ML20099D180

Proposed,Deleted TS 3/4.9.9 Re Refueling Operations - Containment Purge & Exhaust Isolation Sys

ML20099D180
Person / Time
Site:	Davis Besse
Issue date:	07/28/1992
From:	CENTERIOR ENERGY
To:
Shared Package
ML20099D176	List: ML20099D175 ML20099D177 ML20099D180
References
NUDOCS 9208050198
Download: ML20099D180 (19)

Text

e Docket Number 50-346 License Number NPT--3 =m p .

f>cr tal Number 2051 ml I l

Attnch'aent , ia V k 'V Page 10 gg INSTRLM(NTATION 1

3/a,3.2 $1F(TY $YSTEM IN$T2Uw(NTAT10N

$Af(TY f tATUR[$ ACTUATION SYSTEM IN$TRtF(NTATION LIMITING CONDITION FOR OP(RATION 3.3.2.1 The safety Features Actuation System ($FA$) functional units

! snown in Table 3.3 3 shall be OPERABLE with their trip setooints set consistent with the values shown in the Trio Setpoint column of Table 3.3 4 and with At$PON$t TIMr$ as shown in Table 3.3 $.

a#pt1CAllt,17Y: As shown in Table 3.b3. ,

ACTION:

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a. Witn a $FAS functional unit trip setpoint less conservative I

than the value snown in the Allowab's Values column of Table i

. 3.3 4. declare the functional unit iroptrable and apply the applicable ACTION recuirement r,f Table 3.3 3. until the func.

tional unit is restored to OPERAILE tratus with the trip setpoint adjusted consistent with the Trip Setpoint value.

b. With a SFAS functional unit inoperable. take the tction shown

, in Table 3.b3.

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$URVf!LLANCE REQUIREMENTS 4.3.2.1.1 Each $FAS functional unit shall be demonstrated OPERAILE by the perfomence of the CHANatt CHECK. CHAmtL CAL 184AT10N and CNANNEL FUNCTIONAL ft1T during the MODt1 and at the frecuencies shewn in Tabla 4.3 2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERA 8LE during the at power LHANNEL FUNCT!0!LAL ft3T of functional units affected ,

by bypass operation. The total bypass function shall be demonstrated CPEAA48,14t least once per 18 months during CHAmtL CAtllRATION tasting of each functions) unit affected by bypass operation.

4.3.2.1.3 The $AFETY FEATUtt$ AESPt*5t TIME of each 5FAS function shall be demonstrated to be within the limit et least once per 18 months.

toch test shall include at least one fvt4tional unit per function such that all-functional units are tested at least once every N times 18 months where N is the total number of redundant functional units in a specific SFA5 function as shown in the " Tota) he. of Units' Calumn of '

Tab 12 3.3 3. .

CAY 15 SE15t. UNIT 1 3/4 3 9 92000 PDR  % o$$$$$46-PDR P.

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INFORMATION n93

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. M=5 h SAFETT FEATURES ACTUATION SYSTEM INSTRUMENTATION $5b es b$

MINIMUM TOTAL NG. IMITS IMITS AFFLICABLE FIAGCTIONAL tmIT OF IMITS TO TRIP OPERABLE MODES AtTIEW w

I. IN3YRIMENT STRINGS

a. Containment Radiation - I Righ 4 2 3 2,2,3,4,6**** 303

b. Costairment Fressure -

Eigh 4 2 3 1, 2, 3 103 I

c. Centstament Fressure -

Nigh-Eigh 4 2 3 12,3 lug

d. SC5 Fressure - tow 4 2 3 1, 2, 3* 103

e. RCS Fressure - Low-Lov 4 2 3 1, 2, 3** tog m

f. 3V57 I4 vel - Low-tov 4 2 3 1, 2, 3 103

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2. OUTFUT LOGIC

s. Iscident Level 51: i

! Costalmeest Isolation 2 1 2 1,2,3,4,6aaaa it

b. Imeldest tevel 82:

Eigh Fressure Injection sad Starting Diesel Generators 2 1 2 1, 2, 3, 4 11 l

c. Imeldest Level 53:

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tav Fressure Injection Imeldest Level 14:

2 1 2 1, 2, 3, 4 is l 1, 2, 1, a i i

y Costelmeest Spray 2 1 2 iI

- e. Incident lavel 85:

