ML21042B896

Independent Spent Fuel Storage Installation, Biennial Update of the Defueled Safety Analysis Report

ML21042B896
Person / Time
Site:	Maine Yankee
Issue date:	01/11/2021
From:	Norton W Maine Yankee Atomic Power Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
OMY-21-002
Download: ML21042B896 (54)

Text

MAINE YANKEE 321 Old Ferry Road, Wiscasset, Maine 04578 January 11, 2021 OMY-21-002 10 CFR 50.71(e)(4) 10 CFR 50.4(b)(6)

ATTN: Document Control Desk U.S Nuclear Regulatory Commission Washington, DC 20555-0001 Maine Yankee Atomic Power Company Maine Yankee Independent Spent Fuel Storage Installation NRC License No. DPR-36 (NRC Docket No. 50-309)

/ 2 - 0 3 0 Subject Biennial Update of the Maine Yankee Defueled Safety Analysis Report Pursuant to the requirements of 10 CFR 50.71(e)(4) and 10 CFR 50.4(b)(6), Maine Yankee Atomic Power Company (Maine Yankee) is submitting a periodic update of the Maine Yankee Defueled Safety Analysis Report (DSAR) to the NRC. Enclosure 1 provides Revision 29 of the Maine Yankee DSAR in its entirety. This revision was issued after Maine Yankee submitted its previous biennial update on January 14, 2019 (Reference 1).

The following table provides a summary of and the rationale for the changes implemented in Revision 29 to the Maine Yankee DSAR.

Revision 29 The DSAR was revised to update the references in the document. This includes revising the references to the NAC-UMS Certificate of Compliance and NAC-UMS Final Safety Analysis Report to state that the applicable amendment and revision are defined in the 10 CFR 72.212 Evaluation Report and to eliminate duplicate references and historical references that are no Ion er licable i.e. no Ion er referenced in the text of the DSAR.

This letter contains no commitments. If you have any questions regarding this submittal, please contact Mr. Daniel Laing at (207) 882-1303.

I declare under penalty of perjury that the foregoing is true and correct Executed on January 11, 2021.

Sincerely, Wayne Norton Chief Nuclear Officer

Maine Yankee Atomic Power Company OMY-21-002/January 11, 2021/Page 2

Reference:

1.

Maine Yankee letter to the US NRC, "Biennial Update of the Maine Yankee Defueled Safety Analysis Report," dated January 14, 2019.

Enclosure:

1.

Revision 29 to Maine Yankee Defueled Safety Analysis Report cc:

D. Lew, USNRC Region 1 Administrator T. Dimitriades, Chief, Decommissioning Branch, USNRC Region 1 J. Hyland, State of Maine G. C. Poulin, Chairman and President, Maine Yankee

ENCLOSURE 1 TO OMY-21-002 REVISION 29 TO MAINE YANKEE DEFUELED SAFETY ANALYSIS REPORT

Maine Yankee.- Ato*mic *pti,w-er, Comp<<n:y

• nefuele~d... S:afety* Analysis*.Jl~epoJ~t

{FSU)

MYAP,C LIST OF EFFECTIVE PAQES

,Table of Contents All pages are converted to Revision29 Section 1.0 All pages are convert~ to R~siqn 2&

.Section 2.0 All pages are converted to R~vision 2.8 Section 3.0 All pages are converted to Revision 29 Section 4.0 All pages are converted to Revision 28

.Section 5.0 Section previously deleted

. Section 6.0 All pages are converted to Revision 28 Section 7.0 All pages are converted to Revision 28 DSAR Rev.29

Page Repla:cem.ent Instructions for R(}v:ision 29 This is not a complete revision of all the pages contained within the DSAR.

Ilemove and replace onlythe following:

DSM Cover Sheet, 1 page List of Effective Pages, 1 page*

Page Replacement Instructions, 1 page Table of Contents, 2.Pages Section 3.0, 16 pages

MYAPC Defu eled.Saf ety-.Analysis.Report TABLE OF CONTENTS-

1.0 INTRODUCTION

AND

SUMMARY

1.1 Introduction 1.2 Speht Fuel Invoinozy:

1.3

~Rent Fuel °Jnv~tgry,Desi~.ory)e~-

1.4 Plant Site and..Popuhrtiop 1.5

_Material *Incotporated qv Kefetence; 2.0 THE SITE AND ENVIRON~

2.1 Location and Area 2.1. l Population 2.1,2 Land Use 2.2 Meteorology 2.2.1

~neral 2.2.2 Onsite Meteorological Field Proiµ-ams 2.2.3 Coastal Fog 22.4 Tempei:atw:e 2.2.5 Precipitation 2.2.6 Tornadoes, Hurricanes, lllJ,d Severe Thund~rstonns 2.2.7 Environmental Monitoring Program 2.3 Hydrolqgy 2.3.1 Surface Hydrology 2.. 3.2 Oceanographic Feaj;ureg 2.3.3 Probable Maximum Flood 2.3.4 Groundwater Hydrology 2.4 Geology 2.5 Seismology 2.5. l Tectonics 2.5.2 Tsunamis 3.0 ISFSI 3.1 Introduction DSAR t

Rev.29

3.2 3.3 3.4

'3.5 MYAPC General Description.oflsFSr"F~ility

'.3:2. l General 3.2.2 Principal Charlfcteristics of Site 3.2.3 ISFSI Facility Principal Design Features Oen~al lSFSI-System*Describtion

33. l ISFSI Storage System-General 3.3.2 ISFSI Universal Storage System Components 1dentificatlQn,of Agents1and Contractors References 4.0 RAJjIATION PROTECTION

• 4.1

• Radiation Protection Program 4.1.1 H~tb Physics 4.1.2 Radioactive Materials Safety 4.2 ALA.RA:'Program 4.2.1 Policy Considerations 4:2.2 Design Considerations 4.3 Radioactive Waste:Ma:nagornenf 4.3.1 ISFSI Operations*

5.0

-ACCIDENT ANALYSIS (Deleted)

• 6.0 CONDUCT OF O~ERATIONS 6.1 Responsibility and Organiz_ation 62 Technical Specifications 6.3 Training 6.4 Procedures 6.5 Programs 6.5.1 Emergency Plan 6.5.2 Security Plan 6.5.3 Quality Assurance Program 6.6 Review and Audit 7.0 DECOMl\\flSSIONING 7.1 Summary of Activities DSAR Rev.29

Section 1.1 12 13 1.4 l.5 Table No.,

1.3.1 DSAR Introduction MYAPC SECTIONl.0 INTRODUCTION AND SUM1\\1ARY

-~AB~-~~ CONTENTS*

Speht-Fuql Inventory Spent Fuel 'Inventocl*DesiBJJ' overview

_Plant sue and.Population Material Incorporated by Reference LIST OF TABLES

~

Maine Yankee Design Characteristics 1-1

~

1-3 1-4 Rev.28

1.1 Introduction MYAPC SECTION,1~0 INT,l{ODUCll(?NAND 'Sl,JMMARY The Maine Yankee nuclear electrical generation plant was located in the Town of Wiscasset, within the midcoast region of the state of Maine, approximately 27 miles northeast from the city of Portland. The plant, a p~urized light w~ter mo<l~rate<I nuclear reactar; was:oVr'tled by.a'9<>0§0rtforµ of n New

'En~and eiectric utilities reprentjng consumers in ~iile; New*:Hatnpshirt1/4 Vermont,,Massachusetts, Connect,icut, and Rhode Island. During the24*y~ar ~g llfeti~e.9.f~e Maine '¥artkee plant, more than 125 million megawatt-hours of electrical power were generated and distributed to these consumers.

The Defueled -Safety Analysis Report (DSAR) was developed as the principal licensing source document d~cribingrthe:pertinep.t ~uipment, struotures,;systems, operationaf constraints and practices, accident analyses. and de,c;olJltllj_ssioning-aC,tiviti\\;)$ aS;SOO~~~twith the defueled condition of the Maine Yankee 1tl~t. As:sucli, the DSARwas intende,qjo ~~-in$le same role as :(be Finiµ_ Siµety Arullysis Report of Ma,in,e 'Ya:rik:ef;:91,IFing ilie peri<:ids:.'ofpower-operation.between 1972 and 1997: The *osAR was applicable throughout the decommissioning of Maine Yankee.

'the predecessor to the DSAR, the Final Safety Analysis Report (FSAR), *was developed to apply for a license under Section I Q4'(b) c,f the Atomic En6rgy Act of 1954, as amended, and the regulati0ns of the Atomic Energy Commission (AEC) as set forth in.Title 10 of the Code of Federal Reguiations (CFR), to construct and operate the Maine Yankee nuclear electrical generation plant The application for this license was submitted by the Maine Yankee Atomic Power Company (MY APC)'in 1967.

The construction permit was issued on October 21, 1968. The Operating License (OL) was issued on Septe!]1ber 15, 1272. This 0L authorized power.operation of the, facility until October 21, 2008.

Addit(e,nally, th~fOL autboriz¢d pow~r*tevel~ up '10175% rated thermal ppwer. C<;>mmercial operation of the plant commenced* on P~c.ember 28, 1972. The ABC granted a license to operate the facility at 100%

mied_ ~epnaJ:~~-authorized power levels l!P'ta.,al)d inc;luding 2440 megawatts thermal (MWt) in June, 1973.

Various amendments to the operating license were subsequently issued and, for a period, authorized the power 5ta:ti9i;i t.o pperate at power levels up to.and incJuding.2, 7,00 MWt This power level corresponds to.

a nucle,ar ste8DJ, supply system (NS_SS-),--ou_fput of2,715 MWt and a gross electrjcal output of approximately 93 f MWe. On January 3, 199*6,_ ih~.succ~Qrto the* ABC., the Nucli:iat Regulatory

{::ommi~on (NRC), ~cted power o~~n ap the Jviajge Y 8¥~ plru_rt t,cf ~O MWt :(90% of the currently rated licensed power) pending reviews and,asse~ts~ingus~,,qfSII!-,aJJJ?teak Loss.of Coolant Accident analysis methods utilizing the computer code RELAP5Y A.

Maine Yankee ceased power production on December 6, 1996 to address cable separation and other issues. By June 20, -1997. the reactor had beeri completely defueled and all spent fuel was resident in the

~pe~ fuel, pool. On August 6, 1997, the Malne,Yapkee Atomic Power Company Board of Directors

• v9,ted_ to penn_anently cease power operations an,d initiate the decommissioning process. On August 7, 1997. Ma'ine Yankee provided written certification*to;the Nuclear Regulatory Commission, pursuant to I 0 CFRS0.82 (a)(l)(l) and(ii), that the Maine Yankee Atomic Power 'Company permanently ceased op~ons of the Maine Yankee Atomic Power S4tti9n and that all nuclear fuel ha:d been permanently removed from the reactor.

The issuance of this certification fundamentally changed the licensing basis of the Maine Yankee plant in that the NRC-issued 10 CFR 50 license no longer authorized operation of the reactor or emplacement or retention of fuel in the reactor vessel. Therefore, as of August 7, 1997, only those conditions or activities DSAR 1-2 Rev. 28

MYAPC associated with the safe storage of fuel apd radiologiciµ protection (incluqing Y{aste handling, storage ~d disposal) were applicable to the defueled Maine Yankee plant 1.2 Spent Fuel Inventory Following th~ cessation of power operation an~ th~ removal of fuel from the vessel, the ~nt fuel J~xei\\tory, consisted ofatotal,of i 422._c.9miitet~~Juej *~m1?lfes;12 pafflal~1 ccins6lloatecl assen1_blie.s, a,nd i Rartially full failed f"?el rod-*contaiiiers: ~dcfrtio)'IJllry,, 16,~.~~ ~~Pw(.~~rf.9Qritai.Qej:l;ll:5sociated GP.ntrol,.Element Ass~hlles ~CEAs) ~cl QEA,-fi~gerai.As*of.Ma:rob:20Q4) ~I sp:tmt ~:w.asJransfi,rn:g to the Independent Spent Fuel Storage Installation (ISFSI).

1.3

• Spent Fuel Inventory Design'Oveniew Key design data for the spent fuel inventory are listed in Table 1.3.1.

Tho Maine Yankee plant was located on the_ west shore of the Bac_kRiyer approximately 3.9 miles south of'the center qf Wiscasset, Maine. This location is shown in. Figuro 2.1-IA Withjn a 5 mile-rad~s of the.plant site, the resident populatiQD d.~_ify is esiim$#Lto-jv~ge 85 persons pe~ square m~~i29J0). Th~ n~ ~lation,fo~witbinS mil.es was s~tetf aroond,the 1.~wµ of Wiscasset, 3.9 miles NNE.of.*the site. ~

lown:ofWISCasset has a popuJa,tion of about 3,732 people (2:0:l0)..'Uif~und?ig*to~s'.o!E~eoo~b. ~~.tti_bpy, ;~09lw_iel\\*:ap~ '?/~~Isµilid, w~olly or partially w,ithtn a 5 011le..md1us, tiave a population:dta;1~9'j5ersons. {201,Q.), Tije*CJty-_ofLe,wtston, 24 miles v/Nw. frOD) -the:pl~ site, js ~e.: Jl~ ~

'With-a'populatloifin-ex~*.oi25,,00Q~

The site characteristics are discussed in detail: in S~on 2.

