ML20149H579

Application for Amend to License SNM-1773,authorizing Storage of Oconee Spent Fuel at McGuire Facility Prior to Issuance of McGuire OL

ML20149H579
Person / Time
Site:	07002623
Issue date:	03/09/1978
From:	Parker W DUKE POWER CO.
To:	Case E Office of Nuclear Reactor Regulation
References
TAC-57316, TAC-57317, NUDOCS 8802220006
Download: ML20149H579 (36)

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v DUKE PowEn COMPANY Powra Dettatso an Socin Caruca Srnstr. Citantorir R C au ma Acti 9,1176

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.s Mr. Edsen G. Case, Acting Direc:or s,

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Officeof Nuclear Reactor Regulation U. S. Nuclear Regulatory Cor=ission q

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Docket Numbers 50-369, 50-S$710

Dear Mr. Case:

Attached is a copy of an application for an amendment to special nuclear ma terials license number SNM-1773 issued pursuant to 1CCFR Part 70.

This amendment prevides for spent fuel 2:orage of Oconee Nuclear Sta: ion spent nuclear fuel at McGuire Nuclear Station prict to issuance of the McGuire operating licenses.

Although we understand that reviewing this ?ar: 70 application for amend:ent is :he responsibility of the Office of ';uclear Material Safety and Safeguards, we are sending a copy of this application for your information and in view of the fac:, as set forth in the McGuire FSAR and discussed with your staff, that such a Part 70 license c:vering storage at Cconee fuel at McGuire would ultimately merge into Part 30 operating licenses for McGuire.

On the assumptions that we will receive :he requested Part 70 license amendment prior to the issuance of Part 50 licenses, and that merger of the licenses will transpire when Duke receives the operating licenses for its M:Guire uni:s, we request that the specific authorizatica regard-ing fuel under the subject Part 70 license remain in effect under the operating licenses, along with :he related financial protection and indea-nity requirenents (in appropriately increased arounts).

In this regard, Duke requests that :he following language be used in the M:Cuire operating licenses in lieu of the standard language contained in paragraphs 2.b(3) and (6):

(3) Duke Power Company, pursuant to the Act and ICCFR Part 70, to receive, possess and use a: any time special nuclearraterial as reactor fuel, in accordance with the limitations for storage and arounts needed for operating of the facility or previously used in cperation of the reactors licensed under DPR's 33,

'*7, or 55, all as described in the Tinal Sciety Analysis Rerort, as supplemented anu amended.

(6)

Cuke Pcwer Company, pursuant to the Act and 10CFR Parts 30 and 70, :o passess, but not separata, such byprodue: and special nuclear ca:erialsas may be produced by the operation of the facili:y or as have been or cay be produced by the opera:Len of the rea:: ors licensed under DPR's 23, 47 or 55.

8802220006 780309 PDR ADDCK 07002623 php V

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Mr. Edson G. Case, Acting Director Page Two Sy separate letters, we are advising the Antitrust and Indemnity Group, the Atomic Safety and Licensing 3oard, as well as the parties, of the filing of this application for a Part 70 license amendment.

In the event that such application or the related inde nity agreement becenes the subject of a hearing, it may be in order to consolidate such hearing with the'Part 50 license proceeding, in whita Safety hearings are presently anticipated to co=nence this Spring, so as to expedite the mattet.

If any further information is reqaired, please contact Mr. G. J. Pollak at the above address.

Very truly yours, b" N j'

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'w'illian 0. Parker, Jr.

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o DUKE PC4'ER CCMPA'iT MCGUIRE NUCLEAR STATICN INFORMATICN SUPPCRT!'.iG STORAGE OF CCONIE SPEC TUU. AT MCGUrd MARCH 9, 1973 1

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- L-D COSTrr!S Page 1.0 ISTRODUCT CN 1-1

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1.1 General 1-1

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1.2 Need For a ?ar: 70 License for Storing Geonee Spent Fuel at McGuire 1-1

1.3 Impac

of Storing Oconee Seent ?uel at McGuire 1-2 2.0 DESCRI? ION 2-1 2.1 Station Description 2-1 2.2 Site Characteristics 2-1 3.0 DESIGN CCNSIDERA CCNS 3-1 3.1 Desien Criteria 3-1 3.2 Confor ance with General Oesirn Criteria 3-1 3.3 Classification of Structures, Syste=s and Cenpenents 3-1 4.0 DISTRUMENTAnCN A2O Cob-'RCL 4-1 4.1 Incredue:1cn 4-1 4.2 Nuclear Service 'a*ater Systen 4-1

4.3 Componen

Coc11mg '4a t er Sys t em 4-1 4.4 Instr.:=ents:1cc and Control Pewer Supoly Systes 4-1 4.3 Spen: Fuel cooling Sys:em 4-1 4.6 Fuel Handling System 4-1 4.7 Refueling 'a'a t er Sy s t es 4-1 4.3 Control, Ic docent and Cable Roems Heatine, Ventila:1on and Air Conditiening 4-1 4.9 Creundwater Orsin. age Svstem 4-1 4.10 Diesel Genera:or Fuel oil System 4-1 4.11 Diesal Genera:or Cooling 'Jater System 4-2 4.12 Diesel Generator Startin2 Air Svsten 4-2 4.13 Diesel Generator Lubricating 011 Systen 4-2 4.14 Fire Protection Systes 4-2 i

4.13 Fuel Handling Venti.lation Exhaus: System 4-2 4.16 Cperating Cont ol Stations 4-2 i

3.0 E'_IC RIC ?CWIR 5-1 3.1

nrroduction 5-1 3.2 Offs 1:a ?:ver Systea 5-1 5.3 Cnsi:e ?cuer Sysees 5-1 5.0 PETSICAL DF.SC1!?T CN CF FLT., EASDLING A'O STCRAGI STS EMS 6-1 l

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s Page 7,0 SUP?CRT STS~i2iS 7-1 3.0 RADICACnVE '4Asn MANAC1E'iT 3-1 i

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? recess Radiolegical Monitering Syste::s 3-2 I

9.0 RADIA 10N ?ROUCCCN

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,ALARA Oteratienal Considerations 9-l 9.2 General sca:1cn ?adiation ?re:ectice 9-1 10.0 CCR?CRAU AND STACCN ORGANI?.ATION 10-1 11.0 FIRSCNNEL 3Ani!'iG 11-1 12.0

. N-CINCY ?LANNING 12-1 l

13.0 QUALI'"Y ASSCRxiCI 13-1 l

14.0 STAHON ?RCCCUFIS 14-1 15.0 INI nAL ISTS AND GPIP.C CN 15-L 16.0 ACCDENT ANALYSIS 16-1 16.1 Introdue:1on 16-1 16.2 Fuel EandliER Accident 16-1 16.3 Loss Of C.f f site ?:ver 16-1

