ML20248L551

Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI

ML20248L551
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/05/1998
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20248L548	List: ML20248L546 ML20248L551
References
NUDOCS 9806110226
Download: ML20248L551 (48)

Text

_. - - - -

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS 1:1 ACTION ACTION shall be tlQ part.of a specification which prescribes remedial measures required under designated conditions; g

112 CERTINEn FUEL HANDI FR a

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CERTIFIED FUEL HANDLER, is an individual who is ~ qualified in accordance~with?

B.RP Program D25.1/ Certified Fuel Handler Iliitial Certifi3 tion Program"!

8 erwA) m %[y 1.3 CHANNEL CALIBRATION

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a A CHANNEL CALIBRATION consists ofis the'

,5 to thcies-necessary,'of the channel output such that the channel resp 5fds wiih

..jary range and accuracy to known values of the parameter #ybkh the c Itors. -AThe CHANNEL CALIBRATION shaft eaccepp$dildi$:ludests7pe the e

' el including the sensor and alarm and/or trip funcpd@[nd HANNEL FUNCTIONAL TEST. -AThe GHINNElldALIBRAT16N may be performed by any series of sequential, overl ing, orddtal ch' aid 6Iite"ps such that the entire channel is calibrated.

I 1.'4 CHANNEL CHECK $

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AMNEL g(is the gus1@alssessment of channel behavior during e

1. o'p'eisti5it b{obiervatM5hd is pcifornicd by obscrying channci icsyenac dniing es*Ed N ' son?"hel indication and/or status with othe

"$ Thcic p poss o

andVjt(

fronYIfl5 pendent instrumentation channels measuring the same g1,", "'* '%**m*

y^d j CHANNEL FIB [w@IDNAL TEST 1;5 Ta A CHANN FUNCTIONAL TEST is the injection of a simulatedfsignal into the Q

channel a.

'se to the sensor as practicable to verify OPERABILITY, including i

1

' rip functions.

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1;6 NTAINMENT CLOSURE CONTAINMENT CLOSURE is that condition of containment in which there are no direct paths from containment atmosphere to the outside atmosphereEexcept foithe containment ventilation inlet and exhaust lvalyes, which may be.'opb6'if at leastlone sxhaust fan'islin operation ~.. I'er containnicnt piping pcnctrations, CONTAINMENT ELOSURE is dcfincd to cxist when onc valvc is ciescd, er a check valvc picventing 9006110226 9906os 1-1 June 5. 1998 PDR ADOCK 05000155 W

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DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS entneid 00v, of unids fivin coniainnisiii is in IIic linc. - Leak tightness is not required for CONTAINMENT CLOSURE to exist.

}/%j-1.7 DIRECT PATHS A DIRECT PATH is a visually observable oPenin8>P hich iermitfthe free exchan8e l._ _.e of air between containment and the environs. Eguipment configiustidnis or an engineered eitcinelivc5 feature such as a cicsedialve, che,c TraldeMie7s.eal.iclosed m

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door or.s'ecurely fastened plate.may be used to:preclud treet paths.Wedundancy;of engineered features to' eliminate. direct paths is'no't' req %

itired TV TMW w_

l' 8 FUFif HANDI ING gg kES3fIA FUEL HANDLING'means the activities _ associated'with movin(spent micleatifuel; including ' moving ~the 24 ton transfer coffin (also known asihe transfer' cask) when it contains spent fuel.iWhen spent nuclearTel is contained inTelosed and sealed

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permanent storage' cask'or associated transfer device, the activities associated,with moving the' cask or device when it is outside the Spent Fuel Pool Area are notLto be considered FUEL HANDLING.

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1.9 IMMEDIATFI Y l

Wisen "IMMEDIATELY".is used as a completion time for a required l ACTION, the ACTION lshould be pursued without delay.and in a controlled manner.

l 12 June 5, 1998 1

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DIG ROCK POINT

-l PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS (continued) 1 10 MONITORING STATION The MO.NITORING STATION;is.the facility which has monitoring,ialarmirigTdata archiving'and limited l6ontroll capabilities's forLselected s'yste'm parameters during'the deconsnissioning' process 3The Control Room'shall. remain thi MONITORING l

STATION iintil'such tinie:as~a'new facility is activated to'herEthis'fEnctiod::

1:.11 OFF-SITE DOSE CALCULATION MANUAI-M)

.1 ef The' OFF-SITE DOSE CALCULATION MA

(

M) conta meth. :lology and parameters used in the calc ffsite doses res rom l

radioactive gaseous and liquid effluents, in the f gaseous and liquid effluent monitoring alarm and trip setpoints, et of the Envowmusumi i

Radiological Environmental. Monitoring Pro m.

hall also contain (1) j the Radioactive Effluent Controls and alEn Monitoring programs required by Sectioni 6.6;2.5' and (2 ptions of the information that should be includ olo Environmental Operating and Annual Radioact fflue s required by Specifications l

6.7.2 and 6,7,3.

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1,12 DPER ABI.E - OPERAP 1

A em, subsy m, com vice shall be OPERABLE or have I

ILI capab rming its specified safety-function (s)-

'nd~wheri all necessary attendant ins

, co

' al power sources, cooling or seal water, lubrication or o equi is are' required for the system, subsystem, train, l

co to its safety function (s) are also capable of performing lated tion (s).

I 1,13 PROCESS CO PROGRAM (PCP)

The PROC ONTROL PROGRAM contains the methods and determinations which en t the processing and packaging of wet solid radioactive wastes will be j

i.

in such a way as to assure compliance with 10 CFR Parts 20, 61 and I

regulations, burial ground requirements, and other requirements governing isposal of solid radioactive waste.

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.1.14 REPORTABI F EVENT A REPORTABLE EVENT is any of those conditions 'specified as reportable ini 10Cr"'0.72 end 10CTR'0.7% Specification 6.9.,

j 1-3 June 5, 1998 c

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS (continued)

1.15 -

SHIFT A-SHIFT shall be the duration of the normal worifperiod,Lwhich will be~either 8 or 12_ hours'in length as determined by the Site.Gbneral Manager For purpjses' of determining _the maximuni allowable thne between s6rveillance{s, 'w s'uNEillance interval is'"once per SHIFT,"ithelmaximsm' allowable Etension not to~

sx'cced 25 percent of thelspecified surveillance'inte3al dbscribMn' surveillance requirement,4.0.2 shall be based upon the SHIFT ~d'uration~ap roved by the Site General Manager at that'timej j

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=E nOUNnAnY The SITE COUNDARY is thet ;inc t~yeM - '

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1-4 June 5. 1998

BIG ROCK POINT PERMANENTLY.DEFUELED TECHNICAL SPECIFICATIONS 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS There are no safety limits or limiting safety system settings applicable to the permanently j

defueled condition.

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BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION

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ComplianceLwith the Limiting Conditions for Operation andp h 3.0.1 cquircn,cnt3 3h&ll bc applicebic during the 3pccificd applicsbic condj[y for cQQgetion.

contained in the succeeding spe'cifications is reguired during the conditions'~specified8 therein;iexcept that u'pon failure to meet the Limiting' Conditions for

~ 'ation, thef l

associated ' ACTION requirements shall be ~ met R

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'i 3.0.2 Noncompliance with a specification shall exist when thei Adhcicnce to the requirements of the Limiting Condition for OpefiN6dMa'nd' associated ' ACTION requirements are not met:within the specified time irlthbli conai,idic conipliencc Mih ihc 3gcificetion. IfIn G., ant the Limiting ~Cbndition for Operation is restored prior to expiratio[dW cified tNrw litt$rvals, completion of the ACTION statement r6quirementiis#'of n

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3.0.3 Unless otherwise specified, e. into ap[applicabilityJcondition shall n unless the conditions of theIa5Eociated bimiting C8ndition for Operation are met without reliance on provifi,dEIcontalfdd in the,55 tion statements.

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SURVEILLANCE REQUIRE $1ENTS 4.0.1 ifie hSury Requirements shall be applicable during the spi icable 25Eilitidiitfor the associated Limiting Conditions for Operation.

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, k' lRequirernent shall be performed within the specified in@ val withEiditrimiun allowable extension not to exceed 25 percent of the specified surveillance in Y 4.0. % Unless specifi #otherwise, performance of a Surveillance Requirement within the if specified ti nterval including the maximum allowable. extension shall constitute

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complia.

ith OPERABILITY requirements for a Limiting Condition for Operation ted Action statements.

M=3 4.0.4 nless specified otherwise, entry into a specified applicable condition shall not be made unless the Surveillance Requirements associated with the Limiting Condition for Operation have been performed within the stated surveillance interval including'the

m. aximum~ allow' ble extension.

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l-3/4-1 June 5. 1998

BIG ROCK POINi PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS I

LIMITING CONDITIONS FOR OPERATION h% /f,,

3.1.1 The following parameters shall be monitored and maintained yvithin[the limits

$[V indicated:

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The water level in the Spent Fuel Pl>ol shall be m[amtaIns}d2 bo a.

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elevation of 630the syphon brcaksi(00' 42).'

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Spent Fuel Pool water temperature shall be ma,intained greater than 40 F

$ynnnM and less than150140 F.