1.5 Materlal.Jncorpofated ByRe~nce Certain program documents and associated topical reports or analyses have*been *incorporated into the DSAR by reference and are listed in each section as appropriate.

Some documentation that is incorporated by reference continues to be updated to assure that the information used is the latest available. These documents include the following:

1. Quality Assurance Program

2. Emergency Plan

3. Security Plan Each of these programs and plans may be modified as necessary in accordance with th~ regulatory and Maine Yankee requirements identified in Section 6.

DSAR 1-3 Rev. 28

MYAPC TABI;,E 1.3.1

,MAINE y ANKltE'J?ESIGN'CHARACTEIUSnCS Note:,

Selected infonnation in this table is being retained for historical purposes only.

Plant Output l

Net Electrical Power Output (MWE)@2,700 MWt Gross Electrical Power Output (MWE) @2,700 MWt Maximum Expected Gross Electrical Output (MWE)

Reactor Core Total Heat Output (Btu/hr)9.215 x 1<>9 Heat Generated in Fuel (%)

DNB Ratio at Nominal Conditions Minimum DNBR for Design Transients Core Power Density (kW/liter)

Number: of Fuel Assemblies Number of Fuel/Poison Rods per Assembly Fuel Rod Pitch (inches)

Fuel Clad Material Fuel Clad Nominal Thickness (inches) CE & 'Ji..

Fuel Clad Nominal Thickness (inches) Exxon Fuel Poison. Material~

Number of Control Rod Locations (maximum)

CEA Pitch (inches)

CEA Poison Materials Control Ro<fDrive Type Equivalent Core Diameter (inches)

Total Uranium (MTU)

DSAR 1-4 905 931 931 97,5 (Y AEC-1 Correlation) 83.01 217 176 0.580 Zircaloy-4 or ZIRLO 0.028 0.031 85 11.57 B4C/B4C with Ag in Cd tips Stainless Steei M~etic Jack 136 80-83 Rev. 28

SECTION2.0 Sectjon 2.1..

2.2 2.3 2.4 2.5

.FtgureNo.

• 2J-'1A

• 2.I-*IB DSAR Title

).,ooation* And Area

~.1.1 Population 2.1.2 Land Use Meteorology 2.2.1 General MYAPC THE SITE AND ENVIRONS TABLE*OFCO~

2.2.2 On-Site Meteorological Fi<;:ld Programs 2.2.3 Coastal Fog 2.2.4 Temperature 2.2.5 Precipitation 2.2.6 Tornadoes, Hurricanes' and Severe Thunderstorms 2.2.7 Environmental Monitoring Program Hydrology 2.3.l Surface Hydrology 2.3.2 Oceanographic F.eatures 2.3.3 Probable Maximum Flood 2.3.4 Groundwater Hydrology Geology.

Seismology 2.5.1 Tectonics 2.5.2 Tsunamis Title LIST OF'*FIGURES Licensed Site Boundary (Bailey Peninsula)

'Licensed Site Boundary (ISFSI Site) 2-1 2-2 2-7 2-12 2-16 2-P 2-5 2-6 Rev.28

MYAPC SECTION2.0 THE SITE AND ENVIRONS 2.1 Location And Area The Maine Yankee Atomic Power Station was located in the town of Wiscasset; Lineoln County, Maine.

Sit~ coordinates are approximately 43 degre~ ~7 minutes§ seconds north latitude,and 69 degrees 41 minutes 45 seconds west longitude. The licensed site is bounded by Back River on the east, Old Ferry Road on the north, and Bailey Cove/Youngs Brook on the west. The-plant was located on a peninsula known as Bailey Point which extends south to Montsweag Bay, as shown by the site area map 'in Figure 2.1-lA. The waters of Back River, Montsweag Bay, and its-tributaries' are tidal and open to boating, both commercial and recreational. Regulation qfthis boating is the responsibility of the U:nite:d *states.Coast Guard and the state of Maine.

The plant site itself was located on a ridge of bedrock rQDJling northeast to s.outhwest to form-Bailey Point The maximum elevation of this rock is a knob 75* feet-above mean sea level located about 700 feot northeast of the plant. The general elevation of Bailey Point.Varies from sea level to 40 feet above mean sea level. The plant area was graded to elevation 20 feet A layer of glacial till has been deposited ~boye the bedrock and 'has an average depth of 15 to 20 feet. A detailed description of site geology is given in Section 2.4.

2.,1.1 Population The infor'mation provided in this section is "Historical Information".

The concentration of population in the vicinity of the site is low. Within,a 5-miie radius of the site, the r~ident P9pu]ation density is estimated to average abput 79 people JXlf square mile in 2000. The nearest population grouping within 5 miles is situated around the center,ofthe town of Wiscasset, 3.9 miles NNE of the site, S_cattered housing marks the nature of the balanc.e of the population* in the.immediate site area.

For towns within the 5-mile radius, the resident population has shown *a 10% increase between 1990 and 2000, as* compared with a 31 % and 17% increase for the period 1970 to 19'80 and 1980 to 1990, respectively. For those towns wholly or partjally with,in a 10-mile radtus, ~e ~qent popu,Iation experienced a 4% growth between 1990 and 2000, and a 15% growth for the both periods 1970 to 1980 and 1980 to 1990.

There is a summer seasonal increase in population asspciated with ~tional activities which takes place along the Maine coast. Based upon Reference 'I, there is about a 50% increase in the population within a 5-mile radius of the site during the summer period. The total resident 2000 population within 50 miles is-estimated to be about 694,271 (88 people per square mile). This represents-about a 7% growth in population from 1990 when the 50-mile population was estimated at 649,895 as opposed to a 13% growth in population between 1990 and 1980 when the 50-J}lile cumulatj:ve population was estimated at 577,300.

Population changes for the areas in the vicinity of the site were estimated in the original FSAR through the year 2000. The fundamental basis for estimating the year 2000 statistics was the U.S. Census Forecast Il-D (Reference 2) for the whole state of Maine. This information was extrapolated beyond 1985. On the basis of the change in population between 1940 anq 1960, itwM a5;Sll1Iled that one-half the population increase in the future for the entire state would occur in the following seven counties:

Androscoggin, Cumberland, Kennebec, Knox. Lincoln, Sagadahoc and Waldo. A linear extrapolation of the 1960 and 1970 population figures was used to determine the year 2000 distributions. Within 5 miles of the site, no major increase in population is expected.

DSAR 2-2 Rev.28

MYAPC The.original FSAR 50-mil.e radius pppulatio1_1 ~mate for the year 2000 was approximately 816,000.

T}to actual population-for the year 2-0Q0 ~;12'1.,729 below the estimate in the originaJ FSAR If the rate pf1>9pul9,,ti9n '&!"~wth* 6verthe 10.:yearperlpd'fi:oq:t f9,90 to 2000 (7%) for the 50 mile radius from the site I~~

88 the basis*fo pr~Jed the,populatfon*wlthin"50 miles over the next decade, the year 2010 population would be approximately 743,000.

Th_erei~.no.historloaloasis for predictions of-in*dusma'l ~wth in the:iµ-ea. &>!)lmercial *a,ng *service. tracle.5 will Probably continue**to_ be respon~ve to*n,ee(!s.of resi<lents and touil$. ]Jle, r&?reatio~!*.9PP9TW.~

with ~p&t.to-boating,, fishing, and 191,8) f~~s. of historical interest will probably stimulate seasonal trade.

• 2.1.2 Land Use The infonnation provided in this* section is "Hi:,,torical Information".

Within 5 miles of the site, land use is largely QQme sites, small businesses, summer houses, idle farmland-and forest There is one small dairy within this *area, with severaJ other locations having a few milk cows for private use. Housing is scattered alon*g principal roads and is concentrated only'in the center-of Wiscasset The waters near the plant are reported to be relatively low in productivity of fish and shellfish. Some

'L~tenr:ig.is carried*out in Mon~g.B~ ~d ~

~ap~ Riv#, The primmy,type;oft,patin$ fo the-

,M_qnts,_w$ig Bay - Back River area is:shallow *oraf!:.pJ~ ~-* With' no *coifio:ieroiaJ:*traffic.'in the area, th_ere is no hazard to t}i_e siJ~ from potentiah!cci'dents-Wrtli COillJ'lleroial:QBTges or 9.()ats ~in'g !A_xic or explosive materials.

The Wiscasset Municipal Airport is the nearest airport to the s,ite and is located over a mile northwest of the Maine Yankee containmCI)t. It corisists ofone runway 3,400 feet long and 75 t:eet wide. The single

.runway (7-25) is ori~ntechudrthat ~e;O'ff$. and landings are on headings of 070 or 250. Approximately If P3/4 of the time, ru11way he3cling 250 is:use<f.

The airport is used almost e~qlosively'by private-aircraft sucli as thc:{PiperCel1/4 P}pef'Cherokee, <:'.:(!~Qa 150 ru\\a 172, King Air, and queen Air. This n,~,;ofljght~nrfta~unp;:.for*1ilio*ur500 takroffs,and landings,p.er-m(!nth at the*fac}lity. The. largest aircraft thattxpicajly lands-~tWi~et is PJ.e:Kmg.Afr "200:type aircraft. This l_atger type ~rcraft is estimated to account for about 5 takeoffs or landings per month.

The normal takeoff pattern is a straight climb to 700 feet followed by a 45 degree turn to the left. When the aircraft reaches an altitude of 1,000 feet, it is considered to be out of the pattern. During landing, the P.lanes*fly*a. dpwnwind* course parallerto and.tQ. the.rjglit of the runway at !ill altitude *of approximately 1,00of~t-. 'lJP9n passing the end of the runway, th~ afrc;raft would execute two 90 degree-~'riJs* to the left to bring it ~ound.to the pro~r heading for lanqiog', Tho distance between the runway and the airplane 9Jtrjn,gthe downwind leg depends*on the*~ize of~e aircraft.

There are no active plans for expansion of the Wiscasset Airport. Several navigational aid additions to the"airport have been made.. A non-direction1J,I beacon (NDB), approach was instalJed,at.the' WisCllSSet Aitj:>ort in 1977 iaod*two,Global Positioning System approaches vieN jri~led iff l 996~ Neither of these instrument flight rule (IFR) approach.capabilities is expe,cte<l:'to-~hange 'tQ(d~ffic counf. oHy~ of aircraft that frequent the airport.

DSAR 2-3 Rev.28

MYAPC The land.use wit)lin a l 0-inile radius of the Maine Y ankeo site is a1$o mainly f!!fDiland, with recreational activities talcing place on a series of peninsulas jutting into the Gulf ofMafoe. Because of its oniqµe coastal terrain and many bays, the area is a summer ~tional center for boo@g and other,wntfu: related activities. This summer recreation and its supportive businesse,s, motels, restaurants, shops,.etc., provide much of the economic base for the area.

~O~itpti1/:ey'unique*i,n_ m3Jiy respects is the marine 1/.0J1ntlll~.. 1;fie m~ iWf)I'Tii :w#U?lcy' harvests tw* specieS.J@ san~ wQtIJJJthe reveis-yirens}anil the,blood we,i;m';(O~-~rooofiigtaj~ ~

wori'n ~srontis confin~ to.mu.dflats in the:i)'ltarµd~-areas. '1'Ji~ wi:>hns.ate:silld for.bait.to j:)Onmieroial and sports fishermen along the Atlantic coast.

lndustrial activity within the 10-mile radius is somewhat limited, with ship building in the city of Bath on the Kennebec* River the largest industrial faciljty in the state.

9eotibn *2. 1

Reference:

s

1.

Evacuation Time Estimates for the Maine Yankee Plume Exposure Pathway Emergency Planning Zone, HMM Associates, Inc., April 1992

2.

US Bureau of Census, Current Population Reports, Series P-25, #326, Ulustrative Projection of Population ofSt?te, 1960-1985, US Governm~tPrjnting Offi.~ Washington, D.C., 1965.

DSAR 2-4 Rev.28

FOXBIRD ISLAND

~ONTSWEAG E SITE BOUNDARY MAINE YANKE RE 2 1-1A FIGU DSAR-Bailey Cove PROPERTY BOUNDARY DSAR

'ltSk* ;.,m

, JT

,, 'l ~*~ai*

f

-,:; 1

,S ~t. ;Nil£ f

'/

1.1J£'1>,G

~,,.,

~',.

~.. -

LEG-END:

RAlLRCMD PROPERTY ISCNJMDARY OPOGAAPH IC COMA(.~ FEET>

~OUft CHTtR~ / RlVER WA1£R WAY / S ALE lftl.1 CR_APHlC s~T r

t I T 2-5

'\\ *. \\ ~. ~"{.._71:---:_~.

\\;

.. ~ '----,

/ l. ~~',

\\,.

{

~

' "\\

_ _)

~

I

\\I

,...,~

J,:n-- y~~

,J~~

{ I J ti_,-,

-l ( ' i t :..

REV. 28,

MAINE YANKEE ISFS1 BOUNDARY DSAR FIGURE 2.1-18 Maine Yankee REti.-SlE ELECTRtC!TY FOR MAINE SlMC£ li72.

fU K.NII[,

o:s.tfl*f"IQ.1:t*ti,111.V.J.O DSAR

)

~y I,

/

I /

STf 04'04"E 42.11'

--......-- oi~~,s*oBE 11'-22'

,/

/.;.***.,,.* */*,-,,-~..

