ML19093B024

Response to a Request of 05/18/1977 for Additional Information on the Reactor Vessel Material Surveillance Program

ML19093B024
Person / Time
Site:	Surry
Issue date:	01/23/1978
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Case E, Reid R Office of Nuclear Reactor Regulation
References
Download: ML19093B024 (14)

Text

Hr. Edson G. Case, Acting Director Serial No.~~~~~

Office of Nuclear Reactor Regulation PO&H/DLB:das U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 Attention: Mr. Robert W. Reid, Chief DPR-37 Operating Reactors Branch 4

Dear Mr. Case:

This is in response to your request of May 18, 1977 for additional informa-tion on our Reactor Vessel Material Surveillance Program. The following documents are enclosed:

1. Surry Unit No. 1 - Reactor Vessel Material Surveillance Program.

2. Surry Unit No. 2 - Reactor Vessel Material Surveillance Program.

3. WCAP-7723, "Virginia Electric and Power Co. Surry Unit No. 1 Reactor Vessel Radiation Surveillance Program11 *

4. WCAP-8805, "Virginia Electric and Power Co. Surry Unit No. 2 Reactor Vessel Radiation Surveillance Program".

These documents include all the information specified in the attachment to your letter of May 18, 1977 entitled "Request for Information, Reactor Vessel l".Ia.terial Surveillance Program 11

• Very truly yours,

~,J/J?,~iac~~

C. M. Stallings Vice President-Power Supply and Production Operations Enclosures cc: Mr. James P. O'Reilly

-- e SURRY UNIT NO. 1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluence (E > 1 Mev) at the inner suriace of the reactor vessel wall as of March 31, 1977 is 3.92 x 101 n/cm.

2.) The effective- full power years (EFPY) of operation accumulated as of March 31, 1977 is 2.508 EFPY.

3.) Fabrication of the reactor vessel was performed by Babcock &Wilcos Co. and De Rotterdamsche Droogdok Mu.

4.) *a.) Sketch of the reactor vessel showing all *materials in the beltline region is shown in Figure l.

b.) Information on each of the welds in the beltline region is shown in Tables 1 through 4.

c.) Information on each of the plates and forgings in the beltline region is shown in Tables 4 through 7.

5.) Information relative to weld and plate material included in the material surveillance program is shown in-Tables l through 3 and 5 through 8.

FIGURE l Identification ~ocation of Surry Unit No. l R~tor Vessel

.Beltline Region M!3-terial I>

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-woi 0

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TABLE 1

- IDENTIFICATION OF SURRY UNIT NO. 1 REACTOR VESSEL BELTLINE REGION WELD METAL Welding Weld Weld Wire Flux Weld Location Process *

• Contra 1 No. ~ Reat No. ~ Lot No. Post Weld Heat Treatment Nozzle Shell to Inter Submerged Arc J726 SMIT 40 25017 *sAF 89 1197

• ll30°F - 30 HR-FC Shell Circle Seam W06*

Inter ShelJ Vertical Submerged Arc SA1494 Mn-Mo-Ni 8Tl554 Linde 80 8579 1125 + 25°F-48HR-FC Seams L3 &L4 Inter to Lower Shell Submerged Arc SA1585 Mn-Mo-Ni 72445 Linde 80 8597 1125 + 25°F-80HR-FC Circle Seam W05 Lower Shell Submerged Arc Submerged Arc WR 9 SA1494 Mn-Mo-Ni Mn-Mo-Ni 72445 8Tl554

.Linde 80*

Linde 80 8632 8579 1125 + 25°F-48HR-FC 1125 + 25°F-48HR-FC Vertical Seams Ll &L2 Surveillance Weld Submerged Arc SA1526 Mn-Mei-Ni 299L44 Linde 80 8596 1125°.:t, 15 1/2 HR-FC e

• Weld made by De Rotterdamsche Droogdok Mu (All other welds made by B&W)

TABLE 2 CHEMICAL COMPOSITION OF REACTOR VESSEL BELTLINE REGION.WELD METAL Wire Flux **= **** ............

Weight Percent

~ Heat No. ~ Lot No. C Mn p s Si Cr Ni Mo Cu SMIT 40 25017 SAF 89 1197 .093 l.67 .27 .44 .33 Mn-Mo-Ni 8Tl554 Linde 80 8579 .090 1. 52 .015 .012 .44 .07 .45 .42 .14 e.

Mn-Mo-Ni 72445 Linde 80 8597 .080 1.35 .016 0 .011 .43 .06 .51 . .35 .25 Mn-Mo-Ni 72445 Linde 80 8632 .076 1.30 .015 .012 .55 .60 .55 *174 Surveillance'.Weld

• l O. 1.49 .011 .010 .37 .076 .68 .46 .25 a~

/

TABLE 3

• Methanical *ptopartias*of*Reattot Vessel *saltline Region Weld Metal Energy Shelf Wire Flux TNDT* at l0°F RTNDT* Energy vs UTS Elong RA

~ Heat No. ~ Lot No. * * . OF *

• Ft.:.Lbs OF *Ft-Lbs Psi Psi . %  %

SMIT 40 25017 SAF 89 1197 0 64,77,51 0 67.40 82.76 31.0 69.6 Mn-Mo-Ni 8Tl 554 Linde 80 8579 0 54,25,44 0 81.00 Mn-Mo-Ni 72445 Linde 80 8597 0 50,54,51 0 81.00 -- .

