ML20129H258

Forwards Technical Review Rept AEOD/T504, Loss of Instrument Air & Subsequent Pressure Transient

ML20129H258
Person / Time
Site:	Callaway
Issue date:	05/17/1985
From:	Freeman R NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Seyfrit K NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20129H262	List: ML20129H258 ML20129H278
References
AEOD-T504, NUDOCS 8506070530
Download: ML20129H258 (1)

Text

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May 17, 1985 AE0D/T504 MEMORANDUM FOR: Karl V. Seyfrit, Chief Distribjwion Reactor Operations Analysis Branch PDR W SRubin Office for Analysis and Evaluation ROAB SF MChiramal of Operational Data ROAB CF KSeyfrit RFreeman TIppolito FROM: Robert G. Freeman, Engineer DZukor CHeltemes Reactor Systems Section 2 RTripathi Reactor Operations Analysis Branch H0rnstein Office for Analysis and Evaluation WLanning of Operational Data

SUBJECT:

TECHNICAL REVIEW REPORT: " LOSS OF INSTRUMENT AIR AND SUBSEQUENT PRESSURE TRANSIENT" The subject Technical Review Report is enclosed for your information.

On July 16, 1984, with Callaway Unit 1 in cold shutdown, a pressure tran-sient occurred in the reactor coolant system (RCS) as a result of a loss of instrument air. The loss of instrument air caused the charging pump to I

, fail to full speed, and isolated normal letdown. A review of the chemical

! and volume control system (CVCS) with respect to the loss of instrument air revealed that this is a design failure mode (i.e., maximum charging and iso-lated letdown) for most Westinghouse CVCS designs.

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Because this is an analyzed event in Callaway's Fina1 Safety Analysis Report and pressure mitigating systems were available and mitigated the event, it is concluded that adequate RCS pressure boundary protection was maintained during this event. Since this event involved a loss of instru-ment air which resulted in an adverse systems interaction during low temperature plant conditions, this event will be included as a part of the AE00 air systems study. No further action on this event is deemed necessary.

Robert G. Freeman, Engineer Reactor Systems Section 2 Reactor Operations Analysis Branch f Office for Analysis and Evaluation of Operational Data

Enclosure:

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