ML20058G166

Requests Approval to Use plant-specific Data for Reactor Vessel Fracture Toughness Analysis.Justification to Use Subj Data,Including Nonproprietary Rept CEN-612-NP & Proprietary Rept CEN-612-P.Proprietary Rept CEN-612-P Withheld

ML20058G166
Person / Time
Site:	Calvert Cliffs
Issue date:	11/29/1993
From:	Denton R BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19311B212	List: ML20058G166 ML20058G175 ML20058G184
References
NUDOCS 9312090115
Download: ML20058G166 (3)

Text

fE BALTIMORE GAS AND ELECTRIC 1650 CALV5IRT CUFFS PARKWAY LUSBY, MARYLAND 20657-4702 RostRT E. DENTON VICE PatSCENT tWJCLEAR ENERGY (4.o) no-44ss November 29,1993 U. S. Nuclear Regulatory Commission Washingtor., DC 20555 A'ITENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 Request for Approval to Use Plant-Specific Data for Reactor Vessel Fracture Toughness Anah> sis REEERENCES: (a) Letter from Mr G. C. Creel (BG&E) to NRC Document Control Desk, dated December 13, 1991, Response to the 1991 Pressurk. d Thermal Shock Rule (b) Ixtter from Mr. R. E. Denton (BG&E) to NRC Document Control Desk, daied June 22, 1993, Analysis of the Calvert Cliffs Unit j Reactor Vessel Surveillance Capsule Withdrawn from the 97 location Pursuant to 10 CFR 50.61(b)(3), Baltimore Gas and Electric Company (BG&E) hereby submits a request for approval to riodify the Calvert Cliffs Unit 1 (CC-1) reactor vessel Pressurized Thermal Shock (PTS) reference temperatures (RTp33) using plant-specific surveillance data. The RTyp values reported in References (a) and (b) are calculated by the method provided m 10 CFR 50.61(b)(2). Paragraph (b)(3) requires that values of RTp g3 that have been modified using plant-specific information be approved by the Director, Office of Nuclear Reactor Regulation.

The justification to use plant-specific data for fracture toughness analysis is provided in Attachment (1). This document demonstrates that significant improvement in the accuracy of embrittlemen: prediction of the CC-1 reactor vessel beltline materials can be achieved using data obtained from three smveillance programs. In addition to PTS-related requirements of 10 CFR 50.61, BG&E intends to use these data for fracture toughness requi" ments of 10 CFR Put 50, Appendix G. Attachment (2) is a Combustion Engineering, Inc. i.coprietary affidavit for Attachment (3), pursuant to 10 CFR 2.790. Attachment (3) contains the proprietary i version of the enclosure to Attachment (1).

Previously, BG&E had ryorted that the value of RTp33 or f CC-1 Axial Weld Scams 2-203-A,B,C was projected to exceed the PTS screening c:iteria before the expiration date of the current Operating License (References a and b). As mentioned above, that projection was based on the 9312090115 ?31129 '

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Document Control Desk November 29,1993 Page 2 I

calculational method provided in 10 CFR 50.61(b)(2). The attached document shows, based on the I plant-specific data, none of the CC-1 reactor vessel beltline materials will exceed the screening l criteria prior to reaching a fluence value greater than 6.57 x 1019 n/cm2. This fluence value will not be reached before the end of the current 1; cense or before the end of a 20-year renewal perior'-

should it be pursued. ,

SCIIEDULE Baltimore Gas and Electric Company requests that the NRC review and approve this submittal by ,

May 31,1994, to support a timely core loading recommendation for Cycle 13. To meet this schedule., '

we request that you provide us with your initial comments and/or questions by February 1994. Yo. ;

cooperation on this matter is greatly appreciated.

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

truly yours, I

[ N

( ,

RED /GT/ dim

Attachment:

(1) Application of Reactor Vessel Surveillance Data to Calvert Cliffs Unit 1 (2) Proprietary Affidavit for Attachment (3)

(3) Proprietary Version of the Enclosure to Attachment (1) cc: (Without Attachments)

D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC T.T. Martin NRC P. R. Wilson, NRC R. I. McIzan, DNR J. H. Walter, PSC r (With Attachments)

D. G. Mcdonald, Jr., NRC

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ATTACHMENT (1) l 1

APPLICATION OF REACTOR VESSEL SURVEILLANCE DATA TO CALVERT CLIFFS 1 l 4

4 1

Baltimore Gas and Electric Company Docket No. 50-317 Novemher 29,1993