Text

Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS
	ML20154E562
Person / Time
Site:	Fermi
Issue date:	09/28/1998
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20154E556	List: ML20154E562; NRC-98-0122, Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl;
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	NUDOCS 9810080232
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SUMMARY

DISPOSITION MATRIX FOR FERMI-2 RETAINED / (a)

CURRENT NEW CRITERION BASIS FOR INCLUSION! EXCLUSION TS NUMBER TITLE TS NUMBER FOR PROPOSED NEW LOCATION FOR THE RELOCATED REQUIREMENTS INCLUSION 3/4.3.6.18 ' Rod Block Morwtor 3.3.2.1 Yes-3 Prevents conthuous withdrawal of a high worth control rod that would challenge the MCPR Safety l_imit and 1 percent cladding plastic strain fuel design hmit.

3/4.3.6.25 APRM Relocated No Refer to the Discussions of Change *R.1" for ITS Section 3.3.2.1, " Control Rod Block Instrumentation.* for relocation justification and location.

3/4.3.6.3* Source Range Monitors Relocated No Refer to the Discussions of Change *R.2* for ITS Section 3.3.2.1,

Control Rod Block Instrumentation.* for relocation justification and location.

3/4.3.6.4* Intermediate Range Monitors Relocated No Refer to the Discussions of Change *R.3" for ITS Section 3.3.2.1, " Control Rod Block instrumentation.* for relocation justification and loc 3 ton.

3/4.3.6.5" Scram Discharge Volume Relocated No Refer to the Discussions of Change *R.4* for ITS Section 3.3.2.1, " Control Rod Block Instrumentation," for relocation justification and location.

3/4.3.6.6* Reactor Coolant System Recirculation ficw Relocated No Refer to the Discussions of Change *R.5* for ITS Sectbn 3.3 S.I.

Control Rod Block Instrumentation,* for relocation justification and location.

3/4.3.6.75 Reactor Mode Switch Shutdown Position 3.3.1.2 Yes-3 Ensures all control rods remain inserted when reactor is assumed to be shutdown.

3/4.3.7 Morutoring instrumentation - -

3/4.3.7.1" Radiation Monitoring instrumentation - -

3/4.3.7.1. ' " Control Center Normal Makeup Air Radiation 3.3.7.1 Yes-3 Actuates to maintain habitability of the control room so that operators can remain Morutor in the control room following an accident. As such, it mitigates the consequences of an accident by allowing operators to continue accident mitigation activities from the control room.

3/4.3.7.1.2 < Relocated by Amendment 115 > - - -

3/4.3.7.2 < Relocated by Amendment 115 > - - -

3/4.3.7.3 Meteorological Monitoring Instrumentation Relocated No See Appendix A, *R.2". Relocated to the TRM.

3/4.3.7.4 Remote Shutdown Monitoring instrumentation 3.3.3.2 Yes-4 Retained as directed by the NRC as it is a significant contributor to risk reduction.

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SUMMARY

DISPOSITION MATRIX FOR FERMI-2 RETAINED / fa)

CURRENT NEW CRITERION BASIS FOR INCLUSION / EXCLUSION TS NUMBER TITLE TS NUMBER FOR PROPOSED NEW LOCATION FOR THE RELOCATED REQUIREMENTS INCLUSION 3/4.3.7.5 Accident Monitoring Instrumentation 3.3.3.1 Yes-3 Regulatory Guide 1.97 Type A and Category 1 variables retained. Also refer to Discussion s of Change *R.1* for ITS Section 3.3.3.1. "PAM Instrumentation." for individual relocation justification and location 3/4.3.7.6 Source Range Monitors 3.3.1.2 Yes Does not satisfy the selection criteria, however is being retained because tlw NRC considers it necessary for flux monitoring during shutdown. startup, ano refueting operations.

3/4.3.7.7 < Relocated by Amendment 115 > - - -

3'4.3.7.8 < Relocated by Amendment 115 > - - -

3/4.3.7.9 < Relocated by Amendment 62> __ __ __

3/4.3.7.10 < Relocated by Amendment 115 > - - -

3/4.3.7.11 < Relocated by Amendment 82 > __ __ __

3/4.3.7.12 Explosive Gas Monitoring Instrumentation Relocated No See Appendix A. *R.6". Relocated to the TRM.

3/4.3.8 < Relocated by Amendment 71 > __ __ __

3/4.3.9 Feedwater/ Main Turbine Trip System Actuation 3.3.2.2 Yes-3 Actuates to limit feedwater addition to the reactor vessel on feedwater controper instrumentation failure consistent with safety analysis assumptions. Limits neutron flux peak and thermal transient to avoid fuel damage.

3/4.3.10 < Not utdized > __ __ __

3/4.3.11 Appendix R Attemative Shutdown instrumentation Relocated No See Appendix A, "R.7*. Relocated to the TRM.

3/4.4 REACTOR COOLANT SYSTEM 3.4 3/4.4.1 Recirculation System 3/4.4.1.1 Recirculation Loops 3.4.1 Yes.2.3 Recirculation loop flow is an initial condition in the safety analysis.

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OG3 ELECTRICAL POWER SYSTEMS I THERMAL OVE u;g wrTim V MOTOR-OPERATED VAL

/ N' h LIMITING CONDITI,0N F02 OPFRATION l

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l lk 3.8.4.3 Th thermal overload protection of each alve used in safety systems shall be ERABLE.

APPLICA LITY: Whenever the motor operated alve is required.to be OPERABLE.

l ACI ON:

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l Vith the thermal overload protecti for one or more of the above required /

l palvesinoperable, continuously ass the inoperable thermal overload wit n 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected alve(s) inoperable and apply the apprope ate ACTION statem.ent(s) for the af ected system (s).

i SURVEILLANCE REQUIREMENT l 4.8.4.3 The thermal verload protection for the above requir d valves shall be demonstrated OP BLE by the performance of a CHANNEL CA BRATION of a ,

representative s pie of at least 25% of all thermal over ads for the above required valves t least once per 18 months, and by perf .ance of a CHANNEL t'I CALIBRATION a /the affected thermal overload followin .ny reintenance x . activity whi could affect the performance of that Er:21 load. j l

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FERMI UNIT 2 1 REVISION 1, 09/25/98l

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Y DISCUSSION OF CHANGES RELOCATED CTS INCLUDED IN APPENDIX A'TO THE SPLIT REPORT RELOCATED' SPECIFICATIONS

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-h DISCUSSION OF CHANGES RELOCATED CTS INCLUDED IN APPENDIX A TO THE SPLIT REPORT RELOCATED SPECIFICATI0NS'-

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. DISCUSSION OF CHANGES '

RELOCATED CTS INCLUDED IN APPENDIX A TO THE SPLIT REPORT-i

, .I RELOCATED SPECIFICATIONS 4

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DISCUSSION OF CHANGES.

RELOCATED CTS INCLUDED IN APPENDIX A TO THE SPLIT REPORT O RELOCATED SPECIFICATIONS R.5 Not used.

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FERMI - UNIT 2 3/4 3-54 Amenoment No. 83,115 i i

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FERMI - UNIT 2 3/4 3 56 Amenament No. 115 ,

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FERMI - UNIT 2 3/4 3 70 Amendment No. 83,115 I

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DEFINTTIONS " 2 ' ' Y )

V TABLE 1.2

^^=T 06 Cohoi--- $ {A100ES _

MODE SWITCH AVERAGE REACTOR.

_,fa TL ; POSITION COOLANT TEMPERATURE i

1. POWER OPERATION Run Al Any temperature

.. dle M (s

2. STARTUP i A Startup/ Hot Standby Any temperature i 3. HOT SHUTDOWN l lla Shutdown8 ,*** > 200* F

4. COLD SHUTDOWNNN Shutdown 8 ,88,*** M s 200* F****

5. REFUELING

bI Shutdown or Refue 8

-; 47 T, h l

8 l- fee Nkm (8The reactor Refuel mode position to test switch the may switchbeinterlock placedfunctions in the Run, and Startup/

related Hot Standby, 3,'0 L i instrumentation provided that the control rods are verified to remain fully i

% inserted in core. cells containing one or more fuel assemblies by a second l [ licensed operator or other technically qualified member of the unit technical {

i .

us taff. / l l 88 The reactor mode switch may be placed in the Refuel position while a single Qvn@Ucah' control rod drive is being removed from the reactor pressure vessel per 3.(04 Specification 3.9.10.1. ft of mwcD '

p@ *N:1 i- t'e seta- ==" "'tt t% vessel head closure bolts less than fullyf

./t, i i

Vensioned or with the head removed. l. ;

- !ee 5;::i:1 Test :xc.,,Uun 3.40.2 ano a.i .0. - - ~

ca sp;bh **The reactor mode switch may be placed in the Refuel position while a single j,m ,.3 control rod is being recoupled or withdrawn provided that the one-rod-out I gg, g interlock is OPERABLE.

- - - taa taadel T::t ac.g.a. 0.1".7. - - -- A,/7 ,l j

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fly kip QQ A'IG A o p . 1 2. L , m G n u M l.56mpanmTims i l t.'l Rawad

.lt FERMI - UNIT 2 1-10 Amendment No. JJ, JJJ

, 116 PAGE OF 14 pu(

$fGC tPycgqio rJ .1 o l APPLICABILITY (Mso n -Toeci[icofim C5)

SURVEILLANCE RE0UTREMENTS SR 3e.1 4M L.neill.[.. SQ;; ire .; t; shall ' ' se Ars!;eae.*/m) _.

. o. met curing Ine ....... _ 3, 00C 0 GONHHGNG-cr othertconditiontjspecifiedj or individual -"'- #-

"4+4^^CLW fee-epece64ao

*"U:'::t. unless otherwise stated in ::; tr# Jid:;l 5:r""'W^tMg Ug $gg_7 3,o ,_ g ( .2 54'3.o,2_ ' " " X n surveils ce nequi m . snais oc v s iv. uwunm Miw 6... .r aurveil ance'interv with a maxim allowable ext sion not to exce 25 L.

perce of the sp ified surveill nee interval. or the purpose o the sixth j,9 refu ing outage those Surve11 nce Requiremen tJ/2-2 are ex ad d to the da e snacified in a table )

listed orLTable Q,piGT 3,o

.0.2-1 and; 4] g O

54'5.0 3 493Aa1 re to perro a surveillanc Requiressen1; wiInin he allowed SUr7H11 ce interval, fined by Spa ication 4.0.2, s

{ 'noncomp ante wi+h 4km DFDARflTTv em ,_4r-- =+e far a f4 constitute A.g 1

+4an rnaditi fo Ine A t &WM s dis. ..u aus ey "a $ 6su' l u at tur

@Def'at ime it i On.[/Yhelme identified tha 's imiu7T a Surveillance he ACT N requirements quirement has no been perfo y be delayed f up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months permit the i omple on of the surv lance wher. th a

r.T 1 renutrements a 1.c= +han 24 llowahle outman ime limits of h urs / C . M -- ^-,' -+r da -a+

j hr: t: 5: ;: ':r:I :: '::;rd!: : ;;'.; : .S .-

M-W )

""b ctrrm.sonddion ... all not m;m[;

be made anless aen:= .. m.= ==kNET m:e :-m !:-

the Surve lance Requiremen s) associate i with the siting Conditi i for Operation h a been performed ithin the applica e surveillance terval or as et tvise specified. his provision i

shall t prevent pass through or in roar!nual cnuntT_ p .. c.nu4r.d with ACTION re ir:= nts f .11 N.5EET 3,0-11)

.0.T'~1furveillance Requirements for inservice inspection and testing of ASME ode Class 1, 2, & 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves Su- shall be performed in accordance with Section XI of the ASME

$gdhakgn Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50. Section 50.55a(g), except where specific written

)

5.5 relief has been granted by the Connission pursuant to 10 CFR 50, Section 50.55a(g)(s)(1).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

O FERMI - UNIT 2 3/4 0-2 Amendment No. JJ. JJ J75.124 PAGE 6-Oc la Nl

I k%tflL4f1HO 3.0 j/ TABLE 4.0.2-1 P suavEIttAdTrsT INTERVALS FYTENDED TO S/PTEMBER iM 1998 kJC 0 l SURVEILLANCI UIREMENT DESCRIPTI 4.3.1.1, Tab 4.3.1.1 1, Item 3 RPS Rx stham 0 Press Nigh cat.

4.3.1.1, T e 4.3.1.1 1, item 4 RPs RR Low W er Level - Level 3 cal 4.3.1.1, to 4.3.1.1 1, Item 6 RPs Main 5 em Line Radiation Nigh cal 4.3.1.1, able 4.3.1.1 1, Item 7 RPs D Pressure Migh cal 4.3.1.3 Table 4.3.1.1 1, item 2.b APRM F Blased Thornet Pouer - Nigh 4.3.1. , Table 4.3.1.1 1, Item 2.c APRM Red heutron Flux - Migh 4.3. . Table 4.3.2.1 1, Item 1.a.1 Pri ont Isolation Actuation RX Water Low - Level 3 cet 4.3 .1, Table 4.3.2.1 1, item 1.a.2 Pr Cont Isolation Actuation RX Water Lew

Level 2 cal ~

4. 2.1, Table 4.3.2.1 1, item 1.s.3 i Cent Isolation Actuation RX Water Law - Level 1 ca

.2.1. Table 4.3.2.1 1, item 1.b Pri Cent Isolation Actuation Drywell Press Nigh cal

.3.2.1, Table 4.3.2.1 1, Item 1.c.1 Pri Cent Isolation Actuation Main Steam Line Radi on Nigh cel 4.3.2.1, Table 4.3.2.1-1, Item 1.c.2 Pri cont Isolation Actuation Main stems Line P Low cat 4.3.2.1, Table 4.3.2.1 1, item 1.c Pri Cent isolation Actuation Mein Stems Line F Nigh cal 4.3.2.1, Table 4.3.2.1 1, item 1. Pri Cent Isolation Actuation Main stese Li weiel Temp. Nigh cal 4.3.2.1, Table 4.3.2.1 1, Item e Pri Cont Isolation Actuation Condenser P Migh cal 4.3.2.1, Table 4.3.2.1 1, it .f Pri cent Isolation Actuation Turbine Rt . Area Temp. High cal 4.3.2.1, Table 4.3.2.1 1, it 1.h Pri Cent Isolation Actuation Manuel I lation F mettonal 4.3.2.1, Table 4.3.2.1 1, t 2.d RWCU SLCS initiation channel func anel test 4.3.2.1, Table 4.3.2.1 1, tem 2.e RWCU Isolation Rx Water Low Level Level 2 chamel est 4.3.2.1, Table 4.3.2.1 1 Item 5.s RNR $/D Cooling Rx Water Level

Level 3 cat 4.3.2.1, Table 4.3.2.1 , Item 5.c RNR 5/D Cocting km manuel int tion f mettonal test 4.3.2.1, Table 4.3.2. -1, item 6.b sec. Cont. Isolation - 0 Press Nigh channel cal 4.3.3.1, Table 4.3. 1 1, item 1.b C5 Drywell Press Nish Cal 4.3.3.1, Table 4. .1 1, item 2.b LPCI Drywell Press Nigh l 4.3.3.1, Table 4 .3.1 1, Item 3.s MPCI RPV Low Level 2 &

4.3.3.1, febte .3.3.1 1, item 3.b HPCI Drywell Press N Cat 4.3.3.1. Tabt 4.3.3.1 1, Item 4.s ads RPV Low Level 1 at 4.3.3.1, Tab 4.3.3.1 1, item 4.f ADS RPV Low Level Cat 4.3.3.1, i le 4.3.3.1 1, item 4.h ADS Drywell Pre e Nigh Rypass fleer 4.3.4, O 4.3.4, 4.3.4.

able 4.3.4'1, item 1 Table 4.3.4*1, item 2 4.3. 1, Table 4.3.5.1 1, Item a RPV Low Water vel 2 Cal (ATWS)

RPV Press Mi ATWS Logic RPV Low L Cat (ATW5) tem Functional Test 1 2 Cat (RCIC) 1 4.3 .1, T able 4.3.5.1-1, item b RPV Ni evel 8 Cal (RCIC)

4. 5.2 RCic L ic System Functional Test

.3.7.5, Table 4.3.7.5 1, Item i RPv P ess Cal Accident Mon.

.3.7.5, Table 4.3.7.5 1, Item 2.s RPV uel Zone Level Cal Accident Men 4.3.7.5, Table 4.3.7.5 1, Item 2.b *RP Wide Range Level Cat Accident Mon 4.3.7.5, Table 4.3.7.5 1, item 12 MT High Range Red Monitoring Cat Accident Mon.

4.3.7.5, Table 4.3.7.5 1, item 16 CTMT Isolation Valve Position Cat Accleent Mon 4.3.9.1, Table 4.3.9.1 1, item a RPV High Water Level 8 Cal FW/ Main Turbine Trip '

1 4.3.9.2 FW/ Main Turbine Trip LSFT 4.3.11.1, Table 4.3.11.1 1 Item 7 Att S/D system Rx Water Levet instrment operabi ty 4.3.11.1, Table 4.3.11.1 1, Item Alt S/D system Rx Press instrtment operability l

4.4.2.2.b SRV Low Low set Pressure setpoint Cal and LSF l 4.5.1.d.2.a ADS system Functional Test 4.6.3.2 Primary Contalrnent Isot Valve operability

4. 7.4. c.1 RCIC F mettonal Test 4.8.4.2.a.1.s Pri. Cont. Pen. Conductor overcurrent D ices F metional Test 4.8.4.2.s.).b Pri. Cont. Pen. ConchJctor overcurrent evices functional Test ,

)

l FERMI - UNIT 2 3/4 0-4 Amendment No. 106. 108. 124 D 12 PAGE OF g

SpoiRea hw 3.0 O

Page Removed in Rev 1 O l Q Page 10 of 12 Revision 1, 09/25/98

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.5/EC(FrcADord 3/O I

[ TABLE 4.0.2-2 L ;

SURVEILLANCEIESTINTERVALSEXTENDEDTOOdOBER 18. 1998 f,/p SURVEILLANCE REOUIRE NT' DESCRIPTION 4.1.3.5.b.2 Ca Accinutator Inteert Test (Check Velve Leekage)

\I 4.1.5.d.1 SLCs operabitity 1nt t tot ten 4.1.5.d.2 . SLCs pump notlef Voi operability 4.1.5.d.3 SLCs flew poth tretion 4.3.1.1, febte 4 .1 1, Item 11 bps as Mode suit shutdown positten functionet 4.3.1.2 RPs Logic system unction Test 1 4.3.2.1, Table .3.2.1 1, item 6 e 1 4.3.2.2 sec. Cent. les ten as Water Lev Level - Level 2 col 4.3.3.1, 1 e 4.3.3.1 1, item 1.s 1setetten Ac tien Inst. LsFT }

Cs RPV Low L L 1 Cet 4.3.3.1, T le 4.3.3.1 1, Item 1.c Cs As St Press Law Cet {

4.3.3.1, le 4.3.3.1 1, Item 1.d Cs Manuel nittetten 4.3.3.1 able 4.3.3.1 1, stem 2.s 4.3.3. , Table 4.3.3.1 1, Item 2.c LPCI aPV ew Level 1 Cet LPCI steen Dame Press Low Cet 4.3.3 , Table 4.3.3.1 1, item 2.d LPCI Low Level 2 Cal 4.3, .1, febte 4.3.3.1 1, item 2.e 4 .1, fatte 4.3.3.1 1, Jtem 2.h LPC au steen Deme Press Low Cal 4 .3.2 L Manuel initiation Logic system Feettenet Tests )

3.3.3(a) CCS Response flee Tests 1

.3.6, . Table 4.3.61, Item 5.b 4.3.6, f ebte 4.3.6-1, item.7 Scram Disc Vol. Trip Bypees funct. Test 4

4.5.1.c.1 as Nede switch shutdedn Pos. tod Stock F . Test ECCS system Functional feet 4.6.5.1.d.1 seconsory Centeinment SCTs Test 4.6.5.1.d.2 seconsory Centatrusent SGTs Test 4.6.5.2.b 4.7.1.2.b secondary Centainment Isoletten Dampe Actuation 4.7.1.3.b ECCW Autenstic Actuation 4.7.1.4.b EEsW Autenstic Actuation 4.7.2.1.c.1 EDG Costing Water Ptay Automatic tuotion O 4.7.2.1.c.2 4.7.2.1.c.3 4.7.2.1.e.1 CR Ventitetten Filter Penetrett CR Ventitation Filter Charcoat aberatory Anotysis Ca Emergency Filtretten Syst _Flowrote 4.7.2.1.e.2 CR Ventitetten Filter Press e Drop 4.7.2.1.e.4 Ca Emergency Filtration Sy em Operationet Mode Actuation 4.7.5.e Ca Emergency makete Intet stor Dissipetten j 4.8.1.1.2.e.1 Sruater F mettone! Test EDG Inspection

'4.B.1.1.2.e.2 EDG Lead aejection (1 4.8.1.1.2.e.3 kW)

EDG Lead Rejection ( 0 kW) 4.8.1.1.2.e.4. EDG LOP Lead sheddi 4.8.1.1.2.e.4 4.8.1.1.2.s EDG LOP Auto stor and Lead sequencing 4.8.1.1.2. 6.e EDG ECCS Aute s rt 4.8.1.1.2 .6.b EDG LOP / ECCs eed shedding 4.8.1.1. .e.7 EDG LOP / ECC Aute stort and Lead sequencing 4.8.1. 2.e.8 EDG Wen ess let Trip sypses 4.8.1 .2.e.9 EDG 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months e and Not Fast start.

