ML17342A422

Forwards Proprietary Rev 1 to 83-185, Evaluation of Toughness of Irradiated Welds at 200 C & 288 C for Turkey Point Unit 4 Beltline Weld, Demonstrating Fracture Toughness at Specified Temps.Rev Withheld (Ref 10CFR2.790)

ML17342A422
Person / Time
Site:	Turkey Point
Issue date:	03/25/1986
From:	Woody C FLORIDA POWER & LIGHT CO.
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML17342A423	List: ML17342A422 ML17342A424
References
RTR-NUREG-0744, RTR-NUREG-744 L-86-122, NUDOCS 8603310205
Download: ML17342A422 (4)

Text

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ACCESSION NBR 8603310205 DOC. DATE: 86/03/25 NOTARIZED: YES DOCKET 8 FAC IL: 50-250 Turkey Point Plant> Unit 3> Florida Power and Light C 05000250 50-251 Turkey Point Plant> Unit 4> Florida Power and Light C 05000251 AUTH. NAME 'AUTHOR AFFILIATION WOODY> C. O. Florida Power h Light Co.

RECIP. NAME RECIPIENT AFFILIATION THOMPSON> H. L Division of Pressurized Water Reactor Licensing A (post 8

SUBJECT:

Forwards proprietary Rev 1 to 83-185> "Evaluation of Toughness of irradiated Welds at 200 C h 288 C for Turkey Point Unit 4 Beltline Weld>" demonstrating fracture toughness (t

t spe ified temps. R v withheld (Ref 10CFR2. 790).

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DISTRIBUTION TITLE:

COD . 01 CO IES E IVED: LTR Proprietary Review Distribution-Operating Reactor

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FLORIDA POWER 5 LIGHT COMPANY QR 2 5 1988 L I 22 hh Office of Nuclear Reactor Regulation Attention: Mr. Hugh L. Thompson, Jr., Director Division of PWR Licensing - A U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Thompson:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-25 I Pressure Vessel Material Fracture Toughness (NUREG -0744 Rev. I)

Our letter L-84-I20, dated May 3, l 984 transmitted an analysis demonstrating the compliance of Turkey Point Units 3 and 4 with the fracture toughness requirement of Appendix G to IO CFR 50. The analysis was performed utilizing the guidance of NUREG-0744, Rev. I, and the best plant specific data available. The material properties data, however, were obtained from tests at 200 C (392 F). We have subsequently had data obtained at temperatures more equivalent to reactor operating temperatures (288 C - 550 F) become available.

Therefore, attached is the revised analysis which demonstrates that the fracture toughness of the reactor vessel is assured at these temperatures with substantial margins of safety.

This submittal contains information that is proprietary to Fracture Proof Design Corporation. In conformance with the requirements of IO CFR Section 2.790, we are enclosing with this submittal, an Application for Withholding From Public Disclosure and an Affidavit prepared by Fracture Proof Design Corporation. The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission.

Should you have any questions, please call us.

Very truly yours, C. O. Woody Group Vice President Nuclear Energy CO W/TCG/gp Attachments 86033i0205 8~0325 06000250 PDR ADOCN P PDR PEOPLE... SERVING PEOPLF TCG4/0 I I /I

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