Text

February 13, 2002, Meeting with Fort Calhoun Stations, Unit 1, Handouts
	ML020800148
Person / Time
Site:	Fort Calhoun
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)
	v • d • e

1 Fort Calhoun Station LRA Overview

2 Overview of Application

Features of the SRP format (Gasper)

FCS acronyms/terminology (Van Sant)

FCS LRA Methodology & Results

- Scoping, Screening and AMR (Van Sant)

- Aging Management Programs (Henry)

- Break

- LRA Section 3 (Gasper)

- TLAA (Van Sant)

Positions on technical issues (Gasper) 8:45 9:00 9:15 9:30 10:00 10:30 10:35

3 Previous Applications

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

Aging Management Programs addressed ten elements

4 Table 3.2-5 Engineered Safety Features Systems Safety Injection Component Group Passive Function Material Group Environment Aging Effects Requiring Management Aging Management Activity (E) Air None None Required Carbon Steel and Low-alloy Steel (E) Borated Water Leakage Loss of Material Boric Acid Corrosion Surveillance (I) Gas None None Required Accumulators (and cladding)

PB Stainless Steel (I) Treated Water Loss of Material Chemistry Control Program for Primary Systems (E) Air Loss of Pre-Load 1

ISI Program - Component and Component Support Inspections Boric Acid Corrosion Surveillance Bolting PB Carbon Steel and Low-alloy Steel (E) Borated Water Leakage Loss of Material General Condition Monitoring Activities (E) Air None None Required Flow Elements PB;RF Stainless Steel (I) Treated Water Loss of Material Chemistry Control Program for Primary Systems (E) Air None None Required Instrument Valve Assemblies PB Stainless Steel (I) Treated Water Loss of Material Chemistry Control Program for Primary Systems (E) Air None None Required Chemistry Control Program for Primary Systems Cracking ISI Program - Component and Component Support Inspections1 Pipe PB Stainless Steel (I) Treated Water Loss of Material Chemistry Control Program for Primary Systems Surry/North Anna LRA

5 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.

6 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.

7 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.

8 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

9 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

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

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

12 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

13 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

14 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

15 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

16 Scoping and Screening Methodology and Results

17 Screening of components for Passive Long Lived No Yes Describe system/

structure, identify all functions Identify Intended Functions, Determine LR Evaluation Boundary List/Describe Components in Scope For each System RAMS DBDs USAR Engineering Analyses P&IDs CQE List Plant Modification Packages System/

Structure not in Scope System/

Structure Performs Intended Functions Scoping of plant systems and structures Scoping of system and structural components Yes No Source Documents Component subject to Aging Management Review Component not subject to Aging Management Review

18 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

19 Scoping Results TABLE 2.3.2.2-1 SPENT FUEL POOL COOLING Component Types Subject to Aging Management Review and Intended Functions Component Type 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

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

environment Assign Aging Management Program

21 Aging Management Review of Components (On-site documentation)

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

SHELL Carbon Steel Corrosion-Inhibited Treated Water Loss of Material Cooling Water Corrosion Program HEAT EXCHANGER -

TUBE SHEET Stainless Steel Treated Water -

Borated Cracking Chemistry Program Stainless Steel Treated Water -

Borated Cracking Chemistry Program Alloy 600 Treated Water -

Borated Fatigue Fatigue Monitoring HEAT EXCHANGER -

TUBES Alloy 600 Treated Water -

Borated Loss of Material Chemistry Program ORIFICE PLATE Stainless Steel Treated Water -

Borated Cracking Chemistry Program

22 Aging Management Programs Ken Henry

23 Aging Management Program Analysis AERM identified from Aging Management Review Is there a comparable aging management program identified in GALL?

Conduct GALL comparison Conduct 10 element assessment No Yes Determine aging management program to address AERM

24 GALL Comparison FCS aging management program Enhance/develop program.

Justify exception to specified criteria and included in LRA.

