ML020880445

License Amendment 4, Changes in Byproduct Materials

ML020880445
Person / Time
Site:	Monticello
Issue date:	06/17/1974
From:	Goller K US Atomic Energy Commission (AEC)
To:	Mayer L Northern States Power Co
References
Download: ML020880445 (16)

Text

DISTRIBUTION:

. _ CHebroCm DRA Docket NDube AEC PDR MJinks (4) Local PDR RMDiggs ORB-2 Reading HJMcAlduff, ORO JUN 17 1974 JRBuchanan, ORNL TBAbnerathy, DTIE Docket No. 50-263 KRGol ler TJCarter ACRS (16)

RO (3)

Northern States Power Company OGC ATTN: Mr. L. 0. Mayer JSaltzman, OAI Director of Nuclear FLlngram Support Services WOMi 11 er 414 Nicollet Mall DLZiemann Minneapolis, Minnesota 55401 SVarga SLewis, OGC Gentlemen: BScharf (15)

SKari We have completed our review of your application dated August 31, 1973, as previously filed on December 21., 1972, for amendment to the byproduct materials authorized under Provisional Operating License No. DPR-22.

Your application of August 31 requested: (1) an increase in the type and strength of the sealed antimony sources--specifically, an increase from 1250 curies to 5350 curies to account for the licensing of the parasite 122 along with the antimony 124, (2) an increase (from 27 microcuries to 5.5 millicuries) in the unrestricted form of cobalt 60 and the consolidation of the 0.5465 millicurie of cobalt 60 that was previously licensed in solution form, (3) a consolidation of the 2.702 millicuries of cesium 137 in solution form and the I millicurie of cesium that has no restriction as to form as 3 millicurles of cesium without form restriction, (4) the addition of 100 microcuries each of byproduct materials with atomic numbers 3 through 83, and (5) the deletion from licensing requirements of the sealed sources of cesium 137 and strontium 90 because you consider them to be within the exempt quantity limits of Section 30.18 of 10 CFR Part 30.

In connection with item 1 above, the license previously authorized possession of 10 sealed antimony 124 sources up to 1250 curies each.

However, antimony 121 is present to the extent of 57% in natural antimony and the remainder is antimony 123. Activation of natural antimony therefore results i,,the formation of radioactive antimony 122 and 124.

Revised calculational methods using more recent cross section data and Monticello neutron flux values have resulted in a slight increase of the curie content for the antimony 124 source which when combined with the parasitic antimony 122 results in a conservatively calculated limit of 5350 curies per source. The amendment merely makes this fact explicitly covered by the license provisions, and does not in any way affect safety considerations in connection with use or handling of these sources.

Northerff States Power Company -2 -

JUN 1 7 1974 For t 2 above, the license previously authorized 27 microcuries of cobal.A n the unrestricted form and 0.5405 millicurie of radioactive cobalt in solution form. A larger inventory is desirable than previously allowed, 5.5 millicuries, because over a five-year period the inventory is reduced by disposing of small quantities of the cobalt after it has performed its function. The new limit represents the maximum amount that may-be on hand, for example after receipt of a new shipment. Th~ere le J0 isno requirement for, or benefit from, separately licensing 0.5400 j millicurie in solution form.l Possession of the 5.5 millicuries of cobalt does not introduce neW uses or alter procedures that have been previously followed and does not affect reactor operations hence there are no reactor safety considerations associated with the change.

The action requested in item 3 above imposes no safety considerations that are different from those previously reviewed in that you were previously authorized for a total of 3.702 millicurles partly in soldtion form and partly without restriction as to chemical or physical form.

The receipt, possession and use of 100 microcuries each of any one of the byproduct materials requested In item 4 above are within acceptable leveis (as set forth in Regulatory Guide 1r.70.3) and do not involve personnel safety considerations different than those considered for the other materials previously reviewed and licensed for this facility.

Since previously reviewed and authorized operation of the reactor is not changed by the use of these byproduct materials in the manner proposed, we find that there are no new reactor safety considerations.

There is reasonable assurance that the health and safety of the public will not be endangered since the storage and use are consistent with*

and within the scope of that previously authorized by the Regulatory staff andlandling Is by Northern States personnel familiar with such materials.

