ML20080N015

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Informs That Following Discussions W/Nrc,Util Agreed to Withdraw Proposed Elimination of CEAs & Drainage Paragraphs Requested in 931208 Lar,Revising Design Features Section of Ts.Revised TS Pages Encl
ML20080N015
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 03/02/1995
From: Denton R
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20080N018 List:
References
NUDOCS 9503060122
Download: ML20080N015 (2)


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Rostar E. Dswros Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant -

Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 586-2200 Ext.445512.

410 260-4455 Baltimore 1

March 2,1995 i

U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION:

Document Control Desk I

SUBJECT:

Calvert Cliffs Nuclear Power Plant l

1 Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318

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Supplement to a License Amendment Regte-t; Content of the Design Features Section

REFERENCES:

(a)

Letter from Mr. R. E. Denton (BGE) to NRC Document Control Desk, dated December 8,1993, License Amendment Request, Content of the Design Features Section (b)

NUREG-1432, Standard Technical Specifications for Combustion '

j Engineering Plants, Revision 0, September 1992 In Reference (a), Baltimore Gas and Electric Company (BGE) requested an amendment to the Technical Specifications for Calvcit Cliffs Unit Nos. I and 2 which would revise the Design Features section of the Technical Specifications.

Following discussions with the Nuclear Regulatory Commission Staff, BGE has agreed to withdraw the proposed climination of the " Control Element Assemblics" and " Drainage" paragraphs. The existing paragraphs will be retained and renumbered as required by the other proposed changes.

The proposed "Fuct Assemblies" section of the Design Features was based on Revision e of NUREG-1432 (Reference b). It contains the statement, "Each assembly shall consist of a matrix of zirecnium alloy fuel rods with an initial composition of natural or slightly enriched uranium dixoide (UO ) as fuel ma'erial."

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10 CFR 50.46, " Acceptance criteria for emergency core cooling systems for light water nuclear power I

reactors", provides for use of cylindrical zircaloy or ZIRLO as a fuel cladding in light water reactors. The proposed Revision 1 of NUREG-1432 replaces the phrase " zirconium alloy" with the phrase " cylindrical ~

zircaloy or ZlRLO". For consistency with the regulations and the proposed Revision 1, BGE revises our L

proposed change to incorporate that phrasc.

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- Document Control Desic March 2,1995 Page 2 1

In Reference (a), BGE proposed to replace the " Site" section and eeW~i maps with a new wrian, " Site Imition" which describes the leath of the site in ad,cc with SectSn 182.a of the Atomic Energy Act. In our discussions, the NRC has stated that the " Site Le*6" section must contam the minunum Exclusion Area radius to be acceptable. This informaten is not currently included in the Calvert Cliffs Technical Specifications Based on the request by NRC Staff and a need to expedite apprent and issuance of this amendment to support our upcommg refueling outage, we have included the Exclusion Area boundary reference. Inclusion of this reference, however, appears to represent a new requirement wliich we j

would reconsider as part of any future submittals to improve our Technical Specifications.

j Attachments (1) and (2) include revised " Insert A" pages for AM-Wents (1) and (2) of Reference (a).

'Ihe proposed revisions to Reference (a) do not change the " Determination of Significant Hazards" section of that submittal.

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

Very truly yours, s

b

  1. h RED /BDM/ dim i

Attachments:

(1)

Unit 1 Technical Specification Revised Pages i

(2)

Unit 2 Ti ;hnical Specification Revised Pages 4

cc:

D. A. Bnme, Esquire J. E. Silberg, Esquire L. B. Marsh, NRC D. G. Mcdonald, Jr., NR C T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. H. Walter, PSC 4

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