ML20133B552

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Adjusted Reference Temperatures for 21 & 32 EFPY for ANO-1
ML20133B552
Person / Time
Site: Arkansas Nuclear 
Issue date: 07/08/1996
From: Campbell C, Devan M
FRAMATOME
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32-1245917, 32-1245917-00, NUDOCS 9701060010
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ANO Calculation 96-E-0057-02 / FTI Calculation 32-1245917-00

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9701060010 961217 PDR ADOCK 05000313 P

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ARKANSAS NUCLEAR ONE Page 1 FORM TITLE:

FORM NO.

REV.

CALCULATION COVER SHEET 5010.015-ATT-2 1

This Document contains 1 Page.

i l Calc. No.:

96-E-0057 02 Rev. No.:

0 l

Calc.

Title:

Unit: 1 Category:

_Q ART FOR 21 AND 32 EFPY FOR ANO-1 System (s): RCS Calc. Type: NS,,

Component No(s):

Topic (s): PTSI R1 Pit Area: Bldg.

NA Elev.

Room:

Wall Coorcinates:

Config. Checklist (per 5010.004) completed? (Y or N)

Y Document Comment / Resolution Form completed? (Y or N)

Y Abstract (Included Purpose /Results):

The 21 and 32 Effective Full Powtr Year (EFPY) projected adjusted reference teiaperature (ART) values at the 1/4 thickness (1/4T) and 3/4 thickness (3/4T) locations of the ANO-1 reactor vessel. The li:niting 1/4T and 3/4T ART values at the end of 21 EFPY are 161 F and 124 F, respectively for weld WF 18 and 179 F and 136 F respectively for weld metal WF-18 at 32 EFPY. The data will be used to calculate new pressure-temperature operating limits for ANO-1.

6 Pages Revised and/or Added:

ADDED PAGES 1 THROUGH 38 AND ATTACHMENT I PAGES A 1 THROUGH A-2.

Purpose of Revision:

Initialissue

~.

Initiating Documents Resulting Documents Key Design Input Documents ANO-1 Tech Spec 3.1.2.7 REVISED ANO-1 TECH SPEC 3.1.2.7; SEE REFERENCE SECTION OF 96-E-0057-01 CALCULATION Verification Method: Design Review Alternate Calculation O Qualification Testing O Amends Calc (s):

NA

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~Epersedes Calc (s):

NA Computer Software Used:

NA By:

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/ 7/8/96 Rvw'd:

Robert W. Clark

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(Print Name)

(Initials)

(Date)

(Print Name)

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l' PROPRIETARY 20697P-3 (12/95)

CALCULATION

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SHEET (CSS)

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DOCUMENT IDENTIFIER 32 1245917-00 TITLE Adjusted Reference Temperatures for 21 and 32 EFPY for ANO-1 f

4 PREPARED BY:

REVIEWED aY:

l NAME M.J.DeVan NAME C A. Campbell 3

SIGNATURE slONATURE TITLE Engineerill DATE TITLE Engineer 11 DATE 7 /p/

g l

cost CENTER 41020 REF. PAGE(s) 36-38 TM STATEMENT: REVIEWER INDEPENDENCE j

'This document including the information contained herein and any associated drawings,is the i

It contains confidential information and may not be rep uced or

'of Framatome Technologies.

J

' copied in whole or in rt nor may it be fumished to others without the expressed written permission of f

Frematome Technol les nor may any use be made ofitthat is ormay beinjurious to Frematome j

Technologies. This ocument and any associated drawings and any copies that may have been made l

[must be retumed upon request.

j PURPOSE AND

SUMMARY

OF RESULTS:

6 eryears jected adjusted reference te rature values atthe ickness (bEFPY)

The 21 and 32 effective full

/4T)I tions of the Arkansas Nuclear e Unit 1 reactorvesselwere 1/4-thickness (1/4T) and 3/4 calculated per Regulatory Guide 1.99, Revision 2. The limitin 1/4Tand 3/4T adjusted reference temperature values at the end of 21 EFPY are 161F and 124F re for weld metal WF-18. The limiting 1/4Tand 3/4T adjusted reference temperature values at the end of 2 EFP are 179F and 136F respectively for weld metal WF-18. The data will be used to calculate new pressure-temperature operating limits for Arkansas Nuclear One Unit 1.

i l

DOCUMENT 96-E-0057-02, Rev. 0 NUMBER PAGE 1 OF 38 i

THE'F6EO' WING 'CCidPUTER CODES HAVE BEEN UsED IN ISIS DOCUMENT:

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l THIS DOCUMENT CONTAINs ass s sE IED CODENERslONIREV hTHAT CODENERSION/REV t

WORK 8

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1 FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 i

RECORD OF REVISIONS l

i REVISION DESCRIPTION l

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DOCUMENT 96-E OO57 02, Rev. O j

NUMBER PAGE 2 OF 38 I

i i

PREPARER:

M.-J.DeVan DATE:

6l05/96 REWEWER:

C. A. Campbell DATE:

6/05/96 PAGE 2

l FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 l

l TABLE OF CONTENTS TITLE PAGE l

\\

1.0 I N TRO D U CTIO N..........................................

5 2.0 S U M MARY O F R ESU LTS...................................

5 I

3.6 A S S U M PTI O N S..........................................

5 4.0 REACTOR VESSEL FLUENCE...............................

5 4.1 Reactor Vessel Inside Surface Fluence.....................

5 4.1.1 21 Effective Full Power Years.......................

6. 5 4.1.2 32 Effective Full Power Years........................ 5 4.2 Attenuation Through Vessel Wall.........................

8 5.0 REACTOR VESSEL FRACTURE TOUGHNESS...................

9 9

5.1 initial RTuoy.........................................

10 5.2 A RTuo r............................................

5.2.1 Chemistry Factor................................ 10 5.2.2 Fluence Factor.........

11 12 5.2.3 ART,or Calculation...............................

14 5.3 M a rg in............................................

5.4 Calculation of Adjusted Reference Temperature............... 16 DOCUMENT 96-E-0057-02, Rev. O NUMBER PAGE 3 OF 38 I

l l

PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A.. Campbell DATE:

6105/96 PAGE 3

=

FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32 1245917 00 J

TABLE OF CONTENTS (cont.)

4 TITLE PAGE i

6.0 FRACTURE TOUGHNESS DATA WHERE SURVEILLANCE DATA IS AVAI LAB LE.............................................

17 i

4 i

6.1 Calculation of Chemistry Factor Using Surveillance Data........

18 6.1.1 Base Metal Plate Heat Number C5114-1...............

18 i

6.1.2 Weld Wire 621T44 (WF-182-1)...................... 20 6.1.3 Weld Wire 406L44 (WF-112)........................ 22 6.2 Adjusted Reference Temperature Calculated Using Surveillance Data 26 6.2.1 I nitial RTwor.................................... 26 j

6.2.2 ARTuor Calculation............................... ' 27 j

6.2.3 Margin

....................................... 28 l

6.2.4 Calculation of Adjusted Reference Temperature.......... 29 i

i 4

)

APPENDIX A Credibility of Surveillance Data...................... 30 3

i APPENDIX B References.................................... 36 4

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DOCUMENT 96-E-0057 02, Rev. 0 NUMBER PAGE 4 OF 38 j

1 PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 4

FRAMATOME TECHNOLOGIES FTI PROPRIETARY 32-1245917-00

1.0 INTRODUCTION

The purpose of this analysis is to determine the Entergy Operations, Inc.

Arkansas Nuclear One Unit 1 (ANO-1) reactor vessel fracture toughness data for 21 and 32 effective full power yests (EFPY). This information is to be used in the preparation of pressure-temperature operating limits curves applicable to 21 and 32 EFPY.

2.0

SUMMARY

OF RESULTS The adjusted reference temperature (RTuor) values applicable through 21 and 32 EFPY for the ANO-1 reactor vessel beltline materials are listed in Tables 1 and 2 respectively. These values were calculated per the guidelines outlinad in Regulatory Guide 1.99, Revision 2.' The limiting RTwor values at 21 EFPY are 16t*F at the %T wall location and 124*F at the %T wall location, and the l

limiting RTwor values at 32 EFPY are 179'F at the %T well location and 136'F l

at the %T wall location i

3.0 ASSUMPTIONS l

No major assumptions are contained in this report.

