L-77-113, Letter Re Reactor Vessel Fracture Toughness Requirements & Weld Metal Surveillance Data

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

NRCFQRM 1IIS U.S. NUCLEAR REGULATORY CO'SSION DOCKET NUMRFR l2 751 .C?'-.

Flt.E NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO:Mr. George Lear FROMM DATE OF DOCUMENT Miami, Fl. 33101 04 Robert E. Uhrig DATE RECEIVED 04-14-V

~ ~ETTE R 0 NOTOR IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED P(ORIGINAL P( NCLASSIFI ED QCOP Y S(Q,~~M DESCRIPTION ENCLOSURE itr. Ref, our 04-07-77 meeting Consists of .Information concerning reactor vessel status...Advising 'egarding Reactor Vessel Material Sitrveillance Program that an Appendix G. inservice inspection of th for Units 3 IIl, 4 Forged. Pressure Vessels Weld Unit 4 reactor vessel belt-line area need not and Copper Data.....

be conducted until after June 1980...and Trans The Folloving:

( 23 encl rec'd )

( 2 pages ) ( 6 pages )

PIimr NAME: TURKEY POINT UNIT"4 jcm SAFETY FOR ACTION/INFORMATION ASSIGNED AD:

/io PROJECT MANAGER~

C ASS a LIC ASST INTERNAL D ISTRI BUTION G FILE>> SYSTEMS SAFETY PLANT SYSTEMS STESA NRC PDR HEINEMAN 'EDESCO

-IW-E .. SCHROEDER OELD GOSSICK & STAFF ENGINEERING IPPOL 0 MIPC MACARRY ERNST BOSNAK BALLARD HANAUER SIHWEIL OPERATING REACTORS YOUNGBLOOD HARLESS PA K STELLO SITE TECH PROJECT MANAGEMENT 'EACTOR SAFE OPERATING TECH GAMMILL BOYD ROSS EISENHUT STEPP P COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON CHECK B E SITE ANALYSIS VOLLMER HELTEMES AT&I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER PDR rrt~ NAT LAB~

TIC: REG V IE ULR KSON OR NSIC: LA PDR SLB0 CONSULTANTS: 77(a5'0 SC4 ACRS CYS tN&9%NC/ E NRC FORM 195 {Z 75)

P. O. BOX 013100, MIAMI, FL 33101 FLORIDA POWER 8 LIGHT COMPANY 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 H

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Dear Mr. Lear:

Re: Turkey Point Unit 4 i~~"

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Docket No. 50-251 Fracture Tou hness Re uirements 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 i

at the 1/4 location until at this location will have received a least June fluence 1980 of at which time 5.7 x 10 nvt.

PEOPLE... SERVING PEOPLE

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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 Robert Lowenstein, Esquire II

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 Unit P4 Wire , Flux Wire Flux Heat No. Lot No. Heat No. Lot No.

Girth Held 71249 8445 71249 8445 Surveillance Welds 71249 8445 71249 8457 SURVEILLANCE MELD METAL COPPER ANALYSIS WT.

Unit 83

~Sam la Vendor Original Unirradiated .31 Spectro Chemical Laboratory Re-Check //1 Unirradiated .33 Spectro Chemical Laboratory Re-Check //2 Unirradiated .32 Westinghouse R6D Center Unit Pr4

~Sam la Vendor Original Unirradiated" .30 Spectro Chemical Laboratory Irradiated Broken Charpy al .27 Southwest Research Institute Irradiated Broken Charpy I 82 29 Southwest Research Institute Irradiated Broken Charpy fjf3 .30 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)

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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

~ I TURKEY POINT UNIT NO. 3 Ft-lb'nergy SURVEILLANCE WELDMENT C MN P Si CR NI MO at 10'F

'/8" Page Wire Heat No. 71249>

Linde 80 Flux Lot No. 8445

.07 1.28 0.21 0.14 ~ .52 .17 .57 '36 .21 45,45,46 NOZZLE SHELL TO INTER. SHELL WELD 1/8" Page Wire Heat No. 72442> .08 1.52 .018 .015 .42 .06 .64 .39 .25 40,52 41 Linde 80 Flux Lot No. 8579 1/8" E8015 G Wire Heat No. 83D529 .04 .73 , .010 .014 .34 .01 .90 .48 5/32" E8015 G Wire Heat No. 89D285 .04 .66 .010 . .020 .23 .03 1.04 .48 3/16" E8015 G Wire Heat No..86C127 .04 .76 .008 .019 .22 .02 .85 .65 3/16" E8015 G Wire Heat No. 78C491 .05 .82 .009 .015 .22 .02 .76 .66 .02 INTER. SHELL TO LOWER SHELL WELD 1/8" Page Wire Heat No. 71249> .07 1.28 .021 .014 .52 .17 .57'36 .21 45,45,46

'Linde 80 Flux Lot No. 8445 I

'OWER SHELL TO DUTCHMAN WELD 1/8";Wire Heat No. 61782 * .08 1.24 .015 .013 .47 ,06 .50 '54 .17 56,44,55 Linde 80 Flux Lot No. 8457

• Submerged Arc Weld - All others are manual metal arc used for repairs.

TURKEY POINT UNIT NO; 4 Ft-lb Energy, SURVEILLANCE MELDMENT C MN Si CR NI MO CU at 10'F 1/8" Page Mire Heat No. 71249> .07 1.42 .020 .016 .51 .16 .55 .49 .23 38,34,52 Linde 80 Flux Lot No. 8457 NOZZLE SHELL TO INTER. SHELL WELD 1/8" Am. CKC Wire Heat No. 72105>~ .07 1.60 .014 .011 48 .46 .40 .27 39535,44 Linde 80 Flux Lot No. 8669 1/8" Am. C8C Wire Heat NO. 72442> .064 1.49 .014 .017 .54 .02 .57 .41 .27 29,35,30 Linde 80 Flux Lot No. 8669

.66 .010 .020 .23 .03 1.04 .48

'/32" E8015 G Wire Heat No. 89D285 .04 INTER. SHELL TO LOWER SHELL WELD 1/8" Page Wire Heat No. 71249>* .07 1.28 .021 .014 .52 .17 .57 .36 .21 45;"45,46 I

Linde 80 Flux Lot No. 8445 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 * .08 1.24 .015 .013 .47 .06 .50 .54 .17 56,44,55 ',

Linde 80 Flux Lot No. 8457 1/8" E8015 Wire Heat No. 86C127 ,06 .70 .008 .015 .26 .94 .57

• Submerged Ard Welds - All others are manual metal are used for repairs.

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