Text

Proposed Defueled Tech Specs for Big Rock Nuclear Plant
	ML20236T668
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/21/1998
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML20236T666	List: ML20236T665; ML20236T668;
References
	NUDOCS 9807280321
	Download: ML20236T668 (50)
	v • d • e

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1 i.

l V DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

1.0 DEFINITIONS 1.1 ACTION ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.

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1.2 CERTIFIFn FUFL HANDLFR Vf A$h NS$$fA CERTIFIED FUEL HANDLER lis an individual who is qualified in accordance withi BRP Program D25.1 " Certified Fuel Handler Eitial Certificatio

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47 VM 1.3 CHANNEL CALIBRATION kb%

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%R A CHANNEL CALIBRATION consists ofis the aquagment,s to the as-necessary, of the channel output such that the channel resp $ ids witNMhellessary range and accuracy to known values of the paramejergh the cIsagellacinitors. %The j

CHANNEL CALIBRATION shah eys the entire chsenel including the i

sensor and alarm and/or trip functio,ns, and MiiiNkdes [ CHANNEL FUNCTIONAL TEST. 4The CRANNEldCAUBRATION may be performed by any series of sequential, overlNing, orOtal cliannE1[ steps such that the entire channel is calibrated.

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1.4 CHANNEL CHECK f d

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' assessment of channel behavior during operation by observation.,.nu, w ru,ernico,,v_y eum uus mu,_enre,. rcsponsc u,unu3 c

gg cr yp 7mr i 1 tio This assessment shall include,'where possi$i5}Mison o[thEcigu$el indication and/or status with other indications.

angd[Enges$$,frorMind$ pendent instrumentatio 1

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1.5

. CHANNEL FLNGTf0NAL TEST A CHANNE&y x

FUNCTIONAL TEST is the injection of a simulated signal into the I

channel as efldse to the sensor as practicable to verify OPERABILITY, including k'

lagigirip functions.

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1.6 NTAINMENT CLOSURE l

CONTAINMENT CLOSURE is that condition of containment in which there are no t

DIRECT PATHS from containment atmosphere to the outside atmosphere,except for the containment ventilation inlet and exhaust valves, which may be open if at least one

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exhaust fan is in operation. Tor conteiroiicnt piping igreireiiens, CONTAINMENT CLOSURE is defird te exist wign ors valvc is clescd, or & scd velvc picventing 9807290321 980721 11 PDR ADOCK 05000155 W

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BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS 4

outiverd 30- of unids freni centeiroiicnt is in the linc. Leak tightness is not required for CONTAINMENT CLOSURE to exist.

i 1.7 DIRECT PATHS Ak

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A DIRECT PATH is a visually observable openingphich peredts'the,isso m[_

free exchange of air between containment and the environs. Equipment configuratid

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engineered encinadvc3 feature'such as a closed valve, check valve, water seal, closed door,-or membrane layer, 'or securely fastenedgte ma%e used to'%{dIi~ECT PATHS. Redundancy.of engineered features to eluninate DIRECT PATHS is not required; f@

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-1.8 FUFILHANDLING

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$d8 FUEL HANDLING means the activities associated with moving spent nuclear. fuel, including moving the 24 ton fuel transfer cask wheh it contaIIis spent fuel..When i

spent nuclear fuel is ~ contained in a closedjand sealed p_erdIanent storage cask or associated transfer device, the activities associated with moving the' cask or device when it is outside the SpentWel Pool Area are not to be considered FUEL HANDLING.

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1~9 lhMDIATELY

. When "IMMEDIATELY" is used as~a completion time for a required ACTION, the ACTION should be pursued'without delay and in a controlled manner, i

1-2 I=

DIO ROCK' POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS (continued) 1.10 MONITORING STATION I

The MONITORING STATION is the facility which has monitoring, alarming, data archiving and limited control capabilities for selected system parameters iluring the l

decommissioning process. The Control Room shall remain the MONItDRING STATION until such time as a' new facility is activated to serveihis function.-

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1,11 DFF-SITE DOSE CALCULATION MANUA CM The OFF-SITE DOSE CALCULATION MA AL (ODCM) contams'$lef#s methodology and parameters used in the calc j$ffsite doses reiblelagI om radioactive gaseous and liquid effluents, in the of gaseous and liquid effluent monitoring alarm and trip setpoints, and'iri%iInduct of the "nvireiencetel Radiological Environmental Monitoring Pro 65m. T!NODCM shall also contain (1) programs required by Sections 6.6.2.5 Eiid ' ~.Ig3 and (2?pu the Radioactive Effluent Controls and cal Envligs drediptions of the information that should be includedfriiEAiumuldIRadiologid$1 Environmental Operating and Annual RadioactidfEfflue R'eteese ~

h required by Specifications 6.7.2 and 6.7.3.

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M 1,12 OPERABI E - OPERARN BTY

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A system, subsystsia, temin, com '

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or. vice shall be OPERABLE or have OtMBILITYibasiMQs capablegpdibrming its specified safety-function (s)-

' this 1""" 7. ell bc the essen.pilen thetand when all necessary attendant ini '

, coi5td sharical power sources, cooling or seal water, lubrication or othY equifi is are required for the system, subsystem, train, 1

conque$siIer to '

'in its safety function (s) are also capable of performing ddIt elate 2I#hAmetion(s).

W 1.13 PROCESS COMT

, PROGRAM (PCP)

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The PROCEg ONTROL PROGRAM contains the methods and determinations l

which ensupr that the processing and packaging of wet solid radioactive wastes will be d in such a way as to assure compliance with 10 CFR Parts 20,61 and I regulations, burial ground requirements, and other requirements governing dispnul of solid radioactive waste.

1.14 REPORTABLE EVENT i

l A REPORTABLE EVENT is any of those conditions specified as reportable in' 10CTR50.72 es; 10CTR50.73 Specification 6.9.

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DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 1

l 1.0'

' DEFINITIONS (continued) 1.15 SHIFT A SHIFT shall 16 the duration of the normal work period, which will be either 8 or

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12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in length as determined by the Site General Manager. For purposes of l

determining the maximum allowable time between surveillance, wh_en the specified surveillance interval is "once per SHIFT ". the maximum allowable extension not to

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exceed 25 percent of the specified surveillance in$al descrfb'ed in~ surveillance requirement 4.0.2 shall be based upon the SHIFT duration agproved y the Si+.e j[

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General Manager at that time.

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DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS

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1 ere are no safety limits or limiting safety system settings applicable to the permanently

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l DIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY j

LIMITING CONDITIONS FOR OPERATION A

_Ay gf 3.0.1.

Compliance with the Limiting Conditions for Operation andM hquironicnts shell i

bc 3pplicebk during the spcciCcd &pp;;cebic ce for [ d Q g ation.

contained in the succeeding specifications is reguired during the conditions specifiedfE therein;' e~xcept that upon failure to mee' the Liniiting ConditTons'for Ofe7ation, theY associated ACTION requirements shall be mei f

3.0.2 Noncompliance with a' specification shall exist when thep'Adhcicnce to thc requirements of the Limiting Condition for Opo6ii&It'er'and ' associated ACTION requirements are not met within the specifieditIme i$dYilT.Iholl censninic conipliencc wnh the 5pccl3cetion. IfIn 0,;went the diEiting dondition for Operation is restored prior to expiratiaddthe$ccified tiine krIervals, completion of the ACTION statement requirementiWo uhiidg j #

Unless otherwise specified, erdry into an'4 % &

f 3.0.3 applicability. condition shall not be made i

unless the conditions of the'a$s*ociated Nimiting Cdadition for Operation are met l

without reliance on prov.d%contaiNd in theyDTION statements.

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SURVEILLANCE REQUIREMENTS MF j% %

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~Unless' apacified UtherwischSurveillance Requirements shall be applicable during the spe'cifiedspip&

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'licable EnemalEl for the associated Limiting Conditions for Operation.

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4.0.2 EacgSurveiBancoRequirernent shall be performed within the specified surveillance hiit'erval withT surveillance in}Mm allowable extension not to exceed 25 percent of t N0st[b Q

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Unless specified otherwise, performance of a Surveillance Requirement within the U[hl y

specified ti '$iterval including the maximum allowable extension shall constitute complia

' ith OPERABILITY requirements for a Limiting Condition for Operation

$g: goint ted ACTION statements.

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.g 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 i

Operatica have been performed within the stated surveillance interval including the maximum allowable extension.

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4 3/4-1

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1 DIO T.OCK POINT 1

I PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE -

3/4.1.1 SPENT FUEL POOL PARAMETERS LIMITING CONDITIONS FOR OPERATION 3.1.1 The following parameters shall be monitored and intaine e limits indicated:

a.

The water level in the Spent Fuel 1 shall bypriin c cveden of 00' 04 syphen b.. ;' ~30' Thetween 6301 and 632'6".

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b.

Spent Fuel Pool water temperature

' intained greater than 40 *F and less than HB 140 F.

s c.

Water chemistry in the Spent Fuel Pool shall be man ined within the following!

pH 5.0 to 9.0

.+

Conductivity lesi '

or ual to 10.0 micmmhos per em"at.77. degrees F Radiation 1 fin the radiation monitors, each with a locally 4

d:

' of nt Fuel Pool shall be normally monitog

'two a and remotel udible at not less than 5 millirems per hour and not millirems per hour, except during~ the movement of. spent l~or r.

ve components in or adjacent to the Spent Fuel Pool,.when -

setti raised above 20 mrem /hr provided the overall rite n 10CFR70.24(a)(2) is satisfied. At least one monitor

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isrgu to be OPERABLE.L The monitors shall.have remote indication J

and the cap, ability of recording data.

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..vivshstandi..y, th,,cqn...m...;. Of 10CI'd70.24(e)(2), ele.,n 7

-r.vas =asa a vwa au v.=67tafief as an6ama ssu.==---

.wa When nadie:cd spent fuel e;xw.b :c; erc stered is~in the Spent Fue! Pool.

ACTION:

i.