Is FCS aging management program consistent with GALL?

Does applicable OE verify effectiveness of program?

Credit program for aging management No No Yes No Yes

25 10 element assessment FCS aging management activity/program Enhance program.

Does the program include the 10 elements of Branch Technical Position RLSB-1, as appropriate?

Does applicable OE verify effectiveness of program?

Credit program for aging management.

Yes No Yes No

26 Existing Aging Management Activities

B.1.1 Chemistry Program

B.1.2 Containment Inservice Inspection Program

B.1.3 Containment Leak Rate Program

B.1.4 Flow Accelerated Corrosion Program

B.1.5 Inservice Inspection Program

B.1.6 Reactor Vessel Integrity Program

B.1.7 Steam Generator Program

27 Enhanced Aging Management Activities

B.2.1 Bolting Integrity Program

B.2.2 Boric Acid Corrosion Prevention Program

B.2.3 Cooling Water Corrosion Program

B.2.4 Diesel Fuel Monitoring and Storage Program

B.2.5 Fatigue Monitoring Program

B.2.6 Fire Protection Program

28 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

29 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.3.4 Non-EQ Cable Aging Management Program (site specific program)

B.3.5 One-Time Inspection Program

B.3.6 Selective Leaching Program

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

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 Penetrations Alloy 600 Program (B.3.1)

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

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

XI.M13 Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS)

Reactor Vessel Internals Inspection Program (B.2.9)

31 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.

32 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.

33 AGING MANAGEMENT REVIEW RESULTS Joe Gasper

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

35 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 Type Component Aging Effect/

Mechanism Aging Management Programs Further Evaluation Recommended BWR/PWR Closure bolting in high pressure or high temperature systems Loss of material due to general corrosion, loss of preload due to stress relaxation, and crack initiation and growth due to cyclic loading or SCC Bolting integrity No

36 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)

Type Component Aging Effect/

Mechanism Aging Management Programs Further Evaluation Recommended Item Number in GALL BWR/

PWR Closure bolting in high-pressure or high-temperature systems Loss of material due to general corrosion; crack initiation and growth due to cyclic loading and/or SCC Bolting integrity No V.E.2-a, V.E.2-b.

37 GALL Report Volume 2 identifies Aging Management Review Group evaluated in GALL Report V

Engineered Safety Features E. Carbon Steel Components Item Structure and/or Component Material Environment E.2-a E.2.1 Closure bolting In high-pressure or high-temperature systems Carbon steel, low-alloy steel Air, moisture, humidity, and leaking fluid Aging Effect/

Mechanism Aging Management Program (AMP)

Further Evaluation Loss of material/

General corrosion Chapter XI.M18, Bolting Integrity No

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

39 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 Item Structure and/or Component Material Environment Aging Effect/

Mechanism Aging Management Program (AMP)

Further Evaluation E.2-a E.2.1 Closure bolting In high-pressure or high-temperature systems Carbon steel, low-alloy steel Air, moisture, humidity, and leaking fluid Loss of material/

General corrosion Chapter XI.M18, Bolting Integrity No Equipment Type Material External Environment AERM Plant Programs BOLTING Carbon Steel Plant Indoor Air Loss of Material Bolting Integrity Program Three other FCS AMR results are consistent with V.E.2-a or V.E.2-b

40 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 Effect/Mechanism Aging Management Programs Further Evaluation Recommended Discussion Closure bolting in high pressure or high temperature systems Loss of material due to general corrosion, loss of preload due to stress relaxation, and crack initiation and growth due to cyclic loading or SCC Bolting integrity No

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

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

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

41 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.

42 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 Effect/Mechanism Aging Management Programs Further Evaluation Recommended Discussion Closure bolting in high pressure or high temperature systems Loss of material due to general corrosion, loss of preload due to stress relaxation, and crack initiation and growth due to cyclic loading or SCC Bolting integrity No

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

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

43 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 Effect/Mechanism Aging Management Programs Further Evaluation Recommended Discussion Steam generator shell assembly Loss of material due to pitting and crevice corrosion Inservice inspection; water chemistry Yes, detection of aging effects is to be further evaluated

1. The FCS aging management review results are consistent with those reviewed and approved in NUREG-1801.

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.