@ Contaimeeat Sunep s Recirculatloa Fermissive 2 1 2 I, 2, 3, 4 II i 8

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INFORMATION .J

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., @ [ 5 ta TABli 3.3- 3 (Cont inued)

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m SAFETY FEATilRES ACTUATION SYSTEM INSTRtMEhTATION

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MINIMUM $QO

-j TOTAL Me UNITS (MITS AFFLICABI.E b$

4 FUNCTIONAL LMIT OF UNITS TO TRIP OPEstABIE MODES _ ACTIIM [

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3. MANUAL ACTUATION

a. SFAS (except Containment [

Spray sad EmerRency Sump Recirculation) 2 2 2 1,2,3,4,6**** 12

b. Containment Spray 2 2 2 1,2,3,4 12 l ' t'

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• 4. SEQUENCE i.r!C CHANNEI.S

gY' a. Sequencer 4 2*** 3 1,2,3,4 !Of l

, b. Essential Bus reeder j Breaker Trip (90%)  : 1 2***** 1,2,3,4 153

![5 c. Diesel Generator Start.

Lead Shed on Essential

aus (591) 2 1 2 1,2,3,4 153 i l

l 5. INTERIACK CEAIGfELS  ;

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jg a. Decay Ecat Isolation Valve 1 1 I 1,2,3 13 I l lg d. Pressor rer semier, 2 2 2 3- iA l t

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Doiket tJumber 50-346 Liccese Number NPT-3 ktial Numbet 20$1 Attachment l Page 13 TABLE 3.3 3 (Continued)

TABLE NOTATION Trip function may be bypassed in this MODE vith RCS pressure belov 1800 psig. Bypass shall be automatically removed when'RCS pressure exceeds 1800 psig.

Trip function may be bypassed in this MODE vith RCS pressure belov 600 psig, typass shall be automatically removed when RCS pressure 1 exceeds 600 psig.

One sust be in SPAS Channels il or $3, the other must be 1" Channels 02 or 64.

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• • • • ,N This instrumentation must be OPT.AAALE during CORE ALTERATIONS t,- I movement of irradiated fuel within the containment to meet the +

aquirements i of Tech. Spec 3.9.4.

All functional units may be bypassed for up to one sinute when luses.7 .

starting each Reactor Coolant Pump or Circulating Vater Pump.

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When either Decay Heat 1 solation Valve is open.

I The provisions of Specification 3.0.4 are not applicable.

t ACTION STATEMENTS

• ACrION 10 - Vith the number of OPERABLE functional units one less than the Total Number of Units, STARTUP and/or POVER OPERATION may proceed provided both of the following conditions are satisfied: *

a. The inoperable functional unit is placed in the tripped  ;

condition within one hour. For functional unit 4a the '

sequencer channel shall be placed in the tripped condition by physical-renoval of the sequencer module.

b. The Mininus Units OPERABLE requirement is set hovever, one additional functior.al unit may 'un bypassed for up to 2 ,

hours for surveillance testing per Specification 4.3.2.1.1. ,

i- ACTION 11 - Vith any component in the Output Logic inopereble. trip the  ;

o associated ccuponents within one hour or be e at least ROT

-STANDST vithin the next_6 hours and in COLD SIU!D0VN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

$ ACTIOt: 12 - Vith the number of OPERABLE Units one less than the T tal Number L of Units, restore the inoperable functional unit to 0PERA4LE l

status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 90T STANDBY vithin the l-next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SRUrD0VN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, ACTION 13 - a. -Vith less than the Minimum Units OPERABLE and reactor coolant pressure 1433 psig, both Decay Beat Isolation ve,1ves (D811 and D612) shall be verf fled closed.