Since the sealed sources of cesium 137 and strontium 90 referenced in item 5 above fall within the 100 mticrocuries limic of the materials rEquested In item 4 above, It is not necessary to provide for an exemption pursuant to Section 30.18.

Based on the above, we have concluded that the issuance of a license amendment to authorize Items 1 through 4 above will not be Inimical to the common defense and security or to the heal th and safety of the

-public and that this action does not involve a significant hazards consideration.

Consequently, Amendment No. 4 to Provisional Operating License No.

DPR-22 Is enclosed au.t, zing your August 31 request, wi the itulTI10dfiiV ["AM ~IMwUO Tn5VV us fui iu tu~~uw; Tm . -............... . .

UR ...........

. ............................................. ............................................. I.............................................. .............................................. .....................................

Forto AEC-318 (Rev. 9-53) AE*CMJ 0240 Ua 8.; GOVERNMENT* PRINTING OFF.ICE: 1974-9$26-166

Northern States Power Company JUN 1? 1974 Further, It is currently possible that if your application dated September 1, 1972, for conversion of your provisional operating (POL) to a full-term license (FM) is updated to license set forth in the enclosed Regulatory Guide 1.70.3 include the information Information - Radioactive Materials Safety for Nuclear entitled "Additional dated February 1974, we will consider licensing the Power Plants" connection with operation of your Monticello plant materials used in lit the manner set forth in this guide.

The information required by Guide 1.70.3 should be as possible so that we can review it for inclusion provided as soon Safety Evaluation that might be issued in connectionin any supplemental conversion. Also, It is anticipated that a specification with the l1cense leakage testing and surveillance, and a reporting on source thereto will be included in the Technical Specifications requirement related It is requested that all infomation provided pursuant for the facility.

guide be submitted as a supplement to your application to the above of the POL to a FTL with three signed and notarized for conversion originals and

.thlrty-seven additional copies, As rpequired by Section 2.106 of 10 CFR Part

",relating to the issuance of Amendment No. 4 2, to the enclosed notice the "filed with the Office of the Federal Register for license is being publication.

/ Sincerely, Ozqginal signed bX; Karl R. Goller, Assistant Director for Operating Reactors Directorate of Licensing

Enclosures:

1. Miendment No. 4 to License No. DPR-22

2. Regulatory Guide 1.70.3

3. Federal Register Notice cc w/encls:

See next page

/

OFFICE __:ORB-- L :Q- -- OG - AD -ORs SURNA0E, RbD.ig-s: esp. JJShea - DL i.- mm a nm - - di e __jb.5 ......... o11 er -------

Form A,.c-3, (lRov. 9-53) AECMAEC..18...ev.

0240 For 024$..P74- 9-T53)-~o, 6/.,

"48x£-'-s;,;:£ 0 -.147 ...... .

81854/5-/74

Ndrthern States Power Company jo i ý 1974 cc w/enclosures:

Arthur Renquist, Esquire Mr. D. S. Douglas, Auditor Vice President - Law Wright County Board of Commissioners Northern States Power Company Buffalo, ivnnesota 55313 414 Nicollet Mall Minneapolis, Minnesota 55401 cc w/enclosures and cy of NSP's Appls. 12/21/72 & 8/31/73:

Gerald Charnoff Warren R. Lawson, M. D.

Shaw, Pittman, Potts, Trowbridge Secretary. & Executive Officer and Madden State Departrrent of Health 910 - 17th Street, N. W. 717 Delaware Street, S. E.

Washington, D. C. 20006 Minneapolis, vIinnesota 55440 Howard J. Vogel, Esquire Mr. Gary Williams Knittle & Vogel Federal Activities Branch 1154 East Grain Exchange Building Environmental Protection Agency 412 South 4th Street 1 N. Wacker Drive, Room 822 Minneapolis, Minnesota 55415 Chicago, Illinois 60606 Steve Gadler, P. E. Dr. Ed Pryzina 2120 Carter Avenue Minnesota Pollution Control Agency St. Paul, Minnesota 55108 1935 W. County Road B2 Roseville, -innesota 55113 fvhr. Daniel L. Ficker Assistant City Attorney 647 City Hall St. Paul, Minnesota 55102 Ken Dzugan, Director City of St. Paul Pollution CqntrQl Services 100 East 10th Street St. Paul, Minnesota 55102 Sandra S. Gardebring, Esquire Minnesota Pollution Control Agency 1935 W. County Road B2 Roseville, Minnesota 55113 Anthony Z. Roisman, Esquire Berlin, Roisman and Kessler 1712 N Street, N. W.

