ML20127H483

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Order for Mod of License to Require Licensee to Submit Reevaluation of ECCS Cooling Performance Prior to Any License Amend Authorizing Any Core Reloading
ML20127H483
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/27/1974
From: Case E
US ATOMIC ENERGY COMMISSION (AEC)
To:
NORTHERN STATES POWER CO.
Shared Package
ML20127H472 List:
References
NUDOCS 9211180524
Download: ML20127H483 (12)


Text

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. 4 CilTED STATES OF /J' ERICA ATOMIC ESEEG7 C0!?11SS10:

In the !btter of )

)

0FliiE7J; STATES PO'CR CO
TL'Y ) Docket
;o. 50-263

)

(Monticello iiuclear Generating )

Plant)

ORDER FOR MODIFICATION OF LICENSE I.

. The :;orthern States Power Cocpany (the licensee) is the holder of f acility license DPR-22, khich authorizes operation of the Monticello liuclear Generat4 .ng Plant in Monticello, Wright County , Minnesota.

This license provides, among other things, that it is subject to all rul a . regulations and orders of the Co ission now or hereafter in effect.

II.

Pursuant to the requirements of the Co ission's regulations in 10 CFR 5 50.46, " Acceptance Criteria,and E=ergency Core Cooling Systens for Light .

Water Nuclear Power Reactors", on August 20, 1974 and December 11, 1974, the licensee submitted an evaluation of ECCS cooling performance calculated in accordance with an evaluation model developed by the General Electric Company . ("the 9211180524 741227 PDR ADOCK 05000263 P PDR ,

. , _ _a, 21 .

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-vendor"), along with certain proposed technical specifications necessary-to bring reactor operation-into confor=ity:with the results .of the ,

evaluation.

The evaluation model developed by the vendor has been analyzed by the Regulatory staf f for conformity with the requirements of 10 CFR Part' 50,_

Appendix K, "ECCS Evaluation Models". The Regulatory staff's evaluation of the vendor's model is described in two previously published documents:

L Status Report by the Directorate of Licensing in the Matter of General Electric ECCS Evaluatico Model Confor ance to 10 CTR Part 50, Appendix K, p ,

issued October 15, 1974, and a Supplement to the Status Report, issued-November 13, 1974. Based on its evaluation, the Regulatory staf f has

~

concluded that the vendor's evaluation-codel was not in complete l conformity with the requirements of Appendix' K and that certain I

nadifications described :ht the above-mentioned documents were required-in order to achieve such conformity. The Eegulatory staf f assess =ents vere reviewed.by the Co=nission's Advisory Co==ittee on Reactor Safeguards in meetings held on October 26, 1974 and November 14, 1974.

In its Report to the Chairman of the AEC, d ted November 20,-1974, the

( Advisory _ Co==ittee has concluded that "the four light-water, reactor vendors '

i . .

havedevelopedEvaluationPapelswhich,withadditionalcodifications required by :the Regulatory staff, will conform to Append'ix K to Part .50". . ,

l l

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E.44q Since the licensee's evaluation. of ECCS cooling perfor:ance is based upon the vendor's evaluation codel, the licensee's evaDution-is similarly deficient, The Regulatory staf f has assessed the effect of the changes required in the evaluation model upon the results of the evaluation of ECCS perf ormance for the Monticello f acility submitted -

on August 20, 1974. This is described in the Safety Evaluation Report of the Monticello Huclear Generating Plant, Docket No 50-263, dated Dececher 27, 1974. On the basis of its review, the Regulatory staff has determined that changes in operating conditions for ths plant,

^

in addition to those proposed in the licensee's submittals of December 11, and August 20, 1974, e.e necessary to assure that the criteria set forth in I 50,46(b) are satisfied. These additional changes,'which are set

~ forth in Appendix A-to the Safety Evaluation Report, consist of codifications to the licit governing maximum average planar linear ,

heat generation rate. These further restrictions will assure that .

ECCS cooling performance will conform to all of the criteria-contained in 10 CFR H 50.46(b), which govern . calculated peak clad temperature, maximu= ciudding oxidation, maximum hydrogen. generation,-

coolable geometry and long tern cooling.

l f These restrictions were established on the basis of studies j

/

L of the effect of model changes on the previously sub=1tted evaluations. ,

The Regulatory staff believes that these restrictions should be -

1 L

- . . ._ . - . - . n. . . . . ,

v i

verified by a re-analysis based upon an approved evaluation codel, in confor:1ty with 10 CFR 5 50.46 and Appendix K. During the interim, bef ore an evaluation in confor lty witn the requirements of 10 CFR 5 50.46 can be subtitted and evaluated, the Regulatory staf f has concluded that continued conf ormance to the requirements of the Commission's Interim Acceptance Criteria

  • and conformance to the restrictions contained in the licensee's August 20 and December 11, 1974 submittal, together with the additional limitations set forth in Appendix A of the Staff Safety Evaluation Report dated December 27,1974, will provide reasonable assurance that the public health and safety will not be endangered. These additional restrictions are set forth as Appendix A to this Order.

