ML20141G580

Forwards RAI Re TS Change to Moderator Temp Coefficient Limit.Staff Requests Addl Info Be Provided within 30 Days of Ltr Receipt

ML20141G580
Person / Time
Site:	Calvert Cliffs
Issue date:	05/15/1997
From:	Dromerick A NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
References
TAC-M95181, TAC-M95182, NUDOCS 9705220421
Download: ML20141G580 (4)

Text

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(r. Char 1Gs H. Cruse May 15, 1997  !

Vice Presid:nt - Nuclear En:rgy  !

, Baltimore Gas and Electric Company l Calvert Cliffs Nuclear _ Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 1

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE TECHNICAL SPECIFICATION CHANGE TO THE MODERATOR TEMPERATUR COEFFICIENT (TACS NO. M95181 AND M95182)

Dear /*ir. Cruse:

By letters dated March 28, 1996, and November 20, 1996, you submitted a I request to reduce the moderator temperature coefficient limit shown on Technical Specification Figure 3.1-1. The NRC staff is reviewing your submittals and has determined that additional information is required for us

, to complete our review. The information requested is addressed in the enclosure. The staff requests that the additional information be provided within 30 days of receipt of this letter.

If you have any questions regarding this matter, please contact me at (301) 415-3473.

Sincerely,

/S/

Alexander W. Dromerick, Senior Project Manager )

Project Directorate I-l Division of Reactor Projects - I/II .

Office of Nuclear Reactor Regulation l 1

Docket Nos. 50-317 {

and 50-318  ;

Enclosure:

As stated cc w/ enc 1: See next page DISIMBEIQti:

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"%*,,,,+ May 15, 1997 ,

Mr. Charles H. ' Cruse Vice President - Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway  ;

Lusby, MD 20657  ;

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE TECHNICAL ,

SPECIFICATION CHANGE TO THE MODERATOR TEMPERATURE COEFFICIENT (TAC N05. M95181 AND M95182)

Dear Mr. Cruse:

By letters dated March 28, 1996, and November 20, 1996, you submitted a request to reduce the moderator temperature coefficient limit shown on Technical Specification Figure 3.1-1. The NRC staff is reviewing your ,

submittals and has determined that additional information is required for us to complete our review. The information requested is addressed in the enclosure. The staff requests that the additional information be provided .

within 30 days of receipt of this letter.

If you have any questions regarding this matter, please contact me at (301) 415-3473.

Sincerely, 4t[p k  %&

Alexan er W. Dromerick, Senior Project Manager Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation ,

Docket Nos. 50-317 '

and 50-318 Enclosure ~: As stated cc w/ enc 1: See next page 8

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. - == . --

s 4 . I e

Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant -

Baltimore Gas & Electric Company Unit Nos. I and 2 CC: - .

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President Mr. Joseph H. Walter, Chief Engineer - l Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division- l Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire  !

Counsel Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel +

P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102  ;

Baltimore, MD 21202-1631 *

. Jay E. ' Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge Patricia T. Birnie, Esquire ,

2300 N Street, NW Co-Director ,

Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111  ;

-Mr. Thomas N. Prichett, Director Baltimore, MD 21218 -

NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatell  ;

1650 Calvert Cliffs Parkway -

NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road ,

Chattanooga, TN 37411-4017  !

Resident Inspector  !

U.S. Nuclear Regulatory r t

Commission P.O. Box 287 ,

St. Leonard, MD 20685 Mr. Richard I. McLean ,

Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue  :

Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region I i U.S. Nuclear Regulatory Commission l 4

475 Allendale Road  ;

King of Prussia, PA 19406 t

., - - . ___ _ _ _ _ _ _ _ _ _ _ _ -__N

RE0 VEST FOR ADDITIONAL INFORKATION PROPOSED TECHNICAL SPECIFICATION CHANGE TO THE MODERATOR TEMPERATURE COEFFICIENT >

1. On page 2 of the March 28, 1996 submittal, under the heading of the Licensing Basis, it is stated that the MTC value at full power and equilibrium xenon is negative. In the second paragraph under the same heading, it is stated that since BGE has installed the Divers Scram System as a long term solution to ATWS, it is no longer necessary for BGE to design cores with a negative MTC. Is it the intent of BGE to conduct an ATWS analysis with an MTC value different (more positive) to that used in the original (present) CE ATWS analysis?

2. Is the new MTC value used in the ATWS analysis compatible with the ATWS analysis performed to provide for the ATWS Rule. (i.e., is the new MTC value compatible with the value CE used at the time the analysis was done to support the ATWS Rule?)

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Enclosure

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