,. 7 :*'

..*,.. /

J,,.,.,

. /

1/'

-~

2-6 GIW'\\IC ~

. (fU, k~

LEGEND:

REV.28 T~N'lte COl(JOUH COKTOOR l((SNAL no ran WATER WA'I I SlRUM I MVER ISfSI IIOI.H'.WtY

MYAPC 2.2 Meteoroloq_

2.4. l G~neral The informe.tion provided in this section is "Historical Information".

The Bailey Pcijrit siteJ~ l?cited ih the mid-coastal tegion o(~fue. This co"ist~J regib!J is o_b~cterized by meny inlets, P!lys, 9bannels, harbors, rocky, islands, and*pJCimb'ntories. T,heJ3:CAA,a~iacen(tQ,th~ site has many small forested hills, Tire g~~I cliulatjc re,gime is*maritinfo with its-cool air mQVing.in froJ,n tho.No.~ A~lruttic. 'Qf~li)!

'hnportarrce; from *an en*gino¢ng,~dp_oinh.are. the ~mes *hi annwtlisnowt'afl.for the ~

ro-sio!\\;

.ti)~ opt~ional heavy rains. tne epastaJ storm-w-'!Nor'~er" wit)iJts iys~ltimt strqngwirids'.an'd heavy ram or snow; and sometimes glaze or "ice stormsu. These md otheq~rtinentmeteqi:cµogioaj _qsta w,~_clth.li'te been compiled by the TRC C0rporation of Hartford, Connecticut, are presented in the following sections.

2.2.2 On-Site Meteorological Field Programs The information provide<,! in this section is Histprical Information".

An initial data collection program was undertaken at the site of the Maine Yankee Atomic Power Station to,provide information on rnemorologicaJ conditions f9r diip-ersioo analyses f"ot'the:ori'grial FS:AR. *Data for-op~ year, fr6J!) July-1, 1967 to June 3 0, 1 ~68, were _(l:vah,latecf ~~ [cfrrded ~ir~;'f9rtl~6se,:analyses.

An upgraded on-site monitoring program which met the-intent o(Reyisi@-0 to Regu\\atgry-64,ide l,23 was installed in late 1970.

2.2*.3 Coastal Fog

. The information provided in this.section is "Historical Information".

Heavy fog is frequent and sometimes persistent along the coast, and m.ay ~,9.n one dax itJ six during certain portitins of the year. D"ata for the J *J-y¢at*period (1951-I 962)'from the*Brunswick Naval Air S~ti9n located 13 miles-fre.m.the site indiqa~e:'that 4.1% of the time (3,855 om of95,013 pb~ations),

fog conditions exist A fog condition is said to exist when the visibility is Oto 1/2 mile.

The breakdown of fog conditions for the various wind speed classifications is as follows:

0-2 mph 1.6%

3-14 mph 2.2%

15-23 mph 0.2%

24+ mph

<0.1%

Total 4.1%

DSAR 2-7 Rev.28

MYAPG 2.2.4 Temperature The informatio~ provided in this section is "Historical Information".

The temperature of the coastal region tempered by the Atlantic Ocean is not subject to the wider extremes of the inland areas. The ~verage annual teµiperature is abQ\\lt 45°F, with the frequenQy of temperature above 90°F being very small. The average January temperature is about 22°F with between IO and *20 days of sub-zero temperatures occurring yearly.

22.5 Precipitation The information provided in this section is "Historical Information".

Precipitation along the Maine coast is influenced l;>y the Atlantic Ocean. Summer thunderstorm activity is somewhat suppressed by the effects of the cool ocean, whil~ winter precipitatiop is increased J>y coastal stonns or "Nor'easters", These combined effects give this area more precipitation in the winter months than in the summer months. Monthly totals are about 4 inches during the winter as compared to 3 inches in summer. Total precipitation (Reference l) averages nearly 46 inches for the coastal !!feSS. Winter precipitation occurs mostly as rain or wet snow. Al~, this area, more than further inland, is subject to occasional glazing oJ! "ice storm" conditions.

Intense rainfall may be produced by the occasional severe thunderstonn, hurricane, or "Nor'easter. n The maximum recorded point rainfall (References 5 and 6) of short time intervals for Portland, Maine, (period, 1893-196i) is given below.

Minutes Inches Shott TimeJnteryaJ Precipitation Portland. Maine

~

Hours Inches 5

10 15 30 60 2

3 6

12_,

24.

. ~

0.51 0.78 1.09 1.49 2.11 3.40 4.51 5.84 7'.09 7.71 The,retrim period df-extreme short-interval ~infaU is a u~efW* design and planning guide. The 'nearest

,~9on for ayajlable-retum period data-which sho_uld be repres;en):atjve for the Bruley Point ~

is Portland, Maine.

2.2.5.1 Snowfall, Snow and Ice Loading The average seasonal snowfall has a marked variation along the coastal region, which may be as little as 29 inches or as much as 119 inches (References 2 and 3). Along the coast, the snow cover may entirely melt once or more in the midwinter to be replaced by new snow. The average number of days with I inch or more of snowfall for Portland is 20 per season. Snow-foad data for the Bailey Point area, from a HHFA study (Reference 7) conducted in 1952, are*as follows:

Wt of Seasonal Exceeded 1 Yr. in Wt of Max Snowpack on Wt of Estimated Max 10 Snowpack Equaled or 40 lbs tr2 Record 60 lb ff2 Accumulation on Ground Plus Wt of Max Possible Storm 80 lb ff2 DSAR 2-8 Rev.28

MYAPC Data relating to freezing rain and resultant formation of glaze ice on highways and, utility lines have been obtained from the following studies:

American Telephone and Telegraph Company, 1917-18 to 1924-25 Edison Electric Institute, 1926-27 and 1937-38 Association ofAmerican Railroads, 1928-29to 1936-37 Quartermaster Research and Engineering Command, U.S. Anny, 1959 A polar front wave with an active warm front moving in a north,or northeasterly direction toward Maine is the most typical synoptic condition for the formation of glaze or freezing.rain. A-quasi-stationary high pr~re area north of New England, with the center of the ridge or ceil usually located somti_Where northeast of Newfmmcfland, causes a flow of continental-polar air over the area from the south or east behind the -Wann front If :the over-running maritime-tropical. air or )Jlodified conti])~tal-pohu: air i~

warmer than 32°:F, while: the continental-polar air ben~th tjre front has temperatures of20°F tQ 300F, then freezing rain or drizzle,may result.

Glaz.e and ice storms of winter are usually of brief ~on, although a f(}w widespread and J!rolonged i~

storms have occurred. The following data for glaze storms (Reference a) will apply:

1.

Time of occurrence - October through April

2.

Average frequency without regard to ice thickness, 1-3 storms per year

3.

Return periods for freezing rain storms producing ice of various thiokn~s are:,

Ice 0.25 every year 0.50 every year 0.75 at least every 3 years The extrmne radial thickness of glaze on utility wires for the period 1928-29 to 1936-37 for the Bailey Point are*a w,as between 1.75 inches to 1.99 inches.

A U.S. Weather Bureau summary for the years 1939-1948 gives the actual number of days with freezing

~ipitation (without regard to ice formation) for Portland, Maine, as follows:

Total Days in 10 Nov Dec Jan Feb Mar Apr Years I

27 24 20 12 2

2.2.6 Tornadoes, Hurricanes and Severe Thunderstonns The information proYided in this section is "Historical Information".

Coastal regions are sometimes seriously affected by a variety of stonns. They generate strong winds, heavy rain or snow and, occasionally, a glaze of"ice stonn~. In winter, these storms produce some of the heavier snowfalls in the coastal area. In summer or fall, a storm of tropical origin may also affect the coastal area. Usually these are similar to the Nor'easter" but occasionally a few may attain near or full hurricane force..

Collins and Howe (Reference 9) have developed indices of relative stonn damage for different parts of the United States using storm data from the 1954-1963 decade. In the study, an "index damage potential" is de:fmed in units of 1,000ths of l percent of residential property values per year for various types of storms. The "index damage potential" which excludes tornadoes, hurricanes, tropical storms and hail for the Bailey Point area is 8, compared to a value of 16 for the Oklahoma-Kansas area.

DSAR 2-9 Rev.28

MYAPC Storms of hurricane origin do not affect Maine in most years. In 1954, two hurricanes affected Maine within a.period 9f l~tl!Wl'2:w~. The fii$t,, "Carol", traveled northward along the Maine-New

-~pshii'e *borciet*bn August 3J. Wi:Qd speeds,were no longer full hurricane force, but substantial

-pro~rty J~ildJ~r<?P, ~age resulted in western Mame. Then "Edna" entered the coastline near Eastport on Sep~~r t 1., In thw~e~--tli~ prMcipaL damage was due to heavy flooding and washing rains. Two-huiricruies in I ¥~-shpµld,~~xpectaj pr9!;,ably less than 1 year in 10. The "index of hurricane and

¥Opj08,l;$~-damag~:eofential 11 (R~fe~ce-&){i;leftned in units.of 1,000ths of I percent of resid~ntial prQpet:ty*values pe.r.¥&i-J forJIJe,Bailey Point area-is 95 as compared to 337 for the Cape Cod area, 606 fot lhc, Cape'llatte.ras/North.Qtrolina areas, ajid *633 for the Miami, Florida area.

Tornadoes are not a common phenomenon in Maine. Yet they do occur occasionally. Of the ~w, about 80% occur between May 15 and September 15. About 90°/o strike between I :00 and 7 :00 p,m. The peak month is July and the peak hour of occurrence is 2:00 to 3:00 p.m.

Fifty year totals (1916-1965) for tornadoes listed by month for the state of Maine and other New England states are as follows:-

SQ-Year Tornado Recqtd SO yr Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total Maine 0

'()

1 0

5 6

15 1'2 8

2 0

0 49

• Mass 0

• o 0

0 12 1.5 26 9

6 6

3 2

79 Vt 0

1 1

0 3

7 8

2 0

1 0

0 23

• ~

WI

0 0

0 0

6 8

14 6

2 1

0 0

37 Conn 0

0 0

0 7

2 5

8 4

2 0

0 28 A National Severe Storms Forecast Center (NSSFC) listing of tornadoes within a 125 nautical mile radius of the site indicates that 120 tornadoes *occurred during the period l 9SO*through 1993, with a mean path area of0.101 square miles (Reference 10). Thom (Reference I I) has developed a procedure for estimating:thec-probabi!Jty of a.tom~o striking ;wy point from an analysjs of mean tornado path area and

~e qeqr,iency oftomado occurrence*in the.region around the site. Applying Thom's procedure to the N$SFC data gives*$ aririual probability of about,Jxl0*

5 ofa tornado striking any*pbint within 125 rui;uticaf miles{l 44',rruJes) of'jbe site. This calculation accounts for the water area within the 125 nautical mile region.

DSAR 2-10 Rev. 28

t MYAPC Thunderstorms and hail storms occur most :frequently from mid-spring to early fall Thunderstorms occur on about 10 to 20 days a year along the coast The most severe may be attended by hail. The mean number of days that Portland experiences thunderstorms for the period 1940-1965 is as follows:

Jan Fob Mar Apr May Jun Jul Aug Sep I

Oct Nov' Dec Total

. ~

0 1

2 5

4 J

2 l

19

"'Less than onerhalf day 2.2.7 Environmental Monitoring Program' Direct gamma radiation measurements are obtained from Thermoluminescent Dosimeters (JLDs) employed to record the integrated gamma radiation-exposures TA W the requirem.ents in the Off-Site Dose Calculation Manual (ODCM).

1.

"Rainfall Intensity - Duration - Frequency Curv~", Technical ~aper No_. 25, 1955, US Weather Bureau.

2.

"Climatic Summary of the United States-Supplement for 1951-1960'1, New England, US Weather Bureau.

3.

"Climates of the States - Maine", September 1959, US Weather Bureau.

4.

"Local Climatological Data-With Comparative Data"~ 1965, Portland, Maine, US Weather Bureau.

,5, "Maximum 24-Hour Precipitation in the United States", Technical Paper No. 16, US Weather Bur.eau.

• 6.

"Maximum Recorded United States Point Rainfall for 5 Minutes to 24 Hours", Technical Paper No.

2, Revised to 1961, US Weather Bureau.

7.

"Snow Load Studies", Housing Research Pape.r No. 19, Housing and Home Finance Agency, 1952.

8.

"Glaze, Its Meteorology and Climatology, Geographical Distribution and Economic Effects",

Quartermaster Research and Engineering Center, 1959 U.S. Anny.

9.

"Weather ang Extended Coverage", George F. Collins and George M. H,owe, TRC Service Corporation, 1964.

10.

National Severe Storms Forecast Center, A Listing of Tornadoes for Period 1950-1993,@NCAA, Kansas City, MO.

11.

"Tornado Probabilities", H.C.S. Thom, Monthly Weather Review, October/November/December 1963.

DSAR 2-11 Rev.28

MYAPC 2.3 Hydrology 2.3.1 Surface Hydrology The information provided in this section is*"Historical Information'.'.

