ML20064N173

Forwards Application for Amend to License NPF-3 to Revise TSs & Applicable Bases to Relocate Certain cycle-specific Protective Limits & Core Operating Limits to COLR

ML20064N173
Person / Time
Site:	Davis Besse
Issue date:	03/18/1994
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20064N175	List: ML20064N173 ML20064N179 ML20064N181
References
2197, NUDOCS 9403290200
Download: ML20064N173 (2)

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CENTERDOR ENERGY 6200 Oolt Tree Bodevord Mail Address Donald C. Shelton independenceOH PO Box 94601 Senior Vice President 216 44/.3)S3 C!everond. 0H 441014001 Nuclear Tax 216-447-3123 Docket Number 50-346 License Number NPF-3 l

Serial Number 2197 l March 18, 1994 United States Nuclear Regulatory Commission l Document Control Desk  !

Vashington, DC 20555

Subject:

License Amendment Application to Revise Technical Specifications and Applicable Bases to Relocate Certain Cycle-Specific Protective Limits and Core Operating Limits to the Core Operating Limits Report (COLR)

Gentlemen:

Enclosed is an application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1 Operating License Number NPP-3, l Appendix A, Technical Specifications, to reflect the changes attached.

The proposed changes involve Technical Specification (TS) 2.1.2 (Reactor Core), TS 2.2.1 (Reactor Protection System Setpoints), Bases 2.1.1 and 2.1.2 (Reactor Core), Bases 2.2.1 (Reactor Protection System Instrumentation Setpoints), TS 3.2.2 (Pover Distribution Limits, Nuclear lleat Flux Hot Channel Factor - F ), TS 3.2.3 (Pover Distribution Limits, Nuclear Enthalpy Rise 9 Hot Channel Factor - FN ,

Bases 3/4.2(PowerDistributionLimits),andTS6.9.1.7'(Administrh)lve Controls, Core Operating Limits Report).

This application is submitted in accordance with Generic Letter 88-16,

" Removal of Cycle-Specific Limits from Technical Specifications", dated October 4, 1988 (Toledo Edison Log Number'2735), which requires that, for removal of cycle-specific limits from the Technical Specifications, the limits be determined using an NRC approved methodology. On March 16, 1993, the NRC staff approved Babcock and Vilcox (B&V) Topical Report BAV-10179P, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses" (TAC No. M80189). The NRC Safety Evaluation Report (SER) concludes that the inclusion of certain operating limits {

in a COLR is acceptable and that BAV-10179P is an acceptable Technical j g g ,{ r gSpecification-reference for the B&V Fuel Company methodology used to opemtma companies Y4032YU200 v40s m , I Cleveland Elecine mummotmg PDR ADOCK 05000346 ') l-P Toledo Edcon - PDR i

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t Docket Number 50-346 License Number NPF-3 Serial Number 2197 Page 2 establish the values of these limits for the B&W-designed 177-fuel-assembly class of plants (such as the DBNPS). The operating limits that may be placed in the COLR include (but are not limited to):

nuclear heat flux hot channgl factor limit (Fn), nuclear enthalpy rise hot channel factor limit (F g), axial power Ymbalance protective limits and trip setpoint for nuclear overpower based on Reactor Coolant System flow. The above referenced Technical Specification and Bases changes are proposed to implement this guidance.

Generic Letter 88-16 identified that the use of a COLR as an alternative to including the values of cycle-specific parameters in individual Technical Specifications vill eliminate an unnecessary burden on licensees and the NRC. Therefore, this application is considered to be a Cost Beneficial Licensing Action since it vill allow future changes to cycle-specific limits without the expense of processing a License Amendment.

Toledo Edison requests that this amendment be issued by the NRC by-July 1, 1994, to support the planning and scheduling of the Ninth Refueling Outage (9RFO). The 9RF0 is currently' scheduled to commence on October 1, 1994. Should further information be required, please contact Mr. William T. O'Connor, Manager - Regulatory Affairs, at (419) 249-2366.

Very tr y yours, w~,

HKL/amb w x 3 i Enclosure .1 cc J. B. Hartin, Regional Administrator, NRC Region III  ;

S. Stasek, NRC Region III, DB-1 Senior Resident Inspector i R. J. Stransky Jr. , NRC/NRR DB-1 Project Manager i J. R. Villiams, Chief of Staff, Ohio Emergency Management, Agency, l State of Ohio (NRC Liaison) l Utility Radiological Safety Board

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