ML20003B775
| ML20003B775 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/17/1981 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8102250480 | |
| Download: ML20003B775 (14) | |
Text
.
SOUTH CAROLINA ELECTRIC & gas COMPANY POST OF,lCE 301 764 CotuMelA, South CAROLINA 29218 va dsE."'.ISI'.Ne.,~,
February 17, 1981 NUCttan Opse.tes Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Virgil C. Summer Nuclear Station Response to FSAR Questions 121.19, 121.23, 121.28, 121.29 I
Docket No. 50/395 l
Dear Mr. Denton:
South Carolina Electric and Gas Company, acting for itself and as agent for the South Carolina Public Service Authority, submits responses to FSAR questions 121.19, 121.23, 121.28 and 121.29. These. responses will be included in FSAR Amendment 24.
If you have further questions, please let us know.
Very truly yours, f
f T. C. Nichols, Jr.
NEC:TCN:pj
Enclosures:
cc:
V. C. Summer _.w/o enclosures G. H. Fischer_w/o enclosures T. C. Nichols, Jr. w/o enclosures E.-H. Crews, Jr..
O.'W.~Dixon, Jr.
D. A. Nauman O..S. Bradham A. A. Smith A.
R. Koon R. B.'Clary J.,B.
Knotts, Jr.
J.'L. Skolds-B. A. Bursey
'NPCF/Whitaker-g gy", ""! ~
File 3
ms
-8102250ASO i
mn e
}-
N0liF5ln)lhk,l.
- 4
121.19 In order to dmonstrate ccrrpliance with Appendix G,10 CFR Part 50, Paragraph IV.A.3, provide the irrpact test results required by A%E Code Paragraph NB-2333 for all ferritic bolting materials used in the reactor coolant pressure boundary.
RESPONSE
Ferritic bolting materials used in the reactor coolant pressure boundary are fabricated in accordance with the follwing addenda of the A%E Code Section III, all of which predate-the issuance of 10CFR50 Appendix G.
Reactor Vessel 1971 Edition, through Stmner 1971 (closure head bolts)
Addenda
. Steam Generator-1971 Edition, thru Stmrer 1971 (marway bolts)
Addenda Pressurizer 1971 Edition, thru Stmner 1971 (manway bolts)-
Addenda Peactor Coolant Pump 1971 Edition, thru Stmner 1972 f(main flange and seal' Addenda housing bolts)
- 'Ihese materials ocuply with the fracture toughness requirments of the applicable code. Ihese requirements are ccrnpared to.the requirements of 10 CFR Part 50
-Appendix G below.
J e
s.
Test Tttperature ft. lbs.
MLE 1971 Edition, Su:mer 1971 35 Mdendum 0
1971 Edition, Strrer 1972 40 F 25 10 TR 50, Appendix G,1980 Iower of preload or 45 25 service ta p.
(usuallyc50' F)
The fracture toughness data available for these materials are shown in Table 121.19-1.
i
V. C. Summer Plant TABLE 121.19-1 Charpy Lateral V-Motch Expansion Component Test Number Test Temp OF Material (PT-LB)
(MILS)
RV Closure Heat 80751 10 A540-824 50-51-52 31-30-32 Head Studs Bar 66 Bar 66-1 10 AS40-B24 55-54-56 35-30-35 Bar 70 10 A540-B24 57-56-57 36-33-35 Bar 70-1 10 A540-B24 52-51-50 28-28-29 Bar 75 10 A540-B24 48-51-48 32-33-28 Bar 75-1 10 A540-B24 51-52-53 29-32-32 Bar 81 10 AS40-B24 50-47-51 28-26-27 Bar 81-1 10 A540-B24 54-55-54 32-31-30 St. Gen.
To 4051 4 40 SA193Gr-B7 38-40-35-40 Primary Manway Bolts To 3956 6: 40 SA193Gr-B7 39-37-33-39 Pressurizer To 4560 40 SA193Gr-B 89-86.5-86.5 59-60-59 Manway Bolts Reactor Coolant Heat Pump Seal 8082109 10 SAS40Gr-B-23 72-74.5-72.5 50-51-49 Housing Bolts Reactor Coolant Heat 35 SAS40 73, 74, 75 45-47-45 Pump Main 123123 B24CL4 79, 81, 81 46-48-49 Flange Bolts Lot 1 68, 74, 71 40-45-41 83, 85, 81 51-44-43
1" ELE 121.19-1 (Continued)
Iateral Charpy V-Notch Expansion Caponent Test Number Test Tmp F Material (PT-LB)
(MILS)
O Reactor Coolant Heat 35 SA 540 77, 76, 76 51, 47, 49 Pump Main 123123 B24 c14 75, 70, 70 44, 41, 41 Flange Bolts Lot 3 58, 58, 60 38, 37, 37 Reactor Coolant Heat 35 62, 63, 62 39, 37, 37 Pump Main 123123 70, 68, 66 42, 41, 39 Flange Bolts Lot 7 Reactor Coolant Heat 35 63, 63, 62 33, 37, 34 Puap Main 123123 64, 69, 65 33, 42, 39 Flange Bolts Iot 8 Reactor Coolant Heat 35 62, 62, 63 35, 37, 36 Pump Main 123123 65, 64, 64 38, 38, 38 Flange Bolts Iot 9
.w m-m m m-
121.23
%e response to Question 121.13, concerning the fracture toughness requircrnents of certain high strength steels, is not adequate. To provide acceptable information, we require that:
(1)
We applicant supply the specific fracture tcughness test results, for those tests required by Appendix G to 10 GR Part 50 and detailed in Question 121.13, for the actual SA-533 Grade A Class 2 material used in the V. C. Summer steam generators and pressurizer; and (2) We generic fracture toughness requirements of high streryth materials, required by Paragraph I of Appendix G and detailed in Question 121.13, be satisfied. Westinghouse Topical Report WCAP-9292_has been referenced by the applicant as the information necessary to fulfill these generic requirements.
