ML20011A842

Notifies of Resolution of Four SER Open Items.Items Include Low Temp Overpressure Protection Alarm & Shutdown Cooling Sys Isolation Valve Position Alarm

ML20011A842
Person / Time
Site:	05000470
Issue date:	10/30/1981
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
LD-81-076, LD-81-76, NUDOCS 8111030271
Download: ML20011A842 (2)

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C-E Power Systems Tel. 203/688 1911 Combustion Engineenng. Inc. Telex: 99297 1000 Prospect Hill Road Windsor. Connecticut 06095 ,

POWER H SYSTEMS Docket No.: STN-50-470F October 30, 1981 LD-81-076 Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Suaject: CESSAR-F Safety Evaluation Report

Dear Mr. Eisenhut:

During the review of the Combustion Engineering Standard Safety Analysis Report -

FSAR (CESSAR-F), NRC staff reviewers have identified potential open items for the CESSAR-F Safety Evaluation Report. Resolution of four (4) of these items is provided below:

1. Low Temperature Overpressure Protection (LTOP) Alarm CESSAR-F will be amended to include a low temperature overpressure protection alarm to indicate in the event that a LTOP were to occur.

2. Shutdown Cooling System (SDCS) Isolation Valve Position Alarm CESSAR-F will be amended to include an alarm on SDCS isolation valve position. The alarm will alert the operator if the SDCS isolation valves are not properly aligned for LTOP rrotection, when required.

3. Small Steam Line Break 'gdiological Consequences CESSAR-F will be amended 1 ) provide the Small Steam Line Break analyses, as.ag eed in the meeting with Director of Division of Systems Integration on September 17, 1981. The analyses will show that the calculated radiological release dose will meet the SRP acceptance criterion.

9111030271 POR ADOCK 0 0 h Ci PDR 0 E i

Mr. Darrell G. Eisenhut 4

4. Steam Cenerator Tube Rupture - Radiological Consequences CESSAR-F will be amended to provide a revised analysi; of

4. the Steam Generator Tube Rupture with Loss of Offsitt Power i event, .using more realistic assumptions. The analysis will show that the calculated radiological release dose will. meet the SRP acceptance criterion.

.This information is provided to enable the NRC staff to satisfactorily complete the CESSAR Safety Evaluation Report sections that address these issues. If I

, can be of any aaditional assistance in this matter, please contact me or Mr. G. A.

Davis of my staff at (203)688-1911, Extension 2803.

Very truly yours, COMBUSTION ENGINEERING, INC.

~h. 2; senerer 7 p

Director Nuclear Licensing i-l AES:dac i

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