The site is located 1rt the ~ufti end of a peninsula (Bailey"Point) which is bol!nded on the* ~st by Back River and on the west by an arm ofMontsweag Bay. These two contiguous bodies of water, together with Hockomock and Knubble Bays on the squth, are a part of the Sheepscot R,iver estuariaI system.

Hoc~omock Bay~ connected to the Kennebec River on the west by the Sasanoa River. Surface drainage in the area is generally from north to south, roughly parallel to the strike of the regional.bedrock formation.

Rlllloff averages about 50% of the total rainfall on an annual basis, but this i:atio varies seasonably from a maximum of 140% in April to a minimum of 10% in August. Due. to the moderately.sloping terrain, nearly complete vegetational cover and some natural storage, runoff is not excessive and dry period flows are not unusually low..

The principal streams. in the vicinity of the site are the Sheep~t River and Montsweag Brook, which* nave the following watershed areas and approximate flows:

Drainage Area, Square Discharge, Miles cfs ( 193'8-1960}

(Head ofTi_dewater)

Maximum Average Minimum*

~ *-.

SheepscotRiver 190 6,750 307 6.4 Montsweag Brook 10.8 394 18 0.4 Runoff from the power station site is conveyed by tbe unclerground sfonn drain system or flows overland directly to Back River or to the cove west of Bailey Point.

The fresh water discharge of the* Sheepscot River and Montsweag Brook are small when compared with tidal movement of the receiving estuarial waters, and for this,reason, have no significant effect on tide levels, tidal flows, or water temperature.

The, Wiscasset town water system is the source of fresh water supply for usage at the,site.

2.3.2 Oceanographic Features The informatfon provided in this section is "Historical Information".

The Back River extends in a northerly direction from a point known as Long Ledge, which is at the northern limit of Montsweag Bay, a distance of about 4 miles, to a confluence with the Sheepscot River at the northern tip of Cushman Point. It varies in width from a maximum of 1,500 feet at Berry Island to a minimum of 500 feet at Cowseagan Narrows. Channel depths vary between 10 to over 60 feet at mean low water, with a maximum depth at the plant site of approximately 36 feet.

Montsweag Bay extends southward from Back River in the vicinity of Long Ledge a distance of about 4 miles to Phipps and Hubbard Points, where it connects with Hockomock Bay. Montsweag Bay varies in width from approximately 2,000 feet at its northern and southern limits, to about 8,000 feet midway between these points and has mean tide level area of about 1,800 acres. Except for a relatively narrow DSAR 2-12 Rev. 28

MYAPC central channel, the bay is quite shallow, with mean low water depths generally less than 2 feet.

~CCQ'i'$!ln~y *.:e~nsive intertidal,mud flats are exposed atJow fid~ andespecially*so during spring Jo:w Ji4~ Th~-!'(m~ channel VMes*m deptli from 13 to 50 feet. Montsweag Brook.enters the bay qom ;the nort:Qwest Tidal flow!! enter *and leave the Back River-Montsw~ Bay area at the Cowseagan Narrows on the north and through the passage separating Phipps and Hubbard Points to the south.

~ order to comply wjth the Augt!st 23, 1972, Department of Enviro~ental Prot~ctl_qn Order, which

>mposed a 25-acte m~:-zomr-on Maine :'(.auk~s discharge, the Cowseagan Narrows Causeway wn1ch

.e:onhccted WestportJstana to.the mainland~ removed in November 1974 aft~r a high lev,el bridge was constructed in its place. As a result of this action, natural circulation that existed prior to 1950 has been

.restofed. T-h~~et soutb;er~ *f!t;>wint0 an~ ou;tofMbntsweag ~Y thr.ough Cowseagan ~i&mW!,S*has i_~~,.~. tllweoy inducing~urrents ~

of 3 to 4 knots (5 to 7 fps). Tidaleurrenl$:at selected

${j9J1s1:a1e.P._ublis}Jeq anriiµtl!y'bytheNationaLOeean Survey (NOS) of the National Oceanl~and Atmospheric AdmiQistration (NOAA).

In addition to changes in currents, the tidal range has increased both in Montsweag Bay and Back Riv.er.

• Data coll~ since the causeway was removed show a. moan tidal range.of 9.44 feet. This. value coincides closely to the value of 9.1 feet measured in 1943 by the*U.S. Coast and Geodetjc.Burvey (now

'h,l()'S:). lvf~:loWlt'de vafues.are,now rep;orted,at,.4;S.7 ~

l>:e{pw Plewf~'leve\\; :suoli a chab,ae

~presents a 0.6 to 1-fo9tredtiction ~ mean low water. It has al~~t~.D caloµ~.iliat.as,at:es:ult Qfth~

hi creased *water level fluctuationS; apprgxirn~ly ~70: 3 9t additional acres of intertidal :flats ~* now

~~o.sed at low tide.

The.tidaJ datum for the area is 4,5 feet below mean sea level, measured at *Portland, Maine. It should be p.cijp~~ ot,itlbat.the-above differences and r~ges.~ for asfronorriical-tides.orily. A'sttonomioal tides.~

~t,tenily aff~ o.f~ological conditions *\\>/hich m~t b:e ~idcred.~. ThtNtlOlltQly ana_

~uai esti'mate¢Jn"l\\ij ani:l, m:ell!\\* ~um-"ocean watet-tem)?CT8~)Q ~~

~ed q11 t~~

published by NOS for Portland and Bar Harbor, Mafn<;.aie tabulated bcJbw-tQ:tbe..n~ }le}f ~*

Fahrenhett.

Mean Mean Month Mean MaxilJlUID Month Mean

~imlll}J January 33.5 37.0 August 59.0 62.0 February 32.5 34.5 September 57.5 61.0 March 34.5 38.0 October 52.0 56.0 April 40.0 44.0 November 45.5 49.5 May 47.0 52.0 December 38.0 42.5 June 53.5 58.0 July 58.0 62.0 Annual 46.0 The above temperatures are for coastal waters and estuaries exposed directly to the ocean. Water temperatures in confined estuaries such as Montsweag Bay and Back River average a degree or two higher DSAR 2-13 Rev. 28

MYAPC duo to the increased heating of the relatively shallow waters and more widely ex.posed beaches, and flats.

-2.3.1 Probable Maximnnl Flood 2.33, 1 Maximum Water Surface Elevation An i~vestiga.tion w~ mlijie to predic~ th~-prol:>ao!e m~mum flood ley~I which gou_Jd occur,at the:site of the Maine Y ruikee Atomic, Power Station on the Shecpsoot River estuary when, the probab_le maximum hurricane_ is 'falcen as*the design basis meteorologicafevent. The-investigation is bils~F~~ the.

pa,mneters of the probable maximum 'hurricane as.defined by U.S. Weather Bureau R~port HUR 7~97, Interim -Report -Jdeteorological Characteristics of Probable.Maximum llurricane, Atlantic and Gulf -

~-<;>fthe United States (Reference 1).

This inv,estlgation,shows that the-maximum water levels at the Maine Y,ankee site,que to theoprobaole 1JIBXimuni hurricane are preaictecJ to be at.Elevation I 9.9 feet and ~levaiion 21,4 feet on.the plant site*and pre-existing screen well structure, respectively. These levels are based upon the simultane()u&*occurrence oftbe maximum stqrm sur,ge, maximum predicted astrondmical tide, an initial rise in f!ltlaD sea l~ct esuuµia,n*1µnplification, tpe pfObable maxnpum-flood in,the Sheepscot watershed, maximum waves jn Monts"'.e~Bay,and-e~.i,stence of a ~hannel 'restriction at,the fonner Cowseagart Ntµ'ro~ Causeway.

Removf).l*ofthe causeway and replacomentwi1h-a bridge increases the degree ofcgnservation of this 9riginal work beca.u~- the causeway acted as a dam to the hurricane surgo-anc;i causeq "water.pile-up" at its f~ This 98m effect is-included in the maximum water:e}evation mentioned abov.e. As a.resuft ot:tbe:

canseway *~o~'.,the surge resulting. fto~ the probable maximum hurri~ oan now travel well *up the

~;thereby lowering the maximum water.levels at the_plant site, Thus. t}I~ maxin;\\um water levels_*

p~ented above,ru:e higher than what could occur during a probable maximum flood causea* by a probable maximum hurricane.

Tb1t maximum probable flood flow-in the Sheepscot River was detennined by 111eans of a 'l;rianguJar hydrogIJlph method _(Refet'CJ¥)e 2). TIµs*resuJts in a flow at Wiscasset of 126;500 cfs. Dµe to its.vast size, the water levets*in the.S_heepscotBay will remain essentially µnaffected by #;!is flood flow. Therefore,~.

backwater curve was calculated for the.Sheepscot.River from tb,e qpen coast tq Wis98,S8et, assµming conservafiyely that none of the flow passes through. Back River but that the water-surfatle at the plant site

• will* be the same as Wiscasset. *1rwas assumed that the highest watei levels would occur if the peak of the

,runoff' coincided with the peak of the astronomical hlgh tide and.stonn surge. Unifortt1 flow was,assumed with an n= 0.03,-and the area and hydraulic radius at Doggett Castle, as taken.from USC&GS Chart No.

314. was-us,ed as the mean river section. This resulted in-a water slope of0.035' feet per mile, which is equal to a total-increase in *water levels.ofonly 0.4 feet 2.3.'.?2 Wave Runup and Wave Forces Wav~ nmup on the slope aboye.still water level is dependent on the roughness and porosity of the materiaJ c.omposing this slope as well as period and height As given in Reference 3, a $andy slope is cbnsldered StnQ<>th wjiile a rubble-moWld structure or a riprap covered struc~ is consjdered rough. The slope for which wave nmup was determined is covered with trees and brush. Since the-trees will break up and reqrrd the waves in the same manner as rubble, the wave runup ~

determined using a slope roughness equal to the average of smooth and rough as shown in Reference 3. Wave runup from the significant waye at the Maine Yankee site was*detennined in the probable maximum hurricane to be 5.11 feet on the slope south of the pre-existing turbine building and 6.68 feet on the pre-existing circulating water pump house. The wave runup on the slope increases with greater wave period while the wave runup on the pre-existing screen well ir:icreases with shorter wave period. This condition is due to the wave nmup at the pre-existing screen well being a standing wave while the wave runup on the slope is due to a breaking wave.

DSAR 2-14 Rev.28

MYAPC The probability of any wave occurring in a spectrum of waves can be detennined using Bretsohneider's Joint Distrjbution as. found in Roference-3. Assuming that the design wave occurs during the pei:iod of2.'2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the winds in the probable maximum hurricane exceed 110 mph, approximately 1,840, waves can occw"< This period of maximum winds we define as the "critical period" of the probable maximum hurricane. Using*Bretschneider's Distribution, the distribution of waves with a 'height of 5.63, the Wfl.Ve nitiup frequency curve for the pre-existing pump house shows that approximately *10% of the waves during tp.e peri9(1 of ipaximum wiJ19S would result in a wav~ runup equal to or greater than 6 feet For reforeQce purposes,.design wave nmup for both the slope and the pre-existing pump *house is indicated in Qrapb C, Wave tun up equai to or greater than the design runup would owur during approximately 4% of the "critical -~od." Should any wave. run up occur that would overtop the slope or pre-existing p~p house, the flow rate due-to overtopping would be such that the pre-existing slte pump house could drain. It is not considered credible that these waves would be consecutive in the wave spectrum.

An investigation has been carried out to examine the characteristics of waves that could be generated across Back River from th~ east. Significant wave heights of3.6 feet or less were predicted for tonditions of a-2,000 foot fetch length, a sustained wind speed of 110 mph, and 4 different water.surface elevations ~gi;ng from --7 feet to+15 feef(MSL). The Thijsse and Schijf method (Reference 4) fonned the basis of these computations. Each of the four wave heights was examined acc.ordingfo wave-breaking criteria summarized fu Reference 4 and found to oosmaller than a bteaking wave. Consequently, none of the waves ge,nerated under :these conditions could break.

2.3.4 Groundwater Hydro,ogy The infonnation provided in this section is "Historical Information".

Groundwater in the regfon occurs as free groundwater within the clay-silt soil mantle and jpints -in the underlying bedrock. The peninsula on which the plant is located widens' and ~

in elevation toward the not$ so that the general groundwater movement in tho area is from north to south) with a gradual shift toward the east and west in the direction of the adjacent tidal waters. Gradients are expecte<l'to be roughly parallel to. the surface topography. Percolation ratos* are low due to the low penneability of the local soils and limited bedrook jointing.

Water weJJs in the area are either dug wells, usually less than,25 feet deep, or drilled' wells penetrating the bedrock for depths of 100 feet or more. Such wells are for domestic or fann use. Although adequate for the purpose, they seldmp e:i,:.oeed 5 or 10 gpm for short-term pumping and even less with sustained pumping..

Since the yield of a dug well is sensitive to groundwater levels, those in unfavorable locations can dry up during drought periods. ~

drilled wells are consistently reliable because water'table levels haye little effect on their yield. Site potable water is provided from "the town of Wiscasset water supply system.

P~ipitation at the site will percolate downward to the water tab.le and then move with the normal groundwater flows toward the adjoining salt water areas.

Section 2.3 References 1..

