ML020800148

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February 13, 2002, Meeting with Fort Calhoun Stations, Unit 1, Handouts
ML020800148
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/20/2002
From:
Omaha Public Power District
To:
Office of Nuclear Reactor Regulation
Burton W, NRR/DRIP/RLEP, 301-415-2853
References
Download: ML020800148 (62)
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Text

Fort Calhoun Station LRA Overview 1

Overview of Application

  • Features of the SRP format (Gasper) 8:45

- Scoping, Screening and AMR (Van Sant) 9:15

- Aging Management Programs (Henry) 9:30

- Break

- LRA Section 3 (Gasper) 10:00

- TLAA (Van Sant) 10:30

  • Positions on technical issues (Gasper) 10:35 2

Previous Applications

  • Scoping, Screening and AMR results presented in six-column table

Surry/North Anna LRA Table 3.2-5 Engineered Safety Features Systems Safety Injection Component Passive Material Group Environment Aging Effects Aging Management Activity Group Function Requiring Management Accumulators PB Carbon Steel (E) Air None None Required (and and Low-alloy cladding) Steel (E) Borated Loss of Material Boric Acid Corrosion Surveillance W ater Leakage Stainless Steel (I) Gas None None Required (I) Treated Loss of Material Chemistry Control Program for Primary W ater Systems Bolting PB Carbon Steel (E) Air Loss of Pre-Load 1 ISI Program - Component and and Low-alloy Component Support Steel Inspections (E) Borated Loss of Material Boric Acid Corrosion Surveillance W ater General Condition Monitoring Activities Leakage Flow Elements PB;RF Stainless Steel (E) Air None None Required (I) Treated Loss of Material Chemistry Control Program for Primary W ater Systems Instrument PB Stainless Steel (E) Air None None Required Valve (I) Treated Loss of Material Chemistry Control Program for Primary Assemblies W ater Systems Pipe PB Stainless Steel (E) Air None None Required (I) Treated Cracking Chemistry Control Program for Primary W ater Systems ISI Program - Component and Component Support Inspections 1 Loss of Material Chemistry Control Program for Primary Systems 4

Development of SRP Format

  • In late 2000, NRC and NEI agreed to conduct a demonstration project implementing the SRP (NUREG-1800) and the GALL Report (NUREG-1801).
  • NEI submitted SRP (Plant X) and six-column (Plant Y) demonstration LRAs.
  • OPPD prepared the SRP format (Plant X) example for the demonstration project.

5

GALL Demonstration The NRC Lessons Learned letter to NEI (10/3/01) stated:

The staff prefers the SRP-LR format over the Six-column format because the review is based upon the guidance in the SRP-LR which provides consistency and an adequate depth of review.

6

GALL Demonstration The NRC Lessons Learned letter to NEI (10/3/01) also stated:

The staff indicated that the SRP-LR approach used in the Plant X demonstration provided the most consistency. The SRP-LR provides a review procedure for the reviewer to follow which helps to make a more consistent review.

7

Features of the SRP format

  • Section 1 same as previous applications
  • Section 2 contains scoping results, including intended functions
  • Section 3 shows comparison to GALL AMR results and FCS plant specific AMR results
  • Section 4 same as previous applications
  • Appendix A (SAR supplement) utilizes SRP language
  • Appendix B shows comparison to GALL programs and FCS plant specific programs 8

SRP Format Summary

  • Provides an LRA that can be efficiently reviewed using the guidance of the SRP and the results of the GALL report

- Section 2 of the LRA provides information consistent with SRP Chapter 2 review guidance

- Section 3 and Appendices A&B provide information consistent with SRP Chapter 3 review guidance

- Individual component aging management review results are retained by the applicant for inspection by NRC 9

FCS LRA is based on the SRP format and incorporates the GALL demonstration lessons learned 10

FCS Terminology, Scoping, Screening and Aging Management Review Methodologies and Results Bernie Van Sant 11

FCS Terminology

  • RAMS

- FCS equipment database includes CQE and Limited-CQE designations

  • CQE List

- Identifies those SSC that are designated CQE and Limited-CQE

  • USAR: Updated Safety Analysis Report
  • DBD: Design Basis Document 12

FCS Terminology

  • Critical Quality Elements (CQEs) -

Those structures, systems, components or items whose satisfactory performance is required to prevent or mitigate the consequences of accidents that could cause undue risk to the health and safety of the public.