4.0 REACTOR VESSEL FLUENCE 4.1 Reactor Vessel inside Surface Fluence 4.1.1 21 Effective Full Power Years The extrapolated 21 EFPY inside surface fluences for the ANO-1 l

reactor vessel beltline materials are listed in Table 3.8 4.1.2 32 Effective Full Power Years l

The extrapolated 32 EFPY inside surface fluences for the ANO-1 reactor vessel beltline materials are listed in Table 4.2 1

DOCUMENT 96-E 005742, Rev. O NUMBER PAGE 5 OF 38 h

I i

PREPARER:

M.J.DeVan DATE:

6l05/96 REVIEWER:

C. A.. Campbell DATE:

6105/96 PAGE5

t.

FRAMATONE TECHNOLOGIES FTI PROPRIETARY 32-1245917-00 i

i i

Table 1. Data for Preparation of Pressure-Temperature Limit Curves

[

for Arkansas NucIcar One Unit 1 - Applicable Through 21 EFPY i

i I

Oumumus ART, F AftT. F teussene Ommenpuun Camomeaume 21 EfPT Fm summu' as 21 Efry temenu at 21 EFPY f

simummer womune tems Mass k

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3MT emeere stayan teemann tense '

tw. y syy.

est ftf.m Fester gamesmo Lemumen se Lemmuun Lasemme Lacaemn Laemmen Lammuun Lacaemn

,ts m.,G e.1

- - tt fessade see Faerg AV90131 53 ease ASeeCL2 eSS e7f

+3 as S 47E+9e 3 3E+te 1 m +1e 14 e

M S3 et FS ngpur Somme rtmas CS1382 cst M SA493 Gr et e t?

s'A

.te 123 78 emete S m ete 13E+10 se se M

N 113 et lgpar Dee Pause CStt44 CStl42 SA4ss er. et e tt e.a

-10 tWe e m ete a m +te tim +te sa M

M tes 74 k

Lamar tsue rtues CStabt CStakt SA43b er el

$ 17 eM

.te 132.78 SSE*14 SetE*10 13tE +1e W

Se M

M 112 e2 Laser seus pleno CSe ta-t cst:4-t SA4seGr et e.ts esa e

tese S eeE*se sete.se tite te 7s se 34 M

tte se f

ese to US Ca sumas (test)

w. tea.1 eatfee ASAAssesse e 24 ee3 177 eS S47E+te 3 3eE +1e 12EE*18 124 et SS SS 153 1to US tare tusselemen teemi tur-te eft 7s2 ASAA w ee cae o ss 4

19a 38 4 27E+1e 2 87E+te e r i ?'

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n Us to LS Cet veuse(10ent vuF.112 4eoL44 ASAAeues se e 31 e SS 47 teS 7 5seE+te 3 StE+10 12 4+10 148 W

98 SS tee 121 l

LS targyt veuselemen tesEl vuF.te oft 702 ASA4sueses cas G SS 4

182 25 4 2E+1e 2 SE+1e 9 *.ahE*t7 SS et se Se 158 11246 l

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stupeammy Ommen 1 es. fisumuun 2. Panamn 21 Lesur enma rtsee CS194-9 cst 14-1 SA433 Gr et e tt 8 92 d

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[]- Controlkng values of the adjusted RT,,m.

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DOCUMENT 96-E4057-02, Rev. O f

NUMBER l

PAGE 6 OF 38 t

' j PREPARER:

M.J.DeVan DATE:

6105/96 l

REMEWER:

C. A. Campbell DATE:

6905/96 PAGE6

[

FRAMATOME TECHNOLOGIES FTi PROPRIETARY 32-1245917-00 l

+i I

Table 2. Data for Preparation of Pressure-Temperature Limit Curves for Arkansas Nuclear One Unit 1 - Applicable Through 32 EFPY l

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i CIeusmeses aftT. F MIT. F l

Genauemi Ommesgeen Compamenus 32 EFFT Flasuta. summ' s M EFPV thugne a32EFPV Itemener wommes teen,

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emannestsynn - m i naura emanner Type met unit stT,

Famuur ensamme tsumman Lemumen Lesumen Lammmen Lameman Lauemmi Lasapen Lamamos i

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flapsulury Ones 1 es. Itenemen 2. Pommun 11 femaste See Fugue Ayes 131 535350 A 950 Q 2 9SI S 78

+3 30 FSEE+18 4 30E+10 t.73Ee18 18 11 84 83 e3 TT upper Shm3 PIme C$13EL2 cst 3k2 SA433 Gr. 59 8 17 9 56

-18 122 75 8 FtE+10 5 2SE+IS 19tE*te 101 et M

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. Le tamos vumas sassi teems w-te ettver Asmasise es 8 38 ees 4

setas sesE+te SGEE+tt 1.33E+18 tte F2 GB GB 173 135 j

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[]- Controlling values of the adjusted RT..

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DOCUMENT 96-E-OO57-02, Rev. O f

NUMBER PAGE 7 OF 38 i

f

  • =

PREP.'tRER:

M.J.DeVan DATE:

6905/96 l

REWEWER:

C. A. Campbell DATE:

6905/96 PAGE 7 l

I

3 FRAMATOME l

TECHNOLOGIES FTl PROPRIETARY 32-1245917 00 a

1 4.2 Attenuation Through Vessel Wall Per Regulatory Guide 1.99, Revision 2, the neutron fluence at the %T and %T locations in the vessel, f (x 10" n/cm, E > 1 MeV), is 2

l determined as follows:

/=fu (e42*")

(1)

I i

where fu (10" n/cm, E > 1 MeV) is the calculated value of the neutron 2

fluence at the inner wetted surface of the vessel, and x (in inches) is the j

depth into the vessel wall measured from the vessel inner surface. The ANO-1 reactor vessel thickness is reported to be 8.44 inches per BAW-1543, Revision 4.* The %T and %T fluence values at 21 and 32 EFPY are presented in Table 3 and 4 respectively.

6 Table 3.

Arkansso Nuclear One Unit 1 Reactor Vessel Beltline Materiale j

Fluence Values at 21 EFPY i

8 21 EFPY Fluence n/cm U"$.

Inside T/4 3/4T Beltline Materials ident.

Surface (x = 2.11 in.)

(x = 6.33 in.)

i Nozzle Belt Forging AYN 131 5.467E+18 3.295E+18 1.197E+18 Upper Shell Plate C5120 2 6.076E+18 3.662E+18 1.330E+18 Upper Shell Plate C5114-2 6.076E+18 3.662E+18 1.330E+18 Lower Shell Plate C51201 5.991 E+18 3.611E+18 1.311E+18 Lower Shell Plate C5114-1 5.991E+18 3.611E+18 1.311E+18 NB to US Cire. Weld (100%)

WF-1821 5.467E+18 3.295E+18 1.197E+18 US Longit. Weld (Both 100%)

WF-18 4.271 E+18 2.574E+18 9.349E+17 US to LS Cire. Wold (100%)

WF-112 5.825E+18 3.511E+18 1.275E+18 LS Longit. Weld (Both 100%)

WF-18 4.250E+18 2.561E+18 9.303E+17 DOCUMENT 96-E-0057-02, Rev. O NUMBER PAGE 8 OF 38 PREPARER:

M.J.DeVan DATE:

6I05/96 REWEWER:

C. A. Campbell DATE:

6/05/96 PAGE 8

FRAMATOME 1

. TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 Table 4. Arkansas Nuclear one Unit 1 Reactor Vessel Beltline Materiale Fluence Values at 32 EFPY 8

32 EFPY Fluence n/cm I

3/4T Matl.

Inside T/4 Beltline Materials ident.

Surface (x = 2.11 in.)

(x = 8.33 in.)

I Nozzle Belt Forging AYN 131 7.902E+18 4.762EW 1.730E+18 Upper Shell Plate C5120-2 8.710E+18 5.249E+18 1.907E+18 Upper Shell Plate C5114-2 8.710E+18 5.249E+18 1.907E+18 Lower Shell Plate C5120-1 8.582E+18 5.172E+18 1.878E+18 l

Lower Shell Plate C5114-1 8.582E+18 5.172E+18 1.878E+18 l

l NB to US Cire. Weld (100%)

WF-182-1 7.902E+18 4.762E+18 1.730E+18 US Longit. Wold (Both 100%)

WF-18' 6.089E+18 3.858E+18 1.328E+18 l

US to LS Cire. Weld (100%)

WF-112 8.346E+18 5.030E+18 1.827E+18 LS Lo' git. Wold (Both 100%)

WF-18 6.057E+18 3.850E+18 1.326E+18 n

l l

6 l

5.0 REACTOR VESSEL FRACTURE TOUGHNESS i

The following information is required for determinedon of the adjusted reference temperature outlined in Regulatory Guide 1.99, Revision 2.

5.1 Initial RT, y The initial RTuoy is the reference temperature for the unirradiated base metal vessel beltline material as defined in Paragraph NB-2331 of Section ll1 of the ASME Boiler and Pressure Vessel Code.' If measured values of initial RTwor for the material in question are not available, generic mean values for that class of material may be used if there are sufficient test results to establish a mean and standard deviation for the class.