111.

In view of the foregoing and, in accordance with the provisions of 5 50.46(a)(2)(v), the Acting Director of Licensing has found that the evaluation of ECCS cooling performance submitted by the licensee is not consistent with the requirements of 10 CFR R 50.46(a)(1) and, therefore, that the urther restrictions of f acility operation, set forth in Appendix A to this Order, are required yo protect the public health and safety. The Acting Director of Licensing has also found that the public health, safety ,

and interest require that the following Order be made ef fective i=rediately. Pursuant to the Atocic Energy Act of 1954, as amended, the Commission's regulations in 10 CFR S B 2.204, 50.46, and 50.54

  • See next page f

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.I L l

..l 1 l

IT IS ORDERED TRAT: .j

1. As soon as practicable, but in no event later than six months l

from the date of publication of this order in the FEDERAL REGISTER, or j prior to any license a:endment authorizing any core reloading, whichever l

occurs first, the licensee shall submit a re-evaluation of ECCS cooling )

perfor ance calculated in accordance with an acceptable evaluation model l' i

- which conforts with the provisions of 10 CFR Part 50, f 50.46. Such 1

evaluation may be based upon the vendor's evaluation model as modified in accordance with the changes described in the Staf f Safety Evaluation Report of the Monticello Nuclear Generating Plant, dated December 27, 1974.

- The evaluation shall be accompanied by such proposed changes in Technical Specifications or license amend =ents as may be necessary to implement the evaluation results.

2. Effective immediately reactor operation shall continue only within the limits of:

'l (a) The requirements of the Interic Acceptance Criteria, the Technical Spec 1fications, and license conditions imposed by the Commission in accordance with the requirements of the Interim Acceptance Criteria, and (b) The licits of the proposed Technical Specifications subtitted by the licensee on August 20 and December 11, 1974,:as modified by the ,

further restrictions set forth in Appendix A, attached hereto.

l L

Light Water Power Reactors, 36 F.R.12247, June 29,1971, as amended 36 F.R. 24082, December 18, 1971 .

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The license shall conform operation to the foregoing limitations f until such time as the proposed Technical Specifications required to be submitted in accordance with paragraph 1 above are approved or modified and issued by the Co= mission. Subsequent notice and opportunity for hearing will be provided in connection with such action.

IV.

Within thirty (30) days from the date of publication of this Order 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

+

c for a hearing with respect to this Order in accordance with the provisions of 10 CFR I 2.714 of the Co=nission's Rules of Practice.

If a request for a hearing is filed within the time prescribed herein, the Coc=1ssion will issue a notice of hearing or an appropriate order.

For further details with respect to this action, see (1) the licensee's l

submittals dated August 20, 1974 and Dececher 11, 1974 and vendor's topical reports referenced in the licensee's submittal, which describe the vendor's evaluation model, (2) the Status Report by the Directorate of Licensing in the j

Matter of General Electric ECCS Evaluation Model Conformance to 10 CFR 50, Appendix K. (3) Supplement 1 thereto dated November 13, 1974, l

I' i

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December- 27, 1974, and (4) the Saf ety Evaluatior. Report dated (5) Report of the Advisory Corr.ittee on Reactor Safeguards dated b November 20, 1974. All of these ite._s are available at the Coc=.ission's Public Document Room,1717 H Street , N. W. , Washington, D. C. , and at the Environmental Conservation . Library, Minneapolis Public Library, 300 Nicollet Mall, Minneapolis , Minnesota 55401. A single copy each of items (2) through (5) may be obtained upon request addressed to the U. S. Atocic Energy Comission, Washington, D. C. 20545, Attention: .

Deputy Director for Reactor Projects, Directorate of Licensing, Regulation.

Dated At Bethesda, Maryland, this' DEC 2 1 FOR THE ATOMIC ENERGY CODIISSION 06gintl5# D E. G. CrA Edson G. Case, Acting Director Directorate of Licensing h

. . r APPCDIX A ML'TICC.LO OTERATIO:? T.ESTRICTIO :S The proposed Technical Specification limiting conditions of operation present two limitations on power distribution related to the LOCA analysis. These are the limiting assembly maxinum average planar linear heat generation rate, MAPLEGR, and the minimum critical power-ratio limit related to boiling crisis, MCFR. The NCPR value used in the LOCA analysis was 1.19. The limiting value of MAPLEGR included with the proposed Technical Specifications submitted on August 5, 1974, l have been revised to account for the General Elcetric ECCS Evaluation Model deficiencies which have been discussed in this report. The revised values are given in Figures B.3.11-1A and B.3.11-13.. Operation Shall CC;fers to tha$e Values. 0;erati n Shall also Ccnform to a MCPR value of 1.20 as preposed b: the licessee.

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