However, our review of this report is still open and our acceptance of this report is contingent upon adequate responses to questions submitted by the staff to Westinghouse.
RESPCNSE:
-(1)
-SA-533, Grade A, Class 2 material was used in the Virgil C. Summer pressurizer.
(SA-533, Grade A, Class 2 caterial was not used in primary side (BCPB) pressure retaining applications of the Virgil C. Sumner steam generators.) We actual fracture toughness data for' the SA-533, Grade A, Class 2 material in the
- pressurizer are tabulated in Table 121.23-1.
(2)
%c adequacy of the fracture toughness properties of SA-533, Grade A, Class.2 material has been doctrnented in WCAP-9292, entitled " Dynamic Fracture Toughness of
' ATE SA-508, Class 2a, and ASME SA-533, Grade A, Class 2 Base and Heat Affected
Zono bhterial and Applicable Weld Metals". Pesponses to hTC Questions on NCAP-9292 were transmitted to the NPC via IS 'HM-2312, dated Septurber 18, 1980 (to Mr. James R. Miller, NPC, Division of Project bbnagatent, from Mr. T. M.
Andarson, Westinghouse, Nuclear Safety Department).
L l
. = _ _ -
TABLE 121.2321-j FFRmJRC 'ICUGHNESS DA'IA mR SA-533 GRADE A CIASS 2 MATERIAL Charpy Lateral Orientation Test Conpanent Test V-Notch Expansion (Irngitudinal (L)
Tegerature Tndt Rindt (O )
(O )
(O )
Ccmponent
.Part Ntznber (FT.-IB)
(IN.)
or Transvt.:ise (T))
F F
F Pressurizer Iner Head 703639 82, 85, 80
.074,.071,.068 T
70 10 10
'(1581) 90, 90, 78
.063,.072,.072 L
_10 Pressurizer Upper Head 703625 53,'54, 53
.052,.051,.048 T
70 10 10
'(1581) 75, 74, 91
.060,.070,.071 L
10 Pressurizer Shell Barrel 103328 78, 82, 81
.056,.057,.049 L
10 (1581)-
' Pressurizer.Shell Barrel '703704 65, 59, 56
.051,.056,.059 T
70 0
10
_ (1581) -
Pressurizer' Shell Barrel 703606 78, 78,~85
.065,.071,.066 T
70 10 10
-(1581)
- . Drop weight test results not available.
121.28 High Strength ferritic steel, SA-533 Class 2, has been used in the pressurizer. %c specific canponent parts include the lo.er head, upper head, and three shell barrels. Identify the high strength welds joining these cxxnponent parts ard supply the impact energy data necessary to deonstrate their fracture toughness adequacy as required by Paragraph 1, Appendix G, 10 CFR Part 50.
-FESPONSE:
We high strength welds joining the ccrponent parts of the pressurizer are the four girth welds joining the upper head, three shell barrels, aryl the lower head, and the three longitudinal welds joining the three sections of the shell barrels.
The various weld and flux combinations used in these welds are listed in Table 121.28-1 along with the appropriate fracture toughness test inforration.
r y_.
'IRBLE 121028-1 Test Numbers Drop Wt.
Charpy V-Notch ~
Iat. Expansion Test O.
Material Weld Process Electrode Flux. @ 200F.
Ft.-Ib.
mils
'D:mp.oF RTndt F
SFA 5.18 SN4
~2755 3970 2 NB' 130-127-134 59-57-61 70 10 SFA 5.18 SN1 3864 3970 2 NB 121-111-130 80-71-73 70 10 SFA 5.18 SN1 4113 4553 2 NB 111-114-112 84-78-79 70 10 SFA 5.18 SNV 3882 4080 2 NB 126-126-124 61-61-52 70 10
- SFA 5.18 SAW 4098 4553 2 NB 108-106-106 60-78-78 70 10 SFA 5.18 SNV 2881 4080 2 NB 120-138-144 93-92-64 70 10 SFA 5.18 SNV 2755 3561 94-94-87 66-66-61 10 10 SFA 5.5-SMAW 3418 2 NB 210-257-219 91-71-80 70 10
' SFA 5.5 SI M 3991 2 NB 73-78-57 57-62-41 70 10 SFA 5.5 SMAW 3415 2 NB 82-84-84 61-67-61 70 10
~SFA 5.5 SMAW 3419 2 NB 91-92-101 70-71-76 70 10 SFA 5.5.