With the requirement of 3.1.1.a not met, ;,,medie:cly IMMEDIATELY; suspend activities having potential to drain the Spent Fuel Pool. Place fuel assemblies and the crane load in a safe l

condition, ei.d Own 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 levelc Within 24 3/4-2 L-----__-----_--1---_

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I DIQ ROCK POINT

. PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.1-SPENT FUEL POOL PARAMETERS LIMITING CONDITIONS FOR OPERATION hours establish CONTAINMENT CLOSUR g

V ii.

With the requirements of 3.1.lgapt met TELYl place fuel assemblies and the crane load in a safe dondition,, suspend further movement of fuel ass _emblies and cEne i>perations with 10 s

in or over;the; Spent Fuel Pool, and initiste ACTION to restoreP'

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acceptable temperature!

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months establiIHF

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CONTAINMENT CLOSURI$N.

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j iii.-

If the water quality speci ions of 3.1.1.c are exceeded, initiate corrective' measures to meet chemistry requirements within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

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and sample' pool water at least once a' day until readings' meet the requirements ofil.1.c.l.If water quality,cht be ' ecovered after r

one week, prepare a spe_cial report that identifies'the causes'and proposed corrective action (s) to ensure. future. water quality is in

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compliance and submit to'the NiiC by 31 days following entry.into the LCO.

iv.

requi fl.1.d not met, IMMEDIATELY provide te me nitoring Spent Fuel Pool radiation levels.

te instrumentation does not have an audible alarm, locall the~ MONITORING STATION, it-radiatiori levels shall pe co monitored by personnel in communication with the O,

l MONITORING STATION, when personnel are in the vicinity of the uel Pool.

A 1

provisions of Specification 3.0.3 are not applicable.

SU LLANCE RE REMENTS i

4.

Twice once per4 [ hours SHIFT, the water level in the Spent Fuel

. all be determined to be cquel to er gice;ci then its niinininni icqslied

.above the elevation of ti., mmuu me..m sv.m,,630N f

4.1.1.b-Approx;ine;c y Twicelonce per 4 ! hours SHIFT, Spent Fuel Pool water temperature j

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

b 4.1.1'.c App exone:c y.Once' per 31 days,' Spent Fuel Pool ~ water cheraistry shall be I-determined to meet the requirements ' f Specification 3.1.1'.c j

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3/4-3

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DIG ROCK POINT

. PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1-FUEL STORAGE 3/4.1.1 SPENT FUEL POOL, PARAMETERS LIMITING CONDITIONS FOR OPERATION 4.1.1.d The Spent Fuel Pool radiation monitor required by this specifJintion 1 be demonstrated operable:

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Daily by performing a CHANNEL h K. f%

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a Once per 31 days by performing a NNjilCALIBRA1Mlt??

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1 3/4-4

l' DIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEI STORAGE 1-l 3/4.1.2 SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS LIMITING CONDITIONS FOR OPERATION i

1 3.1.2 The capability to supply makeup to the Spent Fuel Pool shall $mai ed as

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follows:

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A diesel generator capable of provi power w s_ to operate?

an on site electric motor-driven pu shall be available>

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I One off-site source of ac power ca A. ding power l

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mperate an j

l on site electric motor-driven pump ilable, M, An on site pump not requiring el rical capable of providing makeup water to th Fuel P 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

A b.

The pump designated t ment d Specification 3.1.2.a temperature equal ['or lessTying water within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a j

l shall be capable of s 1

Spent Fuel Pool cnwigciwy

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niekeep lire. '

apabil to man y initiate at least 28 gpm flow to the Spent Fuc(

et d,d, mini thcycat Tsci Peel cnwigcrey niekenp

rs cnicis, Drent F "%

shen be maintained.

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APPLICAW8MiE-Wh L % pent Qab mbhes-atris stored in the Spent Fuel Po ACTION:

th the s of this specifications 3.1.2.a or 3.1.2.b not met, 24 h ish an alternate source of water capable of delivering j

gpm

'ater at a temperature equal to or less than 100 F to el Pool.

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' The provisions ification 3.0.3 are not applicable.

I St LANCE 4.1.

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

l il MeuiL;yOnce per 31 days, manually start the diesel generator land run loaded for 30 minutes using an electric motor-driven pump as a load, f

4.1.2.b

.i Once per 12 months, verify that the pumps satisfying the requirements of this specification are capable of supplying water to the cnwigciwy niekcnp line within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and will deliver at least 28 gpm of water; 3/4 5

DIC ROCK POINT.

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PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

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3/4.1 FUEL STORAGE t

l 3/4.1.2 SPENT FUEL POOL SUPPORT SYSTEM REQUIREMENTS

' SURVEILLANCE REQUIREMENTS A

Once per 12 months, the Spent Fuel Pool emergen/h 4#

li cymakeup line shall be determined to be OPERABLE by veriffde its ffaiwMspeisky to be at least 28 gpm.

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' DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS' 3/4.1 FUEL STORAGE 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS LIMITING CONDITIONS FOR OPERATION The following limitations shall apply to the storage of spent fuel in theISp A

3.1.3 ent Fuel Pool.

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Spent fuel assemblies'shall be ' stored in fuel stora e racks located in the #7 a.

Spent Fuel Pool.-

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b.

The storage of materials m. the area tween rack B Line east wall of the Spent Fuel Pool is prohEbited.N Akk A

Only spent fuel with a di..iy time %f greate gne year will be stored in the outer three ron of thw 2(rac(adjacen@t 6 diidOioth wall o c.

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I APPLICABILITY:

When irredieted spent fhel esseeuuM.;;.LJ is in the Spent Fuel Pool.

f ff kW ACTION:

With the requira,nants of this specifications 3.1.3.a,3.1.3.b, or 3.1.3.c not met, suspend $ilhiidlN#0ixietijNpent Fuel Pool work activities other than required surveillance activities and perform a prompt investigation to determide tli2cause as idpropriate corrective actions.

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SURVEILLANCBSEQUAREMENT54 V jpWQggh V

a. O At least semi-annually and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months _ of completion of any 4.1.3 9

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3[ verify that the requirements of Specification 3.1.3.a have been m

_ tiv_ity involving movement of spent fuel in the Spent Fuel Pool, bfl.

a f

At least' semi-annually and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of upon completion of any i

activity involving movement of components in the Spent Fuel Pool, b

verify that the requirements of Specification 3.1.3.b have been met.

? i c.

At least' quarterly and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of upon completion of any FUEL HANDLING activity which involves movement of fuel into i

the fuel rack adjacen'. to the south wall of the Spent Fuel Pool, verify that the storage configuration satisfies the requirements of Specification 3.1.3.c. Performance of this surveillance is not required after Scpiciiibcr 15 August 29,1998.

3/4-7 l

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-DIG ROCK POINT c

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.2 FUEL HANDLING 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS LI.MITING CONDITIONS FOR OPERATION 3.2.1 The following conditions apply when handling fuel inside containment.

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es thc ineniter scquiscdy Q4cirse; ion 3.1.1.c,5;[N cepeb [" coniehwnd vuoi;etien vsivc cleenic, er "^"#""""

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hc centehmen; veni;;& tion velvc-al For containment penetrations or ope gjiTAINMENT CLOSURE shall exist and containment ventilation valves shall be closed orl capable ~ of being closed; F-fp Afh

%005$gbf bi Radiation levels shall be maintamed below the alarm settin.g requirements of specification 3.1;1.d 7Q j

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i APPLICABILITY:

When handling fue) iside containme -

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f kiremses of thispeification 3.2.1;a not met, place ACTION:

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With fuel agiriiblies ids)afe cosilition, and suspend FUEL HANDLING g 4 ii; iWth the requirements of specification 3.2.1.b not met,' initiate 2MR closure of containment ventilation' inlet and~ exhaust valves and

'nitiate corrective' actions ~ to' reduce the radiation levels to acceptable alues; V i

SURVE_

NCE REQL ~

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4.2:1 None-1 i

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I rior to commencement of FUEL HANDLING activities, perform ppgypyp verification of CONTAINMENT CLOSURE for all containment

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t penetrations or openings ~ and verify OPERABILITY.of containment

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ventilation valves.(CV-4094, CV-4095, CV-4096, CV-4097) i l.

b; Verify that the radiation levels on the Spent Fuel Pool area radiation monitor are less than the alarm setting requirements of specification 3.L1.d at least twice per SHIFT, 3/4-8 u_ _ _

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DIO ROCK POINT i-PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

I~

i-3/4.2-FUEL HANDLING l

l 3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS l

LIMITING CONDITIONS FOR OPERATION 3.2.2 FUEL HANDLING operations shall conform to thetfollowi ments:

l m,

a.

Movement of spent fuel into and out~

he stora ^

diaspection stations shall be restricted to one aMImbly at

e. ' 'M5 Ik Radiation levels at the Spcni reci 7( i sk tenk esce sout b.

the Spent Fuel Pool, elevation'600' Qkmaintained at less than 50 mrem /hr above the background level dur' FUEL HANDLING operations.

V

- c.

FUEL HANDLING shall be ished by. manual guidance and. visual

~

observation of all FUEL lIXNDLINGTperationE f

f$b W d.

Water shall be u,se_d as_ the b,asic' shield _ing except 'when transferring ' spent fuel from the S nt Fuel Pool using#

the 24 ton fuel transfer cask; 7

s h 1 Pool.

APPLICABILITY:

When g fueliq%W 4%

ACTION: jg ?

ja.

. utrements of Specification 3.2.2.a not met, suspend FUEL HANDLING operations and place irradiated fuel assemblies

'nas

n. Conduct a prompt investigation to determine the a

iate appropriate corrective actions.

u.

e requirements of Specification 3.2.2.b not met, EDIATELY suspend FUEL HANDLING operations, and y(initiate ACTION to restore radiation levels to less than 50 mrem /hr above background levels and conduct a prompt investigation to y

determine the cause ofincreased ladiation levels. FUEL HANDLING may resume if it is determined that increased radiation levels have not been caused by the handling of fuel in the Spent Fuel Pool.'

lii.