4.B. 1.2.e.10 EDG Aute t Lead verification

. 4. .1.2.e.11 EDG Rest etten of Offsite Power c 4. 1.1.2.e.12.s EDG A Lead sequencer Timer EDG & vett Esf aus Leekeut I 8.1.1.2.e.12.b EDG fferentist Trip Lockout

.8.1.1.2.e.12.c EDG hutdown seley Trip Lockout 4.8.2.1.c.3 4.8.2.1.d 1 VDC nettery Connections Resistance 4.8.4.5.e 0 VDC tettery Cepecity LCS Circuit Breakers Functional Test TABLE NOTATIONS i (a) . The surveillance in rval of channels within the ame trip system i required to be te ed at least once every N ti s 18 months, wher N is

. the total number f channels in the trip sys m. may be based up the erformance of e surveillance during the xth ' refueling outa e.

O - -

l FERMI - UNIT 2 3/4 0-6 i Amendment No. 106. m C

PAGE H OF 12 AI

Su4rcaHon3.o

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l Page 12 of 12 O

Revision 1, 09/25/98

- ~ . - - - - . - - . - - - - . . . . - - . . _.

OPEC lFICATlDt0 3 I8 ilEACTIVITY CONTROL SYSTEMS hf5o Su S /d bMN#H 8 43) '

tfMITING CONDITION FOR OPERATION (Continued)

AGI121: (continued) .

2. If the inoperable control rod (s) is inserted, within I hour disam the associated directional control valves ** either:

i ,

ga a) Electrically, or

/

b) Hydraulically by closing the drive water and exhaust i-8IO water isolation valves. l otherwise, be in at least NOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l

p. With more than 8 control rods inoperable, be in at least HOT l l 00 M'E L 5HUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . !

)

- - d. With one or more scran discharge volume vent or drain lines with one i

A mag 4 valve inoperable, restore the inoperable valve (s) to OPERABLE status i i within 7 days, or be in at least HOT SHUTDOWN within the next 12 1

! A CW C hours.

- - e. With one or more scram discharge volume vent or drain lines with both e

Acrimi B valves inoperable.1solate the associated line within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ****, or pgc be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , j SURVEILtANCE REQUIREMENTS 4.1.3.1.: The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

a sR3.l.gia. At least once per 31 days verifying each valve to be open,* and

! . aluating set:sk discharge yo system respop(e prior to pl t LR. l

startup aft V each scram t erify that no a)Mioma11 ties e t.

h.3.1.2 When above the pmset power level of the RWM, all withdrawn control i rods not required to have their directional control valves disamed electrically i

or hydraulically shall be demonstrated OPERABLE by moving each control rod at l 1 east one notch- 1 1

M. a. At least once per 7 days, and 3,83 b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is innovable as a result of

( excessive friction or mechanical interference.

$RQ$ *These valves W be closed intemittently for testing under administrative entrols.

/ Su.

\S P ' ~~

ay be rearned intemittently, under administrative control, to pemit N 3'O *== ting. associated with restoring the control rod to OPERABLE status.

rr-Separate Action entry is allowed for each 50V vent and drain line.

a An isolated 1tne may be unisolated under administrative control to allow draining and venting of the 50V.

k q ui a d At+itn 6 l !JO49--

O AcTZord5 Noir FERMI - UNIT 2 3/4 1-4 Amendment No. J/, M, M 120 PAGE 1 0F 02, pas )

. = _.. _ - . . --- - _. .-

DISCUSSION OF CHANGES ITS: SECTION 3.1.8 SDV VEtlT AND DRAIN VALVES V ADMINISTRATIVE A.1 In the conversion of the Fermi 2 current Technical Specifications (CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not result in technical changes (either actual or interpretational). Editorial changes, reformatting, and revised numbering are adopted to make the ITS consistent with the Boiling Water Reactor (BWR) Standard Technical Specifications NUREG 1433, Rev. 1.

A.2 Not used.

A.3 CTS 4.1.3.1.4.a.1 and a.2 require the performance of a SDV vent and drain valve functional test on receipt and reset of a

" signal . " ITS SR 3.1.8.2 permits the system functional to be initiated by an " actual or simulated" signal. This change allows satisfactory automatic scrams, as well as appropriately simulated scram signals, to be used to fulfill the system functional Surveillance requirement. Operability is adequately demonstrated c because the SDV vent and drain valves can not discriminate between

( " actual" or " simulated" scram signals. Since this is a reasonable interpretation of the existing requirement, this is considered an administrative change.

l O

FERMI UNIT 2 1 REVISION 1, 09/25/98l l

.._._.._..._.__._.__.-._...-._-~..._._.__.___-__...._..._.._.._..._.y l

DISCUSSION OF CHANGES

.ITS: SECTION 3.1'.8 SDV VENT AND DRAIN VALVES

-O TECHNICAL CHANGES LESS RESTRICTIVE

" Specific" ---

y L.1- -Not used,E

+

1 4

O I

i ro FERMI ~ UNIT 2 3 REVISION 1, 09/25/98l

SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves (y5 LC0 3.1.8 Each SDV vent and drain valve shall be OPERABLE.

(31.3.lke)

APPLICABILITY: MODES I and 2.

ACTIONS

NOTE------------------------------------- $I3d Separate Condition entry is allowed for each SDV vent and drain line. xy4 CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Restore valve to 7 days or drain lines with OPERABLE status.

h. Gel) 'I )

one valve inoperable.

B. One or more SDV vent B.1 --------NOTE--------- /

O or drain lines with both valves inoperable.

An isolated line may be unisolated under administrative (3l'3<I;VVNV) control to allow draining and venting of the SDY.

Isolate the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months E'I 3 I) 8 associated line.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months II'3* I') d > C')

associated Completion Time not met.

s.;^j.;

n M 3.1-25 "rf 1. ^'/^7/?! -

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PAM Instrumentation 3.3.3.1 fs

'L) 3.3 INSTRUMENTATION

-3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LC0 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.11 shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTIONS

..................................... NOTES - - - - - - -

1. LC0 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable. status.

(

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.7.

not met.

C. -

NOTE -

C.1 Restore one required 7 days Not applicable to channel to OPERABLE -

primary containment status, hydrogen and primary containment oxygen concentration channels.

One or more Functions with two required channels inoperable.

I (continued) 4 b -v/

l FERMI - UNIT 2 3.3 24 Revision 1, 09/25/98

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION . REQUIRED ACTION COMPLETION TIME D. Two required primary D.1 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment hydrogen arimary containment concentration channels lydrogen inoperable. concentration channel to CFERABLE status.

QB AN_Q Two required primary containment oxygen D.2 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months concentration channels primary containment inoperable, oxygen concentration channel to OPERABLE status.

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1 1 for or D not met. the channel.

/^

k)\

F. As required by F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action E.1 and referenced in Table 3.3.3.1 1.

G. As required by G.1 Initiate action in Immediately Recuired Action E.1 accordance with anc referenced in Specification 5.6.7.

Table 3.3.3.1 1.

l l FERMI UNIT 2 3.3 25 Revision 1. 09/25/98 l

- - - -. . ._-. - . . .-. - - -- ..- . . _ . . .._~.- - . . . - . . -

i PAM Instrumentation 3.3.3.1

. SURVEILLANCE REQUIREMENTS ,

I i

.........................-- NOTE - -- ...........

These SRs apply to each Function in Table 3.3.3.11.

SURVEILLANCE FREQUENCY i

SR 3.3.3.1.1- Perform CHANNEL CHECK- . 31 days SR 3.3.3.1.2 - -- -

NOTES - - - -

1. Only applicable to Functions 7 and 8. 1

2. Not' required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for.one channel, and 7 days for the second channel, after

= 15% RTP.

Perform CHANNEL CALIBRATION. 92 days O lSR 3.3.3.1.3 -

-NOTES- - - --

'l. 1. Not applicable to Functions ~7 and 8. )

2. . Radiation detectors are er.luded.

Perform CHANNEL CALIBRATION. 18 months 1

l FERMI UNIT 2 3.3 26 Revision 1. 09/25/98

, - . . . -- - . - . . . . - . . ~ - . . - - - - - . - - - . . - . - . . . - - . - - -

PAM Instrlmentation 3.3.3.1

'K fable 3.3.3.1 1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED l REQUIRED FROM REQUIRED

., FUNCTION . CHANNELS ACTION E.1 ..

1. Reactor vessel Pressure - 2 'F

2. Reactor Vessel Water Level Fuel Zone 2 F

- 3. Reactor vessel Water Level Wide Range 2: F ;

- 4~ suppression Pool Water Level 2 F I

5.. suppression Pool Water fesperature 2 F

6. ~ Drywell Pressure Wide Range 2 .F l 7. Primary Containment og Concentration 2 .F

l. 8. Primary Containment H, Concentration 2 F j

.9. Primary Containment Mish Range Radiation Monitor 2 .G

10. PCIV Position 2perpenetrat(on F flow path (a)( )

.1 t

i . .

l (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow .

through the valve secured. )

l~ (b) only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

y.

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i-i -l1 FERMI . UNIT 2 3.3 27 Revision 1, 09/25/98 t.

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1 -- . . , --. - . -. - , . - -

i PAM Instrumentation B 3.3.3.1 ;

BASES LC0 (continued)

'Only two Category I thermocouple channels are needed for

- post accident monitoring of sup)ression pool water temperature (Refs. 3 and 4). T1e outputs for the PAM ;

~

sensors T50N404A and T50N405B are recorded on two independent recorders in the control room (channel A is :

redundant to channel B). Both of these recorders must be !

OPERABLE to furnish two channels of PAM indication. These '

recorders are the primary indication'used by the operator during an accident. Therefore, the PAM Specification deals ,

specifically with this portion of the instrument channels.

6. Drywell Pressure I 1

Drywell pressure is a Type A. Category I variable provided to detect a breach of the RCPB and to verify ECCS functions that operate to maintain RCS integrity. Two wide range drywell pressure signals are transmitted from separate pressure transmitters and are continuously recorded and displayed.on two control room recorders. These. recorders .

are the primary indication used by the operator during an accident. Therefore, the PAM Specification deals p specifically with this portion of the instrument channel.

-l- '7. 8. Primary Containment Hydroaen and Oxvaen -

Concentration l Primary continament hydrogen and oxygen analyzers are Type C, Category I instruments provided;to detect high hydrogen

.or oxygen concentration conditions that represent.a potential for containment breach. This variable is also !

important_ in verifying the adequacy of mitigating actions. ;

9. Primary Containment Hiah Ranae Radiation Monitor ;

i Primary containment area radiation _(high range) is a Type E, j Category I variable, and is provided to monitor the potential of significant radiation releases and to provide i release assessment for use by operators in determining the ,

need to invoke site emergency plans. The instrumentation '

provided for this function consists of redundant sensors, ;

microprocessors and indicators. A common 2 pen recorder in the control room continuously records signals from both channels. The redundant indicators in the relay room and the common recorder in the control room are the primary indication used by the operator during an accident.

j. FERMI UNIT 2 B 3.3.3.1 - 5 Revision 1, 09/25/98

l PAM Instrumentation B 3.3.3.1

' (,r')j BASES l

LC0 (continued)

Therefore, the PAM Specification deals specifically with

, this portion of the instrument channel.

10. Primary Containment Isolation Valve (PCIV) Position PCIV position is a Type B, Category I variable, and is provided for verification of containment integrity. In the case of PCIV position, the important information is the isolation status of the containment penetration. The LC0 requires one channel of valve position indication in the control room to be OPERABLE for each active PCIV in a l containment penetration flow path, i.e., two total channels of PCIV position indication for a penetration flow path with I two active valves. For containment penetrations with only one active PCIV having control room indication Note (b) requires a single channel of valve position indication to be OPERABLE. This is sufficient to redundantly verify the I isolation status of each isolable penetration via indicated l status of the active valve, as applicable, and prior knowledge of passive valve or system boundary status. If a penetration flow path is isolated, position indication for I p)

(V the PCIV(s) in the associated >enetration flow path is not needed to determine status. Tierefore, the position l

indication for valves in an isolated aenetration flow path is not required to be OPERABLE. The )CIV aosition PAM instrumentation consists of position switcles, wiring, cabling, and cont,'ol room indicating lamps for active PCIVs.

Therefore, the PAM specification deals specifically with these instrument channels.

i APPLICABILITY The PAM instrumentation LC0 is a)plicable in MODES 1 and 2.

These variables are related to t1e diagnosis and preplanned actions required to mitigate DBAs. The applicable DBAs are assumed to occur in MODES 1 and 2. In MODES 3, 4, and 5, plant conditions are such that the likelihood of an event that would require PAM instrumentation is extremely low; therefore, PAM instrumentation is not required to be OPERABLE in these MODES.

ACTIONS Note 1 has been added to the ACTIONS to exclude the MODE change restriction of LC0 3.0.4. This exception allows entry into the applicable MODE while relying on the ACTIONS m) l FERMI UNIT 2 B 3. 3.3.1 - 6 Revision 1, 09/25/98

i l:

i PAM Instrumentation B 3.3.3.1 BASES ACTIONS (continued) -

! - even though the ACTIONS may eventually require plant ;

shutdown. This exception is acceptable due to the passive function of the instruments, the operator's ability to '

diagnose an accident using alternative instruments and

! methods, and the low probability of an event requiring these instruments.

Note 2 has been provided to modify the ACTIONS related to PAM instrumentation channels. Section 1.3, Completion L Times, specifies that once a Condition has been entered, subsequent. divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within. limits, will not result in separate entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable PAM instrumentation channels provide appropriate L compensatory measures for separate Functions. As such, a Note has been provided that allows separate Condition entry for each inoperable PAM Function.

O u When one or more Functions have one required channel that is inoperable, the required inoperable channel must be restored to OPERABLE status within 30 days. The 30 day Completion Time is based'on operating experience and takes into account

=the remaining OPERABLE channels (or, in the case of a Function that has only one required channel, other non Regulatory Guide 1.97 instrument channels to monitor the Function), the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation during this interval.

Bd If a channel has not been restored to OPERABLE status in 30 days, this Required Action specifies initiation of action in accordance with Specification 5.6.7, which requires a written report to be submitted to the NRC. This report discusses the results of the root cause evaluation of the inoperability and identifies proposed restorative actions.

1 LO UNIT 2 B 3.3.3.1 - 7 Revision 1,

( l FERMI 09/25/98 i

L

I PAM Instrumentation B 3.3.3.1 O

V BASES SURVEILLANCE REQUIREMENTS-(continued)

The 18 month Frequency for all channels except the primary containment hydrogen analyzers (per Note 1 to SR 3.3.3.1.3) is based on operating experience and consistency with the typical industry refueling cycles. The 92 day Frequency for the primary containment hydrogen analyzers (per Note 1 to SR 3.3.3.1.2) is based upon vendor recommendations and instrument accuracy requirements.

SR 3.3.3.1.2 is modified by Note 2 stating that performance of the calibration of the oxygen and hydrogen monitors may be delayed until after exceeding 15% RTP (i.e., the power at which LCO 3.6.3.2 requires the primary containment to be inerted). This delay is allowed for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for one oxygen and one hydrogen monitor, and for 7 days for the second oxygen and hydrogen monitor. These delays facilitate more accurate calibration methods, which can be employed with the primary containment inerted.

SR 3.3.3.1.3 is also modified by Note 2 stating that radiation detectors are excluded from calibration requirements, p

(vl REFERENCES 1, Regulatory Guide 1.97. " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident,"

Rev. 2, December 1980.

2. Detroit Edison Letter NRC 89 0148, " Additional Clarification to Fermi 2 Compliance to Regulatory Guide 1.97. Revision 2." dated June 19, 1989.

3. Detroit Edison Letter NRC 89 201. " Regulatory Guide 1.97 Revision 2 Design Review," dated September 12, 1989.

4. NRC Letter, " Emergency Response Capability Conformance to Regulatory Guide 1.97, Revision 2 (TAC No. 59620),"

dated May 2, 1990.

5. Detroit Edison Letter NRC 93 0105. " Fermi 2 Review of Neutron Monitoring System Against Criteria of NED0 31558A," dated September 28, 1993.

l (rs

%.)

~

)

l FERMI - UNIT 2 B 3.3.3.1 - 11 Revision 1, 09/25/98

i PAM Instrumentation B 3.3.3.1 l - U/ ' .

BASES

!' REFERENCES (continued) -

6. NRC Letter, " Regulatory Guide 1.97 Boiling Water Reactor Neutron Flux Monitoring Fermi 2 (TAC l No. M59620)," dated February 17, 1994.

7. NRC Letter " Regulatory Guide 1.97 Boiling Water Reactor Neutron Flux Monitoring Fermi.2_(MPA 17 TAC No. M59620)," dated May 10, 1993.

f 1

1 1

I D

l l' FERMI UNIT 2 B 3.3.3.1- 12 Revision 1, 09/25/98

a J a J.S. S. I -l

,, TABLE -3.3.7.5 -! -

WL 3 3 5.I-l ACCIDfNT MONITORING INSTRUMENTATION E b och e TINI '

APPLICABLE REQUIRED NUM8ER CHA LS OPERATIONAL

~ 0 INSTRUMENT OF CHANNELS ABLE , CONDITIONS MUOH

/

/ X Reactor Vessel Pressure 2 1, I, 2 80 El Reactor Vessel Water Level

2. a. Fuel Zone 2 1 1, 2 80

b. Wide Range 2 I I, 2 80 3

CD ([ J. Suppression Chamber Water Level 2 1 1, 2 80 g R Suppression Chamber Water Temperature 2 1 1, 2 80 hM

5- Se;;ression C'::d:r ^,WT;g:r;ter: ? ,,

\/l l

a

kl C 5. S";;-er:hr. Ch;ie,er Pr;;;;rc 2 1, 2 60 fo C Drywell Pressure, Wide Range 2 1, 2 80 O -8&DryweH-Afr--Teniperature ? lI i

!. ? GG

& o- I

/ A Primary Containment Oxygen Concentration 2 1' 1, 2 83

!. l g 8 -Hr Primary Containment Hydrogen Concentration 2

/1 1, 2 80 l A

U Miy/RCIIef-VdWPU5itivii indicaivai 1*/WelVC I*/Vels; I ,- 2 60

% 9 J E Containment High Range Radiation Monitor 2 1, l 81 g

,9 ki:

@*1 h L2. E 4

D 3 1 t~ ,r. o ~. . _ _. . . . .- ._ m i e ,. C Q ,1

!n G

Y'

~

SfE~dificA71M) 3 3 3,l TABLE E (Continued) ( }50 3M $ ee/NCdtw 5.la P

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS e_ k400 f AcTroM 6 h

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore U gngperable channel _

(s) to OPERABLE status wit sys e @ W e 'e -+

s' b.

~

[5 75 ~ ~ _ d%ys With the number of OPERABLE accident monitoring instrumentation nneis bog T D y less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within@O : a.c.tr be in Acno4 F. N , 6 at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

-- n. hows AOfMDM 84-- Wth the number of OPERABLE ess than required by the minimum Lg,{

ACTier4 C channels OPERABLE requirementsJinitiatejne prepterirpc e .. y....u,g -

(imonj#nno the spor 6priate narm6eterf anvithin 72 hW0rs/tind:

1) either restore the ino(perable channel (s) to OPERABLE L.4status with days of the event, or N 2) prepara and submit a Special Report to the Commission pursuant to spc. Scab. Sps%.e ,n 6.9.2 within 14 days following the event outlining the action s S 4 *"7 taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

AC'"ON "2 - Mth the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, withinl48.newsbither:

)r-l} Action A{3o A.O a. Restore the inoperable channel (s) to OPERABLE status, or [*p i 4c.Tiod C: W i -==- -

g ( , _ _ ,7-gt, 3,3.3,j ; b., Mots areLa.')

the affected

% specified isolation valve inoperapie ano ==

by Soecrfication Ins mACTION 3.6.3 HUN) aA

- ,9

'~ ' AcT1oM F t(Be,l'e mooE 3 )

c o n, S ,G..*7) }

ACTIONa. 83 With ' -AcVej the num d :(ber of OPERABLE accident monitoring annels instrum less than the Required Number of Channels shown in Table 3.3.7.5-1 the inglerable channel (sHo OPERABLE status within Ta-30 da.ys,p~r sh, re bmoa B -

report to the C'6mm'ission purslianfTo SiiteiFestioE'652 wimin the following 4

Su, bec 6 6 7) and schedule for restoring the instrument channef(s) to 3OPER b.

ShdO Wdh the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of T ble 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within hours or be in g g p: at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

72 L.')

FERMI- UNIT 2 3/4 3-62 Amendment No. 28,59,117 PAGE 9 _

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-I'"LE ' . 2. 7. 5 - !

l ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

APPLICABLE CHAlmEL g INSTRUMENT . CHECK CHANNEL OPERATIONAL

- CALIBRATI0l( CQleill0NS.

