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ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Subject: Document Transmittal: MRP Letter 2008-036 dated June 12, 2008; Subject: Minutes of the Expert Panel Meetings on Expansion Criteria for Reactor Internals I&E Guidelines Reference: 1) EPRI report "Materials Reliability Program: Pressurized Water ReactorInternals Inspection and Evaluation Guidelines (MiRP-22 7-Rev. 0)" EPRI Palo Alto, CA, 2008, 1016596. 2) REQUEST FOR ADDITIONAL INFORMATION NUMBER 4, RE: ELECTRIC POWER RESEARCH INSTITUTE TOPICAL REPORT 1006596,'MATERIALS RELIABILITY PROGRAM: PRESSURIZED WATER REACTOR INTERNALS INSPECTION AND EVALUATION GUIDELINES (MRP-227-REV. 0)' (TAC NO. ME0680) To Whom It May Concern: Two copies of the subject document are being forwarded to assist the NRC Staff in its review of MRP- 227, Reference 1. Specifically, the document is being provided to supplement the response to RAI 26 of Reference 2. If you have any questions on this subject, please contact Anne Demma at 650-855-2026. Sincerely, Terry McAlister SCANA Chairman, Materials Reliability Program Cc: James Lash, First Energy Sheldon Stuchell, NRC (with 8 copies of Subject document) Victoria Anderson, NEI Chuck Welty, EPRI Anne Demma, EPRI Together ... Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA * 650.855.2000 * Customer Service 800.313.3774 * www.epri.com

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Page 1: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ju ELECTRIC POWERRESEARCH INSTITUTE

MRP Materials Reliability Program MRP 2010-065

(via email)

October 27, 2010

Document Control DeskU.S. Nuclear Regulatory Commission11555 Rockville PikeRockville, MD 20852

Subject: Document Transmittal: MRP Letter 2008-036 dated June 12, 2008; Subject: Minutes of theExpert Panel Meetings on Expansion Criteria for Reactor Internals I&E Guidelines

Reference:1) EPRI report "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and

Evaluation Guidelines (MiRP-22 7-Rev. 0)" EPRI Palo Alto, CA, 2008, 1016596.

2) REQUEST FOR ADDITIONAL INFORMATION NUMBER 4, RE: ELECTRIC POWERRESEARCH INSTITUTE TOPICAL REPORT 1006596,'MATERIALS RELIABILITYPROGRAM: PRESSURIZED WATER REACTOR INTERNALS INSPECTION ANDEVALUATION GUIDELINES (MRP-227-REV. 0)' (TAC NO. ME0680)

To Whom It May Concern:

Two copies of the subject document are being forwarded to assist the NRC Staff in its review of MRP-227, Reference 1. Specifically, the document is being provided to supplement the response to RAI 26 ofReference 2.

If you have any questions on this subject, please contact Anne Demma at 650-855-2026.

Sincerely,

Terry McAlisterSCANAChairman, Materials Reliability Program

Cc: James Lash, First EnergySheldon Stuchell, NRC (with 8 copies of Subject document)Victoria Anderson, NEIChuck Welty, EPRIAnne Demma, EPRI

Together ... Shaping the Future of Electricity

PALO ALTO OFFICE3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA * 650.855.2000 * Customer Service 800.313.3774 * www.epri.com

Page 2: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

M R P Materials Reliability Program MRP 2008-036

(Via email)

June 12, 2008

To: Reactor Internals Focus Group

Subject: Minutes of the Expert Panel Meetings on Expansion Criteria for Reactor Internals I&EGuidelines

Expert panel meetings were held at the EPRI office in Charlotte to generate expansion criteriafor the Reactor Internals I&E Guidelines for the Westinghouse and CE components on April 3 0 th

and for the B&W components on May 1s 2008.

The participants on the April 30'h meeting were: Glenn Gardner, Dominion; Tim Wells, SouthernNuclear; David Whitaker, Duke Energy; Ted Huminski, Progress Energy; Cheryl Boggess,Westinghouse; Randy Lott, Westinghouse; John Keilb, Westinghouse; Bob Nickell, Anatech;and Anne Demma, EPRI.

The participants on the May lst meeting were: Glenn Gardner, Dominion; Tim Wells, SouthernNuclear; David Whitaker, Duke Energy; Steve Fyfitch, Areva; Hongqing Xu, Areva; BillBehnke, Areva; Brad Thigpen, Areva; Bob Nickell, Anatech; and Anne Demma, EPRI.

The objectives of the meetings were to review the inputs provided by the NSSS vendors onexpansion criteria prior to the meetings and to make decisions on expansion criteria during thesemeetings.

The process used to generate the expansion criteria was consistent and repetitive to supportconsistency in decision making.

The process steps are outlined below:- Perform integrated review of information for the specific components- Define key contributors- Consider impacts from key contributors- Generate consensus recommendation

Page I of 2 MRP 2008-036

Page 3: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

The results from these steps were recorded in specific sections of a worksheet for eachcomponent and the information that each section contains is explained below.

Section Definition

SECTION 1 Expansion This section contains information describing the component, theComponent degradation and effect, and the Inspection Examination MethodIndentification and Coverage.

SECTION 2 Linked This section contains information describing ihe PrimaryPrimary Component Component, Inspection characteristics, and Disposition/Evaluation

of inspection results.

SECTION 3 Comparison This subsection identifies key factors between the Primary andof Key Factors Expansion components that contribute to the expansion

recommendation.

SECTION 4 Other This subsection identifies additional considerations that support theConsiderations expansion criteria and timing not captured already. Items such as

the impacts of plant modifications or design differences that mightaffect the generic recommendation.

SECTION 5 Expansion This subsection identifies the Expansion Recommendation andRecommendation summarizes the Basis supporting the recommendation. The

information in this section is the culmination of the analysis,information, and results presented in the entire worksheet and theexpert panel process. The expansion recommendation and thebasis for that conclusion are documented in this section.

The panel worksheet descriptions for Westinghouse, CE, and B&W components are attached inAttachments 1, 2 and 3, respectively.

If you have any questions or concerns, please contact Anne Demma (ademma(iaýepri.com, 650-855-2026).

Best Regards,Anne ODenmnaProject ManagerEPRI Materials Reliability Program

Cc: Christine King

Page 2 of 2 MRP 2008-036

Page 4: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:Lower support column bolts

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Lower Support Assembly Lower support column bolts MRP-232 DRAFT

Description/Figure: Figure 4-41 and 4-42 MRP-227 Draft C

Degradation/Effect: IASCC, Fatigue/Cracking MRP-232 DRAFT

Section 2: Linked Primary Component

Name: Baffle-Former Assembly Baffle-Former Bolt MRP-232 DRAFT

Degradation/Effect: IASCC, Fatigue/Cracking MRP-232 DRAFT

How (Inspection Technique): UT MRP-232 DRAFT

When: no later than five refueling cycles following 25 EFPY, MRP-227 DRAFT Cwith subsequent examination after 10 to 15 additional EFPYto confirm stability of bolting pattern. Re-examination forhigh-leakage core designs requires continuing examinationson a ten-year interval.

