ML20133C363

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Forwards Response to RAI Re WCAP-14484, Analysis of Capsule V from Dl Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program
ML20133C363
Person / Time
Site: Beaver Valley
Issue date: 01/02/1997
From: Jain S
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9701070156
Download: ML20133C363 (19)
v • d • e


Text

,. - - . . . . .- . . _ . - - . - _

Beav Valley Power Station Shppingport, PA 15077-0004

  • $$n$N,,,w.n, January 2, 1997 yyy3]y a ow Division U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information Concerning WCAP-14484; RAI Dated October 18,1996 Attached is our response to an NRC request for additional information provided by letter dated October 18, 1996, concerning WCAP-14484, " Analysis of Capsule V from the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program." This response provides information concerning Capsule V and associated reactor vessel fluence, chemistry data, and vessel integrity data. The response to Item 3 will be provided by January 31, 1997, in a separate letter following final acceptance.

In addition, a supplement to our March 27, 1996, submittal will be provided by separate letter to include a no significant hazard evaluation in support of the change to the UFSAR capsule removal schedule. The supplement will be provided following Engineering review and acceptance of the recommended changes.

Sincerely,

\\

,b 'Lp Sushil C. Jain f

c: Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager DEllVE. RING QUALliV 9701070156 970102 PDR ADOCK 05000412 P PDR

. Beaver Valley Power Station, Unit No. 2 Response to Request for AdditionalInformation concerning WCAP-14484; RAI Dated October 18,1996 Item 1 The NRC staff has been using the NRC's Reactor Vessel Integrity Database (RVID) as its evaluation bases for evaluating vessel integrity submittals. With the exception of the fluences for the axial welds fabricated from weld heat 83642, the current version of the RVID lists the neutron fluences for the beltline materials at the ID surface and 1/4T locations as being 6.207x10 n/cm2 and 3.869x10l ' n/cm2 , respectively. The current version of the RVID lists the fluences for the axial welds fabric- i from Heat No.

83642 at the ID surface and the 1/4T locations as being 1.861x10 ' n/cm2 and 1.160x10

2 n/cm , respectively. Westinghouse, in WCAP-14484, states (on page 1-2) that the (revised) fluences for the BVPS-2 vessel at the ID surface,1/4T, and 3/4T locations are 3.85x10l ' n/cm 2, 2.24x10 n/cm ,2 and 0.55 lx10*' n/cm 2, respectively.

Since the fluences for the axial welds differ from those reported for the other beltline materials in the vessel, provide the updated fluence values for each beltline material in the BVPS-2 vessel at the vessel's inner surface, the 1/4T and 3/4T locations at 32 EFPY.

In addition, provide the reference documents where the details regarding these fluences may be found.

' Response 1 Per CE drawings E-9071-124-001, Intermediate Shell Westinghouse Electric Corp.157" 1.D. P.W.R., Revision 2 and E-9071-142-001, iower Shell Westinghouse Electric Corp.

157"I.D. P.W.R., Revision 2, the azimuthal location of the intermediate and lower shell axial welds is 45 and the vessel beltline is 7.875 inches thick.

The details of the latest fluence evaluation are given in Section 6.0 of WCAP-14484. In Table 6-14, Neutron Exposure Values within the Beaver Valley Unit 2 Reactor Vessel, on page 6-31 of WCAP-14484 is the revised calculated fluence values at the ID surface, 1/4T, and 3/4T locations for various azimuthal locations. The peak revised calculated vessel fluence values at the 0 location from Table 6-14 are reported on page 1-2 in WCAP-14484.

Contained in Table 1 is the current vessel ID surface,1/aT, and 3/4 locations at 32 EFPY. These 32 EFPY fluence values are based on the ID surface fluence values reported in Table 6-14 of WCAP-14484 and the calculational rnethodology given in Regulatory Guide 1.99, Revision 2.