[ l J. Reactor Vessel Pressure M (i) R (3 > I, 2 J< Reactor Vessel Water Level 2 -C Fuel Zone

.3 4: Wide Range M <'> R (3 5 1, 2 MO> R<3> . 1, 2 yA Suppression Chamber Water Level M (8) R (3 > 1, 2 f I Suppression Chamber Water Temperature R<3)

H (:) 1. 2

4. ^vypi ca s iun Cii--im Air is ...i.uic M R :, I R.I g 6. S;;n :: Sa C".. 1,e.- 7 e;;.re M i: ;, I- I y 6 -P. Drywell Pressure, Wide Range M(8> R(I> 1, 2 i Q ~0. T,1-ct-i Air ici yc, aiui s E "

5h Primary Containment Oxygen Concentration M (8) f Qi (2 ) 1, 2 l C f-11T. Primary Containment Hydrogen Concentration M(I) Q*f (2) I, 2 gl W 52felvl8k-f Whc re3Run bdiceteri M i I, e 4K nkNine igh Range Radiation Monitor f

M (l) R** O ) #

1, 2 5

i r' 5 " 5 3 3 ' 3 " c * *- '# ' *~

Usi ample gas talning: a 8 2

,o a.

b e volume Four vol cent h dr en, balance nitr rogen, balance

n. IR333*I-(() o 2

percent rogen.

E g BRATION all consist of electronic calibr ton of the chan 1 mot _includine the W l .[**Cifalil!EL 9 detector.Jfor ran decades above I hr and a one popit calibration c ko thedpfctorbfop ?

b GO R/pr with an nstalled or port e gamma sour yc --

j c hu 4 f(13e nrovisions of Specificat one '

leted forcoEtnnat channel within iz hours and car innboth 4.0.4 are not channeis witnin applicable seven saysprovide [that the arter exceeding Iss orsurvelliance-is RArto rowtn.

l se 3 3-3.i t ** L

l DISCUSSION OF CHANGES ITS: SECTION 3.3.3.1 PAM INSTRUMENTATION (3 A.5 CTS Table 4.3.7.5 1 footnote # states that the provisions of Specification 4.0.4 are not applicable. This is not required in ITS 3.3.3.1 because any potential confusion concerning when the surveillance is required is eliminated by specifying the precise requirements for performance of the Surveillance such that an explicit exception to 4.0.4 is not necessary. The ITS SR 3.3.3.1.2 Note 2 modifies the Frequency such that it is "Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for one channel and 7 days for the second channel after 2 15% RTP." This is an administrative change with no impact on safety.

TECHNICAL CHANGES MORE RESTRICTIVE None TECHNICAL CHANGES LESS RESTRICTIVE

" Generic" LR.1 CTS Table 3.3.7.51. Action 81. requires that with the Operable channels less than the minimum required, initiate the preplanned q alternate method of monitoring the appropriate parameter (s) within i f 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the inoperable channel within 7 days. ITS 3.3.3.1, Action C, requires the channel restored within 7 days, but does not require the preplanned alternate method of monitoring to be initiated within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . This is acceptable because the requirement to initiate an alternate monitoring plan does not impact the requirement to restore the channel within 7 days, and the requirement to initiate alternate methods of monitoring post-accident parameters can be removed from the Technical Specifications. Regulatory control of changes to this requirement (e.g., Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since the requirement for post accident instrument channel Operability and actions for inoperable instrumentation, continues to be required by the Technical Specifications.

LR.2 CTS Table 4.3.7.51 footnotes

and ** provide details of performing Channel Calibrations. ITS SRs 3.3.3.1.2 and 3.3.3.1.3 do not include these details; they are removed from the Technical Specifications. Regulatory control of changes to this requirement (e.g., . Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and p1 safety since the requirement for Channel Calibrations continue to y1 be required by the Technical Specifications.

FERMI UNIT 2 2 REVISION 1, 09/25/98l

DISCUSSION OF CHANGES ITS: SECTION 3.3.3.1 PAM INSTRUMENTATION L.4 CTS Table 3.3.7.51 Action 80.a and Action 81.1) require l restoration of a single inoperable channel within 7 days'. CTS Table 3.3.7.5-1 Action 80.b and Action 83 require restoration of l one channel when two are inoperable within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . ITS 3.3.3.1 Action A requires restoration of a single inoperable channel i i within 30 days: ITS 3.3.3.1 Action C requires restoration of one channel when two are inoperable (except two inoperable hydrogen or oxygen concentration channels) within 7 days; and ITS 3.3.3.1 Action D requires restoration of one channel when two hydrogen or oxygen concentration channels are inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

These increased allowed out of service times are consistent with NUREG 1433, and are acceptable based on the remaining Operable post accident monitoring channels, other non-Regulatory Guide 1.97 instrument channels which monitor the function, the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event '

requiring PAM instrumentation during this interval. Therefore.

this less restrictive change will have a negligible impact on safety, p L.5 CTS 3.3.7.51 requires 1 channel per valve for the primary containment isolation valve (PCIV) position, and its Action 82 for inoperable channels requires restoration within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . ITS Table 3.3.3.11 states requirements on a penetration basis -

requiring 2 channels per penetration: but also including Note (b) allowing the requirement to drop to 1 channel on penetrations with only one installed control room indication channel. While this presentation is an administrative presentation preference (also note an additional administrative change: optionally, both CTS and ITS allow isolation of the penetration as addressed in discussion "A.4"), it is provided to assist clarification of the ITS 3.3.3.1 Actions, which are less restrictive:

. ITS 3.3.3.1 Action A allows 30 days if one channel in a penetration is inoperable, and only requires submission of a special report (in.accordance with ITS 5.6.7) if not restored in 30 days; and l

Action C allows 7 days if both channels in a penetration are inoperable, and requires plant shutdown to Mode 3 if one channel is not restored within 7 days.

i 1

FERMI UNIT 2 4 REVISION 1, 09/25/98l l

(

_ _ . _ ___. ___ _ _ ...._., .. _ . .. _ . _ =_... _ _ _ . _ _ . ._ _ _ _ _ _ _ .. _ _ _ _ _ _ . . _ _ __ _ ..__ _ ..

PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION (c7$)

, 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation

[3,3,7,5

l. LC0 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 l shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

j ACTIONS

- NOTES -------------- -------------- --

1. LCO 3.0.4 is not applicable.

(Doc L.))

l 2. Separate Condition entry is allowed for each Function.

(Doc A."L)

CONDITION REQUIRED ACTION COMPLETION TIME l

1 A. One or more Functions A.1 Restore required with one required channel to OPERABLE 30 days (T6L J. A.1. /

m channel inoperable. status.

Do e M.t )

O 8. Required Action and B.1 Initiate action in associated Completion accordance with Immediately(DC L* 3 )

Time of Condition A Specification 5.6. . pot g,i j not met. _

_ _ y g y(, g, y,,, f

@imuy em1 4&>mut ) % ne m a y3.n. j w_ - _'

C. ' NOTE--- -

C.1 Restore one required 7 days TEL 3.17.5-l, k Not applicable to channel to OPERABLE ghydr en---it--g status. M ai 70** O g i/ /

channe s.

__.........f"d_7_- ,

w.__-- OXY $tn .

One or more Functions !

with two required channels inoperable. l (continued) i 8WR/4 STS 3.3-23 Rev 1, 04/07/95 LO

$N l

PAM Instrumentation 3.3.3.1 (CTS) j p ACTIONS (continued)

V CONDITION REQUIRED ACTION COMPLETION TIME mary cevifoMnju.e , QbHad D. Two grequired' hydrogen Restor ne f' require 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 4

t channels D.{1 ,1 hydroge -k 76133.7.5-',

p pe+^rable. channel to OPERABLE Ac b fo.b Ano k hahep s -

,me n Aci;cn 13 b

/

E. Required Action and E.1 Enter the Condition Ismediately l associated Completion referenced in i Time of Condition C Table 3.3.3.1-1 for (y,3,7 5 ' 4

! or D not met. the channel.

F. As required by F.1 'Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

' f Required Action E.1 76L 3.3.M-l, and referenced in Ach 50.b l

Table 3.3.3.1-1. A cym g3.b l

G. As required by G.1 Initiate action in Ismediately Required Action E.1 accordance with rat 33 a. s -1, and referenced in Specification 5. Acu gi,3 O S L. Table 3.3.3.1-1. ), 1 1

ob-

- m_-

A tJO IWO ngvire/ f'riena,y coikinnvaf

ex ygen concuko Hm D.1. Kis%<e on coguial 12kwS cL1aartels inopuoble PrimuY cm kin men +

Q

/ o>o'Om crnun rea risw Of,j l Cbun64 -lo of6EA6(6

.5'fttN.5 BWR/4 STS 3.3-24 Rev 1, 04/07/95 l .

w

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS

NOTE------------------------------------

These SRs apply to each Function in Table 3.3.3.1-1.

y,3,7g)

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days (7843M*l) l SR 3.3.3.1.y a Perform CHANNEL CALIBRATION.

{1gmonths i

l I

I

- - - M o TE'S -- - - - - -

i

/, No4 opplicable h ronc%S 7andB p3 ,

1. _ gqAia_% _Agkeks.pq weluolept I

4 gg 3 3 3. l. 2 - -

- N a TES -- - - - - -

1. On\q afplrcable 40 Funcknr 7avd 8

( 2, do+ ryaired h k @rM' und) 72. hox) & M Chamu:I, ud 7 da p hr k Sumd cknd, a h'a 1 / G % A'TP Pwk cenon. cAuae+vw. 92d ys 1l A ~ -

BWR/4 STS 3.3-25 Rev 1, 04/07/95 k

PAM Instrumentatien 3.3.3.1 (CTS) rh \ table 3.3.3.1 1 (pose 1 of 1)

(' '

\ i gh Post Accident seenitorine snatnmentation TBLs L3.'ES-I g 4543."15-l Cole!?I ID M?T bA REFERENCED _

REGUIRED FROM REeUIRED q[ FLalCTION CNANNELS ACTION E.1

1. Reacter -___ _O__ Preneure _

2 F

[l) 2 Reac h Vt5ftll

h. Reester Weseet M LcV Fael fc.tiQ Wete/ Lowtsgpresalen Pool A Water Lovef - Wid6 E aqC g 4 7l _ _

y 3) 6 /. own Pressure (-Wde RaRai) 2 '

(7) 9j Primary Centei,.ent Gb_183 2 45)<._ (io

? nematt - -

> _- L ...

T'. PCIV Peettien F l lg 2,per ies,penetration g ,ets e><=>

= _ _=,e - -

7

.a.,_; @ _;, @ ca taH"9 : ,

(9>

g . 2 - - g , : =4@unc F

00) i

-4t:-9s4=:; t---e - .. - = ; -

{g $wpreselen Pool Water Temperature 7 h

(a) Not respired for isoletten wetwas uhese eseecleted penetration flew path is isolated try et Leest one \

78L 3.3.51 '

closed and deactivated outeestic velve, closed eenuel veLwe. blind flenge, or check watwo with flew thre g h the w two secured. gg g*g g-(b) Only one position indicotten channel is tap. sired for penetration flew paths with enty one irstatted Q( [,5 control rose indication chamel. \

-M .wni. hw

-E.i v.iv ..M se64esh Reviewer 'te: Table 3.3.3.1 1 shalt ' amended for each plant se to 11sts h'I . Att Regulatory Guide 1.97 ype A fratriments, and

2. Att Regulatory Guiale 1.9 , Category 1, non-type A trat a specified in the p t's seguletory Guide 1.97, Safety Eve tien Report.

BWR/4 STS 3.3-26 Rev 1, 04/07/95 O

Ru/ /

. . . _ ~_. - - -_ -- _ . _ . . _ _ _ - . - - _

l i

PAM Instrumentation l B 3.3.3.1 l

BASES l LCO imary Containment Isolation Valve (PCIV) Positi # )

(contin

[For this plant, PCIV position P rumentation consists of the folio :]

7,3

9. Wide Ranoe Neu Flux N

\i Wide ran utron flux is a Category I varia ovided to ver eactor shutdown. [For this plant, the wide e .

Mutron flux PAM instrumentation consists of the followi '

l 7

m E W.

g, i[-Pri% owfawud)

~..i : =

C

--.n Hydroaen and Oxvaen U* b hhn rifuvy ConMinukt) ,W '

---11 sylroge'n and oxygen analyzers are *7#6 b

......-.4 h'tegory Ca I instruments provided to detect high hydrogen or

._

oxygen concentration conditions that represent a potential ok r* for containment breach. This variable is also important in

-verifying the adequacy of mitigating actions. -[F;r thi -

--p' rt, th. J.,..ii .no uuni.in....ni ;,J,.;;a eaJ s;g;; _

- analy::r: P " in:tr ;atetten cea:i::: ef th: f;P -9 1 h Primary Containment Pressure Primary co nt pressure is a Category I var e provided to ver CS and containment int y and to verify the effectiven f ECCS acti aken to prevent containment breach. Two w primary containment l h pressure signals are tran transmitters and are e

inuously rec e separate pressure d and displayed on two control ro corders. These recorde re the primary

, indicatio by the operator during an acci l

1 Ther , the PAM Specification deals specifically s portion of the instrument channel.

N

! l Suooression Pool Water Temoerature pgg 4 l

Suppression pool water temperature is a gory I variable provided to detect a condition that could potentially lead' to containment breach and to verify the effectiveness of ECCS actions taken to prevent containment breach. The (continued) 8WR/4 STS B 3.3-68 Rev 1, 04/07/95 4

4 i ,

PAM Instrumentation B 3.3.3.1

',R

'O Insert B 3.3.3.1 4

2. Detroit Edison Letter NRC 89 0148, " Additional Clarification to Fermi 2 Compliance to Regulatory Guide 1.97 Revision 2."

dated June 19, 1989.

3. Detroit Edison Letter NRC 89 201 " Regulatory Guide 1.97 Revision 2 Design Review, " dated September 12, 1989.

4. NRC Letter, " Emergency Response Capability-Conformance to .

Regulatory Guide 1.97 Revision 2 (TAC No. 59620)," dated May 2, 1990, i

5. Detroit Edison letter NRC 93 0105, " Fermi 2 Review of Neutron Monitoring System Against Criteria of NED0 31558A," dated September 28, 1993.

6. NRC' letter, " Regulatory Guide 1.97 Boiling Water Reactor Neutron Flux Monitoring Fermi 2 (TAC No. M59620)," dated February 17, 1994. ;

I 7. NRC Letter, " Regulatory Guide 1.97 Boiling Water Reactor Neutron Flux Monitoring Fermi 2 (HPA-17 TAC No. M59620),"

dated May 10, 1993.

Insert B 3.3.3.1 5

... for all channels except the primary containment oxygen and l hydrogen analyzers (per Note 1 to SR 3.3.3.1.3) . . .

1 l

l I'

r. ,

i l i h i i

FERMI - UNIT 2 Page B 3.3 73(1) (Insert) REVISION 1. 09/25/98l

PAM Instrumentation B 3.3.3.1 (3

Q

Insert B 3.3.3.1 6 The 92 day Frequency for the primary containment oxygen and hydrogen analyzers (per Note 1 to SR 3.3.3.1.2) is based upon vendor recommendations and instrument accuracy requirements.

SR 3.3.3.1.2 is modified by Note 2 stating that performance of the calibration of the oxygen and hydrogen monitors may be delayed until after exceeding 15% RTP (i.e., the power at which LCO 3.6.3.2 requires the primary containment to be inerted). This delay is allowed for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for one oxygen and one hydrogen monitor, and for 7 days for the second oxygen and hydrogen monitor. These delays facilitate more accurate calibration methods, which can be employed with the primary containment inerted.

SR 3.3.3.1.3 is also modified by Note 2 stating that radiation detectors are excluded from calibration requirements.

'Ov l

.;A.

, GJ j FERMI UNIT 2 Page B 3.3 73(2) (Insert) REVISION 1, 09/25/98l l

SRVs 3.4.3

/~'

!s,)s SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints In accordance of the required SRVs are as follows: with the Inservice Number of. Setpoint Testing Program SRVs (oslqL 5 1135 i 34.05 5 1145 i 34.35 5 1155 i 34.65 Following testing. lift settings shall be within i 1%.

SR 3.4.3.2 -- ---

---NOTE - - - -- - - -

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

(~

V Verify each required SRV opens when manually actuated.

18 months C\

V l FERMI - UNIT 2 3.4 7 Revision 1, 09/25/98 I

J

SRVs B 3.4.3 BASES APPLICABILITY In MODES 1, 2, and 3, 11 SRVs must be OPERABLE. since considerable energy may be in the reactor core and the ;

limiting design basis transients are assumed to occur in these MODES. The SRVs may be required to provide 3ressure relief to discharge energy from the core until suc1 time that the Residual Heat Removal (RHR) System is capable of dissipating the core heat.

In MODE 4, decay heat is low enough for the RHR System to provide adequate cooling, and reactor pressure is low enough that the overpressure limit is unlikely to be approached by assumed operational transients or accidents. In MODE 5, the reactor vessel head is unbolted or removed and the reactor is at atmospheric pressure. The SRV function is not needed during these conditions.

ACTIONS A.1 and A.2 With less than the minimum number of required SRVs OPERABLE, a transient may result in the violation of the ASME Code limit on reactor pressure. If the safety function of any '

(A) required SRVs cannot be maintained, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS This Surveillance requires that the required SRVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the SRV safe lift settings must be performed during shutdown, since this is a bench test, to be done in accordance with the Inservice Testing Program. The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating tem mratures and pressures. The SRV setpoint is i 3% for OPEMBILITY, however, the valves are reset to i 1% during the Surveillance to allow for drift.

p v

l FERMI - UNIT 2 B 3.4.3-3 Revision 1, 09/25/98

P SPsc memon 3.y.3 O ~3/4.4.2 SAFETY / RELIEF VALVES SAFETY / RELIEF VALVES [,/

LIMITING CONDITION FOR OPERATION D 3.4.2.1 The safety valve function of at least 11 of the following reactor Md oolant sEtem saj.ety/ relief valves shall be OP safety'vaTve Tdnction ITTt settingiI:* ~ ~ LRABj.ywTth UseTpecified code

.sg34.3./ 5 . safety / relief valves 9 1135 psig 43%

5 safety / relief valves 9 1145 psig i3%

, t 5 safety / relief valves 9 1155 psig 13% g APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With the safety valve function of'less than 11 of the above Actron / safety / relief valves OPERABLE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

/~

With o e or more safety / liet vaivaa stucn en, pr unaea Inat suppr ssion pool avera water temperature s less than 95'F, e s the tuck open safet relief valve (s); if nable to close the uck o n valve (s) with 2 minutes or if su ression pool avera water O

emperature is 95 or greater, olace e reactor mode swi h in t

_ h n + *8m nneiti _

. wun . ur ... . . . i. ,,'. el',e ' . .'... pu tion indicators i operable, rest e the inoperab e indicator (s) t OPERABLE status w hin 7 days or e in at least T SHUTDOWN with the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD 5 DOWN within t e following 24_h urs7 a.1

'SURVEILLA'NCE REOUTREMENTS !

/ l f4.4.Z.1.1 The valve posi on inotcator for eacn sarety/rei r vasve snas De demonst ted-OPERABLE wi the pressure s point of each the tail-pipe i press e switches veri ed to be 30 a 5 sig by performa e of a CHANNEL MI TION at 1sact nem nor la mont .f SA '

4.4.2. .7 At least 11/2 o the safety relief valves shall be set oressure .

3S3I testeyat leasfoncie per 15 monShs/such that all)5 safety relM valves are) setgressureAested a* east oncVper 40 monthf '

N ./

-<ao.- a us.2

/

'*The, conoitions or In /J./

LyalgesJ4ft setting prAssure at nominalkneratino snali porrespono taderatures and oressufes to f.muieny/neAlthougn

-touno litt s ing toierange is s u,, Ine as-i -s iiit settin shall be l s ithin al% of e,specified putpoints prior to nstallation fo owing ;

testing. g O ,

FERHI - UNIT 2- 3/4 4-7 Amendment No. 57,123 PAGE 1 0F 01 pu/ I

l l

DISCUSSION OF CHANGES l ITS: SECTION 3.4.3 - SAFETY RELIEF VALVES (SRVs)

L i ,

ADMINISTRATIVE A.1 In the conversion of the Fermi 2 current Technical Specifications (CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not' result in technical changes (either actual or interpretational). Editorial changes, reformatting, and revised numbering are adopted to make the ITS consistent with the Boiling Water Reactor (BWR) Standard Technical Specifications NUREG 1433, Rev. 1. I j

TECHNICAL CHANGES MORE RESTRICTIVE l l M.1 .ITS adds a new Surveillance Requirement. SR 3.4.3.2 requires the i SRVs to be manually opened each cycle after reaching adequate pressure and steam flow for the test. Although SR 3.4.3.2 is current;y.being performed (though it is not specifically in Technical Specifications), this change is considered an additional restrictions on plant operation. This change is a more

! restrictive change which will have no negative impact on safety, p because the surveillance test is required to ensure the

( Operability of components assumed to perform in the plant safety analysis.

