ML20056B605

Summarizes ACRS 82nd Meeting on 670208-11 to Review Util Proposal to Construct Plant on Site Near Monticello,Mn

ML20056B605
Person / Time
Site:	Monticello
Issue date:	04/13/1967
From:	Palladino N US ATOMIC ENERGY COMMISSION (AEC)
To:	US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20056B598	List: ML20056B597 ML20056B605
References
NUDOCS 9102070596
Download: ML20056B605 (3)

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20L45 APR 131967 Honorable Glenn T. Seaborg Chairman U. S. Atomic Energy Comunission Washington, D. C.

Subject:

REPORT ON HONTICELI.0 NUCI. EAR GENERATING PIANT, UNIT 1 Dear Dr. Seaborg At its eighty-second meeting, on 7cbruary meeting, on April 6-8, 1967, 8-11, 1967, and its afghty f- ourth reviewed the proposal of the Northern States Power Company to con the Monticello Nuclear Cencrating Plaat, Unit 1 on a site near Minnesota. M onticello, and March 23, An ACRS Subcocnitts 4 met to reviaw this project on February 1967. -

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During its review, the Coenittee had the benefit of discussions with representatives of the applicant, the General Electric Company, Chicago Bridge & Iron Company, Bechtel Corporation , Harza Engi-neering, General Motors Corporation and the AEC Regulatory Staff and its consultants.

The Cocnittee Thehad Cocnittee previouslyalsoconducted had the benefit of the documents a site review ofnthe proposed listed.

l pla location m y 11, 1966, and had transmitted its comments thereon to you by letter dated

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The Monticello plant includes a boiling water reactor which the appli cant proposes to operate capability for operation at 1674 MW(t). at an initial power of 1469 MW(t) with a design stretch  !

lar to the plants proposed for Quad-Cities.In many respects the plant is simi-United States nucicar plant to use a ficid-erected pressure vesselHowever, Although this plan field erection is not a new procedure. of large pressure vessels is new to the rasetor indust ry, it meticulous care and diligence in the quality ,control it is the programWith the f opinion the Monticello of the ACRS plant can bethat a high-quality field-crected pressure vessel for constructed.

the experts, ent stress analysis report for the reactor vessel be revieThe Co mittee reco::nends that wod by independ- .

The emergency core cooling that vill make river water available to the feedwater pumps systems include ection m

a high event of a steam line rupture external to the rasctor containmentIn the unlikely

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o o Bonorable Glenn T. Seaborg APR 131967 (

isolation valves cust close rapidly. It is our understanding chat valves of essentially idratical design will be teste under siumisted accident conditions. It ii. recomended that the Regulatory Staff satisfy itself with respect to the adequacy of the isolstica valve test program and follow the development of the detailed design of the above systems.

It is of great importance that sufficient electrical p,;wer is available at

' the plant to operate emergency core cooling equipment in the unlikely event of loss of normal coolant to the core. Although the reliability of off-site power was stated to be very high, it is the recommendation of the ACRS that the Monticello plant include a second diesel generator of the same capacity as the one proposed.

The Advisory Co::mittee on Reactor Safeguards believes that the items men-tioned above can be resolved during construction and that the proposed re-actor can be constructed at the Monticello site with reasonable assurance j that it can be operated at power levels up to 1469 m'(t) without undue risk to the health ad safety of the public. .

Sincerely yours.

Q za L :. . ~ .a E7

n. 3. ?;& wa N. J. Falladino f Chairman References Attached.

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i Honorable Clenn T. Seaborg 3 APR 131967 References - Monticello -

1 Northern States Power Company letter datei August 1,1966 to AEC Division of Rasctor Licensing.

2. General Elcetric Company letter dated Augast 5,1966 to AEC Division of Reactor Licencing transmitting "NSP-Meraticello Nucisar Generating Plant, Monticello, Minnasota, Unit 1, facility Description and Safety v Analysis Report", Volumes I and II.

3. Northern States Pcwar Company letter dated September 8,1966 r4 .

Division of Reactor Licensing cransmitting Amendment No.1.

4. General Electric Company letter dated September 9,1966 to AEL :,&f; ton of Reactor Licensing, with enclosures.

5. " Design, Fabrication and Erection of the leactor Vessal", undated, received November 20, 1966.

6. Northern States Power Compasy letter dated December 29, 1966 to AEC Division of Reactor Licensing trancmitting Amendment No. 3.

7. General Electric Company letter dated Decamber 30, 1966 to AEC Division of Reactor Licensing, with attachments.

8. Northern States Power Company letter dated January 10, 1967 to AEC 1 Division of Reactor Licensing transmitting Amendment No. 4.

9. General Electric company letter dated Janaary 10, 1967 to AEC Division

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, of Reactor Licensing with attachn.cnts.

, 10. Northern States Power Company letter datei January 19, 1967 to AEC Division of Reactor Licensing transmitting Amendment No. 5.

11. General Electric. Company letter dated January 21, 1967 to AEC Division of Reactor Lisensing with attach:nants. /

12. Northern States Power Company letter datei March 3,1967 to AEC Division 4 of Reactor Licensing transmitting Amendment No. 6.

13. " Amendment 6, Answers to AEC Questions", dated March 7,1967.

14. " Amendment 6. Errata and Addenda Sheet", with attachments, dated March 8, 1967.

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