ML20127N527
| ML20127N527 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/27/1974 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 9212010298 | |
| Download: ML20127N527 (13) | |
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*INITED STATES OF XIRICA 5 ATOMIC ENERGY CO': ISS10;l
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l NORTE7?; STATES POL'ER C01:PX;Y ) ' Docket No. 50-263
)
(Monticello .iuclear Generating ) Plant) , ORDER FOR H0DIFICATIO'; OF LICENSE I. 1 The Northern States Power Cc=pany (the licensee) is the holder of f acility license DPR-22 khich authorizes operation of the Monticello Nuclear Generating Plant in Monticello, Wright County, Minnesota. This license provides, among other things, that it is subject to all rpla. regulations and orders of the Co:::ission now or hereaf ter in effect. II. Pursuant to the requirements cf the Consission's regulations in 10 CFR
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S 50.46, " Acceptance Criteria jand Emergency Core Cooling Systems for Light Water Nuclear Power neactors", on August 20, 1974 and Dececher 11, 1974, the licensee submitted an evaluation of _ECCS cooling performance calculated in
- accordance with an evaluation model developed by the General Electric Company ("th 9212010298 741227 PDR ADOCK 05000263 3 P PDR
_ c, . s- , t vendor"), along with certain proposed technical specifications necessary , to bring reactor operation into conformity with the resvits of the-evaluation. The evaluation model developed by the vendor has been ana'yzed by the Regulatory staf f for confornity vi .h the requirements Gf 10. CFR Part 50, Appendix K, "ECCS Evaluation tiodels". The Regulatr q staff's evaluation of the vendar's model is described in two prevf. usly published docu=ents: Status Report by the Directorate of Licen',in in the Matter of General e to 10 CFR Part 50 Appendix K, Electric ECCS Evaluation 'edel Confor:an issued Octcher 15, 1974, and a Supplerent to the Status Report, issued November 13, 1974. Based on its evaluation, the Regulatory staff has concluded that the vendor's evaluation codel was not in complete conformity with the requirements of Appendix K and that certain codifications described in the above-centioned documents were required I l in order to achieve such conformity. The Regulatory staf f assessments were reviewed by the Cot:iission's Advisory Cocmittee on Reactor Safeguards in meetings held on October 26, 1974 and Novecher 14, 1974. In its Rep:,rt to the Chairman of the AEC, dated November 20, 1974, the Advisory Cocmittee har concluded that "the four light-water reactor vendors have developed Evaluation Mopels which, with additP 'al codifications. required by the Regulatory staf f, will conform to appendix K to Part 50".
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4 3 l Since the licensee's evaluation of ECCS cooling performance is based upon the vendor's evaluatien model, the licensee's evaluation is-similarly deficient. The T.egulatory staf f. has assessed the effect of the changes required in the evaluation model upon the results of the' evaluation of ECCS perforcance for the Monticello facility submitted on August 20, 1974. This is described in the Safety Evaluation Report , f of the Monticello Nuclear Gener. ting Plant Docket No. 50-263, dated Decenber 27, 1974. On the basis of its r2v'*u, the Regulatory staf f has determined that changes in operating conditions for the plant, in addition to those proposed in the licensce's subtittals of December ll, and August 20, 1974, are necessary to assure that the criteria-set forth in S 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 li=it g,overning maxi =un average planar linear j heat generation rate. These further restrictions will assure that a ECCS cooling perfor:ance vill conform to all of the criteria i i, contained in 10 CFR R 53.46(b), which govern calculated peak clad tecperature, enximum cladding oxidation, maxinus hydrogen generation, l < coolable geometry and long tern cooling. l L { i: j These restrictions were established on the basis of studies of the effect of codel chang'es on the previously subuitted evaluations. t 1 i The Regulatory staf f believes that these restrictions should be i ,. ~ ^ l-1
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O [, ; verified by a re-analysis based upon an approved evaluation model, in i During the interim, conformity with 10 CFR I 50.46 and Appendix K. e before an evaluation in conforcity with the requirements of 10 CFR i. y I 50.46 can be subcitted and evaluated, the Regulatory staff has concluded that continued conformance to the requirements of the Cozzission's Interin Acceptance Criteria *, and conformance to the restrictions contained in the licensee's August 20 and December 11,1974 submittali together with the additional licitations set forth in Appendix A dated December 27, 1974, will of the Staf f Safety Evaluation Report provide reasonable assurance that the public health and safety will not be endangered. These additional restrictions cre set t-rth as
,. j Appendix A to this Order.
l T.II . In viev of the foregoing and, in accordance with the provisions of l E 50.11}a)(2)(v), the Acting Director of Licensing has found that the evaluation of ECCS cooling performance submittet by th'e licensee is not consistent with the requirements of 10 CFR E 50.46(a)(1) and, therefore, I that the further restrictions of f acility operation, set forth in Appendix A i- i The-to this Order, are required yo protect the public health and saf'ety. f '
' Acting Director of Licensing has.also found that the public health, safety, .