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Water chemistry in the Spent Fuel Pool shall be maintained within the following:

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/ID h pH 5.0 to 9.0 Conductivity less. N/

ThbV than or equal to 10.0 micrombos per em at 77' degrees F Radiationlev,f

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els in the grea of the Spent Fuel Pool shall be normally monitodikItwo'a fEedlii adiation monitors, each with a locally a

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audible $larn(sei at not less than 5 millirems per hour and

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and remotely 'hmillirems per hour, except during~ the moveinen k%Nyot ni

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kg 'ifuel or radioactive components'in or adjacent to the Spent Fuel P@l,;when; W '

settinIIdif& raised above 20 mrem /hr provided the overall 4

sv g #jfd*/. ~ f.sgn, criterion;ih 10CFR70.24(a)(2) is satisfied. At f

p is required to be OPERABLE. The monitors shall have remote indication and t cagability.of recording data.

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IIeWdci, netvilih5Linding thc icquircnicnts of 10CFR70.24(a)(2),;alarni sci [$gs inay bc raised above 20 niscni/hr providcd the escrali dctcction d![crien in 10CFR70.24(a)(2) is satisficd.

6 bWI APPLICABILITY:

When irrediated spe~nt fuel assemblies arc storud is in the Spent Fuel Pool.

wxp ACTION-i.

With the requirements of 3.1.1.a not met, immediately IMMEDIATELY suspend activities having potential to drain the Spent Fuel Pool. Place fuel assemblies and the crane load in a safe condition, and then suspend further movement of fuel assemblies and crane operations with loads in or over the Spent Fuel Pool,'and initiate action to restore Spent Fuel Pool water level. Within 24

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3/4-2 June 5. 1998

r _ _ _.-_-- _ - _ ___ __ _ ___--_-__ _ - - - - - _ - - -

$IG ROCK POINT I

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS I

L 3/4.1 FUEL STORAGE l

3/4.1.1 SPENT FUEL POOL PARAMETERS ACTION (Continued)

,/

hours establish CONTAINMENT CLOSUR$

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With the requirements of 3.1.1 met,*gTELY; place fuel assemblies'and the^ crane load in a safe condition, ssspend [

further movement of fuel assemblies snd cisne; operations'with^ loads in orlover the Spest Fuel Pool,2and initiate actios to restoreF '

acceptable' temperature.; and%WM24 hours establis J

L

. CONTAINMENT CLOSUREWA _

iiii If the watefqualityTspecifications:of 3.1~.1.c are'exceededTinitiate correctiv6 mea ~sures to meet chemistry requirements;within 24; hours andlsampicipool water at least once a day until readisgs~ meet _the

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fequiremsntiof 3.1.1.c. ; If water quality cain6t befrecovered after j

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oneLweek,LprepaEa?special report tiiatjdentifies'_the casses;and J

proposed ~ corrective ~ action (s) to ensure future water quality i~s in

. complianc' 'a~nd'submiTto:the NEC by 31[ days following entrylinto e

the'LCO.

7 sv.

requir

.1.d not met, IMMEDIATELY provide te me onitoring Spent Fuel Pool radiation levels.

te instrumentation does not have an audible alarm, locall and

. MONITORING. STATION [it-radiation' isvels'shall be co onitored by personnel'in~communicatiorBivith~the ONITO NG STATION, when personnel are in the vicinity of the uel' Pool.

j rovisions of Specification 3.0.3 are not applicable.

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SU LLANCE RE.

EMENTS 4.

Twicerence per-4 l hours SHIFf, the water level in the Spent Fuel all be determined to be cquel to or gmetci then its niin:,nsni rcquired

.above the elevation of thc syphen bicAcr (630' 4") 630','

4.1.1.b-Approxinietcly Twice once per 4 i, hours SIIIFT, Spent Fuel Pool water temperature

- shall be determined to meet the requirements of Specification 3.1.1.b.

Once'pe~ :31 daps; Spent Fuel Pool water lcheinistry shall be 4;1;17d Ayy.exinietelym r

determined toimeet theiequirements'of Specification 3.1.1;6 3/4-3 June 5. 1998

BIG ROCK POINT' PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS ACTION (Continued) 4.1.1.d The Spent Fuel Pool ra<liation monitor required by this speciferion be demonstrated operable:

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Daily by performing a CHANNEL pCK.

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Once per 31 days by performing a C5 FANN. CALIBRA

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f l-3/4 4 June 5, 1998 L _ _ _ _ -_ _

DIG ROCK: POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEI STORAGE 4

3/4.1.2 SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 3.1.2 The capability to supply makeup to the Spent Fuel Pool shall littmaine as follows:

m a.

A diesel generator capable of provi ower w Jto operat an on site electric motor-driven pu

} shall be available-SR' One off-site source of ac power ca roviding power ate an j

on site electric motor-driven pump ilable,.QE, -

An on site pump not requiring el a

capable of providing makeup water to Fuel P 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I b.

The pump designated t

. ent Specification 3.1.2.a shall be capable of s lying water within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a temperature equal r less n 100 Spent Fuel Pool cnicigcrey niokcep ;;rs, apabilg;to man initiate at least 28 gpm flow to the Spent Fu etO s n; ;i-m Fnc; I' col cnwigersy niekenp g

llrs cnicis.

opent F" vel maintained.

APPLICAREE Wh

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pent 15 stoird in the Spent Fuel Pool.

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ACTION:

th the ]

of this specifications 3.132.a"or 3.L2.b not met,-

24 h ish an alternate source of water capable of delivering

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gpm ater at a temperature equal to or less than 100 F to 1 Pool.

t The provisions ification 3.0.3 are not applicable.

i

.S LANCE IREMENTS 4.1.

Daily, verify the presence of potential on the offsite power line.

li 14enth yOncelper,31Tdays, manually start the diesel generator [and run

)

loaded for 30 minutes using an electric motor-driven pump as a load.

4 4.1.2.b i

Once per 12 months, verify that the pumps satisfying the requirements of this specification are capable of supplying water 20 ihc cnwiscncy niek m p line within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and will deliver at least 28 gpm of water; L

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3/4-5' June 5. 1998

BIG ROCK POINT i

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS f

3/4.1 FUEL STORAGE 3/4.1.2 SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS SURVEILLANCE REQUIREMENTS Once per 12 months, the Spent Fuel Pool mumpuoi,makeu/~W s

ii p line shall be determined to be OPERABLE by verifying its flod;ddpafify to be at least 28 gpm.

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l 3/4-6 June 5, 1998 1

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 3.1.3 The following limitations shall apply to the storage of spent f pent Fuel bSA a:

Spent fuel l assemblies'shall befstored i fuel storage racks locat6d.in the /

Sperii Fuel Pool!

/ T b.

The storage of materials in the are between rack B east wall of the Spent Fuel Pool is prohi 3

6.

Only spent fuel with a decay time f great year will be stored in the outer three rows of the fu djacent,

1 ' h wall of the fuel pool.

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APPLICABILITY:

When hredia:cd spent elass s m.ei, i

~

is in the Spent Fuel Pool.

f ACTION:

With the requi ts of specific ons 3;1'.3:ac 3.~1.3.b,7or 3.L3.'c not met, suspe operattedSpent Fuel Pool work activities.other thariiequired surveillance activitiesTnd perform a prompt investigation to f[propriate corrective actions.

dete cause a SURVEILLAN

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4.1.3 a;

At least semi-annually and 'within.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of completion of any involving' movement of. spent fuel in.the Spent Fuel. Pool,'

"ehthat the requirements of Specification 3:1;3.a'haveLbeen met.!

b.

' At leastl semi-antiuallyfand within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of upon completion of any activity involving movement of components in the Spent Fuel Pool, verify that the requirements of Specification 3.1.3.b have been met.

l-c.

At least quarterly and withinl4. houri ~ f upon completion of any fuel o

handling activity which involves movement of fuel into the fuel rack adjacent to the south wall of the Spent Fuel Pool, verify that the storage configuration satisfies the requirements of Specification 3.1.3.6. Performance of this surveillance is not required after L.gcem r 15 August'29,1998.

3/4-7 June 5. 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDLING 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS LIMITING CONDITIONS FOR OPERATION The following? conditions apply En~ handling fuel inside containment.49 P

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For containment penetrations or opehp,gs,3,0pTAINMENT CLOSURE a-shall exist sad lcohtainmsnt Ventilation valves shall beidperable.

Nsh!b bi Radiation levels ~shall be maintained belowlthe alarm settinglequirements of sp6cification'3l1;1.d.

de con M~ h APPLICABILITY:

When handling fuel ACTION:

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With the

,tre:neg> f this-spification 3.2.11not met, place fuel as les in ' fe conditedn, and suspend fuel handling activi mside inme

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ill pith the r6quirements_of specification 3.2.1% not met, initiat6 closure of c6htainment V6ntilation inlet hnd 6xhaust Vnives~End

. initIEe corrective' actions to reducs the 'rsdiation'leveli.tofacceptable

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a:

Prior to"coniinencement of fuel. handling'activitie's, 'performfverificatiod of a

7)NTAINMENT CLOSURE;for~alll containment penetrations;or' openings

. c -

andVerify_OPERABILITYiof containment ventilation _ valves:(CV-4094, b

C.. V4.095f.CV-4096,;CV-409.7);

3 bl yerify;that thelradiatiohLlevels?on the Spent Fuel Pool ar6ayadiation monitor hre less?thah the alarm %tting requirements of spe6ification

~

3 _1;1 d at. least twice~per SHIFT, l

3/4-8 June 5. 1998

[ DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDI.ING 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS LIMITING CONDITIONS FOR OPERATION f

hu ~

3.2.2 -

Fuel handling operations shall conform to the following requ a.