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17.1 5:stice Securiev Plan 17-l 17.2 Access Recuire. tents, 17-1 17.3 C== uni:stien 17-1 l

17.4 Testing and :taintenance 17-1 l

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..7Al.UATIGtt OF ALTIRNACT.S 13-1 13.1 Introdue:i:n 13-1 13.2 shi-en: of 3t,sn: Fuel :o a Ree:: cessing Taeili:-

13-1 13.3 shitcent of Scen: Fuel :o a Tuel S:cra22 Facili:~

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ctpansion 3:. Ocenee :uci :.:orace u.tpac::7

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Cease Zeac::: Opers-icn W.en Spen Fuel S:::aze Cat.tbili:y Is ?.xhaus:ed

'3-2 13.6 ship 5 pen: Fuel :o Another Rese:.,r site 13-2 13.7 Inprove.d ?uel L':ilization 13-2 s

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19.0 FINANCIAL ?ROTECTICN REQUHDCiTS AND I'IDDGITT 19-1 j

19.1 Introdue::ica 19-1 19.2 Analysis and 3 asis 19-1

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5. 0 INTRODUCTION 1.1 General Duke ?over Company's McGuire Nuclear Station (Docket Nos. 50-369 and 50-370, Units 1 and 2 respectively) consists of two 3411 MWe,1130 We West-inghouse pressurized water reactor (?WR) units loca:ed on the south shore of Lake Ucrnan in Mecklenburg County, North Carolina.

Construc-tion at the McGuire Nuclear Station site was initiated on the standby Nuclear Service Water ?ond under an exc=ption granted by the AIC on June 23, 1971. An additional exemption granted on December 22, 1971 allowed construction to proceed on all belov vade structures until con-struction pe: nits C??R-83 and -84 (Units 1 r 2 respectively) were granted February 23, 1973.

McGuire Unit 1 was originally scheduled for fuel loading in May of 1975 and Unit 2 in October of 1976.

Due to various constructica delays the current fuel loading schedule for McGuire is January, 1979 for Uni: 1

-and September,1980~'for Unit 2 vith 'co._ e:cial operation dates for Unit 1 and Uni: 2 of July,1979 and March,1981, respectively.

Duke ?over Company's Cconee :Melear Station (Docke: Nos. 50-269, 50-270, 50-287 for Units 1, 2 and 3 respectively) consists of three 2568 MWe, 860 MWe Babcock and Wilcox pressuri ed water reactor (?WR) units located on the shore of Lake Keovee in Oconee Ccung, South Carot tnn.

Oconee l

Uni: 1 is presently operating in the fourth fuel cycle and Units 2 and 3 in the third cycle (under D?R's 38, 47 and 55 for Units 1, 2 and 3 respec tively),

1.2 Need For 2 Part 70 License for Storing Cconee Spent Fuel at McGua -

As a consequence of delays and uncertainties in licensing procedures being experienced by Duke'.s spent fuel reprocessor, Allied General Nuclear Services (AGNS), 1: became apparent that spent fuel storage at Cconee needed :o be increased.

~41th the issuance of Amendnen: No.14 to Facility Opera:ing License D?R-55, the Cai: 3 spent fuel pcol was expanded fren 216

o 474 st rage racks (a 119 increase).

The pcol for units 1 and 2 is a shared f acility which has contained spent fuel since :he firs refuel bg of Uni: 1.

Therefore,1:s storage capaci:7 of 336 asse=blies could not be increased.

Af ter a thorough assess =ent of al:ernatives, see See:1on 18.0,1: vas deter-sined that the best course of ac:ica available 0 assura continued Oconee generation was :o ship Cconee spen: fuel to McGuire for storage.

According to the latest predicted fuel burnup ra:es a: Oconee, the first shipcent of spen fuel to McGuire !*ni: 1 nust cecur in the first half of 1979 in order to naintain a full cort discharge capabili:7 a: :he station.

However, in order

o provide for orderly prior planning, a license :o perni such storage is needed in advance of :his da:e.

Siven the licensing uncartainties experi-enced concerning McGuira, i: is prudent :o assune, for planning purposes, that the need o ship Cconee fuel for storage at McGuire vill precede the issuance of a ?ar: 30 operating license and, thus, a Par: 70 license has been sought.

Also, i: is Duke's understanding tha: the subjec: ? art 70 u

i License would nerge into the operating license (?ar: 30) for McGuire 'iuclear Station when received.

The s:orage of Oconee spent fuel at McGuire when compared to other alternatives is the most desirable with regard to both health and saiety and envirocnental concerns.

1.3 I= pact of Storing Oconee Scent Fuel at McGuire 1.3.1 Transportation of Spent Fuel The transfer of spent fuel frem Ocenee to McGuire vill be accomplished using shipping casks approved by the EC for general shipnent of spent fuel.

The shipment of spent fuel assemblies from Cconee to McGuire vill ultimately result in an increase in the number of spent fuel shipments to and from McGuire. The potential envircr= ental ispact attributable to shipnents to and frem McGuire, hcwever, is within the scope of the "Invirocnental Survey of Transportation of Radioactive Materials To and Frca Nuclear Pever ?lants" (WAS'd 1233, December 1972:

NUREG 75/038 - Supplement I, April, 1975).

1.3:2 Envirocnental != pact of the Stored Spent Fuel The storage of Oconee spent fuel at McGuire vill not influence or alter any previous envirocnental studies such as the McGuire ?f ul Environmental State-

=ent (7ES), due to the similarity between Oconec and McGuire spent fuel and the McGuire abill:7 to safely handle and store spent fuel.

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2.0-DESCRI?TICN 2.1 Station Description.

Refer to the McGuire ?SAR, subsection 1.2.2, for a general. station description.

2.2 Site Characteristics Ref er to the following secticas of the McGuire ?SAR:

General Site Characteristics 1.2.1 Nearby Industrial, Transportation and Military Facilities - 2.2 Meteorology - 2.3 Hydrology - 2.4 Geology and. Seismology ~,2.5 For additienal supporting data of site characteristics, ref er to volu=le 2 of the McGuire FSAR as f ollows:

Groundwater Hydrology - Appendiz 23 Geology Appet ddv 2C Subsurface and Foundat. ions - Append's 2D Seisnology - Appendim 22 Flood Studies - Appendix 27 Standby Nuclear Service '4ater Pond Das - Appendis 2G Auxiliary Source of Nuclear Service *4ater - Appendix 23 I

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1 3.0 DESIGN CONSIDIFATICNS 3.1 Desirn Criteria - Strue:ures, Cc=penants,

.nd Systems defer to Chapter 3.0 of the McGuire ?SAR.