TABLE 1 Fluence Values for the Beaver Valley Unit 2 Reactor Vessel Beltline Materials at 32 EFPY Material Peak ID Surfacem 1/4T Location

  • 3/4T Location
  • Intermediate Shell 3.85 x 10 n/cm 2.40 x 10 n/cm2 9.33 x 108 n/cm2 Plate B9004-1 (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 2 2 Intermediate Shell 3.85 x 10 n/cm 2.40 x 10 ' n/cm 9.33 x 10 n/cm2 Plate B9004-2 (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 2 9.33 x 10 n/cm2 2

Lower Shell 3.85 x 10 n/cm 2.40 x 10 n/cm Plate B9005-1 (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 2 2 Lower Shell 3.85 x 10 n/cm 2.40 x 10 n/cm 9.33 x 10 n/cm2 Plate B9005-2 (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 2 Circumferential Weld 3.85 x 10" n/cm 2.40 x 10

  • n/cm' 9.33 x 10 n/cm2 Seam 101-171 (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 2 3

Intermediate Shell 1.21 x 10

  • n/cm 7.54 x 10 'n/cm* 2.93 x 10 n/cm Axial Weld Seams (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 101-124A & Bm Lower Shell 1.21 x 10 n/cm' 7.54 x 10 n/cm' 2.93 x 10 n/cm*

Axial Weld Seams (E > 1.0 MeV) (E > 1.0 MeV) (E > 1.0 MeV) 101-142A & BW J

NOTES:

1. Intermediate and Lower shell weld seams are located at 45
2. From Table 6-14 of WCAP-14484.
3. f = fa(ea24 x) (per Regulatory Guide 1.99, Revision 2)

Where: f = fluence at the 1/4T or 3/4T location fa = The peak surface fluence at 32 EFPY X = depth into the vessel wall (inches) for 1/4T X = 1.969 inches (0.25

  • 7.875 inches) for 3/4T X = 5.906 inches (0.75
  • 7.875 inches)

T

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l

)

Item 2 Table 4-1 of WCAP-14484 lists the chemistries for the surveilla ice materials corresponding to intermediate shell plate B9004-2 and the beltline axial and girth welds.

However, no reference documents were provided in WCAP-14484 for the chemistries ,

for these surveillance materials. Provide the reference document for the revised copper i and nickel content values for these materials, and provide the basis for the revised best i estimate chemistry values.

i Response 2 i Table 4-1 of WCAP-14484 provides the chemistry results documented in WCAP-9615, .

Revision 1, Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program (Reference 3 as indicated in the title of the table). The best estimate chemistry values of the surveillance materials are determined from the mean values of all available data. Contained in the following table are the values used to determine the best estimate chemistry values (NOTE: the reference documents are attached).

TABLE 2 i Values Used to Determine the Average Cu and Ni wt. %

l of the Surveillance Materials Inter Shell Plate B9004-2 Surveillance Weld Metal Cu % Ni % Cu % Ni %

0.07 0.59 0.04 -

0.06 0.56 0.04 0.08 l 0.05 0.56 0.04 0.09 0.05 0.07 0.05 0.07 0.

0.06* 0.57* 0.05* 0.07* l

  • Average wt. % of Cu and Ni

Dsmi In the Section 5.3.4 to NUREG-1507, Supplement 5, " Safety Evaluation related to the operation of Beaver Valley Nuclear Plant Unit 2," the NRC staff required that the 10 CFR 50.61 (PTS) assessment for "..... protection against pressurized thermal shock" be " updated whenever changes in core loadings, surveillance measurements or other information indicate a significant change in projected values." To date, no revised 10 CFR 50.61 (PTS) assessment has been submitted in regard to integrity of the BVPS-2 reactor vessel as determined from the information and data provided in WCAP-14484.

In accordance with the NRC staff's assessment in NUREG-1507, Supplement 5, either submit a revised PTS assessment. based on the data and information provided in WCAP-14484, or provide a basis why the changes to the reactor vessel integrity data in WCAP-14484 are not significant.

Response 3 The response to this item will be provided in a separate letter by January 31,1997.

Item 4 Update the data for the fabrication heat numbers for the BVPS-2 shell plates. The only heat numbers that are currently on record are Heat No. C0544-2 for intennediate shell plate B9004-2, and Heat No. C1408-1 for lower shell plate B9005-2. In addition, provide the most current best estimate chemistries for the BVPS-2 beltline materials, and the most current reference document (s) where these chemistries can be found.

Response 4 Contained in the following table are the best estimate chemistries for the beltline materials not included in Table 2 of this document. In addition, the references for these numbers are attached. The attached Material Certifications provide the heat numbers of all beltline plate materials.