Movement of spent fuel into and ou stora ction stations shall be restricted to one a.

bly at ajtime.

b.

Radiation levels at the Spent Fuel sock tank area maintaimd at less than 50 mrem /hr.

Ntg c2 Fuel handling shall be accomplished by manual guidance land visual observation of all_ fuel hand ons.]

d.

Water shall.be used as the basic shieldingp[when transferring ~~ spent fuel'from the Spent FulPool'usin7g hT24 ton fuel transfer cask'.

~

4 f

$$F APPLICABILITY:

When handli 8 in t pent F fool.

ACTION:

i.

requir cification 3.2.2.a not met, shspend fuel

__ mg operations lace irradiated fuel assemblies in a safe 1

y onduct a prompt investigation to determine the cause bF1 A a

priate corrective actions.

I Aw.

"h the irements of Specification 3.2.2.b not met, suspend fuel i

operations and conduct a prompt investigation to determine

'Te of increased radiation levels. Fuel handling may resume if etermined that increased radiation levels have not been caused.

,e by the handling of fuel in the Spent Fuel Pool and radiation levels

)

are; verified ~to beLwithin expected range.

.iiil With the requirements of Specification 3.2.2.c not' met," suspend fuel L

.l '

requirements;of 3.2.2.Vhave been re-established handling opdrations.Wuel handling may resume)nce the L

l

'ivj With the requirementsfof, Specification 3.2.2.d not; met / suspend fuel handling loperationsE Fuel handling may resume lonce the requirements of 3;2.2.d..have been.re-~ established!

L 3/4-9 June 5. 1998 I

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 14.2 FUEL HANDLING 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS LIMITING CONDITIONS FOR OPERATION A

if MDd,'

SURVEILLANCE REQUIREMENTS 4

\\$

/$%ws&

l 4.2.2 a.

None?

/

N DMh /

A h

Prior 16 commencing and'onc hs.t/

handling operations and upon,h,_'pe,r SNfirs SHIFT b.

M, - ~on of fuel hhndhng

3. m.

monitor the radiation levels inMSpedit: Fuel Pool sock tank area to verify that the requirements a[5p'ehr 2.2.b are met.

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3/4-10 June 5, 1998

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3

' CONTROL OF HEAVY LOADS LIMITING CONDITIONS FOR OPERATION 3.3.1 Handling of heavy loads over or in the Spent Fuel Pool shall conform to the following requirements:

4 Use of the reactor building gantry crane,ver thef ]fiIst Pool for load a.

exceeding 24 tons is prohibited.

%$; fg With the exception of the properly rigged:fuelan(ww. Q[ Mothe f

g h dli N

b.

fe specifically approved by NRC for Ose in or.ofdr the SpedtN $dlif s

Ly%,

w-5, iM i.

No cask shall be moved over 3 stored in the Spent Fuel

pggi,

" peg f

li.

Cask handling operationsp be limi io

southwest corner of t

the Spent Fuel Pool [

j

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iii.

No fuel shall he'it red in hhe* racks adjacent to the cask handling areai6 the souEwest corgprfor the Spent Fuel Pool during cask handgoperathkEs.

J kW Ah ti.7 The trip mechanism ~of the fuel transfer cask' safety catch device shall'be operable rior to handligof the cask over or in the Spent Fuel Pool!

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APPLICABILITYUhh spentN$Y.

in the Spent Fuel Pool, tdhsxd@h ACTION:g Wiiiii tinhuirements of-this specifications 3.3.1.as 3.3.1.b, 3.3.1.c, or 3.3171! $i)riet, IMIviEDIATELY place the crane load in a safe condition,

/

and fiNjkiiIl further load handling activities with the reactor building gantr'y' crane. Load handling shall not resume until permission has been

,/

ined from the Site General Manager.

SU

~~

REQUIREMENTS None 4.3.1 in Prior to moving'a 1.oad'ovei(the SFP, verify that the load does not exceed 24 tons.:

3/4-11 June 5. 1998

DIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS SURVEILLANCE REQUIREMENTS b;

Prio~r to moving a cask over the SFP, verify that the' cask is the' properlp

~

r'igged fuel transfer cask, or anotheFcask specifically~ap~p' oved by NRC for

~

r use.in"orTover the Spent Fuel Pool.

7 A

/&stGt&

d.

Prior to handling bf the fuel transfe'r cask ov'er or in thegnt Fuel Pool,'

the. trip mechanism of the; cask.safet catch device'shall be functio'nallp

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{j}g' tested; S

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l 3/4-12 June 5. 1998

(

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.4 SEALED SOURCE CONTAMINATION LIMITING CONDITIONS FOR OPERATION 3.4.1 Each sealed source containing more than 100 microcuries of beta and/or gamma emitting material, or more than 10l5lmicrocuries of alpha emitting materihl shall not have removable contamination which equals or: exceeds 0.005 inier "s.

j APPLICABILITY:

At all times.

ACTION:

1.

Each F.:aled source with removable contamination iEencess e

above limits shall be IMME61$iFMY withdrawn froEdEand I

either decontaminated and re;Eir$1{Yf ' posed ofin accordance with NRC regulations.

a.

A special report shank submit RC as indicated by Specification 6:7M?

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SURVEILLANCE REQUIREMENTS [

[

ka j

Except for: 1) sealed sop &

4.4.1 which e stored.

not in use, and 2) start up sources and fission detector pdously shted o fore neutron flux, sealed sources containing radioa veMterials iE 7 ther than gas and with a half-life greater gf04ays (gg')'censee or other person specifically authorized shall d for contamination and/ofleakage at least month-NR reeme.

. rform srch services. The test method shall have a

{

~

detect,,

' of h5 microcuries per test sample. The test' sample shall be taken from the sealed s'ource ~or from the surfaces'of the device.in which the

}

' Ti~ed source isfermanently inounted orl stored, on which o'ne) night expect

/, 6ontaniination.to[$rhulatel Records;o microcuries'and maintained for inspection by the'NRC.

I sources requiring testing by this section, but exempted on the basis a.

[{

- y hot being in use, shall have been tested within 6 months prior to being 4

transferred or put into use.

t, l

3/4-13 June 5. 1998

I BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 LOCATION AND BOUNDARIES The plant site, consisting of approximately 600 acres, is locsted in a evoix County, Michigan, about 4 miles northeast of Cgrievoixgggs'n, and about 11 miles west of Petoskey, Michigan. The nearest landside prop _erty,line'is about 2680 feet' and the nearest shoreline propert containment sphere (Reference Figure 5.1-1)i" y line is~about 200 feet p,F W*kiih Q

y kt 5.2 STORAGE AND INSPECTION OF SI'ECIAM- - m,x mm,12,ximo SPENT FUEL 5.2.1 CRITICALITY idl!ifl00

[$$h TF storagei$hks which are designed and shall Spent fuel is stored in hsp[ent.

assemblies to ensure a k y ess than or e,chtddistisichftween s be maintained with sufficient er-to-l e

with unborated water.

7 M

The fuel loading r

centi ofan errbly placed in the Spent Fuel Pool shall be le

1. or equal tkdii@dmum c 8.3 grams of U or 235 lent.

M DV tion st

' mstalled, shall be designed and maintained with

.fh$nce between fuel assemblies placed in the su r-to-ce i

_ to ensure a k,y less than or equal to 0.95 when flooded with rated

• M k

~

gf Nf 5.2 WATER EL Q

AN

^. ut Fuel Pool is designed to mairtain a normal water level of 630' 6" and vent unintentional draining below the syphon breaker which is at cicvation v20' 4" approximately 2" below the normal water le~ vel:

5.2.3 COOLING The configuration of storage racks placed in the Spent Fuel Pool allows for adequate circulation of water to prevent localized pool boiling end cxcesstve thcin>&lly-inuumou,vous in um em, um., vu muum.mm ou ueture.

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5-1 June 5. 1998

i BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES (Figure 5.1-1)

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5-2 June 5. 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES 5.2.4 CAPACITY Subject to the limits listed below, the fuel pool is designed for and shall be maintained with a storage capacity of no more than 441 fuel assemblie6 In se addition, fuel pins which have been removed from fuel assemblies mayshall be f-u stored i; ' the Spent Fuel Pool and shall be in a geometry tp3which ensures m..

e. __ AN subcrit.wah.ty., in v uusu uim s. on ou ouwuomf--~i vi ryy.m.. uus uvs cunteining fuci in the stoicd spcnt fuci essensis. The foll6 wing"'11isits apply to, [

the amount of special nuclear material whichm.:4~ay be stoted'#ah ' in %

^'s thel:S' '2 N Ar'Fu,el h:

% pent

%. m o n #G~

-y Pool:

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2500 kilograms of contained uran,6ntained in: fission ccenters ium 235

.~A 10.32 rams of uranium 235 as.,6 8

150 kilograms of plutonium dinitained'in PsO UO fuel cods.

5 curies of plutonium encapsulated as a hlutdh)iu$i-bery 2

2 e~

.A ym/;ye source.

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'3L 5.3 REACTOR

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5.3.1 STATUS e"

3r The reactor is nofliceEsed for p@6hirzoper6 tion. Fuel s d5$)or vessel %:[

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T@M sw 5-3 June 5, 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECKNICAL SPECIFICATIONS i

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY AND AUTHORITY 6.1 1 SENIOR NUCLEAR OFFICER

^

Ik The Senior Nuclear. Officer ~shall be the Senior Vice President-Nuclear, Fossil, and Hydro Operations ano shall'be responsible for the'overall' operation; maintenance and decommissioning of Consume'rs EnergfTuTiear power plants.