3.2

,Confornance 'Jith General Desirn Cri:eria Refer to See:1on 3.1 of tue McGuire ?SAR for hcv facility structures, systens and cceponents nee: the NRC "General Design Criteria for Nucles: ?over ?lants" specified in Append 1;:: A to 10CFR 50:

Criterien 1 - Quali:7 Standa-ds and Records C 1:arica 2 - Design 2ases for ?rotection Against Natural rhencuena Cri:erion 3 - Fire Protec:ica (In addition, Du'..e has subcittad an indepth Fire Protection 2 valuation Report for McCcire)

Criterion 4 - Invirec= ental and Missile Design 3ases Criterica 3 - Sharing of Structures, Systems and Cceponents Criterion 17 - Electrical ?cwer Systens Criterion 15 - Inspection and Testing of Riectrical ?over Syste=s Criterien 19 - Con:rol Roca Criterien 44 - Cooling 'Jacer Criterica 45 - Inspection cf Cooling 'Ja er Systes Criterien 46 - Testing of Cooling i'..2er System Criterion 60 - Centrol of Releases ci Radicactive Ma:erial :o the Envirocaent Criterien 61 - Fuel S crage and Handling e.nd Radioactive Control Criterica 62 - ? evention of Criticality in Fuel Storage and Handlin3 Criterien 63 - Monitoring Fuel and 'iaste S:orage Criterien 64 - Monitoring Radioactivity Releases 3.3 Classification of 3: uctures. S'ystena and Cocponents 3.1.1 Seismic Classification All s true :ur es, systens and cespenents required to prevent :he "--~ --C ' ed relcase of excessive a=ounts of radicac:ivi:7 have a sai W - ^'assification of Category I.

Ca:egory I structures, systecs and components are identified in Tables 3.2.1-1, 3.2.1-2, 3.2.2-2, and 3.2.3-1 in :he McGuire ?SAR.

i Mechanical and eleenical sys cs ccepocen: safe:7 classifications are fully described in Sections 3.2.2 and 3.2.3, respectively, of the McGuire FSAR.

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3.3.2 Missile ?ro:ec:Lon Refer to See:1on 3.5 of :he McGuire ?SAR.

3.3.3 Seisnic Design Ref er to 3ec:1ons 2.7.1 and 3.7.3 of the '.!cGuirs FSAR.

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3 3.3.4 Design of Category I Structures Refer to Sections 3.3.1, 3.8.4 and 3.3.3 of the McGuire JSAR.

3.3.5 Mechanical Systems and components Refer to Sections 3.9.1.0, 3.9.1.1, 3.9.1.2, 3.9.2.1,:3.9.2.2, 3.9.2.3, 3.9.2.4', 3.9.2.7, 3.9.3.0, 3.9.3.1 and 3.9,3,3 of the McGuire ?SAR.

3.3.6 Seismic Desip of Category I Instru: entatica and Electrical Equipment Refer to Section 3.10 of the McGuire ?SAR.

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v 4.0 INSTRUMEiTAT'ON A.'iD CONTROL 4.1 Introduction The varicus instru=entation and centrol systens

• hich are. equired to sup. cort che storage of spent fuel at McGuire are described in the following' referenced sections of the McGuire ?SAR.

his description includes the functional per-formance require =ents, design basis, systen descriptions, design evaluation,-

and tests and inspections of these various instrumentation and control systems.

4.2 Nuclear Service Water System Refer to Section 7.4.1.2 of the NcGuire ISAR.

4.3 Ccmponent Cooling System Refer to Section 7.4.1.3 of the McGuire ?SAR.

4.4 Instn:=enutica and Control ?over Supply Systen Refer to Section 7.6.1 of the McGuire FSAR.

4.5 Scent Fuel Cooling Systen Ref er to Section 7.6.7 of the McGuire FSAR.

4.6 Fuel Eandling Systen Refer to See:1on 7.6.3 as it applies to the receipt and storage of spent fuel

- i only.

4.7 Refueling Va:er Systen Refer to See:1on 7.6.9 vi:h respect :o nake-up to :he spenc fuel pool culy.

4.3 Control, ?.cui::e-- '" c ble Faens Heatine, ~7en:11stion and.u-a Condi:1cning Refer to See: ion 7.6.10 of the McGuire 7SAR.

i 4.9 Groundwater Drainaze Systea Refer to Sectica 7.6.11 of the McGuire ?SAR.

4.10 Diesel Genera:or Fuel Oil Systea Refer :o See:ica 7.6.12 of :he McGuire FSAR.

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'4 11 Diesel Generator Ccoling Water Syste:1 Refer :ci Section 7.6.13 of the McGuire FSAR.

4.12 Diesel Generator Starting Air Systen Refer u Section -7.6.14 of the McGuire ?SAR.

4.13 Diesel Generator lubricating 011 Systen Refer :o Sec ica 7.6.13 of the McGuire 7SAR.

4.14 Fire Protectica Systen Ref er ':o See:1on 7.7.1.13 of :ho McGuire ?SAR.

4.15 Fuel Handling Ventilatico Exhause Systen Refer to Section 7.7.14-of the McGuire TSAR.

4.16 Operating Control Stations Refer to Section 7.3 of the McGuire ISAR.

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3.0 ELECTRIC ?cW.R 5.1

. Introduction An Offai:e ?over System and an Onsi:e Power Systen are provided :o supply electric power to the syste=s and cecpenents necessary for the storage of spenc fuel at McGuire.

The Offsi:e ?cwer System and the Onsite ?over Systes have adequate redundancy, independence, and testabill:7 to perfora cheir design functions reliably.

5.2 of fsite ?cuer Systems, Refer to.Secrion 3.2 of the McGuire FSAR'for a ccuplete descrip:1on of the offsite power sys cas.

5.3 Cnsite Power Systems l Refer to Section 3.3 of :he McGuire 7SAR for a complece description of.the onsi:e power systems.

(References to the main generator are not applica-ble.)

The Unit i diesel generators vill be available for use before the first shipment of Ocenee spent fuel to McGuire, however, :he auteca:ic s*arting and loading features of the diesel generators vill not be in operation prior to uni s artup.

Manual control vill be available in the event the diesel generators are needed.

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6.0 PEYSICAL DESCRI? TION OF IUIL FULTJLING XO STORAGE STS~I'45 In general, McGuire spent fuel asse=blies and Oconee spent fuel assemblies are very s' d' ar with regard :o both physical and chemical and nuclear characteristics.

Any dif f erences in fuel descriptions, handling, or stor-age are included in the folleving sectices of the McGuire FSAR:

Spen Tuel Storage - 9.1.2 Spent Fuel Cooling Systen - 9.1.3 Fuel Handling Systes - 9.1.4 Also ref er to See: ion QO10.24, '.*olune 11 of the McGuire FSAR for NRC questicus and Duka respceses.

