ML18079A828

Outline of cross-examination of Intervenors Coleman. Questions Relate to Initial Events for TMI Incident, Operation of Reactor Containment Sys During Loss of Feedwater Transient & Operation of Auxiliary Bldg

ML18079A828
Person / Time
Site:	Salem
Issue date:	07/02/1979
From:	Onsdorff K, Vanness S NEW JERSEY, STATE OF
To:
References
NUDOCS 7908220039
Download: ML18079A828 (3)

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMl.'1ISSION BEFORE THE ATOM~C SAFETY AND LICENSING BOARD In the Matter of Docket No. 50-272 Proposed Issuance of Amendment PUBLIC SERVICE ELECTRIC to Facility Operating License

& GAS COMPANY No. DPR-70 (Salem Nuclear Generating Station, Unit No. 1)

INTERVENORS , COLEJ.'1AN OUTLINE OF CROSS EXAMINATION STANLEY C. VAN NESS PUELIC ADVOCATE OF NEW JERSEY DEPARTMENT OF THE PUBLIC ADVOC..'i\TE .

DIVISION OF PUBLIC INTEREST ADVOCA POST OFFICE BOX 141 520 EAST STATE STREET TRENTON, NJ KEITH A. ONSDORFF ASSISTANT DEPUTY PUBLIC ADVOC..;TE

INTERVENORS, COLEMAN OUTLINE OF CROSS EXAMINATION NRC STAFF LICENSEE I. Initiating Events for TMI-2.

A. Loss of feedwater to the steam generators;. its causes, potential for interaction with feedwater for spent fuel pool.

B. Turbine trip; its causes, potential for interaction with electrical energy generating source for the spent fuel pool.

c. Impact of accident initiating events on operating personnel; responses, availability for attention to spent fuel pool transients.

II. Operation of the Reactor Containment Systems During Loss of ~eed-water transient.

A. Operation of the Pressure Relief valves, power source, operating mechanisms, flow rates and direction B. Operation of the Reactor building Containment s~1p, power sources, operation mechanisms, flow rates and direction.

C. Operation of the Containment Isolation valves, power source, operating mechanisms.

III. Operation of the Auxillary Building During Loss of Feedwater Transient.

A. Consequences of Water Levels flooding the building on SFP cooling system.

B. Consequences of radiation levels on the SFP cooling system, operation and maintenance.

IV. Operation of the SFP Building During and After Loss of Feedwater Transient.

A. Series of Reactor vessel hydrogen explosions, impact on t.~e trans-fer tube to SFP, pressure vessel, mainloop piping.

B. Use of SFP for storage of damaged reactor core and/or contaminated cooling water.

KEITH A. ONSDORFF ASSISTANT DEPUTY P{JBLIC ADVOCATE