ML052560447

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B&W Owners Group Reactor Vessel Working Group Summary of the Plans of the B&Wog Reactor Vessel Integrity Program
ML052560447
Person / Time
Site: Davis Besse, Oconee, Arkansas Nuclear, Surry, Turkey Point, Crystal River, Ginna, Crane  Constellation icon.png
Issue date: 08/17/2005
From:
AREVA, B & W Owners Group, Framatome ANP
To:
Office of Nuclear Reactor Regulation
References
Download: ML052560447 (59)
v • d • e


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I B&W OWNERS GROUP REA CTOR VESSEL WORKING GROUP Summary of the Plans of the B&WOG Reactor Vessel Integrity Program August 17, 2005 Rockville, Maryland The MAW OwnersOrou]

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1 Agenda Introduction/Meeting Objective

  • Dan Spond - RVWG Chairman/Entergy 3

Use of BAW-2308 by RVWG members

  • Brian Hall - Framatome-ANP 8

Capsule withdrawal schedule changes in BAW-1543

  • Brian Hall - Framatome-ANP 17 Submittal of MIRVP Capsule DB1-LG2
  • Brian Hall - Framatome-ANP 35 Disposition of specimens/capsules in storage
  • Brian Hall - Framatome-ANP 49 B&WOG Transition into the WOG
  • Dan Spond - RVWG Chairman/Entergy 54 L Oners Group 2

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I August 17 B&WOG-NRC Meeting

> Introductions

> Purpose

  • Update NRC on B&WOG RVWG activities & plans
  • Several years since last NRC update
  • B&WOG folded into WOG in 2006
  • Solicit feedback

> Membership

  • 7 B&W designed units/5 utilities
  • FP&L (Turkey Point 3 & 4) is not participating in '05
  • Constellation (Ginna) has not participated since '96 Owners Gou 3

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f B&WOG Reactor Vessel Working Group (RVWG) l E

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E il Utility Plants NSSS Vendor Entergy Operations, Inc.

ANO 1 B&W FirstEnergy Nuclear Operating Co.

Davis Besse B&W Duke Energy Company Oconee 1,2,3 B&W Exelon Corporation TMI-1 B&W Progress Energy Florida Crystal River-3 B&W Dominion Energy Surry 1, 2 W

I Nuclear Management Company Point Beach 1, 2 W

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Major Accomplishments and Background ma;JI-e1" The fl&W L Owners Gro 5

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  • Surveillance capsule holders X B&WOG RVIP was formed damaged

/ Capsule irradiation in host RVs (Crystal River 3 & Davis Besse) 1976

  • Radiation damage susceptibility

/ Six OG capsules containing fracture confirmed; Upper shelf limit predicted toughness specimens added to to be violated in as few as 2 years surveillance program (Regulatory Guide 1.99)

/ Operational limitations avoided 1980's

  • Pressurized thermal shock concerns v Worked with industry committees to (10CFR50.61) obtain favorable changes; all members good for 40 years

/ ASME Code participation guided 1988

  • Application of elastic-plastic fracture successful code implementation (App. K) mechanics methods approved by v Methodologies using fracture specimens NRC.

available from surveillance program resolved the low upper shelf issue (J-R) 1988

  • NRC concerns with surveillance and

/ Provided the necessary material RV material inconsistencies (Generic traceability and documentation Letter 92-01)

  • Imminent shutdown of member RV X Shutdown due to PTS concerns avoided; 1993 due to PTS issues MIRVP surveillance data and the "Master Curve" method used 2002

/ "Master Curve" data and code case used to lower Initial RTNDT

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REACTOR VESSEL INTEGRITY PROGRAM I

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10CFR50 Appendix G 10CFR5O Appendix G 10CFR50 Appendix HI 10CFR50..61 Complete Owners Group Resolution Imminent 7

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Use of BAW=2308 by B&WOG RVWG Members The e&w Owners Group 8

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TOPICAL REPOR T BA W-2308 "INITIAL RTNDT OF LINDE 80 WELD MATERIALS

> Lowers initial RTNDT or Linde 80 Welds

  • Master Curve testing per ASTM El 921

> Draft SER received on June 2, 2005

> Comments submitted to NRC on June 29, 2005

> Final SER dated August 4, 2005

> Exemption required

  • 1 OCFR50.61 (PTS) and

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Dominion Energy

> Removal of Flux Suppression Inserts and use of Integral Fuel Burnable Absorbers at Surry 1 - Spring 06

  • Hf flux suppression nearing end of life
  • Removal will increase power and reduce cost
  • Surry I very close to PTS limit with suppression