  • SSCs at FCS designated as CQE satisfy 54.4(a) Criterion 1 and therefore are in scope 13

FCS Terminology

  • Limited Critical Quality Elements (Limited CQEs) - Those structures, systems, components, or items whose satisfactory performance is required to prevent or mitigate the consequences of failures of those structures, systems, components, or items identified as CQE.
  • SSCs at FCS designated as Limited CQE satisfy 54.4(a) Criterion 2 and therefore are in scope 14

FCS Terminology

  • Non-Critical Quality Elements (Non-CQEs)

- Those structures, systems, components, or items that have no special performance or quality requirements as defined for CQE or Limited CQE.

  • Non-CQE SSCs were reviewed against Criterion 1, 2, and 3 15

Scoping and Screening Methodology and Results 16

Scoping of plant systems and structures Engineering CQE List Analyses P&IDs Describe System/ System/

system/ Structure No Structure DBDs Source Performs not in structure, Documents Intended Scope identify all Plant functions Functions Modification Packages USAR Yes RAMS Scoping of system and structural components Identify Screening Component not List/Describe Intended No subject to Components of components for Functions, Passive Long Lived Aging in Scope For each Determine LR Management System Evaluation Review Boundary Yes Component subject to Aging Management Review 17

Scoping Results TABLE 2.2-1 Plant Level Scoping Results SSC Within Scope of License Renewal?

120 VAC (2.5.10) yes 120/208 VAC Miscellaneous Power Lighting no 125 VDC (2.5.9) yes 161 KV Substation Equipment no 22 KV no 345 KV Substation Equipment no 4160 VAC (2.5.6) yes 18

Scoping Results TABLE 2.3.2.2-1 SPENT FUEL POOL COOLING Component Types Subject to Aging Management Review and Intended Functions Component T ype Intended Functions Bolting Pressure Boundary Filter/strainer Housing Pressure Boundary Heat Exchanger Heat Transfer; Pressure Boundary Ion Exchangers Pressure Boundary Pipes & Fittings Pressure Boundary Pump Casings Pressure Boundary Valve Bodies Pressure Boundary 19

Aging Management Review of Components Identify component Determine Assign Aging material, & Aging Effects Management environment Requiring Program Management 20

Aging Management Review of Components (On-site documentation)

Equipment Type Material Internal Environment AERM Plant Programs Corrosion-Inhibited HEAT EXCHANGER - Carbon Steel Loss of Material Chemistry Program Treated Water SHELL Corrosion-Inhibited Cooling Water Carbon Steel Loss of Material Treated Water Corrosion Program HEAT EXCHANGER - Treated Water -

TUBE SHEET Stainless Steel Cracking Chemistry Program Borated Treated Water -

Stainless Steel Cracking Chemistry Program Borated Treated Water -

HEAT EXCHANGER - Alloy 600 Cracking Chemistry Program Borated TUBES Treated Water -

Alloy 600 Fatigue Fatigue Monitoring Borated Treated Water -

Alloy 600 Loss of Material Chemistry Program Borated ORIFICE PLATE Treated Water -

Stainless Steel Cracking Chemistry Program Borated 21

Aging Management Programs Ken Henry 22

Aging Management Program Analysis AERM identified from Aging Management Review Determine aging management program to address AERM Yes Is there a comparable aging No management program identified in GALL?

Conduct GALL Conduct 10 element comparison assessment 23

GALL Comparison FCS aging management program No Is FCS aging management program No consistent with GALL?

Yes Enhance/develop program. Justify exception to specified criteria and included in LRA.

No Does applicable OE verify effectiveness of program?

Yes Credit program for aging management 24

10 element assessment FCS aging management activity/program Does the program include the 10 elements of Branch Technical Position No RLSB-1, as appropriate?

Yes Enhance program.

Does applicable OE verify No effectiveness of program?

Yes 25 Credit program for aging management.