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i 7.0' SUPPORT 5?S m s The various auniliary systens or portions of systens required - to supcort the storage of spent fuel at McGuire are described in the following referencedLsections of the McGuire ?SAR.

Th.'s description includes the design bases for.each systen and for critical components, a' safety evaluation demonstrating how the syste:2 satisfies ~ he design bases.

The testing and inspection perforned to verify system capacity and reliability are also provided.

Nuclear Service Water Syste:2-9.2.2 Component Cooling Syste:s - 9.2.4 Refueling Tiater Syste:s - 9.2.5 -

Treated Water Sys: ems - 9.2.6 Conventional Waste Water Treatment Syste= - 9.2.3 Compressed Air.Systens - 9.3.1 Nuclear Sa=pling Systes - 9.3.2 Equipcent and 71oor' Drainage System -'9.3.3 Chemical and Volune Control System - 9.3.4 3cron Recycle Systen - 9.3.6 HVAC Syste=s - 9.4 Control Room - 9.4.1 Auxiliary Building - 9.4.2 Radwaste Area - 9.4.3 Diesel 3uilding - 9.4.5 Fire Protection Systes - 9.5.1 Commications System - 9.5.2 Lighting Systems - 9.5.3 Diesel Generator Fuel Oil System - 9.5.4 Diesel Generator Cooling Water System - 9.5.5 Diesel Generator Starting Air Systea - 9.5.6 Diesel Genera:or Lubricating 011 Systen - 9.5.7.

Groundwa:er Orainage System - 9.5.3

. Diesel Generator Crankcase 7acuu:2 Systen - 9.5.9 Diesel Genera c Roca Su=p ?u=p Syste= - 9.5.10 Diesel Generator Intake and F.zhaus: Systes - 9.5.11-l

3.0 RADICACTI7E 'JAS'"d MANAGEMEh~r 3.1

'Jaste Lov, levels of radioactivity will be int:cduced into the spent fuel pool at McGuire as a result of storage of spent fuel shipped fro: Oconee.. Quanti -

ties of radioactivity released in. airborne and liquid ef fluen: streans vill be vell below applicable criteria and personnel _ exposures vill be mini-sal.

The source of radioactivity in the McGuire fuel pool vill come frem the shipping cask coolan: vben 1: is =1xed with :he fuel pool vater.

The radioactivity in the shipping cask coolant vill co=e fron :he Ocenee spent fuel pool vater when the assenbly is loaded and fren the potential release of fissica products through small defects in the fuel-cladding.

Realis-tically, the a cunt of radioae:171:7 vhich vill migra:e f:cm any fuel pin defects to the cask coolant is expected :o be very s=all; however, for

he purposes of a conservative analysis it is assu=ed : hat 0,12% of the d ef ect activity is released.

This assu=p tion is based en *4AS3-1238, "Environnen:al Survey of Transportation of Radioactive Materials to and from Nuclear ?over ?lants."* yuthermore, since all of the defect activity c

in the 0.12% defective rods is assened :o be cleased in transport, no 1

additional releases af ter the fuel has been stored need be considered.

Table 3.1 indicates the. McGuire fuel pool vater nax1=un activity concen-tration.

A 120 day decay pericd for each spent fuel asse=bly, prior to ship =ent, is asst =ed.

Also, a decontanination f actor by a conservative order of 10 for the cperation of the fuel pool purification equipmen: is f actored Leto Table 3.1.

(The contribution to :he total concentration due to the ::ansfer of Oconee fuel pool water is negligible).

85 Table 3.1 also shows the quan:ity of Kr and H released in airborne affluents and the quantity of fiss' ion produe:s released in liquid ef-fluents.

The liquid effluent releases are based on an inpu to the j

s tation liquid vaste processing equip =ent of 16 pounds per day of leakage f:c=.all sources.

The.si:e boundary doses due :o ai:Lorne releases as iden ified in Table 3.1 are 0.12 sren, 0.001 cree, and 0.0002 =re: :o the skin, whole body, and thyroid, respectively.

Doses :o the =axi=us exposed individual due :o :he liquid releases are less than 0.0001 cre=.

The direc: dose fro: :he fuci pool vater concentra: ions is 0.1 :r/hr a:

the pool surface.

In susmary, small enounts of radioactive = ate ial vill be generated at McGuire from the transporting and storing of the Ococee spen: fuel.

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q is anticipated that any radioac:ive na:erial that is released fran :he i

site vill no: affec: :he health and safety of the public.

• The ac:ual talue in WA5'd-1233 is.25% of :he fuel gap activity, apparen:ly based en :he asscap:ica of a.23% f ailed fuel fraction which was an AIC s tandard a: :he time of publication.

A.12% failed fuel fractica is currently used by URC.

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3.2

?:ocess Radiological Fonitoring Svstems i

8.2.1 Introduction A cc=plete description -of the process radiological nonitering systen is given in Sec':1on.12 of the McGehe ?"1 A su:==ry cf th:.s sec: ion applicable to spent fuel storage follovs:

S.2.2 Design Objectives The ?:ocess Radiation F.onitoring System is designed to:

a.

?:cvide car'.y varad g to sta: ion personnel of equip =ent, ccuponent er system -=13uncticas or poten:ial radiological hazards within the station.

b.

? ovide ccccinuous acuitoring of radioactive liquid aM gaseous effluents during time periods when :sdioactive discharge is in process.

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? ovide interlocka to au:ccatically ter-Mante discharge fren vaste

.l systens at prese activity levels.

2 The ? ocess Radfation Manitoeins Systen is designed to =cni:c: prinary and secondary syste=s -ithin the station during normal operation includ-ing anticipated operatiocal cccur ences.

The location of sensors, the f

parz=eter =oc.itored, the type of sensors, and the ranges of the instru-centation provide the capabill:7 to detect and record required radio-activity levels, to alars high radioactivity, and to autecatically 1

ter=ina:e specific opera:icus in the event of anticipated operational occurrences. The anticipated operational occurrences related to tha.

radiation =cnitoring systens include equip =en: failure, iscperation i

or nalfune:ica vhich veuld resul: in radioactivity approaching lini:-

ing concentrations vi:hin :he ses: ion c in affluent paths f:cs the-s ta tion.

Radia:icn scai:or sensors are placed in loca: ions selec:ad to provide infornation (and cen--i '"~ctions where necessary) abou: the status of the various levels of radioactive fission products.

Radioac:ive 4

liquids and gasses resul:ing f ca spent fuel s:crage are processed by one or more of :he syste=s described in this section prio: :o dis-posi:1on.

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padia:icn detectors are located in the vaste effluent paths and provide l

back-up to laboratory analysis for the control of releasas by supplying interlocks :7 au:ena:ically :erminate releases at predetermined radio-ac:1vity con:entraticus.

