ML20059J058

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Responds to 931007 RAI Re Chemistry Contents of Beltline Matl Under Question 2.b.5 in GL 92-01
ML20059J058
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 11/05/1993
From: Mccoy C
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, LCV-0189, LCV-189, TAC-M83522, TAC-M83523, NUDOCS 9311120001
Download: ML20059J058 (9)


Text

  • Geor;p Poer Cr/many

. 40 inemess Cmer P#rwy Pte;.t Crhte ths 1295

- Eur~rgham. /%rn.4 3520*

Te epnore POL E77,7122 L i

c. x. uccoy Georgia Power su e,neit nu u,p.. en: a ne sacren mac nwm November 5, 1993 LCV-0189 Docket Nos 50-424 50-425 TAC Nos. M83522 M83523 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT ,

REQUEST FOR ADDITIONAL INFORMATION  ;

REACTOR VESSEL STRUCTURAL INTEGRIT_Y In your letter of October 7,1993, additional information on the chemistry contents of .

beltline materials under Question 2.b.5 in Generic Letter 92-01 was requested. ,

Specifically, we were requested to provide within 45 days phosphorous and sulfur data and their bases for the belthne materials for both Units I and 2.

Tables A-1, A-2, and A-3 in WCAP-11011 and Tables A-1, A-2, A-3, and A-4 in WCAP-  !

11381 contain the information requested. A copy of the WCAPs was provided in our original submittal. For your convenience, a copy of these tables is enclosed.

Please contact this office if any additional information is required.

Sincerel ,

k I C. K. McCoy CKM/PAH/gmb

Enclosure:

Tables A-1, A-2, A3, WCAP-11011 Tables A-1 thru A-4, WCAP-11381 i

cc: (See next page) i

./ ll2h 10003S /,j 9311120001 931105 P k

PDR ADDCK 05000424 r i p L)

PDR

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Georgia Power b l l

r U. S. Nuclear Regulatory Commission Page 2 ,

i cc: Georcia Power Company Mr. J. B. Beasley, Jr. .

Mr. M. Sheibani NORMS U. S. Nuclear Reculatory Commission >

Mr. S. D. Ebneter, Regional Administrator

. Mr. D. S. Hood, Licensing Project Manager, NRR  !

Mr. B. R. Bonser, Senior Resident Inspector, Vogtle  :

5 t

i Y

LCV-0189 1t.

' 700776

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.; ;. .. WCAP-11011-TABLE A-1 CHEMICAL ANALYSIS OF THE INTERMEDIATE SHELL PLATES USED IN THE CORE REGION OF THE ALVIN W..VOGTLE UNIT NO.1 REACTOR PRESSURE VESSEL Chemical Compositon (weight %)

Element Plate @l Plate-B8805-1 B8805-2 B8805-3 I

  • 3 R3 B8305-3 talIcl C .24 .24 .25 .22 Mn 1.37 1.37' 1.32 1.32 P .004 .004 .003 .017 S .011 .011 .010 .011 Si , .23 .23 .26 .28 Ni .59 .59 .60 .61 Mo .56 .56 .53 .57 Cr ,08 .07 .04 .057 Cu .08 .08 .06 .058 Al .025 .024 .029 .030 Co .012 .012 .009 .006 Pb <.001 <.001 <.001 <.001 W <.01 <.01 <.01 <.01 Ti <.01 <.01 < 01 .004 Zr <.001 <.001 <.001. <.002 V .003 .003 .003 <.002-Sn .004 .004 .017 .019

'As .002 .002 .001 .003 Cb <.01 <.01 <.01 <.002 N2 .007 .008 .008 .006 B .< 001

. <.001 k.001 < 001

a. Surveillance program.. test plate.
b. Chemical Analysis by Combustion Engineering, Inc,
c. Chemical Analysis by Westinghouse.

A-2

f ,,. ,

'.6 -

u .

. WCAP-11011 TABLE A-2 CHEMICAL ANALYSIS OF THE LOWER SHELL PLATES USEC IN THE CORE REGION OF THE ALVIN W. VOGTLE UNIT NO.1 REACTOR PRESSURE VESSEL Chemical Compositon I*I (weight %)

Element Plate Plate Plate B8606-1 B8606-2 88606-3 C .20 .23 .22 Mn 1.32 1.35 1.38 P .005 .009 .007 S .010 .016 .012 Si .22 .21 .25  ;

Ni .59 .58 .64 Mo .55 .56 .56 Cr .04 .02 .03 Cu .05 .05 .06 Al .028 .03 .033 .

.007 I Co .005 .010 Pb <.001 notrepon.o <.001 W <.01 <.01 <.01 Ti <.01 <.01 <.01 Zr .001 .002 .001 V .003 .003 .003 Sn .001 .003 .004 As .003 .006 .006 >

Cb <.01 <.01 <.01 N2 .007 .009 .008

<.001 B <.001 <.001

a. Chemical Analysis by Combustion Engineering, Inc.

i I

i A-3 i

l i

~

WCAP-11011

,, . TABLE Ae3 CHEMICAL ANALYSIS OF THE WELD METAL USED IN THE CORE REGION WELD SEAMS OF THE ALVIN W. VOGTLE UNIT NO.1 REACTOR PRESSURE VESSEL NOTE The core region (belttine) welds are consdered to include the intermediate and lower sheti plate lorgtudinal seams and the joining intermedete to lower shell girth seam.

All core region (betthne) we60s were fabncated usang Weld Wire Heat No. 83653. Linde 0091 Flux. Lot No. 3536.