With the requirements'of Specification 3.2.2:c not met, suspend FUEL HANDLING operations 7 FUEL' HANDLING may resume l

orse.the requirements of 3.2.2.c have.been re-established, iv; With the requirements of Specification 3.2.2.d not met, suspend

~

3/4-9 j

l_.

OIO ROCK. POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

t l

3/4.2 FUEL HANDLING i

3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS I

LIMITING CONDITIONS FOR OPERATION kk A FUEL HANDLING operations. FUEL HANDLING may resume once the requirements of 3.2.2.d have been re-established.

SURVEILLANCE REQUIREMENTS

@f' yk irJk' ;)

f 4.2.2 ai

None,

. 4g:;?

wai n Prior to commencing,'og% of FUl%NANDLING iik 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months SHIFT ring ftiel and b.

[

IMMEDIATELY of n.c; hendlingywitics4Mlthpygation levels in at the Spent 600'6", toy $y; auk escgsouth wall of the Spent Fuel Poo Fuc! Peel sec i

![' 0} y that die requir'Osisiis'of Spe f

U met.

c:

None.f -

'k

/h d.<dhl$- N e e3 g.

y:

pp y

n

[,

.l ww L

3/4-10

DIQ 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:

fx Use of the reactor building gantry cranepver the,Sp$t; 1 Pool for loads a.

E[f b

%gfQ exceeding 24 tons is prohibited.

/kys b.

With the exception of the properly rigged 24 toMuel t '

C. or other cask specifically approved by'NRC for6Ie in or oderLtES% uel Pool:

3[

%M hijfh No cask shall be moved oveqspent;flM[%

i.

stored in the Spent Fuel Pool.

4"

%$;@g A*%

WnQ ii.

Cask handling operadensikdi be limitedVthe southwest corner of the Spent Fuel

,F 'hk f

!uCQV jsehraje racks adjacent to the cask lii.

No fuel shalp storedr the handling,ards in the.s6dthwest d6rner of the Spent Fuel Pool during cask haddHrij operdti"ons.

F j

The trip meiYb$ l chanism of the 24 ton fuel transfer cask safety catch' device c.'

~

shall bej Table prior to handlin TQ.sgiNg g of the cask over or in the Spent Fuel

fFor C,ontainment penetrations 'or openings, CONTAINMENT CLOSURE d.

exist. V[

sig&%

ss APPLICARILITX:

When spnt fbel is stored in the Spent Fuel Pool.

'ff fih W ACTatW:

Wigthe requirements ofthis specifications 3.3;1.a; 3.3.1.b,3.3.1.c or l

3.3.1.'d not met, IMMEDIATELY place the crane load in a safe condition, jl(k del suspend further load handling activities with the reactor building h{I.

gantry crane. Load handling shall not resume until permission has been obtained from the Site General Manager.

3/4-11 l'

t i

__________.________J

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS SURVEILLANCE REQUIREMENTS None 4.3.1 A

m a.

Prior to moving a' load ~over the SFP,' verify that the load does not exceed gi f

b.'

Prior to moving a ' cask over the SFP; verif{that the cask is_th_ey,r_ogerly o

rigged 24 ton fuel transfer cask,' or another cask specifically approved.by NRC for use'in or over the Spent Fuel Poollg

~

AbkhbA c.

Prior to handling of the 24 ton fuel transfer cask over or in'the Spent Fuel Pool, the trip mechanism of the cask safety catch device shall be functionally. tested.

gf[8g Y

~

N hkhfif d.

Prior to moving a heavy' load over or in the Spent Fuel Pool, verify that CONTAINMENT CLOSUli5 ' xits; ((

e Y$

/

f

$h%c Ql{;fV' ph' h

z gg

. d]@%

uds k[Mb NIr sqy i h

$am i) f" *fhp

^

k J

l 3/4-12 E

+.

' DIG ROCK POINT l

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.4 SEAT FD SOURCE CONTAMINATION LIMITING CONDITIONS FOR OPERATION

)

l l

3.4.1

. Each sealed source containing more than 100 microcuries of beta and/or gamma j

emitting material, or more than +0 5 microcuries of alpha em!tting matedhi shall not j

have removable contamination'which equals or. exceeds 0.00 inicrociffs.

$ih APPLICABII ITY: ' At all times.

ACTION:

1.

Each sealed source with re ~

" lec ~ mination m e

above limits shall be IMME

' withdrawn fronistiiand 2

either decontaminated and rep posed of in accordance with NRC regulations, fy y

a.

A special report s submitt RC as indicated by i

Specification

\\

/

y SURVEILLANCE REQUIREMENTS d hichair stored not in use, and 2) start up sources 3

4.4.1 Except for: 1) sealed s and fission detector p ~ usly sM'"#ted toIb're neutron flux, sealed sources

' ing radio terials

. #bther than gas and with a half-life greater i

%c ys (

3) shal d for contamination and/or leakage at least mon

'censee or other person specifically authorized by the N

reeme rform such services. The test method shall have a i

detect y of 5 microcuries per test sample. The' test sample shall be taken m the sealed source or from the surfaces of the device in which the

~

sealed source is permanently mounted or stored 7on.which one might' expect

. contamination to accinulate. Records ofleak test results shall be kept in units lof i

microcuries andinaintained for inspection by the NRC:

i R

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

lb =$

not being in use, shall have been tested within 6 months prior to being

. transferred or put into use.

3/4-13

DIO. ROCK. POINT 1,

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES i

5.1 SITE 5.1 ~.1.'

LOCATION AND BOUNDARIES

)

The plant site, consisting of approximately 600 acres, is locMMCharlevoix miles west of Petoskey, Michigan. The nearestjandside pr%

County, Michigan, about 4 miles northeast of Chabivoix, operty hne is about j

2680 feet and the nearest shoreline property line is about 200 feet from the J

containment sphere (Reference Figure 5.1-1).[{}g SM h~ MATE"IAL SPENT 5.2 STORAGE AND INSPEcliON'OF S"ECIALE FUEL W

D95 -

hM%h

'5.2.1 CRITICALITY Spent fuel is stored in The-spe I stor w

h e designed and shall be maintained with sufficient ce

-to-ce dista.

een stored fuel assemblies to ensure a k,y less than o ;

I to 0$,when t _

acks are flooded with Y

unborated water.

8 j//

j hg embly placed in the Spent Fuel Pool The; fuel loading 6 1 centi IMs less th to a maI4qsufor 28.3 grams of U " or equivalent.

~

2 F

n stat lied, shall be designed and maintained with suffic to-ce between fuel assemblies placed in the inspection state M "

1,y le n or equal to 0.95 when flooded with unborated i

I r

b l

5.2 '

' WATER LE L

L uel Pool is desigred to maintain a normal water level between 630and l.

'6". end to y,sent unin;cin; enol die;euig below the syphen biceker which is e

)

wa;.;laa :C' 4" a i,eauu;. clj :",a a;^ ll;c noen;a: ;-a:ce lcul.

v t

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 cxcc551vc thmeielly-indeccd seds in iro. Sgn; Fnc; " eel cer mc strucinie, l

l 5-1 L--__-_-.-_--

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

H 2 D.

O 4 i

9 2 1 n

n h

xg N.

g i Eg \\

Ns

^\\

81 @

[2 N.

I u

s 3E 3

d$

slj 3 8> l

~

3)j e

2 5,

tf

~^

f

\\

2

_ ##?iW M 9 9%

n z

x

\\

N

\\

i 8

.\\

2 5

, sm e

3 s

3

'q%7 e

e A

'l a

5 l

5-2 u _-________ __ _ __.

=

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS t

5.0 DESIGN FEATURES 5.2.4 CAPACITY Subject to the limits listed below, the fuel pool is designed for and shall tk maintained with a storage capacity of no more than 441 fuel as'semblicFIn addition, fuel pins which have been, removed from fuel assedbliels.siSI9shall be stored in the Spent Fuel Pool and shall be in~a geoirietry to$$hliinsures jfv cri

_a m

sub.ticality., e.v_,,_ _,.u.s._m_o_.m ou ous_s_ me n. r _ xg,y_ wwm vg

.uwo u u

~u conteining fnc; in the stored spent fuci esscndfks. The folldwing timits apply toy i

the amount of special nuclear material which My be stofid in the S}wniFuelfddi:

2500 kilograms of contained uraniu(mj235$h f??$h'.

NW i

10.32 grams of uranium 235 as contained in ihmon counters.

150 kilograms of plutonium conta#did in"PhD8 fuel rods.

i 5 curies of plutonium encapsulated;as a plutoniana-beqFyllium source, gQQ,9%

Q

/Y}g'%/

5.3 REACTOR 5.3.1 STATUS The reactor is not licensed for power l operation! Fuel shall not be placed in the ef f

'%h;%l$y%s p%a%%a T19 4"

%{je

^

@aL,,-

s I

5-3

e y.

DIG ROCK POINT l

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.1 RFJPONSIBIIITY AND AUTHORITY l

6.1.1 SENIOR NUCLEAR OFFICER Ah l

The' Senior Nuclear Officer shall be the Senior Vice President-Nuclear, Fossil, and Hydro Operations and shall be responsible,f,or the oveTl[ operation,

~

maintenance and decommissioning of Consumers Energy nuclear power plants.

6.1.t2 SITE GENERAL MANAGER

/

The Site General Manager shall be respon:hforloverall facility opeation, L

maintenance and decommissioning ad forjadedsfor absence shall delegate in writing the succession to this responsibility 6Udses)diwrwise specified, the Site General Manager's delegate has authidity to'Mall actions and grant approvals assigned by these specificai~ jo the SitI l Manager. The Site General Manager may deleg

$ tasks to o' ividuals who may perform those tasks whether tl Si iemeEEManager" bsent or present st

%i[

the site.

)l/a s

6.1.3 SHIFT SUPERVISO 1

The SHIFT Supervisor shall be responsible for the' SHIFT command function.

This position will be filled by a CertifiTd Fuel Handler.

~

6.2 7

1 Ng%

LA'IH,NSHIPS 6.2.1 1

On-site org nd corporate reporting relationship shall be established for activiti

. ting safety of the facility.

a.

s of authority, responsibility and comm'.ai :ation shall be stablished and documented in facility administ.ative procedures.