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The parcseter ceasured (gross gn gross beta, or speci'ic isotope) and :he type of sensor sele::ad for each location are chose: to provide informa:icn to he opera:Or consisten: vith the radicactive isotope or ccubinatica of isotopes that are cost indicative of the status cf the unit, or that are expected to be potentially limiting.

Other factors which influence the detector type and the parane:er reasured inchde response :ine, raqubed sensitivity, backg und, and the availabili:y of equip =ent :o reasure the minuta radioactive concentrations consistent with regulatory limits.

Dilution f actors and/or b:egrated sampling are required to approach these sensitivities, particularly for airborne par:iculate, iodice, and liquid effluen:s.

The overall range of the peccess radiation coaltoring instrumenta:ica e=ccapasses the full ranga of radioactive cencentrations expected.

For scue applica icas, the nagnitude of these ranges requi e dual bst

=en-tation vi h videly dif f erent sensitivity characteristics.

W.ere =cre than one sensor is.necessary to insure coverage of the full range, over-lap of ranges is provided.

An analog display which indicates the activity being sensed is provided in the Con:rol Race for each coaitoring cMnnel.

Analog outputs frec all conitoring channels are also recorded en mul:1 point recorders located in the Control loca.

Centrol Room alarns are incorporated for a "unciating high radioactivity freu all conitoring cN"nels, for annunciating loss of sample fhv to detectors where off stress =onitoring is incorporated, and for annunciating failed or abnorr_al cenitor operatica such as :orn or depleted fil:er paper on airborne par:icula:e soni:crs.

rne signal condi:1cning and readou package for each acaitor channel includes a high level contac: cu:pu:,

the setpoint for which is adjus:able over :he full range of the inst:.::en:

Basis for setpoints of each nonitoring channel are Scluded with the description of :ha Ob ~ e1.

h addi: ice to prcviding high ala:n inic =ation, 6:erlocks are provided s e..= _a.., a _>, au.. a., <..y <,.., e.a, _s.

_._. en ~-. -...a

.i,..,.ea s., 3 2.,

e.: _: _,., e n.,

3

.. v e

vasco liquid effhant, ccuponen: :coling water, and C ::rol ?. co ven:i-

• .ati:n.

~'he interbcks are ob:shed in :he sa=e canner as the alar:s with identical se: point capability.

3.2.3 liquid Meni:oring

. g c i e :.n..,,

_t

,, o., a x t _ ko ~.

.v' ~. ~..' ", '_ ~ v, * ~.. c _a ' 2'

'A' _',. * ~.. '.W '.c. 4.

~3.% u y* ~_...,

v.--

3 3

is a s"--n-ry of continuous conitarbs equipment.

7:e liquid process ceni:::s provide indica:ica of radioac:ive oncentrations within closed piping sys:cas and provide an alar for high ccccen::stions b these systsas.

-"ce systans conitored include : hose which are er;ec:ed :o be con: arf.nated vi:h ::dio-ac:ive fission of Oc::csion p;cdue:s and : hose syste..s which would becc e contanica:cd dec :a :ceponen: failure such as hea; exchanger :ube laaks.

A descriptien of each liquid monitor is provided as f0licvs:

Spen: Tuel 20o1 Leakaga Monitoring - Refer :: subsectica 3.3.'..l.1-2 of the McGuire 73AR.

D

Ceeponent Cooling Jater Monitor - refer to subsaction 11.4.2.1.3 of the McGuire ISAR

• Jaste Liquid Monitor - refer :o subsection 11.1.2.1.6 of the McGuire ?SAR Nuclear Se vice 'Ja:er Mcni:or - refer o subsection 11.4.2.1.7 of the McGuire ?SAR 3.2.4.

Airborne Monitoring Table 3.2, Liquid and Airborne Activity Procesa Radiation Moni Oring Equip-nent, is a su= nary of centinuous noni cring equipaen including Airbo ne Activity Monitoring.

Also ref er Oc ISAR Section 11.4.2.2 (excepting contain~

nent).

3.2.3 Calibration of ? recess Fonitors Refer to ISAR Section 11.1.2.3 8.2.6 Sanpling Refer to ISAR Section 11.4.3 3.2.7 Inservice Inspec:ica, Calibra:ica and nintenance Reier to ?SAR Section 11.4.4 2

i 1

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3-4

Tabla 3.1:

.sotope cc

- A1:. borne Releases _ (C') Liquid'. Releases (C').

Fuel Fool Ceccantratica ("~C"') '

^

1 t

v:

vr

-4

-4

. ir 14.2 x 10 42 5.7 x.10 S5 210.

- Kr 39

-6

-5 1.1 x 10 Sr 4.1 x 10 90

-6

-6 5.6 = 10 Sr 2.1 x 10 J

90

-6

-6 5.6 x 10 Y

2.1 x 10

-c1

-6

-5 2.0 x 10 Y

7.5 x 10

-5

-5 Z:95 1.2. x 10 3.2 x 10 95

-5

-5 l

Nb 2.3 x 10

.6.1 x 10 t

1

-6

-5 Ru'03 4.9 x 10 1.3 x 10

-6

-5 Rh'03m 4.9 x 10 1.3 x 10

-5 Ru'06 1.5 x 10 -

4.0 x 10 106

-5

-5 4.0 x 10 Rh 1.5 x 10 t

4 134

-6

-5 2.0 x 10 Cs 7.7 x 10 i

137

-6

-6 7.7 x 10 Cs 2.9 x 10 l

1372

-6

-4 6.9 x 10 Ba 2.o, a 10

~0

~0 9.3 x 10 Ca 3.7 x 10 4

-3

-3 Ca SA 2.9 x 10 7.7 x 10 4

t

-5 2

?r 44 2.9 x 10 7.7 x 10 '

i-7

-6

~0 9.3 x 10

?u 3.5 x 0 N

l 4

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9.0

?ADIATICN ?RGTICTICN 9.1 M.Au Coerational Ccnsidera tons Consistent with Ouke ?over Conc.anv. 's everall cc~ai nec: to keen. cccur.aticcal radia: ion enpesuras as lov as reasonable achievable (Et?A) and vi-hin :he linits of 10 C'~R Par: 20, specific plans and erocedures are followed by

he operations, taintenance, and haalth physics 3:cif s to assura that LtRA 3cals are achieved.

Cperaticnal A1ASA polic7 statenenta are for--0 'ted at :he corporate staf f level 5 the Stean ?rodue:Lon Deg.t: nent :hrough the issuance of the Sv. sten Hea'.:h ?hv. sic.s .anual and are 6plenentad at each nuclear olant by neans of procedu as.

'hese s:stenents and preceda es are consistent with the inten: of Section C.1 of 3agulatory Ouides 3.S and 3.10.

