L-77-113, Letter Re Reactor Vessel Fracture Toughness Requirements & Weld Metal Surveillance Data
| ML18227D273 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/11/1977 |
| From: | Pearson J, Robert E. Uhrig Florida Power & Light Co |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| L-77-113 | |
| Download: ML18227D273 (12) | |
Text
U.S. NUCLEAR REGULATORYCO'SSION NRCFQRM 1IIS l2 751 NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMRFR
.C?'-.
Flt.E NUMBER TO:Mr. George Lear FROMM Miami, Fl.
33101 Robert E. Uhrig DATE OF DOCUMENT 04 DATE RECEIVED 04-14-V
~~ETTE R P(ORIGINAL QCOP Y 0 NOTOR IZED P( NCLASSIFI ED PROP INPUT FORM NUMBER OF COPIES RECEIVED S(Q,~~M DESCRIPTION itr.
Ref, our 04-07-77 meeting
'egarding reactor vessel status...Advising that an Appendix G. inservice inspection of th Unit 4 reactor vessel belt-line area need not be conducted until after June 1980...and Trans The Folloving:
( 2 pages
)
ENCLOSURE Consists of.Information concerning Reactor Vessel Material Sitrveillance Program for Units 3 IIl, 4 Forged. Pressure Vessels Weld and Copper Data.....
( 23 encl rec'd )
( 6 pages
)
PIimr NAME:
TURKEY POINT UNIT"4 jcm SAFETY ASSIGNED AD:
C ASS
/ioa FOR ACTION/INFORMATION PROJECT MANAGER~
LIC ASST G FILE>>
NRC PDR
-IW-E OELD GOSSICK & STAFF MIPC HANAUER HARLESS PROJECT MANAGEMENT BOYD P
COLLINS HOUSTON PETERSON HELTEMES SKOVHOLT PDR rrt~
TIC:
NSIC:
INTERNALD SYSTEMS SAFETY HEINEMAN
.. SCHROEDER ENGINEERING MACARRY BOSNAK SIHWEIL PA K
'EACTOR SAFE ROSS NOVAK
" ROSZTOCZY CHECK AT&I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB~
REG V IE LA PDR ISTRI BUTION PLANT SYSTEMS
'EDESCO IPPOL 0
OPERATING REACTORS STELLO OPERATING TECH EISENHUT B
E ULR KSON OR STESA ERNST BALLARD YOUNGBLOOD SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J
COLLINS KREGER CONTROL NUMBER 77(a5'0 SC4 SLB0 CONSULTANTS:
ACRS CYS tN&9%NC/ E NRC FORM 195 {Z 75)
P. O. BOX 013100, MIAMI, FL 33101 FLORIDAPOWER 8 LIGHTCOMPANY April 11, 1977 L-77-113 Regulator'ffice of Nuclear Reactor Regulation Attention:
Mr.. George Lear, Chief Operating Reactors Branch 53 Division of Operating Reactors U. S. Nuclear Regulatory Commission Nashington, D. C.
20555
Dear Mr. Lear:
Re:
Turkey Point Unit 4 Docket No. 50-251 Fracture Tou hness Re uirements
~ion~
H
~
i~~" /l ~h$
On April 7, 1977, a meeting was held with members of your staff to discuss the status of the Turkey Point Unit 4 reactor vessel with respect to the fracture toughness requirements of Section V.B of Appendix G to 10 CFR 50.
At that meeting, we showed that the weld metal surveillance data for the Turkey Point Unit 3 reactor vessel represent.
not only the core midplane circumferential welds in Unit 3, but in Unit. 4 as well.
Data supporting this conclusion are attached.
The data show that the weldment samples from a Unit 3 sur-veillance capsule "T" and from both the Unit 3 and Unit 4 reactor vessels wer'e made from the same combination of filler wire heat number and welding flux lot number.,
However, the weldment samples from a Unit 4 surveillance capsule "T", although containing the same filler wire hea't number, used a different welding flux lot number. Therefore, the Unit 3 capsule, "T"
sample is more representative of the Unit,4'reactor vessel.
Irradiation data from the Unit 3 capsule was submitted to the NRC on October 19, 1976 (L-75-363).
The data exhibited a shelf energy of 58 ft-lbs at a fluence of 5.7 x 101 nvt.
Accordingly, the mid-plane circumferential vessel weld in Unit 4 can be expected to maintain a shelf energy level in excess of 50 ft-lbs at the 1/4 i location until at least June 1980 at which time this location will have received a fluence of 5.7 x 10 nvt.
PEOPLE... SERVING PEOPLE
~
4 Office of Nuclear Reactor Regulation Page Two In the October 19 letter, we also stated that additional reports were being prepared by our NSSS vendor to complete summarizing the fatigue, accident, and fracture analyses for Units 3 and 4.
We expect to receive these additional reports in draft form in about one week, and should be able to forward them on to your office in approximately 6 to 8 weeks.
The evaluation discussed above supports the conclusion we presented at the April 7 meeting that, an Appendix G inservice inspection of the Unit 4 reactor vessel belt-line area need not be conducted until. after June 1980.
Very truly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachment, cc:
Mr. Norman C. Moseley, Region II Robert Lowenstein, Esquire
FLORIDA POWER 6 LIGHT CO.
REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM TURKEY POINT UNIT NOS.
3 AND 4 FORGED PRESSURE VESSELS WELD AND COPPER DATA MELD DATA Unit
/33 Wire Flux Heat No.
Lot No.
Unit P4 Wire Flux Heat No.
Lot No.
Girth Held Surveillance Welds 71249 71249 8445 8445 71249 71249 8445 8457 SURVEILLANCE MELD METAL COPPER ANALYSIS WT.