Table 5 lists the initial RTuor values for the ANO-1 reactor vessel beltline materials and their applicable sources.

DOCUMENT 96-E OO57-02, Rev. O NUMBER PAGE 9 OF 38 I

i i

PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A.. Campbell DATE:

6/05/96 PAGE 9

~

FRAMATOME l.

TECHNOLOGIES FTl PROPRIETARY 32o1245917-00 ii j

Table 5. Arkansas Nuclear One Unit 1 Initisi RT,,oy Valuee l

for Reactor Vessel Beltline Materiale 1

1 Initial l

Matt.

RT, ;

Beltline Materials Ident.

F Reference Source 8

Nozzle Belt Forging AYN 131

+3 Estimated value per BAW-10046 i

Upper Shot Plate C5120 2

-10 Measured value por BAW-1820' Upper Shell Plate C5114-2

-10 Measured value per BAW-1820 Lower SheH Plate C5120-1

-10 Measured value per BAW-1820 l

Lower Shell Plate C5114-1 0

Measured value per BAW 1820 4

i NB to US Cire. Wold (100%)

WF-182-1

-27 Measured value per BAW-2245. Rev.1' 8

US and LS Loigit. Wolds (100%)

WF-18

-5 Genetic value per BAW-1803, Rev.1 l

US to LS Cire. Wold (100%)

WF-112

-27 Measured value per BAW-2245, Rev.1 5.2 ART,,or l

s l

ART,,or is the mean value of the adjustment in reference temperature caused by irradiation and should be calculated as follows:

i l

ARTuor = (CF) x (/F)

(2) i l

where CF = Chemistry Factor i

ff = fluence factor 5.2.1 Chemistry Factor l

The chemistry factor (CF) is a function of the material's copper i

and nickel content. The CF is determined from Table 1 (for weld i

metals) and Table 2 (for base metals) in Regulatory Guide 1.99, l

Revision 2. Linear interpolation is permitted. When determining j

the CF, the " weight percent copper" and " weight percent nickel" are best estimate values for the material, which will normally be l

the mean of the measured values for the material.

The copper and nickel contents for the beltline base metal j

materials are reported in BAW-1820, and the copper and nickel contents for the beltline weld metals are reported in BAW-2121P.'

i l

DOCUMENT 96-E OO57 02, Rev. O NUMBER PAGE 10 OF 38

]

l PREPARER:

M.J.DeVan DATE:

6/C l

REVIEWER:

C. A. Campbell DATE:

6/Ob/sts PAGE 10

k FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917 00 1

Using Tables 1 and 2 in Regulatory Guide 1.99, Revision 2, the i

CF for the ANO-1 reactor vessel beltline region materials are j

listed in Table 6.

Table 6. Regulatory Guide 1.99, Revision 2, Chemistry Factors for i

Arkansas Nuclear One Unit 1 Reactor Vessel Beltline Materials i

Matl.

Cu Ni Chemistry j

Beltline Materials ident.

wt%

wt%

Factor i

Nozzle Belt Forging AYN 131 0.03 0.70 20.00 i

Upper Shell Plate C5120-2 0.17 0.55 122.75 Upper Shell Plate C5114-2 0.15 0.52 105.60 l

i Lower Shell Plate C5120-1 0.17 0.55 122.75 I

l Lower Shell Plate C5114-1 0.15 0.52 105.60 NB to US Cire. Weld (100%)

WF-182-1 0.24 0.63 177.95 i

US and LS Longit. Welds (100%)

.WF-18 0.20 0.55 152.25 4

US to LS Cire. Weld (100%)

WF-112 0.31 0.59 196.70 6

l i

j 5.2.2 Fluence Factor i

)

Per Regulatory Guide 1.99, Revision 2, the fluence factor (ff) for i

the %T and %T locations is determined as follows:

ff. f(o.as - o.io nos 4 (3) i Tables 7 and 8 list the fluence factors for the %T and %T l

locations for the ANO-1 reactor vessel beltline materials at 21 and 32 EFPY respectively.

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DOCUMENT 96-E 0057-02, Rev. O NUMBER f

PAGE 11 OF 38 i

i PREPARER:

M.J.DeVan DATE:

6105/96 l

REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 11 i

4 m

i FRAMATOME l-TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 Table 7. Fluence Factors for the %T and %T locations of the Arkansas i

Nuclear One Unit 1 Reactor Vessel Beltline Region at 21 EFPY j

T/4 Location 3/4T Location

Fluence, Fluence, Matt.

n/cm' Fluence n/cm' Fluence j

Beltline Materials ident.

(x 10")

Factor (x 10*)

Factor t

j Nozzle Belt Forging AYN 131 0.3295 0.6346 0.1197 0.4538

{

Upper Shell Plate C5120-2 0.3662 0.7224 0.1330 0.4763 Upper Shell Plate C5114-2 0.3662 0.7224 0.1330 -

0.4763 i

Lower Shell Plate C5120-1 0.3611 0.7187 0.1311 0.4733 Lower Shell Plate C5114-1 0.3611 0.7187 0.1311 0.4733

)

NB to US Cire. Wold (100%)

WF 182-1 0.3295 0.6946 0.1197 0.4538 I

US Longit. Wold (Both 100%)

WF-18 0.2574 0.6313 0.0935 0.4035 j

US to LS Cire. Wold (100%)

WF-i12 0.3511 0.7113 0.1275 0.4672 i

LS Longit. Wold (Both 100%)

WF-18 0.2561 0.6301 0.0930 0.4026 i

I I

Table 8 Fluence Factors for the %T and %T locations of the Arkansas l

Nuclear One Unit 1 Reactor Vessel Beltline Region at 32 EFPY 1

T/4 Location 3/4T Location Matt.

Fluence, Fluence
Fluence, Fluence i

Beltline Materials ident.

n/cm Factor n/cm' Factor 2

(x10")

(x10")

Nozzle Belt Forging AYN 131 0.4782 0.7932 0.1730

.0.5353 Upper Shell Plate C5120-2 0.5249 0.8200 0.1907 0.5580 d

Upper Shell Plate C5114-2 0.5249 0.8200 0.1907 0.5580 i

Lower Shell Plate C5120-1 0.5172 0.8159 0.1878 0.5545 t

Lower Shell Plate C5114-1 0.5172 0.8159 0.1878 0.5545 NB to US Cire. Wold (100%)

WF-182-1 0.4762 0.7932 0.1730 0.5353 i

US Longit. Wold (Both 100%)

WF-18 0.3658 0.7221 0.1328 0.4761 i

US to LS Cire. Wold (100%)

WF-112 0.5030 0.8082 0.1827 0.5480 LS Longit. Wald (Both 100%)

VW-18 0.3650 0.7216 0.1326 0.4757 l

5.2.3 ART r Calculation uo The ART values for the ANO-1 reactor vessel beltline materials wor are calculated by multiplying the chemistry factors and fluence DOCUMENT 96-E-OO57-02, Rev. O NUMBER PAGE 12 OF 38 PREPARER:

M.J.DeVan DATE:

610 REWEWER:

C. A. Campbell DATE:

610

i FRAMATOME i

TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 factors. The 21 and 32 EFPY ARTwor values for the ANO-1 i

reactor vessel beltline rnatorials are presented in Tables 9 and 10

[

respectively.

i l

l Table 9.

ART,,y Values for the Arkansas Nuclear One Unit 1 Reactor Vessel Beltline Materials at 21 EFPY i

Matt.

T/4 Location 3/4T Location l

Beltline Materials loent.

1-CF N

ART,

CF M

ART,

i Nozzle Belt Forging AYN 131 20 0.6946 14 20 0.4538 9

l Upper Shou Plate C5120-2 122.75 0.7224 89 122.75 0.4763 58 Upper Shen Plate C5114-2 105.6 0.7224 76 105.6 0.4763 50 Lower Shou Plate C5120-1 122.75 0.7187 88 122.75 0.4733 58 i

}

Lower Shou Plate C5114-1 105.6 0.7187 76 105.6 0.4733 50 NB to US Cire. Wold (100%)

WF-182-1 177.95 0.6946 124 177.95 0.4538 81 3

(

US Longit. Wold (Both 100%)

WF-18 152.25 0.6313 96 152.25 0.4035 61

}

US to LS Cire. Wold (100%)

WF-112 196.7 0.7113 140 196.7 0.4672 92 l

LS Longit. Wold (Both 100%)

WF-18 152.25 0.6301 96 152.25 0.4026 61 I

i

)

Table 10.