' DAVIS-RESSE, UNIT 1 3/4 3-12 Amendeont No. 28, 27.- [

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Docket 11 umber 50-346 (

c License Number 11PF-3 >

Serial Number-2051-Attachment  ;

Pege 14 insert for Table 3.3-3, Notation-'****' ,

This instrunentegion, or the containment purge and exhaust system i

noble gas monitor (with the containment purge and exhaust system in operation), n.ust be OPERABLE during CORE ALTERATIONS or movement of irradiated fuel within containment to meet the requirements of Technien1 Specification 3.9.4.. When using the containment purge and i exhaust system noble gas monitor, STAS is not required to be OPERABLE

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s i INFORMATION N ^* Q

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SAFETI FEATURES ACTUATION SYSTDI INSTRUMENTATION SURVEILLANCE RE0titREMENTS fi 5==[ $ *-

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o- CEANNEL MODES IN VHICH $=$ l j: g CNAsGIEL  : CHANNEL FUNCTIONAL SURTEILtANCE EQO  !

l' Q FUNC710NAL UNIT CSECK CALIBRATION TEST REQUIFED 0$ I

1. INSTRUMENT STRINCS l', .

a. .Contalmeent Radiation - Eigh 5 R N 1.2.3.4,65 l 1 l

i: b. Containment Pressure - Eigh 5 R N(2) I, 2, 3 l

c. .Containeemt Pressure - Eigh-Eigh 5 R N(2) I, 2, 3  :

i d. BCS Pressurs - Low .5 R 'N 1, 2, 3 l

j. e. RCS Presisere - Low-Low 5 R N t , 2, 3 E. BUST' Level - Low-Low S P N 1, 2, 3  ;

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2. DUTFtri IACIC i

a. Incident Level its containeent 1,2,3,4,65 Isolation 5 R M  ;

i b. Incident Levs.1 92: Nigh Fressure Injection and Starting Ctesel ,

Cenerators 5 R M 1, 2, 3, 4

c. Incident Level 13: tav Fressure  :

5 R M 1, 2, 3, 4 Injection .

I d. Incident Level 54: Containment

$ Spray $ R H 1, 2, 3, 4 ,[

l I e. Incident Level 85: Containsect  !

susp Recirculation Fermissive 5 N N 1, 2, 3. 4

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. ,o 3. HANUAL ACTUATION i

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.me y a. .SFAS (Except Containment Spray NA NA M(1) I.2.3.4.68 l g and Emergency Seep Recirculation) ,

l Containment Spray NA N4 M(1) 1, 2. 3 l

b.

j. k NA N I. 2 i. 4 e

4. secuencE tociC CuannetS S

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CHAMfEL HOUES IN WifICl yz$

M. C!!ANNEl. CHANNEL FtmCTIONAL SISVEILiANCE M

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FilHCTIONAL UNIT CflECK CALIBRATION TEST _

SEQUIRED $$

S. INTERP 0CK CliANNELS

a. Decay Heat Isolation Valve S R ** 8, 2, 3 bi l

b. Pressudzer Feater S R ** 3 ##

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r3 TABLE NOTATION

(1) Hanual actuation switches shall be tested at least once per 18 monthe during shutdown. All ot tie r circuitry associated with manual safeguards actuation stea l1 s eceive a CIIANNEL FUNCTIONAL 1EST at least once per 31 days.

) (1) 11 e C11ANNEl. filNCTIONAI. TEST shall inc lu.le exerc i s ing t i..- transraitter by applying either - a c a.ua o r

7. recumure to the appropriate side ..f the transmitter.

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~. # ..6vesitance r eq..i r emen t s ..e S.:. t s. n 4.9.4 ... ply .t.. sing . .> s e alterattons or movement . a s . . ... t .:.s l '

• ( f sel within time .'ont a i nment . p_ _ _ . . _ _ _ _ __ . _ _ _ , . . . _ - -

ga uhen either Detay lleat Isolation Valve is opes:. p\ \

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Docitet Number 50-346 v License Number IJPF-3 Serial 11 umber 2051 Attachment Page 17 Insert for TS Table 4.3-2, Table tiotation 'P These surveillance requirements in conjunction with those of Section 4.9.4 apply during CORE ALTERATIONS or movement of irradiated fuel within the containment only if using the SFAS area radiation monitors listed in Table 3.3-3, Items la, 2a, and 3a, in lieu of the containment purge and exhaust system noble gas monitor.

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( c Doc'tet Number 50-346 l Lic ense Number NIT-3 Setial Number 7051 At t achtnen t Page 18 REPUELING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CONDIT!0N FOR OPERATION

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3.9.4 The containment penetrations shali ta in the following status:

a. The eculpment coor closed and i' eld in place by a minimum of four bolts,

b. A minimum of one coor in each airlock closen, and

c. Each penetration providing direct access from the containment atmosphere to the outstee atmosphere shall be either:

1. Closed by an isolation valve, blind flange, or manual valva, or c-

2. Be capable of being closed by an OPERABLE (automatil', .

I containment purge and exhaust isolation valTe, APPLICABILITY: Durirg CORE ALTERATIONS or movement of irradiated fuel within tM containment.

