ML23222A198
| ML23222A198 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/27/1974 |
| From: | Kniel K US Atomic Energy Commission (AEC) |
| To: | Mayer L Northern States Power Co |
| References | |
| Download: ML23222A198 (1) | |
Text
UNITED STATES ATOMIC ENERGY COMMISSIO~ CENS,E AUTHORITY FIL[ COP 1.
WASHINGTON, O.C. 20545
- - 0 Docket Nos. ~
~
50-306 Northern States Power* Company ATTN:
Mr. L. 0. Mayer Director of Nuclear Support Systems 414 Nicollet Avenue Minneapolis, Minnesota Gentlemen:
oEc 21 ~4 O NOT REit;uYE
- ' The Commission has issued the enclosed Order for Modification of License for the Prairie Island Nuclear Generating Plant Units 1 and 2 pertaining to your proposed Technical Specifications which were submitted pursuant to Section 50.46 and Appendix K of 10 CFR Part 50.
The enclosed Safety Evaluation Report contains the bases for our action.
A copy of the Order is being filed with the Office of the Federal Register for publication. This Order is effective inunediately.
Within 30 days after receipt of this letter, we request that you inform us of your submittal date for the reevaluation requir~d by paragraph 1 of Section III of the Order.
You will note that the Order requires that a reanalysis in conformance with the Order must be submitted along with any _request for authoriza-tion for any core reloading.
In order to provide for sufficient time for our review of your reanalysis, you should assure that such submittal is provided at least 45 days prior to your schedule of initiation of operation following approval of such reloading.
You should also note, that since your current analysis was based upon your presently authorized fuel loading patterns, any modification of fuel design or core configu-ration that affects the basis for the analysis will require staff approval.
Sincerely,
/3//.~
~I Karl Kniel, Chief Light Water Reactors Branch 2-2 Directorate of Licensing
Northern States Power Company 2 -
Enclosures:
- 1.
Order
- 2.
Safety Evaluation Report
- 3.
Status Report by the Directorate of Licensing in the }tatter of Westinghouse
. Electric Hodel Conformance to 10 CFR 50, Appendix K
- 4.
Supplement 1 to the Status Report cc:
Gerald Charnoff, Esquire Shaw, Pittman, Potts & Trowbridge 910 - 17th Street, NW.
Washington, D.C.
20006 Steve J. Gadler, Esquire 2120 Carter Avenue St. Paul, Minnesota 55108 Sandra S. Garctebring, Esquire Counsel for Minnesota Pollution Control Agency 1935 W. County Road Roseville, Minnesota 55113 December 27, 1974
In the ~atter of UNITED STATES OF AMERICA ATOMIC ENERGY CQMMISS ION Northern States Pm*1er Company (Prairie.Island Nuclear Generating Plant, Units 1 and 2)
Docket Nos. 50-282 50-306 ORDER FOR MODIFICATION OF LICENSE I.
The Northern States Power Company (the licensee) is the holder of faci 1 i ty 1 i censes DPR-42 and DPR-60 v,hi ch authorize opera ti on of the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively, in Goodhue County, Minnesota.
These licenses provide, among other things, that they are subject to all rules, regulations, and orders
- of the Commission no\'1 or hereafter in effect.
. I I.
Pursuant to the requirements of the Commission's regulations in 10 CFR.s 50.46, "Acceptance Criteria and Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," on September 6, 1974, the licensee submitted an evaluation of ECCS cooling performance calculated in accordance with an evaluation model developed by the Westinghouse Electric Company (nthe vendor"), qlong_with certain proposed Technical Specifications necessary to brinq reactor oreration int-o *conformity 1.-1ith the results of the evaluiition.
The evaluation model developed by the vendor has been analyzed by the Regulatory staff for confo_rmity with the requirements of 10 CFR I
Part 50, Appendix K~
11ECCS Evaluation Models.
11 The Regulatory staff's evaluation of the vendor's model is described in two previously published documents:
Status Report by the Directorate of Licensing in the Matter of Westinghouse Electric Company's ECCS Evaluation Model Conformance to 10 CFR Part 50, Appendix K, issue~ October 15, 1974, and a Supplement to the Status Report, issued November 13, *1974.
Based on its evaluation, the Regulatory staff has concluded that tne vendor's evaluation model was not in complete conformity with the requirements of Appendix Kand that certain modifications described in the above-mentioned documents \11ere* required in order to
- achieve such conformity.
The Regulatory staff assessments 1*1ere revie\*1ed by the Commission's Advisory Committee on Reactor Safeguards*in meetings held on October 26, 197-i.nd November 14, 1974.
In its Report to the Chairman of the AEC, dated November 20, 1974, the Advisory Committee has concluded that,.the f~ur 1 i ght-water reactor vendors have developed Evaluation Models which,-with additional modifications re qui red by the Regulatory staff, will conform to Appendix K to Part 50.
11 Since the licensee's evaluation of ECCS cooling performance is based upon t~e vendor's evaluation model, the licensee's evaluation is similarl:; deficient.
