ML20247A308
| ML20247A308 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/05/1989 |
| From: | Elliot B Office of Nuclear Reactor Regulation, NRC OFFICE OF THE GENERAL COUNSEL (OGC) |
| To: | |
| Shared Package | |
| ML20247A265 | List: |
| References | |
| OLA-4, NUDOCS 8909120089 | |
| Download: ML20247A308 (15) | |
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UNITED STATES OF AMERICA-o-
1:
NUCLEAR' REGULATORY COMMISSION
- BEFORE THE ATOMIC SAFETY AND LICENSING' BOARD L,
-In the Matter of Docket Nos. 50-250 OLA-4
' FLORIDA POWER AND LIGHT 50-251 OLA-4 COMPANY p
(Turkey Point Plant, Units.3 and 4)
(P/TLimits) 1
' AFFIDAVIT OF BARRY J. ELLIOT I, Barry J. Elliot, being duly sworn, state as follows:
I'am employed as a Materials Engineer in the Materials and Chemical Engineering' Branch.. Division of Engineering and Systems Technology, Office of Nuclear. Reactor Regulation of the U.S. Nuclear Regulatory Commission.. I have provided responses to Interrogatories 1, 3, 4' 6, 7, 8, 9,:10 12, 13, 16, and'17.
I' hereby certify that the. answers are true and correct to the best of my knowledge.
"~
Firry 6K6EH10t Subscribed and sworn before me this d day of d - e A s, 1989.
Wl2dNb AN My comission expires: 7/f/pg ep c-8909120089 890905 n
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AGENDA:
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MEETING WITH NRC ON TURKEY-POI';
, o.EACTOR VESSEL.
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-APRIL'7,-1977 p;
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'1.) ' INTRODUCTION AND PURPOSE G. E. LIEBLER' u
i 2.)"~REACTORVESSELASSESSMENT J. N. CHIRIGOS.
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l A.) ACCIDENT ANALYSIS B.) ASME.III' APPENDIX G ANALYSIS.
C.) FATIGUE CRACK GROWTH ANALYSIS I
3.).
SUMMARY
W. COOPER l
i 4.) DISCUSSION' I
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.SyNARY REACTOR OPERATIONS (EY POINT UNIT NO. 4 I9 1.)' DESIGN FLUENCE: 6.05 X 10 N/CM2 (E >l MEV) FOR 40 CALENDAR YEARS.
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OPERATION AT 2300 MWT AT 80 PERCENT LOAD FACTOR.
2.) DATE OF FACILITY OPERATING LICENSE (2200 MWT)
. APRIL 10, 1973 i
' 3.)
INITIAL CRITICALITY JUNE 11,1973 4.) DATE OF INITIAL POWER GENERATION m
JUNE 19,'1973.
1 5.) START COMMERCIAL OPERATION SEPTEMBER 7, 1973 L
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METHOD OF ASSESSMENT' i
TURKEY POINT UNIT NO. 4 REACTOR VESSEL L.
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L-1.) 4 EFPY OR 5 CALENDAR YEARS CORRESPONDING DATE:
MARCH 15, 1979 PLANNED' INSPECTION DATE: AUGUST, 1978 2.)LACCIDENTANALYSISOFBELTLINEREGION A.) LOCA B.) LSB USING. CONTINUOUS INSIDE SURFACE FLAW
- 3.) ASME III.-APPENDIX G ANALYSIS OF BELT!INE' REGION
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FATIGUE CRACK GROWTH ANALYSIS OF BELTLINE
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RADIATION SURVEILLANCE-CAPSULE DATA O
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t TABLE 3 l.6'l TURKEY POINT UNIT NO. 4 REACTOR' VESSEL DATA 18 1.) FLUENCE X 13 : N/CM2 (E >l MEV)-
MARCH 1,1977 MARCH 15, 1979 AUGUST, 1978 (ACCUMULATED)
(5 CALENDAR YEARS)
(INSPECTION) 1/4T 2.7 L 4.6 4.0 SURFACE 4.5 7.6 6.7 t
USED IN CALCULATIONS 2.) CHEMISTRY - VENDOR CEP.TIFICATES 7
RTNDT-COPPER PHOSPHORUS INITIAL 0.010 50 BASE METAL WELD METAL 0.21 0.021 NA USEDINCALCULATIONS(WDATAl BASE METAL' O.054 0.010 50*F WELD METAL 0.31 0.011 3*F 3.) RT AT 1/4T - WELD METAL NDT MARCH 1, 1977 MARCH 15, 1979 AUGUST, 1978 W CURVES-129 149 144 R.G. i.99 1 51 196 183 18 2
SHELF WELD METAL IS 58 FT LB AT 5.7 X 10 N/CM 18 VESSEL 1/4T FLUEN?E OF 5.7 X 10 OCCURS AT 5 EFPY OR JUNE, 1980 4
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RES'ULTS OF FATIGUE CRACK' GROWTH. EVALUATION -
'b TURKEY POINT UNIT NO. 4 REACTOR VESSEL BELTLINE REGION 4
Postulated Final Flaw Depth (in.) After-(-)
Initial Calendar Years of Operation-
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0.125 0.125' O.126 0.250 0.253 0.255 0.500 0.509 0.518 0.750 0.771 0.791 1.000 1.037-1.073
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. i FLORIDA POWER AND LIGHT COMPANY
_ TURKEY POINT NUCLEAR FACILITY ni 1.) ESTIMATED MAXIMUM FLUENCE (E >l MEV) AT THE INNER SURFACE OF THE REACTOR VESSEL WALL AS OF 1/1/77 18 2
UNIT #3 - 5.33 x 10 N/CH 18 2
UNIT #4 - 4.47 x 10 N/CM 2.) NUMBER OF EFFECTIVE FULL POWER YEARS (EFPY) 0F OPERATION ACCUMULATED AS OF 1/1/77 UNIT #3 - 2.68 EFPY UNIT #4 - 2.17 EFPY 3.) VESSEL FABRICATOR - BABC0CK & 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 NUMBER -
NOT AVAILABLE AT THIS TIME 2.) FILLER METAL AND HEAT NUMBER - SEE TABLE 3.) TYPE OF FLUX AND HOT NUMBER - SEE TABLE 4.) WELDING PROCESS - SEE TABLE 5.) POST WELD HEAT TREATMENT UNIT #3 AND #4 1100 TO 1150*F - 48 HRS. (B&W WELD QUAL. TESTS) l 1100 TO 1150*F 1/4 HRS. (INTER TO LOWER SHELL WELD) 1125'F 1/4 HRS. (SURVEILLANCE KELD) i 0
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7.) DROPWEIGHT:--NOT PERFORMED:
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