ACTION:

0. .

With the requirements of the above specification not satisfied, immediately i suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not

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SURVEILLANCE REQUIREMDff3 4.9.4 Each of the above required containment. penetrations shall be determined to be either in its closed [isoitted condition or capable of being7 closed by an OPERA &LEEtaln % containment n.rge and exnaust valv Qithin 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to thFstart c' and at least once per 7 da 59during CORE ALTtRATIONS or povement of irradiated fuel in the containmen y:

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a. Verifying the penetrations are in their isolated condition, or b, fapplicable s portions of Specification 4.6.3.1.2.esttrg - -i g the containment our DAVIS.BESSE. UNIT 1 3/4 9 4

4 . Docket Number 50-346 l o' License Number NPP-3 ,

. Serial Notaber 2051 l Attachment Page 19 l 1

Insert for TS 3.9.4-ACTION  ;

' b.' Vith the containment purge and exhaust isolation system inoperable, '

close each of the purge and exhaust penetrations providing direct acctss from the containment atmosphere to the outside atmosphere.

c. The provisions of Specification 3.0.3 are not applicable.

- Insert for TS 4.9.4.b Verifying that with the containment putga and exhaust system in operation, and the containment purge and exhaust system noble gas -

monitor capable of providing a high radiation signal to the control  ;

room,-that-after initiation of the high radiation signal, the containment purge and exhaust isolation valves-can be closed from'the control room, or

- If using the $FAS area radiation moisitors, verifying that on a Containment Purge and Exhatat Isolation tett algnal, each purge and exhaust isolation valve automatically ac mates to its isolation position.

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I Docket thimber 50-346

. ' Licent;e Number NPF-3 Set l'al thimber 20$1 I

' Attachment I Page 20 l.

CONTA!NMENT SYSTEMS y PFf*t,-

I 3/4.!. CONTt!4 MENT ISOLATION VALVEi ,

i LIMIT'.'G CONDITION FOR OPERATION CC#Y 4-l l

3. 6. 3.1 All containment isolation vtives shall be OPERABLE with isolation times less tnan or eoual to require: isolation times.*

i ApFLI: ABILITY: MODES 1, 2, 3 and 4.

ACT 10'.:

With cne or more of the isolation valve (s) inoperable, either:

i. Restore the inoperable valve (s) to OPEPABLE status witn3r 4 l nours, or l

"; Isolate eacn affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use Of at least one tienctivated automatic valve secured in the isolation position, or

": . Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or

. Be in ht least HOT STAN0BY witnin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, jSURVE:LLANCE REOUIREMENTS

4. 6. 3.1.1 The isolation valves shall be demonstrated OPERABLE prior to returnin: '

the valve to service af ter maintenan:e, repair or replacement worr tnat could I af fe:t tne valve's perfomance is perfomed on the valve or - associate l

actuator, control or power circuit by perfomance of a cycling test an:

verification of isolation time.

• Surveillance testing of valves M5100. M5101, IC511A and IC511E is not reouire:

prior to entering MODE 4 Lut shall ce perfonned prior to entehng MODE 3.

• • Tne provisions of Specification 3.0.4 are not applicable. Sele:ted valves may be opened on an intermittent easis under administrative controis.

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DAVii-BESSE, UNIT 1 3/4 6-U knens ment No. 'C

/ Dr>elet Number 50-346 License fiumber NPF-3 Serial !Jumber 2051 Attachment

, Page 21 jq, .,,,, ,

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lfCONTAINMENTSYSTEMS

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SURVEILL A' ICE REOUIREMENTS (Continued)

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4. 5. 3.1. 2 Each isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a containment isolation test signal, each automatic isolation valve actuates to its isniation position.

! b. Verifying that on a Containment Purge and Exhaust isolation test signal each Purge and Exhaust automatic valve actuates l

to its isolation position, l

i;4.6.3.'.3 The isolation time of each power operated or automatic valve shall ,

ll be detemined to be within its limit wnen testec pursuant to Specification 4.0.5.