Existing Aging Management Activities

  • B.1.1 Chemistry Program
  • B.1.2 Containment Inservice Inspection Program
  • B.1.3 Containment Leak Rate Program
  • B.1.5 Inservice Inspection Program
  • B.1.6 Reactor Vessel Integrity Program

Enhanced Aging Management Activities

  • B.2.1 Bolting Integrity Program
  • B.2.3 Cooling Water Corrosion Program
  • B.2.4 Diesel Fuel Monitoring and Storage Program
  • B.2.5 Fatigue Monitoring Program

Enhanced Aging Management Activities

  • B.2.7 Overhead Load Handling Systems Inspection Program
  • B.2.8 Periodic Surveillance and Preventive Maintenance Program (site specific program)
  • B.2.9 Reactor Vessel Internals Inspection Program
  • B.2.10 Structures Monitoring Program
  • B.2.11 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel 28

New Aging Management Activities

  • B.3.1 Alloy 600 Program
  • B.3.2 Buried Surfaces External Corrosion Program
  • B.3.3 General Corrosion of External Surfaces Program (site specific program)
  • B.3.5 One-Time Inspection Program
  • B.3.6 Selective Leaching Program 29

Correlation between NUREG-1801 programs and FCS programs NUREG-1801 ID Number NUREG-1801 Program FCS Program XI.M1 ASME Section XI Inservice Inservice Inspection Program Inspection, Subsection IWB, (B.1.5)

IWC, IWD XI.M2 Water Chemistry Chemistry Program (B.1.1)

XI.M3 Reactor Head Closure Studs Bolting Integrity Program (B.2.1)

XI.M10 Boric Acid Corrosion Boric Acid Corrosion Prevention Program (B.2.2)

XI.M11 Nickel-Alloy Nozzles and Alloy 600 Program (B.3.1)

Penetrations XI.M12 Thermal Aging Embrittlement Thermal Aging Embrittlement of of Cast Austenitic Stainless Cast Austenitic Stainless Steel Steel (CASS) (CASS) (B.2.11)

XI.M13 Thermal Aging and Neutron Reactor Vessel Internals Irradiation Embrittlement of Inspection Program (B.2.9)

Cast Austenitic Stainless Steel (CASS) 30

Programs to be modified or developed in the future GALL/SRP demonstration Lessons Learned

- There is no guidance for how the applicant should address programs that have not been developed at the time the license renewal application is submitted where the applicant intends to develop the program at a later time to be consistent with GALL.

31

FCS programs to be modified or developed in the future The Buried Surfaces External Corrosion Program will be consistent with XI.M34, Buried Piping and Tanks Inspection, as identified in NUREG-1801 prior to the period of extended operation.

32

AGING MANAGEMENT REVIEW RESULTS Joe Gasper 33

GALL Reconciliation Process to identify consistency of the FCS AMR results with and deviations from GALL Report 34

SRP summarizes aging management programs evaluated in GALL Report Table 3.2-1. Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the GALL Report Aging Further Aging Effect/ Management Evaluation Type Component Mechanism Programs Recommended BWR/PWR Closure bolting in Loss of material Bolting integrity No high pressure or due to general high temperature corrosion, loss of systems preload due to stress relaxation, and crack initiation and growth due to cyclic loading or SCC 35

GALL Report Volume 1 identifies applicable Volume 2 items included in summary line Table 2. Summary of Aging Management Programs for the Engineered Safety Features Evaluated in Chapter V of the GALL Report (continued)

Aging Further Item Aging Effect/ Management Evaluation Number in Type Component Mechanism Programs Recommended GALL BWR/ Closure bolting Loss of material Bolting integrity No V.E.2-a, PWR in high-pressure due to general V.E.2-b.

or high- corrosion; crack temperature initiation and systems growth due to cyclic loading and/or SCC 36

GALL Report Volume 2 identifies Aging Management Review Group evaluated in GALL Report V Engineered Safety Features E. Carbon Steel Components Structure and/or Item Component Material Environment E.2-a Closure bolting Carbon Air, moisture, E.2.1 In high-pressure or high- steel, low- humidity, and temperature systems alloy steel leaking fluid Aging Effect/ Aging Management Further Mechanism Program (AMP) Evaluation Loss of material/ Chapter XI.M18, No General corrosion Bolting Integrity 37

FCS Aging Management Review Results Equipment Type Material External Environment AERM Plant Programs Bolting Integrity BOLTING Carbon Steel Plant Indoor Air Loss of Material Program 38