TABLE 3 Chemistry Values for the Beltline Materials not Contained in the Surveillance Program Intermediate Shell Plate Lower Shell Plate B9005-1 Lower Shell Plate B9005-2 B9004-1 Cu % Ni % Cu % Ni % Cu % Ni%

0.07 0.53 0.08 0.59 0.07 0.58 0.06 0.57 0.08 0.57 0.07 0.56 0.065* 0.55' O.08* 0.58* 0.07* 0.57'

  • Average wt. % of Cu and Ni

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m AsEn. LUKENS STE COMPANY i

u M r., N . c ,,t,,Vr,,, ,A ,,,,, o,m g.py m* .

,, 4 - M 4 2 TEST CERTIFICATE -

le Para 933 ,,,,yng,gg, Dept., Mr.s. c. Kis a u,a onoeua cono ino chattaneosa, Tenn. 37401 64821-1 42-82819 cJ 4172 Da .

SPECIFICATIONS: -

F3F194-71 5A-533-n class 1 Job #709124 cont. #9071 SEND TE5r .K. soooccut.rv rest

% MELT NO.

CHEMICAL ANALYSIS Basid h 4ss C MN P S Cu St Ni Ca Mo V Te At E 40944 23 1.40 012 015 06 26 56 54 00 Elect ric Y.I.F. Steel RisEAs 1 25 1.40 010 012 07 24 53 54 00 tetssEAs,2 ,.23 1.45 007 014 07 28 59 55 00 P H Y31 C A L PROPERTIES MELT NO. p4 pg g ,  % BHN S$8 g ..A.

DESCRIPTION I I h h 26 O ~7g () g f / I 7 3q692 1/4 2 713 925 24 1- "

712 920 26 8--9C OMTl 2- I 1l I

9 07\/ 1

\

I wets heated to 15J5'F<*25'F, , helti 4 hrsi. ant lW.4.lto400*F.,

. hen tempered 1225 F.825'F., held 4 hrs. and stir ootpled. l 1

ests otresis relieved by hesi;ing to 1150' F.225'F., apeld 40 hrs.

nd furnaco coolod within a rate of 100*F. per hr. to 600"F.,

ne cir ecoled. I I I I I i

' a 4 i' hereby certify the obove figures are correct as contained in the records of the company. s, ,,,so, ,,,,, r T.- '

- M-

Interoffica Correspondence POWER .

. SYSTEMS .. .._. Subject .. . _ .. .___.._. Prom ..

b To T. N. Fazio Test Report Metallurgical & Materials l Westinghouse Electric Laboratory - Chattanooga Contract No. 9071 ces Peggy Webb Job No. 709194 August'19, 1976' Project No. 960001 e

Description:

Intermediate and Lower Shells Analyzed to ASTM E-350 Sample obtained at 1/4 Thickness. ,

Analysis:

J

. Lab No. ?16661 P16362 P16662 P15705 Code No. 5704-1 9004-2 9005-1 9005-2 Shell Intermediate Intermediate Lower Lower i

. Si 0.25 0.26 0.24 0.23 .

S 0.009 0.012 0.013 0.014 P 0.006 0.009 0.006 0.007 i Mn 1.39 1.40 1.31 - 1.28

?

C 0.24 0.26 0.23 0.20 l Cr 0.06 0.07 0.04 0.05 l Ni 0.57 0.56 0.57 0.56 2

Mo 0.43' O.56 0.56 0.55 ,

B <.001 <.001 <.001 <.001 i Cb <.01 <.01 <.01 <.01  ;

Ti <.01 <.01 <.01 . <.01 1 Co , 0.006 0.007 0.007 0.006 -

Cu 0.06 0.06 0.08 0.07

Al Sol 0.039 0.040 0.025 0.028 Al Ins 0.001- 0.006 0.001 Total N2 0.009 0.010 0.008 0.007 V 0.003 0.003 0.003 0.003 W <.01 <.01 <.01 <.01 ~ kd8 ,

As 0.002 0.006 0.005 0.006 Sn Zr 0.007

<.001 0.007

<.001 0.018

<.001 0.015 0.001 d- 9468-/ --

Sb Pb 0.0013

<.001 0.0017

<.001 0.0011

<.001 0.0012

<.001 fg y )

