L-77-326, Responding to Letter of 5/20/1977, Letter Transmitting Information Regarding Reactor Vessel Material Surveillance Program

Responding to Letter of 5/20/1977, Letter Transmitting Information Regarding Reactor Vessel Material Surveillance Program

ML18227B789
Person / Time
Site:	Turkey Point
Issue date:	10/21/1977
From:	Robert E. Uhrig Florida Power & Light Co
To:	Lear G Office of Nuclear Reactor Regulation
References
L-77-326
Download: ML18227B789 (18)

Text

NRC FoRM 195. U.S. NUCLEAR REGULATORY CO'SSION OOCKE (2 76I ww NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Florida Power & Light Company 10/21/77 Mr. GeDrge Lear Miami, Florida DATE RECEIVED Robert Eo Uhrig 10/26/77 ELETTER 0 NO TO R I 2 E 0 PROP INPUT FORM NUMBER OF COPIES RECEIVED BG N C LASS I F I E D ABORIGINAL SCOPY 3 sic p~

DESCRIPTION ENCLOSURE g< o~< 5->-77 (fa "Turkey Point Unit Noi 3 Reactor Vessel Material Surveillance Program" "Florida Power & Light Company << Turkey Point Unit No~ 3 Reactor Vessel Radiation Surveillance Program" DISTRIBUTION FOR i~fATERIAL ON REACTOR VESSEL DATA PER R. INGRAM 5-26-77 PLANT NAIIE: . Turkey Point Units 3 & 4 RJL 10.26/77 (1>>P) (12-P)+(/1-P) ( Pg/I.. gQ./NCAA PePROb SAFETY FOR ACTION/INFORMATION BRANCH CHIEF:

ZWETZIG INTERNAL D ISTR I BUTION MIPC PANLICKI EISENHUT BUTLER GRIMES HAZELTON HOGE R. GABLE RANDALL EXTERNAL DISTRIBUTION

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. BOX 013100, MIAMI, FL 33101 FLORIDA POWER & LIGHT COMPANY October 21, 1977 L-77-326 Office of Nuclear Reactor Regulation Attention: Mr. George Lear, Chief Pt%

Operating Raactcra Branch $ 3 Division of Operating Reactors 8~i @ 4~ 8 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Lear:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reactor Vessel Material Information Your letter of May 20, 1977 contained a Request for Information regarding the Reactor Vessel Material Surveillance Program at Turkey Point Units 3 and 4. On July 6, 1977 (L-77-2ll), we agreed to supply the information by October 22, 1977. The information you requested is attached.

Very truly yours, obert E. Uhrig Vice President REU/MAS/cpc Attachment cc: Mr. James P. O'Reilly, Region II Robert Lowenstein, Esquire p-~(

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TURKEY POINT UNIT NO. 3 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluence (E,> 1 Mev) at the inneI surface of the reactor vessel wall as of March 31, 1977 is 5.65 x 10'/cm .

2.) The effective full power years (EFPY) of operation accumulated as of March 31, 1977 is 2.87 EFPY.

3.) Fabrication of the reactor vessel was performed by the Babcock and Milcox Company.

4.) a.) 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 forgings in the beltline region is shown in Tables 4 through 7.

5.) Information relative to weld and forging material included in the material surveillance program is shown in'Tables 1 through 3 and 5 trough 7.

FIGURE 1 IDENTIFICATION AND LOCATION OF BELTLINE REGION MATERIAL IN THE TURKEY POINT UNIT NO. 3 REACTOR VESSEL ~

Cl 122S146VA1 M

N O

SA-1484

'23P461VA1 Core SA-1101 123S266VAl

TABLE 1 IDENTIFICATION OF REACTOR VESSEL TURKEY POINT UNIT NO. 3 REACTOR VESSEL BELTLINE REGION WELD MATERIAL Weld Wire Flux Wel d Weld Wel d Post Weld Location Process Control No. ~Te Heat No. ~T e Lot No. Heat Treatment Nozzle Shell to Submerged Arc SA-1484 Mn Mo Ni 72442 Linde 80 8579 1100-1125'F-48 Hrs-FC Inter. Shell Inter. Shell to Submerged Arc SA-1101 Mn Mo Ni 71249 Linde 80 8445 1100-1125'F-48 Hrs-FC Lower Shell I

Surveillance Weld 'Submerged Arc SA-1101 Mn Mo Ni 71249 Linde 80 8445 1125'F-10 1/4.Hrs-FC TABLE 2 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION WELD MATERIAL Weld Wire Flux Wei ht Percent We.l d Control No. ~Te Heat No. ~Te Lot No. C P S Mn Si Mo Ni Cr Cu SA-1484 Mn Mo Ni 72442 Linde 80 8579 ,08 .018 .015 1.52 . 42. .39 .66 .06 SA-1101 Mn Mo Ni 71249 Linde 80 8445 .07 .021 .014 1.28 .52 .36 .57 .17 .21 Surveillance Weld .076 .011 .018 1.26 .66 42 57 14 31

CC TABLE 3 .

