ML19353B136

Submits Supplemental Response to Generic Ltr 89-06 Re SPDS Improvements.Brief Description of Activities Currently Planned to Achieve SPDS Improvements & Schedule for Completion of Each Activity Encl

ML19353B136
Person / Time
Site:	Davis Besse
Issue date:	11/28/1989
From:	Shelton D TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1342, TASK-1.D.2, TASK-TM 1739, GL-89-06, GL-89-6, NUDOCS 8912110249
Download: ML19353B136 (2)

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j TOLEDO EDISON Docket-Number 50-346' A Centerer Eregy Comany License Number NPF DONALO C. SHELTON -

Serial-Number 1739 vca P='om-'*r*

(419)249-2300 November 28,-1989 H

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United States Nuclear Regulatory Commission Document Control Desk Washington,1D. C. 20555 Subjects. Generic Letter Number 89-06 Supplemental Response; Safety Parameter Display System Improvements Gentlemen

.In response to Generic Letter Number 89-06, " Task Action Plan Item-I.D.2 -

Safety Parameter Display System - 10CFR50.54(f)" (Serial Number 1707, dated August-25, 1989), Toledo Edison committed to provide a schedule for implementation of identified Safety Parameter Display System (SPDS)

-improvements at the Davis-Besse Nuclear Power Station. The improvements, as cited in Serial Number 1707, resulted from the detailed review of SPDS i

.considering-the guidance of NUREG-1342 which accompanied Generic Letter Number l-89-06. Attached is a brief description of the activities currently planned to 1

achieve the SPDS improvements and the schedule for completion of each I

activity.

l The Davis-Besse Nuclear Power Station is presently preparing for the upcoming refueling and modification outage scheduled for Febrary-June 1990. As a consequence, the SPDS improvement work has been scheduled considering resource E

availability, particularly in the area of human factors. The attached

' schedule reflects the effect of the ongoing and planned outage-related activities.

-If you have any questions, please contact Mr. R..V. Schrauder, Manager -

Nuclear Licensing, at (419) 249-2366.

-Very truly yours, (A.

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RMC/ssg 89121i0249 391128 ADOCK 050 36 Attachment gDR cc: P. H. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III g

T. V. Vambach, DB-1 NRC Senior Project Manager a

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THE TOLEOO EOISON COMPANY EDISON PLAZA 300 MAOISON AVENUE TOLEDO. OHIO 43652

Dock;t Number 50-346

..? o Lic:ns] Number NPF-3 i

Serir1 Number 1739 Attachment l

Page 1 I

Activity Completion 1.

Provide continuous display (versus 4/1/90 continuous availability) of SPDS in the Control Room.

2.

Perform a human f actss 12/1/90 review of SPDS considering SPDS/ Control Room indications and Abnormal and Emergency Operating Procedures.

3.

. Evaluate existing procedures and/or 2/1/91 the need for administrative guidance on the timely and current status assessment of Critical Safety Functions when the SPDS is and is not available.

4.

Add coatainment isolation, decay heat 3/1/91 removal flow, and main steam line radiation information to SPDS displays.

5.

Upgrade real-time validation of 2/3/92 SPDS parameters, and verification and documentation of SPDS software.

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