.., m _

. W. A. House l WAH/sh

IIN i 1:M-UFHCE UUHHi-bPUNDENCE

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sus COMBUSTIDN DIVISIDiil Nuclear Manufacturing Welding Material Certification Nuclear Qiality Superintendent and Release for Section III Engineering Nuclear Weldin:;

Applications Bay 29 Rod Rocn ,fp 7

. Inventory Control

. Welding Inspection

  • LJ.7w (. .; . - . , . m Jr ,
L'." 2 :; : " # ~
  • The folleving velding =aterial has been tested in accordance with the a

requirenents of SCP fico-23 31 and =eets the requirenents of the latest Addenda to Section III of the AStE Code and is released for use an ASMS Code verk only:

I. Coated Electredes (t%)

TYPE SIZE HEAT f IM Y CCUTROL 4 ERA'm i

II. Bare Electredes (GTA & G4A)

TYPE SIZE HEAT # BRAIO III. Flux Electrcde Cc=bination (SAA) ,

TYPE ELECTECDE SIZE M TYPE FLUX T.CT $

"Y //f 0bbVS bMV @il SO b 0f J P. C. Kiel r /

PCx/et

, .n tl$ COMBUSTIDRI DIVISiORI E Subject From - Date Mr. P. C. Kiefer Welding Material Qualification Metallurgical Research and to Requirements of ASME Development Department

Mr. R. Jay Section III ,

Chattanooga Mr. S. A. Lewis Job Number D-32255

,Mr. S . R . Lewis Project Number 960009 -

Mr. .R. E. Lorentz , Jr. '

Mr. L. Rose I Mr.'R. E. Smith D

The following test data is for 3/16" diameter bare wir , type low Cupeat

,' No. 83648, Flux type 091, Lot No. 3536.

=

A weld deposit was made using the above heat of wire and lot of flux. Welding was done in acccrdance with C-E Welding Procedure Specification SAA-33-34 The completed weldment was given a post weld heat treatment of 1150 F

  • 25*F l for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and furnace cooled to 600*F . _

l IMP ACT AND/OR FRACTURE TESTS TYPE TEMP.'Fl VALUES l TEMP.'F VALUES NOT CVN Ft./Lbs. ._ Mils Lat. Exp . Drop Weichts l

's ,  ;

I

-30 108 74 i

-80 1~F l

-20 84 56 '

, -70 2 NF

-20 79 '~~ ~

54 . -60 1 NF -80*F '

+10 84 -40 1 NF -

l

+10 130 129 ; {nv 76 -20 1 NF l

+10 132 85 I

/

ftgc#'

ALL WELD METAL .505 TENSILE Lab Yield Strength Ultimate Tensile Elongation in Reduction of Code KSI Strength , KSI 2" , % Area, %

L. WT 72.0 ,

83.3 30.0 72.8 Dir  %. .

~

[ ,

. 3 DATE //d- 72

/ ' '

/ W

\ METALLURGICAL RESEARCH AND j .

s .

DEVELOPMENT if .

i' TO: NUCLEAR WELDING APPLICATIONS SECTION

  • ATTENTION: etR A F o sz-

' ccz bin faV ,

bnl Eder

JOB NUMBER 332 257 - *
' CHEMICAL ANALYSIS OF WIRE'-FLUX 2~ #

is -

- TEST WELD COUPON e r i SAMPLE NO. jgfg i

LAB NO. 33 /356. f '

TYPE WIRE B-+

l g, , , , p SIZE WIRE Sjg Cf *

( EAT NO. g364g FLUX 09j LOT NO. yggg .

1 SI -

,l3

/

S ,oo9 o j

P. ,oss / l MN J,13 C _i3 -

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M0'

.57 CU g 3/

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  • f
  • l l

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interoffica Correspondence POWER m

BE1q% SYSTEMS Subject From To: T. N. Fazio Test Report - Weld Metallurgical & Materials Westinghouse Electric Laboratory - Chattanooga Contract No. 9071 Job No. 709194 Project No. 960001 August 19, 1976 ,

Analysis:

Lab No. D23549 Seam No. 101-194 Si 0.14 '

S 0.011 '

P 0.008 '

Mn 1.17 -

C 0.10 Cr 0.07 #

Ni 0.07 #

Mo B

0.49

<.001 Cb <.01 Ti <.01 ' ,

Co 0.007 " (

Cu 0.08 ' l Al 0.001 # 1 N2 0.028 " l V 0.002 # 1 W <.01 -

As 0.005 7 Sn 0.005 -

Zr <.001 '

Pb <.001 -

Sb -----

W. A. House i WAH/sh

_ . _ _ _ _ . _ . - - - . _ _ _ _ _ _ _ _ . . _ _ . _ _ . . _ . - - _ _ _ _ . _ .m._._ __-

~

Contract 9071 i

. l Chemical Analysis including all elements listed under ASTM E-350.

