ML20045D926

Forwards BAW-2160, Analysis of Capsule 97,Calvert Cliffs Nuclear Power Plant,Unit 1,Reactor Vessel Matl Surveillance Program.

ML20045D926
Person / Time
Site:	Calvert Cliffs
Issue date:	06/22/1993
From:	Denton R BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045D927	List: ML20045D926 ML20045D931
References
NUDOCS 9306300235
Download: ML20045D926 (3)

Text

n BALTIMORE GAS AND ELECTRIC 1650 CALVERT CUFFS PARKWAY . LUSBY, MARYLAND 20657-4702 ROBERT E, DENTON Vict PRESIDENT uav r--n (4eo) aso-4455 June 22,1993 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 Analysis of the Calvert pliffs Unit No.1 Reactor Vessel Surveillance Capsule Withdrawn from the 97 Location

REFERENCES:

(a) Letter from Mr. R. E. Denton (BG&E) to Document Control Desk (NRC), dated March 22,1993, Reactor Vessel Capsule Report (b) Letter from Mr. D. G. Mcdonald -(NRC) to Mr. R. E. Denton (BG&E), dated April 13,1993, Reactor Vessel Suiveillance Capsule Report Gentlemen:

Pursuant to 10 CFR Part 50, Appendix H, Baltimore Gas and Electric Company (BG&E) hereby -

submits a summary technical report on the subject reactor vessel surveillance capsule. The 97 location surveillance capsule was withdrawn on April 23,1992. Appendix H requires the report to be submitted within one year after capsule withdrawal unless an extension is granted. By letter dated March 22,1993 (Reference a), BG&E requested an extension of the duc date from April 23,1993, to June 23,1993. In Reference b, the NRC approved the extension request.

The 97 location surveillance capsule is the second capsule withdrawn from the Calvert Cliffs Unit I reactor vessel beltline region. The capsule was removed and evaluated after being irradiated in the -

Unit I reactor vessel as part of the reactor vessel materials surveillance program. The objective of the program is to monitor irradiation-induced changes on the reactor vessel beltline material properties.

The capsule analysis results indicate that the tensile specimens are exhibiting normal behavior -

relative to neutron fluence exposure. The Charpy impact specimens exhibited the characteristic shift to higher temperature for thg 30 ft-lb transition temperature and decrease in upper.r,helf energy.

Overall, the results of the 97 location capsule evaluation demonstrate that the current techniques used for predicting the change in the fracture toughness properties due to neutron irradiation and thermal environment are conservative. A change in the Technical Specifications is not required.

9306300235 930622 PDR ADOCK 05000317 P PDR

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Document Control Desk June 22,1993 Page 2 ,

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Should you have any questions regarding this matter, we will be pleased to discuss them with you.

yours, r de 4

RED /GT/gt/ dim

Attachment:

Ana ysis of the Calvert Cliffs Nuclear Power Plant Unit No.1 Reactor Vessel Surveillance Capsule Withdrawn from the 97 location of the Beltline Region ,

cc: (Without Enclosure)

D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC ,

D. G. Mcdonald, Jr., NRC R. I. McLean, DNR J. H. Walter, PSC (With Enclosure)

T. T. Martin, NRC P. R. Wilson, NRC e

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ATTACHMENT Analysis of the Calvert Cliffs Nuclear Power Plant Unit No.1 Reactor Vessel Surveillance Capsule Withdrawn from the 97* Imcation of the Beltline Region F

Baltimore Gas and Electric Company Docket No. 50-317 June 22,1993 I