Mn-Mo-Ni 72445 Linde 80 8632 0 46,43,45 0 65.00 81.00 30.5 Surveillance Weld 0 43,35.5,37 0 70 69.67 83.20 26.5 66.7

• Estimated per NRG Regulatory Review Plan Section 5.3.2.

e

- *----------*~-. ---*-----*--* - _.... ---- __ .

• .., ' \. : ~ ' I .. ~'

e e TABLE 4 MAXIMUM END-OF-LIFE FLUENCE AT .VESSEL INNER WALL LOCATIONS Weld or Base Material Location Fluence (n/cm 2) 18 Nozzle Shell to Inter. 7.8 x 10 Shell Circle Seam W06 Inter. Shell Vertical Seams L3 &L4 l.l X 10 19 Inter. Shell to Lower 5.0 X 10 19 Shell Circle Seam WOS Lower Shell Vertical Seams Ll &L2 l.l X 10 19 Nozzle Shell Forging ).8 X io 18 Inter. and Lower Shell Plates 5.0 X 10 19

TABLE 7 MECHANICAL PROPERTIES OF REACTOR VESSEL BELTLINE REGION BASE PLATES & FORGING Shelf' TNDT RTNDT* Energy* vs UTS Elong RA Code No. OF OF Ft-Lb Ksi Ksi . %  %

122Vl09VA1 40 40 82.5 76.5 96.5 23.25 65.45 C4326-l 10 10 87.5 67.5 88. 1 26.95 67.70 C4326-2 0 0 94 67.6 88. 1 26.95 67.70 C4415-l 20 20 82 72.0 94.6 25.00 65.90 C4415-2 0 0 86.5 69.5 91.8 25.00 64. 10

• Estimated from data in the major working direction per NRC Regulatory Review Plan Section .5.3.2.

TABLE 8 MECHANICAL PROPERTIES.OF SURVEILLANCE PROGRAM BASE MATERIAL Shelf TNDT* RTNDT Energy vs UTS Elong RA Code No. OF OF Ft-Lbs Ksi Ksi  %  %

C4326-l 10 10 115 68.00 90.47 25.75 70.85 C4415-l 20 20 103 71.80 93. 77 24.45 69.80

• Results based on Vessel Fabricators Tests

i. * , ~ ..... e e SURRY UNIT NO. 2 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluence (E > 1 Mev) at the inner su iace o~

the reactor vessel wall as of March 31, 1977 is 3.56 x 101 n/cm

• 2.) The effective full power*years (EFPY) of operation accumulated as of March 31, 1977 is 2.277 EFPY.

3.) Fabrication of the reactor vessel was performed by Babcock &Wilcox Co. and De Rotterdamsche Droogdok Mu.

4.) a.) Sketch of the reactor v~ssel showing all materials in the beltline region is shown in Figure 1.

b.) Information on each of the welds in the beltline region is shown in Tables 1 through 4.

c.) Information on each of the plates and forgings in the beltline region is shown in Tables 4 through 7.

5.) Information relative to weld and plate material included in the material surveillance program is shown in Tables 1 through 3 aDd 5 through 8.

• TABLE l IDENTIFICATION OF SURRY UNIT NO. 2 REACTOR VESSEL BELTLINE*REGION WELD MATERIAL Welding Weld Weld Wire Flux Weld Location Process *control No. ~ Reat No. ~ Lot No. Post Weld Heat Treatment Nozzle Shell to Inter. Submerged Arc L737 S4Mo 4275

• SAF89 02275 ll30°F-24HR-FC Shell Circle Seam W06 Inter. Shell Submerged Arc SA 1585 Mn-Mo-Ni 72445 Linde 80 8597 ll25+25°F-80HR-FC V"'ical Seams L3 & L4*

In er. to Lower Shell Submerged Arc R 3008 S3Mo 0227 Grau Lo LW320 ll30°F-25HR-FC Circle Seam W05 Lower Shell Submerged Arc WF 4 Mn-Mo-Ni 8Tl762 Linde 80 8597 1125+25°F-80HR-FC Vertical Seams Ll &L2* WF 8 II II II 8632 1125+25°F-48HR-FC Surveillance Weld Submerged Arc R 3008 S3Mo 0227 Grau Lo LW320 1140°~-15 1/4 HR-FC

• Welds made by B&W (all other welds made by De Rotterdamsche Droogdok Mu)

TABLE 2 CHEMICAL COMPOSITION OF REACTOR VESSEL BELTLINE REGION WELD MATERIAL Wire Flux Weight Percent e Heat No. ~

~---- -*-*----*---- Lot No. C Mn p s Si .9:_ Ni Mo Cu S4Mo 4275 SAF 89 02275 .084 1.74 035 .38 Mn-Mo-Ni 72445

• Linde 80 8597 .08 1.35 .016 .011 .43 _ .06 *51 .35 .25 S3Mo 0227 Grau Lo LW 320 Not available Mn-Mo-Ni 8Tl762 Linde 80 8597 .07 1.48 .* 017 .011 .51

• 11 .53 .39 *, 7 II II II 8632 .063 1.45 .009 .009 <53 * .61 .47 .20 Surveillance Weld . \. .09 l.51 .017 .016 .46 *10 * .56 .41 .19

.- - \ .