Washington, D. C. 20036 Ernvironmental Library of Minnesota

UNITED STATES "ATOMICENERGY COMMISSION WASHINGTON. D.C. 20545

• ES NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 4 License No. DPR-22 The Atomic Energy Comnission ("the Commission") has found that:

1. The application for license amendment dated December 21, 1972, as amended August 31, 1973, cooplies with the requirements of the Atomic Energy Act of 1 9 54, as amended, and the Commission's regulations set forth in 10 CFR Chapter I;

2. There is reasonable assurance (i) that the activities authorized by the operating license, as amended, can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission;

3. The receipt, possession, and use of byproduct and special nuclear materials as authorized by this license amendment will be in accordance with the Cormiission's regulations in 10 CFR Parts 30 and 70, including Sections 30.33, 70.23 and 70.31;

4. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public, and

5. Prior public notice of proposed issuance of this amendment is not required since the amendment does not involve a significant hazards consideration.

Provisional Operating License No. DPR-22, as amended, issued to Northern States Power Company for operation of its Monticello Nuclear Generating Plant is hereby amended to revise paragraph 2.C thereof in its entirety to read as follows:

2.C. Pursuant to the Act and 10 CFR Part 30, "Rules of General Applicability to Licensing of Byproduct Material," to receive, possess, and use in connection with the operation of the facility:

.(1) antimony 122 and 124, ten sealed sources, not to exceed 5,350 curies per source; (2) americium 241, one sealed source, not to exceed 7 curies; (3) cobalt 60, four sealed sources, two not to exceed 350 microcuries per source, one not to exceed 500 millicuries, and one not to exceed 12.5 millicuries; (4) cobalt 60, 5.5 millicuries (without restriction as to chemical or physical form);

(5) cesium 137, three millicuries (without restriction as to chemical or physical form);

(6) americium 241 and strontium 90, each not to exceed one millicurie per nuclide (without restriction as to chemical or physical form), and (7) any byproduct material with atomic numbers 3 through 83, inclusive, not to exceed 100 microcuries per source (in any chemical or physical form).

This amendment is effective as of the date of issuance.

FOR THE ATOMIC ENERGY COMMISSION Orig!Dal l rl '0 1ole'r by' signed Karl R. Goller Assistant Director for Operating Reactors Directorate of Licensing Date of Issuance: JUN 17 1974

February 1974

• . U.S,*_.fOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.70.3 ADDITIONAL IN.FORMATION RADIOACTIVE MATERIALS SAFETY FOR NUCLEAR POWER PLANTS A. INTRODUCTION report as indicated below. Section 12.4 should be added as follows:

In October 1972, the Commission issued Revision I of the "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." " This document provides a standard format for the safety analysis reports 12.4 Radioactive Materials Safety (FSAR) required by the Commission's regulations and identifies the principal information needed by the Regulatory staff 12.4.1 Materials Safety Programs in order to conduct its safety evaluations.

Describe the program which will be implemented to In its review of recent applications for construction assure the safe storage, handling, and use of sealed and permits and operating licenses, the Regulatory staff has unsealed special nuclear, source, and byproduct identified information that has often been missing from materials. Other sections of the FSAR may be these safety analysis reports. To obtain the information referenced to the degree they are applicable.

needed to perform its evaluation, the staff has had to request this information by directing written questions to each applicant. The Foreword of the Standard 12.4.2 Facilities and Equipment Format states: "Any revisions of the Commission's "needs for information will be conveyed to the Describe the laboratory facilities and equipment industry and the public in various ways such as (1) amendments such as hoods, gloveboxes, filters, survey and measuring to the Standard Format, (2) in the Information Guide instruments, and monitoring devices. Other sections of series, (3) as part of future Safety Guides, or (4) in the FSAR may be referenced to the degree they are Public Announcements." This guide identifies applicable.

information related to radioactive materials safety that has often been missing from the applicant's safety analysis report at the operating license stage of review. 12.4.3 Personnel and Procedures The Commission plans to revise the Standard Describe the experience and qualifications of the Format within the next year to include this key personnel responsible for handling and monitoring modification. In the interim, the information requested the materials. Identify and summarize the content of the here should be included in safety analysis reports radiation safety instructions to working personnel submitted for AEC review. appropriate to the operations to be covered. Other sections of the FSAR may be referenced to the degree B. ADDITIONAL INFORMATION they are applicable.

