ML20040E111

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Submits Addl Info Re First Surveillance Capsule as Requested.Fsar Will Be Revised to Reflect New Sequence to Be Used for Capsule Surveillance Program
ML20040E111
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/20/1982
From: Ash R
BALTIMORE GAS & ELECTRIC CO.
To: Clark R
Office of Nuclear Reactor Regulation
References
NUDOCS 8202030126
Download: ML20040E111 (2)


Text

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l B ALTIMORE GAS AND ELECTRIC CHARLES CENTER . P.O. BOX 1475 BALTIMORE, MARYLAND 21203 stecTnic suomeenisa DEPA=TMENT Januar 20 1982 I

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Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission S FM S CD $

Washington, D.C. 20555 .

2 MO p FEB 2 1982 *- 1 Attn: Mr. R. A. Clark up:aacamra Operating Reactors Branch #3 Wgmuu y//

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Subject:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 & 50-318 Surveillance Ctpsule 263

Reference:

(a) Letter from R. A. Clark to A. E. Lundvall, Jr., dated June 18, 1981 (b) Letter from R. F. Ash to R. A. Clark, dated February 4,1981 (c) Letter from D. G. Eisenhut to A. E. Lundvall, dated August 21,1981 Gentlemen:

Reference (a) included a request for additional information in connection with our earlier submittal on our first surveillance capsule (reference (b)).

Our response to reference (a) was verbally cancelled by NRC Staff with the understanding that most if not all of the requested information would be submitted in the course of our response to reference (c).

The surveillance capsule located at 263 0 from the azimuthal reference (i.e., 97 degrees counterclockwise rather than 97 degrees clockwise) was used for our first capsule analysis. We emphasize that this has no effect upon the results. For each capsule, the results of capsule dosimetry are normalized to the fluence profile at the inner surface of the vessel. Therefore, any capsule used would nominally yield the same value for peak fluence at the inner wall. Since the two capsules in question are identical in composition and occupy isofluent locations in the vessel, there is no difference expected between the observed data and the data which would have been generated in an analysis of capsule 97. We will revise our FSAR to reflect the new sequence to be used for the capsule surveillance program.

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If you have any other questions in this matter which are not treated in our program on pressurized thermal shock, please do not hesitate to ask.

' Very trul yours, R. F. Ash Supervising Engineer Nuclear Generation Engineering cc: 3. A. Biddison, Esquire G. F. Trowbridge, Esquire

. Mr. D. H. Jaf fe - NRC

Mr. R. E. Architzel - NRC l

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