Inspection Data: 100% of accessible bolts or as supported by MRP-232 DRAFTplant-specific justification. Heads accessible from the coreside. UT accessibility may be affected by complexity of headand locking device designs. Any detectable recordable flaw isconsidered.

Disposition/Evaluation: PWROG minimum bolting pattern MRP-232 DRAFTacceptable

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: 150 dpa peak 15 dpa peak MRP-230 DRAFT

Temperature: >608F >608F MRP-191

Mechanical Load: plant and design plant and design MRP-191specific, VS specific

Material: Austenitic 316 SS, 304SS MRP- 191347SS

Other:

Page 5: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower support column bolts

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: observed industry failures in primary MRP- 191component

Plant Specific Considerations:

Additional Considerations: All plants MRP-232 DRAFT

Section 5: Final Expansion Recommendation

Recommendation: >5% of baffle-former bolts confirmed failedon four baffle plates the largest distance from the core(presumed to be lowest dose location). UT Inspection oflower support column bolts within next 3 fuel cycles.Percentage is based only on bolts inspected.

Basis: 60 year irradiation doses in low fluence plate bolts 13-45 MRP-230 DRAFTdpa (former levels 1-8). Majority of support column boltsbelow 10 dpa at 60 years. Fluence distribution flatter on coreplate. Structure is generally a flaw tolerant design and highlyredundant.

Page 6: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Barrel-Former Bolts

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Baffle-Former Assembly Barrel-Former Bolts MRP-232 DRAFT

Description/Figure: Figures 4-37 and 4-38 MRP-227 Draft C

Degradation/Effect: IASCC, Fatigue/Cracking MRP-232 DRAFT

Section 2: Linked Primary Component

Name: Baffle-Former Assembly Baffle-Former Bolt MRP-232 DRAFT

Degradation/Effect: IASCC, Fatigue/Cracking MRP-232 DRAFT

How (Inspection Technique): UT MRP-232 DRAFT

When: no later than five refueling cycles following 25 EFPY, MRP-227 DRAFT Cwith subsequent examination after 10 to 15 additional EFPYto confirm stability of bolting pattern. Re-examination forhigh-leakage core designs requires continuing examinationson a ten-year interval.

Inspection Data: 100% of accessible bolts or as supported by MRP-232 DRAFTplant-specific justification. Heads accessible from the coreside. UT accessibility may be affected by complexity of headand locking device designs. Any detectable recordable flaw isconsidered.

Disposition/Evaluation: PWROG minimum bolting pattern MRP-232 DRAFTacceptable

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: 150 dpa peak 13 dpa peak MRP-230 DRAFT

Temperature: >608F >608F MRP-191

Mechanical Load: plant and design plant and design MRP-191specific, VS specific

Material: Austenitic 316 SS, Austenitic 316 SS, MRP-191347SS 347SS

Other:

Page 7: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Barrel-Former Bolts

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: Observed industry failures in baffle-former bolts. French experience correlates with high fluenceseams. Limited experience in US plants more random.

Plant Specific Considerations:

Additional Considerations: Not all bolts are accessible due topresence of thermal shield or neutron pads. More areaccessible if neutron pads are used. Ability to inspectbarrel-former bolts otherwise is the same as for baffle-formerbolts.

Section 5: Final Expansion Recommendation

Recommendation: >5% of baffle-former bolts confirmed failedon four plates at the largest distance from the core (presumedto be lowest dose location). UT Inspection of lower supportcolumn bolts within next 3 fuel cycles. If>5% of coresupport column bolts then UT inspection of core barrel bolts.Percentage is based only on bolts inspected.

Basis: 60 year irradiation doses in low fluence plate bolts 13-45 MRP-230 DRAFTdpa (former levels 1-8). Majority of barrel-former boltsbelow 5 dpa at 60 years. Fluence distribution flatter on coreplate. Structure is a highly redundant design.

Page 8: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Core barrel welds (Core barrel outlet nozzle welds, core barrel axial welds)

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Barrel Assembly Core barrel welds (Core barrel MRP-232 DRAFToutlet nozzle welds, core barrel axial welds)

Description/Figure: Figure 4-31 MRP-227 Draft C

Degradation/Effect: SCC/Cracking .MRP-232 DRAFT

Section 2: Linked Primary Component

Name: Core Barrel Assembly Upper core barrel flange weld MRP-232 DRAFT

Degradation/Effect: SCC, Fatigue/Cracking MRP-232 DRAFT

How (Inspection Technique): VT-1 MRP-232 DRAFT

When: no later than 2 refueling outages from the beginning of MRP-227 DRAFT Cthe license renewal period and subsequent examination on aten-year interval.

Inspection Data: 100 % of one side of the accessible surfaces of MRP-232 DRAFTthe selected weld and adjacent base metal.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: < 1020 < 1020 MRP-191

Temperature: T-hot T-hot MRP- 191

Mechanical Load: Weld Weld MRP-191

Material: 304 SS/Weld 308 304 SS/Weld 308 MRP-191

Other:

Page 9: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Core barrel welds (Core barrel outlet nozzle welds, core barrel axial welds)

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: Generally Good,

Plant Specific Considerations:

Additional Considerations: All plants MRP-232 DRAFT

Section 5: Final Expansion Recommendation

Recommendation: If an observed surface breaking indication>2" in the Primary component is confirmed then a VT-1inspection of the core barrel to support plate weld isperfoined within completion of one refueling outage.Extensive confirmed indications require further expansion.

Basis: SCC is projected as a slowly progressing degradation.Fluence at both flanges well below IA.SCC threshold.Structure is flaw tolerant.

Page 10: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower support column bodies

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Barrel Assembly Lower support column bodies MRP-232 DRAFT

Description/Figure: Figure 4-42 MRP-227 Draft C

Degradation/Effect: IASCC/Cracking MRP-232 DRAFT

Section 2: Linked Primary Component

Name: Core Barrel Assembly Upper core barrel flange weld MRP-232 DRAFT

Degradation/Effect: IASCC/Cracking MRP-232 DRAFT

How (Inspection Technique): VT-I MRP-232 DRAFTWhen: no later than 2 refueling outages from the beginning of MRP-227 DRAFT C

the license renewal period and subsequent examination on aten-year interval.

Inspection Data: 100 % of one side of the accessible surfaces of MRP-232 DRAFTthe selected weld and adjacent base metal.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: < 1020 < 5 x 1021 MRP-191

Temperature: T-hot >608 MRP-191

Mechanical Load: Weld Weld MRP-191

Material: 304 SS/Weld 308 304 SS/Weld 308/ MRP-191CF8

Other:

Page 11: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower support column bodies

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: No issues observed to date.

Plant Specific Considerations: Majority of core supportstructure should be in compression under normal operatingconditions. However, some designs with "winged" structuremay have local tensile stresses.