The additional information requested should be incorporated into Chapter 12 of the safety analysis 12.4.4 Required Materials The "Standard Format and Content of Safety Analysis Provide a listing of isotope, quantity, form, and use Reports for Nuclear Power Plants" has been designated as for all required byproduct, source, and special nuclear Regulatory Guide 1.70. materials which exceed the amounts in Table 1.

USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indicat;ig the divisions desired to the U.S. Atomic Energy Commission, Washington, D.C. 20545.

Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments and suggestions foe methods acceptable to the AEC Regulatory staff of implementing specific parts of improvements in these guides are encouraged and should be sent to the Secretary the Comineission's r-gulations, to delineate techniques used by the staff in of the Commission, U.. Atomic Energy Commission. Washington, D.C. 20545.

evalu*ting specific prob'ems or pc..ttlated accidents, or to provide guidpnce to Attention: Chief. Public Proceeding* Staff.

apoli;.trts. Reoto-t6 ,' Guides art no' substitutes for regulations and compliBance with them is not required. Methods and solutions different from those set out in The guides are issued in the following ten broad divisionrs the guides will be acceptable if they provide a basis for the findings requisite to the isuance or continuance of a permit or license by the Commission. 1. Power Reactors 6. Products

2. Research end Test Reactors 7. Transportation,

3. Fuels and Materials Facilities 8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate 4. Environmental end Siting 9. Antitrust Revieow comments and to reflect new informat*on or experience. 5. Materials and Plant Protection 10. General

/' Table 1

• Material Form and Use Possession Limit A. Any' byproduct, As reactor fuel; as source, and special Amount required for sealed neutron sources reactor operation nuclear material for reactor startup; as sealed sources for calibration of reactor instruments and radiation monitoring equipment; and as fission detectors B. Any byproduct Any form for sample 100 millicuries each material analysis or instrument isotope calibration C. Any source or Any form for sample 100 milligrams each special nuclear analysis or instrument isotope material calibration

(

1.70.3-2

UNITED STATES ATOMIC ENERGY COMMISSION DOCKET NO. 50-263 NORTBERN STATES POWER COMPANY NOTICE OF ISSUANCE OF PROVISIONAL OPERATING LICENSE AMENDME.NT Notice is hereby given that the United States Atomic Energy Commission

("the Commission") has issued Amendment No. 4 to Provisional Operating License No.. DPR-22 to the Northern States Power Company authorizing a change in the amount of byproduct material they ray receive, possess, and use basically for reactor neutron sources and calibration of radiation monitoring equipment used in connection with operation of the Monticello Nuclear Generating Plant (the facility). The amendment, effective as of the date of issuance, authorizes (1) a change (from 1250 curies to 5350 curies) in the strength of individual sealed antimony sources used for reactor startup, (2) a change (from 27 microcuries to 5.5 millicuries) in the cobalt 60 sources, and (3) insignificant.' changes in other amounts of byproduct materials used for such purposes as instrument calibration. The Northern States Power Company is presently licensed to possess and operate its facility (located in Wright County, Minnesota) at power levels up to 1670 MWt.

The Commission's Regulatory staff has found that the application complies with the requirements of the Atomic Energy Act of 1954, as amended, and the Comnissionts rules and regulations published in 10 CFR Chapter I, and that the issuance of the amendment will not be inimical to the common defense and security or to-the health and safety of the public. The staff also has concluded that this action does not involve a significant hazards consideration

since (1) the use of the ratarials in the ranner pxoposed does not changpe the previously reviekied and authorized. operation of the facility and thn n iew safetY 0M~erations are Jzmlved, (2) the inateria~s ame being sb~rec¶ in pceviamly reviiaed and approve~d storage facilities, and (3) the quantities anid types of ruatweials "eono now personiel safety oomidsrations different than those 0osidez'ed for the other rinteriale previously reviered aWi liaensed for thi facility and materials wil11 be hnle~d by Northsn States Power OCRAn Persom~e1 familiar with thie saffe handling of nwmiezus tbA:s wid quantities of byproduzrt and special nuclear rm.atet'ials. Based upn, the finding of no signif~icant hazards consideration, public nmtloe of prtqxosed issuame of the a~nXW is not required.

