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| {{#Wiki_filter: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 | | {{#Wiki_filter:Advisory Committee on Reactor Safeguards (ACRS) License Renewal Full Committee James A. Fitzpatrick Nuclear Power Plant License Renewal Safety Evaluation Report Tommy Le, Sr. Project Manager, NRR Roy Mathew, Audit Team Leader, NRR Glenn Meyer, Inspection Team Leader, RI March 6, 2008 1 |
| *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
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| *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
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| *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
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| *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)
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| *Total 36 AMPs
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| -26 existing AMPs
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| -10 new AMPs
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| *GALL Report Consistency
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| -10 Consistent
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| -20 Consistent with exceptions/enhancements
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| -6 Plant Specific 11 Section 3: Aging Management Review Results*346 Audit Questions
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| *All Questions except two (2) were resolved
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| *2 Questions Converted to RAIs
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| *Fifty-five of the Questions Resulted in Revisions to the LRA
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| *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
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| applicant has demonstrated that the effects of aging will be adequately managed so that the intended function(s)
| | Introduction |
| | * Overview |
| | * License Renewal Inspections |
| | * Section 2: Scoping and Screening Review |
| | * Section 3: Aging Management Review Results |
| | * Section 4: Time-Limited Aging Analyses (TLAAs) 2 |
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| will be maintained consistent with the
| | Overview Recap of September 2007 sub-committee meeting |
| | * 346 Audit Questions |
| | * 118 RAIs Issued |
| | * Safety Evaluation Report (SER) With Open Items was issued July 31, 2007 3/4 Two (2) Open Items 3/4 Zero (0) Confirmatory Items 3/4 Three (3) Standard License Conditions 3 |
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| CLB for the period of extended operation 13Section 4 -TLAAs
| | License Renewal Inspections Glenn Meyer Inspection Team Leader, Region I 4 |
| *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
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| *OI 4.3.3-1 -Environmentally-Assisted Fatigue (Resolved)
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| ºThe applicant submitted Commitment #20
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| 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
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| 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.
| | Regional Inspection |
| 16 STAFF CONCLUSION*The staff has concluded that there is reasonable assurance that the activities
| | * 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 5 |
|
| |
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| authorized by the renewed license will continue to be conducted in accordance with the CLB, and that any changes made to the
| | Regional Inspection |
| | * Spatial interaction |
| | * Structural interaction |
| | * Scoping and screening 6 |
|
| |
|
| JAFNPP CLB in order to comply with 10 CFR
| | Regional Inspection Aging 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 7 |
|
| |
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| 54.29(a) are in accord with the Act and
| | Regional Inspection Aging Management |
| | * Aging Management Programs support conclusion that aging effects will be managed |
| | * Regional Administrators Letter To NRR Director issued January 25, 2008 8 |
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| Commission's regulations.
| | Section 2 Conclusion |
| 17 Questions 18 Section 3: Aging Management Review Results [backup slide] | | * The applicants scoping and screening methodology consistent with the requirements of 10 CFR 54.4 and 54.21(a)(1) |
| *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] | | * 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) 9 |
| *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}} | | Section 3: Aging Management Review Results Aging 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 10 |
| | |
| | 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 11 |
| | |
| | Section 3 Conclusion |
| | * Based on its review of the AMRs and 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 12 |
| | |
| | Section 4 - TLAAs |
| | * OI 4.2.1 Reactor Vessel Fluence (Resolved) |
| | º New (Reg Guide 1.190-based) calculation submitted on November 5, 2007 |
| | º Methodology acceptable and new value is bounded by initial value |
| | * OI 4.3.3 Environmentally-Assisted Fatigue (Resolved) |
| | º The applicant submitted Commitment #20 |
| | º Will comply with 10 CFR 54.21(c)(1)(iii) 13 |
| | |
| | Section 4 Conclusion |
| | * TLAAs |
| | - 10 CFR 54.3: TLAA list 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): Sufficient supplements to FSAR |
| | - 10 CFR 54.21(c)(2): No plant specific exemptions 14 |
| | |
| | License Conditions |
| | * The first license condition requires the applicant to include the UFSAR supplement required by 10 CFR 54.21(d) in the next UFSAR update, as required by 10 CFR 50.71(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 the capsule. 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 10 CFR Part 50, Appendix H. |
| | 15 |
| | |
| | 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 Commissions regulations. |
| | 16 |
| | |
| | Questions 17 |
| | |