Additional Considerations: All plants MRP-232 DRAFT

Section 5: Final Expansion Recommendation

Recommendation: Any visual indication >2" in the Primarycomponent if confirmed would require complete visual (VT-1) or volumetric (UT) inspection of core barrel to lowersupport plate weld within completion of one refueling outage.Extensive cracking in the expanded welds would requirevisual (VT-1) inspection of the uipper six inches of accessiblesurfaces of the lower support column body within three fuelcycles of original observation.

Basis: The upper six inches of this component includes the MRP-230 DRAFTportion that is susceptible to IASCC.

Action: Change I&E Guidelines Table 4-3 and 4-6 to remove expansion link. Also revise text insections 3 and 5.Assigned: Demma/Nickell

Page 12: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower support column bodies

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Barrel Assembly Lower support column bodies MRP-232 DRAFT

Description/Figure: Figure 4-42 MRP-227 Draft C

Degradation/Effect: IASCC/Cracking MRP-232 DRAFT

Section 2: Linked Primary Component

Name: Control Rod Guide Tube Assembly Lower flanges MRP-232 DRAFT

How (Inspection Technique): VT-i MRP-232 DRAFT

When: no later than 2 refueling outages from the beginning of MRP-227 DRAFT Cthe license renewal period and subsequent examination on aten-year interval.

Inspection Data: 100 % of accessible weld surfaces and adjacent MRP-232 DRAFTbase metal to determine the presence of crack-like surfaceflaws in flange welds.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: 7 x 1020 to 1 x < 5 x 1021 MRP-1911021

Temperature: T-hot >608 MRP-191

Mechanical Load: Weld Weld MRP- 191

Material: 304/CF8 304/CF8 MRP- 191

Other:

Page 13: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower support column bodies

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience:

Plant Specific Considerations: Although drawings of lowerflange weld on CRGT assemblies indicate cast stainless steel,a preliminary review of manufacturing records indicates thatthese components were often fabricated from 304 plate.

Additional Considerations: All plants MRP-232 DRAFT

Section'5: Final Expansion Recommendation

Recommendation: Cracking confirmed in two or more CRGTflanges should expand to a visual inspection for failures inlower support columns within three fuel cycles of originalobservation.

Basis: Primary cracking concern is SCC. (High fluence limitedto upper sections of support.) Operating stresses tend to becompressive and system is highly redundant. CRGTconfiguration has similarities to support column. Welds inCRGT should have similar duplex structure to castings.

Action: Delete item.

Page 14: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

BMI column bodies

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Bottom Mounted Instrumentation System BMI column MRP-232 DRAFTbodies

Description/Figure: Figure 4-43 MRP-227 Draft C

Degradation/Effect: Fatigue/Cracking MRP-232 DRAFT

Section 2: Linked Primary Component

Name: Control Rod Guide Tube Assembly Lower flanges MRP-232 DRAFT

Degradation/Effect: Fatigue/Cracking MRP-232 DRAFT

How (Inspection Technique): VT-I MRP-232 DRAFTWhen: no later than 2 refueling outages from the beginning of MRP-227 DRAFT C

the license renewal period and subsequent examination on aten-year interval.

Inspection Data: 100 % of accessible weld surfaces and adjacent MRP-232 DRAFTbase metal to determine the presence of crack-like surfaceflaws in flange welds.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: 7 x 1020 to 1 x 1 x 1022 to 5 x MRP-1911021 1022

Temperature: T-hot >608 MRP-191

Mechanical Load: Weld Weld MRP-191

Material: CF8 304 SS/Weld 308 MRP-191

Other:

Page 15: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 1

Westinghouse Expansion Components

Section 4: Other Considerations

Operating Experience:

Plant Specific Considerations:

Additional Considerations: All plants MRP-232 DRAFT

Section 5: Final Expansion Recommendation

Recommendation: Flux thimble insertion/withdrawal to bemonitored at each inspection interval. Visual (VT-3)examination of BMI column bodies as indicated by difficultyof insertion/withdrawal of flux thimbles or observed crackingin two or more CRGT lower flanges.

Basis: The BMI column bodies guide BMI flux thimbles intocore. There is no significant structural or pressure boundaryfunction for these columns. Failure of a BMI colunm bodywould result in a misalignment of the structure and difficultieswith insertion. Observation of cracking in CRGT flanges orlower support columns would indicate an active mechanismthat might also affect the BMI columns.

Action: Re-evaluate. Eliminate from Expansion and re-categorize BMI column bodies.Action: Westinghouse

Page 16: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower core barrel flange weld

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Support Barrel Assembly Lower core barrel flange MRP-232 DRAFTweld (i.e. lower flange to cylinder weld).

Description/Figure: Figure 4-15, 4-20, 4-22 MRP-227 Draft C

Degradation/Effect: SCC, Fatigue - Cracking MRP-232 DRAFT

Examination Method/Coverage: One-time visual (VT-1) with MRP-232 DRAFTten-year intervals for 100% of accessible welds and adjacentbase metal.

Section 2: Linked Primary Component

Name: Core Support Barrel Assembly Upper flange weld MRP-232 DRAFT

Degradation/Effect: SCC, Fatigue - Cracking MRP-232 DRAFT

How (Inspection Technique): VT-i MRP-232 DRAFTWhen: no later than 2 refueling outages from the beginning of MRP-227 Draft C

the license renewal period. Subsequent examinations on aten-year interval.

Inspection Data: 100% of the accessible surfaces of the upper MRP-227 Draft Cflange weld.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: < 1020 < 1 020 MRP-191

Temperature: T-hot T-cold MRP-191

Mechanical Load: Weld Weld MRP- 191

Material: 304 SS/Weld 308 304 SS/Weld 308 MRP-191

Other:

Page 17: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Lower core barrel flange weld

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: Generally Good. Recent experience isaccess is fairly achievable for Primary

Plant Specific Considerations:

Additional Considerations: Applies to non-bolted core shroudplants. Fatigue in this weld is substantially less than in theflexure weld so it is not a significant concern for this weld

Section 5: Final Expansion Recommendation

Recommendation: If an observed surface breaking indication>2" in the Primary component is confirmed then a VT-Iinspection of the lower flange welds is performed bycompletion of the next refueling outage.

Basis: SCC is projected as a slowly progressing degradation.Fluence at both flanges well below IASCC threshold.Structure is flaw tolerant. Need an estimate of crack growthrate.

Observation: should use caution in determining supplementary examination. Should not presumeacceptance criteria.

Observation: Fatigue assessment could provide insights for lower flange.

Action: Primary component inspection recommendation should be investigated and changed ifneeded to provide clarity on inspection for single or dual side inspection. Driver in determiningfinal recommendation is to determine surface or full penetration.

Assigned: Westinghouse.