ART,,, Values for the Arkansas Nuclear One Unit 1 j

Reactor Vessel Beltline Materials at 32 EFPY Matt.

Tid Locaten 3/4T Location Beltline Materials ident.

CF N

ART,

CF N

ART,

Nozzle Belt Forging AYN 131 20 0.7932 16 20 0.5353 11 Upper Shen Plate C5120-2 122.75 0.8200 101 122.75 0.5580 69 i

Upper Shell Plate C5114-2 105.6 0.8200 87 105.6 0.5580 59 l

Lower Shell Plate C51201 122.75 0.8159 100 122.75 0.5545 68 Lower Shou Plate C5114-1 105.6 0.8159 86 105.6 0.5545 59 NB to US Cire. Wold (100%)

WF-182-1 177.95 0.7932 141 177.95 0.5353 95 US Longit. Wald (Both 100%)

WF-18 152.25 0.7221 110 152.25 0.4761 73 US to LS Cire. Wold (100%)

WF-112 196.7 0.8082 159 196.7 0.5480 108 LS Longit. Wold (Both 100%)

WF-18 152.25 0.7216 110 152.25 0.4757 72 l

DOCUMENT 96-E-0057-02, Rev. O NUMBER PAGE 13 OF 38 PREPARER:

M.J.DeVan BATE:

6105/96 REMEWER:

C. A. Campbell DATE:

6/05/96 PAGE 13

i FRAMATOME i

TECHNOLOGIES FTl PROPRIETARY 32-1245917 00 I

i 5.3 Margin i

i The " margin" is the quantity that is added to obtain conservative, upper-bound values of the adjusted reference temperature for the calculations j

required by 10CFR50, Appendix G. The margin is determined by the following expression:

l 4

2

,2 (4)

Marykt = 2 $ a where a, = standard deviation for the initial RTwor a = standard deviation for ARTuor j

a i

If a measured value of initial RTwor for the material in question is available, a, is to be estimated from the precision of the test method. If generic mean values are used, a, is the standard deviation obtained 6 j

from the set of data used to establish the mean.

i i

The standard deviation for ART,or, a., is 28'F for welds and 17*F for '

base metals, except that a, need not exceed 0.50 times the mean value j

of ART or.

i i

Tables 11 and 12 list the margin values calculated for the ANO-1 reactor vessel beltline materials through 21 and 32 EFPY respechvely, i

l i

1 i

DOCUMENT 96-E4057-02, Rev. O NUMBER PAGE 14 OF 38 PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 14

FRAMATOME l*

TECHNOLOGIES Fil PROPRIETARY 32 1246917-00

.l Table 11. Margin Values for the Arkansas Nuclear One Unit 1 Reactor Vessel Beltline Materiale Through 21 EFPY i

j Matt.

ART,/2 Margin 1

Beltline Materials ident.

a, a.

j T/4 3/4T T/4 3/4T Nozzle Belt Forging AYN 131 31 17 7'

5 64 63 Upper Shen Plate C5120 2 0

17 45 29 34 34 i

Upper Shou Plate C5114-2 0

17 38 25 34 34 j

Lower Shed Plate C5120-1 0

17 44 29 34 34 i

Lower Shen Plate C51141 0

17 38 25 34 34 i

NB to US Circ. Wold (100%)

WF-182-1 0

28 62 41 56 56 i

US Longit. Wold (Both 100%)

WF-18 19.7 28 48 31 68 68 l

US to LS Cire. Wold (100%)

WF-112 0

28 70 46 56 56 LS Longit. Weld'(Both 100%)

WF-18 19.7 28 48 31 68 68 i

i l

Table 12. Margin Values for the Arkansas Nuclear One Unit 1 l

Reactor Vessel Beltline Materials Through 32 EFPY i

1 1

Matl.

ART

/2 Marge Beltline Matenals ident.

a, a.

Nozzle Belt Forging AYN 131 31 17 8

6 64 63 Upper Shen Plate C5120-2 0

17 51 35 34 34 Upper Shen Plate C5114-2 0

17 44 30 34 34 Lower Shou Plate C5120-1 0

17 50 34 34 34 Lower Shed Plate C5114-1 0

17 43 30 34 34 NB to US Cire. Weld (100%)

WF-182-1 0

28 71 48 56 56 US Longit. Weld (Both 100%)

WF-18 19.7 28 55 37 68 68 US to LS Cire. Weld (100%)

WF-112 0

28 80 54 56 56 LS Longit. Wold (Both 100%)

WF-18 19.7 28 55 36 68 68 DOCUMENT 96-E 0057 02, Rev. O NUMBER PAGE 15 OF 38 PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6105/96 PAGE 15

FRAMATOME TECHNOLOGIES FTI PROPRIETARY 32-1245917-00 f

5.4 Calculation of Adjusted Reference Temperature The adjusted reference temperature (ART) is given by the following expression:

I ART = Initial RTw7 + ARTuor + Margin (5) i

)

Tables 13 and 14 list the %T and %T ART values calculated for the ANO-1 reactor vessel beltline materials through 21 and 32 EFPY respectively.

5 Table 13. %T and %T ART Values for the Arkansas Nuclear One Unit 1 Reactor Vessel Beltline Materials through 21 EFPY I

Adjusted Reference i

Mad.

Temperature, F Beltline Materials ident.

j Nozzle Belt Forging AYN 131 81 75 j

Upper Shell Plate C5120-2 113 82 Upper Shell Plate C5114 2 100 74 1

Lower Shell Plate C5120-1 112 82 3

4 Lower Shell Plate C5114-1 110 84 j

NB to US Cire. Weld (100%)

WF-182-1 153 110 j

US Longit. Weld (Both 100%)

WF-18 159 124 US to LS Cire. Wold (100%)

WF-112 169 121 j

LS Longit. Weld (Both 100%)

WF-18 159 124 i

4 4

5 i

DOCUMENT 96-E405742, Rev. O NUMBER PAGE 16 OF 38,

PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6105/96 PAGE 10

,(.-

i FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 Table 14. %T and %T ART Values for the Arkansas Nuclear One Unit 1 l

Reactor Vessel Beltline Materials through 32 EFPY 1

i Adjusted Reference Matt.

Temperature, F l

Beltline Materials ident.

Nozzle Belt Forging AYN 131 83 77 Upper Shell Plate C5120-2 125 93 Upper Shell Plate C5114-2 111 83 Lower Shell Plate C5120-1 124 92 Lower Shell Plate C5114-1 120 93 NB to US Cire. Weld (100%)

WF-1821 170 124 US Longit. Weld (Both 100%)

WF-18 173 136 US to LS Circ. Wold (100%)

WF-112 188 137 LS Longit. Wald (Both 100%)

WF-18 173 135 6

6.0 FRACTURE TOUGHNESS DATA WHERE SURVEILLANCE DATA IS AVAILABLE Results from plant specific surveillance programs may be integrated into the

)

adjusted reference temperature estimate if the surveillance data have been i

deemed credible as judged by the following criteria:

1.

Materials in the capsules should be those judged most likely to be controlling with regard to radiation embnttlement according to the recommendations of Regulatory Guide 1.99, Revision 2.

2.

Scatter in the plots of Charpy energy versus temperature for the irradiated and unitradiated conditions should be small enough to permit the determination of the 30 ft-Ib temperature unambiguously.

3.

When there are two or more sets of surveillance data from one reactor, the scatter of ART, values about a best-fit line drawn as described in Regulatory Guide 1.99, Revision 2, Position 2.1 normally should be less than 28'F for welds and 17'F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values.

DOCUMENT 96-E405742, Rev. O NUMBER PAGE 17 OF 38 PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 17

FRAMATOME l-TECHNOLOGIES FTl PROPRIETARY 32-1245917 00 l

)

l 4.

The irradiation temperature of the Charpy specimens in the capsule j

should match the vessel wall temperature at the cladding / base metal interface within $25'F.

l 5.

The surveillance data for the correlation monitor materialin the capsule should fall within the scatter band of the data base for that rr._ terial.

l Appendix A provides the evaluation of the Regulatory Guide 1.99, Revision 2, i

credibility criteria for the available surveillance data for ANO-1.

