ML20212P029

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Forwards Assumptions & Calculation of Resistor Temp for Pressurized Thermal Shock at End of License for Matls in Calvert Cliffs Units 1 & 2 Reactor Vessel Beltline Region, Per 860821 Request for Addl Info
ML20212P029
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/29/1986
From: Tiernan J
BALTIMORE GAS & ELECTRIC CO.
To: Thadani A
Office of Nuclear Reactor Regulation
Shared Package
ML20212P031 List:
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8609020145
Download: ML20212P029 (1)


Text

m DALTIVORC GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERN A>4 WetPnse'otNT NucttAn ENCRGY August 29,1986 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION: Mr. Ashok C. Thadani, Director

< PWR Project Directorate #8

'h ,

Division of PWR Licensing-B

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. L & 2; Doc.ket Nos. 50-317 & 50-313 Response to Request for Additional Information: Pressurized Thermal Shock Rule

REFERENCES:

(a) Letter from Mr. S. A. McNeil (NRC), to Mr. J. A. Tiernan (BG&E),

dated August 21,1986 Gentlemen:

In Reference (a) you requested additional technical information regarding the results of our pressurized thermal shock onessment of Calvert Cll!!s. Specifically, you requested the copper and nickel contents and initial RTNDT f reactor vessel materials. In addition, you requested the values of and supporting assumptions for fast neutron fluence used in our assessment.

The enclosed report provides the requested information. Should you have any further questions regarding this matter, please do not hesitate to contact us.

Very truly yours, 060902o140 060029 fDR ADOCK 05000317 PDH i

r i

JAT/SMM/BSM/dtm Enclosure cc D. A. Brune, Esquire J. E. Silberg, Esquire g/) g l S. A. McNeil, NI(C T. Foley, NitC ll s

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