ML20067C091

Forwards Application for Amend to License NPF-3,changing Tech Spec 3/4.1.1.3 Re Reactivity Control Sys Moderator Temp Coefficient & 6.9.1.7 Re Core Operating Limits Rept,Per Generic Ltr 88-16

ML20067C091
Person / Time
Site:	Davis Besse
Issue date:	02/06/1991
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20067C093	List: ML20067C091 ML20067C095 ML20067C099
References
1902, GL-88-16, TAC-M79449, NUDOCS 9102110191
Download: ML20067C091 (2)

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? CENTERIOR ENERGY Donaed C. Shelton 330 Ma$2n Avenue l Vee PrevJent Nucles Toledo. OH 43652 0001 l DMs Dess (419)249 2300 Docket Number 50-346 License Number NPF-3 Setfal Number 1902 February 6, 1991 linit ed St ates Nuclear Regulatory Conenienion Document control Desk Vashington, DC 20S$5 Subject License Amendment Application to Revise Terhnical Specification 3.1.1.3, Hoderator Temperature Coefficient (TAC Number M79449)

Centlement inclosed is an application for an amendment to the Davis-Besse Nuclear Power 9tation (DBNPS). Unit Number 1 Operating License Numbet ""F-3 Appendix A.

Technical Specifications to reflect the attat.hed change. The proposed change involves Technical Specification (TS) 3/4.1.1.3, Reactivity Control Systems -

Hoderator Temperature Coefficient, and Technical Specification (TS) 6.9.1.7, Core Operating Limit s Report .

This requent proposes revising Limiting Condition for Operation 3.1.1.3c to refer to the DBNPS Cote Operating Limits Report for the value of the Negative Moderator Temperature Coefficient limit. Also Technien1 Specification 6.9.1.7, Cote operating Limits Report, will be revised to include 3.1.1.3c, the Negative Moderator Temperatute Coefficient Limi* In its requitements.

Toledo Edinon's rerponse to Generic Letter 88-16 Removal of Cycle-Specific Parameter Limit s f rom Technical Specifications. (Toledo Edison letter Serial Number 1668, dated June 16, 1980). originally requested removing Technical Specification 3.1.1.3 from the Technical Specifications in its entitety. The Nuclear Regulat ory Conenission St af f, in a telephone call, concurred with the telocation of the Negative Moderator Temperature Coef ficient Limit but requested that the positive upper bounds of the Moderator Temperature C3 efficient remain in the Technical Specification 9. Rather than divide the Laiting Condition for Operation between the Technical Specifications and the Cot

• Operating Limits Report (COLR), Toledo Edison elected at that time to I

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.=> Docket Number $0 346 c License Number NPF.3 Scalal Number 1902

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. retain the Specification as it now exists. This communication is documented in  !

j -. Toledo Edison letter Serial Number 1691 to the NRC dated August 21, 1909. This letter was a resubmittal of Serial 1668 removing the request to relocate the moderator temperature coefficient technical specification.

Due to the installation of extended operating cycle cores, it has become 4

necessary to recalculate the 1!mit of the Negative Moderator Temperature coefficient for each core cycle. The limit of the Negative Moderator )

Temperatute Coefficient may be different for each operating cycle. With the '

Negative Hoderator Temperature Coef ficier.t contained in the Technical Specifications it still is necessary to submit a license amendment application for each new reload cycle if the limit changed. To reduce this number of future required license amendment applications, Toledo Edison now requests that the Negative Hoderator Temperature Coefficient portion of Technical Specification 3.1.1.3 be relocated to the Core Operating Limits Report.

Technical Specification 6.9.1.1 is proposed to be revised to reference the Negative Moderator Temperature Coefficient Limit. This then is consistent with the intent of HRC Ceneric Letter 80-16 and HRC staff desires to retain the positive upper bounds of the Hoderator Temperature Coefficient.

As previously discussed with the NRC Staff. Toledo Edison requests that this amendment be issued by the NRC by March 29, 1991, which la prior to the performance of the associated survelliance testing required after reaching a rated thermal power-equilibrium boron concentration of 300 ppm (Surveillance Requirement 4.1.1.3.2b).

g If you have any questions regarding this amendment request, please cent.act 6 Ht. d, W. Schrauder, Manager - Nuclear Licensing, at g419) 249-2366. ,

Very truly yours, f /

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Enclosure cci DB-1 NRC Senior Resident Inspector _ .

A. B. Davis, regionni Administrator NRC Region III Di C. D1 Ianni, DB-1 NRC Senior Project Manager State of Ohio General J. Williams, Chief of Staff, Adjutant General State of Ohio Utility Radiological Safety Board f

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