TABLE 3

• *Mechanical Properties of.Reactor Vessel Beltline Region Weld Material Energy *shelf Wire Flux

• NOT* at lO°'F RTNDT* Energy vs UTS Elong RA er~ Heat No." ~ Lot No. Of Ft-Lbs Of Ft-Lbs Ksi ksi  %  %

S4Mo 4275 SAF89 02275 0 75,62,65.5 0 66.69 82.62 29.0 67.6 Mn-Mo-Ni 72445 Linde 80 8597 0 50,54,51 0 81.00 S3Mo 0227 Grau Lo LW320 0 65.5,50.5,46 0 79.00 89.90 26.0 Mn-Mo-Ni 8Tl762 Linde 80 8597 0 40,31,34 0 65.06 82.25 25.0 64.9 II II II 8632 0 45,38,30 .0 71.00 85.50 25.0 Surveillance Weld 0 53,47,35 .0 91 70.85 86.50 26.4 67.8 e*Estimated

• . per NRC Standard Review Plan Section 5.3.2

~ ---*- .._ .._ __ --* ..... ----*-- ----

e e TABLE 4 MAXIMUM.END.;.QF-LIFE.FLUENCE AT.VESSEL.INNER.WALL LOCATIONS Weld or Base Mat'l Location Fluence (n/cm2)

Nozzle Shell to Inter. 7.8 X 10 18 Shell Circle Seam W06 Inter. Shell Vertical Seams L3 &L4 1.1 X 10 19 Inter. Shell to Lower 5.0 X 10 19 Shell Circle Seam W05 lower Shell Vertical Seams ll &L2 1.1 X 10 19 Nozzle Shell Forging 7.8 X 10 18 Inter. &lower Shell Plates 5.0 X 10 19

TABLE 5

!DENT! FI CATION OF REACTOR VESSEL BEL TUNE REGION BASE MATERIAL Mat 1 1 Heat Treatment Component Code No. Heat No. Spec No~ Supplier Austenitize Temper Stress Relief Nozzle Shell Forging 123V303VA1 123V303 A508 CL.2 Bethlehem 1550°F-12HR-WQ 1200°F-22HR-AC 1125°F-40HR-FC eter. Shell Plate C4208-2 C4208 A533B, CL. 1 Lukens 1600-1650°F~9HR-BQ 1200-1225°F-9HR-BQ 1125°F-60HR-FC II II II C4339-1 C4339 II II II II II Lower Shell Plate C4331-2 C4331 A533B, CL. 1 Lukens 1600-1650°F-9HR-BQ 1200-1225°F-9HR-aQ* 1125°F-60HR-FC II II II C4339-2 C4339 II II II II II Surveillance Plate C4339-1 Same as above* except stress relieved at 1140°~-15 1/4 Hr-FC TABLE 6 CHEMICAL COMPOSITION OF REACTOR VESSEL BELTLINE REGION BASE MATERIAL Height Percent

- Code No.

123V303VA1 C4208-2 C

.20

• 21 Mn

.63 l.28 p

.010

.008 s

.010

.013 Si

.24

~ 24 Ni

.73

.55 Cr

.36 Mo

.58

.55 Cb

.009

.020

. .v

.02 Cu .

• 15 C4339-1* .23 1.30 .* 012 .014 .25 .54 .54 .010 .,,

C4331-2 .23

• 1. 42 .009 .015 ~22 .60 .55 .0,.5 *12 C4339-2 .23 1.30 ** 012 .014 .25 .54 .54 .010 .11

,*Surveillance Plate .,i

TABLE 7 MECHANICAL PROPERTIES OF REACTOR VESSEL BELTLINE REGION BASE MATERIAL Shelf TNDT RTNDT* Energy* vs UTS Elong RA Code No. OF OF Ksi Ft-Lb Ksi  %

123V303VA1 30 30 103 66.37 87. 12 25.00 70.20 e C4208-2 -30 -30 93.5 64.00 85.87 26.55 67.35 C4339-l -10 30 79.0 67.00 90.25 26.95 64.70 C4331-2 -10. 10 84.0 68.75 92.25 25.80 65.25 C4339-2 -20 10 82.5 68.50 92. 12 26.60 66. l 0

• Estimated from data in the major working direction per NRG Standard Review Plan Section 5.3:2.

TABLE 8 MECHANICAL PROPERTIES OF SURVEILLANCE PROGRAM PLATE MATERIAL e TNDT* RTNDT Shelf Energy vs LITS Elong RA Code No. OF OF Ft-Lbs Ksi Ksi  %  %

C4339-l -10 11 104 68.15 91.3 26.35 69.55

e FIGURE l Identification & Location of Surry Unit No. 2 Reactor Vessel

. Beltline Region Material

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