Page 18: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Core barrel welds

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Support Barrel Assembly Core barrel welds MRP-232 DRAFT

Description/Figure: Figure 4-15, 4-20, 4-22 MRP-227 Draft C

Degradation/Effect: SCC - Cracking MR-P-232 DRAFT

Examination Method/Coverage: Visual (VT-1), 100 % of one MRP-232 DRAFTside of the accessible weld and adjacent base metal surfacesfor the weld with the highest calculated operating stress.

Section 2: Linked Primary Component

Name: Core Support Barrel Assembly Upper flange weld MRP-232 DRAFT

Degradation/Effect: SCC - Cracking MRP-232 DRAFT

How (Inspection Technique): VT-I MRP-232 DRAFTWhen: no later than 2 refueling outages firom the begilming of MRP-227 Draft C

the license renewal period. Subsequent examinations on aten-year interval.

Inspection Data: 100% of the accessible surfaces of the upper MRP-227 Draft Cflange weld.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: < 1020 < 1020 MRP-191

Temperature: T-hot T-cold MRP-191

Mechanical Load: Weld Weld MRP- 191

Material: 304 SS/Weld 308 304 SS/Weld 308 MRP-191

Other:

Page 19: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Core barrel welds

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: Generally Good

Plant Specific Considerations:

Additional Considerations: Applies to non-bolted core shroudplants

Section 5: Final Expansion Recommendation

Recommendation: If an observed surface breaking indication>2" in the Primary component is confirmed then a VT-Iinspection of the lower flange welds is performed bycompletion of the next refueling outage. If observed surfaceindication > 2".is confirmed in Lower core barrel flange weldthen perform VT-I inspection of all remaining accessible corebarrel welds by completion of the same refueling outage.

Basis: Barrel is generally flaw tolerant. Through wall crackingrequired for critical crack. Crack growth rate should be smallcompared to size of structure.

Page 20: RESEARCH INSTITUTE MRP · ju ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program MRP 2010-065 (via email) October 27, 2010 Document Control Desk U.S. Nuclear Regulatory

ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:Core support column welds and casting

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Lower Support Structure Core support column welds MRP-232 DRAFTand castings

Description/Figure: Figure 4-20, 4-21, 4-22 MRP-227 Draft C

Degradation/Effect: SCC, IASCC, Fatigue - Cracking MRP-232 DRAFTExamination Method/Coverage: Visual (VT-1), Examination MRP-232 DRAFTcoverage determined by plant-specific analysis.

Section 2: Linked Primary Component

Name: Core Support Barrel Assembly Upper flange weld MRP-232 DRAFT

Degradation/Effect: SCC, IASCC, Fatigue - Cracking MRP-232 DRAFT

How (Inspection Technique): VT-I MRP-232 DRAFTWhen: no later than 2 refueling outages from the beginning of MRP-227 Draft C

the license renewal period. Subsequent examinations on a ten-year interval.

Inspection Data: 100% of the accessible surfaces of the upper MRP-227 Draft Cflange weld.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: <1020 1 x 1021 to 1x MRP-1911022

Temperature: T-hot T-cold MRP- 191

Mechanical Load: Weld Weld MRP-191

Material: 304 SS/Weld 308 304 SS/CF8 MRP-191

Other:

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:Core support column welds and casting

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: No Indications noted under currentVT-3 practices.

Plant Specific Considerations: Multiple column designs.Location of casting within plant should be identified. PotentialThermal Embrittlement must be accounted for in analysis.

Additional Considerations: All plants except those with coreshrouds assembled with full-height shroud plates

Section 5: Final Expansion Recommendation

Recommendation: Visual (VT-1) inspection of core barrelwelds indicates additional cracking concerns.

Basis: Primary cracking concern is SCC. (High fluence limited MRP-230 Draftto upper sections of support.) Operating stresses tend to becompressive and system is highly redundant. Large weldsshould have a duplex structure similar to castings.

Parking Lot: Core Group to decide if Cast version should stay as an Expansion component orbecome a Primary component. Potential RAI.

Observation: less rigorous exam from a more rigorous will attract concern under reviews.

Action: Determine distance criteria compatibility to support VT-I examination recommendation.Consider economics. Westinghouse?

Action: White paper to assess recommendation to support a VT-3 versus the current VT-1. IfVT-3 is acceptable move component to Existing category.Assigned: Westinghouse (Kielb)/Gardner (Dominion Millstone)

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:Remaining axial welds

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Shroud Assembly (Welded) Remaining axial welds MRP-232 DRAFT

Description/Figure: Figure 4-12 MRP-227 Draft C

Degradation/Effect: IASCC - Cracking MRP-232 DRAFT

Examination Method/Coverage: Visual (VT-1), Axial weld MRP-232 DRAFTseams other than the core shroud re-entrant corner welds atthe core mid-plane.

Section 2: Linked Primary Component

Name: Core Shroud Assembly (Welded) Core shroud plate- MRP-232 DRAFTformer plate weld.

Degradation/Effect: IASCC - Cracking MRP-232 DRAFT

How (Inspection Technique): VT- I MRP-232 DRAFT

When: no later than 2 refueling outages from the beginning of MRP-227 Draft Cthe license renewal period and subsequent examination on aten-year interval.

Inspection Data: Axial and horizontal weld seams at the core MRP-227 Draft Cshroud re-entrant corners as visible from the core side of theshroud, within six inches of central flange and horizontalstiffeners.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: 1 x 1022 to 5 x 1022 1 x 1022 to 5 x 1022 MRP-191

Temperature: >608 >608 MRP- 191

Mechanical Load: Weld Weld MRP- 191

Material: 304 SS/Weld 308 304 SS/Weld 308 MRP-191

Other:

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Remaining axial welds

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience: No observations. Core side visual.Recent VT-i inspections returned no indications.

Plant Specific Considerations:

Additional Considerations: Plant designs with core shroudsassembled in two vertical sections

Section 5: Final Expansion Recommendation

Recommendation: Any visual indication >2" in an axial weldseam if confirmed would require complete visual (VT-i) orvolumetric (UT) inspection of the axial weld seams at the coremid-plane within completion of one refueling outage.

Basis: Initial crack growth rate is expected to be high within theexamination region. Driving force for 'crack growth expectedto drop sharply beyond the examination region.

Observation: Concern on initial 1" detection ability (opening and length)f

Action: Verify gap permitted in axial joint for Millstone. Confirm drawings used consistent.Assigned: Westinghouse (Kielb)/Gardner (Dominion Millstone). Glenn's drawings show non-weldedseam with permitted .016 gap, dwg E-STD-164-25 sheets 1 and 2, Rev. 5

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Remaining axial welds, ribs and rings

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Shroud Assembly (Welded) Remaining axial MRP-232 DRAFTwelds, ribs and rings

Description/Figure: Figure 4-13 MRP-227 Draft TBD

Degradation/Effect: SCC, IASCC - Cracking MRP-232 DRAFT

Examination Method/Coverage: Visual (VT-1), Axial weld MRP-232 DRAFTseams other than the core shroud re-entrant comer welds atthe core mid-plane, plus ribs and rings

Section 2: Linked Primary Component

Name: Core Shroud Assembly (Welded) Shroud plates MRP-232 DRAFT

Degradation/Effect: SCC, IASCC - Cracking MRP-232 DRAFT

How (Inspection Technique): VT-1 MRP-232 DRAFT

When: no later than 2 refueling outages from the beginning of MRP-227 Draft Cthe license renewal period and subsequent examination on aten-year interval.