> Revise fluence projections for 60 years

  • in progress

> Submit license exemption to 10CFR50.61 - late 05

> Start-up planned for May 06

> Use of Integral Fuel Burnable Absorber at Surry Unit 2 -

Winter 06

  • Start-up planned for November 06

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Nuclear Management Company

> Support Point Beach 1 & 2 license renewal with possible consideration of

  • Removal of Flux Suppression Inserts
  • Uprate

> Fluence projections for 60 years currently exceed PTS Screen under current rule

> Submit license exemption for

> 10CFR50.61 exemption approval expected within one year after submittal The fgOlAW S

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Exelon Near PTS limit at 40 years at current power

>Support TMI 1 license renewal

>Exemption request will be part of license renewal submittal

>License renewal submittal - mid 07 Evaluating uprate Owners Groupj 1:2

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> Oconee units have license renewal to 60 years

> Exemption request would support

  • P-T curve improvement
  • 24 month fuel cycle

> Possibly 2008 ners Group 13 lMM

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> ANO 1 has license renewal to 60 years

> Exemption request would support

  • P-T curve improvement

> No immediate need him.~

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First Energy Nuclear Operating

> Davis-Besse

> Exemption request would likely support

  • P-T curve improvement

> Tentatively planned for mid 06

> License renewal submittal - December 08

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> Crystal River 3

> Exemption request would likely support

  • P-T curve improvement

> No immediate need

> License renewal submittal - Early 09 OwnersGroup 1

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Capsule Withdrawal Schedule Changes in MIRVP (BAW-1 543 Rev. 4 Supplement 6)

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Purpose of MIRVP Changes

> Ensure all the critical Linde 80 welds in all the RVWG plants have data or will have data at:

  • 40 years
  • 60 years
  • 80 years

> Following is the basis behind the planned changes to withdrawal schedule henfrs lrou 18

F r (7P-F" Linde 80 Weld Matrix

> 11x17 Handout

> Separated by 8 Linde 80 Heats in the MIRVP

> RV welds are listed under each heat

  • BOLD are PTS significant
  • 40, 60, 80, and 2xEOL fluences are indicated
  • Test Data:
  • C = Charpy curve
  • T=To
  • U = Upper shelf
  • sa = specimens available in storage
  • Capsule ID = capsule stored or still being irradiated Owners__GroupJ 19 E

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Projected EFPY 95% Capacity Point Beach

  • Uprate with Hf factor removal of Surry 1
  • Flux suppression in place Turkey Point
  • Removal of Hf Davis Besse
  • MVP uprate Fluence indicated on handout Operating Projected EFPY at 40, 60 License and 80 Years of Operation Facility Expiration 40 60 l

80 ANO-l May-34 30.9 49.9 68.9 CR-3 Dec-16 29.9 48.9 67.9 DB Apr-17 28.2 47.2 66.2 0-1 Feb-33 31.4 50.4 69.4 0-2 Oct-33 32.0 51.0 70.0 0-3 Jul-34 32.3 51.3 70.3 TMI-I Apr-14 29.1 48.1 67.1 PB-I Oct-10 31.8 50.8 69.8 PB-2 Jan-13 33.7 52.7 71.7 S-1 May-32 29.6 48.6 67.6 S-2 Jan-33 30.1 49.1 68.1 TP-3 Jul-32 30.0 48.0 67.0 TP-4 Apr-33 30.0 48.0 67.0 OwnersGrouil 20

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V Heat 299L44

> Limiting in TMI-1, S-1, and 0-2

> Data available for 80 years, except for TMI-1

> Capsules Al, L2 and A4 contain heat

> Untested specimens can provide data past 80 years

> After TMI-1 license renewal, test specimens MA~w2 Ower GruI Emus=01 I

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Heat 406L44

> Contained in ANO-1 and 0-2

> Data available for 80 years

> No further testing required

> No need to test PB2-P or PB2-N L1~wneusf Gru SEZ=M 22

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Heat 61782

> PIT limiting in PB-1

> MC data from DB1-LG2 near 50 years

  • Tested baseline To data in 2003
  • Will be reported in DB1-LG2 in 2005
  • Analyze in BAW-2308 Supplement in 2006

> Sufficient data for 80 years 01 rs Group RN 23

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Heat 71249

> Limiting in: PB-1, TP-3, and TP-4

  • Data available for CR-3 and 0-1 for 80+ years

> 40 years

  • PB-1, TP-3 & 4 covered by capsule TP3-X

> 60 years

  • PB-1, TP-3 & 4 covered by capsule PB2 Suppl.

