L-77-326, 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.
(2 76I U.S. NUCLEAR REGULATORYCO'SSION OOCKE ww NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO:
Mr. GeDrge Lear FROM:
Florida Power
& Light Company Miami, Florida Robert Eo Uhrig DATE OF DOCUMENT 10/21/77 DATE RECEIVED 10/26/77 ELETTER ABORIGINAL SCOPY DESCRIPTION 0 NO TO R I2 E 0 BG NC LASS I F I E D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED 3 sic p~
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)
FOR ACTION/I SAFETY BRANCH CHIEF:
(12-P)+(/1-P)
( Pg/I..
gQ./NCAA PePROb NFORMATION ZWETZIG INTERNALD ISTR I BUTION MIPC PANLICKI EISENHUT BUTLER GRIMES HAZELTON HOGE R. GABLE RANDALL
~
/
EXTERNALDISTRIBUTION
yl t,
~t
. BOX 013100, MIAMI, FL 33101 FLORIDAPOWER & LIGHTCOMPANY October 21, 1977 L-77-326 Office of Nuclear Reactor Regulation Attention:
Mr. George Lear, Chief Pt%
Operating Raactcra Branch
$ 3 8~i 4~
8 Division of Operating Reactors 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-~(
aa g
aa Qp ',j(f PEOPLE... SERVING PEOPLE
> a:fs4C,i 4<<,".'i ri
'I 99 8 Q 9E.g0 JJ,6l (h ~ f 8 I ~
lH3liilJUQ u3AI.- J3tl
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 MNO 122S146VA1 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 Location Nozzle Shell to Inter. Shell Weld Wel d Process Control No.
~Te Submerged Arc SA-1484 Mn Mo Ni Post Weld Heat No.
~T e
Lot No.
Heat Treatment 72442 Linde 80 8579 1100-1125'F-48 Hrs-FC Inter. Shell to Lower Shell Submerged Arc SA-1101 Mn Mo Ni 71249 Linde 80 8445 1100-1125'F-48 Hrs-FC 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 Flux Weld Wire We.l d Control No.
~Te Heat No.
~Te SA-1484 Mn Mo Ni 72442 Linde 80 Wei ht Percent Lot No.
C P
S Mn 8579
,08
.018
.015 1.52 Si
. 42.
.52 SA-1101 Mn Mo Ni 71249 Linde 80 8445
.07
.021
.014 1.28 Mo Ni Cr Cu
.39
.66
.06
.36
.57
.17
.21 Surveillance Weld
.076
.011
.018 1.26
.66 42 57 14 31
TABLE 3 MECHANICAl PROPERTIES OF VESSEL BELTLIHE REGION WELD MATERIAL CC Weld Wire Flux Energy Weld HDT* at 10'F Control No.
~Te Heat No.
~Te Lot Ho;
'F ft-1 b SA-1484 Mn Mo Ni 72442 Linde 80 8579 0
40,52,41 NDT oF 0
SA-1101 Mn Mo Hi 71249 Linde 80 8445 0
45,45,46 0
Shel f Energy ft-lb YS ksi
- 68. 63 UTS Elong.
ksi 84 00 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 Shell For in or Weld Location Nozzle Shell Forging Nozzle Shell to Inter. Shell Circle Seam Inter. Shell Forging Inter. Shell to Lower Shell Circle Seam Lower Shell Forging Fluence
'/cm ssxiO" 9.5 x 10 6.3 x 10 6.3 x 10 6.3 x 10
TABLE 5 IDENTIFICATION'OF 'VESSEL'BELTLINE REGION 'SHELL FORGING MATERIAL
~Com onent Nozzle Shell Material
~Fi N.
tl tN.
~5
-122S146VA1 122S146
.A508 CL 2 Austeni tize
~So lier Bethlehem 1550'F-ll HR-Wg Heat Treatment
~Tem er 1220'F-22 HR-AC Inter. Shell Lower Shell 123P461VAl 123P461 A508 CL 2 Bethlehem 1550'F-13 HR-Wg 1210'F-18 HR-AC 123S266VAl 123S266 A508 CL 2
- Bethlehem 1550'.F-13 HR-Wg 1210'F-18 HR-AC Surveillance Material - Inter.
and Lower Shell as Above Except Stress Relieved by Westinghouse Stress Relief 1125'F-40 HR-FC 1125'F-40 HR-FC 1125'F-40 HR-FC 1125'F-10 1/4 H TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL For in No.
122S146YA1 123P461VA1
-123S266VA1 C
.22
.20
.20 Mn
.64 P
.010
.65
.010
.62
.010 S
.013
.010
.008 Si
.25
.26
.20
.70
.67 Mo
.59
.62
.59 Cr
.35
.40
..38 V
.03
.02
- 02 Co
.014
.011
.016 Cu
.058*
.079*
"Analyses Performed by Westinghouse as Part of Surveillance Program
TABLE 7 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL For in No.