| | Section 3: Aging Management Review Results [backup slide] |
| | * Examples: Two Aging Management Programs Containment Inservice Inspection Program - B.1.16.1 Containment Leak Rate Program - B.1.8 SER 3.0.3.3.2 - Containment Inservice Inspection 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 minimum SER 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 18 |
| | |
| | Section 3: Aging Management Review Results [backup slide] |
| | * Examples: Two Aging Management Programs Containment Inservice Inspection Program Containment Leak Rate Program Consistent with the Staff Interim Guidance LR-ISG-2006-01 No leakage identified in the vicinity of the sand cushion drain line Water leakage monitoring (each refueling) refueling seal bellows drywell air gap drains sand pocket drains functional checks on the alarm system |
| | - The staff finds the AMPs consistent with the GALL report, will manage loss of material, an aging effect caused by corrosion of drywell and torus material 19}} |
Letter Sequence Request |
|---|
|
Results
Other: JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses, JAFP-07-0019, License Renewal Application, Amendment 9, JAFP-07-0021, License Renewal Application, Amendment 6, ML062160494, ML062780187, ML070380370, ML070520059, ML071270080, ML071270377, ML071580049, ML071970491, ML072690528, ML072690529, ML080140266, ML080420252, ML081010259, ML081010277, ML081010332
|
MONTHYEARML0621604942006-07-31031 July 2006
James A. Fitzpatrick License Renewal Application, Cover Page Through Chapter 4
Project stage: Other
ML0627801872006-10-23023 October 2006
Memorandum - Audit and Review Plan for Plant Aging Management Reviews and Programs, and Time-Limited Aging Analyses for the James A. Fitzpatrick Power Plant
Project stage: Other
ML0627801552006-10-23023 October 2006
License Renewal Audit and Review Plan
Project stage: Acceptance Review
ML0634004152006-12-0404 December 2006
(PA-LR) AMP Audit Request and Response Items 50 - 417
Project stage: Acceptance Review
ML0700800142007-01-12012 January 2007
Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant
Project stage: RAI
ML0701201962007-01-19019 January 2007
Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant
Project stage: RAI
ML0703803892007-02-0606 February 2007
JAFNPP AMP and AMR Database
Project stage: Acceptance Review
ML0703803702007-02-0707 February 2007
Docketing of Audit Date Base for Aging Management Programs (AMP) and Aging Management Reviews (AMR) Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant
Project stage: Other
JAFP-07-0021, License Renewal Application, Amendment 62007-02-12012 February 2007
License Renewal Application, Amendment 6
Project stage: Other
ML0705200592007-02-20020 February 2007
Note to File: Docketing of Email Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant.
Project stage: Other
ML0703700232007-02-23023 February 2007
Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant
Project stage: RAI
ML0713504332007-04-0505 April 2007
JAF-RPT-05-AMM30, Rev 4, Draft, Aging Management Review of Nonsafety-Related Systems and Components Affecting Safety-Related Systems, (FitzPatrick)
Project stage: Draft Other
JAFP-07-0019, License Renewal Application, Amendment 92007-04-0606 April 2007
License Renewal Application, Amendment 9
Project stage: Other
JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses2007-04-24024 April 2007
License Renewal Application, Amendment 10, RAI Responses
Project stage: Other
ML0712700802007-05-0404 May 2007
Docketing of E-mail Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant
Project stage: Other
ML0712703772007-05-0404 May 2007
License Renewal Application Amendment 10 - Added Item (4)
Project stage: Other
ML0705804642007-05-25025 May 2007
Audit Summary for the JAFNPP LRA Safety Site Audits
Project stage: Acceptance Review
ML0715800492007-06-19019 June 2007
Audit Summary Report for Plant Aging Management Reviews and Programs for the James A. FitzPatrick Nuclear Power Plant on License Renewal Application
Project stage: Other
ML0719704912007-07-10010 July 2007
Docketing of Document Received from the Applicant Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant
Project stage: Other
ML0720102672007-07-25025 July 2007
Request for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant
Project stage: RAI
ML0715802992007-07-31031 July 2007
Transmittal of Safety Evaluation Report with Open and Confirmatory Items Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant
Project stage: Approval
ML0726905292007-09-0505 September 2007
ACRS License Renewal Subcommittee Presentation September 5, 2007
Project stage: Other
ML0726905372007-09-0505 September 2007
License Renewal Safety Evaluation Report Staff Presentation to the ACRS
Project stage: Approval
ML0726905282007-09-26026 September 2007
Docketing of Slides Presentation to ACRS Subcommittee Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant
Project stage: Other
ML0801402662008-02-0808 February 2008
Audit Q&A Database for FitzPatrick Nuclear Plant Aging Mgmt Programs, Aging Mgmt Reviews, and Time-Limited Aging Analyses - Audit Team'S Evaluation of the Applicant'S Responses
Project stage: Other
ML0801404662008-02-0808 February 2008
Q & a Database - Audit Team'S Evaluation
Project stage: Acceptance Review
ML0804202522008-02-14014 February 2008
Audit Question and Answer Database for James A. FitzPatrick Nuclear Power Plant Aging Management Programs, Aging Management Reviews, and Time-Limited Aging Analyses - Audit Team'S Evaluation of the Applicant'S Responses
Project stage: Other
ML0808400482008-03-0606 March 2008
ACRS NRC, Fitzpatrick Lr SER
Project stage: Request
ML0808400822008-03-0606 March 2008
ACRS Fitzparick Lr Presentation
Project stage: Request
ML0808000342008-03-24024 March 2008
Docketing of Slides Presentations to ACRS Full Committee Meeting Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant
Project stage: Meeting
ML0810102592008-09-0808 September 2008
Renewed Facility Operating License No. DPR-59
Project stage: Other
ML0810102772008-09-0808 September 2008
Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions
Project stage: Other
ML0810102422008-09-0808 September 2008
Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications
Project stage: Acceptance Review
ML0810103322008-09-0808 September 2008
Renewed Facility Operating License No. DPR-59 / FRN
Project stage: Other
ML0824903692008-09-0808 September 2008
Issuance of Renewed Facility Operating License No. DPR-59 for James A. Fitzpatrick Nuclear Power Plant
Project stage: Approval
2007-04-06
[Table View] |
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Category:Slides and Viewgraphs
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Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2
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Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041)
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Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides
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Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a
ML20178A4202020-06-30030 June 2020
NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response
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June 18 Public Meeting Slides (Exelon)
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ML18347B3142018-12-19019 December 2018
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Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018
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Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas
ML18255A0142018-09-12012 September 2018
BWROG Presentation Slides for Public Meeting Sept 12 2018
ML18107A3342018-04-10010 April 2018
Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides
ML18075A1232018-03-20020 March 2018
Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations
ML17047A6212017-02-14014 February 2017
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Entergy Operations, Inc., Project Planning Slides for March 31, 2009, Nrc/Entergy Pre-Application Meeting - Power Uprates
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ML0810600902008-04-0303 April 2008
NRC Slides for the 2008 FitzPatrick Annual Assessment Meeting
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ACRS Fitzparick Lr Presentation
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ML0722600232007-08-0101 August 2007
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ML0721405662007-06-21021 June 2007
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2024-05-16
[Table view] |
Text
Advisory Committee on Reactor Safeguards (ACRS) License Renewal Full Committee James A. Fitzpatrick Nuclear Power Plant License Renewal Safety Evaluation Report Tommy Le, Sr. Project Manager, NRR Roy Mathew, Audit Team Leader, NRR Glenn Meyer, Inspection Team Leader, RI March 6, 2008 1
Introduction
- Section 2: Scoping and Screening Review
- Section 4: Time-Limited Aging Analyses (TLAAs) 2
Overview Recap of September 2007 sub-committee meeting
- Safety Evaluation Report (SER) With Open Items was issued July 31, 2007 3/4 Two (2) Open Items 3/4 Zero (0) Confirmatory Items 3/4 Three (3) Standard License Conditions 3
License Renewal Inspections Glenn Meyer Inspection Team Leader, Region I 4
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 5
Regional Inspection
Regional Inspection Aging Management
- Reviewed program implementation for 22 AMPs
- Reviewed programs, evaluations, and records
- Operational experience information
- Corrective actions on prior plant issues
- Interviewed cognizant personnel
- Performed plant walk downs 7
Regional Inspection Aging Management
- Regional Administrators Letter To NRR Director issued January 25, 2008 8
Section 2 Conclusion
- The applicants scoping and screening methodology consistent with the requirements of 10 CFR 54.4 and 54.21(a)(1)
Section 3: Aging Management Review Results Aging Management Programs (AMPs)
- 26 existing AMPs
- 10 new AMPs
- 10 Consistent
- 20 Consistent with exceptions/enhancements
- 6 Plant Specific 10
Section 3: Aging Management Review Results
- 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 11
Section 3 Conclusion
- Based on its review of the AMRs and 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 12
Section 4 - TLAAs
- OI 4.2.1 Reactor Vessel Fluence (Resolved)
º New (Reg Guide 1.190-based) calculation submitted on November 5, 2007
º Methodology acceptable and new value is bounded by initial value
- OI 4.3.3 Environmentally-Assisted Fatigue (Resolved)
º The applicant submitted Commitment #20
º Will comply with 10 CFR 54.21(c)(1)(iii) 13
Section 4 Conclusion
- 10 CFR 54.3: TLAA list 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): Sufficient supplements to FSAR
- 10 CFR 54.21(c)(2): No plant specific exemptions 14
License Conditions
- The first license condition requires the applicant to include the UFSAR supplement required by 10 CFR 54.21(d) in the next UFSAR update, as required by 10 CFR 50.71(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 the capsule. 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 10 CFR Part 50, Appendix H.
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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 Commissions regulations.
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Questions 17
Section 3: Aging Management Review Results [backup slide]
- Examples: Two Aging Management Programs Containment Inservice Inspection Program - B.1.16.1 Containment Leak Rate Program - B.1.8 SER 3.0.3.3.2 - Containment Inservice Inspection 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 minimum SER 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 18
Section 3: Aging Management Review Results [backup slide]
- Examples: Two Aging Management Programs Containment Inservice Inspection Program Containment Leak Rate Program Consistent with the Staff Interim Guidance LR-ISG-2006-01 No leakage identified in the vicinity of the sand cushion drain line Water leakage monitoring (each refueling) refueling seal bellows drywell air gap drains sand pocket drains functional checks on the alarm system
- The staff finds the AMPs consistent with the GALL report, will manage loss of material, an aging effect caused by corrosion of drywell and torus material 19