Inspection Data: Axial weld seams at the core shroud re-entrant MRP-227 Draft Ccorners, at the core mid-plane (± three feet in height) asvisible from the core side of the shroud.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: I x 1022 to 5 x 1022 1 x 1022 to 5 x 1022 MRP-191

Temperature: >608 >608 MRP-191

,Mechanical Load: Weld Weld MRP-191

Material: 304 SS/Weld 308 304 SS/Weld 308 MRP-191

Other:

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Remaining axial welds, ribs and rings

Component Description and Data 1 Sources

Section 4: Other Considerations

Operating Experience: There are a large number of ribs, ringsand other stiffeners welded to the back side of this coreshroud. Irradiation induced stress relaxation should eliminateweld residual stresses present at the beginning of operation.

Plant Specific Considerations:

Additional Considerations: Plant designs with core shroudsassembled with full-height shroud plates.

Section 5: Final Expansion Recommendation

Recommendation: Any visual indication >2" in an axial weldseam if confirmed would require complete visual (VT-1) orvolumetric (UT) inspection of the axial weld seams at the coremid-plane within completion of one refueling outage.Extensive cracking in the expanded axial welds would requirevisual (VT-1) inspection of accessible ribs and rings welds.

Basis: Axial welds are the initial inspection component.Structure is generally a flaw tolerant design. Ribs and ringsare redundant and do not represent a single point componentitem failure that would prevent continued function.

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Core support column bolts

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Lower Support Structure Core support column bolts MRP-232 DRAFT

Description/Figure: Figure 4-20, 4-21, 4-22 MRP-227 Draft C

Degradation/Effect: IASCC, Fatigue - Cracking MRP-232 DRAFT

Examination Method/Coverage: Ultrasonic (UT), 100 % (or as MRP-232 DRAFTsupported by plant-specific analysis) of core support columnbolts with neutron fluence exposures > 3 dpa.

Section 2: Linked Primary Component

Name: Core Shroud Assembly (Bolted) Core shroud bolts MRP-232 DRAFT

Degradation/Effect: IASCC, Fatigue - Cracking MRP-232 DRAFT

How (Inspection Technique): UT MRP-232 DRAFT

When: no later than five refueling cycles following 25 EFPY. MRP-227 Draft CFollow-up examination after additional 10-15 EFPY toconfirm stability of bolting pattern. Re-examination for high-leakage core designs requires continuing inspections on a ten-year interval.

Inspection Data: 100% of accessible bolts, or as supported by MRP-227 Draft Cplant-specific justification. Heads are accessible from thecore side. UT accessibility may be affected by complexity ofhead and locking device designs.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primary Expansion

hTadiation dose: 1 X 1021 to 1 X 1 X 1021 to 1 x MRP-1911022 1022

Temperature: >608 T-cold MRP- 191

Mechanical Load: Category A Category A MRP-191

Material: 316SS 316SS MRP-191

Other:

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ATTACHMENT 2

Combustion Engineering Expansion Components

i

Expansion Criteria Determination Expert Panel Worksheets:

Core support column bolts

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience:

Plant Specific Considerations: verify bolts are present in design

Additional Considerations: Applies to Bolted designs. There isno current requirement for inspecting lower support columnbolts in plants with welded core shrouds. Industry trendsshould be evaluated for possible revisions to I&E Guidelines.

Section 5: Final Expansion Recommendation

Recommendation: : >5% of bolts confirmed failed on fourplates at the largest distance from the core (presumed to belowest dose location). UT Inspection of lower support columnbolts within next 3 fuel cycles.

Basis: The lowest dose core shroud bolts are roughly equivalent MRP-230 Draftto leading core support column bolts. Temperatures andstresses are lower.

Observation: Vendor to ensure inspection examination detection rate is high.

Action: Check fluence distribution to ensure high dose plate assumption.Assigned: Westinghouse (Lott)

Suggest use dpa instead of fluence or cite a conversion factor. Dpa is preferred, since used inMRP-175 i

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:Barrel-shroud bolts

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Shroud Assembly (Bolted) Barrel-shroud bolts MRP-232 DRAFT

Description/Figure: Similar to Figure 4-28 MRP-227 Draft C

Degradation/Effect: IASCC, Fatigue - Cracking MRP-232 DRAFT

Examination Method/Coverage: Volumetric (UT), 100 % (or as MRP-232 DRAFTsupported by plant-specific justification) of barrel-shroudbolts with neutron fluence exposures > 3 dpa.

Section 2: Linked Primary Component

Name: Core Shroud Assembly (Bolted) Core Shroud Bolts MRP-232 DRAFT

Degradation/Effect: IASCC, Fatigue - Cracking MRP-232 DRAFT

How (Inspection Technique): UT MRP-232 DRAFT

When: no later than five refueling cycles following 25 EFPY. MRP-227 Draft CFollow-up examination after additional 10-15 EFPY toconfirm stability of bolting pattern. Re-examination for high-leakage core designs requires continuing inspections on a ten-year interval.

Inspection Data: 100% of accessible bolts, or as supported by MRP-227 Draft Cplant-specific justification. Heads are accessible from thecore side. UT accessibility may be affected by complexity ofhead and locking device designs.

Disposition/Evaluation:

Section 3: Comparison of Key Factors

Primar Expansion

Irradiation dose: 1 X 1022 to 5 x 1 X 1021 to 1 x MRP-1911022 1022

Temperature: >608 T-cold MRP-191

Mechanical Load: Category A Category A MRP-191

Material: 316 SS 316 SS/A286 MRP-191

Other:

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ATTACHMENT 2

Combustion Engineering Expansion Components

Expansion Criteria Determination Expert Panel Worksheets:

Barrel-shroud bolts

Component Description and Data Sources

Section 4: Other Considerations

Operating Experience:

Plant Specific Considerations:

Additional Considerations: Applies to Bolted designs

Section 5: Final Expansion Recommendation

Recommendation: >5% of bolts confirmed failed on four lowestplates at the largest distance from the core (presumed to belowest dose location). UT Inspection of lower supportcolumn bolts within next 3 fuel cycles. If>5% of coresupport column bolts then UT inspection of core barrel bolts.

Basis: The lowest dose core shroud bolts still lead fluence onbarrel by factor of 5. Temperatures and stresses are lower.

