ML20235D947

Rept to ACRS in Matter of Preliminary Aspects of Comm Ed Application for CP for Proposed Quad Cities Plant

ML20235D947
Person / Time
Site:	Quad Cities, 05000000
Issue date:	07/06/1966
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20235B311	List: IA-87-111, Submits Rept on Plant,As Discussed in ACRS 150th Meeting on 721012-14.Listed Items Can Be Resolved During Const & Facility Can Be Constructed W/Reasonable Assurance for Operation W/O Undue Risk to Public Safety IR 05000254/1972009 IR 05000358/1972003 IR 05000358/1973001 IR 05000358/1973002 IR 05000358/1973003 IR 05000358/1973005 IR 05000358/1973006 IR 05000358/1973007 IR 05000358/1974001 IR 05000358/1974002 IR 05000358/1974003 IR 05000358/1975004 ML20235B308 ML20235B364 ML20235B401 ML20235B405 ML20235B424 ML20235B456 ML20235B461 ML20235B465 ML20235B477 ML20235B488 ML20235B507 ML20235B552 ML20235B582 ML20235B585 ML20235B588 ML20235B605 ML20235B618 ML20235B623 ML20235B649 ML20235B656 ML20235B662 ML20235B670 ML20235B679 ML20235B683 ML20235B687 ML20235B702 ML20235B708 ML20235B713 ML20235B714 ML20235B718 ML20235B720 ML20235B730 ML20235B734 ML20235B748 ML20235B754 ML20235B762 ML20235B764 ... further results
References
FOIA-87-111 NUDOCS 8709250417
Download: ML20235D947 (3)

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l. ' JUL 6 ' 1966 i}lF L ,

E. S. ATOMIC ENERGY COMMISSION DIVISION OF REACTOR LICENSING

' REPORT TO ADVISORY COMMITTEE SAFEGl7ARDS ON RkACTO

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PRELIMINARY ASPECTS OF COMMONWEALTH EDIS ON COMPANY'S APPLICATION FOR A CONSTRUCTION PERMIT FOR ITS PROPOSE UAD-CITIES PLANT

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' Note by the Director, Division of Reactor Li i censing

'Ibe attached, report has been prepared b considerate 6n by the Advisory Committee o meeting. '

y the Division of Reactor Licensing

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SFRGAL-USE-ONLi PRELIMINARY ASPECTS OF COMMONWEALTH EDISON COMPANY'S APPLICATION FOR A CONSTRUCTION PERMIT FOR ITS PROPOSED QUAD-CITIES PLANT Introduction The Commonwealth Edison Company has submitted an application dated May 31, 1966 for a construction permit and facility license for Unit 1 at its Quad-Cities Station. The site is located on the east bank of the Mississippi River about 3 miles north of Cordova, Illinois. The h88 acre site vill have a mini-mum exclusion distance of about 0.25 miles and the nearest residence is at 0 32 miles. The nearest population center, Clinton, Iowa (3h,000) is about 5 miles northeast of the site. The Quad-Cities (Lovenport, Iowa; Rock Islend, Moline, and East Moline, Illinois) are about 20 miles southwest of the site.

The station vill have a rated thermal output of 2255 MW and a net electrical output of*715 MW. Qued-Cities Unit 1 has the same power rating es Dresden Unit 2 and Unit 3 The only design departure from the Dresden units is the use of the Reactor Core Isolation Cooling System in place of isolation ecndensers.

No meetin6s have yet been held with the applicant. Several aspects of the siting and design have been identified and vill be investigated in the course of the staff's review. A list of important areas which will be included in the staff review follows below.

Idscussion

1. The site is located in. an area of relatively high tornado frequency.

Eighteen tornadoes have occurred in the last eighteen years within a 10 sector (3600 square miles) around the site. The staff, with its consultants, vill l

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review the adequacy of the design and specific tornado design criteria to insure that functions importent to the safety of the plant cannot be impaired by j tornado conditions. (Vol. I, Sections I-2 5, II-3 3 2, page V-3-7; Vol. II, l Figures 7, 8).  !

2. The gaseous, liquid, and solid radioactive vaste disposal process and control system vill be investigated to insure that the release of radioactive vaste to the environs is minimized. Particular attention vill be given to the liquid vaste system in view of the public water supply intake approximately i 20 miles downstream of this power station' and the fish and wildlife preserve opposite the plant on the Iowa side of the Mississippi. (Vol. I; Sections VII, j IX-6; Vol. II, Figures 12,24,25,73,74).  !

3 The applicant has proposed that the natural circulation Isoletion Condensers be replaced by the Reactor Core Isolation Cooling (RCIC) System l vhich uses the pressure relief valves to blevdown excess steam to the sup- i pression chamber. Makeup water to the reactor primary would be supplied by pumps driven by steam frca the pressure relief valves. "he system tes the

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advantage that no external or diesel power other than thst required to initiate the system is necessary. The conceptual disadvantage is the " routine" release of radioactive primary system water to the containment efter a turbine trip.

(Vol. I, Sections IV-3, X h; Vol. II, Figure 101; also Dresden 3 Report vol. I, Section V-5.2 for Isolation Condenser).

h. The staff vill continue to investigate the core melt problem end vill pay close attention to the details of the core cooling systems.

_Cpnelusion Based on a preliminary look at the application the staff believes that the unique design and site features identified present no problems which cannot te resolved.

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