When two or more credible surveillance data sets are available, these data may be used to determine the adjusted reference temperature of the reactor i

vessel beltline materials as follows:

j First, if there is clear evidence that the copper or nickel content of the

{

surveillance weld differs from that of the reactor vessel weld, the measured i

values of ART., should be adjusted by multiplying the values by the ratio of the chemistry factor for the reactor vessel weld to that for the surveillance i

weld. Second, using the ARTer and its corresponding fluence, the chemistrl l

' factor may be calculated by multiplying each adjusted ART., by the corresponding fluence factor, summing the products, and dividing by the sum t

j of the squares of the fluence factors:

(6) l E (/f8) i The ANO-1 plant specific reactor vessel surveillance program (RVSP) provides data for predicting the reference temperature shift for the base metal plate heat number C5114-1. In addition, the Master Integrated Reactor Vessel Surveillance Program (MIRVP) described in BAW-1543, Revision 4, provides surveillance data for weld metals WF-182-1 and WF-112 on predicting the 4

i reference temperature shift.

i j

6.1 Calculation of Chemistry Factor Using Surveillance Data i

j 6.1.1. Base Metal Plate Heat Number C5114-1 1

Table 15 lists the available surveillance data for the base metal a

j plate heat number C5114-1 and the reference sources.

j j

DOCUMENT 96-E4057 02, Rev. O NUMBER PAGE 18 OF 38 j

PREPARER:

M.J.DeVan DATE:

6:uurau REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 18

FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917 00 Table 15. Reactor Vessel Surveillance Material Data for Base Metal Plate Heat Number C5114-1

Fluence, ARTuor, Capsule n/cm" F

Reference l

l AN1-E 7.27E+17 30 (LT)

BAW-2075, Rev.1" 10 (TL) l AN1-A 1.03E+19 48 (LT)

BAW-2075, Rev.1 66 (TL)

AN1-C 1.46E+19 64 (LT)

BAW-2075, Rev.1 38 (TL) i l

Using the above information and Equation 0, the chemistry factqr for base metal heat number C5114-1 is calculated to be 51.2*F (see Table 16).

l Table 15. Calculadon of Chemistry Factor for Base Metal Plate l

Heat Number C5114-1 Using Surveillance Data l

l l

Fluence Capsule ARTuay, F Factor (ff)*

ARTuay,F

  • ff ff' AN1-E 30 (LT) 0.356 10.7 0.127 l

10 (TL) 0.356 3.6 0.127 AN1-A 48 (LT) 1.008 48.4 1.016 66 (TL) 1.008 66.5 1.016 l

AN1-C 64 (LT) 1.105 70.7 1.221 38 (TL) 1.105 42.0 1.221 SUM 241.9 4.728 CF = I (ART,

  • ff) / I (ff') = 51.2

- Calculated using Equation 3.

DOCUMENT 96-E4057 02, Rev. O NUMBER PAGE 19 OF 38 I

PREPARER:

M.J.DeVan DATE:

6105/96 l

REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 19

,e--

n,w.------

--,r-

,e---

,,w

~. - _

4 1

FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 3

i.

6.1.2 Wold Wire 821T44 (WF-182-1) i Table 17 lists the available surveillance data for the weld wire 821T44 (WF-182-1) and the reference sources.

i Table 17. Reactor Vessel Surveillance Material Data j

for Weld Wire 821T44 (WF-182-1) l

Fluence, ARTer, l

Capsule n/cm F

Reference 8

f TE1-F 2.29E+18 127 BAW-2125

l TE1-B 5.92E+18 125 BAW-2125 l

TE1-A 1.29E+19 175 BAW-2125 i

TE1-D 9.62E+18 150 BAW-2125 6

TMl2-C 1.68E+18 117 BAW-2190

l TMl2-E 1.74E+18 99 BAW-2190 i

1 The reported copper content for the above two surveillance welds are 0.21 wt% for the Davis-Besse data" and 0.28 wt% for the l

Three Mile Island-2 data." while the best estimate copper content j

for this weld wire is 0.24 wt%.' Therefore, the measured ARTer values are adjusted by multiplying these values by the ratio of the l

chemistr/ factor (as determined in accordance with Regulatory l

Guide 1.99, Revision 2, Position 1.1) for the reactor vessel to that j

of the surveillance weld. The data used to determine the ratio of the weld wire 821T44 best estimate chemistry factor to that of the surveillance weld chemistry factor are presented in Table 18.

1 i

DOCUMENT 96-E-0057-02, Rev. O a

i NUMBER j

j PAGE 20 OF 38 j

i k

PREPARER:

M.J.DeVan DATE:

6105/96 REWEWER:

C. A. Campbell DATE:

6/05/96 PAGE 20

s FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 f

Table 18. Ratio of Weld Wire 821T44 Best Estimate Mean Chemistry Factor to That of the Surveillance Wold Chemistry Factor i

4 Chemistry j

Factor from Ratio Weld Wire RG 1.99/R2 (Vessel to

]

Heat No.

Weld Identification Cu Ni Table 1 Sury. Data) i 821T44 WF-182 Davis-Besse 0.21 0.63 169.0 1.053 WF-182 TMI-2 0.28 0.63 191.7 0.929 Weld Wire Best Estimate 0.24 0.63 178.0 The adjusted measured ARTuor values are presented in Table 19,'

j and these values are used to determine the chemistry factor in accordance with Regulatory Guide 1.99, Revision 2, Position 2.1.

l l

Table 19. Adjustment of Measured Surveillance Data Using i,

Ratio Procedure of Regulatory Guide 1.99, Revision 2 I

Ratio Adjusted Weld Wire Heat No.

Measured CF Ratio Measured (Weld Identification)

Capsule ARTuor, F (See Table 18)

ARTwor, F 821T44 TE1-F 127.0 1.053 133.7 (WF-182-1)

TE1-B 125.0 1.053 131.8 TE1-A 175.0 1.053 184.3 TE1-D 150.0 1.053 158.0 TMl2-C 117.0 0.929 108.7 TMl2-E 99.0 0.929 92.0 Using the above information and Equation 6, the chemistry factor for weld wire 821T44 (WF-182-1) is calculated to be 172.7'F (see Table 20).

DOCUMENT 96-E4057-02, Rev. O NUMBER PAGE 21 OF 38 PREPARER:

M.J.DeVan DATE:

6l05/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 21

v,- -

l-j FRAMATOME 1

TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 i

i Table 20. Calculation of Chemistry Factor for Wold Wire 821T44 (WF-182-1) Using Surveillance Data i

i Ratio y

Adjusted Measured Fluence i

Capsule ART, 1, F Factor (ff)*

ARTuor,F

  • ff ff' l

TE1-F 133.7 0.602 80.5 0.362 i

TE1-B 131.6 0.853 112.3 0.728 i

TE1-A 184.3 1.071 197.4 1.147 TE1-D 158.0 0.989 156.3 0.978 TMl2-C 108.7 0.529 57.5 0.280 TMl2-E 92.0 0.537 49.4 0.288 SUM 653.4 3.783 CF = Z (ART,., ? ff) / Z (ff') = 172.7 6

- Calculated using Equation 3.

6.1.3 Wold Wire 406L44 (WF-112)

Table 21 lists the available surveillance data for the weld wire 406L44 (WF-112) and the reference sources.

i i

DOCUMENT 96-E4057-02, Rev. O NUMBER PAGE 22 OF 38 PREPARER:

M.J.DeVan DATE:

6l05/96 REVIEWER:

C. A. Campbell DATE:

6/05/98 PAGE 22

j.,-

i FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 5

l Table 21. Reactor Vessel Surveillance Material Data for Wold Wire 406L44 (WF-112) 1

Fluence, ARTuor, j

Capsule n/cm F

Reference 2

AN1-E 7.27E+17 105 BAW-2075, Rev.1 l

AN1-A 1.03E+19 151 BAW-2075, Rev.1 AN1-C 1.46E+19 185 BAW-2075, Rev.1 OC1-E 1.50E+18 78 BAW-2050

OC1-A 8.95E+18 191 BAW-2050 OC1-C 9.86E+18 185 BAW-2050 i

RS1-B 3.99E+18 99 BAW-2074" RS1-D 6.60E+18 152 BAW-2074 i

RS1-F 1.42E+19 166 BAW-2074 DB1-LG1 8.21E+18 204 BAW-1920P" i

PB2-V 6.50E+18

165 BAW-2140" PB2-T 8.61 E+18

150 BAW-2140 6

i '

, PS2-S 3.10E+19

231 BAW-2140 PB2-R 2.20E+19'8 235 BAW-2140 I

j-The reported copper content for the above surveillance welds are j

0.28 wt% for the ANO-1 data," 0.32 wt% for the Oconee-1 and B&WOG data," 0.31 wt% for the Rancho Seco-1 data,' and 0.25 wt% for the Point Beach-2 data, while the best estimate copper content for this weld wire is 0.31 wt%.' Therefore, the measured ARTuor values are adjusted by multiplying these values by the i

ratio of the chemistry factor (as determined in accordance with j

Regulatory Guide 1.99, Revision 2, Position 1.1) for the reactor i

vessel to that of the surveillance weld. The data used to i

determine'the ratio of the weld wire 406L44 best est! mate i

chemistry factor to that of the surveillance weld chemistry factor j

are presented in Table 22.

i I

l DOCUMENT 96-E4057 02, Rev. O NUMBER j

PAGE 23 OF 38 j

1 i

PREPARER:

M.J.DeVan DATE:

6105/96 l

REVIEWER:

C. A. Campbell DATE:

6105/96 FAGE 23 i

?

l

..l FRAMATOME l

TECHNOLOGIES FTl PROPRIETARY 32-1245917 00

\\

)

Table 22. Ratio of Weld Wire 406L44 Best Estimate Mean Chemistry l

Factor to That of the Surveillance Wold Chemistry Factor

]

i i

Chemistry Factor from Ratio Weld Wire RG 1.99/R2 (Vessel to Heat No.