Compare FCS AMR results to GALL Report AMR and identify consistency with and deviations from GALL Report V Engineered Safety Features E. Carbon Steel Components Structure and/or Aging Effect/ Further Item Component Material Environment Mechanism Aging Management Program (AMP) Evaluation E.2-a Closure bolting Carbon Air, moisture, Loss of material/ Chapter XI.M18, Bolting Integrity No E.2.1 In high-pressure or high- steel, low- humidity, and General corrosion temperature systems alloy steel leaking fluid Equipment Type Material External Environment AERM Plant Programs Bolting Integrity BOLTING Carbon Steel Plant Indoor Air Loss of Material Program Three other FCS AMR results are consistent with V.E.2-a or V.E.2-b 39

Consistent with GALL TABLE 3.2-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Component Aging Aging Further Discussion Effect/Mechanism Management Evaluation Programs Recommended Closure bolting in high Loss of material due to Bolting integrity No 1. The aging management results pressure or high general corrosion, loss are consistent with the results temperature systems of preload due to stress documented in NUREG-1801.

relaxation, and crack 2. Consistent with NUREG-1801, initiation and growth due this group includes carbon and to cyclic loading or SCC low alloy steel in ambient air at FCS.

The aging management results are consistent with the results documented in NUREG-1801.

40

Materials and Environments

  • GALL demonstration Lessons Learned

- With the Plant X format, it is difficult to determine if all the material and environment combinations in GALL have been addressed in the sample license renewal application.

  • In the FCS LRA, OPPD clearly identified the specific FCS materials and environments which are consistent with NUREG-1801.

41

GALL material and environment TABLE 3.2-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Component Aging Aging Further Discussion Effect/Mechanism Management Evaluation Programs Recommended Closure bolting in high Loss of material due to Bolting integrity No 1. The aging management results pressure or high general corrosion, loss are consistent with the results temperature systems of preload due to stress documented in NUREG-1801.

relaxation, and crack 2. Consistent with NUREG-1801, initiation and growth due this group includes carbon and to cyclic loading or SCC low alloy steel in ambient air at FCS.

2. Consistent with NUREG-1801, this group includes carbon and low alloy steel in ambient air at FCS.

42

Further evaluation required TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Component Aging Aging Management Further Evaluation Discussion Effect/Mechanism Programs Recommended Steam Loss of material due Inservice inspection; Yes, detection of 1. The FCS aging management review results generator to pitting and crevice water chemistry aging effects is to are consistent with those reviewed and shell corrosion be further approved in NUREG-1801.

assembly evaluated 2. This aging effect is managed by the Inservice Inspection Program (B.1.5), the Chemistry Program (B.1.1) and the Steam Generator Program (B.1.7). The Steam Generator Program includes methods to detect general, crevice and pitting corrosion discussed in NUREG-1801, Volume 2, IV.D1.1-c. These programs are described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes carbon steel in deoxygenated treated water at FCS.

This aging effect is managed by the Inservice Inspection Program (B.1.5),

the Chemistry Program (B.1.1) and the Steam Generator Program (B.1.7).

The Steam Generator Program includes methods to detect general, crevice and pitting corrosion discussed in NUREG-1801, Volume 2, IV.D1.1-c. 43 These programs are described in Appendix B of this application.

Plant specific program TABLE 3.2-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Component Aging Aging Management Further Discussion Effect/Mechanism Programs Evaluation Recommended Components in Loss of material due Plant specific Yes, plant 1. The FCS aging management review containment spray to pitting and crevice specific results are consistent with those (PWR only), standby corrosion reviewed and approved in NUREG-gas treatment (BWR 1801.

only), containment 2. The Chemistry Program (B.1.1) isolation, and supplemented by the One Time emergency core Inspection Program (B.3.5) manages cooling systems the aging effects of these components. These programs are described in Appendix B of this application.

3. Consistent with NUREG-1801, this group only includes stainless steel in oxygenated treated water for components in containment isolation at FCS.

The Chemistry Program (B.1.1) supplemented by the One Time Inspection Program (B.3.5) manages the aging effects of these components. These programs are described in Appendix B of this 44 application.

Site Specific Components GALL demonstration Lessons Learned

- There is a need for the applicant to reference a program evaluated in the GALL report for a component, not covered by the GALL report, if it involves similar intended function, environment, material, aging effect, system, and ASME Code Class (if applicable) with another component.