U.S. Department of Commerce, 1968, Interim Report - Meteorological Chara,cteristics of the Probable Maximum Hurricane, Atlantic and Gulf Coasts of the United States, Weather Bureau Memorandum HUR.7-97.

2.

U.S. Department oflnterior, 1965, Design of Small Dams, Bureau of Reclamation.

3, U.S. Army, 1966, Shore Protection, Planning and Design, Coastal Engineering Research Center, Technical Report No. 4.

DSAR 2-15 Rev. 28

MYAPC

4.

A. T. Ippen, 1966, Estuary and Coastline Hydrodynamiv5, McGraw-Hill.

2.4 *Geology The information provided in this-section is "Historical Information".

S-ite,geographical in.ffumatj'on was devel~d.fn?IJJ. _swly of t;liacavailaliJe::ltferature, s_orfac6'"rennaissance a;i'd fielf ~'d5'..,'and*examfuation ofsamples:of sofl B!1d r~k co~ takt?n fr<?in,bot_in~*0n tb~site:

Refraction seismic surv~ys were also made to determine the r_ocl; su_r:fac~ ~leyatiQJ:!S_; Ilef~ces 1, 2 and 3 contain detailed reports on these studies.

Tw~lve borings w~re made on the site in the initial studies and these have been supplemented.by 12 more 6oti.ngs.-in.the s.outh~rtr9-9rti<m~rtw.. site where.the plant was previously located. Overburden fn this area

¢'C?,tisists.ofmedinm soft."to. meohun stiff silty cl!lYS with occasional sandy lenses and pebbly sands.

Overburden varies 1 S to 20 feet in thickness. Bedrock is.of Silurian-Devonian age characterized by steeply dipping schistose rocks oftpe Cape Elizabeth fonnation, interlayered with lenticular masses of granite and coarse crystalline pegmatite.

Joints ip. the bedrQCk, as they appear in outcrops and cores, are medium spaced, ranging from. 1 ~ 5-foot intervals and less. Variation from quartzite to mica schist, to granite and pegmatite, is a common geologic feature. Though the mica schist is relatively weaker than the other ro~~. if is fresh, sound, and 'n'ot

~~alJyW,Cath~,ed: Both borings ~d g~logic,surveys,sJtow th~~~oftjgq!,fuJ, mostly in.the

~histbse (otmattons. No major faults_.h!JVe. l,leen ieyordoo in*the area.dul)hg the site stn<;IJ~ or in previous

$!fies by other geofogj~. Two minor,'f.mlt$, 'g since h,~led, fJav'e~been-recbrcled in the.outcrops ahmg tli~ shore. They are l~te'd appfdxirilat.ei>: 90.0 feet:t)ortheast of'th_~-p]?,tlt site. '11tese do no!,~h:Ow any app~ii;tble brecciation or gouge fonnation.

'fhe studies show that, geologically, the site is saitaJ?le* for an *ato!Ilic power*plant No ma.Jor or active 1aults:ha~*~ d~~*or,are-~spected in-.the :v.foinity ofth*e 0sJ.te. Hedro,ol<,,i§ soµnff, within ~b-and provides.good.founaatj_o,n* S\\ll?por:t fqr- ~e_ Sf!'uctjlres:arld equipment The maj9r..:'Struc.turos are fqlpldep

~~tly pn *bard,-crystallrne1Jx,dtock. MiQor s~

are founded either on* rook or on compacted granular fill above the rock.

The seismic surveys at the site show average values of'compression*wave velocity ofIJ,Oiio'to:i~,QOQ fps and shear wa,ve velocity of 7,000 fps. From these, vaJueS, of PoissQl)'Ji mti6 of 0,33 anq Yoiuig'-s-m'oda lus of 5 x 1 <f-P.$i were;~cuh_rte4,: From work by Eristov, 8th International Conference on Large Darns, Young's mQCfu.lus for the b,Q11CTock w.oulp ~-equal to 5,0 x-106 = 2.9, x 106 psi and the shear modulus, I.I x 106 psi.

1.7 The valu~ of Youngs modulus range from 4.94 x 106 psi to 5.67 x 106 psi. The shear modulus varies from 1.80 ~ 1,if to2_.M-x l0G psi. Variations of this amount in the moduli'have been shown to have no effect on the containment vtoration modes.

Section ZA References.

1.

"Geological Considerations, Maine Yankee Atomic Power Project," John Rand, Consulting Geologist, November 15, 1967.

2.

"Seismic Survey, Proposed Nuclear Power Plant, Bailey Point, Wiscasset, Maine," Weston DSAR 2-16 Rev. 28

MYAPC Geophysical Research, Inc., November 4, 1966.

3.

"Seismic Survey, Maine Yankee Atomic Power Project," Weston Geophysical Research, fuc., June 1967.

2.5

.Seismology.

2.5.1 Teotohics Despite rather complex interrelations between tocks of various ages and types, New England is generally characterized by competent, unweathered bedrock and stable geologic conditions. The nearest significant fault is located about 75 rrules to the west. In the geological investigation, two.small inactive faults were found about-900 feet from the historical structures.

Since Triassic time,..] 80 million years ago, no major geologic changes other than those*produced by glaciation have* oeyurr~. Tho southern part of Maine, in vicinity of the site, is composed-of three gen~

types of.PaJeozolc roc,ks. North of the area, the bedrock consists of consolidated early Paleozoic (350 million years old) sediment which has been metamorphosed through intense folding. Some middle and late Pa.leozoic (250 to 350 million years old)Jgneous intrusives are also present. During'the late Paleozoic Era (250 to 100 million years old), sedimentary material was deposited and lithified in a series.of basins extendin'g from the Narragansett Bay area of:Rhode Island through, eastern MassachuSftls int9 southwestern Maine ahnost as far north as the site area. The bedrock*of southern Maine was last affected by orogenic movements at the close of Paleozoic time by the Appalachian orogeny.

Regional Seismioi_ty Seismic activity in New England is small and typified by infrequent shallow focus earthquakes oflow inagnitu.de and intensity. Historical records or'New England earthquakes date back 300 years; more tlian 30 years of instrumental cf~ exist for the New England area. A total of 15 earthquakes which have occurred since the middle of the 18th century, with epicenters within about 150 miles of the site.

The -largest of these earthquakes *have been previously assigned a Modified Mercalli Intensity ofVm.

There were three such earthquakes, all of which OCyUroed before 1800. Historical records of earthquakes in this area, especially the older ones, must be evaluated with considerable caution. Much of colonial construction was of poor quality, and this is especially true for chimneys. Population centers tended to be clustered al9ng and at the mouths of rivers on soft, recent alluvium and, in many cases, epicenters have b~n assigned to population centers. The records are of variable quality, a few indicating careful observation, but many showing obvious exaggerations. A review indicates the intensify assigned to these earthquakes is questionable. There is evidence that all the intensities were less than Vlli, in one case probably VI, and in the two other cases, probably VI or VII. Instnnnental observations over a period of more than 30,years have indicated 4 areas in New England where concentrations of shocks have been noted. These are the Milo, Maine area, the Ossipee-Lake Winnipesaukee area of New Hampshire, the Cape Ann-Massachusetts.l3ay area, and Augusta, Maine. The closest earthquake to the plant site was a magnitude 4.J) mb earthquake that occurred on April 17, 1979, approximately four miles from the site.

The largest earthquakes to occur in New England since the installation of seismic instrumentation occurred on December 20 and 24, 1940, in the Ossipee, New Hampshire area. Both of these earthquakes were of Intensity VII with a ruchter magnitude of 5.8, which is the largest magnitude determined for any New England earthquake. Magnitude determinations for most of the larger Now England earthquakes tango between 4 and 5 on the Richter scale.

DSAR 2-17 Rev. 28

MYAPC The St. Lawrence River Valley, lying more than 200 miles north of the site, is an area of significant tectonfc activity: Earthquakes occµrring along the St. Lawrence aro feij:_ throughout New England. A number ~f lar~e.earthquakes of Intensities VIII, IX, and X have occurred in the St. ~nee River*V~ley.

Nearly aU-ofthese:~qJJak:<l$ o't-0.9rre;d:e,arty f11 c9lpni,a1 ~~ Th~ mosfrecent ofthese,occurred'o'O Feprii!lh' i~. f$>25,, and was*Intensity:I:X. ll~portir ofih~ ~quake in_~e~He a~ JnqiCilte-iliat its

,ln~ns~ w~J:vl alih9~gQ at Bi:un~~-Maine the:intemity ma)' ~-~$ld as:higti;~v. -~,.

earthquake 01;1 October 20,.1870, also of Intensity IX, reportedly':broke-afew wmi:lows* (Intensity V}al:;

• Portland, Maine.

Seismi¢Ji¥

¢'4be WIBOaSSethca Seism_icity-of the southern Maine area surrounding indic<!!es that nearby sm.all eartp.quakes include the earthquake at Bmnswfok in 1881, approximately 15 miles from the site, which had an epicentral intensity otapproximately:IV ot-V,-based Qll :histornml cJa~ *. wiUi~ P.f.Qh:able.~t,eiisltfIV-aftheplant:sitejand.th~

• ApriJ 1.7,. IP?~~ rruj'gnitµde 4:0:mb event a.bout 4 mil~ from tpe*~*wlt:fl 8:,sfte ~*.ofappu,t y, The:

earthq~~e.g_f April ~6, 1957, 1.ocated 25 mll_~ to the soutli, was.offsh*or.e, but,li~:~:~funat_ed;to,l1{lve h'ad-aii epiceritral'Jntensity of VI. All of the other eartl\\quakes which nave 1:>Cctufed wtthin a 10;.nrl}e

• f'l\\djus of ti},~ &te"we_re,of.Jntensity ill or less. The site may be expected to be subjec4:d to earthquake vibrations from relatively nearby, local quakes of small magnitude or from major earthquakes along the St.

Lawrence River Valley.

A numl:>er-ofstudies have been made relating maximum ground acceleration and.earthquake ihter,sity.

These studiel:I have largely been based on experience outside of New England. However, recent

,~mpansons-of-instruri1entally deteJ11?1ned magnitude~ and,~nteusi~ iiJ ~all,earthqoakes:in,this:repon:,

hay.ct~ we.n **tt!J -~e* re_latie~given_ by TID-7024-. A~rdingly,J1:l~e rcMilti~h~ ~J,t~ugn based,

~pramJUilt9Jl ~91l-'s1.mP9~.:5-tru,cttJ.res,.,haye f?een a~ted as reasonaQle and: ~efV$v~ f9r"~1I eartfiquakes1o'f-the=ta:ng6 of inp,Q§ifies antj,cipafe~.- J;lasei:I upon-a relatively long -histori.c,al nicor~ on ~

-~,tternia1f9i):~l: ~liquak'¢.Jiitensity with distan~*'in:the-n911h~rn United -~ta;r~ and eastern anaaa, re~qn, on-~ gegJqgy of the arefand on the character trf the component l:>edrock on which th.e*f~i!ey is

-fountle'd,'.Jm,estmurteofthe prob8,ijJ~.maximum fntemsity at the site is a Modified Mercalli In~sity V to low Intensity VL corresponding to a ground acceleration of 0.04g.

2.5.2 Tsuruµnis It is considered that_ tsun_amis would not have any measurable effect on this site. The only !$UllBfili on record on the East Coast is from the Grand Banks earthquake of November 18, 1929, for which a water level hofght 0f 1/2 inch was noted at* Atlantic <;::ity. "f:here was;Jittle'or'1'10 tsunami effectto,the Maine opast from ~earthquake, nor has there.,been a recoi:d of ~nami e~ from any othereaiihquake'.

DSAR 2-)8 Rev. 28

Section 3.1 3.2 3.3 3.4 3.5 Introduction MYAPC SECTION3.0 ISFSI T~LE OF CONTENTS Genetal Description ofFaciley 3..2.1 General 3.2.2 Principal Characteristics of Site 3.2.3 ISFSI Facility Principal Design Features 3.2.3.1 ISFSISite 3.2*.3.2 ISFSI Benn 3'.2.3,.3 ISFSI Storage Pad 3.2.3.4 Security/~ons Building General ISFSISystem Desgription 3.3.1 ISFSI Storage System-General

-'.3.3.2 ISFSI,Universal Storage System Components J.3:2.1 Transportable Storage Canister 3.3.2.2 Fl;iel Baskets 33.2.3 Vertical Concrete Cask 3.3.2.4 Deleted 3'.3.2.5 Temperature Instnnnentation 3.3.2:6 Operational Features Identification of A gents anci' Contractors

References:

LIST OFT ABLES 3.2-1 Maine Yankee Principal Environmental ISFSI Design P.arameters LIST OFFIGURES 3.2-2 ISFSI General Arrangement & Haul Route 3.2'.-3 ISFSI Site Plan 3.2-4 ISFSI Grading Plan 3.2-6

{SFSI Cask Storage Pads 3.3-1 Vertical Concrete Cask DSAR 3-1

~

3-2 3-2 3-6 3-8 3-S 3-11 Rev.29

3.1 Introdu,ction MYAPC SE'CTION3.0 ISFSI The Maine Yankee nuclear power plant wa~ a sµigle unit pressurized water reactor locawd in Wi~!lSSet, Maine. The plant began.operation in December 1972 and permanently shut down in August, 1997. The plant-last operated on December 6, 1996. By June 20, 1297, the reactor bad been completely defueled and-all 'spent fuel.resided in the spent fuel pooi. On August 6, 1997, the Maine Y ank:ee* Atqmic Power Company B6ard of Directors voted to permanently ~ase power operations-and initiate*the decommissiQI!ing process. On August 7, 1997, Maine Yankee provided, written certification to the

'Nuclear Regulatory. Commission, pursuant to 10 CFR50.82 (a)(l)(i) and (ii), that the Maine Yankee Atomic Power.Company penp.aneritlyceased operations of the Maine Yankee Atomic Power Station and thaj all n~lear fuel had been permanently temoved from the reactor (Ref. 1 ).

