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MONTHYEARML20134K7911997-02-13013 February 1997 Forwards RAI to Complete Review of Licensee 970131 Submittal Re Proposed TS Changes to RCS Flow Limit at Plant,Units 1 & 2 Project stage: RAI ML20135E1151997-02-28028 February 1997 Forwards Request for Addl Info Re License Amend Request Change to RCS Flow Requirements to Allow Increased Steam Generator Tube Plugging Project stage: Request ML20135E7321997-03-0505 March 1997 Forwards Request for Addl Info Re Proposed TS Changes to Reactor Coolant Sys Flow Limit Project stage: RAI ML20137F2401997-03-25025 March 1997 Forwards Response to RAI Re 970131 Amend Request to Change Reactor Coolant Sys Flow Requirements to Allow Increased Steam Generator Plugging Project stage: Response to RAI ML20137X8791997-04-16016 April 1997 Provides Response to Questions Posed in 970320 Telcon Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging Project stage: Other ML20139A3031997-04-22022 April 1997 Forwards RAI Re Proposed TS Changes to Reactor Coolant Sys Flow Limit Concerning Radiological Controls for Plant Project stage: RAI ML20140E0901997-06-0909 June 1997 Forwards RAI Re Changes to Reactor Sys Flow Limit Amend Related to Reactor Sys.Based on Review,Addl Info Is Required to Complete Review Project stage: RAI ML20149J1841997-07-25025 July 1997 Forwards Request for Addl Info Re 970131 & 0416 Proposed Technical Changes to Reactor Coolant System Flow Limit, Calvert Cliffs Nuclear Power Plant,Units 1 & 2 Project stage: RAI ML20210M6511997-08-19019 August 1997 Forwards Response to 970422 & 0609 RAIs Re License Amend Request Change to RCS Flow Requirements to Allow Increased SG Tube Plugging Project stage: Other ML20217C7311997-09-29029 September 1997 Forwards Response to 970725 RAI Re License Amend Request Revising RCS Flow Requirements to Allow Increased SG Tube Plugging.Ts Page from 970609 License Amend Request to Convert to Improved Ts,Encl Project stage: Other ML20199B6611998-01-22022 January 1998 Provides Supplementary Responses to NRC 970422 & 0725 Requests for Addl Info for LAR Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging Project stage: Supplement ML20217K0961998-03-30030 March 1998 Forwards RAI Re RCS Flow Requirements to Allow Increased SG Tube Plugging.In Order to Expedite Staff Review,Response Requested by 980415 Project stage: Approval ML20216D6321998-04-0808 April 1998 Forwards Response to 980330 RAI Re LAR Change to RCS Flow Requirements to Allow Increased SG Plugging.Response Does Not Change No Significant Hazards Determination Previously Provided Project stage: Other ML20217D2921998-04-21021 April 1998 Responds to Request for Addl Info Re LAR Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging Project stage: Request ML20217D2301998-04-21021 April 1998 Submits Revised TS Pages for 970131 Application for Amends to Licenses DPR-53 & DPR-69 Re RCS Flow Requirements to Allow Increased SG Tube Plugging,As Requested by NRC in 980325 Telcon Project stage: Request ML20247R8811998-05-22022 May 1998 Concurs W/Listed License Condition for RCS Low Flow Amend Request for Units 1 & 2 Project stage: Request ML0519903452005-07-13013 July 2005 License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process Project stage: Request 1997-07-25
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a s-CnAnt.Es II. CutsE Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calven Cliffs Parkway Lusby, Maryland 20657 410 495-4455 May 22,1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Reactor Coolant System Low Flow License Amendment Request: Concurrence with License Conditions (TAC Nos. M97855 and M97856)
Baltimore Gas and Electric Company concurs with the License Condition presented below for the Reactor Coolant System low flow amendment request for Units 1 and 2.
Condition Implementation Date The licensee is authorized to incorporate The updated Updated Final Safety certain changes in the Updated Final Analysis Report shall be implemented l
Safety Analysis Report regarding Main within six months after restart from the Steam Line Break, Steam Generator Tube spring 1998 and spring 1999 refueling Rupture, Seized Rotor and Boron Dilution outages (Unit I and Unit 2, respectively).
Analyses.
I Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours,
+ 0 ti d Q fik
}g CllC/ PSF / dim cc:
R. S. Fleishman, Esquire
- 11. J. Miller, NRC h0;3 J. E. Silberg, Esquire Resident Inspector, NRC t
S. S. Bajwa, NRC R.1. McLean, DNR A. W. Dromerick, NRC J. II. Walter, PSC 9805290235 990522 PDR ADOCK 05000317 P
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