ML20126B146
| ML20126B146 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/24/1973 |
| From: | Bender P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | OFFICE OF THE FEDERAL REGISTER |
| References | |
| NUDOCS 9212210422 | |
| Download: ML20126B146 (1) | |
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N Dt UNITED STATES ATOMIC ENERGY COMMISSION O
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' NAsyINGTON. c.c. Se645 August n, 1973 flirector office of the Federal Register Nattonal Archives and Records Service l
Washington, D. C.
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!) car Sir:
At tached for publication in the Federal Register are an original and two cert i f ied copies of a docuxnent entitledt NOR1 TEN WTATM IWER 6 ORnm HE W3DIFICATICE OF LICM please banale as Sched d e I for Per telects with Mrs. Rosenberg,8,1973 publication cus Tuesdny, AuEust 2 Publication of the above document at the earliest possible date would be appreciated.
Sincerely, Paul C. Bender Secretary of the Comunission
Enclosures:
Original and 2 certified copies bec: docket Clerk (Dir. of Reg.)
Information Services g
Legal Files (OCC)
Of fice of Congressional Relationa Cr Files (SECY)
Public Proceedings Branch (SECY)
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.TfD b UNITED STATES OF AMERICA y-?
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NORTilERN STATES POWER CO.
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(Monticello Nuclear Power Station,
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ORDER FOR MODIFICATION OF LICENb3 s
1.
The Northern States Power Co. ("the licensce") is the holder of Facility License DPR-22. License DPR-22 authorizes operation of the Monticello This Nuclear Power Station, ("the plant") in Wright Coanty, Minnesota.
license expressly provides, inter alla, that it ie. subject to all rules, regu-lations and orders of the Commission now or hereinafter in effect.
II.
I On November 14, 1972, the AEC Regulatory Staff ("the Staff") issued a i
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. report entitled " Technical Report on Densification of Light Water Reactor Fuch;" ("the Iteport"). By letter of November 20, 1972, the Staff requested the licensee to submit analyses and data specified in the report relatec} to determining the consequences of fuel densification for normal operation of the plant, for operation of the plant during various maneuvers and transients, and under postulated accident situations, including the design basis loss-l/
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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, "Dencification Considerations in BWR Fuel Design and Performance" dated December,1972. The Staff review'ed the licensce's sub-mission as well as five additional supplements to NEDM-10735 which were submitted by the General Electric Company in response to reque'sts for additional information from the Staff. The latest of these supplements was dated July,1973. By letier of July 16, 1973, the Staff requested the licensec, inter alia, to furnish additional analyses regarding the calculated peak t
l On cladding temperatures during a postulated loss-of-coolant accident.
August 15, 1973, the licensee submitted the requested information including s
l Supplement 6 to NEDM-10735.
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,f On the basis of the Staff's reviow of the above identified submittals and its' 1
-i cvaluation of fuel densification effects upon the operation of boiling water 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 i:
operating conditions for the plant ar'e necessary in order to assure that the
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postulated loss-of-coolant accident will not exceed 23000F taking into account 1
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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should be amended to require: (1) the immediate control of steady-state power operation to that the average linear heat generation rate of all the rods 'n any fuel asumebly, as a function of planar exposure, at any axial i
location, shall not exceed the maximum average planar linear heat generation rate of 11.5 kw/ft; and (2) that during steady state power operation, the linear heat generation rate (LHOR) of any rod in any fuel assembly at any axial location shall not exceed the maximum allowable LilGR as calculated using the equation for maximum LliGR provided in Limiting Condition for Operation, cection 3.5.K of the attached Appendix 1.
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.
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Commission's regulations in 10 CFR $$ 2.204 and 50.100 and the license
' condition noted in Part I above b
IT IS ORDERED TilAT:
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The Technical Specifications of License DPR-22 are hereby changed, to include Limiting Conditions for Operation,
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sections 3.5.J. and 3.5.K., and Surveillance Requirements, ucctionn 4.5.J. and 4.5.K. attached hereto as Appendix I and the plant shall be operated iminediately in accordance therewith.
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Within thirty (30) days from the date of publication of this notice in the il i
dgl,1 Winter the licensee may file a request for a hearing with respect to thiu Order.
Within the same thirty (30) day period any other pert.on 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 x
Rules of Practice,
,a if a requent for a hearing is filed within the time prescribed herein, the Commission will issue a notice of hearing or an appropriate'oi der.
For further details pertinent to this Order see:
the Staff Technical Report on Densification of Light Water Reactor Fuels, November 14, 1972; letter to A. V. Dienbr.rt from A. Giambusso, November 20, 1972; letter to A. Giambusso from L. O. Mayer, December 29, 1972, with enclosure General Electric top report, Densification Considerations in BRW Fuel Design and Performance; letter to A. V. Dienhart, with entlosure the Staff's GE Model for Fucl Densifi-cation, July 16, 1973; letter to D. Zieman from I,. O. Mayer, Aut;ust 15, 1973; i
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 StatiIn, August 24, 1973; all of which are available for public inspection at the Commission's Public Document Room, 3
1717 11 Street, N. W., Washington, D. C.
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s Copies of these documento may be obtained upon request addressed to the Deputy Director for Reactor Projects, Directorate of Licensing, U. S. Atomic Energy Com:-.ission, Washington, D. C.
20545.
4 FOR Tile ATOMIC ENERGY COMMISSION
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Director of Regul i})
'b Dated at Bethesda, Maryland this 24th day of August,1973 e
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!t0TICE OF AVAll ABILITY Copies of Appendix I to Order for flodification of License, dated August 24, 1973, are available for public inspection at the Conrnission's Public Document Room,1717 H Street, fl.W.,
Washington, D. C., or 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.
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