ML20247A308

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Affidavit of Bj Elliot.* Advises That Author Responded to Interrogatories 1,3,4,6-10,12,13,16 & 17.Related Correspondence
ML20247A308
Person / Time
Site: Turkey Point  NextEra Energy icon.png
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)


Text

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, i 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 1 (Turkey Point Plant, Units.3 and 4) (P/TLimits)

' 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.

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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 J. : PDR ADOCK 05000250 '

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p 1 AGENDA: 1 u ;,l 1

. . . l MEETING WITH NRC ON TURKEY- POI'; , o.EACTOR VESSEL. j

-APRIL'7,-1977 p;

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'1.) ' INTRODUCTION AND PURPOSE G. E. LIEBLER' u

i J. N. CHIRIGOS.

2.)"~REACTORVESSELASSESSMENT {

l A.) ACCIDENT ANALYSIS B.) ASME.III' APPENDIX G ANALYSIS.  !

C.) FATIGUE CRACK GROWTH ANALYSIS I W. COOPER  ;

3.).

SUMMARY

l i 4.) DISCUSSION' I q

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> . TABLE

.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

-4',) 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 RT NDT-COPPER PHOSPHORUS INITIAL BASE METAL -- 0.010 50 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.) RTNDT AT 1/4T - WELD METAL 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 OCCURS AT 5 EFPY OR JUNE, 1980 VESSEL 1/4T FLUEN?E OF 5.7 X 10 4

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RES'ULTS OF FATIGUE CRACK' GROWTH. EVALUATION -

'b TURKEY POINT UNIT NO. 4 REACTOR VESSEL BELTLINE REGION 4

Final Flaw Depth (in.) After-(-)

Postulated

, Initial Calendar Years of Operation-

- Flaw Depth'

(inch)- 5* 10 I. 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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REACTOR VESSEL MATERIAL' SURVEILLANCE PROGRAM .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

  • UNIT #3 - 5.33 x 10 18 N/CH 2

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:

E  : 5.) A&B.)1 INFORMATION ON WELD MATERIAL INCLUDED-IN THE VESSEL MATERIAL SURVEILLANCE PROGRAM - SEE TABLE; ,

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