copies Of the (1) pliaindated Decerber 21,, 1972, as amended August 31, 1973, (2) Anx~mt 1b. 4 to~ i~canse No. DPR-22,, and (3) the letter tO Ibrthern Stats PAmer CkiVaW (trantshitting Amfrident No. 4) 4dchi provides an rawduation of the nbsffst for the vnm araaibl for puzblic Ixn~psotic at the C~anuuim~'s Public Docume~nt Romt at 1717 H Street,, N. W.,Iashington, D. C.,F and at the &nivrormntal Library of Ruvasota, 1222 S. H. 4th Stxeet, Kiftweaplis# Minnesota 55414. Sinlre, copSies of the licmensem a eobanduo eqetaIem to the U. S. Atmiic Energy Comiasionj, Washington, D. C. 20545., Attention:

D0putY Diroetor for Poaotor P=rojetsMe~aeofLonig D~ated at D&M1g rlf! hsday of P MAlTM4C BENM OZC4ISSICH Original Sigrxed by:.

Dennis L. Ziemann

June 5, 1974 Note to Jim Shea This note transmits certain suggested language additions and changes to the package on the amendment of the Monticello operating license with respect to amounts of byproduct materials. It also poses remaining unresolved questions.

1. On page 1 of the letter to NSP between the second and third sentences, d following:

< # The license previously authorized possession of 10 sealed antimony 124 ources up to 1250 curies each. -!T!,e Pa, zi+^ ta.t.. .. c.

.% . --t-nat a "source conltaining 1250 a " a2 there-r contain a t qantity of antimony 124 ard-122i Lhe am!un' ur approximately b.350 C-. The amendment merely 4,6  ?' - 9makes this fact explicitly covered by the license provisions, and does not in any way affect safety considerations in connection with use or handling of these sources.

The second change, simply increases the total amount of radio j

/ active cobalt in unsealed sources from 27 microcuries each to

.. 55.NJllicuries each [give reason for change and explain why it et presents no safety problem. Then proceed to itemize the remaining

//0 !~J-r/7

-2 changes, assigning reasons therefor and explaining why they present no safety problems.]

2. On page 1 of the letter in the present third sentence strike "and the procedures associated therewith", since the staff does not specifically review and authorize "procedures".

3. In the last sentence of the first paragraph on page 1 of the letter, L change the closing phrase to "it is not necessary to address the issue of exemption pursuant to Section 30.18."

4. Still on page 1 of the letter, add the word "further," at the beginning 0 \ý of the second paragraph .

5. In the Notice at the top of page 2 in explaining the reason for the finding of no significant hazards considerations, replace the present language with language indicating:

1. the technical nature of the changes. (I know this holds for antimony, can we similarly characterize the other changes.)

2. the fact that previously approved plant operations are not being changed. You can continue to use the present language on this point.

6. In the last sentence of the continuation paragraph on page 2 of the Notice, change "Consequently" to "Based upon the finding of no signifi cant hazards consideration,".

-3

7. The changes and additions suggested here are intended to clarify which of the items listed in paragraph 2.C. of the operating license.

constitute amendments, the reason for the various changes, and the basis for finding that there are no safety considerations involved.

Stephen H. Lewis

Distribution Docket File AEC PDR Branch Reading Iocket No. 50-263 HJMcAlduff, OR00 JRBuchanan, ORNL TBAbernathy, DTIE KRGoller, L:OR TJCarter, L:OR Northern States Power Company ACRS (16)

ATTIN: 'Mr. L. 0. Mayer RO (3)

Director of Nuclear OGC Support Services JSaltzman, L: OAI 414 Nicollet Mall FLlngram Minneapolis, Minnesota 55401 HIMueller, DMR/H WOMiller Gentlemen: DLZiemann, L:ORB #2 We have completed our review of your application dated August 31, 1973, as previously filed on December 21,,1972, for amendment to the byproduct DPR-22.

materials authorized under Provisional Operating License No.