Long Seam

. Lab No. D13784 D13785 D14181 D14182 S.O. No. 709124 '709124 709142 709142 Seam 101-124A 101-124B 101-142A 101-142B Si 0.17 0.17 0.16 0.16 l S 0.008 0.009 0.010 0.01'  !

P 0.008 0.008 0.010 0.010  !

Mn 1.14 1.19 1.13 1.23  !

C 0.14 0.14 0.14 0.14 Cr 0.04 0.04 0.05 0.C: i Ni 0.08. 0.09 0.07 0.07 i Mo 0.60 0.61 0.62 0.62  ;

B 0.0004 0.0004 0.0005 0.0006  !

Cb <.01 <.01 <.01 <.01 -

V 0.006 0.006 0.007 'O.007 ,

Co 0.010 0.010 0.010 0.010 i Cu 0.04 0.04. 0.05 0_.05 i A1 0.003 0.004 0.004 0.003 i N2 0.008 0.004 0.004 0.003

  • Ti <.01 <.01 <.01 <.01-W <.01 <.01 0.01 0.01 As 0.013 0.014 0.014 0.014  ;

'Sn 0.004 0.004 0.006 0.005 l RZr 0.001 0.001 0.001 0.001 i Pb. 0.002 0.002 <.001 <.001 h

l l

+

~

i 1

l l

l l

i J

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METALLL

,1 CAL RESEARCil AND 'sEVELOPl. .T DEPT Cctober 4,1974

}"[N

, MATERIALS CERTIFICATION REPORT

~

MATER'1AL SPECIFICATION 01 119 (al CONTRACT NO, 9071 VENDOR T uken Tat 001 Coinpany JOB NO. 709124-004 HEAT NO. C 0544-1 ___

CODE NO. 11-9004-1 .

MATERI AL DESCRIPTION _292-1/4" X 104-13/1G" X C-7/8" Intermediate ShcIl

~

MIL L CHEMICAL ANALYSIS

_itrI_, ! c vs n Is (i si c, l uo es cv

.010 l_n17 _94 I _ qa n7

. .Chnck I .75 1.40

t

- /

' MECHANICAL TESTS ULTIMAT E .

TEST YlELD ELONG. R EDUCTION

  • TEST 140. GAUGE TErntLE TEMPERATURE *F STRENGTH,K51 STRENGTH,K$l IN 2i OF A R E A *; ,

Et_G. .Tf.__ .505 R. T . 69.0 91.0 94 g G1.6 M G-Tl .505 R.T. 69.1 91.9 ?A_n A7 A

'l' IMPACT AND/OR FRACTURE TESTS I

VALUr5 hyle VALUES tJOT 5 TYPE TE MP. *F l _l TEMP.*F I

~ CV:: Ft/Lbs % Shear Lat.Exo.I Drop Wef ahts i I upacts ' -40 5 0 5 0 IF 0*F

-40 6 0 ' 8 2M

-40 24 7 0 10 7 f0 ,. ,

i

+10 19

+10 20 10 18

+10 19 10 16 +120 59 / 40 46 / '

+40 22 20 21 +120 53 < 30 40 ' '

+40 26 20 23 I" +120 62 / 40 50

+40 24 20 20 +160 73 80 61 -

+100 43 30 37 +160 70 80 58

+100 51 30 42 +160 71 80 59 i

+100 45 30 40 +212 82 100 64 '

+110 48 25 39 +212 85 100 67

+110 50 30 40 +212 83 100 65 .

' +110 48 25 38

' 8

e. AtDIT'ON AL DATA ttJCLUDlt4G llEAT TREATMENT:

(1) 3600 F i25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ' Water quenched ,;

, 0:) .1225 P *25 F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

.-(C) J 150 F *25 P 4 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> . Furnace coded to 600 F.