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l Amenoment Fo, 147 DAV!5-BE55E. UNIT 1 3/4 6-15

i D/cket Numtiet 50-346 License Number NPP-3 Serial Number 2051 Attachment Page 22 g ~ N PEP.'ELING OPERATIONS CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPEPATION 3.9.9 The containment purge and exhaust isolation system snail te OPERABLE.

APPLICABILITY: MODE 6.

ACTION:

With the containment purge and exhaust isolation system in0perable, close each of the purge and exnaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

The provisions of specification 3.0.3 ar'. not applicable.

SURVEILLANCE RE0VIREMENTS 4.9.9 The containment ourge and exhaust isolation system snail be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at i least once per 7 days during CORE ALTERATIONS by verifying tnat contain-ment purge and exhaust isolation occurs on manual initiation anc on a high radiation test signal from the safety Features Actuatien System N

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,, DAVIS-BESSE,'JNIT 1 3/4 9-9

_.m... _ _ .

_. ._,3

' s i Docket Number 50-346 >

License Number NPT-3 Serial Number 2051 Attachment Page 23  ;

3/a.9 REFUEL!!S OPEP.aTIONS P.ASES 3/4.9.1 BORON CONCENTRATION t The limitations on reactivity conditions during REFUELING ensure that:

1) the reactor will ren.ain subcritical' during CORE ALTEMTIONS, and 2) a  :

unifom boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. These limita-tions are consistent with the initial conditions assumed for tne boron dilution incident in the accident analysis.

3/4.9.2 INSTRUMENTATION i

The OPERABILITY of source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the

- reactivity condition of the core.

3/4.9.3 DECAY TIME The minimu'n requirement for reactor suberitical!ty prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the i short lived fission products. This decay time is consistent with the assumptions used in the safety analystb.

3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPEMBILITY ensure that a release of radioactive material within containment will be restricted-from leakage to the environment. The OPEMBILITY and closure i requirements are sufficient to restrict radioactive material release from a fue) element rupture based upon the lack of conta1, ment pressurtra-tion potential while in the REFUELING MODE.

• thset 4 nod: 3/4.9.5 COMMUNICATIONS b The requirement for comunications capability ensures that refueling 3 station perscnnel can be promptiv infonned of significant changes in tho facility status or core reactivity t.ondition during CORE ALTERATIONS.

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DAVIS-8 ESSE, UNIT 1 8 3/4 9-1 i

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i. , , Docket llumber $0-346

/ License liumber IJPF-3 Sorial fiumber 2051 Attachment Page 24 Insert for TS 3/4.9.4 Bases Vith the containment purge and exhaust system in operation, a high radiation signal received from the containment purge and exhaust system nobic gas monitor vill cffectively automatically contain the release by ,

shutting der the containment purge systera supply and exhaust fans and ,

closing their inlet and outlet dampers. On a valid signal, the control  ;

room operator vill then manually close the containment purge and i exhaust isolation valves. Therefore, the uncontrolled release of  ;

radioactive material from the containment to the environment vill be testticted.

Likewise, use of the SFAS area tadiation monitors provide an automatic ,

containment isolation signal on high radiation, restricting the l uncontrolled rtlease of radioactive material from the containment to the environment. l l

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/ Docket Number 50-346 License Numbei NPT-3 Serial Number 2051 Attachment Page 25 REFUELING OPERATIONS BASES 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITT The OPERABILITY requirements of the hoist bridges used for movement of fuel assemblies ensures that: 1) fuel handling bridges vill be used for movement of control reds and fuel assamblies, 2) each hoist has sufficient load capacity to lift a fuel elemant, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lif ting operations.

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of losos in excess of the nominal veight of a fuel assembly in a failed fuel container over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release vill be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks vill not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 COOLANT CIRCULATIO!!

The requirement that at least one decay heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the vater in the reactor pressure vessel belov 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two DER loops OPERABLE vhen there is less than 23 feet of water above the core ensures that a single failure of the operating DER loop will not result in a complete loss of decay heat removal capability. Vith the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for cora cooling. Thus, in the event of a failure of the operating DER loop, adequate time is provided to initiate emergency procedures to cool the core.

