ML20077B394: Difference between revisions

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#REDIRECT [[BECO-91-064, Forwards Changes to Tech Spec Bases for Section 3.10, Core Alterations Per 791121 Amend 39 to License DPR-35,in Response to NRC Concerns During 1989 Refueling of Browns Ferry.Changes Cover Spiral Reload]]
| number = ML20077B394
| issue date = 05/07/1991
| title = Forwards Changes to Tech Spec Bases for Section 3.10, Core Alterations Per 791121 Amend 39 to License DPR-35,in Response to NRC Concerns During 1989 Refueling of Browns Ferry.Changes Cover Spiral Reload
| author name = Davis G
| author affiliation = BOSTON EDISON CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000293
| license number =
| contact person =
| document report number = BECO-91-064, BECO-91-64, NUDOCS 9105140298
| package number = ML20077B396
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
}}
 
=Text=
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[I BOSTON E0ISON hignm Nudear Pov.er Station Rucky Kl! Road Ph moum. Massachusetts 02300 George W. Davis                                                        May 7  1991 sew v.cc eine - Neear BECo 91- ou U.S. Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555 License DPR-35 Docket 50-293 CbJtnaes to Technical SDecification _ Bases for Spiral Reloitd                '
The Technical Specification (TS) Bases for Section 3.10 " Core Alterations" for            l Pilgrim Station have been revised. These Bases include a discussion of " Spiral Reload" which was inserted into the Pilgrim TSs in Amendment 39 (BECo letter November 21, 1979, NRC letter January B, 1980).
In response to NRC concerns during the January 1989 refueling for Browns ferry Unit 2, General Electric has recommended modifying the pattern followed for reloading a full reactor core. This revision changes tFe Bases discussion from the past practice of beginning core loading at the geometric center of the core, to describe the recommended practice to begin core loading around a single Source Range Monitor.
In accordance with 10CFR50.36(a), bases are not a part of the Technical
            -  Specifications. Therefore, these Bases changes do not constitute an amendment to the operating license and prior NRC approval is not required. These changes have been reviewed by the Pilgrim Operations Review Committee. Please incorporate these Bases changes into your copy of the Pilgrim Nuclear Power Station Technical Specifications by replacing Pages 204A and 205 with the attached Revision 149 pages.
                                                                                    )t( N.tn1 G. H. Davis HTL/cic/5689
 
==Attachment:==
Technical Specification Bases Pages 204A and 205, Revision 149 Cc:
Mr. R. Eaton, Project Manager                          U.S. Nuclear Regulatory Commission Division of Reactor Projects - I/II                    Region 1 Office of Nuclear Reactor Regulation                  475 Allendale Road Mail Stop: 1401                                        King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission 1 White Flint North                                    Senior NRC Resident Inspector 11555 Rockville Pike                                  Pilgrim Nuclear Power Station Rockville, MD 20852 9105140290 910507 400I J dt,          PDR  ADOCK 05000293 P                  PDR                                                          Fl
__          _-      _    -_----QI}}

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