The Site General Manager shall be responsible for safe operation of f

l the facility and shall have control over thuse on-site activities 1

necessary for safe operation and maintenance of the facility. The J

individual filling this position shall report directly to the Senior Nuclear Of0cer, c.

The individuals who perform audits, surveillance and independent safety reviews report to the Manager, Nuclear Performance 6-1

l DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

6.0 ADMINISTRATIVE CONTROLS (continued)

Assessment Department.

d.

The' individuals who train the Certified Fuel Handlers and those who carry out radiation protection functions report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence' from operating pressu5s3f P

%Q%

Q %r a 6.2.2 FACILITY ORGANIZATION

'ing:/

s.k -,. 7:

TO]p The facility organization shall be subject to the foi h_hh NON a.

Each on-duty SHIFT shall be comprised of atlleast the minimum SHIFT crew j #Q composition shown in Table 6.2-1.

bA b'.

A!! fuc! hsadling operations sha!! bc d%,;'y supervi.;;d ti e C;nincd Fuci AM e,u e v u _ ;, _...t _

_t_,,t_.

_.t _ _

.u_ _.u_

. 4anuma n uv ouun uu.._ _ _

wuvvumas Ccnifcd Fuci !!andicrs 3hs!! nicdi;dfdif ^^ah: fonhjf$hc s:stion's

> " 6 " " 3 "F" "" v"-

admin.strativc proccJurer At1Iast one $disid6Nwhoihall be qualified to stand watch in the MONITditING STXTION,"shalflTe in the MONITORING STATION when irradiatedTuel is in'ihe SpentYuel Pool, f

,k?

A qus!!nc;i Racia:!w re:ce:ica Tcchnicle;/f ' bc cn site during fac shs!

c.

epersuons su;ff j$ fspecinc[M., idcs v,hich hsvc the potentis!10 rcault in ii 4

/r_& _ _ _

rma.___..

.. _.t _..

..t_

n._,

_.t _

F 'O: ive ni/lp;g~"-"d on si:c, en individus! quslincd inadiatitm vaam m

' s r - m -"->'""" ""- '"" v>""->

arc

%protestient proccM*1-N he prcacnt cn snc. During operations without FUEL IfARIEIRG either ihiSilIFT Supervisor or the Non-Certified Operator shall be qualifiEdin~Ta'diation protection procedures. During FUEL H ANDLING (x: ratio'ns a qualified.Ra'diation Protection Technician shall be on site.

m&wp When spent $$)fIIstored in the Spent Fuel Pool or during FUEL HANDLING

347

/

operations ilministrative procedures shall be implemented to limit the working pk hours of t.hEfacility staff who perform safety related functions, and activities MQ impstaniIo the safe storage of spent fuel and the monitoring and control of hNTpJsdioEgical hazards. These individuals include the minimum SHIFT crew g@%M@N iTeiuired by Table 6.2-1, key maintenance pers l

t a# technicians.*

i esc GvCniliiC iCstr5C !Gus G[!!iis SCC !GL spf y Gn!y G pcikOds WiiCii spCii [uCI !s l

s:cred in the Spen: Fuc! Foci, or when spcn: FUEL !!ANDLING or radicsc;ive v.ssic headling setivnics arc conduc:cd-6-2

I

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

. Adequate SHIFT coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

y work more thanj#$

(1)

An individual should not be permitted to,l) 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months straight, excluding SHIFT turnover time

%f %

lY JhWlkm jf,f (2)

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

in any 24-hour period, nor more th$n 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sNany 48-h'6ur]periSfhd more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day pe'ridd,'all $ilcluding SHIFT tuinnd Y E7%

time.

k sh%s (3)

A break, including SHIFT turnover time, ofnleast 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed after continuous work periods of 16 $$urs ddition.

AWh f

Any deviation from the aboveg$ inaccoElince witiEest'a51ished ad Manager or designated alternat procedures and with docum Ktation of9fie ba'sikfdgr![nting the deviation.

Administrative procedur0sIhall inclS$e a regulieNient for the Site General ne a

u Manager or designated alternates to reviewMdividual overtime on a monthly basis in order to verif[that exc"edive houb'have not been' assigned. Routine deviations fro, nit,hdabove gu ' 'lin$iii,O, 6t authorized.

r n

m i.; nf 4[&@q!;fQ Mg Q,Q

- ;4 vg g.

g'"R

u-A r.

,m TARI R &2-1: MINIMUKi SHIFT CREW COMPOSITION g$DURING PERMANENTLY DEFUELED CONDITION g/

- [-

STAFFING FOR STAFFING f

POSITION OPERATIONS DURING FUEL WITHOUT HANDLING g% :

FUEL HANDLING OPERATIONS

CD sw,,

SNGTSupervisor or Centrol 1

1 dfIrator(CERTIFIED FUEL HANDLER)

Auxiliary Opera:ct Non-Certified Operator 1

1 CERTIFIED FUEL HANDLER 1

Radiation Protection Technician l

6-3

lg

' DIG ROCK POINT t a l

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) l c.

FUEL HANDLING ' operation.s shall be directly supervised by a. CERTIFIED FUEL HANDLER: who shall have no other concurrent responsibilities during this operaticact ERTIFIED FUEL HANDLER shall meet qualifications set forth C

l in the CERTIFIED FUEL HANDLER Training Program.

A l

' f.

The SHIFT Supervisor shall be'a CERTIFIED FUEL HA LE.

g.

The SHIFT Supervisor shall report to an ind ual who is a CERTIFIED FUEL' HANDLER.

A f

l u

L h.

Personnel requirements of(a) and (c) above may ess than the; minimum specified for a period of time not to exceedThours in order to accommodate unexpected absence.of on47y personnel provided immediate t

ACTION is.taken to restore the minimum requirements specified. This provision

- only applies to on-SHIFT personnel and'does not permit any SHIFT crew

, position to be unmanned upon S111FTihange diie to oncosiing SHIFT crew member being late or absent.

[/

r, 63 STAFF OUALIFICAT'-

[

Each member of the facilit)f Pa$P

/

x" nage mds isory staff shall meet the minim requiremen

j. SI N18 omparable positions. The ind ponsi f ation p Tunctions shall meet the mi'.

ireme

' atory Guide 1.8, September,1975.'

g A g...: e e.

.al:

8 9 usca.u rua..c rac;;;w c a;;;cd ruci::=:ces

/ - bc cei-J nc;c i kc w;;h en NRC eppieved tre.ning pivgreni. A treining

[ugreni foi ;he fep'f%ff shell bc in plen.cnted erd shell nicci ihc sc+nen~nts end v..... rde;;ensg

,;;en 5.5 ef ANS' NIS.1-1971. A training program for the S

lip (facility's CERTIFIED FUEL HANDLERS shall meet the requirements and commendations of Section 5.5 of ANSI N18.1-1971.

I

, gggy 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 6-4

F-

)

\\

i DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) 6.5 REVIEW AND AUDIT 6.5.1 Requirements for on-site and off-site reviews and audits are described in CPC-2A, L

Quality Program Description.

6.6 PROCEDURES AND PROGRAMS g;

6.6.1 PROCEDURES h

pf 6.6.1.1 Scope j

Written procedures shall be established, implemen maintained for safety related structures, systems, components and safety actio

_ Big Rock Point Decommis~ ioning Quality List and those stmetures, systems, comp _onents and activities s

important to the safe storage of spent fuel (ISSSF) and monitoring and control of radiological hazards'(IMCRH). These 1 meet Kas,ceed the requirements of ANSI N18.7-1976, as ~

ors

ualit Pfogram Description (CPC-2A).

[

.4 Written procedures shall alsb be established, implemented, and maintained covering the following activities:

[

{

4

^

Site security d;[

'fk a.

c d

b.~

te emergencyylan; and, Til~ grams listedIn'S ' ification 6.6.2.

c; kh fy, AnorovaD, t 6.6.1.2 Re.

.Re ments approval of procedures (and revisions thereto) required L

is section are in CPC-2A, Quality Program Description.

Temoorarvh)hances ti i

6.6]j l

quirement

_ making temporary changes to procedures which fall within the scope j

'are described in CPC-2A,' Quality Program Description.

6.6.2 S

The following programs shall be established, implemented and maintained in accordance"with written procedures meeting thErequirements contained in specification

'6.6.1:

6-5 L

i

4 DIG' ROCK POINT r

-PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) 6.6.2.1 Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and ad ^ d to for all operations involving personnel radiation exposure.

4 6.6.2.2 High Radiation Area 6.6.2.2.1 Dose Rates less than 1000 Millirem per I pf In lieu of the " control device" or " alarm signal" r Paragraph 20.18Ha) of 10 CFR Part 20, each high radiation area in whic of radiation is greater than'10Crmrem/hr but less than 1000 mrem /hr at s) from the radiation.

source or from any surface which the radiation trates arricaded and conspicuously posted as a high radiation are trance I be controlled by the use of a Radiation Work Permit (.

tion pro qualified -

' hon qualified personnel or personnel continuously r

personnel may be exempt from wo g under, the performance of their assigned radiation protectio @bties in kh rad areas with exposure rates of less than or equal to 1000

^ ',prov they otherwise following facility radiation protection proced

. r ent to such h radiation areas. Any individual or group ofindi%als pe

.t

~ r such areas shall be provided with i

siIore of t or acc.

anied by,

i

a. -

' ' ' l tion evice which continuously indicates the radiation dose area,'

b.

toring-ice which continuously integrates the radiation Jose

- Mate in t alarms when a preset integrated dose is received. Entry into such a

, 'this monitoring device may be made after the dose rate levels in

, ave been established and personnel have been made knowledge e of them, or l

A rad' n protection qualified individual (e.g., IIcent l'hysics Radiation L

Ion Technician) with a radiation dose rate monitoring device,

'nsible for providing positive control over the activities within the area.