"O 3/4.9.9 CONTAINKEtrf ~

PURGE AND EIRAUST ISOLATION SYSTEM p/ c~,

/ The OPERABILITY of this system ensures that the containment purge and exhaust

/ renetrations vill be automatically isolated upon detection of high radiation

! levels within the containment. The OPERABILITT of this system is requited to k restrict the telease of radioactive material from the containment atmospnere to ,

\s the enstronment. ___, _,

3/4.9.10 and 3/4.9.11 VATER LEVEL - REACTOR VESSEL AND STORAGE POOL 1

phe restrictions on minimum vater level ensure that ruf ficient water depth is available to remove 99% of the assumed 10% iodine gap activity released f rom the ruptere of an irradiated fuel assembly. The minit:ua vater depth is consistent vith the assumptions of the safety analysis.

DAVIS-BESSE, UNIT 1 5 3/4 9-2 Amendment No. 381 I25

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/ Dotket fJumber 50-340 1.icente fJumber fJPF 3 M t ial fJumber ?O51 Attathment Page .%

INDEX t.lMITING CONDITIONS FOR OPTRATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BO RO N CONCENT RAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 9- 1 3/4.9.2 INSTRUMENTATION.......................................... 3/4 9-2 3/4.9.3 O E CA Y T 1 HE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/49-3 3/4.9.4 CONT AINMENT P ENET RATI ONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 9-4 3/4.9.5 COMMUNICATIONS........................................... 3/4 9-5 3/4.9.6 FUEL HANDL ING BRIDGE OPERABILITY . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-6 3/A 9.7 CRANE TRAVEL - FUEL HANDLING BUILDING. . . . . . . . . . . . . . . . . . . 3/4 9-7 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION g'gpN~ Al l Wa t e r L e v e l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 9- 8

% Low Water Leve1.......................................... 3/4 9-Ba

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3/4.9.9 (CONTAINMENT PURGE AND' EXHAUST ISOLATION SYSTEM;..........

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3/4 9 9 l 3/ 4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4.9.11 STORAGE POOL WAT ER LEVEL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 9-11 3/4.9.12 STORAGE POOL VENTILAT10N................................. 3/4 9-12 3/4.9.13 SPENT FUEL 900L FUEL ASSEMBLY STORAGE. . . . . . . . . . . . . . . . . . . . 3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION L IMITS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 10- 1 3/4.10.2 PHY S I CS T E5TS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 10- 2 3/4.10.3 RE ACT OR COOLANT L00P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 10- 3 3/4.10.4 SHUT 00WN MARGlH.......................................... 3/4 10-4 DAVIS-BESSE, UNIT 1 Vill Anenament ho. 2B, 230

y Docke't Number 50-346 Ocense Number NPF-3 Serial Number 20S1 Attachment l Page 27 i INDEX BASES 1

SECTION PAGE l i

3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY. . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9 2 l 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING. . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 IN R _ 3/4.9.8 x COOL ANT C I RCUL ATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 9- 2 y __ -

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3/4.9.9 (CONTAINMENT t PURGE AND EXHAUST ISOLATION s SYSTEM.J..Z ...... B 3/4 9-2 l i 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND T STORAGE P00L............................................ B 3/4 9-2 / i 3/4.9.12 STO RAG E POOL V E NT I L AT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 '9- 3 3/4.9.13 SPENT FUEL POOL FUEL ASSEMBLY STORAGE..................... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT. INSERTION AND POWER DISTRIBUTION LIMITS..... B 3/4 10-1 3/4.10.2 PHYSICS TESTS............................................. D 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS.................................... 3 3/4 10-1 3/4.10.4 S HUT DOW N MAR G I N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 10- 1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 L I QU I D E FFL UENT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 1 1 - 1 3/4.11.2 GAS EQU S EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 11 - 3 v

3/4.11.3 SOL ID RADI0 ACTIVE WASTE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11- 6 3/4.11.4 TOTAL 00SE................................................ B 3/4 11-7

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t 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING I

3/4.12.1 MON ITO R I NG P R0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 12- 1 3/4.12.2 LAND USE CENSUS........................................... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM........................ B 3/4 12-1 DAVIS-BESSE, UNIT 1 XI!! --Amenament No. 85.J30. J M L _ _ . _ . .

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