SMNV 3401 Average 65 10 30 SFA 5.5 SMNV 4507 2 NB 80-79-74 67 ~T3-64 70 10 SFA 5.5
.SMN1 3993 2 NB 102-104-100 81-77-80 70 10 SFA 5.5 SMN4 4503 2 NB 52-75-56 43-61-51 70 10 SFA 5.5 SMAW 2165 Average 52 10 30 M7IE: Where cmplete Charpy or drop weight data was not obtained, RTndt was estimated in accordance with the guidelines of MrEB 5-2 and Westinghouse NCAO-7924A, " Basis for IIeat-Up and CooldOsnr Curves".
O 121.29' Paragraph IV.A.2a requires the applicant to calculate a reference tmperature, RI}g, for all ferritic reactor coolant pressure boundary materials in the reactor vessel, pressurizer, and steam generators. 'Ihis includes base, weld and weld heat-affected zone metal. Supply the impact test results for any we.h ferritic material in the primary side of the steam generator.
RESPOtEE:
'Ihef ferritic material in the primary side of the steam generators includes the following: channel head casting, tube sheet, manway covers and marreay cover bolts.
Fracture toughness data for channel heat casting, tube sheet and marreay covers are shown in Table 121.29-1; data for the manway cover bolting is shown in Table 121.29-2; and data for the channel head casting to tube sheet weldment is given in Table 121.29-3. Note that no datun is available for the heat affected zone of-the weldment.
-,,,; 5.
n g.
Y
- V.' C. = Sumer Plant TABIE 121.29-1 Cmponent Conponent Test Material 01arpy V-Notch Lateral Test Tndt Rr dt*
n Equipnent Part Number Specification (Fr.-IB)
Dqunsion Tmp.. (OF)
(O )
F (O.)
(MIIS)
F Steam Generator Channel Head'
'I03599 SA216 gr WCC 51-64-59 10 0
0 (1571)'
Casting 37.5-36-39 Tube Sheet
'IO2960 SA508 cl. 2 55-72-65 41-53-52 10 10 95-61-78 68-45-29 Marway Covers
'IO3729 SA533 gr. A cl.1 40-46-48 42-36-41 70 47-47-44 43-41-41 10 40 53-51-52 51-47-49 100 52-53-54 49-52-52 Steam Generator Channel Head T03591 SA 216 gr NOC 63-61-69 55-55-59 10 10 (1572)
Casting.
79-71-63 65-59-63 t
Tube Sheet
'IO2935 SA 508 cl. 2 82-76-43 57-55-30 10 30 34-50-46 24-37-34 Manway Covers
'IO3729 (Same as Steam Generator 1571)
- Steam Generator Channel Head TO2999 SA 216 gr NCC 46-47-47 10 10 10 (1573)
Casting 76-78-85 Tube Sheet
'IO2942 SA508 cl 2 69-70-50 48-47-37 10 30 68-28-63 50-21-47 i
Manway Covers
'IO3729 -
(Same as Steam Generator 1571)
Where emplete Charpy or drop weight data was not cbtained, Rrndt was estimated in accordance with the Guidelines of MIEB 5-2 and Westinghouse' NCAP-7924A, " Basis for Heat-Up and Cooldown Curves".
i 5
1 i
+
7-
..--.4
V. C. Su:mer Plant TABLE 121.29-2 S7EN4 GDEPA70R PRLVARI WJ7/AY BOL75 Charpf V-Notch Lateral Dcpansion Test No.
Test Tarp. OF.
Material PT.-LBS.
MILS To 4251 1 40 SA 193 Gr-B7 38-40-35-40 To 3956 6 40 SA 193 Gr-B7 39-37-33-39 1
l I
l 2
V. C. ' Simner Plant -
TABLE 121.29-3.
~
QWNEi HEAD 70 7UBESIIEET WEIDETr Test Ntznbers Drop Wt. Charpy V-Notch-Lat. Expansion Test Tmp. RTndt l
- Material; Weld Process
. Electrode' Flux
@ 200F Pr. LB.
MIIS OF.
OF i-FA'5.18-
.'SAW 2754 1341 2 NB 77-59-81 63-46-68.
70 10 FA 5.18 SAW 2755 1341 2 NB 83-83-82 70-70-68 70 10 SFA 5.5 St M 2261 Average 83 10 10 i'
SFA 5.5.
'3420 2 NB 92-108-114.
68-80-83 70 10 i
~ SFA 5'. 5'-
SMAW 3407 Average 30 10 30 l
SFA 5.5 SEM -
3396 Average 45 10 30 t
.SFA 5.5 ~
SMAW 3422 2 NB'
-112-116-115 87-82-85 70 10 SFA 5.5 SMAW 3417 2 NB 125-126-120 88-83-78 70 10 2-I h
When emplete Charpy or drop weight data was not obtained, Erndt was estimated in accordarre with the l
Guidelines of cITEB-5-2 and Westinghouse NCAP-7924, " Basis for IIcatup and Coldown Curves".
i.
[
I I
L m
~-