Weld Identification Cu Ni Table 1 Surv. Data) 4 406L44 WF-193 - ANO-1 0.28 0.59 185.7 1.059 j

i WF-112 - Oconee-1 0.32 0.59 200.7 0.980 1

l WF-193 - Rancho Seco-1 0.31 0.59 196.7 1.000 f

4 l

WF-112 - B&WOG 0.32 0.59 200.7 0 980 WF 193 - Point Beach-2 0.25 0.59 174.6 1.127 i

j Weld Wire Best Estimate 0.31 0.59 196.7 6

i The adjusted measured ART, values are presented in Table 23, l

and these values are used to determine the chemistry factor in i

accordance with Regulatory Guide 1.99, Revision 2, Position 2.1.

f l

1

!~

i s

1 l

f i

i 4

i l

I I

l l

}

j DOCUMENT 96-E-OO57 02, Rev. O j

NUMBER 1

PAGE 24 OF 38 i

l l

PREPARER:

M.J.DeVan DATE:

6105/96 i

REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 24 4

f FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 l

l Table 23. Adjustment of Measured Surveillance Data Using i

Ratio Procedure of Regulatory Guide 1.99, Revision 2 i,

1 Ratio Adjusted j

Weld Wire Heat No.

Measured CF Ratio Measured l

(Weld Identification)

Capsule ARTuor, F (See Table 22)

ARTuor, F i

406L44 AN1-E 105.0 1.059 111.2 (WF-112, WF-193)

AN1-A 151.0 1.059 159.9 AN1-C 185.0 1.059 195.9 l

OC1-E 78.0 0.980 78.4 OC1-A 191.0 0.980 187.2 i

OC1-C 185.0 0.980 181.3 RS1-B 99.0 1.000 99.0 RS1-D 152.0 1.000 152.0 RS1-F 166.0 1.000 166.0 D1 204.0 0.980 199.9 6

PB2-V 165.0 1.127 186.0 PB2-T 150.0 1.127 169.1 PB2-R 235.0 1.127 264.8 PB2-S 231.0 1.127 260.3 Using the above information and Equation 6, the chemistry factor for weld wire 406L44 (WF-112) is calculated to be 185.6*F (see Tab!e 24).

DOCUMENT 96-E OO57-02, Rev. O j

NUMBER i

PAGE 25 OF 38 PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 25

FRAWATOnfE TECHNOLOGIES FTl PROPRIETARY 32-1246917-00 Table 24. Calculation of Chemistry Factor for Weld Wire 406L44 (WF-112) Using Surveillance Data Ratio Adjusted Measured Fluence Capsule ARTuor, F Factor (ff)*

ARTuor,F

  • ff ff' AN1-E 111.2 0.356 39.6 0.127 AN1-A 159.9 1.008 161.2 1.016 AN1-C 195.9 1.105 216.5 1.221 OC1 E 76.4 0.503 38.4 0.253 OC1-A 187.2 0.969 181.4 0.939 OC1-C 181.3 0.996 180.6 0.992 RS1-B 99.0 0.745 73.8 0.555 RS1-D 152.0 0.884 134.4 0.781 RS1-F 166.0 1.097 182.1 1.203-DB1-LG1 199.9 0.945-188.9 0.893 PB2-V 186.0 0.879 163.5 0.773 PB2-T 169.1 0.958 162.0 0.918 l

PB2-R 264.8 1.214 321.5 1.473 PB2-S 260.3 1.299 338.1 1.686 i

SUM 2382.0 12.831 CF = Z (ART,

  • ff) / E (ff') = 186.6 l

- Calculated using Equation 3.

6.2 Adjusted Reference Temperature Calculated Using Surveillance Data l

6.2.1 Initial RTuor l

The initial RTuor for base metal plate heat number C5114-1 and weld metals WF-182-1 and WF-112 are the same values specified in Section 5.1:

DOJUMENT 96-E-0057-02, Rev. O

{

PAGE 26 OF 38 l

t PREPARER:

M.J.DeVan DATE:

6105/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 26

FRAMATOME TECHNOLOGIES Fil PROPRIETARY 32-1245917-00 Beltline Materials initial RTuor, F i

Lower Shell Plate 0

~

NB to US Circ. Weld (WF-182-1)

-27 i

US to LS Cire. Weld (WF-112)

-27 i

6.2.2 ARTuor Calculation The %T and %T ARTwor values for the beltline region materials l

where surveillance data are available are calculated in l

accordance with Equation 2 using the chemistry factors j

determined in Section 6.1 and the respective fluence factors i

determined in Section 5.2.2. The 21 and 32 EFPY %T and %T i

ARTwor values for the ANO-1 reactor vessel beltline region materials where surveillance data are available are presented id Tables 25 and 26 respectively.

i l

Table 25. ARTuor Values at 21 EFPY for the ANO-1 Reactor Vessel l

Beltline Materials With Surveillance Data Available 1

Matt.

T/4 Location 3/4T Location Bettiine Materials ident.

CF N

ART.

CF W

ART,

Lower Shell Plate C5114-1 51.2 0.7187 37 51.2 0.4733 24 NB to US Cire. Wald (100%)

WF-182-1 172.7 0.6946 120 172.7 0.4536 78 US to LS Cire Wold (100%)

WF-112 185.6 0.7113 132 185.6 0.4672 87 I

l I

J j

DOCUMENT 96-E405742, Rev. 0 NUMBER f

PAGE 27 OF 38 s.

4 PREPARER:

M.J.DeVan DATE:

6105/96 i

REVIEWER:

C. A. Campbell DATE:

6105/96 PAGE 27

\\

\\

l

- ~ -

~.

^

i FRAMATOME TECHNOLOGIES Fil PROPRIETARY 32-1245917-00 Table 26. ART,or Values at 32 EFPY for the ANO-1 Reactor Vessel Beltline Materiala With Surveillance Data Available Matl.

T/4 Location 3/4T Location Beltline Materials ident.

Lower Shell Plate C5114-1 51.2 0.8159 42 51.2 0.5545 28 NB to US Cire. Wold (100%)

WF-182-1 172.7 0.7932 137 172.7 0.5353 92 US to LS Cire. Wald (100%)

WF-112 185.6 0.8082 150 185.8 0.5480 102 i

6.2.3 Margin l

Applying the credibility criteria defined in Regulatory Guide 1.99, Revision 2, the scatter of the measured ARTuor values about a best-fit line drawn as described in Position 2.1 is greater than i

17'F for the lower shell base metal plate and 28'F for weld wireb 821T44 and 406L44 (see Appendix A). For these materials a two

(

standard deviation (a ) from the generic data base (i.e., 34*F for base metals and 56*F for weld metals) were used as the margin l

term to ensure that all the surveillance data are bounded.

To calculate the margin values for beltline materials with surveillance data available, Equation 4 is used. Table 27 lists the j

margin values calculated for the ANO-1 vessel beltline materials

{

where surveillance data available.

i Table 27. Margin Values for the ANO-1 Reactor Vessel

}

Beltline Materials With Surveillance Data Available l

l Matl.

Margin Beltline Materials ident.

a, a.

g g

i Lower Shell Plate C5114-1 0

17 34 34 l

I NB to US Cire. Weld (100%)

WF-182-1 0

28 56 56 j

US to LS Cire. Weld (100%)

WF-112 0

28 56 56 i

h DOCUMENT 96-E 0057 02, Rev. O

{

NUMBER j

PAGE 28 OF 38 1

l PREPARER:

M.J.DeVan DATE:

Blbomo

]

REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 28 e

m..

-._m

j.'. '

FRAnfATOME i*

TECHNOLOGIES Fil PROPRIETARY 32-1245917 00 2

i i

i 6.2.4 Calculation of Adjusted Reference Temperature i

The ART is calculated using Equation 5. Tables 28 and 29 list b

the %T and %T ART values through 21 and 32 EFPY respectively calculated for the ANO-1 reactor vessel beltline materials where surveillance data available.