(f' ghk??k ff 6.1.12 SITE GENERAL MANAGER

/

maintenance'and decommissioning and foh(riodshf absence sh The Site General Manager shall be responNbl fofoverall facility oMatidE, writing the succession to this responsibilitygUnlEddherwise specified, the Site General Manager's delegate has authbilty to'peiforkall actions and grant approvals assigned by these specificationrto the Site'Generai' Manager. The Site General Manager may delegateTpecifiilasks to obrpiIividuals who may perform those tasks whether thej$it8G$iidril$danager,iPabsent or present at the site.

8 M$ > YW ff ff k b f 6.1.3 SHIFT SUPERVISOR &f 8

1y

^^

fg ff The Shift Stipervisor shall be respo,nsible_for the shift command function. LThis position.will be filled by a CeEified Fuel Handler.

%.gdd(" NIZATI NC,h

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6.2 MM@A Nijk$P 6.2.1 REP.ORTING: RELATIONSHIPS g(j0' Myz#$,

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On-site organizationind corporate reporting relationship shall be established p((

for activitieNdf{edting safety of the facility.

s C

a.

es of authority, responsibility and communication shall be

'g The Site General Manager shall be responsible for safe operation of o

the facility and shall have control over those on-site activities necessary for safe operation and maintenance of the facility. The individual filling this position shall report directly to the Senior Nuclear Officer.

The individuals who perform audits, surveillance and independent c.

safety reviews report to the Manager, Nuclear Performance 6-1 June 5. 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS Assessment Department.

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e DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) 1 6.2.2 FACILITY ORGANIZATION The facility organization shall be subject to the following:

h a.

Each on-duty shift shall be comprised of at least the minim shiftcrew 1

P la composition shown in Table 6.2-1.

f/

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b; A!! fuci handling opcrations shall bc direct!7 rvised h;,

uci IIandler.vhc shall have no other concurrenw

---DSe adniinistrativc procedurcs. At least one indW s se:[in the 3 e

~

qua.lified as'a N_on-Certified Operator, shall Firtfie MONITORING STATION whenfirradiated fuel is in the Spent Fuel Pool.7%iyQ

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Y A qualined PM'n: ion Pro:cc: ion Tcchd ' h..,. tut tM. Dng fuci' andhng c.

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a uuwuv u.w mmva ma ao oms wu a ouw, y uu. m usu au mumuvu protectionproccdurcs sha!!Ac prescat en sitcMIi nidividualfqualified in radiation protection prochd$res shallTe onsite when fuel is in the Spent Fu.el

~

Pool.;A; qualified.RadiEIEiProtecYon Technician shall _be on site:during fuel handling operations]

n (5mfC d.

. S. pAdm,inistra ures shall be emented to limit the working hours of the

-r staff safety reisted function 3 activities associa.ted.with the ma e storagefcon_ trol, and maintenance of spent fuel. These individuals include thTeiilnTsisiina shift c~iWiiiijited by Table 6.2-1, key maintenance personnel t

gltadijinos$hotectiIk f ^'q$A ' technicians.'

[//

Adequate shsit c$r) in the event that unforeseen problems requ overage shall be maintained without routine heavy use of overtime. FNM

,M substantial,diilounts of overtime to be used, the following guidelines shall be wed:

n

[

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />

),

y straight,)xcluding shift turnover time:

(2)

An individua' should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 1

The overtime restrictions of this section apply only to periods when spent fuel is stored in the Spent Fuel Pool, or when spent fuel handling or radioactive waste handling activities are conducted.

6-3 June 5, 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day periodi all excluding shift turnover time.

(3)

A break, including shift turnover time, of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed aller continuous work periods of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> ddration/[

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gf 4

Any deviation from the above guidelines shallk"authorifed liy th'e Site General Manager or de_signated alternates inaccordancNith establihedIshi)inistrative procedures and withdocumentation of the ba$iI for grantibithE08diatidn2 u u mh ra Administrative procedures shallinclude a re uiremenIfor the Site GeneraJp, l

r u

w-Manager'or designated alternates.to revied

,idtial overtime on a m6nthly v

basis in order to verify that excessive hours h6eli6fbeen assigned. Routine deviations from the above guidelines i

,atg VE TABLE 6.2-1: MINIMUM SHIFT CREWCOMPOSITION DURING PERMANENTL DEFUEITED CONDITION

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STAFFING POSITION Af f"

REQUIRED Shift Super isorcrmmtrol O ~Mf..turuv 1

pg unon-h. censed)&c,dr R>e a

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s

?1NiIlary Or,$$$7Nhn-Certified Operator 1

Ido$iiIEnsed) N77%

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1. pwgve m v

e. YAll fuel handimg operations (defined as movement ofirradiated fuel assembifeiBliill be directly supervised by a Certified Fuel Ilandler who~shM1 have no other concurrent responsibilities during this i

9g operation.' Uertified Fuel Handlers shall meet qualifications set forth 44 m the Cedified Fuel HandlerTraining Program.

Q d Q y

t hTl ift Supervisor'shall be h Certified Fuel Handler.

Qhny[$

l g;

The Shift Supervisor _shall rep, ort to an individual who is a-Certified Fuel Handler.

h.

Personnel requirements of(a) and (c) above may be less than the minimum specified for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to j

accommodate unexpected absence ofon-duty personnel provided immediate' j

i 64 June 5, 1998 E_

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIF% CATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) action is taken to restore the minimum requirements'specified.

~ Ihis provi.sion on_ly. applies to on: shift personnel and does no_t permit any. shift crew position to be unmanned upon shift change due to oncoming shift crew member being late or absent.

$7 e

fd STAFF QUALIFICATIONS My su L member of the facility management and supervisory staff 11 meet ihggg

~ EW:

minimum requirements of ANSI N18.1-1971 for c4 arable' positions. Thep' p lmeet the individual responsible for radiation protection fun minimum requirements of Regulatory Guide 1.8, S 1975.'

bbk (L4 TRAINING

pg e9Ryx 49

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. a..m ys v5 ous ava utu nowun,y stos ouau puuinsmg" 1 197QA training prog am f vu gwus mw ausguuumsma ouu rcconiuicndenens of Sccdon 5.5 o#

fANSI Nji. -

~

r or the facility's Certified Fuel Handlers shall meetihe require 5ents and recommendations of Shiion 53of'ANSIN1851MI_T 'g# ~

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6.5 -

REVIEW AND AUD

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6.5.1 a -efor on-site reviews and audits are described in CPC-2A, Qualit'y Progr$h Descripkj[%

4 MMA NNY l

6.6 PROCEDURESAND PROGRAMS

(

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6.6.1 PROCEDURES DiJ i

6.6.

Scope f

a itten procedsfes shall be established, implemented and maintained for safety related ThIems components and safety actions defined in the Big Rock Point Decommissioning Quality List:and thosel structures [systemsfcomponents and activities

'important to the' safe ~ storage, c_ontrol and inaintenan'cefor the spent fuel. These 1

As applied to this specification, " equivalent", as used in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) formal training in science engineering, or (b) operational or technical experience and training in nuclear power.

l

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6-5 June 5. 1998 I

L lL-_-__-___

BIG ROCK POINT l

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) procedures shall meet or exceed the requirements of ANSI N18.7-1976, as endorsed by the Quality Program Description (CPC-2A).

6.6.1.1~ (cont.)

p dA 47 Written procedures shall alsoLbeLestablished,'iniplementedlland ' maintained covering the following a'ctivitie's!

g{>

%{f:!

a.

Site' security plah; h

^

y bi Site: emergency plan; and,

[i dhaw c."

All progra'ms listed in Specification 6.6.2.Q 6.6.1.2 Review and Anproval y.

Requirements for review and approval of procedure,s (and rp;thereto) required by this section are described in CPC-2A,4salifflPr gram Deschn.

o

/^T$Q4

<f 6.6.1.3 Temporary Changes f)'

M Requirements for making temp 6irary changes to proyures which fall within the secpe

~ PC-2 (Quality groi; ram Description.

of this section are describe a

6.6.2 PROGRAMS

/M MhE sk Mb Thei]gprog&$]W rak be, established, implemented and maintained is accordance with' written procedures meeting the requir'ements;cohtained'in specification 6~.6^.1 :

'%I

'47 7

6.6.2.1 adiation<PMn Program

%gi ocedures for pershllff radiation protection shall be prepared consistent with the requirements of 10'CFR Part 20 and shall be approved, maintained and adhered to for

1. 11 operations iny $ing personnel radiation exposure.

6.

bT7 Radiation Area 6.6.2.

Dose Rates less than 1000 Millirem per Hour In lieu of the " control device" or " alarm signal" required by Paragraph 20.1601(a) of l

10 CFR Part 20, each high radiation area in which the intensity of radiation is less than

[

1000 mrem /hr at 30 cm (12 inches) from the radiation source or from any surface f

which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by the use of a Radi:

• ion Work 6-6 June 5. 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued)

Permit (RWP). Radiation protection qualified personnel or personnel continuously escorted by radiation protection qualified personnel may be exempt from working i

under an RWP during the performance of their assigned radiation protection duties in high radiation a eas with exposure rates ofless than 1000 mrem /hr, provided they are otherwise following facility radiation protection procedures for enfry radiation areas. Any individual or group of individualgpermitted 16~ enter such areas shall be provided with or accompanied by one or more of the f0110windf(

fp;k:)

abh L ei-Q f.

na a.