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Internal Baffle-to-Baffle, External Baffle-to-Baffle, and MRP-231/MRP-227Core Barrel-to-Former Bolts

Description/Figure: Figure 4-2 (MRP-227) MRP-23 1/MRP-227

Degradation/Effect: Cracking (IASCC, IE, MRP-231/MRP-227IC/ISR/Fatigue/Wear, Overload)

Section 2: Linked Primary Component

Name: Baffle-to-Former Bolts MRP-231/MRP-227

Degradation/Effect: Cracking (IASCC, IE, MRP-231/MRP-227IC/ISR/Fatigue/Wear, Overload)

How (Inspection Technique): UT MRP-231/MRP-227

When: no later than two refueling outages from the beginning MRP-231/MRP-227of the license renewal period

Inspection Data: 100% of accessible bolts MRP-231/MRP-227

Disposition/Evaluation: ASME Code MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

(InternalBB/External

BB/CB)

Irradiation dose: 100 dpa max. 124/<40/12 dpa MRP-229/MRP-231

max.

Temperature: 671F max. 642/602/679F MRP-229/MRP-231max.

Mechanical Load: High Low/High/High MRP-229/MRP-231

Material: SA Type 304 SA Type 304. MRP-229/MRP-231SS SS

Other:

Section 4: Other Considerations

Operating Experience: European and US failures in CW Type316 SS observed and German CB bolt failures with CW Type316Ti material

MRP-231

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Plant Specific Considerations: power histories

Additional Considerations: power uprates and baffle-fuelinteraction

Section 5: Final Expansion Recommendation

Recommendation: Confirmed rejectable indications in greaterthan or equal to 5% (or, 43) of the FB bolts, provided none ofthe rejected bolts are in former elevations 3, 4, and 5, or greaterthan 25% of the bolts on a single plate, shall trigger anevaluation of the internal baffle-to-baffle bolts for the purposeof determining whether to inspect or replace them. Thisevaluation may include external baffle-to-baffle bolts and corebarrel-to-former bolts for the purpose of determining whether toreplace them.

Basis: Redundancy; past operability analyses support rows 3-5;functionality analysis supports minimal expected failures; onlyinternal BB bolts are accessible and potentially inspectablewhile the external BB and CB bolts are inaccessible

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Locking Devices, Including Locking Welds, of External MRP-231/MRP-227Baffle-to-Baffle and Core Barrel-to-Former Bolts

Description/Figure: Figure 4-2 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (IASCC, IE) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: Locking Devices, Including Locking Welds, of Baffle- MRP-231/MRP-227to-Former and Internal Baffle-to-Baffle Bolts

Degradation/Effect: Cracking (IASCC, IE) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-231/MRP-227

When: 10-yr ISI MRP-231/MRP-227

Inspection Data: 100% of accessible locking devices to detect MRP-231/MRP-227damaged, grossly cracked, or missing locking devices or welds

Disposition/Evaluation: AS ME Code MRP-23 1/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

(External BB/CB)

Irradiation dose: Range of 60- 30/5 dpa max. MRP-229/MRP-231120 dpa max.

Temperature: 600F 590/590F MRP-229/MRP-231

Mechanical Load: High + weld High/High + MRP-229/MRP-231welds

Material: SA Type 304 SA Type 304 MRP-229/MRP-231SS SS

Other:

Section 4: Other Considerations

Operating Experience: CR-3 internal BB bolt locking deviceindications, German replacement CB locking device cracking

Plant Specific Considerations: power histories

Additional Considerations: power uprates and baffle-fuelinteraction

MRP-231

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data I Sources

Section 5: Final Expansion Recommendation

Recommendation: Confirmed rejectable indications in greaterthan or equal to 1% (or, 11) of the FB or internal BB boltlocking devices shall trigger an evaluation of the lockingdevices for the external baffle-to-baffle bolts and core barrel-to-former bolts for the purpose of determining continued operationor replacement.

Basis: Redundancy; concerns with loose parts and potential fueldamage; only the locking devices of the FB and internal BBbolts are accessible and inspectable while the locking devices ofthe external BB and CB bolts are inaccessible

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Lower Thermal Shield (LTS) Bolts (all plants) and MRP-231/MRP-227Lower Grid Shock Pad Bolts (at TMI-l only)

Description/Figure: Figure 4-7 (MRP-227) MR.P-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: UCB and LCB Bolts MRP-23 l/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

How (Inspection Technique): UT Exam MRP-231/MRP-227

When: Two outages or next 10-yr ISI (from 1/1/2006) / next NEI 03-08 /B&WOG10-yr ISI (from 1/ 1/2006) recommendation

Inspection Data: 100% of accessible bolts MRP-231/MRP-227

Disposition/Evaluation: Evaluate baseline results and decide MRP-231/MRP-227next steps

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: 604/557 F max. Similar MRP-229/MRP-231

Mechanical Load: 103/82 ksi Similar MRP-229/MRP-231(generic)

Material: Alloy A-286 Alloy A-286 MRP-229/MRP-231(some Alloy X- (some Alloy X-750) 750)

Other:

Section 4: Other Considerations

Operating Experience: A-286 failed in early 80's; X-750 failedin other plant designs

Plant Specific Considerations: material used, loading, and lastinspection performed

Additional Considerations: most not inspected in 15-20+ years

Section 5: Final Expansion Recommendation

B&WOG documentation

i

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ATTACHMENT 3,1

B&W.Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Recommendation: Confirmed rejectable= indications exceeding10% of either primary component (UCB or LCB bolts) shalltrigger UT inspection of 100% of the accessible LTS bolts andis required by completion of the next refueling outage

Basis: Redundancy; engineering judgment based on flawtolerance of the assembly; no safety consequences with UTSbolts (economic concerns)

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Flow Distributor (FD) Bolts MRP-231/MRP-227

Description/Figure: Figure 4-7 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

Section 2: Linked -Primary Component

Name: UCB and LCB Bolts MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

How (Inspection Technique): UT Exam MRP-231/MRP-227

When: Two outages or next 10-yr ISI (from 1/1/2006) / next NEI 03-08 /B&WOG10-yr ISI (from 1/l/2006) recommendation

Inspection Data: 100% of accessible bolts MRP-231/MRP-227

Disposition/Evaluation: Evaluate baseline results and decide MRP-23I/MRP-227next steps

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: 604/557 F max. 554F max. MRP-229/MRP-231

Mechanical Load: 103/82 ksi peak 76 ksi peak MRP-229/MRP-231

(generic) (generic)

Material: Alloy A-286 Alloy A-286 MRP-229/MRP-231

(some Alloy X- (some Alloy X-750) 750)

Other:

Section 4: Other Considerations

Operating Experience: A-286 failed in early 80's; X-750 failed B&WOG documentationin other plant designs

Plant Specific Considerations: material used, loading, and lastinspection performed

Additional Considerations: most not inspected in 15-20+ years

Section 5: Final Expansion Recommendation

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Recommendation: Confirmed rejectable indications exceeding10% of either primary component (UCB or LCB bolts) shalltrigger UT inspection of 100% of the accessible FD bolts and isrequired by completion of the next reftieling outage

Basis: Redundancy; engineering judgment based on flawtolerance of the assembly; no safety consequences with UTSbolts (economic concerns)