I

\\

Table 28. %T and %T ART Values Through 21 EFPY for the ANO-1 Reactor i

Vessel Beltline Materials With Surveillance Data Available i

Adjusted Reference i

Matt.

Temperature, F l

Beltline Materials ident.

T/4 3/4T I

Lower Shell Plate C5114-1 71 58 6

1 i

NB to US Cire. Weld (100%)

WF-182-1 149 107 l

US to LS Cire. Weld (100%)

WF-112 161 116 Table 29. %T and %T ART Values Through 32 EFPY for the ANO-1 Reactor Vessel Beltline Materials With Surveillance Data Available l

Adjusted Reference Matt.

Temperature, F Beltline Materials ident.

T/4 3/4T l

Lower Shell Plate C5114-1 76 62 k

i NB to US Cire. Weld (100%)

WF-182-1 166 121 l

US to LS Cire. Weld (100%)

WF-112 179 131 i

l i

DOCUMENT 96-E OO57 02, Rev. O i

NUMBER PAGE 29 OF 38 i

PREPARER:

M.J.DeVan DATE:

6105/96 i

' REVIEWER:

C. A. Campbell DATE:

6105/96 PAGE 29 I

l

FRAMATOME TECHNOLOGIES FTI PROPRIETARY 32-1245917 00 1

i i

1.

3 6

1 APPENDIX A 1

I' Credibility of Surveillance Data i

DOCUMENT 96-E405742, Rev. O NUMBER PAGE 30 OF 38 PREPARER:

M.J.DeVan DATE:

6l05/96 REMEWER:

C. A. C'ampbell DATE:

6105/96 PAGE 30

l FRAMATOME l'

TECHNOLOGIES FTl PROPRIETARY 32 1245917-00 l

i To verify that the adjusted reference temperature for each beltline material is a i

bounding value for the specific reactor vessel, plant specific information that could affect the level of embrittlement should be considered. This information includes, but l

is not limited to, the reactor vessel operating temperature and any related surveillance data that is available. The results of plant specific surveillance program data should be integrated into the adjusted reference temperature projection if the l

plant specific surveillance data has been deemed credible as judged by the criteria presented in Section 6.0 of this calculation. This Appendix provides the review of tho available surveillance data for ANO-1 against these credibility criteria.

i Criterion 1. Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement according to the recommendations of Regulatory Guide 1.99, Revision 2.

i Surveillance data available include the following materials:

l l

Base Metal Heat No. C5114-1 (ANO-1 plant-specific RVSP data) 6 i

Weld Wire Heat No. 821T44 (MIRVP data)

Weld Wire Heat No. 406L44 (MIRVP data) 4 i

i l

All these heats of material lie within the reactor vessel belthne region of the ANO-1 I

reactor vessel as defined in 10 CFR 50, Appendix G. Therefore, these materials could be controlling with regard to radiation embrittlement.

l Criterion 2. Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature unambiguously.

The available Charpy V-notch data for these surveillance data permit the determination of the 30 ft-Ib temperatures and are presented in their respective RVSP reports.

DOCUMENT 96-E4057-02, Rev. O NUMBER PAGE 31 OF 38 PREPARER:

M.J.DeVan DATE:

6/05/96 REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 31

,=

\\

l FRAMATOME I'

TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 i

j Criterion 3. When there are two or more sets of surveillance data from one reactor, the scatter of ART values about a best-fit line drawn as uor j

described in Regulatory Guide 1.99, Revision 2, Position 2.1 normally should be less than 28'F for welds and 17'F for base i

i metal. Even if the fluence range is large (two or more orders of l

magnitude), the scatter should not exceed twice those values.

1 i

The scatter of the measured ARTuor values for the available surveillance data are presented in Table A-1 for the base metal and Table A-2 for the weld metals. The scatter of the measured ART,or values about the best-fit line drawn as described in i

Regulatory Guide 1.99, Revision 2, Position 2.1 is greater than 17'F for the base metal and greater than 28'F for the weld metals.

I l

{

Criterion 4. The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding / base j

i metal interface within t25'F.

6 r

l The surveillance data for the base metal C5114-1, the Davis-Besse (TE-1) and Three Mile Island Unit 2 (TMI-2) weld metal WF-182-1, the ANO-1 and Rancho Seco Unit 1 l

(RS-1) weld metal WF-193, and the Oconee Unit 1 (OC-1) and B&WOG weld metal l

WF-112 were irradiated in either the Crystal River Unit 3 (CR-3) or TE-1 reactor i

j vessel with a cold leg operating temperature of 556*F which is the same as the cold leg operating temeperature for the ANO-1 reactor vessel. The cold leg operating i

temperature for the Point Beach Unit 2 (PB-2) surveillance weld data (WF-193) is l

542'F and is within 25'F of the cold leg operating temperature for ANO-1.

l Therefore, all the available MIRVP surveillance weld data for the welds WF-182-1 and l

WF-112 can be used in the chemistry factor determination.

I i

i Criterion 5. The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material.

2 l

All available surveillance data used in the chemistry factor determination ~ have i

correlation monitor material data which fall within the scatter band of the available l

data base for that material.

DOCUMENT 96-E-0057-02, Rev. O NUMBER PAGE 32 OF 38

[

l l

PREPARER:

M.J.DeVan DATE:

610 5196 j

REVIEWER:

C. A. Campbell DATE:

6/05/96 PAGE 32 4

J

FRAMATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 Table A-1. Base Metal Plate Heat Number C5114-1 Surveillance Data Credibility W

i Factor ART.,

Meas.

Base Metal Capsule Fluence ff (Secton 6.1)-

(CF

  • ff)

ART.,

Scatter

<17'F i

Arkansas Nuclear One Unit 1 AN1-E 7.27E+17 0.356 51.2 18.2 30 (LT) 11.8 Yes Plate C5114-1 0.356 10 (TL)

-8.2 Yes AN1-A 1.03E+19 1.008 51.2 51.6 48 (LT)

-3.6 Yes 1.006 66 (TL) 14.4 Yes AN1-C 1.46E+19 1.105 51.2 56.6 64 (LT) 7.4 Yes 1.105 38 (TL)

-18.6 No l

l i

i DOCUMENT 96-E-OO5742, Rev. O I NUMBER PAGE 33 OF 38 PREPARER:

M.J.DeVan DATE: 6105196 REMEWER:

C. A. Campbell DATE: 6105/96 Page 33

FRAntATOME TECHNOLOGIES FTl PROPRIETARY 32-1245917-00 Table A-2. Weld Metal Surveillance Data Credibility Chemstry Ratio Weld Wire Heat Number Factor ART,m Adjusted (Weld identifications)

Capsule Fluence ff

_ (Sechon 6.1)

(CF

  • ff)

Meas.

Scatter

<t28'F ART,m 821T44 TE1-F 2.29E+18 0.602 172.7 104.0 133.7 29.7 No TE1-B 5.92E+18 0.853 172.7 147.3 131.6

-15.7 Yes TE1-A 1.29E+19 1.071 172.7 185.0 184.3

-0.7 Yes TE1-D 9.62E+18 0.989 172.7 170.8 158.0

-12.8 Yes TMl2-C 1.68E+18 0.529 172.7 91.4 108.7 17.3 Yes TMl2-E 1.74E+18 0.537 172.7 92.7 92.0

-0.7 Yes DOCUMENT 96-E4057-02, Rev. O NUMBER p

PAGE 34 OF 38 PREPARER:

M.J.DeVan DATE: 6105/96 REMEWER:

C. A. Campbell DATE: 6105/96 Page 34

._____m_._m..

