ML20247D358

Provides Addl Info Re Util 890221 Application for Amend to License NPF-3,per 890510 Telcon.Amend Increases Reactor Protection Sys Response Time Requirement for High Flux/Number of Reactor Coolant Pumps on Trip Function

ML20247D358
Person / Time
Site:	Davis Besse
Issue date:	07/19/1989
From:	Shelton D TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1690, TAC-72015, NUDOCS 8907250174
Download: ML20247D358 (2)

Text

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TOLEDO

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. a cm,- tnm c-on, DONAU) C. SHELTON ve.p ,,,aa -n o w Docket Number 50-346 ""UN'*3" License Number NPT-3 Seri.al Number 1690

" July 19, 1989 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ect: License Amendment Application to Increase the Reactor Protection System Response Time Requirement For the High Flux / Number of Reactor.

Coolant Pumps on Trip Function, Supplemental Information (TAC Number 72015)

Gentlemen:

Toledo Edison submitted a license amendment request (Serial Number 1634, dated February 21, 1989) which proposed changes to the Davis-Besse Nuclear Power Station, Unit Number 1 Operating License, Appendix A, Technical Specifications Section 3/4.3.1.1, Reactor Protection System Instrumentation, Table 3.3-2, Reactor Protection System Instrumentation Response Times. The request

. proposed-an increase in the response time requirement for the High Flux / Number of Reactor Coolant Pumps On (power / pumps) trip function of the Reactor Protection System (RPS) provided in Table 3.3-2 from 451 milliseconds to 631 milliseconds. 'The proposed change is based on an analysis performed with a Nuclear Regulatory Commission (NRC) topically approved code system named VIPRE.

The proposed changes were discussed in a telephone conference call between Toledo Edison personnel and.NRC staff personnel on May 10, 1989. As a result of the telephone conference call, Toledo Edison committed to supply the following information to supplement the original request:

A description of the type of noding studies which were performed.

An explanation of why VIPRE is reasonable for this application.

Acknowledgment that the Critical Heat Flux (CHF) correlation for VIPRE is different from that of LYNXT and discussion that VIPRE provides the 95/95 confidence level for CHF.

- Confirmation statement that this is a one time specific use of VIPRE and Toledo Edison agreement that additional justification vill be necessary in order to use VIPRE in other applications.

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THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MAD! SON AVENUE TOLEOO, OHIO 43652 I

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• Licensa Nucbar NPF-3 S: rial Numb:r 1690

. -Page 2 Toledo Edison confirms that this is a one time specific use of VIPRE and that further justification vill be needed to use VIPRE in other applications. The remainder of~the supplemental information vill be provided by Toledo Edison in a submittal to the NRC by August 31, 1989. Toledo Edison requests the NRC staff continue to process the existing amendment request in order that the amendment can be issued by December 31, 1989, to support Davis-Besse Nuclear Power Station (DBNPS) outage work during the sixth refueling outage and startup for Cycle 7 operation.

Should further information be required, please contact Mr. R. V. Schrauder, Nuclear Licensing Manager, at (419) 249-2366.

Very truly yours, GBK/dlm cc P. M. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III T. V. Vambach, DB-1 NRC Senior Project Manager State of Ohio

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