45

Site Specific Components The FCS LRA references a program evaluated in NUREG-1801 for a component not covered by NUREG-1801, only if it involves an intended function, environment, material, aging effect, system, and ASME Code Class (if applicable) similar to a component included in NUREG-1801.

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FCS specific components in same system TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Component Aging Aging Further Discussion Effect/Mechanism Management Evaluation Programs Recommended Spent fuel storage Crack initiation and Water chemistry No 1. The aging management results are racks and valves in growth due to stress consistent with those reviewed and spent fuel pool corrosion cracking approved in NUREG-1801.

cooling and cleanup 2. Consistent with NUREG-1801, this group includes stainless steel in borated treated water at FCS.

3. In addition to the components in NUREG-1801 this group includes fuel tilting machine, fuel transfer tube, fuel transfer conveyor, fuel transfer carrier box and miscellaneous fuel handling equipment at FCS.

In addition to the components in NUREG-1801 this group includes fuel tilting machine, fuel transfer tube, fuel transfer conveyor, fuel transfer carrier box and miscellaneous fuel handling equipment at FCS. 47

FCS specific components in different system groups T A B L E 3 .2 -1 S U M M A R Y O F A G IN G M A N A G E M E N T P R O G R A M S F O R E N G IN E E R E D S A F E T Y F E A T U R E S E V A L U A T E D IN N U R E G -1 8 0 1 T H A T A R E R E L IE D O N F O R F C S L IC E N S E R E N E W A L Com ponent A g in g A g in g F u rth e r D isc u s sio n E ffe c t/M e c h a n ism Managem ent E va lu a tio n P ro g ra m s Recom m ended P u m p s, va lve s, C ra ck in itiatio n an d W ate r No 1. T h e a g in g m a n a ge m en t re su lts a re con sisten t w ith p ip ing , a nd fitting s g ro w th d u e to S C C c h e m istry th e re su lts d o cu m e nted in N U R E G -18 01 .

in con ta in m en t 2. C o n siste n t w ith N U R E G -18 0 1 , th is g rou p in clud e s sp ra y a nd sta in le ss ste e l a nd sta in le ss stee l clad ca rb o n e m e rge n cy co re ste e l in ch e m ica lly tre ated b o rate d w ate r a t F C S .

co o ling syste m s 3. In a dd ition to th e co m po n e nts in N U R E G - 1 80 1 ,

th is g ro up in clu de s th e safe ty in je ction ta n ks (a ccu m u la to rs), flo w e le m e n t an d o rifice b od ie s, o rifice p la te , a nd h ea t e xch a ng e rs in th e E n g in ee red S afe ty Fe atu re s S yste m a t F C S .

4. In a dd ition to th e co m po n e nts in N U R E G -1 8 01 ,

th is g ro up in clu de s p ipe s, fittin g s, va lve bo d ie s, filte r ca sin g s, p u m p ca sin g s, io n e xch ang e rs a nd h e a t e xcha n g e rs in th e S p en t Fu e l C o o ling S yste m , w h ich is o n e of th e A u xilia ry S ys te m s a t FCS.

In addition to the components in NUREG-1801, this group includes pipes, fittings, valve bodies, filter casings, pump casings, ion exchangers and heat exchangers in the Spent Fuel Cooling System, which is one of the Auxiliary Systems at FCS. 48

Site Specific Materials

  • GALL demonstration Lessons Learned

- It is the applicants responsibility to provide the basis for the determinations on materials and aging effects that are not addressed in GALL and justify them in the application.

49

Site Specific Materials The FCS LRA references a program evaluated in NUREG-1801 for a material, not covered by NUREG-1801, only if it involves the same environment, same aging effect and same aging management program as the material(s) included in NUREG 1801.

50

FCS specific materials TABLE 3.2-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Component Aging Aging Further Discussion Effect/Mechanism Management Evaluation Programs Recommended Carbon steel Loss of material Boric acid No 1. The aging management results are consistent components due to boric acid corrosion with the results documented in NUREG-1801 corrosion 2. Consistent with NUREG-1801, this group includes carbon and low alloy steel at FCS.

3. In addition to the materials discussed in NUREG-1801, this group includes cast iron and galvanized carbon steel at FCS.