6.6.2.2.2 Dose Rates equal to or greater than 1000 Millirem per Hotir In addition to the requirements of 6.6.2.2.1, areas accessible to personnel with j

radiation levels greater than or equal to 1000 mrem /hr at 30 cm (12 inches) but less than 500 rad /hr at 1 meter from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, l

l 6-6 L---

- - - - - ~ _ _

____--_________.--------_________.________________j

O G)I@ ROCK ' POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTR ATIVE CONTROLS (continued) and the keys shall be raaintained under administrative controls specified in the facility administrative procedures. Doors shall remain locked except during periods of access i

by personnel under an approved RWP. The dose rate levels in the immediate work areas and the maximum ellowable stay time for individuals in that area shall be communicated to the individuals. In lieu of a stay time specificaten, diredt'or remote (such as closed circuit TV cameras) continuous surveillance mayfbelmalilby personnel qualified in radiation protection procedures to provide [p)sitive#exposumiPcontrol over

/(@~

%$k the activities being performed within the area.

kMgMN For individual high radiation areas accessible to 1[e$yrsonnel, ' h radia d

cve' to er greater than 1000 mrem /hr that are loi: seed lwi'tfiin large areas Eheriho enclosure exists for purposes oflocking, and no erN.losurchan be reasonably constructed around the individual areas, then that inifividual $ca shall be barricaded, conspicuously posted, and a flashing light shall 17activEtsd hYwarning device.

r w %r 6.6.2.3 Process Control Progam (

W #m hf 6.6.23.1 Changes to the PCP

%M Changes to the PCP shall bedo?h 4

ene effecifye after appsoval by the Site General d@e Manager.

A k$ ports k

[

6.6.2.3.2 khh

$h%

Chrnges to die FCP shan be sedunitted to the Commission in the Radioactive Effluent c

Release R'epestMthe perikMiwbkh the changes were made effective. This each;6fiin; sher postmiit=sufficiEngl[ detailed information to submittal ge arididesmSnmtioit that the change did not reduce the overall conformance of thEsslidlBid waste product to existing criteria for solid wastes, fW Offsite Dose' Calculation Manual (ODCM) 6.6.

6.

Chan lo the ODCM l

RMg he ODCM shall become effective after approval by the Site General M ager.

6.6.2.4.2 Reports Changes to the ODCM shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the changes were made effective. This submittal shall contain sufficiently detailed information to support the rationale for 6-7 l

l

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) l each change and a determination that the change did not reduce the accuracy or reliability of dose calculations or setpoint determinations.

l 6.6.2.5 Radioactive Effluent Controls Procram i

A

,Jt, A program, conforming with 10 CFR 50.36a, for the' control of ve effluents and for maintaining doses from radioactive effluent $W. members shad [

as low as reasonably achievable. The program (1) shall Mcontained)Eth

,I be inuhmented by facility procedures, and (3) sig$ includdemedial ac 1

taken whenever program limits are exceeded. TikM shall include t wing

~

elements:

. \\;WW Limitations on the operability of radioactW[e liquidkh s monitoring i

a.

instrumentation including surveillance I

accordance with the methodology l

and set

. ination in u_

b.

Limitations conforming to 10 times the conceAEation values specified in

~

10 CFR Put 20, Appendig, Tabl 20.2402, averaged over one hour..gif2, Colyfio 10 CFR 20.100

. L. ce, 7,aelens of for radioactive l

material released in gefflu to unredri ted areas, i

y a

, onitoring, pg and a,

,pioactive liquid and gaseous effluents in c.

rdance 310 CFR 20;1302 with the methodology and parameters in M;

d.

L onfom;

-7pendix I to 10 CFR Part 50 on the annual and r do itment to a member of the public from radioactive aterial _

ffluents released from the facility to unrestricted areas; l

Determinat umulative and projected dose contributions from radioactive effluents e current calendar quarter and current calendar year in accorda hvith the methodology and parameters in the ODCM at least every

' 31 da f Itations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period 'would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.

. g.

Limitations conforming to 10 times the concentration values specified in Appendix B, Table 2; Column' 1_ to 10 CFR 20.1001-20.2402, averaged for one 6-8 l'

' ' DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS L

6.0 ADMINISTRATIVE CONTROLS (continued) hour die desc5 esseie:cd with 10 CFR Pert 50 cii the desc retc ic5ni;iiig from radioactive material released in gaseous effluents to areas beyond the site boundary; A

h.

Limitations conforming to Appendix I to 10 CFR Part 50 Athe ammial and quarterly air doses resulting from noble gases released ia#ggigimde effluents

^'

from the facility to areas beyond the site bou

andQ){

b n1 dose;er$ A -

i.

Limitations conforming to 40 CFR Part 190 n the ange/

commitment to any member of the public d to reldfes of radiE to radiation from uranium fuel cycle sources 7

%d7 i

?

59 b;.. f l

l 6.6.2.6

' Radiological Environmental Monitorinahram ?"9 l

A program shall be provided to monitorethe&&

}

ra radi lides in the environs of the facility. The program shall pai$Iide (1gfik ~['$0d(2) verifica

. measurements of radioactivity in the highest potentigexposuar pathEM accuracy of the effluent moni% prog,rdiand modEling of environmental exposure

pathways. The program sha$ftYbe coatiined in taif0DCM, (2) conform to the guidance of Appendix I to 10 CFR Pads 0, andMIinclude the following:

h3I5]jh7

, analysis,M[ reporting of radiation and radionuclid x

' ~

a.

itoring ironm

. appardance wirit the methodology and parameters in the b.

sus to Mure that changes in the use of areas at and beyond the l

~ $lte bou

~

entified and that modifications to the monitoring program are made i y the results of this census, or alternatively, that critical f

receptors a, huuined to exist at the site boundary or offsite location of highest dose conse ence; and i

'4 l

Partic' on in a Interlaboratory Comparison Program to ensure that l

ent checks on the precision and accuracy of the measurements of x <.,

oactive materials in environmental sample matrices are performed as part of

~

the quality assurance program for environmental monitoring.

6.6.2.7 Fire Protection Program A fire protection program meeting the requirements of 10 CFR 50.48(f) shall be established, implemented, and maintained.

6-9 1

E______._.____

l DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS (continued) 6.6.2.8 Cold Weather Protection Program This program provides administrative ' controls to ensure that appropriate measures are implemented and maintained during cold weather to protect the facility againjt cold l

temperatures which could impact the safe storage of irradiated fuel or result in unplanned or unmonitored radioactive material release.%

M[

l w

y y

+

Y.54 W h${ "

6.6.2.9 Soent Fuel Fool Water Chemistry Program,. '

j ki Ah This program uses procedures to provide controls for monitormg Spent Fuel Poolz water chemistry.

QT Mis Inservice Insoection and Testine Program [Qk;$

6.6.2.10

~

9

%pfk a.

Applicability

,ggg Md)

.edkOh h.

\\h Applies to inservice inspection and testing of the_reacto_r vessel and ~other i

ASME Code Class 1,. Class 2 and Class 3 pi ing systems and components.

NfY [

&V b.

Objective A}/

To insure the integru.of the Class 1, Class 2 and Class 3 piping systems and omponents; Af f7"EjV

N21

+(hdk NOS#

. specifications % W4 c.

' Ph 6$hk 1.

lInservice Inspetion of ASME Code Class 1,2 and 3 components and Minservice testing of'ASME Code Class ~ 1,2 and 3 pumps and valves shall be performed in accordance with Section XI of the' ASME Boiler and Pressure [sel Code and applicable Addenda as required by 10 CFR j

50, Section 50.55a(g),'except where specific written relief has been granted by the Commission purs~uant to 10 CFR 50, Section

}

50.55a(g)(6)(i),"and where provisions of sections 11.4.1.4, 4.1.5 and Q

11.4.3.4 take precedence.

k:N a J, 1

Sufficient records of each inspection shall be kept to allow comparison and evaluation of future tests'. (ic ehe idlerm 6.9.3 erd 0.10.2.g.)

3.

The' inservice inspection program sl;.ll be reevaluated as required by 10 CFR 50, Section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been proven practical, and the conclusions of the evaluation shan be used as appropriate to update the inspection program.

6-10 E_________-_--_---___-_-----.

BIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS l

6.0 ADMINISTRATIVE CONTROLS (continued) l l

i 4.

. A esivcil:asc y.egies. te nienher i&dietien Indewd chengc5 in is niveI an!ch. &nd uy&ct y.vys iic5 ef $4 icdcies ic&K'. nudci &i5 5I4ll bc Eelum md es dcailbcd in &Gien 4.1.I(h) of C4K Tsiouced -

Sgelfkehere.

Thc Irmivis !ieyvalen Piegseni feijj[ing ide.ab' in NRC C.issic 5.

Lat.i = c: st_:1 bc sif... d in acco.2& rec we. e.c mg Rea reint

)

ICSCC Pregieni eyy.eved by thw%yd

]w]h

~

j

.a h.

Mdf' 6.7 REPORTING REQUIREMENTS bv aih l

.a The reports identified in this section shall be submiiEdLin'achdance with 10 CFR 50.4.

Y Y 3%p Ah 6.7.1 ANNUAL OCCUPATIONAL RADIATION EXPOSURE RE10RT fff k An annual report of radiation exposses received'during the'f previous calendar year shall be submitted prior to MarchYof enchj$ar. This; rep 6rt shall tabulate the numbers of facility, utility and $Eer perso$iel (inciddIng contractors) receiving exposures greater than 100 dillirEm durliig the y[eadalong according to work and jobjndtions,j [examp operations and surveillance, routine dil maintemnce, specialpigliance (identiff)@; and waste processing. The do n.

m w

assi.

s,.=-

to various nct.ionsmiqi.. estimated based on pocket dosimeter,

)

TL.

adge%

ts. Small exposures totalm.g less than 20 percen' of the ihthilliose nel$h, accounted for. In the aggregate, at least 80 percent of indivi the total M% gly ose rNiliped Aom external sources should be assigned to specific major warf4ladlinois N(/j 47 MWL 6.7.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT gn annual radiolog}lfVEal environmental operating report cov y

g cility during t Trevious calendar year shall be submitted prior to May 1 of each 4 ar. The r

' shall include summaries, interpretations, and statistical evaluation of j

$ e Radiological Environmental Monitoring Program for the reporting hI e materiel provided shall be consistent with the objectives outlined in the dDCM and Sections IV.B.2, IV.B.3 and IV.C of Appendix I to 10 CFR 50.

