U-600171, Forwards Rev 0 to Procedure SPDS-DST-001, SPDS Dynamic Simulation Test Plan Per 850612 Commitment Re NUREG-0737, Item I.D.2.Test Scheduled for Late Aug.Results Will Be Submitted to NRC by 851004
| ML20128L992 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/09/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20128L997 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-TM U-600171, NUDOCS 8507110520 | |
| Download: ML20128L992 (2) | |
Text
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U-600171 L30- 85(07-09)-L P04 85(07-09)-L 1A*120
. ILLINDIS POWER 00MPANY IP CLINTON POWER STATION, P.o. BCX 678. CLINTON ILLINOIS 61727 July 9, 1985 Docket No. 50-461 Director of Nuclear Reactor Regulation Attn:
Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Safety Parameter Display System Dynamic Simulation Test Plan NUREG-0737, TMI Action Plan Item I.D.2
Dear Mr. Butler:
IP Letter U-600066, dated June 12, 1985, provided the NRC Staff with responses to remaining concerns associated with the design and implementation of the Clinton Power Station (CPS) Safety Parameter Display System (SPDS).
In the CPS response to NRC General Comment #1, Illinois Power reiterated that dynamic simulation testing of the CPS SPDS would be performed and committed to provide the Staff with the plan for these tests by July 1, 1985.
Attached is the " Safety Parameter Display System Dynamic Simulation Test Plan", Revision 0, dated June 13, 1985. This document describes the purpose, scope, methodology, performance and evaluation criteria for the Dynamic Simulation Test (DST). The DST will be performed on the CPS simulator using the recently revised SPDS display formats. The primary purpose of the SPDS DST is to demonstrate, through direct
" man-in-the-loop" simulation of potential plant transient / accident scenarios, that the SPDS design objectives related to critical safety function detection / resolution, subsequent execution of the symptomatic Emergency Operating Procedures, and the adequacy of the information displayed meet the requirements for SPDS. This will be accomplished, as described in the DST plan, through separate assesements of two Main Control Room operating teams (of five individuals each), for scenarios where the SPDS is available and unavailable. Following these tests, as part of the evaluation process, feedback will be solicited from the operating teams on various aspects of their individual and team scenario responses and the overall usefulness of the SPDS.
Currently, the DST is scheduled to take place in the late August timeframe. The results of the DST, along with the corresponding ratings and evaluations, will be documented and submitted to the Staff by October 4, 1985.
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U-600171 L30- 85 ( 07-09)-L P04-85 ( 07-09)-L 1A.120 If you should have any questions on the SPDS DST plan, please call me.
Sincerely yours, A ll-D.
bergf F. A.
yang Director - Nuclear Licensing and Configuration Nuclear Station Engineering TLR/ lab Attachment ec:
B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III USNRC Illinois Department of Nuclear Safety