ML20125A614

Forwards Order for Mod of License DPR-22,w/encl App I,Issued by Commission on 730824.W/o Encl

ML20125A614
Person / Time
Site:	Monticello
Issue date:	08/28/1973
From:	Gitner G US ATOMIC ENERGY COMMISSION (AEC)
To:	Geyer J, Lazo R, Luton E JOHNS HOPKINS UNIV., BALTIMORE, MD, Atomic Safety and Licensing Board Panel
References
NUDOCS 9212080417
Download: ML20125A614 (1)

Text

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Chron August 28,1973 hk Robert M. Laro, Esq., Chainnan Dr. John C. Geyer,: Chairman-Atomic Safety & Licensing Boand Department of Geography & 5 U. S. Atomic Energy Comalssion Environmental Engineering Washington, D. C. 20545. The Johns Hopkins University 513 Ames Hall Edward Luton, Esq. , Alternate' Baltimore, Maryland Chaiman Atomic Safety & Licensing Board Dr. Walter H. Jordan U. S.-Atonic Energy Commission 881 West Guter Drive Washington,' D. C. 20545 Dak Ridge Tennessee 37830-In the Matter of Northem States Power Company (Monticello Nuclear Power Station) ,

Docket No. 50-263 Gentlemen:

' Enclosed you will find the Order for Modification of License, DPR-22, with the attached Appendix I, issued by the Commission on August 24, 1973. This Order is effective as of date of issue.

Sincerely,

/5 Geoffrey P. G1tner-Attorney for AEC Regulatory Staff cc w/ enclosures-Daniel L. Flicker, Esq.

Joseph Gallo, Esq. 5 Gerald Chernoff, Esq.

Donald E. Nelson, Esq.

Howard J. Vogel, Esq.-

-- Mr. Steve J. Gadler Honorable Jonathan H. Morgan Geoffrey P. Ja . Esq.:

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Form AEC-51, (Rev.9-53) AECM 0240 **o .4s -to-si4as-t ses-ers 9212000417 730828

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PDR ADOCK 05000263 PDR P

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AUG 2 41973

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UNITED STATES OF AMERICA j ATOMIC ENERGY COMMISSION In the Matter of )

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NORTHERN STATES POWER CO. ) Docket No. 50-263

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(Monticello Nuclear Power Station. )

ORDER FOR MODIFICATION OF LICENSE I.

The Northern States Power Cc ("the licensee") is the holder of Facility Licensh DPR-22. License DPR-22 authorizes operation of the Monticello Nuclear Power Station, ("the plant") in Wright County, Minnesota. This license expressly provides, inter alia, that it is subject to all rules, regu-lations and orders of the Commission now or hereinafter in effect.

II .

On November 14, 1972, the AEC Regulatory Staff ("the Staff") issued a report entitled " Technical Report on Densification of Light Water Reactor Fuels" ("the Report") . By letter of November 20, 1972, the Staff requested the licensee to submit analyses and data specified in the report related to determining the consequences of fuel densification for normal operation of

_4 the plant, for operation of the plant during various maneuvers and transients,

\ and under postulated accident situations, including the design basis loss-i

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of-coolant accidents. On December 29, 1972, the licensee provided the requested information including, by reference, the General Electric Company Report NEDM-10735, "Densification Considerations in BWR Fuel Design and

! Performance" dated December,1972. The Staff reviewed the licensee's sub-mission as well as five additional supplements to NEDM-10735 which were submitted by the General Electric Company in response to requests for additional information from the Staff. The latest of these supplements was

. dated July,1973. By letter of July 16,1973,Lthe Staff requested the licensee, inter alia, to furnish additional snalyses regarding the calculated peak

' cladding temperatures during a postulated loss-of-coolant accident. On August 15, 1973, the licensee submitted the requested information including Supplement 6 to NEDM-10735.

On the basis of the Staff's review of the above identified submittals and its evalus don of fuel densification effects upon the operation of boiling water

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i reactors which are reflected in a safety evaluation report relating to the plant dated August 24, 1973, the Staff has determined that changes in the operating conditions for the plant are necessary in order to assure.that the calculated peak cladding temperature of the core of the plant following a postulated loss-of-coolant accident will not exceed 23000F taking into account fuel densification effects as described in the Staff's safety evaluation identified above, and, therefore, that the Technical Specifications of License DPR-22 i

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I should be amended to requiret (1) the immediate control of steady-state power operation so that the average linear heat generation rate of all the rods in any fuel assmebly, as a function of planar exposure, at any axial location, shall not exceed the maximum average planar linear heat gene.ation rate of 11.5 kw/ft; and (2) that during steady state power operation, the linear heat generation rate (LHGR) of any rod in any fuel assembly at any axiallocation shall not exceed the maximum allowable LHGR as calculated

.using the equation for maximum LHGR provided in Limiting Condition for ,

Operation, section 3.5 K of the attached Appendix I.

III.

In view of the foregoing, the Director of Regulation finds that the public health, safety, and interest require that the following Order be made effective immediately. Pursuant to the Atomic Energy Act of 1954, as amended,' the Commission's regulations in 10 CFR 55 2.204 and 50.100 and the license condition noted in Part I above

IT.IS ORDERED THAT:

The Technical Specifications of License DPR-22 are hereby .

changed, to include Limiting Conditions for_ Operation, sections 3.5.J. and 3.5.'K . , and Surveillance Requirements, sections 4.5.J. and 4.5.K. attached hereto as Appendix 1 and the plant shall be operated immediately in accordance therewith .

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Within thirty (30) days from the date of publication of this notice in the Federal Register the licensee may file a request for a hearing with respect to this Order. Within the same thirty (30) day period any other person whose

- interest may be affected may file a request for a' hearing with respect to this Order in accordance with the provisions of 10 CFR $ 2.714 of the Commission's Rules of Practice. If a request for a hearing is filed within the time prescribed herein, the Commission will issue a notice of hearing or an appropriate order.

For further details p'ertinent to this Order see:- the Staff Technical Report on Densification of Light Water Reactor Fuels, November 14, 1972; letter 4

to A. V. Dienhart from A. Giambusso, November 20, 1972; letter to A. Giambusso from L. O. Mayer, December 29, 1972, with enclosure General Electric topical report, Densification Considerations in BRW Fuel Design and Performance; letter to A. V. Dienhart, with enclosure the Staff's GE Model for Fuel Densifi-cation, July 16,.1973; letter to D. Zieman from L. O.' Mayer, August 15, 1973; the Staff Technical Report on Densification of General Electric Reactor Fuels, August 23. 1973; the Staff Safety Evaluation of the Fuel Densification Effects on the Monticello Nuclear Power Station, August 24, 1973; all of which are available for public inspection at the Commission's Public Document Room, a

1717 11 Street, N. W. , Washington, D. C.

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5-Copies of these documents may be obtained upon request addressed to the Deputy Director for Reactor Projects, Directorate of Licensing, U. S. Atomic Energy Commission, Washington, D. C. 20545.

FOR THE ATOMIC ENERGY COMMISSION  ;

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O Dir'ectorb Regul }.

Dated at Bethesda, Maryland this 24th day of August,1973 i

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