The Regulatory staff has assessed the effect of the changes required in the evaluation model upon the results of the evaluation of ECCS perfor~ance for the Prairie Island plant submitted on September 6, 1974.
This is described in Supplement No. 4 to the Safety Evaluation Report of the Prairie Isl and Nuclear Generating Generating Plant, Units 1 and 2, Docket Nos. 50-282 and 50-306, dated December 24, 1974.
On the basis of its review, the Regulatory staff has determined that changes in operating conditions for the planti in addition to those proposed in the licensee*~ submittal of September 6, 1974, are necessary to assure that the criteria set forth in § 50.46(b) are satisfied. These additional* changes, which are set forth fo Appendix A of Supplement No.. 4 to the Safety Evaluation Report, consist of modifications to the limit govern-ing the total
- peaking factor.
These further restrictions will assure that ECCS cooling perfonnance \'/ill conform to an of the criteria contained in 10 CFR § 50.46(b), which govern calculated peak clad tem9erature, maximum cladding oxidation, maximum hydrogen generation, coolable geometry and long tenn cooling.
These further restrictions were established on the basis of studies of the effect of model changes on the previously submitted evaluations. The Regulatory staff -believes that these restrictions should be verified by a re-analysis based upon an appr'oved evaluation model, in 'conformity \*tith 10 CFR 5 5Q.4e; and Appendix K.
During tne interiri,before an evaluation in conformity i.1it, the requirements of. 10 CFR J 50.46 can be submitted and evaluated, t
the Regulatory staff has concluded that continued conformance to the requirements of the Commission's Interim Acceptance Criterio.,*and conformance to the restrictions contained in the licensee's September 6, 1974 submittal, together with the additional limitations set forth in Appendix A of Supplement No. 4 of the Staff Safety Evaluation \.,,ill provide reasonable assurance that the public health and safety \*Jill not be endangered.
These additional restrictions are set for.th as Appendix A to this Order.
III.
In view of the foregoing and, in accordance with the provisions of
- I 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 ~ 50.46(a)(l) and *that' the further restrictions set forth in this Order are required to 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 9rder be made effective immediately. Pursuant to the Atomic Energy Act of 1954, as amended, the Commission's regulations in 10 CFR I§ 2.204, 50.46, and 50.54.
IT IS ORDERED THAT:
- 1.
As soon as practicable, but in no event later than six months from the date of publication of this ord~r in *the FEDERAL REGISTER, or prior to any license arner.amerit authorizi:19 any core reloadino, \*1hichever occ*urs first, the license(? shall submit a l(cJnterim Acceptance Criteria for Emergenc*y Core Cooling Systems for Light Water Power Reactors, 36 F.R. 12247, June 29, 1971, as amended 36 F.R. 24082, December 18, 1971 re-evaluation of ECCS cooling performance calculated in accordance.,.,ith an acceptable evaluation model which conforms with the provisions of 10 CFR Part 50, § 50.46.
Such evaluation may be based upon the vendor's evaluation model as modified in accordance with the changes described in the Supplement No. 4 to Safety Evaluation for the Prairie Island Nuclear Generating p*1ant, dated December 24; 1974.
The evaluation shall be accompanied by such proposed changes in Technical Specifications or license amendments as may be necessary to implement the evaluation
' *results.
2; Effective immediately, reactor operation shall continue only within the limits of:
(a)
The requirements of the Interim Acceptance Criteria, the Technical Specifications, and license conditions imposed by the Cof11Tlission in accordance with the requirements of the Interim
-Acceptance Criteria, and (b)
The limits of the proposed Technical Specifications submitted by the licensee on September 6, 1974, as modified by the further restrictions set forth in Appendix A, attached hereto.
The license shall conform operation to the foregoing limitations until such time as the proposed Technical Specifications required to be submitted in accordance \vith paragraoh 1 ab.ove q.re approved or
- 7lodifiec and issued by the Commission.
Subsequent notir.e Jnd opportunity for heari~g.~ill be provided in connection ~ith 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 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 vlithin the time prescribed herein, the Commission will issue a Notice of Hearing or an appropriate order.
For further details \*lith respect to this action, see (l} the licensee's submittal dated September 6, 1974, and the 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 Matter of Westinghouse Electric Company tees Evaluation Model Conformance to 10 CFR 50, Appendix K; (3) Supplement l thereto dated November 13, 1974, (4) Supplement No. 4 to the Safety Evaluation dated December 24, 1974, and (5) Report of the Advisory Conmittee on Reactor Safeguards dated November 20, 1974.
All of these items are available at the Commission's Public Document Room, 1717 H Street, NH, Washington, D. C., and at the Environmental Library of r-linnesota, 1222 S.E. 4th Street, Minneapolis, ~:innesota 55414.
A single copy each of items (2) through (5) may be obtained upon request addressed to the U.S. Atomic Energy Commission, Washington,
- 0. C.
20545, Attention:
Deputy Director for Reactor Projects, Directorate of Licensing, Regul?tion.
Dated at Bethesda, Maryland this ~fl1J day of December, 1974.
FOR THE ATOMIC ENERGY COMMISSION
/s/.
Edson G. Case, Acting Director Directorate of Licensing