ML20137M084

Provides Util'S Overall Plans & Schedule for Completion of Dbnps,Unit 1 Design Basis Validation Program as Described in Ltr Dtd 970211

ML20137M084
Person / Time
Site:	Davis Besse
Issue date:	03/31/1997
From:	Jeffery Wood CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2455, NUDOCS 9704080010
Download: ML20137M084 (4)

Text

F

. re CENTERDOR

- ENERGY 5601 N. State Route 2 419-24fr2300 John K. Wood Oak Hartor,OH 43449 FAX: 419 3218337 Vce Presdent . Nuclear Davis-Besse Docket Number 50-346 License Number NPF-3 Serial Number 2455 March 31, 1997 o

Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001

Subject:

Plan and Schedule for Completion of the DBNPS Design Basis Validation Program ,

l Ladies and Gentlemen:

This letter provides Toledo Edison's (TE's) overall plans and schedule for completion of the Davis-Besse Nuclear Power Station (DBNPS), Unit 1 Design Basis Validation Program as described in TE's letter dated February 11, 1997 (Serial Number 2438).

As discussed in the February 11, 1997 letter, the DBNPS has completed much of the effort required to compile the DBNPS design basis through the .

establishment of the DBNPS " Configuration Management Program" and through the development of " System Descriptions" and the " Design Criteria Manual".

In a continuing effort to strengthen the design basis, the DBNPS has commenced a Design Basis Validation Progranf. The purpose of this program is to provide further assurance that design basis information, specifically design basis calculations, are consistently reflected in the physical plant and controlled documents used to support plant operation, and contain sufficient information to support the underlying assumptions contained in the calculations.

The validation effort will be conducted consistent with the guidance of Nuclear Utility Management and Resources Council (NUMARC) 90-12, " Design Basis Program Guidelines." The system's design basis documentation will be reviewed to validate the safety design basis through a review of the v "PS 3 Final Safety Analysis Report (FSAR), the Updated Safety Analysis Mport (USAR), the NRC's Safety Evaluation Report (NUREG-0136) and its supplement g j

\

for the Operating License, the Operating License Technical Speifications g 9704080010 970331  :"

PDR ADOCK 05000346.

P PDR j $,EE; %,55%

Dockat Numbar 50-346 Licensa Number NPF-3 Serial Number 2455 Page 2 (TS), and TS amendments Safety Evaluation Reports. Analyses and calculations will be reviewed to identify component performance and analytical requirements and key values and parameters essential in determining component performance requirements. Finally, the existing calculations will be reviewed for adequacy and to verify that the parameters are properly implemented in the plant (i.e., procedures, drawings, and setpoints) validating that design basis information is translated into DBNPS procedures. Missing analyses or calculations will be generated, as necessary.

The scope of the program will include, at a minimum, the 10 CFR 50.65 Maintenance Rule risk significant systems and selected topical areas as listed on Attachment 1. The DBNPS Design Basis Validation Program is scheduled to be completed by December 17, 1999.

Should you have any questions or require additional information, please contact Mr. James L. Freels, Manager - Regulatory Affairs at (419) 321-8466.

Very truly yours, JCS/laj attachment cc: A. B. Beach, Regional Administrator, NRC Region III S. J. Collins, Director, Office of Nuclear Reactor Regulation A. G. Hansen, DB-1 NRC/NkR Project Manager S. Stasek, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board

.- .+

~

Docket Number 50-346 Licenze Numbar NPF-3

'Sarial'Numbar 2455 Attachment Page 1 DAVIS-BESSE NUCLEAR POWER STATION DESIGN BASIS VALIDATION PROGRAM Systems and Selected Topical Areas The following systems were ' selected based on being a Maintenance Rule -(10 CFR'50.65)-Risk Significant System or topics which are covered by the.10 CFR 50,' Appendix A, General Design Criteria:

~

• Safety Features Actuation System

- 4160 Volt Electrical System

- Emergency' Diesel Generator / Station Blackout Diesel Generator

- 125/250 VDC Electrical System

- 240/120 VAC Instrument Electrical System

- 480 Volt Electrical System

- Steam and Feedwater Rupture Control System

- Anticipatory Reactor Trip Systems

- Reactor Protection System

- Diverse Scram System

- Auxiliary Feedwater System / Motor Driven Feedwater Pump / Condensate Storage System Emergency Ventilation System

- Containment Hydrogen Control System High Pressure Injection System Decay Heat Removal System

- Spent Fuel Pool Cooling System

- Main Steam System

- Main Feedwater/ Condensate System

- Component Cooling Water System

- Service Water System / Dilution Pump /ECCS Room Coolers

- ' Containment Air Cooling System

.-=-

a' Dockst Number 50-346 LicInra Number NPP-3 Scrial Numb:r 2455 Attachment Page 2

- - Containment Vacuum Relief Valves ,

a Control Room Normal and Emergency Ventilation Systems

- Chemical Addition System

- Reactor Coolant System

- Containment Spray System

- Core Flooding System Steam Generators

- Make Up System

- Integrated Control System Station and Instrument Air

- Switchyard / Transformers

- Low Voltage Switchgear HVAC ,

Service Water Ventilation

- Flooding

- High Energy Line Break Seismic Missiles r

e w