TECHNICAL CHANGES' LESS RESTRICTIVE l !

"Generi c" l l

LA.1 CTS 3.4.2.1 footnote "*" requires that the lift setting pressure shall correspond to ambient conditions of the valves at nominal !

operating temperature and pressure, and also details the ;

application of the 31.setpoint tolerance (i.e., the need for as-left settings It). ITS SR 3.4.3.1 specifies the required lift 4

pressure for the SRVs, but does not specify the ambient conditions or details of. as left settings. This is acceptable because the >

criteria for the ambient condition or details of as left settings do.not impact the requirement to perform the surveillance and the requirement for the Operability of the SRVs. Therefore, these details will be relocated to the ITS Bases which require change l control in accordance with ITS 5.5.10, Bases Control Program.

These details are not required to be in the ITS to provide adequate protection of the public health and safety, because these details do not impact the requirement to perform the surveillance or the requirement to maintain the SRVs Operable.

{(rmM

~

FERMI - UNIT 2 1 REVISION 1, 09/25/98l L

L i ._ . - . . _ - . _ _ _ . _. - _ _ -

S/RVs 3.4.3

[C75)

SURVEILLANCE REOUIRENENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints iln accordance '

of the frequired{ S/RVs are as follows: with the d 2"21*'l/

Inservice Number of Setpoint jj3g s 3a.,r Testing Program S/RVs (nsio) -er [18] mun uisj -

f$

3M 1 I j [$..$. 7

~

h,( & 9,

[hh.k.k.

m-1-110 1 33.b u%ily'g

, Following testing, lift settings shall be within i 1%.

SR 3.4.3.2 --- - -

NOT E------------------

Not required to be perfomed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are M ",

adequate to perform the test.

Verifyeach4requiredS/RVopenswhen T187 months:Bla-manually actuated. g;--2.p ,

( ,3 3 v 4

t f-l *

, 3"_ U. M,"

i 1

BWR/4 STS -

3.4-6 Rev 1, 04/07/95 O

wI

l i-5/RVs B 3.4.3 O BASES (continued)

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS ThisSurveillancerequiresthatthefrequiredpS/RVswill open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the S/RV safe lift settings st be performed during shutdown, since this is a bench test , to done in accordance with the Inservice Testing P gr The lift setting pressure shall i

correspond to tent conditions of the valves at nomhal operating temperatures and pressures. The S/RV setoo 4t is q8 i for OPERABILITY; however, the valves are reset t iL uring the Surveillance to allow for drift.

y,.g,,j t,9 fu he KiiiiiiBi\ Frequency #-- i---- an: =h YN94 Me N 0 l'd5 Surveillance must be perfomed durin S et pres su rc s for Gid " ~~ - ", , - -'---- <=~gshutdown

= ' =e "

mm cond1k%i win % ;oct gj ([ $g Vs (MIG N Cb f{we ver s S I r\Ct *b/ U ^^

6F L/. orc reg uirec( N A manual actuation of each b quired}(5/RV is performed to g . /3 mef ;p // savs, verify that, mechanically, the valve is functioning properly 1 and no blockage exists in the valve discharge line. This o /c set //off//Vi can be demonstrated by the response of the turbine control valves or bypass valves, by a change in the measured steam flow, or by any other method suitable to verify steam flow.

'O Adequate reactor steam done pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor l pressure when the S/RVs divert steam flow upon opening. I Sufficient time is therefore allowed after the required s gro pressure and flow are achieved to perform this test.

Adequate pressure at which this test is to be rfomed is 1 psig (the pressure recommended by the va e '

manu acturer). Adequate steam flow is represented by [et-

/prh,n e b Yf d**

i ?:: IJ5 t -tin: i;; ::: velv:: :;::r-or-total-steam flow W g g ogen Id:' lb/.'. G. Plant startup is allowed prior to performing d gt this test because valve OPERABILITY and the setpoints for (T overpressure protection are verified, per ASME Code

/ O '/o requirements, prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test. The 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed for manual actuation after the required pressurs is reached is sufficient to achieve stable (continued)

M /^ .ia B 3.4-15 Rev-Ir04/07/95 I

au u

.1FJCTOR COOLANT SYSTEM S'f6CjpgqpaM 3 </.f g VEfttANCE REOUTREMENTS (Continued) q SA 3,9 -5. /

4*.t+:f- Each reactor coolant system pressure isolation valve -sp;. m-n in_

(d mi ^ 2-1 shall- be ' demonstrated OPERABLE by leak testing pursuant to LA.l Specificatter. 4.0.5 and verifying the leakage of each valve to be within the specified limit:

h AL iss>L unwu ys , mun6ni. =>>u J~ l

. rrior 0 re i. urn i ng 6us s'avu LD service folloWing malnten e, rep or replacemen ork on the valvgwhich could aff it 1 age rate. f -

N Tl.; ; - - -- r .;;i' ;;ti= ' 0.' are not appTicable -fm ..... , :- tqh 8j'hj OPERATIONAL CONDITION 3.

N.4.3.z.s ine nigfiow pressure interrace ^ ive seaKage pressure mo ors snai-be demonstrated ERABLE with alarm setpo ts per Table 3.4.3.2-2 b performanc of a:

a. NEL FUNCTIONAL TEST least once per 31 day , and

b. CHANNEL CALIBRATION least once per 18 mon s.

LA./

O FERMI - UNIT 2 3/4 4-11a Amendment No. pp,118 iO PAGE = & _0F 03 i

AI

DISCUSSION OF CHANGES ITS: SECTION 3.4.5 RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE O -TECHNICAL CHANGES LESS RESTRICTIVE

" Generic" LA.1 CTS 3.4.3.2. Table 3.4.3.21 provides details relating to system design and purpose (i.e., the list of PIVs). ITS 3,4.5 requires the Operability of the PIVs, but does not specify the design details. This is acceptable because these design details do not impact the ITS requirement for PIV Operability, they only provide information specifying the particular PIVs. Therefore, these details can be' relocated to the UFSAR. This change is consistent I with NUREG 1433. The information moved to the UFSAR requires changes to be controlled in accordance with 10 CFR 50.59. This relocation continues to provide adequate protection of the public health and safety since the requirement for PIV Operability continues to be required by the Technical Specifications.

LA.2 CTS 4.4.3.2.2.a. specifies the Frequency for performing the RCS Pressure Isolation Valve (PIV) Surveillance including both

" pursuant to Specification 4.0.5" and "once per 24 months." ITS l SR 3.4.5.1 requires that the surveillance be performed but only identifies that the frequency is determined by the Inservice Testing (IST) program. This is acceptable because any additional requirement to perform the surveillance.(1.e., "once per 24 months") is not impacted by where the frequency is specified. l Therefore, this information can be defined and controlled in the IST Program. This change is consistent with NUREG 1433. The information moved to the IST Program requires changes to be controlled in accordance with the 10 CFR 50.55a. This relocation continues to provide adequate protection of the public health and safety since the requirement for PIV Operability continues to be required by the Technical Specifications.

O FERMI UNIT 2 2 REVISION 1, 09/25/98l a

' $ M /F/Ck11ed .& C / ;

3 /4 . 5 EMERGENCY CORE COOLING SYSTEMS l

3 /4 . 5.1 FCCS - OPERATING LIMITING'CONDiff0N FOR OPERATION LC d 3.5.1 The emergency core cooling systems shall be OPERAB h The core' spray system (CSS) consisti subs Etem comprised of:

of two subsystems with each Two OPERA 8LE CSS pumps, d

2. An OPERABLE flow pat capable of taking suction from e suppression chambe and transferring the water thr gh the spray sparger to he reactor vessel.

b. The low pressure e ant injection (LPCI) system o the residual heat removal system c sisting of two subsystems with ach subsystem comprised of:

1. Two 0 RA8LELPCI(RHR) pumps,and

2. PERA8LE flow path capable of king suction from the ppression chamber and transfe ing the water to the reactor vessel."*

c. T high pressure cooling injec on (HPCI) system consisting of

, 1. One OPERA 8LE HPCI p and O 2. An OPERABLE flow suppression cha h capable of taking suction fr m the r and transferring the water t the reactor el. ~

@ 3,5,/ g The automatic depressurization system (ADS) with at least five OPERABLE ADS valves.

APPlfCABIlfTY: OPERATIONAL CONDITION 1, 2* ** I and 3* **.

I

The HPCI system is not required to be OPERABLE when reactor steam done 1

/\ gum pressure is less than or equal to 150 psig.

- The ADS is not required to be OPERABLE when reactor steam dome pressure is i u less than or equal to 150 psig. i

'J%ld "* Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam I' A done pressure less than the Residual Heat Removal RHR) cut-in permissive pressure in OPERATIONAL CONDITION 3, if capable of(being and not otherwise inoperable.

manually r

!;: i; xid --Test O ce4 M :.;e.;. L !

FERMI - UNIT 2 3/4 5-1 Amendment No. 126 O PAGE 3 0F 10 O

l l

DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating b

V ADMINISTRATIVE l

q A.1 In the conversion of the Fermi 2 current Technical Specifications l l (CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not result in technical changes (either actual or interpretational). Editorial changes, reformatting, and revised numbering are adopted to make the ITS consistent with the Boiling Water _ Reactor (BWR) Standard Technical Specifications NUREG 1433. Rev. 1.

l A.2 Not used. l A.3 CTS 3.5.1, footnote "#" to the Applicability, references CTS 3.10.6. Training Startups, which allows a relaxation to the requirements for ECCS system Operability if certain conditions are maintained during training startups. ITS 3.0.7 adequately ,

prescribes the use of the Special Operations LCOs and eliminates l the need for this " cross reference." Elimination of this reference is an administrative change with no impact on safety.

A.4 The CTS provides a specific Action for LPCI cross tie valves closed. The ITS recognizes that both LPCI subsystems are j inoperable with a LPCI cross tie valve closed (ITS Bases 1 specifically discusses). Therefore both the CTS and ITS Actions for LPCI cross tie valve closed are the same as for both LPCI subsystems inoperable. This administrative presentation preference to eliminate specific treatment of a closed cross tie valve, and allow the definition of Operability to accomplish the identification of the appropriate Action does not result in any technical changes. Therefore, this is an administrative change with no impact on safety.

I i

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i FERMI UNIT 2 1 REVISION 1. 09/25/98l i

l

, FfECIPCMIOAE S[2

$ EMERGENCY CORE COOLING SYSTEMS 3/4 5.2 ECCS - SHUTDOWN .

LIMITING CONDITION FOR OPERATION ubsystems s' hall be OPERABLE:

LCD 3.5.2 At least twofof the followl i a. Cor spray system (C subsystems with a s ' system comprised of:

! . At least two PERABLE CSS pumps, an

2. An DPERA . flow path capable of aking suction from at east ,

one of e following water sou s and transferring t water; throu the enray enarner to e reactor vessel: #

y , , _ 36; ...an ee4-- ,k " , ne

-tt- When the suppression chamber water level is less than the 6N ES*N limit required in Specification 3.5.3 or is drained, from the condensate storage tank containina at least 150,000 ' '

l available feet. gallons of wa)ter,ti;;'=t tW level of 18 i I.

b Low pre ure coolant injection LPCI)systemsubs tems with a

, subsy em comprised of: )

1. At least two OPERABL PCI (RHR) pumps, d

[ . An OPERABLE flow p h capable of taki suction from the i i suppression cha r and transferring he water to the re or l

! N vessel **.

APPLICABILITY: OPERATIONAL CONDITION 4 and 5*.

! ACTION:

1 1 AWaA e: with aa' af th' above r'avired sub$rst'=(5) taapar>ble restar' at

least two subsystem (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or suspend L..l AcnoAl6 all operations with a potential for draining the reactor vessel.

T dC , Wini bo".1 of the above required subsystems inoperable, suspend

, ggC f ^1 :" ? "S and all operations with a potential for draining the

' reactor vessel. Restore at least one subsystem to (PERABLE status h T10 N b YNd k,I gr establish (5ECONDARY wn1AINMEN" HT EGRIT, ,

( _ , ir PThe ECCS is not required to be OPERABLE provided that ? " :::^-~ r : r b

[ g N. the cavity is flooded, the spent fuel pool gates are removed. and water level is maintained within the 1,imits of(5pectrication ?

,i

' O.5.8 and 3.9. D i **LPCI subsystem (s) may be considered OPERABLE during all neent and operation Gt 35~2' C. for decay heat removal if capable of being manually rea igned and not No otherwise inoperable.

i FERNI - UNIT 2 3/4 5-6 Amendment No. 126 l mee 3 w as ea

)

DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown O A.8 CTS LC0 3.8.3.2.a.3 requires the LPCI swing bus to be Operable and the associated Action c requires declaration of LPCI inoperability with the swing bus inoperable (i.e., not energized or automatic throwover scheme inoperable). The ITS provides this intent within the ECCS Specification, without separately specifying Operability of ,

the swing tas .in another Specification. The ITS recognizes that l LPCI is inoperable with the swing bus inoperable (ITS Bases specifically discusses). Therefore both the ITS and CTS Actions for an inoperable swing bus are the same. This administrative presentation preference does not result in any technical changes.

Therefore, this is an administrative change with no impact on safety.

A.9 Not used.

A.10 CTS 4.5.1.b.2 specifies that the LPCI pump flow verification test be performed at a pressure corresponding to a reactor vessel to l primary containment differential pressure (psid) greater than or equal to the value assumed in the safety analysis. ITS SR 3.5.1.8 and SR 3.5.2.7 specify that the LPCI pump flow test be performed at a system head corresponding to a reactor pressure greater than i, or equal to the value assumed in the safety analysis. This change was made to make the test description.for the LPCI test the same as that currently used for th.e CS test. Both tests are intended to verify the flow rates at the reactor pressures assumed in the safety analysis, NEDC 32071P, Table 4-3. NEDC 32071P, Table 4 3 footnote (1), indicates that the pressures assumed for LPCI or CS pump injection and the values at which the pumps are tested is expressed in " vessel to drywell differential pressure." The acceptance criteria used for ITS SR 3.5.1.8 (and ITS SR 3.5.2.7) l 1s expressed as minimum flow rate against a system head corresponding to reactor pressure. This criteria is clarified in the Bases which states that pump flow rates are verified against a system head equivalent to the elevation head pressure between the

pump suction and the vessel discharge, the piping friction losses, L

and RPV pressure present'during a LOCA. The SR acceptance criteria is presented in "psig" (instead of psid) and clarified in

i. the Bases to ensure that the flow verification test is not

!o FERMI UNIT 2- 3 REVISION 1, 09/25/98l g

L i , , - . _ _ __ _ . - - _-

I a

Specevierios> 3.9 2-5a .C Nu Olso

W I S Qb'D1 N'b D.C. SOURCES - OPERATING

.gg./ffy,J.F.f,)

g LIMITING CONDITION FOR OPERATION f3.8.2.1 As a minimum,~the following D.C. electrical power sources shall be OPERABLE:

a. Division I, consisting of:

4

' 1. 130 VDC Battery 2A-1.-

" 2. 130 VDC Battery 2A-2.

3. Two 130 VDC full, capacity chargers. .

l 4

b. Division II. consisting of:

1. 130 VDC Battery 28-1.

1. -% '2.

3.

130 VDC Battery 28-2.-

Two 130 VDC full capacity chargers. 4 l

[g* lPPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

N W/ ""With a b'attery charger in either Division I o .

)

D.C. electrical power sources inoperable, restore the inoperable battery i

charger to OPERABLE status or replace with the spare battery charger within in COLD4SHUTDOWN hours or be within in the at following least HOT SHUTDOWN within the next 12 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

! , With either Division I or Division II of the above required D.C.

electrical power sources otherwise inoperable restore the inoperable

! .n

,g 4

division to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or,be in at least HOT SHUTDOWN within hours."the'next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 SURVETLLANCE REOUTREMENTS 4

,[4.8.2.1 y *

.' idemonstrated OPERABLE:Each of the above required 130-volt batteries and chargers f a.

t least once per 7 days by verifying that:

, P4ei Ecdiani. I. 1.

t-4 The and parameters in Table 4.8.2.1-1 meet the Category A limits, 9 2.

' Total batter terminal voltage is reater than or eoual to 130 e . ~

-t'"b > 3*9'y volts for Di ision I and greater t an or equal to 125.7 volts for Division 11 on float charge.

t,

b. At !

discharge with battereast once per 92 days and within 7 days,after a battery It<

, battery overcharge wi h battery termi al volta eterminal volta e less than volts for Division reater than 150

Qtc8cakA

5. % verifying that: 1 and greater than 145 volt f r Division II, by '

(1. The parameters in Table 4.8.2.1-1, meet the Category B limits, f'This TION may delayed for up ino rable due 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for ba ry chargers e i loss of EECW c ing provided th CTIONS

_ t . .l.2 are ta en.

3 of Spe ication i

p *

( FERMI - UNIT 2 l.1 3/4 8-10 Amendment No. 20.121 PAGE Tl 0F 09 (b l l

.._=. _ . .. _._. _ ._... _. _. _ .. _ ..-_ _ .. _ . _... .._... _ ... _ ._

DC Sources-Operating $

3.8.4

~

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ;

.SR 3.8.4.1 . Verify battery terminal voltage is = 130 V 7 days.

for Division I and = 125.7 V for Division II on. float charge.

.SR -3.8.4.'2 Verify no visible corrosion at battery 92 days terminals and connectors.

E Verify each battery cell to cell and terminal connection resistance is 5 1.5E 4 ohm-1 l

SR 3.8.4.3- Insmet battery cells, cell plates, and '18 months rac(s for visual indication of physical

. damage or abnormal deterioration.

l .-

SR 3.3.4.4 Remove visible corrosion and verify battery 18 months cell to cell ~and terminal connections are.

coated with anti corrosion material.

~

i

-SR 3.8.4.5 Verify each battery cell to cell and 18 months )

terminal connection resistance-5 1.5E 4 ohm.

SR 3.8.4.6 . Verify each required battery charger 18 months supplies for Division I: a 100 amps at a 129 V for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s: and Division II:

-= 100 amps at = 124.7 V for = 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(continued) lLFERMI UNIT 2 3.8 17 Revision 1, '09/25/98 m

DC Sources-Operating B 3.8.4 BASES BACKGROUND (continued)

Each DC battery subsystem is separately housed in a ventilated room apart from its charger and distribution centers. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels.

The batteries for DC electrical. power subsystems are sized -

such that under the worst case condition, with no battery charger available and the battery cell electrolyte temperature at 60*F, the batteries are able to carry all required loads for four hours without the minimum cell voltage dropping below 1.75 VDC for Division I and below 1.81 VDC for Division II.

Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation, while at the same time maintaining its battery bank fully charged.

Each battery charger has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying normal steady state loads (Ref. 11).

APPLICABLE The initial conditions of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses in the UFSAR, Chapter 6 (Ref. 4) and Cha)ter 15 (Ref. 5), assume that Engineered Safety Feature (ES:) systems are OPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the EDGs, emergency auxiliaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis of the unit. This includes maintaining sufficient DC sources OPERABLE during accident conditions in the event of:

a. An assumed loss of all offsite AC power or all onsite AC power; and O l FERMI UNIT 2 B 3.8.4- 2 Revision 1. 09/25/98 i

L_______~_____m

DC Sources-Operating B 3.8.4 BASES APPLICABLE SAFETY ANALYSES-(continued)

b. A worst case single failure.

The DC sources satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).

LCO The DC electrical power subsystems-with each DC subsystem consisting of two 130 VDC batteries in series, two battery chargers, and the corresponding control equi ment and interconnecting cabling supplying power to tle associated bus, are required to be OPERABLE to ensure the availability of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (A00) or a postulated DBA. Loss of any DC electrical power subsystem Joes not prevent the minimum safety function from being performed (Ref. 3).

APPLICABILITY The DC electrical power sources are required-to be OPERABLE in MODES 1, 2 and 3 to ensure safe unit operation and to

[ ensure that:

a. Acceptable fuel design limits and reactor coolact l pressure boundary limits are not exceeded as a rcsult of A00s or abnormal transients; and

b. Adequate core cooling is provided, and containment integrity and other vital functions are maintained in the event of a postulated DBA.

The DC electrical power requirements for MODES 4 and 5 are addressed in the Bases for LC0 3.8.5, "DC Sources-Shutdown."

j ACTIONS A.1 and B.1 l

Conditions A and B represent one division with a loss of i ability to completely respond to an event, and a potential loss of ability to remain energized during normal operation.

If one of the required DC electrical power subsystems is inoperable (e.g., inoperable battery, inoperable battery charger (s), or inoperable battery charger and associated L l

O l FERMI UNIT 2 B 3.8.4-3 Revision 1, 09/25/98

DC Sources-Operating B 3.8.4 i BASES

.G ACTIONS (continued) -

inoperable battery), the remaining DC electrical power subsystems have the capacity to support a safe shutdown and to mitigate an accident condition. A subsequent worst case single failure could, however, result in the loss of minimum necessary DC electrical subsystems to mitigate a worst case j accident. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the potential' for com)lete loss of DC power to the affected j division. The 4 lour Completion. Time (Required Action A.1) 1 for restoration of an inoperable battery charger allows time '

to replace the inoperable charger with an OPERABLE spare battery charger, if available. The four hour limit is reasonable based on the remaining capability of the battery to carry the loads for this period. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limit for i Required Action B.1 is consistent with the allowed time for l an inoperable DC Distribution System division. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time is based on Regulatory Guide 1.93 (Ref. 6) and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown.