Based on our review, we have concluded that the issuance of the enclosed amendment will not be inimical to the common defense and security or to Since the storage and use of the the health and safety of the public.

and within the scope of, that byproduct material is consistent '.with, is no previously reviewed and approved bt the Regulatory staff. and there change in the previously authorized nner of operation of the Monticello facility and th* n oc-itcd'.theithwe t* also have concluded that this action does not involve a significant hazards consideration.

Operating License No. DPR-22 2 Consequently, AAendment No. 4tjo Provision\al is enclosed authorizing your request of Augu>st 31, 1973. Since the sealeda',

100 microcurie limit sources of cesium and strontium 90 fall within\the of the materials licensedi a jtoin ers *tvgugh 8 in item 7 of the enclosed amendment, - e-f exemption pursuant to Section 30.18. 0 o

' pplication dated September 1, 1972, for convers of your

• fL) is provisional operating license (POL) to a full-term license updated to include the information set forth in the enclosed Regulatory Guide 1.70.3 entitled "Additional Information - Radioactive Materials Safety for Nuclear Power Plants" dated February 1974, we will consider Monticello licensing the materials used in connection with operation of your

., ,plant in the manner set forth in this guide. This means that only specific ---

(

in your license when they exceed the limits

-! ýquantities will be enumerated amendments V

• " and uses set forth in Table 1 of the guide. No subsequent license

\J ~ r evaluations for materials would be required as long as you do not exceeda' these limits and uses.

\) SVarga BScharf (15) CHebron, DRA SLewis, OGC RMDiggs NDube, L: OPS SKari MJinks (4)

orhrSt~~ 2 mrO:p 2 The information required by Guide possible so that we can review it 1.70.3 should be provided as soon as "

for inclusion in any supp lemental 1 afety Evaluation that might be issued in connection U.. conversion. Also, it is anticipated with the license that a specificatin onsouce j'2leakage testing and surveillance, thereto will be included in the and reporting requirement related Technical ks*i It is requested that all information provided Specifications for the facility.

guide be submitted as a supplement pursuant of the POL to a -_TLfwith three signedto your application to the above for conversion and notarized originals and thirty-seven additional copies.

As required by Section 2.106 of 10 CFR Part 2, the enclosed notice relating to the issuance of Amendment filed with the Office of the Federal No. [4to the license is being Register for publication.

Sincerely, Karl R. Goller Assistant Director for Operating Reactors Directorate of Licensing

Enclosures:

1. Amendment No. 4 to License No. DPR-22

2. Regulatory Guide 1.70.3

.3. Federal Register Notice cc w/enclosures:

See next page GPO C43 16 81465.1 520-284

since (I)" thn use of the materials in the manner proposed does not change th, nreviously reviewed and authorized operation of the facility and thus no new safety considerations are invclvedQ (2) the materials are being stored in previously reviewed and approved storage facilities, and (3) the quantitibs and types of materials pose no new personnel safety considera tions different than those considered for the other materials previously r ivowed and licensed by the Ccmmsin and'

• ding-of the-materials will b KZ y Northern States Power Company personnel familiar with the safe r

handling of numerous types and quantiti s of materials. Based upon the A

finding of no significant hazards consideration, public notice of proposed issuance of the amendment is not required, Copies of the (1) application dated Lecember 21, 1972, as amended August 31, 1973, (2) Amendment No. 4 to License No. rPR-22, and (3) the letter to Northern States Power Company (transm-tting Amendment No. 4) which provides an evaluation of the request for the amendment are available for public inspection at the Commission2s Public Document Room at 1717 H Street, N.W., Washington, D.C., and at the Environmental Library of Minnesota, 1222 S.Eo 4th Street, Minneapolis, Minnesota 554lh. Single copies of thel icense amendment may be obtained upon requicst addressed to the U. S. Atomic Energy Commission, Washington, D, Co 20545, Attention: Deputy Director for Reactor Projects, Directorate of Licensing.

Dated at Bethesda, Maryland, FOR THE ATCM.C 1DNRCY COMMTSSYON Dennis L. Ziemann, Chief Operating Reactors Branch #2 Directorate of Licensing