The isruance oftbis certification fundamentally chapged the licensing basis of.the Maine Yankee pl~t in

,that the'NR.C-issued 10 CFR 50 license no longer authorized operation of The reactor or emplacement or retentioD"offuel in the*reactot vessel. Therefore, as of August 7,.1997, only those conditions or activities f\\SS0ciatedwith the safe stoi:,age of fuel and.radiplogical protection (including waste handJing,.storage,, 11Pd disposal) wore applicable to the defueled Maine Yankee plant.

The Maine Yankee ISFSI was licensed under the "general" license approach in accordance with SlµJpart K of 10 CFR Part 72 (Ref.20). The ISFSI.general license allows a 10 CFR Part 50 power plant licensee to 11&e a ~

stora_ge system th.at is, p_i:e-approved by the NRC:, provided that,all requirements of the cask vendor's license are complied wi!fi. The cask storage' system selected for use: at Maine Yankee, is the Universal MPC*System (UMS'J, wbicb is '4:&igned and licensed by_NAC International (NAG). To use this system-under the general license approa9h, the ISESI licensee must comply with tbe requirements c_onta.ined in NAC UMS' }in'al Safety Analysis Report (FSAR) (Ref. 10) and the NRC issued Certific;ite of :Co:µ:rpliaµc~ to tqe NAC UMS' sy&tem (Ref. 2).

The Independent Sp.ent Fuel Storage Installation (lSFSI) provides safe, economic, and long-teon storage of used nuclear fuel and facilitated the decommissioning and dismantlement of the existing Maine Yankee nucleai]>dwer*plant The ISFSI provides onsite ory cask storage for the total inventory of used nuclear

(uel that was stored 'in the Maine Yankee spent fuel pool. The ISFSI also stores th~ Greater-Than-Class C

( GTCC) waste,, which consists of the irradiated reactor internals. The Licensing Basis for GTCC being stored :;,.t Maine Yankee is 10 CFR 30 (Ref29) which is reflected in Interim Staff Guidance-17, Interim Storage of Greater Than.Class C Waste (Ref 30). The design specification for the GTCC is NAC International DocwnenrN o. 790-S-l 8 (Ref 31 ). Placing the used fuel and GTCC waste in dry storage allowed the fuel building,. including the spent fuel *pool, to be decommissioned,and dismantled in the same manner as all other plant structures. The used fuel and GTCC waste will be stored safely in the spentfuel ISFSI storage system, co~sting of sealed (airtight) metal.canisters placed inside of concrete casks. The ISFSI will remaln operational until the US Department of Energy (DOE) or another licensed, entity has temporary storage or a permanent high-level waste disposal facility to accept the Maine Yankee spent fuel and GTCC waste, or until another suitable disposal facility becomes available.. Constructiop of the ISFSI facility was completed in the fall of 2001. Spent fuel and GTCC waste transfer to the ISFSI was completed in the spring of 2004.

DSAR Rev. 29

MYAPG 3.2 Ge.geral-Oe!ttiption oflSFSl,FadJJty 3.2.1 General The ISFSI is located within the site boundary, of the pre-existing Maine Y ank:ee nuclear powi;rplant in the Town of Wiscasset, Lincoln County, Maine. The site selected for the ISFSI was, an open area appro~ly 120~ft north of the pre-existing power plant in an area that was used as a vehicle parlpng lot Toe ISFSI is located within the owner-controlled area. There are no permanent occupants that reside in the owner.-controlled area. The ISFSl occupies a land area of approximately 12 acres.

3.2.2 Principal Characteristics of Site The ISFSI co1l811rts of the storage system and concrete storage pads, a Protected Area (PA) for spent fuel

,storagc:;,.an:d a Security/Operations Building for equipmenrand.staff. The PA is surrounded by a 12-ft.

high security fence and encomMSses en ~

of approximately 3 acres. Adqiti~ security is provid~ _by a,second 8-ft high 111.U8ance fence outside the security fence with a 20-ft wide isolation.zone between the two fences, The PA contains 16 concrete cask storage pads ( each being approximately 3 l-ft wide by 31-ft long) with driveway access around the pads. Each pad holds up to four spent fuel or GTCC conc;rete storage casks. A partial earthen berm is provided around the-facility to reduce the visual impact of the facilify. The ISFSI site plan is shown on Figure.3.2-3. The ISFSI site grading is shown on Figure 3,2-4.

The fapility was designed and sized to be only large e.o.ough for the exis.ting licensed spent fuel and GTCC at Maine Y~kee. Maino Yankee will not storo any spent fuel or GTCC from other generators. The storage capacity of the ISFSiutllized a total of 64 cpncrete storage cask,s, with one sealed canister per storage cask,. The types of canisters stored in the storage casks include 60 for spent fuel and four fur GTCC waste. Dama~ fuel is stored in special cans having mesh screens, in the same canisters with intact fa.el. S~n storage pads of equal size are provided for uniformity. The storage pad* details are shown on Figure 3.2~. The ISFSI site is arranged to provide maneuvering room around the storage pads for access to each cask with the heavy haul tractor-trailer. The security/operations building is approximately 10,500 square feet in area approximately (68-:ft x 154-ft) and approximately 40-ft high.

3.2,3 ISFSI Faciljty Principal D,esign Fea,tµres 3:2.3.1 ISFSI Site TheJSFSI facility principal design features include the design codes, standards, and design requirements applicable fo the site, earthen berm, cask storage pads, and the Security/Operations Building. In May of 1999 Maine Yankee submitted to the Maine Department of Environmental Protection (MDEP) a major amendment ffPJ)lication (Ref. 3) to the existing MY Site Location of Development Permit. The major amendment application W8,S to allow construction of an ISFSI for the interim storage of Maine Yankee's spent fuel and GTCC. The application, pursuant to State laws, provides detail design information relative t0 State environmental compliance in areas, such as, solid wastes generated.by the development, antlcipated air emissions and noise impact*during development, assessment of site soils for the ISFSI, ISFSI impact on groundwater and stormwater management during site development and ISFSI operation.

The ISFSI site area is above the 100-year flood plain, as shown on the "Flood Plain Map" prepared for the Maine Yankee Land Use by Robert G. Gerber, Inc. and dated February 6, 1997 (Ref. 4). The ISFSI site area is also above the Probable Maximum Flood (PMF) elevation as descn'bed in Section 2.3.3 of the DSAR, and as such, flooding is not a consideration in design of the facility.

DSAR 3-3 Rev.29

MYAPC Snow Load - A design ground snow load of 60 psfper ASCE-7 (Figure 7-1) (Ref. 5) has been considered for the site. Snow load data for the Bailey Point area is identifie*d in the site DSAR (Section 22.5,1) as 40 psf{l 0-yr storm), 60 psf (max. recorded), and 80 psf (&timated max. accumulation plus weight of max.

possible stonn).

Wind Loads - Site calculated wind loads have been determined in accordance with ASCE-7 using a basic wind speed of 105 mph (Figure 6-1 and linear interpolation), Occupancy Classification III.

Temperature Range-Temperature extremes at the Maine Yankee site are also descnoed in the DSAR (Section 2,.2.4) as-approximately -40F to + 1 OOF. The average annual temperature is approximately 45F.

Tornado Design Criteria - The design basis tornado for the vertical concrete casks (VCC's) is *based on Regulatory Guide l. 76 (Ref. 25) and N(JR.J:?.G - 0800 (Ref. 26).

Seismic Design -The.Maine Yankee ISFSJ site seismic analysis is based on a 0.18g-NUREG/GR-0098 grolllld response ~

for the plant site and on an evaluation of the effects associataj from appropriate soil amplification and soil-structure interaction (Ref. 27 & 28).

Load combinations, allowable stresses, and factors of safety, are in accordance with NUREG-1567 (Ref.

6),ANSI/ANS-57.9 (Ref. 7), ACI-349 (Ref. 8), ACI-318 (Ref.11), and/or ASCE-7, as applicable to the design element wider consideratjon.

3.2.3.i ISFSIBerm The ISFSl is provfded with l!,1l ~en berm on three sides to QJinimize the visual impact of'the facility.

The earthep berm was classified as a QA Category'Jil structure under.the qesigner's (S&W) Qµality Assurance Program (QAP) since it is not used for shielding credit in the site dose assessment. 'The seismic design of the berm conforms to BOCA NBC Section 1'610 (Ref. 9). The seismic design did not necessarily qualify that the berm remains intact after a Design Basis Earthquake (DBE). After such an event, repair of the berm could be performed in a short period of,time. However, the berm arrangcmeflt is such that a faih:ire of the berm does not have any effect on the storage casks or pads. Design and construction of the berm followed QA Category III requirements under the designer's (S&W) QAP.

3.2.3.3 ISFSI Storage Pad The cask stora~e pads are provided to support the storage casks that*contain the sealed metal spent fuel canisters. The storage technology selected for use.at Maine Yankee is the UMS' storage system designed by NAC International (NAC).

A design for a light water reactor spent fuel dry cask storage was submitted to the U.S. Nuclear Regulatory Commission (NRC) for licensing approval in th~ NAC Final Safety Analysis Report (Ref.

10).

The cask storage pads are capable of adequately supporting the storage casks/canisters under all load conditions. The cask storage pads were designed and constructed to assure the pad/soil system is "soft

enough to limit the deceleration forces encountered by the camster during the hypothetical cask tip over event. As such, the cask storage pads were classified as QA Category II under the designer's (S&W)

QAP, which provided additional quality assurance and quality control requirements during design and construction oftbe pads to ensure compliance with the NAC FSAR requirements. Pad construction documents (drawings and specifications) were marked as QA Category II undet the designer's (S&W)

QAP, with specific QA/QC requirements identified therein. Pad calculations were prepared in accordance DSAR 3-4 Rev. 29

MYAPC with QA Category I requirements. All geotecbnicaJ field investigation work, laboratory testing ofs.oil

_samples, and ge9techrucaJ calculations were classified as QA Category I to assure a conseryative*

approach to data gathering and establishment of the design base.5.

The critical attributes identified by the NRC issued Certificate of Compliance (Ref. 2) for the NAG UMS' system and associated technical specifications (e.g., concrete strength, thickness, surface roughness, subgrade soil properties, etc.) are.identified on the construction drawings a,nd specifications.,

The compressive strength for the concrete met the specified 3,000 psi at 28-days nominal requirements.

Th~ quality attn'butes descn'bed above are based upon th,e designer's (S&W) quality program d.e:finitions.

The pads were classified as ITDC/NNS in accordance with the Maine Yankee QA Program during design and construction to assure that th(l reqi,med engineering attn'bu~ were verified. The MY ISFSI QAP defines the.current classification of MY Important to Safety SSCs.

Tl;le, storage pad thickness is a, maximum of3 feet with the top Qf concrete set approximaJely*2'-6" above grade to accommodate cask transfer. The existing soil beneath the pads has been replaced with compacted struc.tural bedding material (non-frost susceptible) to a depth of 4'-6" with a tolerance of:(+6"/-

6").

NAC identified the size and wtjght of the storage system components to be used in the storage pad design in the NAC Final Safety Analysis Report (Section 3.2). The storage pad design considered the different

,load combinations associated with the progressive placement of storage casks.

The cask.storage pads were designed in accordance with ANSI/ANS 57.9 and ACI-349. Computer methods W~lJ.Sed to perform the ~tic*and ~ynamic (!?eismic) at;tal,ysis_ of the storage pads. Soil-structure interaction was considered in the computer model and follows recommendations identified in ASCE-4 (Ref.,12~.

3.2.3.4 Security/Operations Building The Security/Operations Building.is a steel framed metal sided building. The building is approximately 68 feet wide* by 154 feet long and approximately 40 feet high. The Security/Operatio~ building provides an area for security, maintenance, and operations.

The design codes and standards applicable to the design of this facility include the BOCA National Building Code, International Building Code 2009 (Ref. 32), NFPA 101 (Ref. i3) and security requirements contained in NUREG*0508 (Ref. 14).

The_ Security/Operations Building houses the ISFSJ security staff, security equipment, communications equipment, and provides site.~ccess control,a,nd issuance of dosimetry for persons entering the Protected Area. The Security/Operations Building also:provides support facilities for the ISFSI, such as offices and work space for the, operating and maintenance personnel, including a health physics area, lunch/conference rooms, restrooms, shower/locker rooms, docmnent control room, and a diesel generator for emergency power. Site Access is controlled from the Security/Operations Building with provisions for issuing security badges and dosimetry for personnel entering the ISFSI Protected Area.

