2): No plant specific exemptions 15 License Conditions*The first license condition requires the applicant to include the UFSAR supplement required by 10CFR54.21(d) in the next UFSAR update, as required by 10CFR50.71(e), following the issuance of the renewed license.*The second license condition requires future activities identified in the UFSAR supplement to be completed prior to the period of extended operation.*The third license condition requires that all capsules in the reactor vessel that are removed and tested meet the requirements of American Society for Testing and Materials (ASTM) E 185-82 to the

extent practicable for the configuration of the specimens in thecapsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the staff prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the staff, as required by 10CFRPart50, Appendix H.

16 STAFF CONCLUSION*The staff has concluded that there is reasonable assurance that the activities

authorized by the renewed license will continue to be conducted in accordance with the CLB, and that any changes made to the

JAFNPP CLB in order to comply with 10 CFR

54.29(a) are in accord with the Act and

Commission's regulations.

17 Questions 18 Section 3: Aging Management Review Results [backup slide]

• Examples: Two Aging Management ProgramsContainment InserviceInspection Program -B.1.16.1Containment Leak Rate Program -B.1.8SER 3.0.3.3.2 -Containment InserviceInspection Program:-Interior Torus Suppression pool area above and below the water line are inspected via IWE program during refueling outages-Torus was drained / cleaned in 1998, identified areas of pitting-Over 5 years performed UT and found pitted areas remain acceptable per Code requirements -During RFO-16 (2004), UT results shown 3 pitted depths 0.019", 0.010", and 0.014", below design (0.632") -Vs 0.503"Code minimumSER 3.0.3.1.1 -Containment Leak Rate Program:-The Staff finds program elements consistent with the GALL Report. Provides assurance leakage through Primary containment will not exceed Allowable TS value 19 Section 3: Aging Management Review Results [backup slide]

• Examples: Two Aging Management ProgramsContainment InserviceInspection Program Containment Leak Rate Program Consistent with the Staff Interim Guidance LR-ISG-2006-01No leakage identified in the vicinity of the sand cushiondrain lineWater leakage monitoring (each refueling)refueling seal bellowsdrywell air gap drainssand pocket drainsfunctional checks on the alarm system

-The staff finds the AMPsconsistent with the GALL report, will manage loss of material, an aging effect caused by corrosion of drywelland torus material