4 i and interest require that the following Order be made ef fective immediately. Pursuant to the Atomic Energy Act of 1954, as amended, l ' the Conmission's regulations in 10 CFR ! D 2.204.- 50.46, and 50.54
< *See next page a
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IT IS' ORDERED THAT:
I 1. As soon as practicable, but in no event later than six months
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from the date of publication of this order in the FEDERAL REGISTER, or , prior to any license amendment authorizing any core reloading, whichever occurs first, the licensee shall submit a re-evaluation of ECCS cooling performance calculated in accordance with an acceptable evaluation.model-which conforms with the provisions of 10 CFR Part 50, B 50.46. Such evaluation may be based upon the vendor's evaluation mo. del as modified in accordance with the changes described in the Staff Safety Evaluation Report of the Monticello Nuclear Generating Plant, dated December 27, 1974. The evaluation shall be acco=panied by such proposed changes in Technical Specifications or license amendments as may be necessary to implement the evaluation results.
- 2. Effective i=cediately reactor operation shall continue only within the limits of:
(a) The requiremants of the Interim Acceptance Criteria, 2 the Technical Specifications, and license conditions imposed by the' Coccission in accordance with the requirements of the Interim Acceptance Criteria, and (b) The limits of the proposed Technical Specifications submitted by the licensee on August 20 and December 11, 1974, as modified by the
'further restrictions set forth in Appendix A, attached hereto.
d
- Interim Acceptance Criteria for Emergency Core Cooling Systems for as amended Light Water Power Reactors , 36 -F.R.12247, June 29,1971, 36 F.R. 24082, December 18, 1971- .
l- . 6- A The license shall conform operation to the foregoing limitations until such time as the proposed Technical Specifications required to . be subtitted in accordance with parasraph.1 above are approved or - 1 ' ~ modified and issued by the Co=aission. Subsequent notice and opportunity for hearing will be provided in connection with such action. IV. Within thirty (30) days f rom the date of publication of this Order . 5 in the FEDERAL REGISTER the licensee cay file a request for a hearing
- with respect to this Order. Within the same thirty (30) day period a 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 E 2.714 of the Co=:ission's Rules of Practice.
If a request for a hearing is filed within the tire prescribed' herein, the Co=nission will issue a notice of hearing or an appropriate order. For further details with respect to this action, see (1) the licensee's j submittals dated August 20, 1974 and December 11, 1974 and' vendor's topical reports referenced in the licensce's subcittal, which describe the vendor's P / evaluation model, . (2) the Status Report by the Directorate of Licensing in the l
'1beter of General Electric ECCS Evaluatioc .Model Conformance to 10 CFR 50, .
3 , Appendix K, (3) Supplement 1 thereto dated November 13, 1974,
+
i- .
g i December 27, 1974,- and 25 (4) the Safety Evaluation Report . dated
* (5) Report of the Advison Cormittee on Reactor- Safeguards dated j
November 20, 1974. All of these items are available at the Commission's 1 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 $5401. A single copy each of-items (2) through -(5) may be obtained upon request addressed to the U. S. Atomic Energy Cocnission, Washington,- D. C. 20545, Attention: Deputy Director for Reactor Projects, Directorate of Licensing, Regulation. Dated At Bethesda, Maryland, this DEC 2 7 19N -l FOR TJE ATOMIC ENERGY CotDIISSION ( , a iJ)% -h Edson G. Case, Ac' ting Director Directorate of Licensing .] t i f. 1 s l L
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s - fl0TICE-0F AVAILABILITY 4 ~f Copies of Appendix A.~to Order for tiodification of- License, . dated December 27, 1974, are' available for public. inspection at , the Conynission'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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! APPENDlX A
}!ONTICELLO OPERATIC:I PISTRICTIO :S ,
The proposed Teci.. ' ical Specification limiting conditions of operation present two limitations on power distribution related to the LOCA analysis. These are the liniting assembly maximum average planar . i linear heat generation rate, MAPLHGR, and the minimum critical power-ratio limit related to boiling crisis, MCPR. The MCPR value used in the-LOCA analysis was 1.19. The limiting value of MAPLHGR included
,vith the proposed Technical Specifications subnitted on August 5,-1974, have been revised to account for the General Electric ECCS Evaluation Model deficiencies which have been discussed in this report.- The-revised values are given in Figures B.3.ll-1A and B.3.ll-1B. Operation-shall confcrm to these values. O,nratien shall also cenfom to a UCPR valus of 1.20 as preposed by the licensae.
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l I MO;ITICELLO nitial Core (7 x 7)
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