?crsonnel and job exposure trends cre revievad by wng-enant at the plant and in the general office, and appropriata ac:ica is takan as necessa 7 Sc~-etry reycrts of occupati:n excosure are prcvidad : hat:

(a) describe problen areas. tere high radia:1ca doses are enecentered; (b) iden:ifv.tich verk trous is accunu-lating the highese dcscs; and (c) naka reem.ndations Ior changes 5 opera-ting naintenance, and in.spectica procedures or (d) naka reconnenda:icas for nodifications to the plan: as appropriate to reduce deses.

Maintanance activities that could involve significant radiation exposure of personnel are pre--planned. ~ hey utilize say previous cperating experience, and are carried out using trained personnel and proper equipnant.

Radiatica Work Per21:s (R:i?'s), are issued for each job which list health physics requircacces that nuse be folleved by all perscenel verking in the Radiation Control :cces (20:).

iaere applicable, speci'ic radiatien exposure redue: ion

echniques, such as these in ?.egulatory Guide 3. 3, are evaluated and used.

Procedures fer such radia:ica exposure rela:cd opera:icas as - -anance, fuel handling and ::.dvaste handling are planned and developed by cognizan:

groups, and are reviewed and approved by :he heal:h physics staff to ensure

hat expo sur e s v"

• 1 be AI.V.A.

Careful personne'. radiatica and contanin2 tion noni:oring are integral parts of such nain:enance ac:ivi:les.

Curing and

-upon ca:ipletice of najo:.2ia: c22nc e j o b s, persennel radiation exposures are evalua:2d and assessed ralatire :o estinated exposures so :ha: appropria:e changes can be nade in :echniques or procedures as seen as prac:icable for

..a.....v-c a.

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e p. g.

3. %..y 3.4.. - o.,..e.: 312 e --

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.d e #.'. ~.d... c.' a. a-4.=.

amequ. a. s,.,,..

a

~

. r.

corrected as soon as practicable :o ensure :hc: enposures vill be MA?a.

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a.

• >... -adi er.a c' 4...,

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1

-(

I 10.0 COR?CR.C 10D STATICS GRGANILCION Refer to Section 13.1 of the McGuire 75?d.

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2' W_ ~f.~. a..1 ~. ^ =. C e_ _ - a_ s_

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=."a.'.

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there vill be sufficien: perscenel trained and qualified in accord.uce with See:ica 13.2 of :he F.cCuire F3.G as necessary :o handle or direc:

he handling of :he fuel. Also, there vin be sufficient persc--a1 - ained and qualified to opera:s and naintain all the systens or parts of systeca necessar7 for the storage of Ocence spent fual.

Supervisory persocasi respeccible for spent fuel handling v

b e c," $ 1 ' = # ed Senior Reactor Cpera: Ors (cold license hciders per 1CCFR33).

i l

i I

i i

1 1

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i

4 12.0 DE.RGr*CT PLUCCNG Duke Power Conpany vill be prepared for any radioicsical energency situacien by developing * -

gancy Plan and imple.enting mergency procedures that protect the health and saf ety of the zaneral public. enplev..es of the station, or other persons tenporarily or pennently assigned to cGuire prio

o the receipt of Oconee spent fuel.

Ref er to the McGuire ?SAR ecd :he fact::ent entitled "'roposed ?.nergency Plan for McGuire Nuclear Station", yebrun7,1976, for :he followin~, 2egulator-i Guide 3.24 App - M " A info ma: ion:

Regulatorf Ocide 3.2i Iten Applicable 2sferenca 1

bergency ?lan See:icca 5.0 and 7.1.1 FSAR See: ion 13. 2 2

FSAR Secticus 13.1.2 and 13.1.1.4 3

h ergency Plan Sectiona 3.2, 3.0, 6.3 and 9.2 4

Emergency Plan See:1cn 3.0 5

hergency ?lan See:icas 4.3.2, 4.4, and 5.0 6

b ergency ?lan Secti:n 7.0 7

b ergency ?lan Sectices 6.5, 3.5, and 9.1 3

.b ergency ?lan factica 3.5.1 9

?.=ergency ?lan See:ict 7.1.1 10 Energency ?lan See: ion 3...a and 7.i.1 11 hergency ?lan See: ion 7.3 FSAR Section 12. 3.2 l

1 1

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i l

e 13.0 QUALI 7 ASSUFX;CE Refer to :Opical report DUIC-L-A, "Quall:7 Assu 2 ce Program", for a descrip-tion of :he Duka ?over C cpany quality assurance progran.

Bis topical is directly applicable :o che design, constructica, and operation of P.cGuire Nuclear Statica.

1 1

l

1 -

14.0 SnTION ?RCCELE Sectica 13.3 of the McGuira FSAR provides a 3eneral discussion of procedural activity for non:a1 statice eparation.

?roceduras vill be codifiad or new ones developed, as necassary, for the specific purposa of receiving and storing spen: fuel.

i 14-1

15.0 INITIAI, TISTS.UD OrI2.C'ONS The systens er portions of systent aceded to supporr the storage of Oconea s c. ent fuel ud

cno. '.ete and co. eraticral ud the a.c. o. cco. R.:2 testic3 sf.11

,a have been ccupleted prior to shipn=_n: cf Cc0cee spent fuel to .cCuire Unir 1.

A descripticn of :his tes progra.2 aill be available by "ay,1978 and vill be si,ilar to the test progran described in Sectica 14.1 of the McGuire ?SAR.

s l

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1 I

16.0 ACCIDENT ANALYSI5 16.1 In: reduc:ica With regard to storage of Oconea spent fuel a: McGuire, a fuel handling acciden; and the loss of of f site pcuer are f aults which are not expected to take place, but are postulated because thet consequencea veuld in-clude the potential for :he release of significant arounts of radioactive saterial.

A descriptica of each of these faults follows.

16.2 Fuel Handling Accident Ref ar to Section L5.4.3 of the McGuire TSA1.

16.3 Loss of Offsi:e ?over In the even: of a less of of fstre power the spent fual cooling systa= and associated systems necessary for cooling :Se spen: fuel pool vould be re-energized within amo (2) hour period sith pcvar provided by a diesel generator.

This provides sufficient :ine to start a spent fuel ocol cooling trata in D

order to maintain the poci :euperature less than 150 ? vith no rote than 300 Oconee spent fuel asse blies in the pool.

A brief analysis using the highes hea lead conditicas deconstrates this:

a.

Spent fuel is resoved fram Occuee reactor vessels in batches of 60 asse=-

blies.

Each ba:ch is allowed to decay for 120 days (=lai=ua) and is : hen transferred to McGuire a: the rate of cue asse bly per day.

No. of Total Decay Hea:

Assenblies Time (days)

Lead 3:u/hr.

60 180 1.62 x 10?