6.7.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

l An annual radioactive effluent release report covering operation of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The report l

shall include a summary of the quantities of radioactive liquid and gaseous effluents 6-11

GIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS I

i 6.0 ADMINISTRATIVE CONTROLS (continued) l and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the ODCM and the PROCESS CONTROL PROGRAM, i

and shall comply with the requirements of 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

gh A

h 6.7.4 SPECIAL REPORTS gQ) p jh The following special reports shall b: submitted to NRC ad bd D

sf mL /

% dg a.

If the water quality specifications of 3.1.1.c are exceeded, and the water quality can not be recovered after one week, prepare a_spgereport that identifies the causes and proposed corrective action (s) to, ensure future water quality is in compliance and submit to the NRC by 31 days following entry into the LCO.

AMN Nfb!)

b.

Prier-to Fchinari 1, subnin a e W.

Spccifica; ion 3.4.1 was dc cctyCh$,in cxcesdnhc linins ofgen m

q picvious calendar ycar. If the sealed source contamination limits of 1

specification 3.4.1 are exceeded, a special report shall be submitted to the NRC J

within 30_ days of identification of the existence of the~ excessive contamination.

The report shall descil6Itile equf[ ment invdfved, the test results and corrective i

4 8

p%

actions taken.

4 9

c;<$o3E.L nservice Insp/Kih -ection reports re@qutTe'd 10 CFR 50.55(a) and Section XI of the x

m VS

~

57$h h$1 RECORDS,,:g kg l[O 6.8

+ w,ac.7g Recosi$ etentiod sequksinents are described in CPC-2A, Quality Program Description.

\\W l 9

6.9 MREPORTABIF EVENTS lQ jf QA regrtable event is any event or condition that must be reported to the NRC in Maccordance with 10CFR50.72,10CFR50.73, or 10CFR50.9(b).'

Qy l

6-12

1*

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f-s

' jD (BIG RO,CK4 POINT R.E. STORATIONTROJECTL t

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RDEFUELED TEC5INICAU. SPECIFICATIONS: #

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1 BASES:

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LIMITING CONDITIONS F($43RiiRATION

>ss SURVEILLANCE REQLIJREMENT,Sf8b 4%F V'^

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3 ELEDTECHN

' L SPECIFICATIONS PERMANENTLY f

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NOTE bases contained in this section summarize the fireasons for the Specifications in Section 3/4, but in

' (([accordance with 10 CFR 50.36, are not part of these Technical Specifications.

l-l t.O_ _._ _

BIG ROCK POINT I

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS J

3/4.0 APPLICABII ITY BASES 3.0.1 This specification defines specifically when the other speglGeatiosk Section 3/4 are applicable.

3.0.2 This specification defines those conditions h must seder to g'

comply with the terms of a Limiting Co on of O ion'S$ j$ socia 4

Action requirement, h

i 3.0.3 This specification provides that entry into applicability condition may be made only when (a) the full com ired systems, equipment and components are OPERA Ea parameters as specified in the Limiting Conditionsggration hout regard to allowable deviations and out o c-M -

-ions co in the Action j

statements.

3

/

The intent of this provis*

is to e re tha s are not initiated with required equipment i ble oc4iher spe ed limits being exceeded.

k A

k

~

4.0.1 i

speci i blishei-ess otherwise specified, surveillance per the specified applicable conditions for which the nts o Conditions for Operation apply. The purpose of

! tion i that surveillance are performed to verify the s of ms and components and that parameters are within

)

specifi nsure safe operation of the facility when the plant is in a E

specified /

ty condition. The specification also establishes that SURVEIL]f REQUIREMENTS do r.ot need to be performed when the facility i

, a condition for which the requirements of the associated Limiting Conditi for Operation do not apply.

I specification establishes how long the specified time interval for a j

L VEILLANCE REQUIREMENT may be extended. The intent of providing this allowance is to facilitate surveillance scheduling to account for conditions that may not be suitable for conducting the surveillance. It is not intended that this provision be used repeatedly as a convenience to extend the surveillance intervals beyond those specified.

1 The allowable extension provided by Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any B3/4-1 l;

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.0 APPLICABILITY BASES (continued) particular surveillance is conformance with the SURVEILLANCE REQUIREMENT. These provisions are sufficient to ensure that thdireliability demonstrated through surveillance activities is not significantly deIgladed as a result of an extended interval.

Mdh[

3 kNNb The provisions of this specification set forth the criteria 4kilesecouning

//

4.0.3 compliance with the OPERABILITY requh$ments o,fdiniti$g(Conddions forf Operation. Under these criteria, equipmkystedfor components stE$hI assumed to be OPERABLE if the associajad suNeillance activitiesEnbeen satisfactorily perfonned within the specifi5d[tiskSterval, including the maximum allowable ~ extension. Nothing infthi(proviiion is to be constmed as defining items OPERABLE when they sEknown {dk. rable even if they meet their associated SURVEILLANCE REQUIRhWs

,4fh This specification ensures that thd su!S k 4.0.4 rveiManen nctivit associated with a Limiting Condition for OpgIon hahenM5rin' ell within the specified time interval, including the maximum allowable extension, prior to entry into specified applicability @have been%ihe intenfof this provision is ition surveillance activitus satisfactorily 0 demonstrated on a current basis

. as required to mee(GIe OPERARILIT%$lpiirements of the Limiting f )j [

/ Condition for:

tion.

/ %

,: A Qg

\\ das raates otherwise, applicable surveillance activities must

\\%ished VMMitated surveillance interval prior to placing the assanidadhm inhMBLE status.

D. f V

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@z..F.q%q mso-B3/4-2

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

'3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS g

i i

BASES

.Y 3.1.1.a Spent Fuel Pool water level is normally maintained at c:A:eng 5". This is the elevation of the discharge overflow weiriwhich is at elevation'630'f6"'

per (icfcicesc drawing 0740G40153). However,'the range for control is from 630',(siphon breaker level) to _632'6" (reactor deck)h. - '

ee, cve:/

i,,,c. J by ::.ii.+e,;f; ;;vo le 4". t ew 72rs w.;2e.e:E M E ining 4pf water level above 630'..t... ;;~. : / ---. lc.

ensures that 22' of water is maintained above the active fuel contained in the70 red fuel assemblies in the i

~

spent fuel pool,' which is the assumption _used in the analysis of heavy load drop event in section 15;10.2.2 of the UFli5'R7 7

(

Emergency cooling of the pool wat mplis and bleed" method that adds cooler invento ndre he hotter inventory at the discharge vel iired by this specification will ensure t le init ter in the pool is i

consistent with the Spen el Poo rmal which concludes that feed and bleed is a viable gm for the' pent Fuel Pool. This level allows operaticaal ity b) lowing '

rruption of Spent Fuel Pool l

cooling when dic by o [ j (nal Me'nie;u;ng we:cilcyc;ebevc I

. $ "' '","$mE""""l

"""_'k*" f

$ ""~' R.

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. g%t" = %__._ ___; ="" -

-~4-"~""

">"~-'-"'=a=~"=~""s

is cm

_$;h ;he iWinc ice; eve; fec;ers 3;.;c,i in Regnie;ery mNg

^ nt 5f this specification requires ininicdie:c IMMEDIATE suspens ties that can result in draining the pool to minimize the loss ofinvento IMMEDIATE initiation of the restoration of the water leve fuel assemblies and crane loads must be placed in a' safe configur

and further fuel movement suspended until level is restored.

This ac '

will minimize the probability of a fuel handling event before the wat 1 is restored. However, containment closure is required within 24 to minimize a release if an event were to occur and the water level is not ilable to support the thermal analysis or the radiological mitigating effects of scrubbing or shielding.

4.1.1.a Since installation of the" stainless steel liner noLliquid attributable to leakage of the Spent _ Fuel Pool has been observed.l Based on empirical data, the rate of water loss from normal evaporation in the Spent Fuel Pool is not expected to i

exceed 0.1 gallons per minute (corresponding to less than a half inch loss in j

water level per day). As a result, the specified frequency for monitoring B3/4-3

l DIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS L

3/4.1 FUEI STORAGE 3/4.1.1' SPENT FUEL POOL PARAMETERS BASES 1

Spent Fuel Pool water level provides for early detection decr water level and provides assurance that water level will not d vel significantly less than the specified level dugehe in en readings. f The level specified may be verified by niu Cenuul Reuni, or by visual inspection off..ing Icycl ' Spen

en in ;h, l

{h7 instnamentation itelf.

3.1.1.b The maximum; allowable Spent Fuel Pool ir.' based.upon are dsTn cd by the structural analysis of the 1,jg the cialcelity da.niinotion for the sgn; Rici in the ws. performed for the. Spent Fuel Pool capacity expansion find is based on the concrete prgx:rties used in the analysis?, Above : 150_*F concrete strength p_roperties may be' in to be reduced.

g Structural integrity is maintained for temperatures'upjo 150*F Specifying j

140*F as the upper temperature limityrovides assurance that the pool remams

~

at a temperature below the temperature at which concrete strength properties may;begin to be reduced' f

^

f

,f j

f l

As documented in the UFHSR, a loss 'of Spent Fuel Pool Cooling ~ event and its l

gotential to resialt in approacyggxceeding the' Spent Fuel Pool; water

amnerature uppgeimit has been evaluatedi/At the' time of permanent plant l

}- ktdown, an analysis was performed to determine the' Spent Fuel. Pool heatup irate, based'upoEIbe op_erating history of each a'ssembly:in the. poolR On l

Wamher 20i1997, the last fuel assembly'was removed fr6m the reador l '-

Nvessel and placed in~the Spent Fuel Pool.1The results Mf the' heat-up an how that the fuel had decayed sufficiently by December 5,~ 1997, to allow l

pool cooling to be removed for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months without temperaturefexceeding 150*F L

(fromian initial temperature of 80*F);

i The cr' lity analysis performed for the Spent Fuel Pool expansion L

dete d that K (neutron multiplication fac:or) is less than 0.95 at the most i

e temperature, which is greater than the minimum specified temperature 0 F.