DSAR 3-5 Rev.29

MYAPC

'Fire P:rotecfi93 -Fire protection is proviqeclin the _Security/Opeyations..B\\!Uding in accordance wiJ:11 the requirements of the BOCA National Bwlding Code (NBC), 'International Bmlding code 2009, and NFP A The Maine Yankee Fite Protection Program 'provides the requirements for file protection in suppqrt of the ISFSL Ernewmcy)>b:Wg - Emergency backup powei; is prqyi~d for the ISESI securi:tY sy$tem anq_ consis~ Q{

'an Uninterruptible Power Supply ~S-batteries) and a diesel generator. The diesel generatods sized to support the required 'Security loads and emergency exit lighting in the Security/Operations Building. Tb:e UPS suppoz;ts the security loads until the di~l i,tarts and comes up to speed.

3.3

,QeneraLl,SFSTSysteriTDes~npfio}!

3.3.1 ISFSI Storage System-General The ISFSI utflizes the Universal MPC System (UMSTM) developed by NAG International. The UMS' is a canister-based multi~purpose canister (MPC) system designed for both storage an<l transportation of spentJ1,ucl,ear fuel ?,nd GTCC w~te. Jb*~ ISFSI op~es under the provisions of a general licen&e utilizing the UMS' spent fuel storage/transportation system. NRC Certificate of Compliance (CoC) No. 1015 (Ref.2) has* been issued, approving use of the NAC-UMS' system for storage of spen.t nucJ~ fuel under the g;en~ lic-ense provisiqns of 10 CFR 72.210.

The qanister-has..ed spent fuel stor:age system is. a simple and passive _system which utilizes an QlJ.iey-concrete cylinder called a "storage cask to protect and shield the inner sealed metal canister. The storage cask js vented for natural convection cooling and has no moving parts.

33.2 lSFSI Universal StoFage System CompoJ:\\ents

• The Universal Storage-System QOnsists of two principal components

'f.-i:ansportable Storage Canister (including PWR fuel basket) and Vertical Concrete Cask 3.J.2.1 Transportable Storage Canistei:

The 1:ransport]ilile Storage Canister cobsists,qf a stainless steel canister that contains tp.e fuel basket structure ~d contents. The canister is defined as confinement for the spent fuel. during storage and is provided with a doubfe welded closure system. The welded closure system prevents the release of contents.in a.J.lY design basis n:ormal, off-normal or accident condition. The basket assembly in the canister provides the structural support and primary beat transfer path for the fuei assemblies while maintaining a subctitical configuration for all normal conditions of storage, off-normal events, and-hypotheti,cal accident conditions.

The major components of the Transportable Storage Canister are the shell and bottom, a bask~t assembly, shield lid, and structural lid. The canister and the shield and structural lids provide a confinement boundary during storage ancj. lifting of the TSC. The Transportable Storage Canister. is designed to the requirements of the ASME Boiler and Pressure Vessel Code (ASME Code), Section IIl, Divisfon I, Subsection NB (Ref. 21 ). It is' fabricated and assembled in accordance with the requirements of Subsection NB to the maximum extent practicable, consistent with the conditions of use.

DSAR 3-6 Rev.29

MYAPC 33.2.2 Fuel Baskets The transportable storage canister contains a fuel basket which positions and supports the stored fuel in normal,, off-normal, and accid~t conditiQns. The fuel basket is designed and fli.bricated to th~

requirements of'the ASME Code, Section ID, Division r, Subsection NG (Ref: 22). However, the basket assembly is rrot Code stamped and rro reports relative to Code stamping are prep~esl-Consequently, an.

exception is taken tq Article NG 8000, Nameplates, Stamping and Reports. The fuel basket is contained within the transportable storage canister. It is c6nstructed of stainless steel, but incorporates' alumimnn disks.for enhanced heat transfer. The fuel basket design is a right-circular cylinder configuration :with square :fuei tubes laterally supported by a series of support disks. The fuel tubes include Bo.ral sheets on all four sides for criticality control.

3.3.2.3 Vertical Concrete Cask The Vertical Concrete Cask is the storage overpack for the Transportable 'Storage Canister. The concrete*

cask provides.structural support, shielding, protection from environmental conditions, and natural convectjon cooling of the canister during long-t~rm storage. The concrete cask is.a reinforced concre~

(Type II Portland cement) structure with a structural steel inner liner. The concrete wall and steel:liner provide neutron and gamma radiationshieldjng-for the spent fuel. Inner and outer reinforcing steel (rebar) asseml:ilies are conqlined within the concrete. Toe reinforud. concrete wall provides the*structural strength to protect the canister and its *contents in natural events such as :tornado wind loading and* wind driven missiles. The ooncret~ cask is shown in the UMS FSAR.

The Verti.Gal Concrete Cask fortns an annular airpas'sage to allow ihe natural circulation of air around the c~r w rembve the decay heat from the spent fuel. The air inlets' and outlets are steel-lined penetrations that taJce nonplanar paths to the concrete cask cavity to minimize radiation streaming. The decay heat is transferred fr.om thf; fuel assemblies to the tµbes in the fuel basket and through the heat transfer disks to the canister wali. Heat flows by radiation and convection from the canister wall to the air Qirculating through the-concrete ~k annular air passage and is exhausted through the air outlet vents.

This,passive cooling system is designed to maintain the peak cladding temperature of the Zircaloy-clad fuel well below acceptable limits during long-term storage.

The top of the Vertical Concrete Cask is closed by a shield plug and 'lid. The shield plug ts approximately 5 in'. thick and inc,orporates carbon steel plate as gamma and neutron radiation shielding. A carbon steel lid that provides additiqnal gamma radiation shielding is installed above the shield plug. The shield plug.

and lid reduce skyshlne radiation and provide a cover and seal to protect the canister from the environment and:postulated tornado miggj\\es. The lrd i~ bolted in place and bas provisions for a tamper indicating seal wbi'ch was installed as a security measure during transport of the loaded VCC to the ISFSI.

3.3.2.,5 Temperature Instrumentation The V ertic1).l Concrete Cask ha:s four air outlets,ne;ai:: the top of the cask and four air inlets a( the bottom.

Each outlet is equipped with a permanent remote temperature detector mounted in the outlet air plenum tO' monitor spent fuel in storage in accordance with the NAC Certificate of Conformance (C of C) and the associated Technical Specifications. The detector is used to measure the outlet air temperature, which can be read at a junction box located on the outside surface of the concrete cask or at a remote location.

DSAR 3-7 Rev. 29

MYAPC 3.3.2.6 *Operational FC;atures Temperature monitoring of the Vertical Concrete Cask outlet air is the only active system-used for monitoring the spent fuel in storage. This tempera,ture is checked as required by the applicable Amendment,of the NAC C of C Technical Specifications.. This system does not penetrate the confinement boundaty and is not essential to the safe operation of the Universal Storage System.

The principal activities associated with the use of the Universal Storage System were loading the -canister with spent fuel, closing the-canister and loading the canister in the concrete cask. The transfer cask was.

designed to meet the,requirem~nts of these operations. Toe transfer cask held the canister during loading with fuel,_ provided for canister exterior surface flushing with non contaminated water while in the spent fuel pool, provided biological shielding during closing of th~ canister, and provided th~ means by which the loaded canister was moved to and installed in the concrete cask.

The canister*consi$ts of four priµcipal.compQnents: the canister shell (side,wall anc;l bott.o~), the shield and structural lids, the vent and.drain ports (together with the vent and drain port covers) and the basket assembfy.. A drain. tube extends from the shield lid drain port to the bottom of the canister. Toe* vent and drain ports allowed the draining, vacuum drying and backfilling with helium necessary to provide a dry, inert atmosphere for the contents. The vent '8lld drain *port covers, the shield lid, the canister shell and the joinin~ welds form the primary confinement boµndary. A s~ndary confinement bmmdary is form~d over the.shield lid by the structural lid and the weld that Joins it to the canister shell. The structural lid contains the drilled and tapped hQles for attachment ofthe,swivel hoist rings used to lift and Io~, the loaded canister. The step-by-step procedures of the Universal Storage System are presented in Chapter 8.0 of the NAC-FSAR. The auxiliary equipment needed to operate the Universal Storage System 1s desyribed in SectiOI! 3*,3.2.5. 0th~ itetns r~ed include miscellaneous hardware, connection hoses and fittings and, hand tools typically found at a reactor site.

3.4 ldenti(ieation of Agents ai:id Con,trntors Thi; prime contractm: for the, design of the ISFSI facility was Stone & Webster Engineering Corporation.

In this capacity, Stone & Webster provided the design of the ISFSI site, facility berm, cask storage pads, Security/Operations Building and associated support,systems. Th~ prime contractor for the design and licensing oftbe canister-based Universal MPC System (UMS') is NAC International Inc.

3.5

,References

.....t,

1.

Maine Yankee Letter.to NRC dated August 7, 1997, "Certification of Permanent Cessation of Power Operation and That Fuel Has Been Permanently Removed from the Reactor."

2.

NRC issued Certjficate of Compliance to NAC-UMS System, the Amendment to which the casks are registered is established in the 10 CPR 72.212 Evaluation Report.

}.

Site Location of Development Permit #L-17973 Application for Amendment, dated May 5, 1999.

4.

Maine Yankee Land Ose Report by Robert G. Gerber, dated February. 6, 1997.

5.

ASCE-7, "Minimum Design Loads for Buildings and Other Structures," 1995, Ameri'can Society of Civil Engineers.

6.

NUREG - 1567, "Standard Review Plan for Spent Fuel Dry Storage Facilities," March, 2000.

DSAR 3-8 Rev.29

MYAPC 7:,

ANSI/ANS - 57._9 - 1984, "Design Criteria for an Independent Spent Fuel Storage Installation."

~-

ACI - 349, "Code Requirements foi: Nuclear Safety-Related Concrete Structures and Commentary, 1997, American Concrete Institute.

• 9.-

BOCA National Building Code (NBC)- 19%, published by the Building Officials & Code Administrators lnternational, Inc.

10, NAC-UMS Final Safety Analysis Report, Docket No. 72-1015, the revision and other adopted changes are established in the-i O CFR 72.212 Evaluation Report.

11.

ACI - 318-.95, "Building Code Requirements for Structural Concrete."

12.

ASCE - 4, "Seismic Aiµtlysis of Safety Related Nuclear Structures and Comn;teritary on Standard for Seismic Analysis of Safety Related Nuclear Structures," 198.6, American Society of civil Engineers.

13.

NFP A -. 101, "Life Safety Code," National Fire Protection Association, 19% and 2009.

14.,

NUREG --0508, "Design Methodology for the Physical Protection Upgrade Rule Requirements

15.

16.

17.

for Fixed-Sites," June 1980.

Not Used.

Not Used.

Not Used.

Not Used.

Not Used.

20.

10 CFR 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and.

High-Level.Rad,ioactive Waste."

21.

ASME Boiler and Pressru:e Vessel Code, Division I, Section ID, S.ubsection NB, "Class I Components," 1995 Edition with 1995 Addenda

22.

ASME Boiler and Pressure Vessel Code, Division I, Section Ill, Subsection NG, "Core Support Structures, 1995 Edition with 1995 Addenda.

23.

Not Used.

24.

Not Used.

25.

USNRC Regulatory Guide 1.76, "Design Basis Tornado for Nuclear Power Plants," April 1974.

26.

USNRC, "Standard Review Plan," NUREG - 0800, Apnl 1996.

27.

USNRC Letter (NMY 87-48), Patrick M. Sears (Project Manager) to J.B. Randazza, dated March 26, 1987.

DSAR 3-9 Rev. 29

.I 1

I

• 1

MYAPC

28.

Stone & Webster Calculation No. 08196.16-SG-7, "Seismic Analysis of Cask Storage Pads -

NUREG-0098* Earthquake."

29.

10 CFR 30, Rules of General Applicability to Do_mestic Licen~ing of Byproduct Material.

30.

Spent 'Fuel Project Office, Interim Staff Guidance-17, Interim Storage of Greater Than Class C w~.

31...

NAC Intemational ~ument No. 790-S-l 8, Design. Specification for Greater Than Class C

{GTCG) Waste Transportable Storage Canisters for the Maine Yankee Project.

32.

International building Code-2009-published by the International Code Council.

DSAR 3-10 Rev.29

MYAPC

];'able 3.2.1 Malne 'Yankee Pr.indpll Envtrontt:fental

~'

JSFSJ: Dvlim 'parameters Parameter Value Tornado & Wii,d Loads Regulatory Guide 1.76 (Ref. 25) a:ndNUREG-0800*ffief. 26)

Ambient-Temperatures

-40 degrees F to 106 degrees F (133 del!fces F for Agcident-Extreme Heat)

Flood Lever**

El. 11 feet for "100 year flood" EL 19.9 feet for "maximum site watedevel due

/

to probable maximum hmricane" Design Basis Earthquake 0.26g for NAC Cask Design

. 0)81! for Cask Storaize Pad Desi1r11<Note 1)

Snow and Ice LQads 100 psf for NAC Cask 60 -psffor ISFSI Site Note (1):- 'I;Qe site grolllld resppnse (0.l 8g NUREG/CR-0098 Median Spectra) must be modified to account for local soil and soil-structure interaction concerns (Ref. 28).

DSAR 3-11 Rev.29

EATOMIC POWERCO.