60 240

1. 30 x 10' 60 300 1.13 x 10 5 60 360 0.98 x 10, 60 420 0.36 x 10' 6

Total Hea: Load 5.39 x 10 3 U/hr.

s 0

The total heat lead of approaina:ely 5.0 x 10 3!U/hr., as shown above, was calculated using NRC 3 ranch Technical ?osi: ion A?C33 9-2, "Residual De:sy Energy for Light Wa:er leac: ors for Long Tern Cooling".

6 5.

With a heat load of 6 x 10 3'. U / h r. and a va:er capaci:v in :he McGuire 6

spen: fue a. poo. c: ox 0

lb. nass, a heat up rate af,o_,hr.

vculd 3

/

resul on a co:ple:e loss of spea fuel pool coolins (assuaing no hea:

loss f rca :he pool :o :he environne :).

c.

W1:h a haa: up ra:e of 2 T/hr. and an assaned ini:ial spent fuel pool

enpera:ure of 10'i ?, 1: vill :aka approx 124:ely 24 hcurs :o reach a pool :e:pera:ure of if 0*? acd appreaias:ely !? hcurs to reach 112 ?.

ht

17.0 FFTSICAL ?ROTICTIC'i This page is vi:hheld f ec public disclosure pursuant to ICCB. i:.790(d)(1) s 4

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17-1

13.0 EVALi'ATION 07 AL~I?3AT!7~.S 13.1 Introduction The al:erna:ives considerad fall into :he following general categories:

(a)

Shipcent of spent fuel :o a reprocessing fecility for storage.

(b)

Shi nant of spent fuel to a faal stor23e facility.

7 (c)

Expansica of Cconee spent fuel storage capacit7 (d) Cease reactor operation when spent fuel storage capability is exhausted.

(a)

Thipnent of spen: fuel to another reac ce site.

(f)

Inproved fuel utili:2: ion.

Each of -the alternr.tives is discussed in the follo -ing Subsections 13.2 through 13.7 18.2 Shipnent of Spenc ?2el to a Reprocessing Facility Duke has a centract with Allied General Nuclear Services (ACNS) for transportation and reprocessing sortices.

To date AGNS has not been able to obtain either a plant operating license of a license to :cceive and store spent fuel.

Shipping spent fuel to AGNS is therefore not legally possible and is not a sufficiantly dependabla option for Duk.e to raly upen.

Likewise, c:her potential reprocessors such as General Ilectric (GE) or

.. c_3 ear cue.3 serv 4ces (.so) are not v,aor, e op t,.ons.

..u 13.3 Shircene of S?en: Tuel to a ?uel Storage ?acili:v Spent fuel storage facilities at reprocessing plant sites have been dis-cussed in sectica 13.2.

This section considers s:orage facilities

o be built apar: frec reprocesso plan t sites e.g.,

a independen: si:es or at reac:o: plan: si:es).

13.3.1 Shipnen: of Spen: Fuel :o EECA for Tecporary 3:oraga i

The possible use of :he Depart:ent of Energy (002) facili:les at Handard j

and Sava---h Rive: Plan:s :s store spent fuel has been investiga:ed.

Sinc e 30E has no present plans :o nake :hese facilicias available :o the u:111:7 industry for 3:orage of spent fuel, :his option is no: curren:ly viable.

13.3.2 Construe: an Independen: Spen: Fuel Storage Facili:7 Ouke has considered :;as::ucting an independent spen: fuel s: ora;e f acility which cot 11 Se buil: 4: 2n iniscing Duka nuclear si:e c: another site for receip: ]! spen: fuel beginnin3 in 1933.

This alterna:ive is :urrently judged undesirable for adding fuel s: ora;a capabi'i:y becauce of :he large cenat:nen: af rascur:es requirad.

10-1

4 e

i e-k

/i 13.4 Exoancien o f C._c_6.e. Fuel Storn e Capac':7 Consider 1 tion was gtten to providing addi:1:nal storage a: Oconec so that transporta:Lon of spent fuel to another storaae locatien W d4 ot be re-quired.

The addition of high' densi v. racks a: Ccenee Unt: 3 (See:ica 1.2 of i

this doctrnant) aliciated.h2 stort-*

- oblcn :e:porarily.

Storage 2npansion of the Osi: L and 1 s orage pool veuld also requira use.af high density s

s torage rac's.s.

To tecet:711sh thb, all fuel veuld have to be cved cise here, the pool ixatnad and decentrnicatad, eniacin3 racks renovad, cnd ne 3 rack 3 f

installed.

Since spaca for interin s:ces p of the fuel in the Ccense 1 and 2 pool 1a not available this optica is not considered riable.

18.5

<Ceash 2aactor Opera:Mu *.Thea Joent Fuel 5: orate Carability Is ?.xn...us t ed If no ac;bn is talen by Du'ce, Ccenee 2:1:s 1, 2, and 3 voeld be forced :c shut deva during 1990.

~'his shutdown ve"'# % ~^ssary due to full spect fuel pools 26.1:g further fual discharge fren -he raacto:s in;ossihla.

• he econcale penalty for such action is obvi;usly 2n= nous and unacceptabla.

s,

l'he cost of reolac2=ent power bv. fossil futi planes on the Duka systes a

would be several hundred thousand dollars per day b 1980, if the pcuer was available.

If purchaael cursida the Dv'ca 'sys ca, the cost vould be evan grea:er. Therefore, it is considertd that ceasing operatica of the Cconee reaccora due to insudficie.: fo me fuel scorage is not in the interest of s

Duke or hs custccera.

13.6 ship Spent ?uel to'Ano.th.er 7.can: r site Considera:1cn was 3 7ec :o tha pas.uibility of shipphg spent fuel to 1

other reac:0: si:es w h hia :he Duke sys::=.

In :he required :isa frane, only }'cGuire is avail.ble f or such storage in 1979 and 1930.

13.7

• preved Fuel Utiliza:ica n

Duke is involved in several programs :o improve :he utili:a:ica of fuel.

Duke is studying :he feasibill:y of i=plenen:ing an 13-aca:h fuel e.ycle a: :he Cconee 3:2 ion.

In addi:i:n, Duke is cut ently discuss h3 with

he Depar:nen: of I.nergy, a propcsal for a ecopera:1ve prograa which 411 result ia ex:ending :ha 211:vable burnup of fuel assa:Olia nsed 2:

Cconee and ochar dcaestic pressurined va:c: r eac:::s. If these prograns are su::estful, an increac2d acount of energy would be derived iron each fuel asse bly, thereby decreasing the nte:ber of spen: fuel asse m ies i

dis cP.s:ged.

1*cvever, the impac: of such p rgra=3 ac near-:er: fuel l

storage requirements is neglizible and the problen of ever inc: easing av; e m.,,

s y a a.,, s _ _s 2 --,.s

,,X.< a-. s.