{ The impacts were taken transverse to the major rolling direction of the plate at the ~

i 2/4.T level and notched perpendicular to the plate surface. l i "Th2 tensiles were taken in accordance with ASTM A-20-68.

The drop weights were taken transverse to rolling direction.

F.,,a EL.2120 We hereby certily ' hot the foregoing doto 1, o true copy of the dato ec: P. Webb (2) su,ni s a y,6yih, ,,os c;o,,.iii, ,a ,o ,,,oi,io,e,.. te... pe,_

'c 'aed 'a 'he Coat >ui'*aa Malia's cal Laba'a'a'v-S. R. Lewis H. Dinwiddic couauSTION ENGD fERINO, INC.

R. E. Lorentz, Jr. ,,

/

or Qfx_.

f ..J 44.[hrnold

' ~

j Inf rmation Only

r.J. S M ' COMBUSTi0h~ENGINEkRING, INC.

eat'TALLURG" ',L RESEARCH AND DEVELOPMEr DEPT l IAATERIALS CERTIFICATION REPORT m ERIAL SPECIFICATION P3F19 (c)

C'ONTRACT NO. 9071 YENDOR_ Lukens Steel Company JOB HO. Rei. Notice 02521-004

~ l ttEAT tlO._ C0544-2

. CODE NO. B-9004-2 )

}

AMTERI AL DESCRIPTION _ 292-1/4" X 104-13/16" X 8-7/8" (Testflate "B") Intermediate

}I MILL CHEMICAL ANALYSIS

, TYPF c y, p $ $1 NI Cr Ma

' ch C. -V check .23 1.45 .0071 .014 .28 .59 .55

.07 .00 MECHANICAL TESTS ,

TEST NO. TEST ULTIMATE  !

CAUGE Y1 ELD TEN 5tLE Eto4G. REDUCTION TEMPERATURE 'F STRENGTH,K$1 $TRENGTH,K$1 l IN 2'% OF AREA t l WO-TA .505 R.T. 70.9 92.0 25.0 61.6 WO-TB .505 R.T. 69.8 92.5 25.5 61.3 IMPACT AND/OR FRACTURE TESTS TYPE T E MP. 'F I VALUES i TEMP.'F' VAL.UES NOT CVN Mils '

Impacts Pt/Lbs. 'X Shear Lat.Exo. '

' _ DROP WEIGHTS I

. -40 8 0 5

-40 10 0 7 -20 1F

-40 10 0 6 i

1

+10 15: 5 13 -10 1F

+10 16

-10*F 5 15

+10 18 5 16 0 2 NF

+40 24 10 19

+40 26 10 20

+40 23 10 17

+75 39 25 29 '

+75 38 25 30

+100 i 50 35 40 '

+100 51 35 40

+160 69 90 57 l

+160 68 90 55 ADDITION AL DATA INCLUDING HEAT TREATMENT:

(A) 1650*F

  • 25'T for 1 Hour / Inch thickness. Water Quenched.

(B) 1225'T

  • 25'T for 3/4 Hour / Inch thicknese (Held on High Side).

(C) 1.150*F A 25'T for 40 Hours (Held on High Side). Furnace cooled to 600*F.

The impacts were taken transverse to the major rolling direction of. the plate at the 1/4T level and notched perpendicular to the plate sullace.

The tensiles were taken in accordance with ASTM A-20-68'.

The drop weights were taken transverse to the rolling direction.

Form E-2120 We hereby certily that the leregoing dote is e true copy el the dote pgg (wnished us by the producing mill, se date sesultlas leem tests pesa lesmed in the Combustlen Metellwgical Leberatory.

S. R. Lewis R. E. Smith USTION ENG EERING, H. Dinwiddle R. E. Lorentz, Jr. av -

J. b[. h,rnoldhe DATE November 17, 1972

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, y , T,.~,v e,. Luuuuallut4 Lt ve it:ERllib. lilC. , '"' '"'""flUh v'

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' g METAll.U. . CAL RESEARCH AND DEVELOPM. .T. DEPT Revision # 1

' MATERIALS CERTIFICATION REPORT July 3,1973 skATERIAL SPECIFICATION P3P19 (a)

  • CONTRACT NO._ 9071 VENDOR racne 9tnct e'omnany -

JOB NO. 709142-005 HEAT NO. C-1408-2 _.