C.1 and C.2 If the station service DC electrical power subsystem cannot be restored to OPERABLE status within the required Completion Time, the unit must be brought to a MODE in which the LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the recuired plant conditions from full power conditions in an orcerly manner and without challenging plant systems. The Completion Time to bring the unit to MODE 4 is consistent with the time required in Regulatory Guide 1.93 (Ref. 6).

SURVEILLANCE SR 3.8.4.1 REQUIREMENTS Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the contir.uous charge b

l FERMI UNIT 2 B 3.8.4-4 Revision 1, 09/25/98

1 DC Sources-Operating B 3.8.4 BASES SURVEILLANCE REQUIREMENTS (continued) required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with manufacturer recommendations and IEEE 450 (Ref. 7).

SR 3.8.4.2 I Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistar.ce of each inter cell and terminal connection, provides an. indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The connection resistance limits procedurally established for this SR are no more than 20% above the resistance as measured during installation and not above the ceiling value established by the manufacturer. This provides conservative measures to assure the Technical Specification limit is not exceeded.

The Frequency for these inspections, which can detect conditions that can cause power losses due to resistance heating, is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends.

SR 3.8.4.3 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. Indications of damage or abnormal deterioration are evaluated to assess impact on the OPERABILITY of the battery. l The 18 month Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable from a standpoint of maintaining reliability.

A U

l FERMI UNIT 2 B 3.8.4-5 Revision 1, 09/25/98 f

DC Sources-Operating B 3.8.4

,m (j BASES SURVEILLANCE REQUIREMENTS-(continued',

SR 3.8.4.4 and SR 3.8.4.5 Visual inspection and resistance measurements of inter cell and terminal connections provides an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti corrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each terminal connection.

The removal of visible corrosion is a preventive maintenance SR. The presence of visible corrosion does not necessarily represent a failure of this SR, provided visible corrosion is removed during performance of this Surveillance.

The connection resistance limits procedurally established for this SR are no more than 20% above the resistance as measured during installation, and not above the ceiling value established by the manufacturer. This provides conservative measures to assure the Technical Specification f- limit is not exceeded.

U The 18 month Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable from a standpoint of maintaining reliability.

SR 3.8.4.6 Battery charger capability requirements are based on the design capacity of the chargers (Ref. 3). According to Regulatory Guide 1.32 (Ref. 8), the battery charger supply is required to be based on the largest combined demands of the various steady state loads and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the unit during these demand occurrences. The minimum required amperes and duration ensures that these requirements can be satisfied.

The Frecuency is acce> table, given the unit conditions requirec to perform tie test and the other administrative l FERMI UNIT 2 B 3.8.4 -6 Revision 1, 09/25/98 i.

DC Sources-Operating B 3.8.4 BASES-SURVEILLANCE REQUIREMENTS (continued) controls existing to ensure adequate charger performance during these 18 month intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.

SR 3.8.4.7 A battery service test is a special test of the battery's capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length corresponds to the design duty cycle requirements as specified in Reference 4.

The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.32 (Ref. 8) and Regulatory Guide 1.129 (Ref. 9), which state that the battery service test should be performed during refueling operations or at some other outage, with intervals between tests not to exceed 18 months.

This SR is modified by a Note that allows the performance of a performance discharge test in lieu of a service test once

,: per 60 months.

v_

SR 3.8.4.8 A battery performance discharge test is a test of constant current capacity of a battery, normally done in the as found condition, after having been in service, to detect any change in the capacity determined by the acceptance test.

The test is intended to determine overall battery degradation due to age and usage.

The battery performance discharge test is acceptable for satisfying SR 3.8.4.7 as noted in SR 3.8.4.7.

The acceatance criteria for this Surveillance is consistent with IEEE 450 (Ref. 7) and IEEE 485 (Ref.10). These i references recommend that the battery be replaced if its l capacity is below 80% of the manufacturer's rat' g. A L capacity of 80% shows that the battery rate of deterioration

is increasing, even if there is ample capacity to meet the f load requirements.

The Frequency for this test is normally 60 months. If the

, battery shows degradation, or if the battery has reached 85%

O l FERMI - UNIT 2 B 3.8.4 - 7 Revision 1, 09/25/98

L l DC Sources-Operating B 3.8.4 l

] .8ASES l l SURVEILLANCE REQUIREMENTS-(continued) of its expected life, the Surveillance Frequency is reduced to 18 months. Degradation is indicated, according to IEEE 450 (Ref. 7), when the battery ca>acity drops t' more than 10% relative to its capacity on t1e previous performance test or when it is 10% below the manufac .irer's rating. The 60 month Frequency is consistent with the recommendations in IEEE 450 (Ref. 7): however, the 18 month Frequency is based on previously accepted industry practice.

and the need to perform this test during an outage.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would remove a required DC electrical power subsystem from service. perturb the electrical distribution system, and challenge safety l systems. Credit may be taken for unplanned events that !

satisfy the Surveillance.

REFERENCES 1. 10 CFR 50. Appendix A GDC 17.

2. Regulatory Guide 1.6.

kJ 3. IEEE Standard 308, 1978. l

4. UFSAR, Chapter 6. l

5. UFSAR, Chapter 15.

6. Regulatory Guide 1.93.

7. IEEE Standard 450.

8. Regulatory Guide 1.32, February 1977.

9. Regulatory Guide 1.129, December 1974.

10. IEEE Standard 485, 1983.

11. UFSAR, Section 8.3.2.

l FERMI UNIT 2 B 3.8.4-8 Revision 1, 09/25/98

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1 S f E l't R l' M 1 erd & S'. Y l ELECTRICAL POWER SYSTEMS N.so h 3/4.8.2 D.C. SOURCES D.C. SOURCES - OPERATING

[g g %Ym gj gm Nari I.Mg))

fg g,7, LIMITING CONDITION FOR OPERATION uo 3.8.2.1 As a minimum, fthe follow' g D.C. electrical power sources shall be 37q OPERABLE:

}

I a. vision I. con sting of:

I 1. 130 VDC attery 2A-1.

2. ~ 130 V Battery 2A-2. bA5' l

3. Two 0 VDC full capa ty chargers,

b. Divisi II consisting :

1. 30 VDC Battery -1.

( 2. 130 VDC Battery B-2.

( 3. Two 130 VDC f I capacity cha ersy I APPLTCABfLITY: OPERATIONAL CONDITIONS 1, 2, and 3. !

ACTION:

g, a With a battery charger in either Division I or Division II of the above ALTtotJ 4 D.C. electrical power sources inoperable, restore the inoperable battery charger to OPERABLE status (or reslace wtp tne soarvbattery ch#get gpon c, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With either Division I or Division II of the above required D.C.

O (V Acttora 8 electrical power sources otherwise inoperable, restore the inoperable division to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 A CTl0td C- hours.8 SURVETLLANCE RE0VIREMENTS 1

4.8.2.1 Each of the above required 130-volt batteries and chargers inall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

S u.

$ptKwahm [1. The 1.7. 4 L and parameters in Table 4.8.2.1-1 meet the Category A limits,

2. Total battery terminal voltage is greater than or equal to 130 M '5'7'41 volts for Division I and greater than or equal to 125.7 volts for Division 11 on float charge, b.

At least once per 92 days faIEFwn.nin 7 days atter a battery s I' Joiscnarge witn cattery terminal voltage less than 105 volts, o 8 Spc;IcqHon battery overcharge with battery terminal voltage greater than 150 I

) volts for Division 1 and greater than 145 volts for Division II, by i 3.t.L I "'"ifYi" l 1.

th*tf 4 @ M5

m v.r.2.aq The parameters in Table 4.8.2.1-1 meet the Category B s, l

['This ACTION may be delayed for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for battery chargers made

/ inoperable due to loss of EECW cooling provided the ACTIONS of Specification l

3.7.1.2 are taken.

\ u l\ Set Spc;5ccaKm 3. 7. '2 FE I - UNIT 2 3/4 8-10 Amendment No. 80.121 PAGE i 0F 02 Pu i

i .$$G;Cf FICA 77CA) f.[,t/

i ELECTpfCAL POWER SYSTEMS (Aiso su spe;%is n.4.)

i SURVEILLANCE REOUIREMENTS (Continued) 4

2. There is no visible corrosion at either terminals or j 6A D2- connectors, or the connection resistance of these items is l 1ess than 150 x 10 6 ohm, and su \ p. The average electrolyte temperature of ten cf the connected

pchbm 3.24 cells is above 60*F.

c. At least once per 18 months by verifying that: i L

f gg 3.y,d,3 1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnomal deterioration, 5 4 '5. yg.t/ 2. The cell-to-cell and terminal connections are clean, tight, '

free of corrosion and coated with enticorrosion material, N 3, y,y* g 3. The resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10 ' ohm, and '

4. The battery charger will supply at least 100 amperes at a 7 3' 8'Y' b j

minimum of 129 volts for Division I and at a minimum of 8

~

124.7 volts for Division II for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ! i 1 d. At least once per 18 months by verifying that_either*

i 1.

oc s:m IO4 -

1 The battery capacity is adequate to suppiy ind maintain in M 7. FA.~7 OPERABLE status all of the actual emergency loads for the design duty cycle [U M = 0 when the battery is subjected t ' '

f a battery service test, or "

. anu D tery capac1sy is

[Q uguate tu supply a o y loao of \

the llowing profile w le maintaining the b tery terminall vol age greater than o equal to 105 or 210 its, as ap icable:

4

) Batteries 2P and 2PB greater than r equal to 710 '

amperes dur' g the initial 6 seco s of the test.

1 b) Batteries A and 2PB greater th 182 amperes dur' g i

the next 2 seconds of the test i

c) Batteri 2PA and 2PB greater an or equal to j ampere during the next 4 hou s of the test,

< d) Batte ies 2PA and 2PB greate than or equal t 480 amne et durino the last 6 rnnrfe af + ka +me 4-

. sA N oTir - - - - -

s _ _

e. / At least once per 60 months (durino shutdownIby verifying that the g .5'7'd'Fn' battery capacity is at least 80% of the manefacturer's rating when t

subjected to a performance discharge test. lAt thTs once per 60-

g 3.t M.~7 g8 N. month in lieuintervas, of the batteryinis performance service test. oisenarge test may be performed

f.

1 At least once per 18 months performance discharge tests of battery i capacity shall be given to any battery that shows signs of

! degradation or has_ reached 85% of the service life ernected for j i the anolication. /Degrad ion is inoicated when he battery

! capac' prev' usyperformance drops more tha 10% of rated capacit from its averag on sts, or is below 90%

i the manufactur 's Q t' g. j LA.'I

O i

FERMI - UNIT 2 3/4 8-U Amendment No. M , 121

'02 4 P GE A -

0F fox /I 2

-, , -__~ ,.

. . - . - . . - . . - . . . - -... ._ .- - -.-- - . - ..... . - - ~ . _ . . _ - - . . .

DC Sturces-Operating 3.8.4 SURVEILLANCE REQUIREMENTS O SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 7 days

'T '7 *) , g -

P// 2 "?^%on float charae.

(iio (fv diWsionT. M (125,7 9-/w bm H.

SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.

E eac k-to-pll and @ inak _

Verify tterhconnection resistance (is s 41.5E-4 ohok fe- 4=+- -r-" =- ---ti e r .

f. l 4 :1.;:- ? il *a- 4=+== n d e;...;;ti n e, f ;:1.EE ' - M f:r int:r ti;r ........u ..e, r-1 f [1 U A 4-] f;r te,;.ir.;1 r u ntier,e].

(*I SR 3.8.4.3 Swww.y batter cells, cell plates, and '

months racks i. F.e visual indication of physical damage or abnormal deterioration. [ll.%.2.. ( , C ' !-

SR 3.8.4.4 Remove visible corrosion and verify battery months cell to cell and terminal connections are f,j -[:!r : d tigt. r-'] coated with 4 8' 2* I' O *'2- )

anti-corrosion material. l 1

"h AY YMEO /8 SR 3.8. Ver' fiibattery/ connection resistance montns j tac 5 J . 5E 4 04 fer '-t- -r-" ~----+ a= = -

C . ", -4 alsh -- ' - anest4enei p*g s ;1.;;-4 -Q Te. intop-44cr =xxtirr. %E,2,1 0. 3 nd ; lI.5E M i ] f-- t; nt--'

ex..xt ....J .

i (continued)

J sun -tu 3.8-25 . n 1, 04/07/^5

- \~

_ _ _ _ _ . . _ _ _ _ ~ _ _ _ _ _ . . _ _ . . _ . . . _ . _ _ _ . _ _ _ _ . _ . . _ . . . _ _ _ _ _ _ . _ _ _ _ . _ - .

DC Sources-Operating i 3.8.4 l

l t

g SURVEILLANCE REQUIREMENTS (continued)

/C75

\

SURVEILLANCE FREQUENCY SR 3.8.4.6 ---- ------ I --NO 'E--------- ------ #-

Thi Surveil nee s 1 not be erfome in E 1, , or 3. However, dit a be l oI

r. t en for plann events th satis j is SR.

,p,70;63;mT,.* Verify each required battery charger (18monthsf supplies:i 7 00 m : fr statie-ee m te l'

-9 eye +-' . =d 2 100 amps fe, 0". /t-(,g, t ,j , c , L}

"9 err +-r] at 2 {129[ V for _2 (4} hoursy N QDysWE' 2 too anyg Qntq.i VT,v- } ( nour5~

SR L8.4.7 -----------

--NOTEh-QP.I K The Mified perfomance discharge test in SR 3.8.4.8 may be performed in [y.T.2.1, e) lieu of the service test in SR 3.8.4.7 once per 60 months.

4. his surve lance shall et be perfome in MODE 1, or 3.

. However credit may taken for unplanced events th satisfy th SR.)

d Verify battery capacity is adequate to

{18 months (

supply, and maintain in OPERABLE status, theer;t:f n:gency loads for the design /q N,g,1,g,d\

duty cycle who subjected to a battery /

l 9.I service test. - -- - -

=

ackat orsimtl0kh (continued)

SWR /* ATE- 3.8-26 "r; 1, 01/07/ M l

i

O '

hv I

l. _

DC Sources Operating B 3.8.4

Os ~

%/

l l

INSERT B 3.8.4 2'-

such that under the worst case condition, with no battery

charger available and the battery cell- electrolyte l temperature at 60*F, the batteries are able to carry all

! required loads for four hours without the minimum cell ,

l voltage dropping below 1.75 VDC for Division I and below 1.81 VDC for. Division II, j i

O l 1 (h

!V t

FERMI UNIT 2 Page B 3.8 51 (Insert) REVISION 1, 09/25/98l

4 ELECTRICAL POWER SYSTEMS 9EC/Ae4770Al.3.F.6 C. SOUR E -

R ING b80

M #

1

[Also su .SyciRca Hsn 3. 7.2-)

[T)

LIMITING CONDITION FOR OPERATION (3.8.2.1 As a minimum,-the' following D.C. electrical power sources shall be

' OPERABLE:

a. Division I, consisting of:

1. 130 VDC Battery 2A-1.

2. 130 VDC Battery 2A-2.

3. Two 130 VDC full capacity chargers. i i

b. Division II, consisting of:

1. 130.VDC Battery 28-1. i

'2 . 130 VDC Battery 28-2. l

) 3. Two 130 VDC full capacity chargers.

APPLfCABfLITY: OPERATIONAL CONDITIONS 1, 2, and 3.

)

i y [. ACTION:

th i.

bg With a battery charger in either Division I or Division II of the above 1

N[A D.C. electrical power sources inoperable, restore the inoperable battery charger to OPERABLE status or replace with the spare battery charger

!' within in COLD4SHUTDOWN hours or be in at within theleast HOT following SHUTDOWN within the next 12 ho 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . '

[ b.

. With either Division I or Division II of the above required D.C.

electrical power sources otherwise inoperable restore the inoperable l

4. division to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or,be in at least HOT SHUTDOWN within Y .

hours."the' next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 .

SURVETLLANCE RE0VIREMENTE '

4.8.2.1 b 1 demonstrated OPERABLE:Each of the above required 130-volt batteries and charg

,4 f

a.

.At least once per 7 days by verifying that:

' 5R 3.3.f . l 1.

{hg parameters in Table 4.8.2.1-1 meet the Category A limits,

[ Su \ .

otal battery terminal voltage is Spt@caktn LK q/ voltsforDivisionIandgreatertkreaterthanorequalto130an or equal to 125.7 volts fe DLvision !! on float charge. _

b. 2Li hovr.S ['j i

At least once per 92 days and within(7Arys ,a er te h M 3.E.(a.'2- dischargewithbatteryterminalvoltageienthan105volb :

battery overcharge vo with battery terminal voltage greater than y,y r ion I and greater than 145 volts for Division II, by 50 I l ,

5-1.

e i The parameters in Table 4.8.2.1-1 meet the Category B limits, j- This i ACTION may be delayed 'for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for battery chargers made i' '3.7.1.2 noperable due to loss of EECW cooling provided the ACTIONS of Specifi are taken.

l FERM - UNIT 2' a Srib > saz) 3/4 8-10 4 _ . . .

Amendment No. 80.121 t

fASE 1 QF 03 61 8

i , . - . . -

SPGC i FtcNnon) .3 L(o ELECTPTCAL POWER SYSTEMS r SURVElllANCE REOUIREMENTS (Continued)

( 5" 2.

%' There is no visible corrosion at either terminals or

[ connectors, or the connection resistance of these items is less than 150 x 10 6 ohm, and SR 3, 74,3 3.

The cellsaverage is aboveelectrolyte 60*F. temperature of(ten /of the /onnecte()

c. least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show no visual 2.

indication of physical damage or abnomal deterioration, i The cell-to-cell and terminal connections are clean, tight, !

3. free of corrosion and coated with anticorrosion material, The is lessresistance of each than or equal cell-to-cell to 150 and terminal x 10 ' ohm, and connection

4. The battery charger will supply at least 100 amperes at a j minimum of 129 volts for Division I and at a minimum of 8

124.7 volts for Division II for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . I i

d. At least once per 18 months by verifying that either:

1.

The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual ' emergency loads for the gF[gggg design duty cycle (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) when the battery is subjected to a battery service test, or 3 *%M

2. !'

'The' battery capacity is adequate to supply a dummy load of the following profile while maintaining the battery terminal voltage applicable:

greater than or equal to 105 or 210 volts, as l

{ a) Batteries 2PA and 2PB greater than or equal to 710

amperes during the initial 6 seconds of the test.

b)

Batteries 2PA and 2PB greater than 182 amperes during the next 42 seconds of the test, c) Batteries 2PA and 2PB greater than or equal to 54 amperes during the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the test.

d) Batteries 2PA and 2PB greater than or equal to 480 amperes during the last 6 seconds of the test, e.

At least once per 60 months during shutdown by verifying that the battery capacity is at least 80Y, of the mar.ufacturer's rating when subjected to a performance discharge test. At this once per 60-month interval, this perfomance discharge test may be performed

.in lieu of the battery service test. .

f.

At least once per 18 months performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation the application. or has reached 857. of the service life expected for Degradation is indicated when the battery capacity drops more than 107. of rated capacity from its average on previous rating. performance tests, or is below 907. of the manufacturer's

%J FERMI - UNIT 2 3/4 8-11 Amendment No. 95,121

~

PAGE c1 0F 03 6I

5%6/FIc4770d 58./ !

, <}

\ REFUELING OPERATIONS

' (A1w su- SpeciRcahw 3.12-)

g <f,g g ,

SURVEllt ANCE REOUTREMENTS 9.1.1 position Refuel The reactor mode switch shall be verified to'be locked in the Shutdown or as specified:

i h a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to:

pq 1. Beginning CORE ALTERATIONS, and

\ 2. Resuming CORE ALTERATIONS when the reactor made switch has been unlocked.

t b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , SR 3.9al. I g,

i.S.i.2 Each of the above require eactor mode switch Refuel osition interlocks

mshallu...e be demonstrated

. 4 n ,. +- %

OPERABLE e+, + d by performance of a CHANNEL FUNC_UONAL TEST de- %,

sg withdrawa 3.

or ORE ALTERATION as applicable.=n3 at least once per 7 days (during contro 4.a mnm una ouvvp . yu n su . s mw mwww swi6cn neruei s u. ion interiou that iV affected shaly be demonstrate OPERABLE by perfo ance of a CHA EL i

FUNCTI,0NAL TEST prior o resuming cont 01 rod withdrawal or CORE ALTERATI0 , as !

pj appl} table, followin repair, mainten ce or replacement of ny component tha could LLfe'ct the Refuel o citinn int rinc - )

v i l i

l. Sal l l

t 5d b 5puifkak The reactor mode switch may be placed in the Run or'Startup/ Hot Standby 3,10.7. position to test the switch interlock functions provided that all control rods are verified to remain fully inserted in core cells containing one or more fuel assemblies by a second licensed operator or other technically qualified member of the unit technical staff.

u FERMI - UNIT 2 3/4 9-2 Amendment No.116 PAGE e4 0F 02 04/ I

SPECIPic@ohJ 3R.2.