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Surveillance Specimen Holder Tube (SSHT) Bolts MRP-231/MRP-227

Description/Figure: Figure 4-7 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: UCB and LCB Bolts MRP-23 I/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

How (Inspection Technique): UT Exam MRP-231/MRP-227

When: Two outages or next 10-yr ISI (from 1/1/2006) / next NEI 03-08 /B&WOG10-yr ISI (from 1/1/2006) recommendation

Inspection Data: 100% of accessible bolts MRP-231/MRP-227

Disposition/Evaluation: Evaluate baseline results and decide MRP-231/MRP-227next steps

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: 604/557 F max. Similar MRP-229/MRP-231

Mechanical Load: 103/82 ksi Similar MRP-229/MRP-231(generic)

Material: Alloy A-286 Alloy A-286 MRP-229/MRP-231(some Alloy X- (some Alloy X-750) 750)

Other:

Section 4: Other Considerations

Operating Experience: A-286 failed in early 80's; X-750 failedin other plant designs

Plant Specific Considerations: material used, loading, and lastinspection performed

Additional Considerations: most not inspected in 15-20+ years,only used at CR-3 and DB, but remains of original design maystill exist'at other units

B&WOG documentation

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 5: Final Expansion Recommendation

Recommendation: Confirmed rejectable indications exceeding10% of either primary component (UCB or LCB bolts) shalltrigger UT inspection of 100% of the accessible SSHT bolts andis required by completion of the next refueling outage

Basis: Redundancy; engineering judgment based on flawtolerance of the assembly; no safety consequences with UTSbolts (economic concerns)

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Upper Thermal Shield (UTS) Bolts MRP-231/MRP-227

Description/Figure: Figure 4-7 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: UCB and LCB Bolts MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

How (Inspection Technique): UT Exam MRP-231/MRP-227

When: Two outages or next 10-yr ISI (from 1/1/2006) / next NEI 03-08 /B&WOG10-yr ISi (from 1/1/2006) recommendation

Inspection Data: 100% of accessible bolts MRP-231/MRP-227

Disposition/Evaluation: Evaluate baseline results and decide MRP-23 1/MRP-227next steps

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: 604/557 F max. Similar MRP-229/MRP-231

Mechanical Load: 103/82 ksi Similar MRP-229/MRP-231(generic)

Material: Alloy A-286 Alloy A-286 MRP-229/MRP-231

(some Alloy X- (some Alloy X-750) 750)

Other:

Section 4: Other Considerations

Operating Experience: A-286 failed in early 80's; X-750 failed B&WOG documentationin other plant designs

Plant Specific Considerations: material used, loading, and lastinspection performed

Additional Considerations: most not inspected in 15-20+ years

Section 5: Final Expansion Recommendation

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Recommendation: Confirmed rejectable indications exceeding10% of either primary component (UCB or LCB bolts) shalltrigger UT inspection of 100% of the accessible UTS bolts andis required by completion of the next refueling outage

Basis: Redundancy; engineering judgment based on flawtolerance of the assembly; no safety consequences with UTSbolts (economic concerns)

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Core Barrel Cylinder and Former Plates MRP-231/MRP-227

Description/Figure: Figure 4-2 (MRP-227) MRP-23 1/MRP-227

Degradation/Effect: Cracking (IE) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: Baffle Plates MRP-231/MRP-227

Degradation/Effect: Cracking (IE) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-23 1/MRP-227

When: 10-yr ISI MRP-231/MRP-227

Inspection Data: 100% of the surface within 1-inch around each MRP-231/MRP-227flow and bolt hole to detect grossly cracked areas

Disposition/Evaluation: ASME Code and MRP-210 MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

(Core Barrel /Former Plates)

Irradiation dose: 127 dpa max. 9/86 dpa max. MRP-229/MRP-231

Temperature: 600 F max. 577/665 F max. MRP-229/MRP-231

Mechanical Load: Generally low Generally low MRP-229/MRP-231or compressive or compressive

Material: Type 304 SS Type 304 SS MRP-229/MRP-231

Other:

Section 4: Other Considerations

Operating Experience: no indications to date

Plant Specific Considerations:

Additional Considerations: very large critical flaw sizes MRP-210required for brittle failure concerns

Section 5: Final Expansion Recommendation

Recommendation: Gross cracking (if confirmed) on baffleplates shall trigger VT-3 inspection of the accessible areas of

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

the former plates and it is required by completion of the nextrefueling outage. Gross cracking (if confirmed) of the formerplate shall trigger an evaluation of the inspectability of the corebarrel cylinder.

Basis: Flaws (i.e., Cracking) not detected by VT-3 examination MRP-210having a small COD are considered insignificant and is stillsafely below critical flaw size even if it extends outside the one-inch zone of the baffle plates; baffle plate and former platerelative motion initiates bolt prying action, which is mostprevalent in locations having insignificant ISR/IC (i.e., upperand lower former plate areas), and for cracks to grow, due to thesmall pressure difference across the baffle plates, there wouldhave to be such a prying action that would result in a largeCOD.

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: CRGT Spacer Castings MRP-231/MRP-227

Description/Figuie: Figure 4-5 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (TE) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: CSS Cast Outlet Nozzle MRP-23l/MRP-227

Degradation/Effect: Cracking (TE) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-231/MRP-227

When: 10-yr ISI MRP-23 l/MRP-227

Inspection Data: 100% of accessible surface to detect surface MRP-231/MRP-227irregularities (including damaged, grossly cracked, or fracturedmaterial)

Disposition/Evaluation: ASME Code MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: 600 F 600 F MRP-229/MRP-231

Mechanical Load: Low Low MRP-229/MRP-231

relatively highcompressivestress wherecontact occurs

Material: CF8 CF3M MRP-229/MRP-231

Other: Need CMTRs for allCASS

Section 4: Other Considerations

Operating Experience: none

Plant Specific Considerations:

Additional Considerations: CASS outlet nozzles only at ONS-3and DB

Section 5: Final Expansion Recommendation

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Recommendation: Confirmed evidence of damage, grosslycracked, or fractured nozzle material shall trigger VT-3examination of 100% of the accessible surfaces at the 4 screwlocations (at every 90') of the CRGT spacer castings and it isrequired by completion of the next refueling outage

Basis: Higher mechanical stress on the primary item; fabricationdefect unlikely; damage must be service-induced; grossdegradation consequences unacceptable

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: CRGT Spacer Castings MRP-231/MRP-227

Description/Figure: Figure 4-5 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (TE) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: IMI Guide Tube Spider MRP-231/MRP-227

Degradation/Effect: Cracking (TE, IE) MRP-23 1/MRP-227

How (Inspection Technique): VT-3 MRP-23 1/MRP-227

When: 1 0-yr IST MRP-231/MRP-227

Inspection Data: 100% of accessible surface to detect surface MRP-231/MRP-227irregularities (including damaged, grossly cracked, or fracturedmaterial)