In addition to the materials discussed in NUREG-1801, this group includes cast iron and galvanized carbon steel at FCS.

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FCS AMR results not evaluated in GALL

- the aging mechanisms are identified for the applicable AERMs 52

FCS AMR results not evaluated in GALL TABLE 3.2-2 FCS ENGINEERED SAFETY FEATURES COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW NOT EVALUATED IN NUREG-1801 Component Material Environment AERMs Program/Activity Types Heat Exchanger - Alloy 600 Treated Water - Loss of Material Chemistry Tubes Borated Crevice Program(B.1.1) corrosion in the presence of sufficient levels of oxygen, halogens, sulfates, or copper Crevice corrosion in the presence of sufficient levels of oxygen, halogens, sulfates, or copper 53

Operating Experience

  • GALL demonstration Lessons Learned

- The GALL report is based on industry operating experience prior to June, 2001.

  • Industry operating experience issued after the publication of NUREG-1801 is addressed by a review of operating experience issued during 2001.

54

Uncommon Components

  • GALL demonstration Lessons Learned

- Additional description of uncommon components not addressed in the GALL report should be included in the license renewal application to facilitate staff review of the aging management program.

  • Inclusion of the text searchable FCS USAR with the LRA should allow reviewers to obtain additional information on uncommon components.

55

Time Limited Aging Analyses Bernie Van Sant 56

Time Limited Aging Analyses Documents reviewed for FCS TLAA

- Statements of Consideration (SOC) for 10 CFR 54

- NUREG-1800

- NEI 95-10

- Industry license renewal applications

- FCS CLB (including licensing documents and the USAR)

- Design Basis Documents 57

TLAA Applicable to FCS LRA TLAA Category Analysis 54.21(c)(1) Resolution Description Section Reactor Vessel Pressure/Temperatures (ii) The analyses will be projected to the 4.2.1 Neutron (P/T) Curves end of the period of extended Embrittlement operation.

Low Temperature (ii) The analyses will be projected to the 4.2.2 Overpressure Protection end of the period of extended (LTOP) PORV Set points operation.

Pressurized Thermal Shock (ii) The analyses have been projected 4.2.3 (PTS) to the end of the period of extended operation.

Reactor Vessel Upper Shelf (ii) The analyses will be projected to the 4.2.4 Energy end of the period of extended operation.

Metal Fatigue ASME III, Class 1 (vessels) (iii) The effects of aging on the intended 4.3.1 RCS Piping function(s) will be adequately managed for the period of extended operation.

Pressurizer Surge Line (iii) The effects of aging on the intended 4.3.2 Thermal Stratification function(s) will be adequately managed for the period of extended operation.

Fatigue of Class II and III (i) 4.3.3 The analyses remain valid for the Components (excluding period of extended operation.

NSSS Sampling)

NSSS Sampling (iii) The effects of aging on the intended 4.3.3 function(s) will be adequately managed for the period of extended operation.

58

TLAA Applicable to FCS LRA TLAA Category Analysis 54.21(c)(1) Resolution Description Section Environmental EQ of Electrical Equipment (iii) The effects of aging on the 4.4 Qualification intended function(s) will be adequately managed for the period of extended operation.

Concrete Containment Tendon Pre-stress (iii) The effects of aging on the 4.5 Containment Pre- intended function(s) will be Stress adequately managed for the period of extended operation.

Containment Liner Containment Liner Plate and (ii) The analyses will be 4.6 Penetration Sleeve Fatigue projected to the end of the period of extended operation Other TLAAs Reactor Coolant Pump Flywheel (i) The analyses remain valid 4.7.1 Fatigue for the period of extended operation.

Leak Before Break (LBB) (ii) The analyses will be 4.7.2 and Thermal Aging of Cast projected to the end of the Austenitic Stainless Steel period of extended operation High Energy Line Break (i) The analyses remain valid 4.7.3 for the period of extended operation.

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Current Technical Issues Positions in FCS LRA 60

Current Technical Issues

  • Concrete Aging

- ISI and Structures Monitoring are credited as AMPs

- Commitment to ground water monitoring

  • II/I

- All components whose failure could cause a failure of CQE equipment are classified as Limited-CQE and are included in scope

  • Fire Protection 61

Questions 62

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