DSAR MYAPC ISFSI GENERAL ARRANGEMENT AND HAUL ROUTE 3-12 MYAPC DS.AR

_._...~

~I.

~

-M'

~ -~,- ~,,.

ISFS l 0Ct£RAL JJniAHQ:)l.NT" AICJ HA1.IL AOITt

~a.!!!! Ya.. n~

',tli.

O.W-fit;.}.:Z...Z.

FIGURE 3.2-2 Rev.29

EE ATOMIC POWER CO.

DSAR MYAPC y"

j I

,//"'

J,,

ISFSI SITE PLAN 3-13 MYAPC DSAR

.,':~)

1:-

i:

,i~

'~....,_.,,.,;-

ISFSL SITE PLAN Maine Yalikee

!1.,,F I; N<4> Sf.<:~. *'STOR,.l('jf.. Of 5PtNr FOlt.

~ DSAR-FIG.3.. 2-3

_j FIGURE 3.2-3.

Rev. 29

MAINE YANKEE ATOMIC POWER CO.

DSAR MYAPC

\\.

~.

('::;.

... ~

.'lt, : '"..

~~~

~

~h'A*

--~~.

~_!~~* Jr 11

,-._.,_,~

,-,..:.i,~

~.

l.......,_ rj!!

t(

.I:(

I ISFSI GRADING PLAN 3-14

\\ r

~.

c

1\\

• al

\\-

\\

-r:-~

~

,,,.. *

~

\\

MYAPC DSAR Maine Yankee t:./;

DSAR-F JC. J.Z-4 FIGURE 3.2-4 Rev. 29

MYAPC r,---------------------- ---------------------------------------------------,

tit P l.;AN-S 'fOflt,G.lt PAD NKEEATOMIC POWER CO.

DSAR

, ii~~t~JO~fA.

"~ ({4.1'"-'f e':f.,_

~.

~

.., rlJ.;c~ (-u* 1 *

.. ~.,~,

t"~

ISFSI CASK STORAGE PADS 3-15

• • * *,t *-

• .,..* --*.l'U *"-1.c.-.*t*KJM,Jr

~~-.c Maine Yankee i #C HiO "S~

Sl ortACE: OF -~

Ji.fi(t.

FIGURE 3.2-6 Rev. 29

SHIELD PLUG CONCRETE TRANSPORTABLE STORAGE CANISTER

~,(;\\..:~

~;\\~~!:

"*~./'.:

.~,;,.$!;

¥:.*.*

• MYAPC LID STEEL LINER VERTiCAL CONCRETE CASK Maine Yankee S/>f E AND SECURE STORAGE OF Sf>ENT FUEL FILE NAME DSAR-F!C.3.3-1

~'--- ------ --------------'----------------'

MAINEY ANKEE ATOMlC POWER CO.

DSAR VERTICAL CONCRETE CASK 3-16 FIGURE 3.3-1 Rev.29

-~tion, 4:1 4.2 4.3 DSAR MYAPC SECTION4.0 RADIATION PROTECTION roiiE oF eoNr,E19TS Title

~

Railiation Protection Program 4.1. l I:Iealth Physics *-

• 4.1.2 Radioactive Materials Safety 4.12.1 Materials Safety Program 4.,12.2 Personnel ~d Procedures ALAR.A Program 42.1

• i>oficy Considerations 4.2.2 Design Considerations Radioacttve *wastc:Managemerit.

4.3.1 ISFSI Operations 4-1 4-2 4-3 4-3 Rev.28

MYAPC SECTION 4.0 RADIATION PROTECTION 4.1 RADIAJ:10N:PRQ'fECIJQNPROGRAM 4.1.1 Heahh Physics Personnel requiring unescoljed access to-n\\diologicaUy controlled areas are given training in RadiologicaJ Health and Safety. Personnel requiring escorted access to radiologically controlJed areas are given tr&ining commensurate with potential*radiological health protection problems in the radiologically controlled-a:reas*to be' frequented. Administrative ~ntrols are established to~ that procedures and requirements relating to radiation protection are followed by site personnel. These procedures include a radiation work permit system. Work orrsystems or in locations where exposure to radiation or radioactive matyriafs is expected to occur requires an appropriate radiation work permit before work can begin. The radiological haz.ards associated with the job are determined and evaluated prior to issuing the permit

• Pef:sonnelMotritbring ~em Personnel monitoring equipment is issued to and worn by personnel within radiologically controlled areas as directed by the radiatioo*work pennit in accordance wifuthe applicable procedure. Personnel monitoring equipment *is also available *on a daY-:-to-day basis for visitors not assigned to the she who have occasion to enter m,diologically controUe<;f areas. Records of complete radiation exposure history are obtained for the current year for individuals prior to allowing. those individuals to exceed 10 percent of the applicable limit in one year.

Hea1th Piwc1i fustrumentatfoo Portable radiation survey instruments are provided for use.by trained personnel. A sufficient number of instrun;ients for detecting and nieasuring radiation are available.

4.1.2 Radioactive Materials Safety 4.1.2.1 Materials Safety Program Site personnel with access to radiologically controlled areas are given training in radiological safety as direc~ by Radiation Protectfon Procedures.

Sealed Soµrces Additionally, those personnel whose job entails the handling of sealed and unsealed sources are given additional training, as,required. Procedures detail methods of leak testing sealed sources and receipt, handling control, and storage of radioactive materials.

Radioactive sealed sources shall be leak tested for contamination. Tests for leakage and/or contamination shall be performed by the licensee *or by other persons specifically authorized by the NRC or an agreement State as (ollows:

1.

Each sealed source containing radioactive materials, other than tritium, with a half-life greater than 30 days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.

DSAR 4-2 Rev. 28

MYAPC

2.

The periodic leak test required does not apply to sealed sources that are stored and are not being used. The sources exempted :(rom this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to date of use or transfer. In the absence of a certificate from a transfer indicating that a leak test bas been made within six months prior to the transfer, sealed sources shall not be put into use until tested.

3.

The leakage. test shall be capable of detecting the presence of 0.005.rriicrocurie of radioactive material on the test sample. 1f the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall immediately be withdrawn from use, decontaminated, and repaired, or disposed ofin accordance with Commission re~lations.

4, Notwith~ding the periQ<ljc leak tests require above, !UlY licensee_! se{lled source is exempt fron;i such leak test when the source contains I 00 microcuries or less of beta and/or gamma emitting material or 10 microcuries or k,ss of alpha emitting material.

4.1.2.2 Personnel and Procedures Implementation of the-radiation protection program, including source, special nuclear material, and byproduct mate-rial safety, is accomplished by-trained personnel. Th~ qualificatidns of these personnel in radioactivti m_aterials safyty st~rn from foonal ~<;l infonnal training, and from applied_ experience in the radiation protectfon field. Specific-training of other personnel in the safe handling of radioactive materials is co:vered by other training.

4.2 42.1 Policy Considerations "It is the policy of Maine Yankee to maintain radiation exposures ALARA. Maine Yankee's ALA.RA policy complies with 1 0CFR 20.

4.2.2 Design Considerations The basic objectiv.e offacility radiation shielding is to reduce external doses to site personnel.

4.3

~IOA¢:tn%_WASTE MANAGEMENT 4.3.1 ISFSI Operations With the completion of plant decommissionipg and the storage of spent fuel and GTCC at the ISFSI, there is only a small potential to generate radiological material that will have to be managed as radioactive waste until decommissioning of the ISFSL 1f it ~es necessary to process radioactiv,e waste, them aii applicable regulatory commitments will *be met using programmatic controls and licensed contractors for handling, shipping and disposal.

DSAR 4-3 Rev.28

Section 6.1 62 6.3 6.4 6.5 6.6 DSAR

Title:

MYAPC SECTION,6.0 CONDUCT Of 'OPERATIONS TABL;E OF-CQWENTS, R,espensibiliw an;d Prs~

Tec~*cal Specifitation:s -

Procedures PJ;ograms 6.5.1 Emergency*Plan 6.5.2 S,ecutity Pllm 6.5.3 Quality Assurance Program Review' and Audit 6-1 6-2 6-2 6-2 6-2 6-2 6-3 Rev.28

MYAPC SECTION 6,0

-¢0ND]Jc;r'oF OPERATIONS Maine Yankee Atomic Power-Company is r~nsible for all aspeci:!l of the JSFSI operation..

6.1

Rea1toostbilify;anll Ofgitnh.atiotf'.

The. functional organization and key lines of responsibility for the Maine Yankee ISFSI are *described in the Quality Assurance Program for Maine Yankee.

6.2

• Technical Spec{(lcatiom Maine Yankee Atomic Power S~tion is governed by the Technical Specifications which is provided with the Operating License No. DPR-36,'Docket Nq. 50-309'.

63 Training Programs are conducte,J to train ISFSI personnel. Key personnel receive classroom or guided self-study and on-the--job training. Appropriate personnel receive instruction in emergency plan and radiation protection procedures. Spec:ialized training is uti1i2;ed as n~sary. Continuing Training is used to maintain a high.ievel of proficiency in tho staff.

6A

erocednres Written procedures are requi~ to be* establi~hed, implemented and maintained per the Quality Assuran~

~~-

6.5 6.5.1 Emergency Plan The Maine Yankee ISFSI Emergency Plan js dQCk(?ted as a separate document. Changes to the Emergency Plan are evaluated under 10 CPR 50.54( q) which allows changes to be made without regulatory approval ifthe1?e changes do not decrease the effectiveness of the plan and the plan, as changed, continues to meet the standards of 10 CFR 50.47(b) and the applicable requirements of 10 CFR 50 Appendix E. A report of such changes is required to be-submitted.to the NRC within 30 days after the change is made.

6.5.2 Security Plan The Maine Yankee ISFSI PhysicaJ Security Plan is docketed as a separate document and is required by 10 CFR 50.34(c), 50.34(d), and 10 CPR 73. Changes to the Physical Security Plan are evaluated under 10 CFR 50.54 (p) which allows changes.to be made without regulatory approval if these changes do not decrease the safeguards effectiveness of the plan. A report of such changes is required to be submitted to the NRC within two months after the change is made.

6.5.3 Quality Assurance Program The Quality Assurance Program for Maine Yankee is docketed as a separate docwnent and is required by l 0 CFR 50.54(a). Changes to the Qualify Assurance Program are evaluated under 10 CFR 50.54(a) which allows changes to be made without prior NRC approval if these changes do not reduce the commitments in the program description previously accepted by the NRC. These changes must be submitted to the NRC in accordance with the requirements of 50. 71 ( e ), FSAR update requirements.

DSAR 6-2 Rev.28

MYAPC 6.6 Review and Aqdit, The Review and Audit functioqs and responsibilities are described in the Quality Assurance Program.

DSAR 6-3 Rev.28

Sectjon Title 7.1 SimlJnru:y of Actiyities DSAR MYAPC SECTION7.0 DECOMMISSIONING TABLE OF CONTEN'l'S 7-1 7-2 Rev. 28

7. I

'§l!mDUUjV ofActiyitir#

MYAPC SECTION7.Q

_DECOMMISSIONING.

Maine Yankee csed power production on December 6, 1996. By June 20, 1997, the reactor had b.een completely defueled and all spent fuel was resident in the spent fuel pool. On August 6, 1997, the Maine Yankee Atomic Power Conipany"Board of Directors-voted to-permanently cease power operations and initiate the decommissioning. process. On August 7; 1997, Maine Yankee provided written certifiC!liion to the,Nuclear Regul,atory Commission, pursuant to f 0 CFR 50.82 (aX 1 Xi) and(ii), that the Maine Yankee Atomic Pow~r Company permanently ceased oporations of the Maine Yankee Atomic Power Station and that all nuclear fuel had be'en permanently removed from the.reactor.

The decommissioning mission ofMipne Yant.ee was to i:lecpmmission the plant safely and in a cost effective manner. Prompt decommissioning satisfied both objectives. Maine Yankee intended to decontaminate and dismantle tlie,plant in a man:ner*that resulted in prompt removal of the existing nuclear plant, which was one of the approaches found acceptable to*the NRC in NUREG-0586 "Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities.~* The NRC refers to this approach as the DECON al:ternative.

Maine Yankee's intent was to complete decontamination and dismantlement-otthe majority of plant*

structures and facilities within approximately seven*years of cessation of pperations. Deoommissioning of the pfant. was completed in 2005 which was within 8 years of cessation of operations. The Decommissioning-process included the transfer 9f the-spent fuel fromJhe spent fuel pool and the Greater-Than'"Class-C waste to the on-site Independent Spent*Fuel Storage lnstallatiop (JSFSI) for.dry storage until the Department of Energy (DOE) takes posse.,ss{on or'the s:tored.maleriaJ.

As of June 30, 2005, all Final Status Survey Packages.fQr the non-lSFSI land had been completed and submitted fqr NRC for review. License tennination for the non-JSFSI land was implemented by Amendment Change No. 172 to the Facility Operating License on September 30, 2005.

The few facilities and structures required to support the spent fuel and Greater-Than-Class-C waste storage will~ decontaminated and dismantled after the Department of Energy (DOE) has taken possession of the stored material. FSS of any remaining structures and the ISFSl land will be perfonned in accordance with the Maine Yankee License Termination Plan at that time.

DSAR 7-2 Rev 28