' FRAMATONE TECHNOLOGIES FTi PROPRIETARY

'32-1245917-00 c

Chemistry Ratio Wold Wire Heat Number Factor ART.,

Adjusted (Wald identincatens)

Capsule Fluence ff (Sechon 6.1)

(CF

  • ff)

Meas Scatter

<i28'F ART.,

406L44 AN1-E 7.27E+17 0.356 185.6 66.1 111.2 45.1 No (WF-112, WF-154, & WF-193)

AN1-A 1.03E+19 1.008 185.6 187.1 159.9

-27.2 Yes 1

AN1-C 1.46E+19 1.105 185.6 205.1 195.9

-9.2 Yes OC1-E 1.50E+18 0.503 185.6 93.4 76.4

-17.0 Yes OC1-A 8.95E+18 0.960 185.6 179.8 187.2 7.4 Yes OC1-C 9.86E+18 0.996 185.6 184.6 181.3

-3.3 Yes RS1-B 3.99E+18 0.745 185.6 138.3 99.0

-39.3 No RS1-D 6.60E+18 0.884 185.6 164.1 152.0

-12.1 Yes RS1-F 1.42E+19 1.097 185.6 203.6 166.0

-37.6 No D1 8.21E+18 0.945 185.6 175.4 199.9 24.5 Yes PB2-V 6.50E+18 0.879 185.6 163.1 186.0 22.9 Yes 3

PB2-T 8.61E+18 0.958 185.6 177.8 169.1

-8.7 Yes

~

PB2-R 2.20E+19 1.214 185.6 225.3 264.8 39.5 No PB2-S 3.10E+19 1.298 185.6 241.1 260.3 19.2 Yes 1

DOCUMENT 96-E-OO57 02, Rev. O j

NUMBER PAGE 35 OF 38 y

PREPARER:

M.J.DeVan DATE: 6905!96 REMEWER:

C. A. Campben DATE: 6005/96 Page 35

a FRAMATOME TECHNOOLOGIES FTl PROPRIETARY 32 1245917 00 4

)

h l

6 APPENDlX B References 4

4 3

4 i

1 4

d f

l l

l l

DOCUMENT 96-E405742, Rev. O NUMBER i

PAGE 36 OF 38 i

~

PREPARER:

M.J.DeVan DATE: 6105/96 REWEWER:

C. A. Campbell DATE: 6105/96 Page 36

t

', o ~ -

FRAMATOME l'

TECHNOOLOGIES FTi PROPRIETARY 32-1245917-00 i

i 1.

U.S. Nuclear Regulatory Commission, Radiation Damage to Reactor Vessel l

Material, Reaulatorv Guide 1.99. Revision 2. May 1988.

l 2.

Framatome Technologies Document 32-1244469-00, "ANO PT Fluence Results,"

July 1996.

3.

L. S. Harbison, " Master integrated Reactor Vessel Surveillance Program," B6W.-

1543. Revision 4. B&W Nuclear Technologies, Lynchburg, Virginia, February i

1993.*

i l

4.

American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section ill, Nuclear Power Plant Components, Subsection NB, Class 1

)

Components.

5.

H. S. Palme, H. W. Behnke, and W. J. Keyworth, " Methods of Compliance with Fracture Toughness and Operational Requirements of 10 CFR 50, Appendix G,"

i BAW-10046P. Babcock and Wilcox's Nuclear Power Generation Division, l

Lynchburg, Virginia, March 1976.*

i 6

i 6.

J. D. Aadland, " Babcock & Wilcox Owners' group 177-Fuel Assembly Reactor i

Vessel and Surveillance Program Materials Information," BAW-1820. Babcock and 1

Wilcox's Nuclear Power Division, Lynchburg, Virginia, December 1984.*

1 7.

K. K. Yoon, " Initial RT of Linde 80 Wolds Based on Fracture Toughness in the Transition Range," BAW-2245. Revision

1. B&W Nuclear Technologies, Lynchburg, Virginia, October 1995.*

l 8.

A. L. Lowe, Jr. and J. W. Pegram, "Correlationr, for Predicting the Efbets of i

Neutron Radiation on Linde 80 Submerged-Arc ' Welds," BAW-1803. Revisloq.1, B&W Nuclear Technologies, Lynchburg, Virginia, May 1991.*

9.

L. B. Gross, " Chemical Composition of B&W Fabricated Reactor Vessel Geitline l

Welds," BAW-2121P. B&W Nuclear Technologies, Lynchburg, Virginia, April l

1991.*

i 10.

Code of Federal Regulation, Title 10, Part 50, Fracture Toughness Requirements for Light-Water Nuclear Reactors, Appendix G,

Fracture Toughness l

Requirements.

11.

A. L. Lowe, Jr., mLaL, " Analysis of Capsule AN1-C Arkansas Power & Light i

Company Arkansas Nuclear One, Unit 1 - Reactor Vessel Material Surveillance

~

j Program," BAW-2075. Revision 1. Babcock & Wilcox's Nuclear Power Division, j

Lynchburg, Virginia, October 1989.*

i l

l PREPARER:

M.J.DeVan DOCUMENT 96-E4)057 02, Rev. O NUMBER REVIEWER:

C. A. Campbell p

37

e.

FRAntA10ntE TECHNOOLOGIES FTl PROPRIETARY 32-1245917-00 12.

A. L. Lowe, Jr., gLgL, " Analysis of Capsule TE1-D The Toledo Edison Company l

Davis Besse Nuclear Power Station Unit 1 - Reactor Vessel Material Surveillance i

Program," BAW-2125. B&W Nuclear Technologies, Inc., Lynchburg, Virginia, December 1990.*

i 13.

A. L. Lowe, Jr., glat, " Evaluation of Capsules TMl2-C and TMl2-E Irradiated in Davis-Besse Nuclear Power Station Unit 1 - EPRI Reactor Vessel Embrittlement j

Program," BAW-2190. B&W Nuclear Technologies, August 1993.*

i i

14.

K. E. Moore and A. S. Heller, " Chemistry d 177-FA B&W Owners' Group Reactor i

Vessel Beltline Welds," BAW-1500. Babcock & Wilcox' Nuclear Power Generation j

Division, Lynchburg, Virginia, September 1978.*

i l

15.

S. L. Anderson, " Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company Point Beach Unit 2," WCAP-12795. Revision 3, j

Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, August 1995.

I j

10.

A. L. Lowe, Jr., glaL, " Analysis of Capsule OC1-C Duke Power Company Oconte Nuclear Station Unit 1 - Reactor Vessel Material Surveillance Program," BAW-l 2QEQ, Babcock & Wilcox's Nuclear Power Division Lynchburg, Virginia, October i

1988.*

17.

A. L. Lowe, Jr., gM " Analysis of Capsule RS1-F Sacramento Municipal Utility l

District Rancho Seco Unit 1 - Reactor Vessel Material Surveillance Program,"

BAW-2074. Babcock & Wilcox's Nuclear Power Division Lynchburg, Virginia, April 1989.*

18.

A. L. Lowe, Jr., glRL, " Analysis of Capsule DB1-LG1 Babcock & Wilcox Owners Group - Integrated Reactor Vessel Materials Surveillance Program," BAW-1920P.

Babcock & Wilcox's Nuclear Power Division Lynchburg, Virginia, October 1986.*

19.

A. L. Lowe, Jr., gl3L, " Analysis of Capsule S Wisconsin Electric Power Company Point Beach Nuclear Plant Unit No. 2 - Reactor Vessel Material Surveillance Program," BAW-2140. B&W Nuclear Technologies, Inc., Lynchburg, Virginia, August 1991.*

20.

S. E. Yanichko and G. C. Zula, " Wisconsin Michigan Power Co. and the Wisconsin Electric Power Co. Point Beach Unit No. 2 Reactor Vessel Radiation Surveillance Program," WCAP-7712. Westinghouse Electric Corporation, Pittsburgh, Pennsylvania, June 1971.

\\

PREPARER:

M.J.De\\ DOCUMENT 96-E-0057-02, Rev. 0 REVIEWER:

C.A.Cas NUMBER Page 38 PAGE 38 OF 38

.e-e o

96-E-0057-02, Resision 0 Page A-1 1

4 ATTACHMENT 1 FTI DISCLOSURE 4

6 1

I j

e

DOCUMENT 96-E-OO57 02, Rev. O NUMCER PAGE A-2 OF A-2 November 20,1996 F R AM ATO M E INS-96-7661 TECHHOLOG1E5 Integrated Nuclear Services Mr. Bob Clark GSBI3W Entergy Operations, Inc.

Arkansas Nuclear One Route 3, Box 137G Russellville, AR 72801

Subject:

Arkansas Nuclear One Unit 1 Adjusted Reference Temperatun 'alculatirans

Reference:

FTl Job No. 4100692 Entergy Contract NAC00123 - NAAM1003 Dear Mr. Clark-6 Two FTl proprietary calculation package documents for the determination of the adjusted reference temperature (FTl Document No. 32-1245917-00 and FTl Document No. 32-1257716-00) were submitted to Entergy as part of the referenced contract. FTl has reviewed the content of these two documents and has determined that no information contained in these documents is proprietary. Therefore, no restrictions are placed on these documents, and Entergy is free to distribute these documents to applicable parties.

If you have any questions, please call me at (804) 832-3160.

Sincerely, M.J.DeVan 3315 Old Forest Road, F.O. Box 10935, Lynchburg, VA 24506-0935 Telephone: 804-832-3000 Fax: 804-832-3663 Internet: http /www.framatech.com 1

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