The criticality. parametric study l conducted over the' temperature range of 40'F to'212*F concluded that'40*F is the least reactive condition and 212*F is the'most reactive condition.' This The'specified minimum temperature ensures that freezing of the Sgni Tuci Puol. Spent Fuel Pool will not occur.

Based ~upon the~~UFHSR, achieving the minimum Spent Fuel Pool temperature of 40*F (or below) is considered unlikelyL Initiators oflow temperature L

B3/4-4

E

-DIC ROCK POINT l

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS BASES AN

' onditions would. include loss of offsite power, boiler problems or ventilation c

system failures Suchfa pool temperature.would notlonly requir~e a sustained loss of both?offsite and onsite AC power during extremely coliweather donditions, but would' presume that decay heat production from the s at fuel is negligible

[f r

?

The inexisissi 4:!vwa, c poo! teingc.ets, Wmeion t!,c Spent."-->

m _ _,

_____,m

' "" "l'"l '" """,r'#f._'" 'r ' ',' ""'"#f ',", _'."..". 'E77hu md"' f" "/ "".,"'.. _ff.. "'"#

l mm.

,,m,....

. m7 m

.m The ACTION requirements'of t ',; Win lead toration of acceptable temperatures in th nt f he ' nner of temperature restoration is not specified ; e sup d by Specification 3.1.2 provide assurance t Spent 1P g can be restored.

p g-pivxLiia^ ' A' }f r tempe 4.1.1.b Spent Fuel Pool w is5 ed twice per shift uims r.

t o.) in oq t early detection of abnormal Spent ool ens corrective action can be promptly taken.

3.1.1M Maintaining Spent buel Pool' water chemistry as specified' ensures the Spent

~

Fuel Pool water lis suitable for long' term stornge of spent fueliThe j

ifications~provided are consistent with the practices'at facilities that (begyThe SURVE provide long terin storage of fuelLThe conductivity' limitation will ~ maintain chlorides at less than 3' parts per.million.

V The~Antion requirements of this' specification lead to' restoration'of acceptable i

water chelitistryjonditionsi 4.1.1.

i surance that the chemistry l criteria are.being met.

3.1.1.ed Maintaining the at least one of the two Spent Fuel Pool area radiation monitors operable as specified in this section permits meeting the criticality accident monitoring requirements of 10 CFR 70.24(a)(2). The fixed gamma radiation monitors provides an indication of Spent Fuel Pool criticality and elevated i

b-

. radiation levels that may be indicative of a release. Raising alarm settings

- beyond 20 mrem /hr may be necessary during the movement of spent fuel'or B3/4-5

OIO ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.1 SPENT FUEL POOL PARAMETERS BASES AV

&ctivince vvhich involvc lifung !iied!A;cd radioactive ~comg+a,nents ym uf the peel or ncer its snifacc.in'or adjacent to th ent Fuel Pool.yWhen the option to raise the alarm setpoint is exercised /

continue to meet the criticality detection crlhifa of 10 CMRn2NaX2).

The' ACTION requirements associated with this spe/f b?bbh?%4h

$f cification will provide _the equivalent monitoring capability at a level required by 10CFR70.24(aX2).

4.1.1.ed The SURVEILLANCE REQUIREMENT provide confidence in instrument performance. Acccpiebic$$thodI'{E h3 3.yr.g & C CIIECK incindc coinpering the indi_ ' f.harrci O

' ' cxisdng p;&ni condidens, or cenipering-char.nd^ EIh,At of a FDIE rediatten

, 7 t4Jkg r_________.

51&OLA L55&Is&1L e 4 A ff.';;,.';,. pg The ACTION essocieted,9,di thisg?_cir.cei'[-.._Ji".. provide the cquiveicnt

_**__.._______L?t**__

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3RIVIIALVA 1335 wagiavia: Ly av vua Le sa agigis siv=,sa vy a vwa asi v.s. rgaj f.

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

L 3/4.1.2 SPENT FUEL POOL EMERGENCY SUPPORT SYSTEM REQUIREMENTS BASES Aa#

3.1.2.a Maintaining a diesel generator as an alternate source of al power provides redundancy in the power supply toffelectric%% water source. The' identification of the diesel generator is'not specified, howev the most likely alternates are' the~ units preEously identified aTtIEme ncy Diesel Generator or Standby Diesel GeneEtor. TgredundancY n

supph.es to an electric-motor driven pumpppgees;that a loss of o wer will not result in a loss of emergency maketpcoethig to the Spent Fuel Pool.

In the event no ac power source is availaid,T@l$g iint reqairing ac electrical power will provide emergency makeup 8$E) ling Acccp;&bic epilens won;d irwisdc pd ' x to niea-

--Gens fron; thc a:: cine:c equipnwn; ;e en si;c s(( Ming the*

bility of a diesel generator or pump not requiring ac electrical p$/jfhm 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is ower.w consistent with the slow rataTf heat ufoY$

be epproxinie:cly less tha$$ F pe,rjhour UMNIssi hcei leed ceedi;iens else censis;cn; widgl(ow rat %f Spentgl Pool water inve after December "i:1997 the historical lack of Spent Fuel Pool leakage and is to evaporation jdi sed in tde! BASES for SURVEILLANCE fh? REQUIREMENT ' sis for N_?'Y"'.I4.1.1.a).

QO 3.1.2.b.~

ip requirements are to supply at least 28 gpm of water, at 100 the Spent Fuel Pool. These parameters satisfy the d

menu

,.uwis iwy reekenp cw;ing imi is used in the c

_ginie, fdienlic analysis of to maintain the Spent Fuel Pool

[e.mperature less than~150 F.

f Sources a ired inventories of water to be used as the makeup supply are l

not speci

. Normal Spent Fuel Pool makeup.is s.upplied from treated t

radwaste or the' demineralized ' water system.iThe pump design capacities

(

associated with these sources are 100 gpm'and 50 'gpm respectively Normal e

k'f cooling'is~provided by a' ~ ool cooling system capable of removing the decay p

t.J As a backup, in the event that the normal makeup sources are unavailable, Imke Michigan water"can be~provided by the fire protection system.~ i A neniki of pi fomd 50siccs, such es deniincielizcd weici, irceicd wes:c end condense c 3;eregc ;2nk inven;ery wenid neinielly bc used, howcyci, weici freni Lekc Michigen is else eyeliebic end would bc necd in ;hc l

cvent ;hesc ;&nks shw d bc,,npiled or essiwisc dlsebicd. rei psipescs of cnx.3cizy niekcep er cewigeriy coeling, lekc we:ci hes sufficicn; pniny for now in e s S pc ni E Uca E c e$.

B3/4-7

OIO ROCK POINT PERMANENTLY ~DEFUELED TECHNICAL SPECIFICATIONS 3/4.1 FUEL STORAGE 3/4.1.2 SPENT FUEL POOL EMERGENCY SUPPORT SYSTEM REQUIREMENTS i

i BASES A

J Thc nse of the cnwi3cucy w.akcup linc will engc thei '/A~- #, uf l

l

__________________....____it__

_____r__t_

_ Af% _ _.e Efflh _ 3

.t.

{

suss2 56"6J ""'"up suvuan5 vroma as os u m c jusouu.s wou an um Owiniel hydreglic an 'ysis. This will cnsi/dit notsig,.._ "d;--i!! eccur af_ _..e, _ >. m mW m

._,___.m m,,.._,,,__,

un uusuum um q~m us,, uu, suu-.m3

, u uusu

..u um

- essenihilcs end icmelisd hui!!ng ducs ne'q-

"M_.gy j

m.

h The ACTION requirements;of this specifi

~ weigu,res that an analyzed Spent Fuel Pool cooling source (28 gpm of watafia.

ure not greater than 100 *F) will be available. Allowing 24'Nours to mf the SpM.y.~4his alternate sou hjool(calculated to is consistent with the slow rate of h m.. - highc,: p,leed conditions be eyeroxinietcly less than 1 F after December 5,1997), the storical lack ol Sp,ent Fuel Pool leakage and the low rate of Spent Fuel P,ool ~ water inventory loss,due' to evaporation (discussed in th6 BASES for SURVEILLANCE REQUIREMENT 4.1.11a).

k j

b'

'b N Th,I _ b s b b k "m o"3_

3F

A 2 MN' osm o.m

- u symy.

1 syu u su.

'h f$hbh Y-guu 411.2.a3 s SURVEILLANCE REQUIREMENT provides assu'rance'of the

~availabili of offsite AC wer.

?'

41.2: alii This SURVEILLANCE REQUIREMENT. provides assunnce of the availability (dn '

~

of ons te AC power; j

\\%

)

4.1.2.b.i This SURVEILLANCE REQUIREMENT provides assurance that the makeup g'

pumps are available,within the prescribed time land will perform _as required.

ARM f[

4.1.2.b.il

. This SURVEILLANCE REQUIREMENT provides assurance of the availability and flow capacity of.SFP makeup?

I I

B3/4-8

L

[- e '

DIG ROCK POINT L.

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

~

\\

3/4.1 FUEL STORAGE 3/4.1.3 FUEL STORAGE GENERAL REQUIREMENTS BASES-AW 3.1.3.a The placement of material in the Spent Fuel Pool is rest dt ure that the flow paths required'to supply cooling to t spent lies stored in the racks are clear. Natural circulation will, op a nt fuel assemblies as buoyancy changes in the wa ue to he.

. Its in the

. armer water rising to the top of the w

/

s 3.1'.3.b Storage of material between the east wall.

B can result in ing l

the natural circulation patterns required fo fer in the pool and adversely affect the cooling flow to vario semblies. (This i

storage restriction applies only to the s e dir Rack B and the east wall of the Spent Fuel Pool.)

3.1.3.c The south wall provides the I amo di

' h respect to the thickness of the other Spe '

1P.

ity level of the spent t

fuel stored closest to the [ th wat restri minimize the radiological I

field through the wal 3

/e t

The ACTION to shnd fue igdfs[ metry and ALARA considera

',g rations and perform corre::tive etions will at the i Spent

,re esta ' ' M4iefore fuel movement resumes.