O V

REFUELING OPERATIONS (%n seeH SfecdRcaNem H s.9.1) 3,g SURVEILtANCE REOUTREMENTS

,4.9.1.1 The reactor mode switch shall be verified to be locked in the Shutdown or Refuel position}as specifie{

Wi n 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pri to:

Beginnin' ORE ALTERATIONS, nd 2.

Resum unlo ed.g CORE ALTERATION whenthe.*eactormodeswi[hasbkn

b. At least once per hours.

SR 39.Z.g,.0... V

' L Each of the above required eactor mode switch Refuel position interloc *

/T($g\i (z; shall be demonstrated neurs r'- tr th; OPERABLE by performance of a CHANNEL FUNCTIONAL TEST mun

rv" =; at least once per 7 days during control rod

+ n withdrawal orp0RE ALTERATION 5} as applicable.

WLNM 6.1.3 6% Each of the above required reactor mode switch Refuel position interlocks

that is affected shall be demonstrated OPERABLE by performance of a CHANNEL 38.

FUNCTIONAL TEST prior to resuming control rod withdrawal or CORE ALTERATIONS, as bq applicable, following repair, maintenance or replacement of any component that could

{fect the Refuel position interlock.

<A dd : se a.9.2. 2. ^Iok- %

M Spec The reactor mode switch may be placed in the Run or'Startup/ Hot St y, position to test the switch interlock functions provided that all control y rods are verified to remain fully inserted in core cells containing one or

,more fuel assemblies by a second licensed operator or other technically qualified member of the unit technical staff; O FERMI - UNIT 2 3/4 9-2 Amendment No.116 PME c2 0F 02 &(

l

$9ED Rc41od _F, t p.*L Also see. K'Ra #en /, o ) l n a o 5.ie.3 ) l DEFINITIONS <l " "

ddo V ) l

. TABLE 1.2

, Sperjhc,km OPERATIONAL CONOTTTONS l bo {

L j MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature t 2. STARTUP Startup/ Hot Standby Any temperature

3. HOT SHtTIDOWN ShutdownI ,*** > 200* F

4. COLD SHUTDOWN ShutdownI ,II.*** s 200* F****

hpfliC4bIf -

l S.

~

REFUELING

Shutdown or Refue s 140* F 1 I

The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully jnserted in core cells containing one or more fuel assemblies a secgild T l perator or oprer tecnnicasiyqualified myrrber or tp unit tje'chnical)

G The reactor mode switch may be placed in the Refuel position while a single fIped8ca4m control rod drive is being removed from the reactor pressure vessel per 3.io.4 5 ecification 3.9.10.1.

g

Fuel in the reactor vessel with the vessel head closure bolts less than fully

,g tensioned or with the head removed.

/* **See Special Test Exceptions 3.10.1 and 3.10.3.

W* M *The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out 3'[- interlock is OPERABLE.

ru See Special Test Exception 3.10.7.

SFttiktahat\ '

Io : 1.w 3,to,2. .b Add: 3.to.2 knorLS 5R Lo,2./ M S 2 .3.to . 2. 2-FERMI - UffiT 2 1 10 Amendment No. U , JJJ 116 PAGE i 0F 01 bI

SPECIncA'notJ 3 I0.2-

}

REFUELING OPERATIONS {[Mso see .Speedf*6He t, u il 3 77 SURVEllt.ANCE REOUTREMENTS 4.9.1.13e Refuel reactor position mode' as specified: switch shall be verified to be locked in the S

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to:

1. Beginning CORE ALTERATIONS, and Spudake y' 7 2. l Resuming CORE ALTERATIONS when the reactor mode switch has been unlocked. l b.g At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.x 4.9.1.2 Each of the above required reactor mode switch Refuel position interlocks

9db6, shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST within ,

3A*I i 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of and at least once per 7 days during control rod

$ withdrawal or CORE ALTERATIONS, as applicable.

4.9.1.3 .Each of the above required reactor mode switch Refuel position interlocks

that is affected shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST prior to resuming control rod withdrawal or CORE ALTERATIONS, as applicable, following affect the Refuel repair, maintenance position interlock. or replacement of any component that could

( y L(p 3./02. 4 *

\ L.R.I

/

The reactor mode switch may be placed in the Run or Startup/ Hot Standby N position to test the switch interlock functions provided that all control rods are verified to remain fully inserted in core cells containing one or. 8 qualifie<Vmember of thfunit techni@l staff:,more fuel mesemblies !

O FERMI - UNIT 2 3/4 9-2 Amendment No.116 pg g 0F 02 NI ~

DISCUSSION OF CHANGES ITS: SECTION 3.10.2 REACTOR MODE SWITCH INTERLOCK TESTING n

TECHNICAL CHANGES LESS RESTRICTIVE

" Generic" -

LR.1 CTS Table 1.2, Note #, and CTS 4.9.1.2 & 3. Note *, allow mode switch interlock testing to be conducted provided that "a second licensed operator or other technically qualified member of the unit technical staff" verify that control rods are fully inserted.

ITS 3.10.2 does not specify the method or administrative controls for verifying that control rods remain fully inserted. The details of how this verification is performed are removed from the Technical Specifications. Regulatory control of changes to these requirements (e.g., Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since the requirement for the control rods to remain fully inserted is still required by the Technical Specifications.

TECHNICAL CHANGES - LESS RESTRICTIVE

" Specific" l } L.1 Not used.

R E0CATED SPECIFICATIONS None

.O V

FERMI UNIT 2 2 REVISION 1. 09/25/98l

, ~ . _ . . - . . _ _ . _ _ . _ ... ._.._._._ _ ._ _ -... _ _. . . _ . - _ . . . . _ . . _ . _ _ . _ . . . _ _ _ _ _ _ . _ . _ . . . _ .

~

NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.10.2^ REACTOR MODE SWITCH INTERLOCK TESTING

)

, ? TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.10.2 "L.1" Labeled Coments/ Discussions)

Not used.

l 1

4 1

. O 4

4. ;

I d

J s

4 L

Y 3.

t

.FERHI.- UNIT,2 1 REVISION 1 09/25/98l.

L !

l O ELFICAnch] 3,to,3

[kiSO$elSpecifcca % t.o ')

A C" "" " .3. (0, L ')

DEFINITIONS' OHel /" " S , /o , Y )

0; v ABLE 1.

! Set l

, seweCaken PERATIONAL CONDITTONS t.o

)

l . i MODE SWITCH F AVERAGE REACTOR

! CONDITION POSTTION COOLANT TEMPERATURE l i j, 1. POWER OPERATION Run Any temperature ETADT"D 't -t"-/.":t St:-^y Any temperature

3. HOT SHUTDOWN ShutdownI ,*** > 200* F

4. COLD SHUTDOWN Shutdown I ,88,*** s 200* F****

l (5 - REFUELING

Shutdown or Refuel **,# s'140' F i

l l

l e reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related D.N instrumentation provided that the control rods are verified to remain fully L 3dO1 inserted in core cells containing one or more fuel assemblies by a second L licensed operator or other technically qualified member' of the unit technical gff.

! #A The reactor mode switch may be placed in the Refuel position while a single QuikceHm control rod drive is being removed from the reactor pressure vessel per j 3,,o,Q Specification 3.9.10.1.

64 el in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

5paikake

l. l'D

See S ecial Test Exceptions 3.10.1 and 3.10.3. .

' tg 3,gj3,g***The reactor mode switch may be placed in the Refuel position while a single f control rod is being @ ana h m withdrawn provided that the one-rod-out Agl%W h4 interlock is OPERABLE.

See Special Test Exception 3.10.7. I,2 ses Spett0ca#m

/. o l

[

i

! , FERMI - UNIT 2 1-10 l Amendment No. 25, JJJ 116 PAGE 1- 0F 03 g,g i

- . . .- - . . - . - - . = - . - - . - . -.. .

SkaptcAnM 3.t0ll

{Ako$2L&ci(itah%

(.D )

l" 3. ro .2.

DEFINTTIONS [" 3 loo O .

ABLE 1.2. 'I Sf M '* M OPERATIONAL CONDITIONS I.o l MODE SWITCH AVERAGE REACTOR CONDTTTON POSITTON COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature

2. STARTUP Startup/ Hot Standby Any temperature

3. HOT SHUTDOWN shutrinwn8 *** > 200* F

4. COLD SHUTDOWN Shutdown I ,88,*** s 200* F**** l

5. Kt.P ut Lints' Shutdown or Refuel **,' s'140' F re, 8 The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related Spes:0:omb 30.2_ instrumentation provided that the control rods are verified to remain fully inserted in core cells containing one or more fuel assemblies by a second licensed operator or other technically qualified member of the unit technical

(( taff.

88 The reactor mode switch may be placed in the Refuel position while a single L(A3.104 control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.

sa Fuel in the reactor vessel with the vessel head closure bolts less than fully g;[gg tensioned or with the head removed.

f. O *See Special Test Exceptions 3.10.1 and 3.10.3.

- - The reactor mode switch may be placed in the Refuel position while a single g3g control rod is being r- ' ' ~ ' withdrawn provided that the one-rod-out interitsck is OPERABLE.

Su See Special Test Exception 3.10.7. A.2.

Sydbbm ,

l.o l

() FERMI - UNIT 2 1-10 Amendment No. JJ, JJJ 116 _

PAGE 1 0F .03 fes /

SPED PtcMp0s) & T 0

M N" N"1 S' SURVEILLANCE REOUTREMENTS

[0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance

Requirement.

i 4.0.2 Each Surveillance Requirement shall be performed within the specified 4

surveillance' interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. For the purpose of the sixth refueling outage, those Surveillance Requirements listed on Table 4.0.2-1 and l i

4.0.2-2 are extended to the date specified in the table.

5 4 Failure to perform a Surveillance Requirement within the allowed g$%g / rveillance I

su.0.3 interval, defined by Specification 4.0.2, shall constitute

' noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

- The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the

completion of the surveillance when the allowable outage time lim ~its of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

1 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable i ~

condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision all not prevent passage through or to OPERATIONAL CONDITIONS as required to ely d th ACTION requirements.

g g 4-et Surveillance Requirements for inservice inspection and testing of AS Code Class 1, 2, & 3 componentsahall be applicable as follows:

Lq j

p Inaervice imspec1.lon or asML ode Class 1, z, a 4 component.s anu '

' inservic testing of ASME de Class 1, 2, and pumps and valves shall performed in ace dance with Sectio I of the ASME

Bolle by I CFR and 50, Pressure Section Ves 1 Code and applica e Addenda as requ ed

.55a(g),except re specific writt rel ef has been grant d by the Commissi pursuant to 10 CF 50, ion 50.55a(g)(6) 1), f 554,a g SurveillanceintervalsspecifiedinSectionkloftheASMEBoiler and Pressure Vessel Code and applicable Addenda for the inservice

inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications

1 I

i PAGE c2 0F 24 FERMT - UNIT 2 3/4 0-2 Amendment No. JJ, EE, JEE.124 Rd I 1

r i ~

YEdif1C$7]&& (*&

l TABLE 3.3.7.5-1 (Continued) ISO * $ cikah'es M.L h

/

ACCIDENT MONITORING INSTRUMENTATION

t. -

ACTION STATEMENTS l ACTION 80-a.

(

l fWith the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7, days or be in at least l HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , giheYpfdw b. With the number of OPERABLE accident monitoring instrumentation channels

! 3'O'3'l less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in i at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 81 - With the number of OPERABLE channels less than required by the minimum l

channels OPERABLE requirements, initiate the preplanned altemate method -

of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable channel (s) to OPERABLE status within 7 l ( days of the event, or

,3F prepara and submit a Special Report to the Commission pursu' o A.I L

{,y,'} Specificaten 8.9.2 within 14 days following the event outlining to action taken, the cause of the inoperability and the plans and schedu' 1r O restoring the system to OPERABLE status.

ACTION 82 IWith the number of OPERABLE accident monitoring instrumentation cha less than required by the Minimum Channels OPERABLE requirements of 5cc Table 3.3.7.5-1, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months either:

a. Restore the inoperable channel (s) to OPERABLE status, or H .3,I b.

l Declare the affected isolation valve inoperable and take the ACTION h specified by Specification 3.6.3 ACTION a.

J t

ACBON83 -

! a. With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore he inanmble channel (s) to OPERABLE status within 30 days, or submit a i

{'g] report to the Commission pursuant to Specification 6.9.2 within the following ],

14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the instrument channel (s) to OPERABLE status.

E With the number of OPERABLE accident monitoring instrumentation channels W less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in

$peiMNth at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , 3,3.'6. I C i

e g g me i w o5 y

$PctF1 s.47ze>J !o

({M20n s n .S/kJ* Aca Non 3, 3,waz.)

w.3)

DEFINITTO W "

I ' ' "

2' # ' Y )

TABLE 1.2 0'"'- ",7 ^ 0;im CenLi-^ ;

{Af00E5 )

TIIIf, MODE SWITCH AVERAGE REACTOR J:0!TM POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run_ Any temperature

2. STARTUP

..-kleMk i A StaMup/ Hot Standby Any temperature

3. HOT SHU1DOWN I A A Shutdown8 ,*** > 200* F

4. COLD SHUTDOWNbN Shutdown 8 ,88,*** M s 200* F****

5. REFUELING

I Shutdown or Refuel 8 a ';40" T ih fCf-N b (8TheRefuel reactor mode switch may be placed in the Run, Startup/ Hot Standby, position to test the switch interlock functions and related 3,80 L l Iinserted in core cells containing one or more fuel assemblies by a 0,

(licensed staff. / operator or other technically qualified member of the unit technical (4- 88 The reactor mode switch may be placed in the Refuel position while a single Sptu4lCaN control red drive is being removed from the reactor pressure vessel per 3(04 Specification 3.9.10.1. fe. or mwt) .

( Q

N :1 '- the --Sc+c- "=er- "!th t4 vessel head closure bolts less than fully 4,fk ensioned or with the head removed. ,

'**See Sp::i:1 Test Oceguvns 5.iv.i ano 2.10.0. -~

Sa sgt;6h **The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out j,g 7 ,, ,,3{ interlock is OPERABLE.

- - - taa (nam 2! T::t Ocepuer. 3.10.7. -- ---

&c *N l}DO;l.l.lsGICK0nMb ly }eyS, ! f 0MPLEDMll/MS

/ t.4 Rmwe</

,lb

(~

' V) FERMI - UNIT 2 1-10 Amendment No. JJ, JJJ 116 PAGE OF 14 9M

i:

E

$9E.4Ffcetriod .K t a,'L

[ M50 o

54 %hkan

't

/.D )

3. se ,3 )

DEFINITIONS e/ H h

ddo V )

V I 1

60- ~ TABLE 1.2{

l

! , Spu@km OPERATIONAL CONDITIONS

, l t.o L

MODE SWITCH

}E CONDITION i

POSITfON AVERAGE REACTOR COOLANT TEMPERATURE i 1. POWER OPERATION Run Any temperature

2. STARTup Startup/ Hot Standby Any temperature

3. HOT SHUTDOWN Shutdown 8 ,*** > 200* F

!~ 4. COLD SHUTDOWN ShutdownI '8,*** s 200* F**" i

5. REFUELING

Shutdown or Refue s'140' F i 8 The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related i instrumentation provided that the control rods are verified to remain fully

' p inserted in core cells containing one or more fuel assemblies l)y a sec d l

perator or o3Ntr tecnnu;as syqualif ted mylDer of 1;pr unit t hnical 4

4 b

j @ScMim {i control rod drive is being removed from the reactor pres I

{ ~ 3. t o Y Jecification 3.9.10.1.

g

Fuel ~ in the reactor vessel with_ the vessel head closure bolts less than fully

{

pg.g tensioned or with the head removed.

l

- See Special Test Exceptions 3.10.1 and 3.10.3.

1I 5" 5 '* 4 * *The reactor mode switch may be placed in the Refuel position while a single i control rod is being recoupled or withdrawn provided that the one-rod-out ji interlock is OPERABLE.

3*['3

, See Special Test Exception 3.10.7.

i Qttlktshot\

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{AM: Lw 3.i0.2. .b M.

Add: 3 to.2 Acmil5

- S R ?.to, 2 .1 T

S E 3 to ,2. 2-4 ,

FERMI - UNIT 2 1-10 Amencment'No. U , JJJ 7 116 B

mGE A 0F 0F bI

$fE4 Pit'Anobl 3stoo3

[Also set. Speafica kon c- " ~ .s,

/.0 e )> \

DEFINITTONS {Ml /"" " 8' * ' Y }

l I

.O U ABLE 1.t See

, $gggg PERATIONAL CONDITIONS

/,0 l

t MODE SWITCH AVERAGE REACTOR F

CONDITION POSITION COOL ANT TEMPERATURE !

1. POWER OPERATION Run Any temperature sTanmo et -t ;/":t it:- ^y Any temperature

3. HOT SHUTDOWN Shutdown'I ,*** > 200* F

4. COLD SHUTDOWN Shutdown I ,88,*** s 200* F****

t.5 REFUELING

Shutdown or Refuel **,# s'140' F l

Sg e reactor mode switch may be placed in the Run, Startup/ Hot Standby, or D., Refuel position to test the switch interlock functions and related MO*2- instrumentation provided that the control rods are verified to remain fully inserted in core cells containing one or more fuel assemblies by a second O licensed operator or other technically qualified member of the unit technical gff. i The reactor mode switch may be placed in the Refuel position while a single St *4kc6m control rod drive is being removed from the reactor pressure vessel per 3,,o,q Specification 3.9.10.1.

$4 el in the reactor vessel with the vessel head closure bolts less than fully 5puka4ie tensioned or with the head removed.

l'D See Special Test Exceptions 3.10.1 and 3.10.3.

6 LO; 3 (***The reactor mode switch may be placed in the Refuel position while a single control red is being @a"ahNwithdrawn provided that the one-rod out Agl; law h4 interlock is OPERABLE.

See Special Test Exception 3.10.7. I,2-su Sputkcakm

/.O FERMI - UNIT 2 1-10 Amendment No. 25, JJJ 116 PAGE 1- 0F 03 gy f

i 1

i SPECNICAnbra Lt0/{

' h 54L"'@ ficAhan

I.D )

L" 3.to A

[" ^

3*'0'3 O DEFINTTTONS

.ABLE 1.2 sa Sfed A 'Md OPERATTONAL CONDITTONS l l 1. 0 1

/ l MODE SWITCH AVERAGE REACTOR j ,

CONDITION POSITION COOLANT TEMPERATURE

1. POWER OPERATION Run Any temperature

) 2. STARTUP Startup/ Hot Standby Any temperature

3. HOT SHUTDOWN shuttinwnf *** , > 200* F

] 4. COLD SHUTDOWN Shutdown i ,88,*** s 200* F**"

, nr. rut. u n c Shutdown or Ketuel**," s'140' F i

j ra The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Spet:enk Refuel position to test the switch interlock functions and related t 3m.2_ instrumentation provided that the control rods are verified to remain fully inserted in core cells containing one or more fuel assemblies by a second licensed operator or other technically qualified member of the unit technical i

%ff.

88 The reactor mode switch may be placed in the Refuel position while a single L(.43.lO.Y control red drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.

su Fuel in the reactor vessel with the vessel head closure bolts less than fully

, g;Q, tensioned or with the head removed.

l' O See Special Test Exceptions 3.10.1 and 3.10.3.

***The reactor made switch may be placed in the Refuel position while a single

' g3'g control rod is being r ' ' -" withdrawn provided that the one-rod-out interlock is OPERABLE.

i i Su See Special Test Exception 3.10.7. Al

}'

5%bbm i.,

s i

FERMI - UNIT 2 1-10 Amendment No. JJ, JJJ 116 ,

PAGE 1 0F 03 fes /

SMCim mto& Lo APPLICABILITY (Mso Sao .foecdice&n 55) l

' SURVEfLLANCE RE00fREMENTS g +,e. Appiteaan:H2 S# 3ed -4sM- 0;neilla[.o..y ... . :r; ;r.3 shall mer curing ne ==. r-@g- oa-O i -

40NHT49NG-er othertconditionsJspecified) or individual ti;itir; CrM4+4--CLCo s

6"""0;t ~.~;t5 T'- - unless otherwise stated In' = ir.d;^.^tds! !:r :i'?M 1

~ @ $ery 10

$A '3.0/2 - 4.".2 /E n surveill ce nequi....... -snais ce p.ssv.~ . w unin i;.. y i";

turveil ance'intary with a maxis perce of the sp ified surveill nceallowable interval. artorsion not to exce 25 O ' '

the purpose o the sixth refu ing outage those Survell nce Requiremen list on Table .0.2-1 andt 2-2 are ex nded to the da a enseified in a tab 1 54'3.0,3 4:6 3 1ral re to perro a surveillanc Requirement witni yn'qggy h i

11 ce interval, fined by Spec ication 4.0.2, sh ne allowed j

%noncomp anci! Wi+h +ha DFDAETIITV ** - . -4 r '+ ' fa"

l4 constitute / a.g DDerat on/[ he time limiu T Ine M 44WR s dir.m.nu are my+4"O -

fa"'litiarf fa 1 s us!,s w paa it 1 identified tha a Surveillance quirement has no been perfo e6 Lass The ACT N requirements y be delayed f .