MECHANICAl PROPERTIES OF VESSEL BELTLIHE REGION WELD MATERIAL Weld Wire . Flux Energy Shel f Weld HDT* at 10'F NDT Energy YS UTS Elong.

Control No. ~Te Heat No. ~Te Lot Ho; 'F ft-1 b oF ft-lb ksi ksi SA-1484 Mn Mo Ni 72442 Linde 80 8579 0 40,52,41 0 84 00 SA-1101 Mn Mo Hi 71249 Linde 80 8445 0 45,45,46 -

0 68. 63 84.26 28.5 Surveillance Weld 0 26,37,25 3 64.5 76.30 92.35 24.9

• Estimated Per NRC Standard Review Plan Section 5.3.2.

I TABLE 4 MAXIMUM END-OF-LIFE FLUENCE AT VESSEL INNER WALL LOCATIONS Fluence Shell For in or Weld Location '/cm Nozzle Shell Forging ssxiO" Nozzle Shell to Inter. Shell Circle Seam 9.5 x 10 Inter. Shell Forging 6.3 x 10 Inter. Shell to Lower Shell Circle Seam 6.3 x 10 Lower Shell Forging 6.3 x 10

TABLE 5 IDENTIFICATION'OF 'VESSEL'BELTLINE REGION 'SHELL FORGING MATERIAL Heat Treatment Material

~Com onent ~Fi N. tl tN. ~5 ~So lier Austeni ti ze ~Tem er Stress Relief Nozzle Shell -122S146VA1 122S146 .A508 CL 2 Bethlehem 1550'F-ll HR-Wg 1220'F-22 HR-AC 1125'F-40 HR-FC Inter. Shell 123P461VAl 123P461 A508 CL 2 Bethlehem 1550'F-13 HR-Wg 1210'F-18 HR-AC 1125'F-40 HR-FC Lower Shell 123S266VAl 123S266 A508 CL 2 - Bethlehem 1550'.F-13 HR-Wg -

1210'F-18 HR-AC .

1125'F-40 HR-FC Surveillance Material - Inter. and Lower Shell as Above Except Stress Relieved by Westinghouse 1125'F-10 1/4 H TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL For in No. C Mn P S Si Mo Cr V Co Cu 122S146YA1 .22 .64 .010 .013 .25 .59 .35 .03 .014 123P461VA1 .20 .65 .010 .010 .26 .70 .62 .40 .02 .011 .058*

-123S266VA1 .20 .62 .010 .008 .20 .67 .59 ..38 ;02 .016 .079*

"Analyses Performed by Westinghouse as Part of Surveillance Program

TABLE 7 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Shel f*

TNDT RTNPT Energy YS UTS Elong. RA For in No. oF oF ft-lb ksi ksi x 122S146VA1 50 . 50 98.5 64.0 85.5 26.0 69.95 123P461VA1 40 40 98.5 68.0 90.7 25.0 68.35 123S266VAl 30 30 117.5 58.1 83.4 28.0 71.40 123P461VA1 . 40 94.0 64.4 96.2 26.1 70.35 Surveillance 123S266VA1 30 96.0 57.4 92.6 26.1 70.70 Test Data.

• Estimated From Test Data in the Major Working Direction Per NRC Standard Review Plan Section 5.3.2

TURKEY POINT UNIT NO. 4 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluen:e (E > 1 Mev) of the jnner surface of the reactor vessel as of March 31, 1977 is 4.79 x 101~ n/cm".

2.) The effective full power years (EFPY) of operation accumulated as of March 31, 1977 is 2.43 EFPY.

3.) Fabrication of the reactor vessel was performed by the Babcock and Hilcox Co.

4.) a.) A sketch of the reactor vessel 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 forgings in the beltline region is shown in Tables 4 through 7.

5.) Information relative to weld and forging material included in the material surveillance program is shown in Tables 1 through 3 and 5 through 7.

FIGURE IDENTIFICATION AND LOCATION OF 1

t BELTLINE REGION MATERIAL IN'THE TURKEY POINT UNIT NO. 4 REACTOR VESSEL

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124S309VA1 Wf 70 5 WF 67 123P481VA1 Core SA-1101 122S180VA1