Chemical Compositon (weight %)

Element Wire Flux Actual Production Westinghouse Test Weld Weld (Intermediate Surveillance Samplel 'I To Lower ShcIl Girth Program Test Seam,101-171)W Weidment "D"I*I C .14 .09 .13 Mn 1.06 1.17 1.15 P .007 .008 .017 S .009 .009 .010 Si .16 .17 .19 Ni .10 .10 Mo .52 .63 .61 Cr .05 .052 Cu .03 .04 .037 Al .009 .002 Co .01 .005 Pb <.001 < 001 W .02 <.01 Ti <.01 .006

' < 002 Zr .001 .

V .005 .007 .003 Sn .003 <.002 As .006 .004 Cb .01 <.002 N2 .021 .003 B <.001 <.001

a. Chemical Analysis of Wire-Flux Weld Sample, Test Number D32255 by Combustion Engineering. Inc.
b. Chemistry Data Sheet for Final Vessel Assembly, Contract 8971, Job 708171, Control Number 009, Weld 101-171 by Combustion Engineenng. Inc.
c. Chemical Analysis by Westinghouse of Weld Test Plate "D" Supplied by Combustion Engineering, Inc.

Representative of the Cicsing Girth Seam Weld.

A-4 5

WCAP-11381 i-TABLE A-1 CHEMICAL ANALYSIS OF THE INTERMEDIATE SHELL PLATES USED IN THE CORE REGION OF THE ALVIN W. VOGTLE-UNIT NO. 2 REACTOR PRESSURE VESSEL Chemical Compositon taj U

Element Plate Plate Plate R-4-1 R-4-2 .R-4-3 C .21 .20 .25 Mn 1.28 1.25 1.37 .;

P .009 .009 .009 S .010 .009 .012 i Si .23 .22 .20 Ni .64 .62 .59 ,

Mo .57 .55 .56 Cr .03 .03 .03 Cu .06 .05 .05 Al .026 .024 .017 Co .012 .011 .008  :

Pb not detecreo not oetected not oeiected W <.01 <.01 <.01 Ti <.01 <.01 <.01 Zr <.001 <.001 <.001 V .005 .004 .005  ;

Sn .005 .005 .004 As .007 .007 .008 Cb < 01

. <.01 <.01-N2 .009 .008 .008 'l B < 001

. <.001 <.001 i j

a. Chemical Analysis by Combustion Engineering, Inc. .j l

u A-2 i

r 1

WCAP-11381 TABLE A-2  ;)

CHEMICAL ANALYSIS OF THE LOWER SHELL PLATES USED IN THE CORE REGION OF THE ALVIN W. VOGTLE UNIT NO. 2 REACTOR PRESSURE VESSEL Chemical Compositon (weight %)

Element Plate (b) pyg B8825-1 R-8-1 B8628-1 I*IIDI B8628-1[al [c]

C .23 .21 .24 .23 Mn 1.31 1.34 1.34 1.30 P .006 .007 .007 .007 S .014 .012 .016 .014 S .25 .25 .25 .23 Ni .59 .62 .59 .59 Mo .59 .62 .59 .50 Cr .02 .02 .02 .07 Cu .05 .06 .05 .05 Al .031 .019 .029 .034 Co .004 .011 .004 .008 Pb ,ot detecreo not cetecteo not detecteo <.07 W <.01 < 01

. < 01

. <.05 Ti <.01 <.01 <.01 .005 Zr <.001 < 001

. <.001 <.03 V .004 .004 .004 <.005 Sn .004 .004 .017 .007 As .006 .008 .007 .008 Cb <.01 <.01 <.01 <.05 N2 .009 .011 .008 .007 B <.001 <.001 < .001 .008 i l

a. Surveillance program test plate.
b. Chemical . Analysis by Combustion Engineering, Inc. j
c. Chemical Analysis by Westinghouse.

I i

j A-3

~ '

WCAP-11381

~

TABLE A-3 CHEMICAL ANALYSIS OF THE WELD METAL USED FOR THE INTERMEDIATE AND LOWER SHELL PLATES LONGITUDINAL SEAMS FOR THE ALVIN W. VOGTLE UNIT NO. 2 REACTOR PRESSURE VESSEL Chemical Com ositon Element Wire Flux Test Weld Sample tal (Weid Wwe Heat No. 87005 Linde 0091 Flux. Lot No 0145)

C .15 Mn 1.34 P .007 l S .011 Si .13 Ni .13 Mo .55 Cr Cu .07 Al Co Pb i W

Ti Zr V .005 Sn As Cb Ng l B

a. Chemical Analysis by Combustion Engineering, Inc.

)

I i

A-4 1

i, WCAP-11381 TABLE A-4 CHEMICAL ANALYSIS OF THE WELD METAL USED FOR THE INTERMEDIATE TO LOWER SHELL CLOSING GIRTH SEAM OF THE ALVIN W. VOGTLE UNIT NO. 2 REACTOR PRESSURE VESSEL Chemical Compositon U

Element Wire Flux Test Weld Surveitlance Sample tal Weldment (Weld Wee Heat No 87005.

Test Plate Dtb]

Linoe 124 Flus. Lot No 1061)

C .075 .099 Mn 1.27 1.25 P .007 .008 S .010 .013 .

Si .50 43 Ni .12 .17 Mo .52 .47 Cr .07 .061 Cu .06 .040 Al .015 Co .002 Pb <.01 W <.01 Ti <.001 Zr --

<.01 V .004 <.004 Sn

<.001 As .003 Cb <.002 N2 .002 B .009

a. Chemical Analysis by Combustion Engineering. Inc.
b. Chemical Analysis by Westinghouse of the Surveillance Program test plate "D" representative of the closing girth seam. Weld wire Heat No. 87005, Linde 124 Flux l Lot No 1061. .

j A5

.