> 80 years

  • TP4-X and A2 for PB-I, TP-3 & 4

> A2 will have ~2.8eI9n/cm2 at withdrawal in 2011

  • Lags RV ID; recommend longer irradiation to -6e19n/cm2

> Heat is sufficiently covered Ownes 24 Ate

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Expected Irradiation for Heat 71249 7

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  • Verify B&WOG upper-shelf model at high fluence
  • Capsule A4 contains heat MIEIALM a&w Owners Oro upj
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> Limiting in 0-3 and PB-2 Data available for 0-3 at 80 years and beyond Capsules Al and L2 lag RV ID fluence A4 will provide PB-2 80 year data in 2036 PB2 supplemental capsule

  • will provide PB-2 60 year data in 2016 jwners Group]

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4 L2 (DB) 2005 m___w i OwnersGroup 2010 2015 2020 2025 2030 201 Year 28

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Heat 72445

Will not be limiting in any plant

> Has high fluence in S-1

> PB1-P withdrawn and has 50 year fluence

> PB1-N is being irradiated

> A2 withdrawal in 2030 or later would provide 80 year data Thu 2&W OwnersGr MJ ?Awl Y--If

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> Limiting in DB

> With testing of TE1 -C, data available for ~80 years

> Retain TE1-E for possible future irradiation ners Group 30 3S

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> Are scheduled for withdrawal from DB at EOC 17

(~2011)

  • Al is scheduled for testing
  • L2 is slated for disposal (redundant materials)

> At current flux these capsules will never reach desired fluence for W designed units

> Proposed plan:

  • Keep in DB as a standby/Back-up capsule
  • Might be valuable long term to evaluate
  • Irradiation damage saturation
  • Effect of long irradiation time O

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> Model developed

  • 106 tests
  • Up to 0.845e1 9 n/cm2

> Since then 23 additional tests validate model to 1.86e19 n/cm2

> Model extrapolations to ~5e19 n/cm2

> Will be verified to high fluence from specimens irradiated in A2 and A4 Owne~rs_

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F-Proposed Changes to BAW-1543 Rev. 4, Suppl. 5

> Test TE1-C (WF-1 82)

> Retain TEI-E and CR3-A

> Keep Al and L2 in DB as standby/fluence monitors

> Irradiate A2 and A4 to ~6e19n/cm2

  • Beyond CR-3 current EOL (40 years)
  • Submittal of BAW-1 543 Rev. 4, Suppl. 6 planned for late 05 prior to CR-3 license renewal
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  • Several B&W plants have data covering more than 80 years of operation

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> Final capsule from original 6 SUPCAPs

> Tested in 03-04

> Benefits:

  • Contains ANO-1 PTS significant weld
  • Contains Point Beach Unit 1 P-T limiting weld
  • Irradiated To data for heat 61782
  • Higher fluence upper-shelf data

> Fluence

  • 1.10 to 1.65 x 1019 n/cm 2
  • Point Beach-1 at 40+ years
  • Slightly higher than ANO-1 at q70 years Ow r

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> Testing conducted

  • Charpy
  • Master Curve
  • Upper Shelf Toughness
  • Tensile

> Materials

  • WF-112 (heat 406L44)
  • Limiting weld in ANO-1
  • SA-1135 (heat 61782)
  • P-T limiting in PB-I
  • Master Curve data needed for BAW-2308 Supplement
  • WF-70 (heat 72105)
  • Not tested; Data not needed TThIU LOwners Group 37

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DB1-LG2 Results 406L44 120 110 100 90 t0 80 U0 WF-193 AN01 RVSP WF-193 RS1 RVSP o

WF-193 AN01 RVSP A

WF-193 RS1 RVSP WF-112 01 RVSP o

WF-112 01 RVSP WF-193 PB2 RVSP o

WF-193 PB2 RVSP

-Power Law Fit to Yield Power Law Fit to Ultimate Typical tension behavior 60 50 0.0 0.5 1.0 1.5 2.0 2.5 3.0 Fluence x1019, nlcm2 (E>1 MeV) 120,

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WF-112 01 RVSP WF-193 PB2 RVSP o WF-193 PB2 RVSP

-Power Law Fit to Yield Power Law Fit to Ultimate 70 60 bu *.

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Weld Average Number of To E1921-02 Fluence Specimen Uncensored (OF)

Validity x 1019 Type Specimens/

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Required WF-1 12 (Oconee-1 1.408 Various 9/7 55 Valid RVSP Weld)

Wire Heat 406L44 CTs SA-1 135 (Oconee-2 1.368 Various 9/6 66 Valid nozzle drop-out)

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> WF-112(406L44) 1.379 x 1019 n/cm2 (E > I MeV)

  • 47 ft-lbs

> SA-1 135 (61782) 1.635 x 1019 n/cm2 (E > I MeV)