A radiation monitoring device which continuously indicates the<, radiation dose h

% << Y rate in the area, or QhY

%Y A radiation monitoring device which conti Inoubhhtegrates the radiation dose b.

rate in the area and alarms when a preset inthgrated dose is received. Entry into such areas with this monitoring devicEmayYeMaddssfter the dose rate levels in the area have been established =and personnlllhhvellisen made knowledgeable of them, or b 'h Y[

h*

Wh f

Protection Technician) withI radiatidlIdose}rateimonitoring device,A c.

responsible for providingfsitive,cEntrol ove[the activities within the area.

Mr df ll 6.6.2.2.2 Dose Rates squal to or greaterdhan 1000 jfillirem per Hour In additioin to the reg,gs%

[O $h A

uirements of 6.64 2jRiircas accessible to personnel with radiitionlE@els greateEdiaE1000 mrem /hr at 30 cm (12 inches) but less than 500 rad /hr*$tMdrsfromilAlrMNElon source or from any surface which the radiation penetratel? shill @providelliwittbd$ked doors to prevent unauthorized entry, and the keys shallNmsintaSed und$$N!Ininistrative controls specified in the facility adminfNEativeNohAdur$ib Doors shall remain locked except during periods of access

~

gYersonnel unde'r ved RWP. The dose rate levels in the immediate work jarcas and the maxim [an a um; allowable stay time for individuals in that area shall be

[Nhuch as closed ci[luit TV cameras) continucus surveillance m communicated to tlEindividuals. In lieu of a stay time specification, direct or remote

. } qualified in radhfion protection procedures to provide positive exposure control over 4tdactivitiM$ing performed within the area.

$b [

~Por ihdividual high radiation areas accessible to personnel with radiation levels of equal to.or greate than 1000 mrem /hr that are located within large areas where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6-7 June 5, 1998

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) 6.6.2.3 Process Control Progam (PCP) 6.6.2.3.1 Changes v the PCP 1

l Changes to the PCP shall become effective after approval by the Site Ge 1

j Manager.

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)>

8$h.

6.6.2.3.2 Reports

.f QQjg f

sionjfhe RadioaE$kM' l

Changes to the PCP shall be submitted to the Co Release Report for the period in which the chang' anade effective. ilS57 submittal shall contain sufficiently detailed inform port the rationale for each change and a determination that the change ithe overall conformance of the solidified waste product to e ting c solid wastes, y

Ik ;

j 6.6.2.4 Offsite Dose Calculation Manual f

-A 6.6.2.4.1 Changes to the ODCM Changes to the ODCM shall le effegdte after royal by the Site General Manager.

J-g j

i 6.6.2.4.2 rts Ch O

ubmitted to the Commission in the Radioactive Efflue feport in which the changes were made effective. This

~

submittal

'n su tailed information to support the rationale for each chgl$$$'Minat at the change did not reduce the accuracy or reli ty of do's or setpoint determinations.

W 6.6.2 Radioactive _

t Controls Program program, con ing with 10 CFR 50.36a, for the control of radioactive effluents for main ng doses from radioactive effluents to MEMBERS OF THE PUBLIC ably achievable. The program (1) shall be contained in the ODCM, implemented by facility procedures, and (3) shall include remedial actions ken whenever program limits are exceeded. The program shall include the following elements:

a. -

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 6-8 June 5, 1998

IgIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) b.

Limitations conforming to 10 CFR Part 20, Appendix B, Table II, Column 2 on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS; c.

Monitoring, sampling and analysis of radioactive liquid and gaseou fluents in accordance with 10 CFR 20.106 and with the methodolo lasdjirameters in the ODCM; TRt M

1. 5 Limitations conforming to Appendix I to 1%CFR Parg50 on the; k'

WE t?k d.

quarterly doses or dose commitment to a MEMBER'OF THE PUBLIC from/

radioactive materials in liquid effluents reMf$In the facility toDY UNRESTRICTED AREAS; Yh k$Ekh Determination of cumulative and projected (dose contritat, ions from radioactive e.

effluents for the current calendar quarterand curren'tMD; year in accordance with the methodolo aid " rs in thEODdM at least every 31 days-

%M5h

%$hh f.

Limitations on the operab and usf f thep4 d gaseous effluent treatment systems to ensure that th$ appropriate portions of these systems are used to reduce releas$[radiokvity whefIhe projected doses in a 31-day period would exceedfpercent6f the guidNines for the annual dose or dose commitment co$foNing to Akendiit 10 CFR Part 50.

g@/IJiniations c47s %dM k

<to the doses associated with 10 CFR Part 50 on the g.

' MYatS resultik frMioactive material released in gaseous effluents to ark 65/ind the SItifBOUNDARY; Skhhk Y h.

imitations conformmg to Appendix I to 10 CFR Part 50 on the annual and quarterly a}idosesNsulting from noble gases released in gaseous effluents from the fadilitjjdareas beyond the SITE BOUNDARY; and

~

Limitatica$ onforming to 40 CFR Part 190 on the annual dose or dose i.

commitddnt to any MEMBER OF THE PUBLIC due to releases of tivity and to radiation from uranium fuel cycle sources.

6.6.2.

Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the facility. The program shall provide (1) representative measurements of

(

radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways The program shall (1) be contained in the ODCM, (2) conform to the 6-9 June 5. 1998

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6._0 ADMINISTRATIVE CONTROLS (continued) guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

a.

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parametersiin the ODCM;

/g fjf Mik A Land Use Census to ensure that changes iq;t$use A

b.

SITE BOUNDARY are identified and that tuodifications td?thimositoring g#

program are made if required by the results[f tnis c that critical receptors are assumed to exist at tiielSITE BOUNDAR[NMfsiti location of highest dose consequence; and g

ME9 Participation in a Interlaboratory Compariso$i?%

nW to, ensure that c.

independent checks on the precision and $25urac[ofi hsfiilcasurements of t

radioactive materials in environmental sample matri$es$thMiformed as part of the quality assurance program for,eiNironnsnral moniIdingI g?f'"%Q W 6.6.2.7 Fire Protection Program I

E%

A fire protection program meptag the requirements,10 CFR 50.48(f) shall be established,' inipleinented, Wangmiintaine' f gh d

~/$#

Cold Weather Protection ~Pronranh@@At 6.6.2'8

)$k d[$$$

neb This!ptogrgrovides administrative controls to ensure thaf Appropriate mea'sures~ are r

implemented and maintained duringicokl weather to l rotect"the facility against cold i

^

tempei Atures which could impact the' safe ^storige of irradiated fuel or result in nnolanned'or unmonitored radio'Tetive material release; 64(.29 Mbh Soent Fuel Eqol Water Chemistry Program hY is program uses roc'edures tol provide. controls.for monitoring' Spent Fuel Pool iter lchemis. ' "

~

J 6.7

' RTING REQUIREMENTS i

The reports identified in this section shall be submitted in accordance with 10 CFR 50.4.

6-10 June 5. 1998 E---_--.------_--------

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) 6.7.1 ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT An annual report of radiation exposures received during the previous calendar year shall be submitted prior to March 1 of each year. This report shall tabulate.the numbers of facility, utility and other personnel (including contracks) reciNing exposures greater than 100 millirem during the year, along witidhiiihak$ciated dose according to work and job functions, for example, opdhons aQiggghnce, routine maintenance, special maintenance (identify), and wss,td'processjap.%TheM2ise, assignments to various duty functions may be estimated basedpn pocddamsneter, TLD or film badge measurements. Small exposufS totaling less than 2'djaEent i

e individual total dose need not be accounted for lEftIE~ag the total whole body dose received from external s'6urdes'[regate, a id be assigned to specific major work functions.

[i 3,~

u 6.7.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPE T210 REPORT

{

42 %

NV An annual radiological environmental operatmgy% port sovertyoperati facility during the previous calendarfdar shall be year. The report shall include suuN1 aries, id$;rpret$tions$nd statistica the results of the RadiologicalJhE!ronmedIl Monitddng Program for the reporting period. The material proviM31[all bejhiisistent yh the objectives outlined in the ODCM and Sections IV.B V.B.3 dd!IV.C ohppendix I to 10 CFR 50.

A Ak hh!k NDRADIOA.,un

. EFFLUEtITTjjRELEASE REPORT 6.7.3 AN wm

~~

An an tive e

. se report covering operation of the facility during shall inclede$ssaphrinary,of t equantities of radioactive liquid a the previo year i

and Midliasts$ledoodirem the facility. The material provi: led shall be consistent wNIthe objectiveMMSEin the ODCM and the PROCESS CONTROL PROGRAM, b.J[ Appendix I to 10 CFR Part 50.

d shall comply w)dfgrequirements of 10 CFR 50.36a and Section IV.B.1 of 6.

W

,L

)ECIA TS 4

Ing special report shall be submitted to the NRC as indicated.

a.

