ML20125B315

Discusses ACRS 82nd Meeting on 670208-11 & 84th Meeting on 670406-08 Re Review of NSP Proposal to Construct Monticello Nuclear Generating Plant,Unit 1 on Site Near Monticello,Mn

ML20125B315
Person / Time
Site:	Monticello
Issue date:	04/13/1967
From:	Palladino N Advisory Committee on Reactor Safeguards
To:	Seaborg G US ATOMIC ENERGY COMMISSION (AEC)
References
ACRS-GENERAL, NUDOCS 9212090306
Download: ML20125B315 (3)

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION -

WASHINGTON. D.C. 10M5 ph APR 131967,

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I Honorable Glenn T. Seaborg Chairman U. S. Atomic Energy Consnission  !

g[6y i Washington, D. C.

Subject:

REPORT ON MONTICEllo NUCLEAR CDiEPATING PIANT, UNIT 1 Daar Dr. Seaborgt i

At its eighty-second meeting, on February 8-11, 1967, and its eighty-fourth meeting, on April 6-8, 1967, the Advisory Comnittoo on Reactor Safeguards reviewed the proposal of the Northern States Power Company to construct the Monticello Nuclear Generating Plant, Unit 1 on a site near Monticello, Minnesota. An ACRS Subcoaxnittee met to roviaw this project on February 3 and March 23, 1967. During its review, the Comittee had the benefit of discussions with representatives of the applicant, the General Electric Company, Chicago Bridge & Iron Company, Bechtel Corporation, Harr.a Engi-neering, General Motors Corporation and the AEC Regulatory Staff and its consultants. 20 Coaxnittee also had the benafit of the documents listed.

The Cor:xnittee had previously conducted a sita review of the proposed plant location and had transmitted its com:ncnts thereon to you by letter dated

. Hay 11, 1966, /

The Monticello plant includes a boiling water reactor which the applicant proposes to operate at an initial power of 1469 MW(t) with a design stretch -

capability for operation at 1674 MW(t). In many respects the plant is simi-lar to the plants proposed for Quad-Cities. However, this plant is the first United States nucicar plant to use a field-erected pressuro vessel. Although field erection of largo pressure vessels is new to the reactor industry, it is not a new proceduro. With the fabrication techniques proposed and with meticulous caro and diligence in the quality control program, it is the opinion of the ACRS that a high-quality field-erected pressure vessel for the Monticollo plant can be constructed. Tha Co::xnittee rococunends that the stress analysis report for the reactor vessel be reviewed by independ-ent exports.

The emergency core cooling systems include a high pressure coolant injection system, a low pressure coolant system, two core spray systems, and a system that vill maka river water available to the feedwater pumps. In the unlikely event of a steam line ruptura external to this reactor containment, steam lina

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Honorable Glenn T. Seaborg ~

APR 131967 isolation valves must close rapidly. It is our understanding- that valves of essentially identical design vill be testod under simulated accident conditions. It is recomended that the Regulatory 8taff satisfy itself with respect to the adequacy of the isolation valve test program'and follov '

' the development of the detailed design of th.a above systems, i

It is of great importance that sufficient electrical power is available at the plant to operato amargancy 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 Committee on Reactor Safeguards baliavas that the items man-tioned above can be resolved during construction and that the proposed re- ,

actor can be constructed at the Monticello site with reasonable assurance that it can be operated at power Icvola up to 1469 MW(t) without undue risk to the health and safety of the public. .

Sincerely yours, Ga;;.I L..J: 0 EY U. J. PEmo ,

N. J. Palladino '

f Chairman Rafarences Attached.

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a Honorable Glenn T. Saaborg APR 131967 References - Monticello .

1, Northern States Power Cccpany letter dated August 1, 1966 to AEC Division of Reactor Licensing. .

2. Cenoral E1cetric Company letter dated August 5,1966 to AEC Division

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of Reactor Licensing transmitting "NSP-Monticello Nucisar Generating Plant, Monticello, Minnesota, Unit 1. Pacility Description and Safety Analysis Report". Volumes I and II,

3. Northern States Power Company letter dated September 8,1966 to AEC i

Division of Reactor Licensing transmitting Amendment No.1.

4. General Elcetric Company latter dated September 9,1966 to AEC Division of Reactor Licensing, with enclosures, ,

5. "Dosign, Fabrication and Erection of the Reactor Vassal", undated, received November 28, 1966.

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

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7. Concral Electric Company letter dated Decambor 30, 1966 to AEC Division

! of Reactor Licensing, with attachments.

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

9. General Elcetric Company letter dated Janaary 10, 1967 to AEC Division of Reactor Licensing with attachments.

'~~ " 10. Northern States Power Company letter datei January 19, 1967 to AEC Division of Reactor Licensing transmicting Amandment No. 5. .

11. General Electric Company letter dated January 21, 1967 to AEC Division

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of Ranctor Licensing with attachmonts. /

12. Northern Statos Power Company letter dated March 3,1967 to AEC Division L of Reactor Licensing transmitting Amendment No. 6.

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

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

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