  • 53 ft-lbs
  • 41% decrease

> RG 1.99 Rev 2 Prediction

  • 45% decrease
  • 30% decrease

> RG 1.99 Rev 2 Prediction

  • 46% decrease The flaW n

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DB1-LG2 Capsule Summary

> Tensile

  • Typical irradiation induced hardening

> Upper-Shelf CVN

  • Less decrease than RG 1.99 Rev. 2 Prediction
  • At or below 50 ft-lb limit

> Upper-Shelf Toughness

  • B&WOG model conservatively bounds measured data

> CVN 30 ft-lb shift

  • WF-112 matches RG 1.99 Rev 2 prediction
  • SA-1135 showed less shift than prediction

> Master Curve To

  • Shift is less than RG 1.99 Rev 2 prediction
  • Shift agrees with average CVN shift 47
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> Framatome-ANP preparation and internal review

  • Complete (BAW-2486)

> RVWG member review

  • Ongoing

> Submit to NRC for information only

  • Not required per MIRVP
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Capsules Stored at Hot Cell

> 8 Unopened B&W Plant Specific Capsules

  • TE1-C
  • TEI-E
  • CR3-A
  • OC2-F
  • OC3-E
  • OC3-C
  • TM12-A
  • TM11-D ersGroup 50 B

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Capsules Stored at Hot Cell

> Retain

  • TE1-E (Contains DB limiting material)
  • CR3-A (Contains CR-3 second limiting material)

> Dispose of Remaining 5 Capsules

  • No limiting or near limiting materials
  • Disposal is approved by NRC eoupj 51

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Irradiated Specimens Stored at Hot Cell Tested and Untested Specimens

> Specimen Types

  • Tensile
  • Charpy
  • Fracture Toughness (0.394TCT, 0.5TCT, 0.936TDCT)

> Source

  • W plant capsules - 16 (Surry, PB, and TP)
  • Operating B&W plant capsules - 31 (ANO-1, CR3, DB, Oconee, TMI)
  • Shut-down plant capsules - 9 (Zion & Rancho Seco)
  • MIRVP Capsules - 10 (32 Linde 80 CVN sets; 6 untested sets)

> -280 material conditions (CVN data sets)

  • -110 base metal (transverse, longitudinal, forging, plate)
  • -45 correlation monitor

> Fluence

  • Up to 3.8 x 1019 n/cm2 (E>IMeV)
  • Most <2 x 1019 n/cm2 (E>1 MeV) r..

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' Owners Group 52

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> Specimen Ownership

  • Plant specific capsules-owned by each utility
  • MIRVP capsules-owned by B&WOG

> No further testing of stored specimens planned

  • PTS Issue resolved
  • BAW-2308 SER issued
  • PTS Rule change

> Options

  • Continued storage
  • Disposal
  • All
  • Material that is not projected to be useful K'

53

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Reactor Vessel Integrity Program Technical Issues

> RV Integrity Issues

  • 1 OCFR50.61
  • Pressure-Temperature Limits
  • 1 OCFR50 Appendix G
  • Surveillance Capsules

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Supplement to BAW-2308

> Purpose

  • Close open items in SER
  • Heat 61782 data
  • Update loading rate evaluation per E1921-05

> Submit to NRC in mid 2006

> WOG Materials Subcommittee Approved

> Moves to WOG General Session in October WA I 1aw rs Gro uj 56

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PTS Rule making, RG 1.99 Rev. 3, Risk Inform App. G, Industry, and Code Support

> Collaborative effort between AREVA and Westinghouse

  • Codes and Standards Activities
  • ASME Code Section Xl
  • ASTM E08 Fatigue And Fracture
  • E1921 El0 Behavior and Use of Nuclear Structural Materials
  • Industry participation

- Risk Inform Appendix G

> WOG Materials Subcommittee Approved

> Moves to WOG General Session in October The^ fla57 Owners GroupJ

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MIRVP Master Integrated Reactor Vessel Surveillance Program

> Produce data at 60 and 80 years for PB-1, PB-2 and S-1

  • Irradiation of A2 and A4 capsules to -- '30
  • Store & Maintain Capsule Removal Tooling

> Meet requirements of 10CFR50 App. H

  • ANO-1, CR-3, DB, 0-1, 0-2, 0-3, and TMI-1
  • Maintain MIRVP: BAW-1543
  • Maintain Linde 80 Database
  • Store irradiated specimens
  • Thermal Aging Temperature Evaluation: '05-'07

> WOG Materials Subcommittee Approved

> Moves to WOG General Session in October 58

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Projects Proposed to the WOG Materials Subcommittee Project Participation 06 07

'08 Supplement to B&W + TP +

X X

BAW-2308 Surry + PB PTS Rule making, X

X RG 1.99 Rev. 3, All PWRs x

Risk Inform App. G, X

X Industry, and Code x

x Support MIRVP B&W + PB X

X X-

___EOL

>Essential elements of RVIP will continue under WOG O w r

r EM3 59

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