Prior 10 rchinery 1, subniit e myert if Icakagc in cxcc55 ef the liniits of Spccificetien 3.4.1 w&5 dciccicd freni eny scalcd sonicc icsicd during thc picviens celcnder ycer. If thisealed' source l contamination limits of specification'3.'.'4;1'are exceeded, a special report'shall be submitted tof the NRC within 30 ' days of identification'of the existence of theiexcessive ' contamination:

The report shall describe the equipment involved, the test results and corrective l

l 6-11 June 5. 1998

BIG ROCK POINT

/

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS I

6.0 ADMINISTRATIVE CONTROLS (continued) actions taken.

6.8 RECORDS px Record retention requirements are described in CPC-2A, Quality l Progra Whh*

x p )p

% %.% y,y N A

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"l". gn 43

6.9 REPORTABLE EVENTS NY '$?:?$h y

A reportable event is' any event or condition that must be reported to' the NRC in '

accordance.with 10CFR50.72,10CFR50.73, or 10CFR50.9(b)?

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.k ih 6-12 June 5, 1998

BASSS FOR LIMITING CONDITIONS FOR ATIdN$$$4 AND SURVEILLANCE REQ TS TMTW%<..

W Qf 5fi BIG ROCsp a y

PERMANENTLY DEFUEIED TEC SPECIFICATIONS gr 3r

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ThIkidbained in this section suntmarize the acconlan[or Nie Specifications in Section 3/4, but inrea ce w Te Ical Specifications.

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June 5, 1998

. R T(2 W o r'TC D o T M'T' PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.0 APPLICABILITY BASES 3.0.1 This specification defines specifically when the other specifications in Section 3/4 are applicable.

j i

3.0.2 This specification defines those conditions which must ben rder to comply with the terms of a Limiting Condit{oif[$f Ope

[

its associated

(((

Action requirement.

y' khWb ad applicability /boddition"i/

3.0.3 This specification provides that entry into:a'speci may be made only when (a) the full com[ldise~htkf required systeisN3V equipment and components are OPERABI'E'and;(b}d) net w all other parameters as specified in the Limiting Conditions for Or$$atiorfn allowable deviations and out of service [Fovisioiis% in the Action statements.

The intent of this provision is to: ensure dat activitiesire not initiated with required equipment inoperabidor otheFs'pe6ifiadliiiiirs being exceeded.

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4.0.1 This specification e shes unless_o rwise specified, sur.cillances must be performed *ddring the;specifiedIIplicable conditions for which the

. requirementsffth$ limiting (CohdjinnEfor Operation apply. The purpose of fhids

""gpecifi85ilbEifio ensure 05tIsdrveillances are performed to verify the

' nal slituiN)Esafe operation of the facility when the pla stems and components and that parameters are within limitsY$l$$su

~

_, Applicabilithd60$ition. The specification also establishes that s

VEBLLANCE REQUIREMENTS do not need to be performed when the (Ng facilityIMifaYoYidition for which the requirements of the associated Limiting Conditions * 'Ojidiation do not apply.

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June 5, 1998 B3/4-1 L_-__--_.

BIG ROCK. POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.0 APPLICABII.ITY BASES (continued) 4.0.2 This specification establishes how long the specified time interval for a SURVEILLANCE REQUIREMENT may be extended. The inten

. providing this allowance is to facilitate surveillance schedO4ng

^ count for -

conditions that may not be suitable for conducting the s,. _..

e. It is not surveillance intervals beyond those specifiM[ilita co~

extend the intended that this provision be used repeatedl

^

The allowable extension provided by S ation 4:0.2 is base engineering judgement and the recognitioNildlitli$most probable any I

particular surveillance is conformance witk%SUR EILLANCE REQUIREMENT. These provisions arepiffibNdk re that the reliability demonstrated through surveillance activifiEs is n%

ly degraded as a result of an extended interval.

g

' criteriffor determining 4.0.3 The provisions of this specifi n se compliance with the OPElgILIT

[

dimiting Conditions for ment, syisEns or components are sociated}:s, surveillance activities have bee Operation. Under these @fteria, assumed to be OPER if th :

satisfactorily perfo ( Iithi

, specifidiime interval, including the maximum" allowable extensi othi this provision is to be construed as efining ite RABLE

, e known to be inoperable even if they h their [ ~. ll,SURV.

E REQUIREMENTS.

9 4.0.4 ificati at the surveillance activities associated with a L

itio I

tion have been performed within the specified i

including the maximum allowable extension prior to entry into

{

specifi y conditions. The intent of this provision is to ensure that je surveillanceactidNes have been satisfactorily demonstrated on a current basis

)

as require $I;Eet the OPERABILITY requirements of the Limiting I

Conditio

't Operation.

4.

Unle -

specification states otherwise, applicable surveillance activities must ormed within the stated surveillance interval prior to placing the ociated item in an OPERABLE status.

i l

l June 5, 1998 B3/4-2

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE l

3/4.1.1 SPENT FUEL POOL PARAMETERS BASES Spent Fuel Pool water level is normally maintained at eleMong?

f 3.1.1.a 6". This I

is the elevation of the discharge overflow weir; which is at elevation 630' 6" per; (refsencc drawing 0740G40153). The nEimum level required by this specification is.4":below norisal water? lev [5 Maintaining water level above

~

i theininimum level ensures'that 22'fof water is'niaintamed' abo.ve the actigp fuel contamed in the stoired fuel assernblieTin the sp7e it fuel'pooWich is the assumption'used in theTanaly~ sis of heavyLload dro event'iri'section 15.10.2.2 of the.UFHSRO V

E Emergency cooling of the pool water is omp!,

geed and bleed" method that adds cooler inventory tg "

level d by this I

I and r hotter inventory at the discharge weir..

specification will ensure that nitia w.

r in the pool is consistent with the Spent F ' Pool m

hich concludes that feed and bleed is a viable coo meth r the uel Pool. This level allows operational 11 ty by wing interruption of Spent Fuel Pool

.E,

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"r'"r:7! 2:.-r"' 1 "we"W l'm" "r"r_"1"In"l..

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, statement is specification requires bror.cdi.tc IMMEDIATE tiviti at can result in draining the pool to minimize the loss f inve w-for IMMEDIATE initiation ~of the restoration of the hiel' assemblies and crane loads must be placed in a safe water lev jg'and further fuel movement suspended until lev configurat' ;

This acti ill minimize the probability of a fuel handling event before the water 1 is restored. However, containment closure is required within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inimee a release if an' event were to occur and the water level is not le to support the thermal analysis or the radiological mitigating effects l

rubbing or shielding.

4.1.1.a Since'installatiori of thsstainlessisteel liner'rio liquid attributable to'le~akage of tiie; Spent Fuel Pool his'been? observed 3 Based on empirical data, the rate of water loss from normal evaporation in the Spent Fuel Pool is not expected to

. exceed 0.1 gallons per minute - (corresponding to less than a half inch loss in l

water level per' day). As a result, the specified frequency for monitoring f-Spent Fuel Pool water level provides for early detection of decreasing water June 5, 1998' B3/4-3 i

1L ___:_ x -___ --

BIG ROCK POINT PERMANENTLY-DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUFI STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS BASES level and provides assurance that water level will not droho a lditel significantly less than the specified level during' ie int-M'$en readings.

The level specified may be verified by nier. L icC~" 4&;ir,n in the Centro! "eeni, or by visual inspection of[$ hit F I

~$el or level in';trumentation itself.

3 s

.3.1.1.b The maximuniallowable Spent Fuel Poo res is bised upon are-dcfim.d by the structural analysis of the co end the cinicelity de:ciniine; ion for the sgni n.cl in the

.perforrned foFlthe Spest Fdel

' P6ol.iiapacitj expansion'and is bused lon thel concrete properties ssed in the knalysisEAbove1150.*F' concrete?strdngth' properties _may begin'to be'reducef Structurst integrity.is maintained for temperatures up to 150'FftSpecifying

~

~

140'F asthe~ upper' temperature liinit prov, ides assurance that"the'poolfemains i

atja; temperature below~ the temperature at whiciIco' ncrete strengthpr6perties may begin to be reduced. [ B[

. $$ N AS As dochmented'in'the UFHSR, a loss of S ent Fuel Pool Cooling event and its 2

potentiil~t6iresialt in a'pproachjor'excsEling;ths Spent Fuel Pool;;w' ter

~

a

' '~~ ature uppjeimit has been evaluatedJAt the time ~bf permhnent plant

)

owni an analyj was performed to"detsrinineithe Spent;Fdel Pool.heatup

)

_ bhssd upon the_ogfating hist 6r9'of eicif Essembly;iri the~p661 eon Wmbef 20',t1997, the last fuel ssembly wss~ removed'from the Yeactor

~

vessel and placed in tpipent Fuel PoolC Ths.16 shits of the heat-up" analysis show~ that the fuel had deca' ed sufficiently by Dscember SF1997tto allow y

pool lco81ing,topmoved forl72 hours without temperaturefexceeding 150 F

' (from an initial temperatureiof 80'F).

NY f

The criti y analysis performed for the Spent Fuel Pool expansion determi that K (neutron multiplication factor) is less than 0.95 at the most reac emperature, which is greater than the minimum specified temperature l

F.

The c'riticility parametric" stud conducted'6verlthe tbniperaturs efof 40*F to 212?F concl6d6d thaf;40*F isithe Isait rehetiveLeondition and 212*F is the mostl reactive conditi6n.1 This The specified'ininimsm temperature ensures that freezing of the Sgni Fsci I'esi: Spent Fuel Pool will not occur.