: omple on of the sury up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months permit the ArTin renuirn- nte a lance when the llowable autane ime limits of h late than 24 h urs / 4 7 f -^ " '

-** da aa+

TN 5Er2T S.0 - 10 t 93 - nsry

'O sonddion in6. .o 0?2;MT:~im. CGsa7:0;; .,. ^..tr ; :i'id 2; 'i9'--

.d with the siting Conditt all not be mad unless the Surve lance Requiremen s) associate l applica e surveillance for Operation h a been performed ithin the J

shall terval or as et rwise specified. - his provision ,

t prevent pass e through or in odroaT!=ai_ e m giv__ n .. rannired ni ! i i

with ACTION re irements / .il l

QINSEET 3,o-11)

Code Class 1, 2, & 3 components shall be applicable as follows:ve a.

i Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 3, 2, and 3 pumps and valves M shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required

$h'ca h by 10 CFR 50, Section 50.55a(g), except where specific written 56 relief has been granted by the Comission pursuant to 10 CFR 50, Section so.s5a(g)(c)(1).

4 b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

i l

lO FERMI - UNIT 2 3/4 0-2 Amendment No JJ. JJ JSJ,124 PAGE --

5' O.* 12 ' '

5PEttFt orpord 55 APPLICABILITY SURVEILtANCE REOUIREMENTS 60.1 Surveillar.:e Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in' an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be perfomed within the specified surveillance' interval with a maximum allowable extension not to exceed 25 ~

percent of the specified surveillance interval. For the purpose of the sixth j i refueling cutage, those Surveillance Requirements listed on Table 4.0.2-1 and 4.0.2-2 are extended to the date specified in the table.

4

/su.0.3 Failure to perform a Surveillance Requirement within the allowed tg%9 rveillance interval, defined by Specification 4.0.2, shall constitute

' Operation.

noncompliance with the OPERABILITY requirements for a Limiting Condition for The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

have to be performed on inoperable equipment. Surveillance Requirements do not 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable O condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision a

gm,ll not prevent passage through or to OPERATIONAL CONDITIONS as required to 1v with ACTION requirements.

jgg. j[g g

+:t:t Surveillance Requirements for inservice inspection and testing of AS Code Class 1, 2, & 3 components hall be applicable as follows:

LAl f( In==rvicejinspection or asnt ode class 1, z, a .5 component.s uno inservici testing of ASME de Class 1, 2, and pumps and valves shall perfomed in acc dance with Sectio I of the ASME Boile by and 50, I CFR Pressure SectionVes 1 Code and applica e Addenda as requ ed

.55afg),except re specific writt rel ef has been grant d by the Conrnissi pursuant to 10 CF 50, Se tion 50.55a(g)(6) 1), f '

F.5.6 a,,M Surveillance intervals specified in Section kl of the ASME Boiler t

and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and i

Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications: i

{

l O l PAGE c2 0F 24 j FERME - UNIT 2 3/4 0-2 Amendment No. JJ, EJ. 195.124 l get \

WEDF1cAmN 30 j/ TABLE 4.0.2-1 SURVFit t AdTF[1NTERVA!S EXT;NDED TO S#PTFMBFR 14 1998 f,/O l SURVElllANCIP UTREMENT DESCRIPTT 4.3.1.1, Tab 4.3.1.1 1 RPs Rs steen D Press Nigh cal.

4.3.1.1. T toe 4.3.1.1*1, 4.3.1.1 1, Item 3 Item 4 RPS Rx Low er Level Level 3 cal 4.3.1.1 4.3.1.1, able 4.3.1.1 1, item RPS Main 5 em Line Radiatten Nigh cel item 6 7 RPs D Pressure Nigh cal 4.3.1.3, Table 4.3.1.1 1, Item 2.b , APRM FL Blased Thermal Power - Nish 4.3.1. , Table 4.3.1.1 1, Jtem 2.c APRM sed Neutron Flus Nigh 4.3. Table 4.3.2.1-1 Pri ont Isolation Actuation As Water Law - Level 3 cat 4.3 .1, Table 4.3.2.1 1, Item

, , Item 1.a.1 1.a.2 Pr cent Isolation Actuation Rx Wster Low Level 2 cat'

4. 2.1, Table 4.3.2.1*1, item 1.a.3 i Cent isolation Actuation Rx Water Low - Levet 1 ca

.2.1 Pri Cent isstation Actuation Drywell Press Nigh cal

.3.2.1,, Table Table 4.3.2.1 4.3.2.1 1, 1, ItemItem 1.c.1 1.b i 4.3.2.1, Table 4.3.2.1 1, Item 1.c.2 Pri cont Isoletion Actuation Main steen Line Radi on Nish col l Pri cont Isetation Actuation Main steen Line P Low cal. !

4.3.2.1, Table 4.3.2.1 1, Item 1.c Pri Cent isolation Actuation Main steam Line F Nish cal i 4.3.2.1, Table 4.3.2.1 1, J tem 1. Pri Cent isolation Actuation Main steen Li tsinet Temp. High cal l 4.3.2.1, Table 4.3.2.1 1, item e Pri Cent Isolation Actuation Consenser Prest Nigh cet 4.3.2.1, Table 4.3.2.1 1, it .f Pri cont Isolation Actuation Turbine 5146 Area Temp. Nigh cal l 4.3.2.1, Table 4.3.2.1 1, Ited 1.h Pri cont isolation Actuotion Manual tr4 tation functionet 4.3.2.1 Tabte 4.3.2.1*1 2.d RWCU - SLCS initiation channet f mc t test 4.3.2.1, Table 4.3.2.1 1, tem 2.e 4.3.2.1, Table 4.3.2.1 1 Item 5.s Rwu isolation Rx Water Low Level Level 2 channet cal RNR 5/D Cooling Rx Water Level - Level 3 cat 4.3.2.1, Table 4.3.2. , item 5.c RNR s/D Coeting As manuel fritJ6 tion fmetional test 4.3.2.1, Table 4.3.2 1 item 6.b sec. Cont. Isotation Drywe#1 Press Nish channel cal 4.3.3.1 Table 4.3. *1, item 1.b , Cs Drywett Press High Cal i 4.3.3.1 .ial, Jtem 2.b LPCI Drywell Press Nigh L 4.3.3.1, Table Table 44. .3.1 1 Item 3.a 4.3.3.1, Table .3.3.1 1, item 3.b MPCI RPV Low Level 2 t

, , NPCI Drywett Press N Cat 4.3.3.1, Tabt 4.3.3.1 1, Item 4.a ADS RPV Low Level 1 at 4.3.3.1, Tab 4.3.3.1 1 ADS RPV Low Level Cat 4.3.3.1 T to 4.3.3.1*1, , Item 4.f Item 4.h ADS Drywell PressWe Nigh Sypass Timor 4.3.4, able 4.3.4 1, Jtem 1 RPV Low Water H vel 2 Cal (ATWS) 4.3.4, Table 4.3.4 1, Item 2 RPV Press Mien Cat (ATWs)

4.3.4. ATW5 Logic ten Fmctionst Test !

4.3. Table 4.3.5.1 1, Item a RPV Low L L 2 Cat (RCIC)

.1, RPV Nig eyel 8 Ct.l (RCIC) 4.3)5.2, 4.s. Table 4.3.5.11,Itemb RCIC '. ic system Functional Test 1.7.5, Table 4.3.7.5 1, Item 1 RPV P ess Cal Accident Mon.

.3.7.5, Table 4.3.7.5 1, Item 2.s RPV uet Zone Level Cat Accident Mon 4.3.7.5, Table 4.3.7.5 1 Item 2.b "RP Wide Range Level Cal Accident Mon 4.3.7.5, Table 4.3.7.5 1, item 12 , MT Migh Range Red Monitoring Cat Accident Mon.

4.3.7.5, Table 4.3.7.5 1, Item 16 CTNT ! solation valve Position Cat Accident Mon 4.3.9.1 RPV Nish Water Level 8 Cal FW/ Main Turbine Trip 4.3.9.2, Table 4.3.9.1 1, Item a 3 FW/ Main Turpine Trip LSFT i 4.3.11.1, Table 4.3.11.1 1, item 7 Alt s/D system Rx Water Level instroent operabi ty 4.3.11.1, Table 4.3.11.1 1, item 8/ Alt s/D system RE Press instrunent operability 4.4.2.2.b sRV Low Low 5et Pressure setpoint Cat and Lsf 4.5.1.d.2.s ads system functional Test 4.6.3.2 Primary contaiment isot Valve operability 4.7.4.c.1 RCIC F mettonal Test 4.8.4.2.a.1.s Prf. Cont. Pen. Conductor Overcurrent 0 ices Fisictional feet 4.8.4.2. s. t . b Prl. Cont. Pen. Conauctor overcurrent evices functionet Test u

_y FERMI - UNIT 2 3/4 0-4 Amendment No. 206. 108. 124 D OF 12 PAGE gi

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l O FERNI k UNIT 2 -

3/4 0-5 Amendment No. Jpp,124 PAGE IR OF 57 R*/ I

StEClFuhDOTO 3:0

[ TABLE 4.0.2-2 Q SURVEILLANCEMST INTERVALS EXTENDED 18. 1998 TOy OdOBER f,

SURVEILLANCE RE001RE DESCRIPTION 4.1.3.5.b.2 CR Accisautator Integri 4.1.5.d.1 fest (Check Valve Leekage) sLCs operability 1nittetten 4.1.5.d.2 SLCs puse Relief Vet 4.1.5.d.3 operability sLCs flow path tration 4.3.1.1, Table 4. .1 1, Item 11 4.3.1.2 RPS Rx Mode Swit shutdown position functionet 4.3.2.1, Table .3.2.1 1, item 6.a RPs Logic system metten Test 4.3.2.2 sec. Cont. Isol ion - an Water Low Level - Level 2 cal 4.3.3.1, To e 4.3.3.1 1, item 1.s 1 solation Act tien Inst. LsFT 4.3.3.1, T le 4.3.3.1 1, item 1.c CS RPV Low L t 1 Cal CS as ste one Press Low Cat 4.3.3.1, le 4.3.3.1 1, item 1.d 4.3.3.1 able 4.3.3.1*1, item 2.s CS Manuel nitiation 4.3.3. , Tabte 4.3.3.1 1, Item 2.c LPCI RPV ow Levet 1 Cat 4.3.3 , Table 4.3.3.1 1, Item 2.d LFCI a steam Dome Press Low Cal LPCI Low Level 2 Cat 4.3 1, Tabte 4.3.3.1 1, Itee 2.e 4.3 .1, Table 4.3.3.1 1, Item 2.h LPC ax steen Dome Press Low cal 4 .3.2 LP Manuet Initiation 3.3.3(a) Cs Logic system Fmettonal Tests CCS Response Time Tests

.3.6, Table 4.3.6 1, Item 5.b 4.3.6. Table 4.3.6 1, item 7 scram Disc Vol. Trip Bypees Funct. Test 4.5.1.c.1 Rn Mode switen shutdown Pos. Aod stock F . Teet 4.6.5.1.d.1 ECCS system Functional fest 4.6.5.1.d.2 secondary contairement SGTs Test 4.6.5.2.b secondary contairinent SGTs Test 4.7.1.2.b seco asery conteirunent isolation Danpe Actuation 4.7.1.3.b ECCW Automette Actuation 4.7.1.4.b EESW Automatic Actuation

} 4.7.2.1.c.1 EDG Cooling Water Ptsup Automatic tuotion 4.7.2.1.c.2 CR ventitetton Fitter Penetrati 4.7.2.1.c.3 CR Ventilation Filter Charcoal /aboratory Analysis 4.7.2.1.e.1 CR Emergency Filtration syste9f Flowrote

4. 7.2.1. e.2 CR Ventitetton Filter Pressure Drop

4. 7.2.1. e.4 CR Emergency Filtration System Operational Mode Actuation

4. 7. 5. e Ca Emergency Makeup Intet ester Dissipation 4.8.1.1.2.e.1 snuteer Functionet Test EDC Inspection 4.8.1.1.2.e.2 4.8.1.1.2.e.3 EDG Load sejection (1 kW) 4.8.1.1.2.e.4.. EDG Load Rejection (2850 kW)

EDG LDP Load shedding 4.8.1.1.2.e.4f EDG LDP Auto start /and Lead sequencing 4.8.1.1.2. e J 4.8.1.1.2 6.s EDC ECCS Auto stort 4.8.1.1.2 .6.b EDG LOP / ECCSAoed shedding 4.8.1.1. e.7 EDG LOP / ECCFAuto start and Load sequencing 4.8.1. 2.e.8 EDG kon eseewtiet Trip sypees 4.8.1 .2.e.9 EDG 24 Mourjaun and Hot fast start.

4.8. 1.2.e.10 EDG Auto 06 meet Lead Verification 4.8/1.1.2.e.11 EDG Restoration of offsite Power 4 5.1.1.2.e.12.s EDC Aut4 Load secuencer Timer 4/8.1.1.2.e.12.b EDC 4140. volt Esf Bus Lockout p.8.1.1.2.e.12.c EDC Dif ferentist Trip Lockout '

4.8.2.1.c.3 EDC/ shutdown teley Trip Lockout 4.8.2.1.d 13e VDC settery Connections aesistance 4.8.4.5.s )SOVDCBatteryCanecity jsLCs Circuit greskers F mettonal Test TABLE NOTATIONS (a)

The surveillance int $rval of channels withiname thetrip system required to be terted at least once every N ti es 18 months, wher the total numberkf channels in the trip sys m. may be based up N is the er,formance W of pe surveillance dur1ng the sdxth ~ refueling outat e l

FERMI - UNIT 2 3/4 0-6 Amendment No. 106.124 PAGE // OF 12 %i

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FERNI - UNIT 2 PAGE1W4Tff ""'""'"'"'"'

57 Apil I

,r I

O PEC- @ lClrT1D N 3* W l REACTIVITY CONTROL SYSTEMS hfS6 TM S 6'fhd'AN#h

/ 8*^

_ LIMITING CONDITION FOR OPERATION (Continued)

EI1(3: (Continued)

2. If the inoperable control rod (s) is inserted, within I hour disarnr the associated directional control valves ** either:

Sh a) Electrically, or 7

S8'IO t4ficeliw h b) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HDT SHilTDOW within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

p. With more than 8 control rods inoperable, be in at least HOT

__ O 3d 'I _L l

SHUTD0WN,within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

- - d. -

With one or more scram discher7e volume vent or drain lines with one Acpog 4 valve inoperable, restore the inoparable valve (s) to OPERABLE status g h 7 days, or be in at least HOT SHUTDOW within the next 12

- - e. With one or more scran discharge volume vent er drain lines with bo+h Acr/oN B valves inoperable, isolate the associated line within a hourr>***, or pgc be in at least HOT SHUTDO W within the next 12 h r s.

SURVEILLANCE RE00fREMENTS

. .:.I.:- The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

sR3.I.8la. At least once per 31 days verifying each valve to be open.* and aluatingregr discharge yo system respops'e prior to p1 t LR. l startuo aftu each scram t erify that no genormalities e t.

.3.1.2 When above the preset pcwer level of the RW, all utthdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstratad OPERABLE by moving each control rod at (least one notch:

h a. At least once per 7 days, and 3,l.3 b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any contral rod is immovable as a result of C excessive friction or mechanical interference.

5 0 %

controls.These valves may be closed intemittently for testing under administra

/Su.

\S f '*-p**ay be rearmed intermittently, under administrative control, to permit

'3M

ting. associated with restoring the control rod to OPERABLE status.

- - 5eparate Action entry is allowed for each SDY vent and drain line.

An isolated line may be unisolated under administrative control to allow draining and venting of the SDY. "

hpf ad Az.% 8.I tJoH

- M Tis N s M o r g O~ FERMI ~DNIT 2 3/4 1 4 Amendment No. J/, SJi M,120 PAE 1 0F 02 g)

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l FERMI - UNIT 2 3/4.3-51 Amenament No. 83, 115 O

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I I-FERMI UNIT 2 3/4 3 52 Amenament No.115 cO

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l FERMI - UNIT 2 3/4 3 53 Amendment No. Ils .

O PAGE / / C. OF 57 hI

N l

- INSTRUMcNTATION I

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FERMI UNIT 2 3/4 3 54 Amenament No. 83.115

[

L'. PAGE llo} 0F 57 Au l

_ .,_. .-_ _ -- - ._ -... _ .-... ._ ._.._ _.._._. . __ .. _ .. _ ~._ _ ____. _ . _ ..... _ __,.-.. .. .. _ _ .-_ -. _..-_ _ _. - ...m .... -

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UNIT 2 rERMI -3/4 3 55 Awnament to.115 '

Lo L PAGE //6 0F 57 r

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14

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FERMI UNIT 2 3/4 3 56 teenament No. 115 PAGE / 'E OF 57 L

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3 3.3.1-l ;

,, TABLE-2.3.7.5-! - ;

TBL 3-3 51-I ACCIDENT NONITORING INSTRUMEHIATION :

t E Furc44e fEiNi ' appt caste :

-* CHA LS OPERATIONAL

- REQUIRE 0 NUMBER :

" 0 INSTRUNENT OF CHANNEL 5 ABLE lCONDIIIONS. ACTIPN j'

/

/ K Reactor Vessel Pressure 2 3 , I, 2 80 [

2 Reactor Vessel Water Level !

1 a. Fuel Zone 2 1 1, 2 80

b. Wide Range 2 I 't, 2 80 3 l O

g 4 3. Suppression Chamber Water Level 2 1 1, 2 80 ;

E Je Suppression Chamber Water Temperature 2 I 1, 2 80 hN

_S~ Suppression-Ch---tr ".f r T.-;:r:twe ?

.2 ""

I l

l v \/; \ e.> .

21 -6i---Suppress!;r. Clie;ter "s;;;;;re 2- _ 1, 2 GG i 4:> K Drywell Pressure, Wide Range 2 1, 2 80 O g -8r-Drywell-Air Temperature - ? lI

'.? 00 t

f 7 Jh Primary Containment Oxygen Concentration 2 1, 2 83 l

F 8 -lO Primary Containment flydrogen Concentration 2 1 1, 2 80 l A

y -I l&S a fe ty/Re l l e F Val ve-Po ri ti on-i nd i cators 1*/valv: 1*/;elv 1. 89

% 9 J2r Containment liigh Range Radiation Monitor 2 [ 1, BI g h (Priew h 2. &

Pi a i i1 -

4.= = .+u g i

M A i

WEElfu+ng) 113 5, j 3.33.M

TABLEB4'Ed (Continued) ( }50 3## P S '#ibCON ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS !

! m k400 f Ac1toA) 6 h

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channets shown in Table 3.3.7.5-1 restore U

'U' --*Y' #

s b.

.N..._?**'*.. . _.W'E.*N.??. _?,

.e_ . . . -

___ _- Aavs g*

i With the number of OPERABLE accident monitoring instrumentation bg() less than the Minimum Channels OPERABLE requirements of Table /3.3.7.51, restore the inoperable channel (s) to OPERABLE status withint

...k be in ArW F y\ U s. at _. _least

_ _ _ HOT SH._UTDOWN within the next 1 l

1 AG999N44-- With the number of OPERABLE che. .... .ess than required by the minimum g,}

ACT10A O channels OPERABLE requirementsArMe e provi.. po ag. .. )

y......g if moniWnno the as.E,.x,ste omrmeneterf hin 72 hs6rs/hnd: ,

_ (ant kss +kalk.gviced ', Rdd Ar.TinAl 44 6 L.9 I 4 ', 1) either restore the inoperable channel (s) to OPERABLE status within 7 t

days of the event, or M 2) prepara and submit a Special Report to the Commission pursuant to i spr.Scah Specification 8.9.2 within 14 days fol!cwing the event outlining the action I

j 6' G7 taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

j -AGRON With the number of OPERABLE accident monitoring instrumentation channels

!' less than required by the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, withinr48. news'aither:

rll AcTic)N AT3odAv3 1 a. Restore the inoperable channel (s) to OPERABLE status or i r b-1~

Ii ActodC:

are the affected isolation valve inoperaDie ano == me m iivm i

g

(~ .~_ ,, gc.A)DTE3.3 3,l.i LM "'lb.J_ spec eifi d by Soecification 3.6.3 ACTION a/-

9 J

, - Ac11ow F (Oc. sh rn00E 3 )

ACTION 83 ' -AcM d :M o n, 5 (. *1) }

n. With the number of OPERABLE accident monitoring instrumentation channels 4 less than the Required Number of Channels shown in Table 3.3.7.5-1 the ingerable enannel(s)_t, o OPERABLE status within 30 days,p~r s%

mTa--

l' b.ma B report to the 65'mm'ission puritiantTo SiiscEstion 652 within the follovnng

4 Sc.e, S/tt 54 7f and schedule for restoring the instrument channeI(s) to OP

b. With the number of OPERABLE accident monitoring instrumentation channels ACM O less than the Minimum Channels OPERABLE reouirements of T ble 3.3.7.5-1, 4 restore the inoperable channel (s) to OPERABLE status within hours or be in gg p at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l 72. LN

!. FERMA - UNIT 2 3/4 3-62 Amendment No. 28,56.117 4

PAGE N OF 06 4

Real r

, , , - + , , - - - - - --

~

i WEEtf7cA716sl f=la TABLE 3 3 7 6-1 (Continued) (/F Y50 384 8 d b ACCIDENT MONITORING INSTRUMENTATION

_ ACTION STATEMENTS ACTION 80-

4. With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7, days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

fr d w b. With the number of OPERABLE accident monitoring instrumentation channels 3,.,3.j o, less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 81 - With the number of CPERABLE channels less than required by the minimum channels OPERABLE requirements, initiate the preplanned altemate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1 1) either restore the inoperable channel (s) to OPERABLE status within 7

( days of the event, or g prepara and submit a Special Report to the Commission pursuant to f.l

{ (p, ) Specificenon 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 82 IWith the number of OPERABLE accident monitoring instrumentation chan less than required by the Minimum Channels OPERABLE requirements of 5et Table 3.3.7.5-1, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months either:

6ftCikuthN a.