-l 1

4.1.3 illanc y this specification provide assurance that the S

ool s iguration continues to be satisfactory after fuel or ts ha en handled in the Spent Fuel Pool. PerformanceTof Surveillance 4.173'c is not required after' August 2921998. because~after that

~

datefall; fuel in the Spent Fuel Pool will have decayed by at'least one' year.

{;Y Y

L B3/4-9

i p.

DIG' ROCK POINT' l _

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

~3/4.2 FUEI IIANDLING 3/4.2.1 FUEL HANDLING SUPPORT SYSTEM REQUIREMENTS j

l

' BASES I

t f

+

m n.mcm..m.t to m.

t.:.. tuer,eu::ty te nevc.mU.,

c:w.geu:ity e

si the cente!....cn; v4.ni,1&tien velvcs, es Aitcindivcly, ^

d OSUIE bJ L.1 t

_ t __ J _i it_.____

___e__.__

.._!3_

E_--_

LIRIJ5Eb%5 GL LAsbJb Y ER YbJ {1 U T IL5bJ RJJLE A R&IW

_ Gabs _

N 3& U155 a b5 Eb1 IkIhh bbb cbt 7 && bet Ub bl5 8i536~

5[ I 5

0 I

This specification assures that ne 5 gnlTQLciq;g dil occur 4_3%

3.2.1.ba g

. Opbnings v.hich niey bc niedc release ~s'to the site boundary resulting from fuel handling events will be reduced by in the %,t shell during the 085 %

decommissioning process. CONTAINMENT'C4'M,E,, as opp leak-tightness, is specified, since there ifilo pro analyzed fuel handling accidents. g$g$$$kr

%dh,P g

Ah$

N The' ACTION. associated with_this specification is reguired to preclude' fuel handling when CONTAINMENT CLOSURE does not exist or..when

- containment ventilation valves'are INOPERABL57 AGI J

B 4.2.lia The surveillance regui, red by this specification provides assurance the Containment Closure exists and that the~ containment ventilation valves are OPERABLE 1iorTo handling inside' containment.'

s w

3.2.1:b -

s specification has the'same radiation level ~ alarm setting requirements as

)

3T1 1.d. The gamma radiation monitors are to provide;an indicationbf Spent

[g uel Po_o1 criticality and elevated radiation levels that may be F

release. Raisingalarm' settings beyond 20 mrem /hr may be r.ecessary during movement of sp_ent fuel lor radioactive components in or adjacent to'the Spent

~

y f

Fuel Poolc;When the option ~to raise the alarm ~setpoint is exercised, the j

revised alarm setpoint must continue to meet the criticality detection criteria of i

10 CFR 70.24(a)(2);

M.

The ACTION associated with this specification is required to mitigate 1a adioactive' release.which may be indicated by the radiation. alarm'and to provide for the reduction' of radiation levels to acceptable values.-

~

4.2.1.b The surveillance required bp this specification prov~ide ~ assurance that the SFP

~

radiation monitor is OPERABLE to provide indication and alarm functions.

~

l l

B3/4-10

E<

DIO ROCK POINT

=.

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

L 3/4.2.

FUEL HANDI ING l

3/4.2.2 FUEL HANDLING GENERAL REQUIREMENTS L

BASES-f 3.2.2.a The movement of spent fuel is restricted to one assembi,' a tiam to minimize the consequences of a fuel handling accident t those a MIr the drop of a single assembly.

{

M The ACTION associated with this specif ion is re dt assemblies in en en.lyzcia' safe conditioIt.

1@

av 3.2.2.b The specified radiation level within the area of the south wall of the Spent Fuel Poolielevation'600'6" 24 si~nt nogZ[] esce is scen cicd to e veinc t;cli assures that if fuel movement has caused gjeater than expected

_ Y ' ?E$"

'!' mmY

.mo u;.mm v um ovum.$u 3,__,4,Y, '

, '?,

?

'~

vu,

,. us vui, the movement of fuel will be sus nded and an mvestigation conducted.

7 f}

The ACTION associated th this f cificat quired to permit determining the caus, e inc ed radi n levels, and specifically to I

determine if stored the f e of th reased levels.

4.2.2.b he frequen formin radiation monitoring will provide j

lssed radi is near the' south' wall of the Spent Fu~el ance

, 24...

%.i en.e caused by movemest p;&ccnicnt of fuel in the 1Poo ndetected. The radiation readings should be nce all which satisfies ALARA considerations and etri uirements to consider the Spent Fuel Pool wall as a lane so istance (or location) will be governed by applicable radiation procedures.

Manual" guidance ~and visual observation"of fuel handling ^ operations will provide a'ssurance that fuel movement is carefully' conducted and monitored!

Tlie ACTION: associated with this~ specification'is required to p' revent fuel ling operations in the absence of adequate provisions fo~r manual guidance and observation"of the activity; 3.2.2.d Spent Fuel Pool water provides necessarp shielding for ~the fuel handlers'to minimize occupational' dos 6 during normal SFP activities'.iTransfer of fuel

~ from the pool requires the use of the 24. ton fuel transfer casic

)

L B3/4-11

DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

~ 3/4.2 FUEL HANDLING 3/4.2.2

' FUEL HANDLING GENERAL REQUIREMENTS BASES AY The ACTION associated;with this specification is required to p event fuel movement without using SFP. water as shielding or the using,"t,he 24 ton fuel

~

transfer cask; h

h i.

j st

'I:-Q, ppfo i

j)

L, kj?4)'

8g" py, A

B3/4-12 L__---___________-

l DIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS 1

l BASES i

l 311 A heavy load is defined as'500 pounds (the weight of a fuel assembly and'the

. handling equipment),

p 3.3.1.a This specification reflects a license condition resulting fsamtthe Spent Fuel

^

Pool twerings expansion and is reported in the May 157Is5i'Slifety Evaluation. Tk fuci storege recks adjeccf[the ces%"skkt L eic l

.i g

Recks D &nd F, es dcsciikd in the FIIS4 It is expecidi th Puel Pool is'ihehol

$, Spent;tully evaluated byM@N that would be required to be moved over Fefs' transfer cask and therefore no other load

$$$$b The~ ACTION associated'with this..~ specification is required to place the crane

~

load in a safe condition and prohibit resumption ofload handling activities until approved by the Site General Manager.

]T!f$$}

MEM$h

$$k 4.3.1.a This SURVEILLANCE REQUIREMENT provides assurance.that the load

(

will not exceed the 24 ton'loid limit.

T7 3.3.1.h This specification s a re., ement s.

d in NRC SER dated May 15, 1981, related to t Spansiogt,hejS, #. Fuel Pool storage capacity. It is

~ pected that the onlyLcasks_reguired to be moved over the' Spent Fuel Pool

_the 24 ton fuel transfer' cask and possibly a cask required for. permanently j

1 removing fuel from thei Spent Fuel PoolE Use;of the cask for permanent -

iyeal of the[ fuel from the' Spent Fuel Pool (if not the 24. ton fuel transfer l

cas,k in its current configuration) would require NRC ' approval because' this

/ situation has not been fully evaluated,T lwith this specification is required to place the crane bh?b$i f

ociated y

load in'a safe condition and prohioit resumption ofload handling activities until approYed by the Site General Manageri NA 8

4.3.1.b This SURVEILLANCE REQUIREMENT providesl assurance that the 24 ton fuelTansfer cask is properly rigged ~and that only an NRC approved cask is

^

,g The ACTION associated.with thisipecification is required to place the crane i

load in'a safe condition and prohibit resumption ofload handling activities until approved by'the Site General Manageri 3.3.1'.c This specification reflects a requirement stated in May 15,1981 Safety Evaluation Relating to the Modification of the Spent Fuel Storage Pool and B3/4-13

b i*

BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS f

3/4.3 CONTROL OF IIEAVY LOADS BASES l

i requires ~ operability of the 24 ton fuel transfer cask safety catch device so that this backup feature is ~ vailable prior to handling the' cask over the SFP.

a bk sf l

The ' ACTION associated with this specification _is'requged,to place the crane i

load in a safe condition and prohibit resumption ofload handling activities until approved by the. Site General Manag 7 f%

l 4.3.1.c This surveillance provides assurance that the' trip mechanism is OPERABLE.

{0WWF NiiF ist3A l

4.3. L^d The surveillance required by this specification provides assurance that Containment Closure exists.

V T(

.k

%s h

P&yQf?Q

,i % %

/)

{e T ~

j j$

W u_

B3/4-14 u_______________

________._____________u

l-ef D2IG ROCK POINT PhlRMANENTLY DEFUELED TECHNICAL SPECIFICATIONS i

3/4.4 SEALED SOURCE CONTAMINATION BASES l

3A.1 The limitation on removable contamination for sources requiring leak testing j

meets the limits of 10 CFR 70.39 for sources containing plutoniugThe limitation provides assurance that leakage from sealed sou,rces coyered by the specification will not exceed allowable intake values.

Nh;[

8 Ag%

&e,00.1.

e The ACTION ensures that sources exhibitingleakage ari

.in accordance with NRC regulations.

47N E

j 4.4.1 For purposes of testing, the specification pateganzes sealed sources'hn6'two groups (in use, or stored and not in use), kith SURVEILLANCE REQUIREMENTS commensurate with theNobetdlitR[e in that group. Thc5c 50sicc5 which erchqucedi -

jcquirc nierc ficqncnt ic5;Ing. Scalcd sentcc5 wpgcentins[ufgkscd with 5 hic ldcd siicchhiil5Li (50ch 55 5cM idWithin i&dZii HiGiiitGiiiig e #r w w _.c_

._%.._,___.e..___

.s___s.

w.

uw v swwaj aiw uvuonuva wu tu uw n wu a2ms - sain uwja.cwu usuwaa unwy aaw avan G v~c d fi G Hi i!ic 5Iilc}dCd, j hdii55 -.

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i B3/4-15

_ _ _ _

ML20236T668

Text

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