122S146VA1 123P461VA1 123S266VAl 123P461VA1 123S266VA1 40 30 40 30 40 30 TNDT RTNPT oF oF 50 50 98.5 117.5 94.0 96.0 68.0 58.1 64.4 57.4 Shel f*
Energy YS ft-lb ksi 98.5 64.0 90.7 83.4 96.2 92.6 25.0 28.0 26.1 26.1 UTS Elong.
ksi 85.5 26.0 RA x
69.95 68.35 71.40 70.35 70.70 Surveillance 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.
t FIGURE 1
IDENTIFICATION AND LOCATION OF BELTLINE REGION MATERIAL IN'THE TURKEY POINT UNIT NO.
4 REACTOR VESSEL
~ ~
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 Location Nozzle Shell to Inter. Shell Weld Meld Process Control No.
Submerged Arc NF 70-Submerged Arc WF-67
~T e
Heat No.
~T e
Lot No.
Mn-Mo-Ni 72105 Linde 80 8669 Mn-Mo-Hi 72442 Linde 80 8669 Post Weld Heat Treatment 1100-1150'F-48 HR 1100-1150'F-48 HR Inter Shell to Lower Shell Submerged Arc SA-1101 ttn-Ho-Hi 71249 Linde 80 8445 1100-1150'F-48 HR 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 Meld Control No.
~T e
Heat Ho.
MF-70 Mn-tIo-Ni 72105 Flux Wei ht Percent
~Te Linde 80 Lot No.
C Mn P
S Si 8669
.070 1.60
.014
.011
.48 Ni Mo Cr Cu
.46
.40
.27
.57
.41
.02
. 57
.36
.17
.21
.55
.49
.16
.23 SA-1094 Surveillance Meld 71249 Linde 80 8457
.070 1.42
.020
.016
.51
.098 1.44
.014
.011
.50
.60
.36
.14
.30 MF-67 Mn-Mo-Ni 72442 Linde 80 8669
. 064
- 1. 49
. 014
. 01 7
. 54 SA-1101 Mn-Mo-Hi 71249 Linde 80 8445
.070
- 1.28
.021
,014
.52
d
'f
TABLE 3 MECHANICAL PROPERTIES'OF VESSEL'ELTL'INE'REGION WELD'MATERIAL Weld Wire Flu Weld Control No.
~Te Heat No.
~Te WF-70 Mn-Mo-Ni 72105 Linde 80 x
NDT Lot No.
F 8669 0
'F 39,35,44 0
Shel f Energy ft-lb YS ksi 69.0 UTS ksi 85.5 Elong.
x
- 25. 8 RA x
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 Surveillance Weld 0
- Estimated Per NRC Standard Review Plan Section 5.3.2 29,39,36 0
SA-1094 Mn-Mo-Ni 71249 Linde 80 8457 38,34,52 0
72.5 86.0 26.7 66 70.2 '1.3 23.8 65.1 6C 7
TABLE 4 MAXIMUMEND-OF-LIFE FLUENCE AT'VESSEL INNER WALL LOCATIONS Shell For in or-Weld Locations Nozzle Shell Forging Nozzle Shell to Inter. Shell Circle Seam Inter. Shell Forging Inter. Shell to Lower Shell Circle Seam Lower Shell Forging Fluence n/cm 9.5 x 10 9.5 x 1.0 6.3 x 1019 6.3 x 10 6.3 x 10
TABLE 5
'IDENTIFICATION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL e
~
~Ct
~Fi N.
II t II Nozzle Shell 124S309VA1 124S309 Material
~Sec.
A508 CL 2 Heat Treatment
~Su lier Austenitize
~Tem er Bethlehem 1550'F-15 HR-Wg 1220'F-22 HR-FC Inter. Shell Lower Shell
-123P481VAl 123P481 A508 CL 2 Bethlehem 1550'F-10 1/4HR-Wg 1210'F-18 HR-AC 12S180VAl 122S180 A508 CL 2 Bethlehem 1550'F-10 1/2 HR-Wg 1200'F-18 HR-FC Surveillance Material - Inter.
and Lower Shell as Above Except Stress Relieved by Westinghouse Stress Relief 1125'F-40 HR-FC 1125'F-40 HR-FC 1125'F-40 HR-FC 1125'F-10 1/2 HR-C TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Wei ht Percent For in No.
124S309VA1 123P481VA1 122S180VA1 123P481VAl*
.20
.21
.22
.22
.60
.65
.60
.67
.010
.010
.010
.010
.012
.011
.009
.009 Si
.27
.25
.23
.20'22S180VA1*
.21
.67
.011
.009
.23
- Surveillance Material Analysis Performed by Westinghouse.
Ni
.70
.69
.74
.71
..70 Mo
.57
.59
.60
.56
.56 Cr
.33
.33
.34
.33
.31 Co
.02
.008
..02
.011
.02
.013
.002
.017
.001
.015 Cu
.054
.056
TABLE 7 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL For in No.
124S309VA1 123P481VA1 122S180VA1 123P481VA1 122S180VA1 NDT NDT OF oF 40 '0 50 50 40 40 50 40 Shel f*
Energy ft-1 b 101 93 97 86 YS ksi 66.1 71.0 72.2
- 68. 5 70.8 UTS ksi 89.5 93.2 92.7 90.1 91.5 Elong.t 26.2 25.0 24.0 25.4 24.2 RA x
- 69. 3
- 67. 2 66.9 68.1 67.8 Surveillance Test Data
- Estimated From Test Data in the Major Working Direction Per NRC Standard Review Plan Section 5.3.2