TABLE 1 IDENTIFICATION OF REACTOR VESSEL TURKEY POINT UNIT N0.4 REACTOR VESSEL BELTLINE'REGION'WELD MATERIAL Meld Mire Flux Meld Weld Meld Post Weld Location Process Control No. ~T e Heat No. ~T e Lot No. Heat Treatment Nozzle Shell to Submerged Arc NF 70- Mn-Mo-Ni 72105 Linde 80 8669 1100-1150'F-48 HR Inter. Shell Submerged Arc WF-67 Mn-Mo-Hi 72442 Linde 80 8669 1100-1150'F-48 HR Inter Shell to Submerged Arc SA-1101 ttn-Ho-Hi 71249 Linde 80 8445 1100-1150'F-48 HR Lower Shell Surveillance Weld Submerged Arc SA-1094 Mn-Mo-Ni 71249 Linde 80 8457 1125'F-10 1/4 HR-FC TABLE 2 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION WELD t@TERIAL Meld Mire Flux Wei ht Percent Meld Control No. ~T e Heat Ho. ~Te Lot No. C Mn P S Si Ni Mo Cr Cu MF-70 Mn-tIo-Ni 72105 Linde 80 8669 .070 1.60 .014 .011 .48 .46 .40 - .27 MF-67 Mn-Mo-Ni 72442 Linde 80 8669 . 064 1. 49 . 014 . 01 7 . 54 .. .57 .41 .02 SA-1101 Mn-Mo-Hi 71249 Linde 80 8445 .070 -

1.28 .021 ,014 .52 . 57 .36 .17 .21 SA-1094 71249 Linde 80 8457 .070 1.42 .020 .016 .51 .55 .49 .16 .23 Surveillance Meld .098 1.44 .014 .011 .50 .60 .36 .14 .30

d

'f

TABLE 3 MECHANICAL PROPERTIES'OF VESSEL'ELTL'INE'REGION WELD'MATERIAL Weld Wire Flu x

• Energy RT

'* Shel f Weld NDT at 10'F NDT Energy YS UTS Elong. RA Control No. ~Te Heat No. ~Te Lot No. F ft-lbs 'F ft-lb ksi ksi x x WF-70 Mn-Mo-Ni 72105 Linde 80 8669 0 39,35,44 0 69.0 85.5 25. 8 64.7 WF-67 Mn-Mo-Ni 72442 Linde 80 8669 0 29,35,30 0 64.0 81.5 31.3 65.8 SA-1101 Mn-Mo-Ni 71249- . Linde 80. 8445 0 45,45,46 0 68. 6 84. 3 28.5 SA-1094 Mn-Mo-Ni 71249 Linde 80 8457 38,34,52 0 72.5 86.0 26.7 65.1 Surveillance Weld 0 29,39,36 0 66 70.2 '1.3 23.8 6C 7

• Estimated Per NRC Standard Review Plan Section 5.3.2 TABLE 4 MAXIMUM END-OF-LIFE FLUENCE AT'VESSEL INNER WALL LOCATIONS Fluence Shell For in or- Weld Locations n/cm Nozzle Shell Forging 9.5 x 10 Nozzle Shell to Inter. Shell Circle Seam 9.5 x 1.0 19 Inter. Shell Forging 6.3 x 10 Inter. Shell to Lower Shell Circle Seam 6.3 x 10 Lower Shell Forging 6.3 x 10

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TABLE 5

'IDENTIFICATION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Heat Treatment

~Ct Nozzle Shell

~Fi N 124S309VA1

. II t 124S309 II Material

~Sec.

A508 CL 2

~Su Bethlehem lier Austenitize 1550'F-15 HR-Wg

~Tem er 1220'F-22 HR-FC Stress Relief 1125'F-40 HR-FC Inter. Shell -123P481VAl 123P481 A508 CL 2 Bethlehem 1550'F-10 1/4HR-Wg 1210'F-18 HR-AC 1125'F-40 HR-FC Lower Shell 12S180VAl 122S180 A508 CL 2 Bethlehem 1550'F-10 1/2 HR-Wg 1200'F-18 HR-FC 1125'F-40 HR-FC Surveillance Material - Inter. and Lower Shell as Above Except Stress Relieved by Westinghouse 1125'F-10 1/2 HR- C TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Wei ht Percent For in No. Si Ni Mo Cr Co Cu 124S309VA1 .20 .60 .010 .012 .27 .70 .57 .33 .02 .008 123P481VA1 .21 .65 .010 .011 .25 .69 .59 .33 ..02 .011 122S180VA1 .22 .60 .010 .009 .23 .74 .60 .34 .02 .013 123P481VAl* .22 .67 .010 .009 .71 .56 .33 .002 .017 .054

..70

.20'22S180VA1*

.21 .67 .011 .009 .23 .56 .31 .001 .015 .056

• Surveillance Material Analysis Performed by Westinghouse.

TABLE 7 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Shel f*

Energy Elong.

For in No.

NDT OF NDT oF ft-1 b YS ksi UTS ksi t RA x

124S309VA1 40 '0 101 66.1 89.5 26.2 69. 3 123P481VA1 50 50 93 71.0 93.2 25.0 67. 2 122S180VA1 40 40 97 72.2 92.7 24.0 66.9 123P481VA1 50 68. 5 90.1 25.4 68.1 Surveillance 122S180VA1 40 70.8 91.5 24.2 67.8 Test Data 86

• Estimated From Test Data in the Major Working Direction Per NRC Standard Review Plan Section 5.3.2