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1 1

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49.0 TDAhCut ?ROTIC";IGN RIr5IRF.EIns AND DiDI?2i;~T 19.1 Int:cdue: ion Duka p 0posas to ship to and store at its McGuire facility fue!-used or p;cduced at its Ococte faci' tty, both befora ::d afte: Y.cCuire is licensed

o operate.

With re3ard to the fiaaucial pro:actica tad ir 11:7 require-

=ents of 3actica 170 oe the Accuic Inergy Ac:,

13 a: ended ( c e SC 2210), and 10C71 Far: 140 Duke b.alieves that it is :cqui cd ' provide financial prote :1ca and to execute an inde:alty agreenent.

?c the reaseca set forth in Sec:1on 19.2, Duke believes : hat an app::priate maccc: of financia'. pro-tectica (perd123 issuance of cperatin3 licecaen in McGuira) vculd be fise sillieu dollars ($5,000,0C0) and tha: the tadacaity fea sneuid be se: a:

five hundred foliara ($500) per atsum.

As set forth in Section 19.2, Duke is of the viev that an apprep..a:e acdi-fication c: the Lada-vf :7 23:coccat contained in 10CTRil50.92, Appendi: 3 vould be required, but tha: no change 1: :he facili:y form of nucles: '1 ability insurance set fs :h in 10CTRil10.91, Appendix A 34t:3 :o be needed.

AccordiO3 y 1

Duke requests that :he Cornisaica issue a cotice pursuen to 10CTR1140.9 ci its intecc ta issue n indm' 7 agrecreat.

Followins issuance of operatics liceases, the acou:: of financial 7: tec:1oa and applicable fen parsuant to 10CTR$140.7, with respec: :o activities, lucluding storage o* Ccosae fuel a: McGuire, vould be thore applicabic under presen: law.

19.2 Analysis and 3 asis Duke received cotstruc:1cn per:1:s, C??R-33 and C??R-a4, for McGuire Units 1 a nd 2 en Feb ruar y 23, 5373, p.rsua:: :o See:iots '.03 and '35 (42 USC 5 5 2133 and 2235, respe<.:ively) of -he A::mic Inergy Act, as m:endnu ("Ac:").

Secti:n 170a s2 the Ac: requires proof of financial p: '.ection by facility liccnsces and coes::ue:ic n pe:mit holders.

provii a:

• Iach li<.etse issued under sec:1;c 103 and '.Ci and each construe:10:

)

per:1: i ssued under see:10: 1351' shall.

. have as 2 c di:lo:

of the ticense a requirezca: :ha: :he licenseu hace and rain:si financ141 protec:ica f such :ype end in such accu::s and regula: cry authori:7 and responsibi'i:7 shall require in a::ctda::e.-ith sub-sec:ian 170b :o cover ;ublic liabill:y clains.

t Section 17Cb of the Act authori:es -he Ccznissica :o es:ablish a:cun:s of finaucial pro:ec:1cc.

An exanizatice of the re3ula:1 cts reveals that a v ~-

speal.

• ire l/ :o :he za::er of financial ;;otecti:: and indennity vi:5 resp

he storage of i::adia:ed fuel (us -d or pe:duced at ano:her of :h6 135 cf :he Ac: also p::videa cha: "a c ts:ruc:ian ;e rni: is e, cel$ e en

)

O a L.

e 19-l

-hm e--

.-mi i

e licensee's licensed facilities) at a facility for which construe: ion

• permits and an appropriate na:ertats license have been tasuad, and he operating licensa has 2o: yet been :aceived.

10 C7R$140.13 rela:es to cold fuel and requires financial protectica in :he 12cun of 31 nillica when the fuel is abou: to be received en site.

In :hree paralle' inc:ances, applicationa vare cada :e ste:1 apant fuel at facilities other tha: :hosa Vherein the fuel becane 1 :adiated.

Each of :he facilities in question had received cotstrue:1cn per:1:s hu: had yet to ob t ain op erating 11cena - n -

In simh circums tanc ea, the Cc 213sion, a

parauan to ita rulecakin3 authori:7, es:ablished financial p ctacti n requircrents en in in: erin basis.2/ See the Ccerission's a:: ion in Nuclea: Fual 3ervices, Inc. (N?S)7 30 Fed leg.1015 (Januar7 30,19c5);

Xidwes: ?ual Iacevcry Plant (.1712), M Tcd. Reg. 17979 (Sep:achar 3, 1971); and 3c:nve11 Nuclear 7uel Plac: (3N7?), 40 Fed. Reg. 11S53 (March 21, 1973).

La each instance, :;e Cennisaien established a five nillica dollar (35,000,000) require:e ct f, e ficaccial protec:icn for the p:eapara-ticcal stsres: :f fuel with an annual dede=at:7 fes of five hundred dollars (3500) for s:orage :217 of fuel.3/

In light of the. beve, tuke submits tha: a five nillica dollar (35,000,000) :equire:ent f: fi1ancial pro:ectica and a five hundre.1 dalla: (S500) annual inde:nity f ee for :be precperstional ste:a3a of Ccocee spe : fuel at McGuire are appropriata.

Duke is in the precess of chtainia; covera 3e in the anoun: reflected above and c pects that, pursuant to 10 C72140.13,1: vill provide proof of financial protection prior to the receipt of Cconee spent fuel a

McGuire, i

In light cf the above, Duke requesta tha: the inderni:y agree:4n: p roviding inde=21:7 ceverage for McGuire incorpo:2:e an apprep:ia:e modifica:ica to j

the standard definitica of "the radicactive sa arial" con:ained in 10CF25 140.92, Appendix 3, A::icle 1, paragraph 9, so as to provide indennity 4

ecverage for r:crage a: McGuire of spect fuel genera:cd by the Oconee Fa-i

-<,<~.,;.

\\.

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i 2/ A1: hough the Oc:21:aica u:llicec i:s rule =Aking zu:hori:7 in -Jie above 4:stacces, i: ia 2o: nacesaar7 to rely upon ru',e:aking far :he 23:ablish-

f financial pro:ec:1:a requirenents and inde=ni:7 fees i: this case.

men:

l Rule =aking v2s enbarked upon because :he fccilities in questica vere :heni-cal repr cessing planta led :he Cornissica's regula:1:cs fid not prescribe j

ft:accial prote::iaa and indet:1:7 f e a raquira:ents for such facilities.

l The Carnissica's sgu'.a:icas ia 10 CF2 ?ar: *40 do pras::ibe :ha requi-si:e requirt2e :3 ?ar reac: cts and actice ;ursuan: :: 10 ;?R 140.9 prio:

o issuance of aa indemnity agreenact in:cepera:ing :he varia:1;; ra-ques:ed hereia, should suffica.

19-2

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