Bised upon the UFHSR7 achieving the' minimum Spent Fuel Pool 1temperatur6

~

of40*F (or below)_ isTcon'sidersd unlik61yJInitiators oflo^w temperature

~

conditions.would incidde loss?of offsite power, boilsIr problems lor v6ntilstion June.5, 1998 B3/4-4 i

L-__-_-_.___-

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

.3/4.1 FUFI. STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS

. BASES AW systemLfstilures?.Such'a pool temperature w0cid not?only require a sustained lossiof both offsite?and;6nsite AC power during'extremel cold weathet

~

t conditions;but.would presume'that decay hea roductlim,fEiEthe spent fuel

~

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is" negligible l t

ihc inex.ni-m e;;eweh c imui i mysioiniggbg3sjsi the }gra,. _

.[

%m.. -..-,,... u m - -,,. s u us,e-cxist; if the Sget Fue: " eel is-mamtained po m ou os.m..

__ny boscoflce;then ei 150 F.

The ACTION requirements'of this,gtion lea ation of acceptabl,e temperatures in the

. The r of temperature restoration is not specified; ppo 1

by Specification 3.1.2 provide assurance pent F, l' tcan be restored.

' wice per shift (encc gi-4.1.1.b

. Spent Fuel Pool w inper is veri t

yy us..4cly 41-

.) in or arly detection of abnormal Spent i nel Pool e ise rective action can be promptly taken.

3.1.Ec :

1 Maintaining Spent i Pool water chemistry asfspecifi4s6sufeiths Speht

' IFuel P6ol water is suitable for long term. storage.of spent fuel.iThe specifications"pr6vided are consistent.with the'practicesLatifacilitie~s?that

~

^grovide long term storage of fuel.TThe' conductivity limitation'will~maihtain chlorides at less than 3 parts per million.'

~

Nk The~A6ti6h_requirementsiof thisEspecification lead to'restorati6n~of acdEptable water chemistrv coUditions:

C 1.li The SURVFJILANCE REQUIREMENTS of this' specification provide "that the: chemistry criteria;are being'niet!

3.1.

Maintaining the at lestionelof the two; Spent Fuel Pool area radiation monitor 5 operable as specified in this section permits meeting the criticality accident i

monitoring requirements of 10 CFR 70.24(a)(2). The fixed gamma radiation

}

monitors provides an indication of Spent Fuel Poc! criticality and elevated

(.

radiation levels that may be indicative of a release. Raising alarm settings beyond 20 mrem /hr may be necessary during the in6vement of speht fuel or p

activmes wh;ch involv; ;;fi;eg irradhited radioactiRcomponents eut of i;m r-June;5, 1998 B3/4-5 l

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS I

3/4.1 FUEL STORAGE l

(

3/4.1.1 SPENT FUEL POOL PARAMETERS 1

BASES

~

gY peel or neer !is serfecc.in.or adjacent to the Spent Fuel Pool. When the option to raise the alarm setpoint is exercised, Ale revis,ei.lNaniI/s'etpoint must a

continue to meet the criticality detection critenasf 10 CFRt70.24(a)(2).

If AkN b?W jf The ACTION requirements associated;wigthis specification willyrovi_de thef equivale^nt monito"ing capability at a level required by 10CFR70.24(a)(2). V r

~

hhk 4.1.1.ed The SURVEILLANCE REQUIREMENTS A1 Jcd to provide confidence 1

in instrument performance. Acccpiebic reded $lkforniing & CIIANNEL

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EIIECli include conipering the indicetedThenn2ihQMr cxisting plant j

ceeditiere, er ceinpering dienusi[en-- S.%thet of a P)"/

"redieiles M/

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.A auau uu.sm.

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[,$eiadc the cqnr e'.cn' 2 Nk Thc ACTION e550cieted -(a# 055 5i

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auvautuoug, sayavauty as a w vsa uses p appa ur%vy avwa au v.

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June 5, 1998 B3/4-6 e________--___

l l

OIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

3/4.1 FUEL STORAGE 3/4.1.2 Spent Fuel Pool EMERGENCY SUPPORT SYSTEM REQUIREMENTS BASES sy 3.1.2.a Maintaining a diesel generator as an alternate source of g,elecpal power provides redundancy in the power supply to agelectricg,jn water source. The identification"of the diesel generator is not specifiedlhowever, the'most likely alternates;are.the units'prevfo'uTly identified as ETEmergency /7 DieselLGenerator or Standby Dissel Generator.iThisitI(unda57:y[ power,,

~

supplies to an electric-motor driven pumpliasuresat$t a loss of"oSsONMr will not result in a loss of emergency ma%l #ng to the SpentMNol.

In the event no ac power source is availableZa.

not requiring ac electrical power will provide emergency makeup cooliiigg""#nt Fuel Pool.

Acccpiotic options wenid incind; prevffns toJ

tions fieni thc

&hernoic cquipnicni ;c 0;t-siresystems lity of a diesel generator or pump'not requiring ^ guiring consistent with the slow rate on;ac eIectriEil power 9

'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is be epymxiine;cly;1essLthanJ[M per,l[paf therSpentrNdfMYi bat u Pool (calculated to after December'5,(1997 historical'lacl[$l\\ pent Fuel Pool leakage:and is else consis;cnt with tip' ratepfSpent FuEf Pool water inventory loss due to evaporation (dis in thofBASES for SURVEILLANCE REQUIREMENT Zs for S cetic/4T1.1.a).'

f ce requNhhhki are to supply at ! east 28 gpm of water, at 3.1.2;b ump n1 p to the Spent Fuel Pool. These parameters satisfy the iremg gicigency ivanp cooling thet is used in ;hc g

_j iisa mwAic enelysis of to maintain the Spent Fuel Pool

/emperamre less than 150 F.

t hbh Sources atisaquired inventories of water to be used as the makeup supply are 1

not specifi[ Normal Spent Ftiel Pool makeup'is supplied from treated radwaste'or the demineralized water'systemiflhe pump design ~ capacities asiociate(with thesel sources are 100ipm and 30 gpm'respedivelyCNornial doolindprovided by a ~ pool coolingsystem capable of removing the~ decay TAsVbackup? in thelevent.that the normal makeupfsourcesLare

~

vailable7Imire Michigan water:can be provided by'the' fire protection iystemU A nenibcr of pimfmuud sonicus, snch es dernirsielisd weici, ticeicd wastc and conicasaic storagc taaL lavcatory +mild acciiially bc uxd, 5:ewcyci, w&ici fieni L Nc Mich g&n is A$50 AVai!&hlc hio$ Wou$d he used in dic cvcat thcx touts shou lJ bc caipilcd oc etl cwix J;sablcd. For paipuxi of cn igency inekcup er cnwis iwy cooling, ;&kc wois hos sufficicnt pniny for c

ax la thc SpuaiTuc: Puel.

June 5,,1998 B3/4-7 L

BIG ROCK POINT l

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

1 3/4.1 FUEL STORAGE 3/4.1.2 Spent Fuel Pool EMERGENCY SUPPORT SYSTEM REQUIREMENTS BASES Y

Thc n5c Of dic cnicigcncy niekcup linc will cnsdic th&t did.nppig/'f o

cnicigency niekcup cooling weicr is et the 3snglecetig'a;.discd in t thcinial hydienlic an& lysis. This will cnsuicietneinia

-_ "^:.n will occur throughout thc Spent Fuci Poci, cooling ishE71dcd to& kM fuci 5

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The ACTION requirements of this specincatio%;e,igsures that an ana yzed' Spent n

Fuel Pool cooling source (28 gpm of water (at a tentperature not greater than 100 *F) will be available. Allowing 24 hou/s'tiSataE)ish this alternate source is consistent with the slow rate 'of heatuf6f the Pdiil1 Pool (calculated to be epproxinistcly less1than;l F per hourgdci higEd'hed conditions after December.5,1997), the historical lack ' f Spent Fuel Pool leakage and 1

o

~

the low rate' of Spent' Fuel Pool water inventofy los's 'due to' evaporation

{

(discussed in the BASES for SURVEILLANCE REQUIREMENT:4.1.1 a).

A b

4+-2 Thc SURVEILLANOOREQUmEMENT3 ef this specification provide cquipedOil![,$,#b d fi % f rin 25 scquaicd.

assurancc thei g%uQ cc 4

n n

n.. ~.,

4.1.2.a.i

%jThis' SURVEILLANCE REQUIREMENT p ovides assurance of yEvaIlability MisTe~AC power; a

k$$%,

$$bh 411.2. alii This SURVEILLANCE REQUIREMENT provides assurance of the valia~biIlty$~WSof onsite Ei>ower.

~

T.a.m,A u

4.1.2.b.i This SURVEILLANCE REQUIREMENT piovides. assurance that the makeup gJ pumps are9alifa~ble Within' the' prescribed time and will perform as required.

h I

i 4.1.2.b.'il This SURVEILLANCE REQUIREMENT provides assurance of the Q

hvailabliity'and flow capacity of SFP makeup.

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I June 5, 1998 B3/4 8 u________

_ _ _. _ _ _ =

l BIG ROCK POINT PERMANENTLY'DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS BASES

~

p 3.1.3.a

- The placement of material in the Spent Fuel Pool is restridted to.

ure that the flow paths required to supply cooling to th pent f[;

lies stored in the racks are clear. Natural circulation will.

lop actuss nt fuel hits in the[

assemblies as buoyancy changes in the wa ue to he warmer water rising to the top of the poo

,9 3:1:3'.b Storage of material between the east wall "

B can result in mg_

the natural circulation patterns required fo S

" fer in the pool and adversely affect the cooling flow to variog #

semblies. (This storage restriction applies only to the spit:e direc Rack B and the east wall of the Spent Fuel Pool.)