These programs are described in Appendix B of this application.

44 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 Effect/Mechanism Aging Management Programs Further Evaluation Recommended Discussion Components in containment spray (PWR only), standby gas treatment (BWR only), containment isolation, and emergency core cooling systems Loss of material due to pitting and crevice corrosion Plant specific Yes, plant specific

1. The FCS aging management review results are consistent with those reviewed and approved in NUREG-1801.

2. 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 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 application.

45 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.

46 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.

47 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 Effect/Mechanism Aging Management Programs Further Evaluation Recommended Discussion Spent fuel storage racks and valves in spent fuel pool cooling and cleanup Crack initiation and growth due to stress corrosion cracking Water chemistry No

1. The aging management results are consistent with those reviewed and approved in NUREG-1801.

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.

48 FCS specific components in different system groups T ABLE 3.2-1 SUM M ARY O F AG ING M AN AG EM ENT PRO G RAM S FO R ENG INEERED SAFET Y FEAT URES EVALU AT ED IN NUREG -1801 T HAT ARE RELIED O N FO R FCS LICENSE R ENEW AL Com ponent Aging Effect/Mechanism Aging Managem ent Program s Further Evaluation Recom m ended Discussion Pum ps, valves, piping, and fittings in containm ent spray and em ergency core cooling system s Crack initiation and growth due to SCC W ater chem istry No

1. The aging managem ent results are consistent with the results documented in NUREG -1801.

2. Consistent with NUREG -1801, this group includes stainless steel and stainless steel clad carbon steel in chem ically treated borated water at FCS.

3. In addition to the com ponents in NUREG - 1801, this group includes the safety injection tanks (accum ulators), flow elem ent and orifice bodies, orifice plate, and heat exchangers in the Engineered Safety Features System at FCS.

4. In addition to the com ponents in NUREG -1801, this group includes pipes, fittings, valve bodies, filter casings, pum p casings, ion exchangers and heat exchangers in the Spent Fuel Cooling System, which is one of the Auxiliary System s at 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.

49 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.

50 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.

51 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 Effect/Mechanism Aging Management Programs Further Evaluation Recommended Discussion Carbon steel components Loss of material due to boric acid corrosion Boric acid corrosion No

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

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.

52 FCS AMR results not evaluated in GALL

FCS AMR results not evaluated in NUREG-1801 are discussed in Tables 3.x-2.

- the aging mechanisms are identified for the applicable AERMs

53 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 Types Material Environment AERMs Program/Activity Heat Exchanger -

Tubes Alloy 600 Treated Water -

Borated Loss of Material Crevice corrosion in the presence of sufficient levels of oxygen,

halogens, sulfates, or copper Chemistry Program(B.1.1)

Crevice corrosion in the presence of sufficient levels of oxygen, halogens, sulfates, or copper

54 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.

55 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.

56 Time Limited Aging Analyses Bernie Van Sant

57 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

58 TLAA Applicable to FCS TLAA Category Analysis 54.21(c)(1)

Resolution Description LRA Section Reactor Vessel Neutron Embrittlement Pressure/Temperatures (P/T) Curves (ii)

The analyses will be projected to the end of the period of extended operation.

4.2.1 Low Temperature Overpressure Protection (LTOP) PORV Set points (ii)

The analyses will be projected to the end of the period of extended operation.

4.2.2 Pressurized Thermal Shock (PTS)

(ii)

The analyses have been projected to the end of the period of extended operation.

4.2.3 Reactor Vessel Upper Shelf Energy (ii)

The analyses will be projected to the end of the period of extended operation.

4.2.4 Metal Fatigue ASME III, Class 1 (vessels)

RCS Piping (iii)