Disposition/Evaluation: ASME Code MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: -1 dpa (not a factor) MRP-229/MRP-231

Temperature: -554 F - 600 F MRP-229/MRP-231

Mechanical Load: Residual stress Low MRP-229/MRP-231in HAZ

Material: CF8 CF3M MRP-229/MRP-231

Other: Potential Need CMTRs for allsynergistic CASSeffect of TE/IE

Section 4: Other Considerations

Operating Experience: none

Plant Specific Considerations:

Additional Considerations:

Section 5: Final Expansion Recommendation

Recommendation: Confirmed evidence of separation, grossdamage, or a missing spider arm for two or more locations shalltrigger VT-3 examination of 100% of the accessible surfaces at

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

the 4 screw locations (at every 90') of the CRGT spacercastings and it is required by completion of the next refuelingoutage

Basis: Looking for more than a single random fabricationdefect; higher residual stresses present on the primary item;consequences of arm failure are minimal

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: CRGT Spacer Castings MRP-231/MRP-227

Description/Figure: Figure 4-5 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (TE) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: CSS Vent Valve Disc MRP-231/MRP-227

Degradation/Effect: Cracking (TE) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-231/MRP-227

When: 10-yr IST MRP-231/MRP-227

Inspection Data: 100% of accessible surface to detect surface MRP-231/MRP-227irregularities (including damaged, grossly cracked, or fracturedmaterial)

Disposition/Evaluation: ASME Code MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: -600 F -600 F MRP-229/MRP-231

Mechanical Load: Low Low MRP-229/MRP-231

Material: CF8 CF3M MRP-229/MRP-231

Other: Need CMTRs for allCASS

Section 4: Other Considerations

Operating Experience: none

Plant Specific Considerations:

Additional Considerations:

Section 5: Final Expansion Recommendation

Recommendation: Confirmed evidence of damage, grosslycracked, or fractured material in two or more vent valve discsshall trigger VT-3 examination of 100% of the accessiblesurfaces at the 4 screw locations (at every 900) of the CRGTspacer castings and it is required by completion of the next

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

refueling outage

Basis: Looking for more than a single random fabricationdefect; consequences of damage are minimal during operation

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Alloy X-750 dowel-to-upper fuel assembly support pad MRP-231/MRP-227welds

Description/Figure: Figure 4-6 (MRP-227) MRP-23 1/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: Alloy X-750 dowel-to-guide block welds MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-231/MRP-227

When: No later than two refueling outages from the beginning MRP-231/MRP-227of the license renewal period

Inspection Data: 100% of the locking welds of the 24 dowel-to- MRP-231/MRP-227guide block welds to detect locking weld separation

Disposition/Evaluation: ASME Code relevant conditions MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: -554 F -600 F MRP-229/MRP-23I

Mechanical Load: Weld residual Weld residual MRP-229/MRP-231stress stress

Material: Alloy 82 Alloy 82 or 69 MRP-229/MRP-231

Other:

Section 4: Other Considerations

Operating Experience: N/A

Plant Specific Considerations: none

Additional Considerations:

Section 5: Final Expansion Recommendation

Recommendation: Confirmed evidence of separation, grossdamage, or a missing locking weld for two or more locationsshall trigger VT-3 examination of the expansion categorylocking welds and it is required by completion of the next

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

refueling outage

Basis: Looking for more than a single random fabricationdefect; potential for PWSCC of the weld (redundancy); lownominal loads to cause complete separation; nonexistent for theguide block bolt; expansion item dowels are captured withoutweld (for lower but not upper)

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Alloy X-750 dowel-to-lower fuel assembly support pad MRP-231/MRP-227welds

Description/Figure: Figure 4-6 (MRP-227) MRP-23 l/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: Alloy X-750 dowel-to-guide block welds MRP-231/MRP-227

Degradation/Effect: Cracking (SCC) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-231/MRP-227

When: No later than two refueling outages from the beginning MRP-231/MRP-227of the license renewal periodInspection Data: 100% of the locking welds of the 24 dowel-to- MRP-231/MRP-227guide block welds to detect locking weld separation

Disposition/Evaluation: ASME Code relevant conditions MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: (not a factor) (not a factor) MRP-229/MRP-231

Temperature: -554 F -554 F MRP-229/MRP-231

Mechanical Load: Weld residual Weld residual MRP-229/MRP-231stress stress

Material: Alloy 82 Alloy 82 or 69 MRP-229/MRP-231

Other:

Section 4: Other Considerations

Operating Experience: N/A

Plant Specific Considerations: none

Additional Considerations:

Section 5: Final Expansion Recommendation

Recommendation: Confirmed evidence of separation, grossdamage, or a missing locking weld for two or more locationsshall trigger VT-3 examination of the expansion categorylocking welds and it is required by completion of the next

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

refueling outage

Basis: Looking for more than a single random fabricationdefect; potential for PWSCC of the weld (redundancy); lownominal loads to cause complete separation; nonexistent for theguide block bolt; expansion item dowels are captured withoutweld (for lower support pads but not upper support pads)

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Section 1: Expansion Component Identification

Name: Lower Fuel Assembly Support Pad Items: Pad, Alloy X- MRP-231/MRP-227750 Dowel, Cap Screw, and their Locking Welds

Description/Figure: Figure 4-6 (MRP-227) MRP-231/MRP-227

Degradation/Effect: Cracking (IE) MRP-231/MRP-227

Section 2: Linked Primary Component

Name: IMI guide tube spiders and spider-to-lower grid rib MRP-231/MRP-227section welds

Degradation/Effect: Cracking (TE, IE) MRP-231/MRP-227

How (Inspection Technique): VT-3 MRP-231/MRP-227

When: no later than two refueling outages from the beginning MRP-231/MRP-227of the license renewal period

Inspection Data: none MRP-231/MRP-227

Disposition/Evaluation: ASME Code MRP-231/MRP-227

Section 3: Comparison of Key Factors

Primary Expansion

Irradiation dose: - I dpa - 2 dpa MRP-229/MRP-231

Temperature: -554 F -554 F MRP-229/MRP-231

Mechanical Load: Weld residual MRP-229/MRP-231stress

Material: CF8 and Type Type 304, Type MRP-229/MRP-231308L 308L, Alloy X-

750, Alloy 69

Other: Casting and Wrought andweld (TE/IE) Weld (IE)

Section 4: Other Considerations

Operating Experience: none

Plant Specific Considerations:

Additional Considerations:

Section 5: Final Expansion Recommendation

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ATTACHMENT 3

B&W Expansion Component

Expansion Criteria Determination Expert Panel Worksheets

Component Description and Data Sources

Recommendation: Confirmed evidence of separation, grossdamage, or a missing spider arn for two or more locations shalltrigger VT-3 examination of 100% of the accessible expansioncategory lower fuel assembly support pad items and it isrequired by completion of the next refueling outage

Basis: Looking for more than a single random fabricationdefect; primary item is subject to TE/IE and expansion itemonly to IE;