4 3.1.3.c The south wall provides the 1, mo

'n ahth respect to the thickness of the other Spe el Poo ity level of the spent fuel stored closest to the th wall restr inimize the radiological field through the wal The ACTION to ad fue li. ~ ' rations and perform corrective etions will f.2 at the

. ' etry and ALARA considerations of pent :..

re esta fore fuel movement resumes.

411 ill y this specification provide assurance that the

- S',.

Ist iguration continues to be s:ttisfactory after fuel or ts ha n handled in the Spent Fuel Pool. Performance of

$ surveillance (.'173'c is not required'after August 29L1998 because~ after;that date alliuel in ~the_ Spent Fuel Poolfwill have dcca ed by at 1 east one ear;

~

~

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L, Junte 5,. 1998 B3/4-9

[

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l QIG RO(SK POINT PER(ANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDLING 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS BASES Thc icquiscnicni 10 nieintein the cepebility in hevc intenidtic cle 'h?

3.2.1.&

n3 c&pebility At ihc conteinnicni vcnilletier. valvcs, er ehcinejivcly, #;ddkd[OSURE c5tebi!5hcd at thc5c veivc5 pievidc5 -'--'-- "^ --

" g ficin &

g

[

fuci handling eccidcst will not bc significed[M[khh'Q@Nh h

This specification assures that no signifig scicapill occur thM.M ep/

)

3.2.1.ba epuning5 which niay bc siedc releases to 16eIIte boundary resulting from fuel i

handlihg events will be reduced by in the c6f5I60$ bot shell during the i

decommissioning process. CONTAINMENYtLOSURE, as opposed to leak-tightness, is specified, since there iflio pro"philidg)f$rce associated with analyzed fuel handling accident

'~ j The ACTION as'sociated with,this specification is regu, ired'to preclude fuel handling,when CONTAINMENT CLOSURE does not exist or when containment ventilation valies are lh"OPERAli[F i

M f

B 4:2. Ea The surveillance reguired by this specification provides assurance that

~

^~

Containment Closure exists adihat the containment ventilation valves are six &priorTo handlin%iidide conta#nme

~

OPERABLE

&V tsE!A (4^This specification has the^same~ radiation level alarm set 3.2.1.6 STOld'Ibe ga'mma radiat' ion" monitors are to' pro' vide'an indicationiof Spent Fuel Pool criticality aTid Eevated radiation levels that may be indicative of a

~

~

releaseII6is'iH[ alarm settings beyond 20 mrem /hr may~oe nece'ssary during inovem6at of spentluel or radioactive components in or adjacent to the Spent Psel Pool. TheT1 theTopti6n to rais6 the alarm setpoint is 'exbreised, the

,m

~

revi!ed alarm setpoint n:ust continue to; meet the criticalityidetdction criteria of d#

10.CFR'70.24(a)(2);

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The ACTION ' associated,with tnis specificati6n is required to mitigaie a radioactive release'which~may be indicated by the radiation alarm and to pro' vide for the reduction of rtMiation levels to acceptable values.

4.2.1.b The surveillance required by this^ specification provide assurance that the SFP radiation monitor is, OPERABLE to provide indication and alarm ~functionsi June 5, 1998 B3/4-10 l

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUFL HANDIJNG 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS BASES 32fla The movement of spent fuel is restricted to one assembl t

minimize the consequences of a fuel handling accident t.those a the drop of a single assembly.

j The ACTION associated with this specifi.kon is dt c

assemblies in en - ysd"a safe configu 31Lh

' The sp6cifiedl radiation level within the s r sock tank area is.

sou;cica te e vehac whkh assures that if fuel movement has'icassed greater s n the r S

I Pool 7tisinovement of fuel,will be sus unded'and an investigationionducted l

The ACTION associated this s ired to permit determining the cause of incre radi Is, and specifically to determine if stored e ca of the increased levels.

q

)(

adiatic:. monitoring will provide l

4.2.2:b The frequency of rmin surance th sed rad I

n the filter sock tank area caused by ment.

Spe l[

l will not be undetected. The radiation ss at a distance from the wall which satisfies ALARA

'ons a e geometric requirements to consider ine Spent 11 as rce. This distance (or location) will be governed iati nitoring procedures.

ssa A

3.2.2.

Manual guidance and? visual observation'of fuel handling ~ operations will

~

Mide assurance that;fuelfm6vement;is carefully ~c6Mv'M aiidfniositored!

l M

Thi" ACTION; associated Lwithithis" specification is reghiredlt6pSvent;fdel handin~g operations;in the absence of adequatiprovisioniifor manual guidance' j

observations of the activityi j

31 Spent Fuel Pool water pisvidedzcessary' shielding for the fuel handlers'to

~

ininimize occupational ldosi"during normal SFPfactivitiesNTransfer of fuel from'the~ pool.requirs ths use of the 24ft6n'transfefcask.

1 NACTION associated;iwith tids specificati6n'is required ltd prevent fuel novementWhout niing'SFP water as shieldingTor the'using Lthe transfer cask.

June 5, 1998 B3/4-11 s

L__z__ __ _ _ - _ _ _ _ _ _ _ _ _

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

3/4.3 CONTROL OF HEAVY LOADS BASES.

3.3.1.a

' This specification reflects a license condition resulting from the Spent Fuel Pool kerings expansion ind.isTreported in the May 15l 1981: Safetgp Evaluhtios. T;.c fecl storegc recks edjeccni to Oc cesk :

• ilin # ee ecc "ecks O end I:, es dcsciikd in icfHSR. Itjp expect largest load I

that would be required to be moved over th t Fu e fuel he NRC.[

transfer cask and therefore no other load lg en full h

agV The ACTION l associated ' ith'this specitica ion is required to place the crane I

w load in a safe condition land prohibit resumption 8f 16ad handling ~ activities

{

~

sntil sppr6ved by;the Site General Mana l

4.3'.1".a This SURVEILLANCE REQUIREMENT provid6s assurance that,the load will not exceed ~the.24' ton' load 1

' ]4

~

This specification reflects a rpemel NRgsSER. dated May 15, 3.3:1.b 1981, related to the expans)p,5 of the

' storage capacity. It'is

^

expected that thefonly casks regs' to be moved over'thelSpsnt Fuel Pool are the fuel transfer'cas'kTuxi pos'sibly~a cask required foi-l permanently

~

~

removing fuel from t7he pent Fu'el Poolf UTe~of the'caskLfor permanent.

removal of the fuel fTom the$nf Fuel Pool (if not;the fuel transfe'r_ cask in

~

ts current configuytion) would rec uire NRC ~ approval bechsselthis situation

~

~

s not been Elly evaluated.3F

~

~

Tkh i

ACTIONLassociated with this'ipicificatioh is required.to placelthe cran 6

~

load in a safe condition and prohibit resumption"ofload handling activitie's

/ntil approved by the' SiiEGeneral Mansgeri Mbb 4.3.1.b This SURVEILLANCE REQUIREMENT provides nssurance that the cask'is

~

properlpirigged and that oni 'an NRC approved daskisused:

M The'ACTIONissociated:withthis; specification'is required to' place the crane 16iui'inisafe condition and prohibit resumption of load handling activities Iapproved.by the Site'. General Manager?

3 '.3.1.

This specification reflects a requirement statsd in May 15,:1981. Safety l

Evaluation Relating to the Modification"of.thel Spent Fuel Storage Pool 'and l

- reipires operability.of the cask'iafety? catch device so that'this backup' feature is}ivailable'piidi to handling the:'ssk overLthe SFP.

e June 5, 1998 B3/4-12

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS l

BASES The ACTION associated 'with this specification'is required.to place the crane load.in a" safe condition and prohibit' resumption of load handling activities untill approved by the Site General Manager.

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/$$$[N 4:3il:c This. surveillance providesl assurance that the trip mechanism is OPERABLE;

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June 5, 1998 B3/4-13

i l

BIG ROCK POINT i

i PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

{

3/4.4 SEAIID SOURCE CONTAMIIN A110N BASES 3.4.1 The limitation on removable contamination for sources requiring leak testing meets the limits of 10 CFR 70.39 for sources containing plutonium [The specification will not exceed allowable intake yalues. fyh limitation provides assurance that leakage from sealed scSces co The ACTION ensures that sources exhibitingSeak f

/M lle accordance with NRC regulations.

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v groups (in use, or stored and not in use), gtegoriz,es seale.1 so For purposes of testing, the specification to'two 4.4.1 with; SURVEILLANCE REQUIREMENTS commensurate with theNobikof damage to a source in that group. Thc5c sourcc5 which Arcifcqncnliff"jN{cquirc niorc ficqncliiic5 ting. Sc2 icd 50nicc5 which.u cnniinnC.jM5cd within &

5hicidcd iiicchini5ni (such 55 5cAlsNNN.25'g&. u.2%.._,_ss iihin i&IddInieni;0 ring

,__ e w m "n

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uv uvusf aiw vvaisiuss wu 6u vw m uu aim..-.an uw miwu usuu icinGVcd fiGniihc 5hicidcdIjchdnl5idbdbM3[

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l June 5, 1998 B3/4-14 l

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