  • CODE NO.B-900ci-1 MAMRI AL DESCRIPTION 292-1/4" X 104-13/16" X 0-7/A" Lower Shell Scoment #1 MILL CHEMICAL ANALYSIS

.,_typr I e ... p I s I si Im c, i v, ' I ch I c., I v Checkl .23 1.33 .009 i .021 l .25 l .59 i .57 l .00 l l .00 MECHANICAL TESTS TEST HO. TEST ULTfusiE cAUGE YtELD TEmiLE E LCNG. ~~

R E DUCTION TEMPE RATURE 'F STRENOTH.KSI STRENGTH.K51 IN 2"'; orAREA ,

VL-TA .505 R. T. )

N-Tq .505 6.6_ 3 n7.6 25.5 G2.3 l R. T. 66.3 I H7.1 21t . 0 6'J.4 l 1

fMPACT AND/OR FRACTURE TESTS i '

TYPF l TEMP.'F} VA L UE S lTEup.o r-VALUE5 k t40T 1 Ft/l.bs % Shear Mils Lat.Lxo.

Impacts ,40 10 0 6

-40 0 Drop Wolohts 11 7 .

-40

. . 15 0 10

+10

-70 1P

'18 10 14

+10 15,

-60 1 NT,1 F '

'28 21

+10

-50 1F -50*F 21 10 17

+40 29

-40 2 NF 15 23

+40

-20 1Nr 38 20 28

+40 30 15 26

+74 54 40 42 .

+74 30 j

41 32- .Ft/Lbs 3 Shear,MilstatExo

. t74 49- -35 37

- ~ ~ ~

+100. 65 60 51 4160 85 100 65

+100 76 70 57 +160 82 100 63

, +100 57 - 60 45 +160 80 100 60 ADDITICH AL DATA INCLUDING HEAT TREA TMENTs A) 1600 Pt i25'T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.

'D) 1225'r 25*T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

C) 1150*T *25'T 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Turnaco cooled to G00*T.

The Impcets were tahon trant. verse to the nujer tulling direction of the plate Lithe 1/4T '

Jcvel and r.otched perpendicular m ihe plate surface.

The tensiles were taken in accordance with ASTM A-20-6D.

The drop weights were taken transverse to the major rolling direction.

F anE-2123 We hereby certify ther the fe,egolag .ite to e oro, copy .I the deve

.cc.: P, Wghh (2) 1,ne h.d . b, ik p,.4 ci mitt. ., det. ....tilas b. i..ti e.,-

S. R, Lewis I., ~ d .. s h. c.,b vie ... u...u,,.c. L.6......r.

N. Wamack R. E. Lorentz, Jr. couousTioN ENGINEERlNC.ylNC.

R. E. Smith 3y_ .[, ,fQ,, e </

f. M. Arnold DAT E . N'ccmher 4.1972

~

~4

  • 1 l

. .. . 1

......... ...ius...... g;,,g,,,,j,;iTIOli v.. ..

METALLUR*' CAL RESEARCil A'ID DEVELOPM"T DEPT Revision # 1  ;

. MATERIALS CERTIFICATION REPORT' July 3,1973 l MATERIA' SPECIFICATION 191'19 (c) CONTRACT NO. 9071 I VENDOR hikenr. Ster 1 Company JOB NO. 700142-007.

HEAT 'NO. r*-1 Ann-1 CODE NOB-9005-2 MATERI AL DESCRIPTION __2Q.?cl/4" X 104-13/15* X D-7/8" Lower ShcIl Segment #2 .

1

, MILL CHEMICAL ANALYSIS l LTn c I "- ' a I5 I" I "i e, "> ct I c. I v  !

.Qcch .24 1.1.34 .000 l.022 { .25 i.50 1 .56 l .u7 l .00 l MECHANICAL TESTS ULTIMA T E TEST NO. GAUGE TC$T YLE LD 'ELCNG.

1 Cl4'.tLE R E 0VCTic4 TCurtRATURE 'F STREtGTH.K$1 ST R E tiG rit. r$1 114 2 " *. ,,I

' OF A R E A *.

Y M-TA .505 R. T. 65.3 n7.4 27.0 63.0 VM-TD l.505 It . T . 65.3 87.1 27.0 61.0 l

luPACT AND/OR PRACTURE TESTS l l TYPF TrMP.*rl VAplC3 lTEUP.'F Y Al.U(5 l UOT I CVN l't/lbs % Shear M ils 1.nt . IS:o.

