ML20196G918

Forwards Application for Amend to License NPF-3,redefining Relationship Between Total Operable Main Steam Safety Valve Relieving Capability Per Steam Generator & Reduced Reactor Protection Sys High Flux Trip Setpoint.Fee Paid

ML20196G918
Person / Time
Site:	Davis Besse
Issue date:	03/04/1988
From:	Shelton D TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20196G923	List: ML20196G918 ML20196G933 ML20196G955
References
1487, TAC-67394, TAC-M68250, NUDOCS 8803100026
Download: ML20196G918 (2)

Text

,\ -

t> A .

TOLEDO EDISON nc warn c m DONAto C. SHEUDN w , n.- %

Docket No. 50-346 H "l ? " ""

License No. NPF-3 Serial No. 1487 March 4, 1988 United States Nuclear Regulatory Commission Document Control -k Washington, D, C. 20555

Subject:

License Amendment Application to Reviee Main Steam Safety Valve Relief Capacity /High Flux Trip Setpoint Relationship and Restate ASME Code Requirements for Main Steam Safety Valves (TAC No. 67394)

Centlemen:

The enclosed application requests that the Davis-Besse Nucient Power Station (DBNPS), l' nit No. 1 Operating License, Appendix A. Technical Specifications be revised to reflect the attached. The proposed changes involve Technical Specifications Section 3/4.7.1.1. Turbine Cycle-Safety Valves; Table 3.7-1. Maximum Allowable High Flux Trip Setpoint With Inoperable Steam Line Safety Valves; Table 4.7-1. Steam Line Safety Valves Per Steam Generator; and Bases Section 3/4.7.1.1. Turbine Cycle -

Safety Valves.

The proposed changes would incorporate into the Limiting Condition for Operation a redefinition of the relationship between the total operable main steam safety valve relieving capability per steam generator and the reduced Reactor Protection System High Flux Trip setpoint. This redefini-tion would allow the high flux trip setpoint reduction due to an inoperable safety valve (s) to directly reflect the actual loss of steam relieving capability, versus the unnecessarily conservative relationship (resulting in an increased reactor power penalty) presently eeplcyed in the Technical Specifications. The p oposed changes would also allow the main steam safety valve setpoints and minimum number of valves to be more clearly stated consistent with the requirements of American Society of Mechanical Engineers (ASMF) Boiler and Pressure Vessel (B&PV) Code,Section III, 1971 Edition, in order that greater flexibility in valve set pressure and replacement enn be attained while maintaining required overpressure 001  !

l protection for the steam generators, t

'(

O !

8C03100076 090304 I PDP ADOCK 05000346 Wl C'ht i i

e ncn 5*lU THE TOLEDO EDSON COWANY EDGON PLMA 300 N'AD: SON AVENUE TOLEDO. DHO 43G52

( .

.. '.i ,

Dockst No. 50-346 License No. NPF-3 Serial No. 1487 PaFe 2 This change must be issued prior to startup from the fifth refueling outage, presently scheduled for August 1988. However, expeditious issuance by June 1, 1988 is requested to support the desired main steam safety valve adjustment. As discussed with Mr. A. W. DeAgazio, NRC Project Manager for DBNPS, Toledo Edison has requested a meeting with the NRC staff to discuss these proposed changes. This meeting has been tentatively scheduled for March 17, 1988.

Enclosed is a check for $150.00 as required by 10CFR170.12(c) for a License Amendment Application.

Very truly yours, f /

RMC:bam ec: DB-1 Resident Inspector A. B. Davis, Regional Adninistrator (2 copies)

A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager State of Ohio