~Sam la Original Unirradiated
.31 Re-Check
//1 Unirradiated
.33 Re-Check
//2 Unirradiated
.32 Unit 83 Vendor Spectro Chemical Laboratory Spectro Chemical Laboratory Westinghouse R6D Center
~Sam la Original Unirradiated" Irradiated Broken Charpy al Irradiated Broken Charpy 82 Irradiated Broken Charpy fjf3
.30
.27 29
.30 Unit Pr4 Vendor Spectro Chemical Laboratory Southwest Research Institute I
Southwest Research Institute Southwest Research Institute
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REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR FACILITY
'1.)
ESTIMATED MAXIMUM FLUENCE (E
>1 MEV) AT THE INNER SURFACE OF THE REACTOR VESSEL WALL AS OF 1/1/77 UNIT 83 - 5.33 x 10 tt/Ctl UNIT 84 - 4.47 x 10 N/CM I
2.)
NUMBER OF EFFECTIVE FULL POWER YEARS (EFPY)
OF OPERATION ACCUMULATED AS OF 1/1/77 UNIT 83 - 2.68 EFPY UNIT 84 - 2.17 EFPY 3.)
VESSEL FABRICATOR - BABCOCK 5 WILCOX COMPANY 4.)
A.)
LOCATION OF WELDS IN THE REACTOR VESSEL - SEE SKETCH B.)
INFORMATION RELATIVE TO WELDS IN BELTLINE REGION OF THE VESSEL 1.)
SHOP CONTROL NUMBER OR PROCEDURE QUALIFICATION NUtlBER-NOT AVAILABLEAT THIS TIME 2.)
FILLER METAL AND HEAT NUMBER - SEE TABLE 3.)
TYPE OF FLUX AND LOT NUtlBER SEE TABLE 4.)
'WELDING PROCESS - SEE TABLE 5.)
POST WELD HEAT TREATMENT UNIT 83 AND 84 1100 TO 1150'F - 48 HRS.
(B&W ltELD QUAL, TESTS) 1100 TO 1150'F 1/4 HRS.
(INTER TO LOWER SHELL WELD) 1125'F 1/4 HRS.
(SURVEILLANCE HELD)
I
(
I
~ *
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6.)
CHEMICAL COMPOSITION - SEE TABLE 7.)
DROPWEIGHT - NOT PERFORMED 5.) ASB.)
INFORMATION ON WELD MATERIAL INCLUDED IN THE VESSEL MATERIAL SURVEILLANCE PROGRAM - SEE TABLE
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TURKEY POINT UNIT NO.
3 SURVEILLANCE WELDMENT
'/8" Page Wire Heat No. 71249>
Linde 80 Flux Lot No. 8445 C
MN P
.07 1.28 0.21 Si 0.14
~
.52 CR
.17 NI MO
.57 '36 Ft-lb'nergy at 10'F
.21 45,45,46 NOZZLE SHELL TO INTER. SHELL WELD 1/8" Page Wire Heat No. 72442>
Linde 80 Flux Lot No. 8579 1/8" E8015 G Wire Heat No. 83D529
.06
.04
.73
.010
.014
.34
.01
.08 1.52
.018
.015
.42
.64
.39
.90
.48
.25 40,52 41 5/32" E8015 G Wire Heat No. 89D285 3/16" E8015 G Wire Heat No..86C127 3/16" E8015 G Wire Heat No.
78C491
.04
.04
.05
.66
.010
.020
.23
.03 1.04
.48
.76
.008
.019
.22
.02
.85
.65
.82
.009
.015
.22
.02
.76
.66
.02 INTER. SHELL TO LOWER SHELL WELD 1/8" Page Wire Heat No. 71249>
'Linde 80 Flux Lot No. 8445 I
'OWER SHELL TO DUTCHMAN WELD
.07 1.28
.021
.014
.52
.17
.57'36
.21 45,45,46 1/8";Wire Heat No. 61782 Linde 80 Flux Lot No. 8457 *
.08 1.24
.015
.013
.47
,06
.50 '54
.17 56,44,55
- Submerged Arc Weld - All others are manual metal arc used for repairs.
TURKEY POINT UNIT NO; 4 SURVEILLANCE MELDMENT 1/8" Page Mire Heat No. 71249>
Linde 80 Flux Lot No. 8457 C
.07 MN 1.42
.020
.016 Si CR
.51
.16 NI MO Ft-lb
- Energy, CU at 10'F
.55
.49
.23 38,34,52 NOZZLE SHELL TO INTER. SHELL WELD 1/8" Am.
CKC Wire Heat No. 72105>~
Linde 80 Flux Lot No. 8669
.07 1.60
.014
.011 48
.46
.40
.27 39535,44 1/8" Am.
C8C Wire Heat NO. 72442>
Linde 80 Flux Lot No. 8669
.064 1.49
.014
.017
.54
.02
.57
.41
.27 29,35,30
'/32" E8015 G Wire Heat No. 89D285
.04
.66
.010
.020
.23
.03 1.04
.48 INTER. SHELL TO LOWER SHELL WELD 1/8" Page Wire Heat No. 71249>
Linde 80 Flux Lot No. 8445
.07 1.28
.021
.014
.52
.17
.57
.36
.21 45;"45,46 I
5/32" E8015 G Wire Heat No. 78C180
.08
.67
.31
.04
.79
.51 LOWER SHELL TO DUTCHtQN WELD 1/8" Wire Heat No. 61782 Linde 80 Flux Lot No. 8457
- 1/8" E8015 Wire Heat No. 86C127
.08
,06 1.24
.015
.013
.70
.008
.015
.47
.06
.26
.50
.94
.54
.17 56,44,55
.57
- Submerged Ard Welds - All others are manual metal are used for repairs.
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