-40 8 0 4 Oron Wolahts l Impacts '

- -40 8 0 4  !

-40 1T

-40 7 0 3 i

+10 22

-30 2NF -40*F , i 10 18

+10

-20 1 NP 24 10 - 20

+10 28 15 23

+40 34 20 26

+40' 33 20 27

+40 37 20 29

+74 40 30 33

+74 4P 35 39 Ft/[bs % Shear MilsIatExo

-;-7 4 52 40 41 77

+160 100 til

+100 60 60 49 4160 75 100 62 j

+100 59 ,

60 47 +160 81 100 Go j

+100 , . 5 5 . 60 45

{

ADDn:DH AL DATA it.CLUDING llEAT T RE ATi.'ENT:

  • )

A) 1600*r 25'r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Water quenched.  !

'B) 1225 T 25'r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

C) 1150*r 25 P 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Et naco cooled to 600*F.

The linpacts were taken transverse to the raajor rolling direction of the plato at the 1/4T Jcvel and notched perpendicular to the plato surface. .

The tensiles were taken in accordance with ASTM A'-20-68.

The dropweights were tchen transverse to the rnajor rolling direction. I Wsom E-212' i We hereby cetilly ihot the foregoing dois h e in,. cope si e . de's cC* P. Webb (2) felsked n I,y W reedwieg miti. or dois esivtileg i,em sesta au-3,g, g.wg3 fermed la si., Cemb ,si..a u es.LL.,,g.cel Loootsiety.

N. Wamach CouBUSTION ENCinfIRING. INC. I R. E. Lorentz, Jr.

R. E. s,enh

,, ._.,# m ofjj

r. u. Arnow

_ ........i...~.-,,.

8

. _ _ _ . _ _ _ - .-. - _ _ . _ . - - _ . . _ . . _ . _ . - . ._- .. . . . _ . . _ . . . . . . . ~ _ _ . - . . _ . _ - - . _

, C:

u.d.. .

. C-E check ;f.alysis -

9 ry7 ) I Code B-9004-2 Her.t No. C-0544-2 B -9004-2. i J,

SI .24
. S .016

$ P .010 t

I- MN 1 32

i C .24 i

CR .08 ,

NI 56-1 4

2 MO 59  !

B . 0 03 l CB Less Than .01 ,

V .003  ;

i CO .C09

, . CU .05 AL .c47

]

N2 009 l T1 IASS Thcn~ .01 W .01

  • AS .010 SN .003

.002 2R i

M OC.k Wk 1 .

, WESTINGHOUSE CLAD 6 3 ',

N 4

i~

I W

CENTRAL NUCLEAR de ALMARAZ ALMARAZ UNIT NO. 2 REACTOR VESSEL f RADIAftON SURVEILLANCE PROGRAM l l

J d

)

i P. J. Fields i J. A. Davidson j S. E. Yanichko ,

i December 1977 i

APPROVED: - ki i O

! J. h. Chirigos, Managej

Structural Materials Engineering Work Performed Under ASZP 106 i

1 i

WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P. O. Box 355 Pittsburgh, Pennsylvania 15230 ,

~

VNP - 3 7 2 h TABLE A 2 CHEMICAL COMPOSITION (WElGHT PERCENT) PERFORMED BY COMBUSTION ENGINEERING Element !al Plate B94051 Weld Me[allbl C 0.260 0.150 S 0.018 0.011 N2 0.007 0.003

~

Co 0.007 0.005 Cu 0,080 Si 0.220 0.100 Mo 0.530 0.620

- Ni 0.560 0.040 Mn 1.330 1.130 Cr 0.060 0.050 V 0.002 0.005 P 0.009 d004 Sn 0.004 0.001 Al 0.042 <0.001 Cb < 0.010 < 0.010

<0.010 l W <0.010

/ .s 0.004 0.004 Zr <0.001 <0.001 Ti < 0.010 <0.010 s._All elements nne Untas are less than 0.001 me neht percent.

b. W" eld wire ftype B41 heet number 83C42 fium type Linde 0001, flus lot number 3536 and representative of all core region welds. Surveillance weldment is from seem no. 101 194.

I i

i A2

'

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