7,3 3.I Restore the inoperable channel (s) to OPERABLE status, or b.

Declare the affected isolation valve inoperable and take the ACTION h specified by Speerfication 3.6.3 ACTION a.

ACTION 83 -

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore inenarnble channel (s) to OPERABLE status within 30 days, or submit a report to the Commission pursuant to Specification 6.9.2 within the following j

{,g'/ !

14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the instrument channe((s) to OPERABLE status.

t With the number of OPERABLE accident monitoring instrumentation channels i

W less than the Minimum Channels OPERABLE recuirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in

$fe e.hcAfnh at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. 3.'5. I FERAh- UNIT 2 3/4362 Amendment No. 28.58.117-mi w as y

~O O O 1

L'"L E t . 3. 7. 5-!

&[CIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

- APPLICABLE CHANNEL CHANNEL OPERATIONAL g INSIRLMNT CHECK CALIBSATI0f( COID[TIONS_

[ l-1. Reactor Vessel Pressure M (1) R (3 > l. 2

,2< Reactor Vessel Water Level 2 -a Fuel Zone M<'>

J 1r; R O5 1, 2 Wide Range M (' > RO> 1, 2 y )- Suppress 1on Chamber Water Level M (8> R (3 > 1, 2 I 4. Suppression Chamber Water Tesiperature M (s ) R<3) 1. 2

-Suppression Cii.-i,c Air i ye. .Lui . " i; :. 2 N.I g 4 -Suppressie.1 Che;.ter .". 2;;ure M i. I I y 6 J. Drywell Pressure, Wide Range M (8 > R(1) I, 2

{

Q '8:-Drywel11ir is-ywr aiur N "

, 2

[ .A Primary Containment Oxygen Concentration M (8) Qf (2) 1, 2 ! j C I 4f. Primary Containment Hydrogen Concentration M(1) Q*f (2) 1, 2 g j IL _Safetw/Reitsf-Vabe-Petirtlon-Indicators M ii h E CUh mehtighRangeRadiationMonitor

!, 2 f

i s a s u .i.s a r.

Usin ample gas

'R t W(1)

M R** G ) >

1, 2 5

g 2 a. e volume talning:

cent h dr en, balance nitr n. (R3331-Q) o E

o b. four vol percent rogen, balance rogen.

g D

- 0iAllHEL CA BRATION all consist of electronic calib lon of the ch not _ i nc' tafine the W detector,f or ran decades above I hr and a one po calibration c Y b (10 R/y with an estalled or port e gassia sourc of the (J4Feter D% *

=

j c G

ie nrovisions of Soecification 4.0.4 are not applicable provide _@ that the survelliance is co leted for one i c iannel within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and for both channels witnin seven says after exceeding 15% of RATED SERNAL POWLR. l' 5 e 3 3.3 . l ,'2_ Aloh 2_

. , . . . . - . - . . . . . . . . . . - . . . . . - . . - . . . . . . . . - . . . - - . ~ . _ . _ . - . . - . _ . . _ . . . - - . - .

INSTPUMEWATION 3/4.3.7.7 DELETED gp l 1

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I I FERMI UNIT 2 3/4 3 65 a.

Amenament No. 83, 115 i

!O V

PAGEIROtOF 57

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. -~ . . . . .. - - .... ... _ . . . . - . . . - . . . - . - . . - . - - - . - . - . . - . . - ~ . . . - - . . . - . . - - . . - . . . -

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INSTPUMENTATION 3/4.3.7.8 DELETED khh ,

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1 j; FERMI . UNIT 2 3/4 3 66 Amenament No. 83,115 1

!O l PAGE l8 b0F 57 e

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, ,4-RRM.] - UNIT 2 3/4 3-70 Anenoment No. 83,115 O,' mGE //pt0F 57 gj1 I

Spec w1omwJ 3 4 3 O- 3/4.4.2 SAFETY /RElfEF VALVES SAFETV/RElfEF VALVES [,/

LIMITING CONDITION FOR^0PERATION d 3.4.2.1 The safety valve function of at least 11 of the following reactor M0 ' olant slstem sajaty/ relief valv_qtshall be OPLRA8]J/wTth tTieTpecified code

~

1 safety vaTve Tunction ITft settings:* ~~

Sg 343./ 5 safety / relief valves 9 1135 psig t3%

'5 safety / relief valves 9 1145 psig 23% l c 5 safety / relief valves 91155 psig 13%

1 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. !

EIIDH: ,

~

a. With the safety valve function of less than 11 of the above Ac7 tog A safety / relief valves OPERABLE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , l

. With o e or more safety / lief vaiven asucn

..., psunoso Inat r*

suppr ssion pos) avera water temperature s less than 95'F, c s the tuck open safet elief valve (s); if nable to close the uck A o n valve (s) with 2 minutes or if su ression pool avera water -

V emperature is 95 k..+ % naciti or greater, place he reactor mode swi h in t

p. wun is vi -v . . .T ..l.. pu ition indicators i rest #/..l'.;T (s) t OPERABLE status w hinperacle, e the inoperabN. indicator 7 days or e in at least ydT SHUTDOWN with S

the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD DOWN within tKe following 24_h ur y LA 2.

SURVEILLA'NCE REOUTREMENTS l

4.4.Z.1.1 The valve posi on inoicator for eacn sarety/re er vasve / i snasi De 1

~

demonst ted-OPERABLE wi the pressure s point of each the tail-pipe press e swit'ches veri ed to be 30 e 5 sig by perform e of a CHANNEL MI T10N at 1satt nee nar 18 mont .f ,

R .

_1 4.4.2.:.? At least 11/2 o the safety relief valves shall be set nressure 3.93 :testep/a'; leasyonce per 15 months /such that all J5 safety reliDf valves art) setgressure/ tested a east oncVper 40 monthsr I i

\ _

./ '

&DD.- .:rA M.3. 2 / \

(*The (valgesJ4ft setting14 at nomina jirpssure snall S4rrespono to amoienyconotions of In /J./ i seratina tenwieratures and oressuresfn,ithoug Ine !

7 touna sitt e.specified J within $1% of 1:4 tonerence u da,, tne as- -t i ut setti shall be 7 6 tpoints prior to nstallation f owing te st,i ng ' /

O l

l t

FERMI - UNIT 2 3/4 4-7 Amendment No. E7,123 i PAGE 1 0F 01 Ravl

REACTOR COOLANT SYSTEM SPECIF/c+77ad 3 V.5' SURVETLLANCE REOUTREMENTS (Continued) f~\ SA 345. /

V 4.4.3.2.2 Each reactor coolant system pressure isolation valve spa m n in _

T M - 33.3.2 shall- be ' demonstrated OPERABLE by leak testing pursuant to LA.l Specification 4.0.5 and veriffing the leakage of each valve to be within the specifiedlimit:

pg.z c.- _

et .... ... . -. _., _.. . _ t, ,

s

. rrior o reiurning 6,i .i v e to service on towing mainten u, rep or replacemen rk on the valv hich could aff age rate. 7 1 -

)

..... , Mqh Tia , n: -

R ;ifi;;ti:: " .0.' -are not appTicable -f 8h OPERATIONAL CONDITION 3.

H4 .4.3.z.a ine niv'Iiow pressure interrace "sve seaxage pressure mo ors snn-be demonstrated ERABLE with alarm setpo' ts per Table 3.4.3.2-2 b performant of a:

a. iNEL FUNCTIONAL TEST t least once per 31 day , and

b. CHANNEL CALIBRATION least once per 18 mon s.

+

[N,/

O J

W 4

TERMI - tmIT 2 3/4 4-11a Amendment No. Ep,118

!O PAGE -

c2 _0F 03

&I

l SMtF/CA11ed .&C /

3/4.5 EMERGENCY-CORE COOLING SYSTEMS 3 /4 . 5.1 ECCS - OPERATING

LIMITING' CONDITION FOR OPERATION i LC O 3.5.1 The emergency core cooling systems shall be OPERABL%

l j

f.

The to subs spray system (CSS) consisti em comprised of:

of two subsystems with each

Two OPERA 8tE CSS pumps, d

2. An OPERABLE flow pat capable of taking suction from e f i suppression chambe and transferring the water th gh the I

! spray sparger to he reactor vessel.

1 i b. The low pressure e ant injection (LPCI) system o the residual heat

~

i removal system c sisting of two subsystems with ach subsystem comprised of.

l 1. Two O RA8LELPCI(RHR) pumps,and i l

2. PERA8LE flow path capable of king suction from the l-ppression chamber and transfe ing the water to the reactor vessel.*** I

! c. T high pressure cooling injec s n (!!PCI) system consisting of

{ l. One OPERA 8LE HPCI p and

' 2. An OPERABLE flow h capable of taking suction fr the suppression ch r and transferring the water t the reactor el.

j

@ 34,/ g The automatic depressurization system (ADS) with at least five j OPERABLE ADS valves.

4 -

APPLICABfLfTY: OPERATIONAL CONDITION 1, 2* ** I and 3' **.

(1

! klEg {*The HPCI system is not required to be OPERABLE when reactor steam dome 1

pressure is less than or equal to 150 psig.

- The ADS is not required to be OPERABLE when reactor steam dome pressure is

u less than or equal to 150 psig.

l 5k%l Y *** Low pressure coolant injection (LPCI) subsystems may be considered OPERA 8LE during alignment and operation for decay heat removal with reactor steam i

A done pressure less than the Residual Heat Removal (RHR) cut-in peruissive

! pressure in OPERATIONAL and not otherwise CONDITION 3. if capable of being manually realigned inoperable.

!!;; !;;;id Ten LW6;6 3.G.". ;

'( FERMI - UNIT 2 3/4 5-1 i Amendment No. 126 I

iO eaas 3 or 10 1-2

~

_ _ _ _ ._. __.-_..__m._ , _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ . . _ _ _ . . _ . _ _ . _ _ _ . . _ .

4 5

ffECtPCR710A) M.2 iO

! EMERGENCY CORE COOLING SYSTEMS i 3/4 5.2 ECCS - SHUTDOWN {C, .

j LINITING CONDITION FOR OPERATION

[,(O 3.5.2 At least twjo of the followl kubsystemss'ha11beOPERA8LE:

l a. Cor/spraysystem(C subsystems with a s system comprised of:

a j . At least two PERABLE Css pumps, an I 2. An OPE one of flow path capable of aking suction from at east following water sou s and transferring t water; 3

thena the many ea=rner to e reactor vessel: #

y , _ m . .. = = , . u i. + or I

5R 3.5,N- -trt- When the suppression chamber water level is less than the

! iinit required in specification 3.5.3 or is drained, from i the condensate storage tank containino at least 150,000 o g i f:; P;dri 4 + level of 18 l l available feet. gallons of wa)ter

!' I.

b Low pre 'ure coolant injection LPCI) system subs tems with a j subsy em comprised of:

! 1. At least two OPERABL PCI (RHR) pumps, d 1

. An OPERABLE flow p h capable of taki suction from the

suppression cha r and transferring he water to the re or j vessel **. ~

APPLICABILITY: OPERATIONAL CONDITION 4 and 5*.

EllQti:

AWa A d' with aa' af th' abave r'avired subsyst'=(5) taaPerabi' restare at 1 east two subsystem s AcenoAl 6 all operations with(a) potential for draining the reactor vessel.to OPERABL c

4 , Wini both of the above recuired subsystems inoperable, suspend fg,g C f f1 :""?:"""!and all operations with a potential for draining the

' reactor vessel. Restore at least one subsystem ".o OP ERABLF status h T10 N D ghy 4 ho{s or establish (SECONDARY LDNIAINMEN IhT[ GRIT ,

nn. /

,,, l

$[pgI %The.ECCS is not required

f.

to be OPERABLE provided that 2" :: " r :

the cavity is flooded, the spent fuel pool gates are M-rimoved. and water level is maintained within the 1,imits of(spectrication t ,1 LLB.8 and 3.9% )

M3,5~1 G ;;**LPcl subsystem (s) may be considered OPERABLE during allonnent and operation i Nog g for decay heat removal if capable of being manually realigned and not !

otherwise inope,rable.

EERMI-tlNIT2 3/4 5-6 Amendment No. 126 PAGE 3 0F 08 &j l

5p g i m e ro a s'.9 2 3 YB .C U D.C. SOURCES - OPERATING-Uw O WEAN N'b g -- g ./ f m 3 . F. 6 )

LIMITING CONDITION FOR OPERATION- _

f3.8.2J. As a minimum, the following 0.C. electr,ical power-sources shall be 1 OPERABLE >

a. Division 1, consisting of:

1. i 130 VDC Battery 2A-1. I

2. 130 VDC Battery 2A-2..

3. Two 130 VDC full. capacity chargers. i t

b. . Division'II. consisting of:

1. 130 VDC Battery 28-1.

h *2 .

3.

130 VDC Battery 28-2. i Two 130 VDC full capacity chargers. I

[g t

LPPLTCABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

E g - $JlQH:

\ .

With a battery charger in either Division I or Division II of the above i

D.C. electrical-power sources inoperable, restore the inoperable battery charger to OPERABLE status or replace with the spare battery charger within in COLD 4 hours or within SHUTDOWN be intheatfollowing least HOT SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With either Divistor, I er Division II of the above required D.C.

electrical power sources otherwise inoperable restore the inoperable O division to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or,be in at least HOT SHUTDOWN within hours ,the' next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 SURVETLLANCE PEOUTREMENTS

,[4.8'.2.1

,- ' (demonstrated OPERABLE:Each of the above required 130-volt batteries and charg i

a.

4 At least once per 7 days by verifying that:

(fPteincahmf.I.4/ 1.

The parameters in Table 4.8.2.1-1 meet the Category A limits, and w 2.

\ g b,3*p

' Total battery terminal voltage is greater than or equal to 130 for Division 11 on float charge. volts for Division I and lgre

b. (rTtTeast once per 92 days and within 7 days ,after a battery N discharge with battery terminal voltage less than 105 volts, or 8 QK$C4D L A .to

$j verifying batterythat: overcharge with battery. terminal voltag I I

(1. The parameters in Table 4.8.2.1-1 meet the Category 8 limits, f'This JtCTION may delayed for up M 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for b ry chargers m e inondrable due Q.7/.1.2 are ta en. lossofEECWcp411ngprovidedth CTIONS of Spe ficationf 3

Q FERMI - UNIT 2 3/4 8-10 L.I AmendmentNk20,121 PAGE F 0F 09 %l

. . - 1 S fECsPt W 3.f.Y ELECTRICAL F0WER SYSTEMS blSo Ste. S/Wc/[fce #an d'.f.6 )

D . SOUR E 0 ING

8*7' 4TMITING CONDITION FO[ OPERATION '

20 3.8.2.1 As a minimum, he follow' g D.C. electrical power sources shall be

3.2.9 OPERABLE

F.a vision 1. con sting of:

1. 130 VDC attery 2A-1.

2.

130 V Battery 2A-2. bA I

3. Two 0 VDC full capa ty chargers. ;

. Divisi II consisting :

1. 30 VDC Battery -1. ,

'2. 130 VDC Batter B-2.'

3. _

Two 130 VDC f I capacity cha ersy APPLfCABILfTY: OPERATIONAL CONDITIONS 1, 2, and 3.

M; LA, a

4<.TiptJ d With a battery charger in either Division I or Division II of the above D.C. electrical power sources inocerable, restore the inoperabl battery charger to OPERABLE statusfor reslace wtrr, tne soarvDattery chafaeh MT)oN c. within in COLD 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SHUTDOWN or be in at least within HOT SHUTDOWN the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and

b. With either Division I or Division II of the above required D.C.

Ac.non 8 electrical power sources otherwise inoperable, restore the inoperable division to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDO 4th C within hours.8the'next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 SURVEftlANCE REOUTREMENTS 4.8.2.1

- Each of the above required 130-volt batteries and chargers shall be ;

demonstrated OPERABLE: '

a. At least once per 7 days by verifying that:

$faiRcd m 1.

The 3.fh

parameters in Table 4.8.2.1-1 meet the Category A limits, 2.

g .5.T.q,l Total battery terminal voltage is greater than or ecual to 130 volts for Division I and greater than or equal to 125.7 volts for Division !! on float charge.

b.

' At least once per 92 days fano wn.nin 7 days arter a Dattery s '

'oiscnarge witn Dattery terminal voltage less than 105 volts, o '

S g coHow battery overcharge with battery terminal voltage greater than 150 3.t.(,

volts for Division I and greater than 145 volts for Division II by l' verifying thaty + (as nia ks m CT5 V.E.2.1.b.7.) -

1.

The parameters in Table 4.8.2.1-1 meet the Category B 1 s.

This ACTION may be delayed for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for battery chargers made O inoperable due to loss of EECW cooling provided the ACTIONS of Specification U 3.7.Il.2 are taken.

qj \

( S.ts SPet;kcaj{m ?7.'2 FERMI - UNIT 2 3/4 8-10 Amendment No. 80.121 MI PAGE i- 0F 02

y l

c ELECTRICAL POWER SYSTEMS 3/4.8.2 0.C. SOURCES

[p5C / P'/ (47ZDAl .3 if.b 3 D,C, SOURCES - OPERATING g pggg g,g,f (V LIMITING CONOTTION FOR OPERATION (Also su 4aciRca H6n 5.7.2d 3.8.2.1 (OPERABLE:As a minimum, the following D.C. electrical power sources shall

a. Division I. consisting of:

1. 130 VDC Battery 2A-1. ,

2. 130 VDC Battery 2A-2. )

3. Two 130 VDC full capacity chargers. :

b. Division II, consisting of: l

,1. 130 VDC Battery 28-1. I

2. 130 VDC Battery 28-2.

3. Two 130 VDC full capacity chargers.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

y I ACTION:

t? A

\N i.

With a battery charger in either Division I or Division II of the above I D.C. electrical power sources inoperable, restore the inoperable battei charger to OPERABLE status or replace with the spare battery charger l within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or in COLD SHUTDOWN bethe within infollowing at least HOT SHUTDOWN within the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With either Division I or Division II of the above required D.C.

electrical _ power sources otherwise inoperable k within the' next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDO restore the inoperable hours.8 SURVETLLANCE REOUIREMENTS 4.8.2.1 tdemonstrated OPERABLE:Each f of the above required 130-volt batteries and a.

At least once per 7 days by verifying that:

gg 3,g,g.l 1.

The and parameters in Table 4.8.2.1-1 meet the Category A limits, su. \ .

Spd keakm 3 K'//

volts for Division I and greater than or equal to for nivision 11 on float charge. j b.

At least once per 92 days and within 7 ggg ,

discharge with battery terminal volta sa er tery

$g3g.(,.'2- than 105 volts, or battery overcharge with battery terminal voltage greater than 150l '

volts for that:

verifying Division I and greater than 145 volts for Division II, by 1.

l The parameters in Table 4.8.2.1 1 meet the Category B limits, This ACTION may be delayed for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months fo 3.7.1.2 are taken.

[

\ FElRMI-UNIT 2SK Systi$cakan 3A.2.h 3/4 8-10 Amendment No. 20.121

,PAGE -1 JF 03 b\

. _ . _ _ _ . _ . _ _ _ - . _ _ _ _ ._. _ _. _ _..~. _ _ _ _ _ _

.5h;cIF169 770n) g.[,t/

ELECTPTCAL POWER SYSTEMS (Aiso w. Spe;%% ub)

SURVE1LLANCE RE001REMENTS (Continued)

2. There is no visible corrosion at either terminals or M N'N'1 connectors, or the connection resistance of these items is less than 150 x 10 6 chm, and su .

The average electrolyte temperature of ten of the connected Spec % ben 3.34 cells is above 60*F.

c. At least once per 18 months by verifying that:

gg 3, y,,J,3 1. " The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, 54 3' gg.y 2. The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with anticorrosion material, 64 U*Y'g 3. The resistance of each. cell-to-cell and terminal connection is less than or equal to 150 x 10 ' ohm, and )

4.

M 3' N' b The battery charger will supply at least 100 amperes at a minimum of 129-volts for Division I and at a minimum of '

124.7 volts for Division II for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . l l

d. At least once per 18 months by verifying that _either-l M 7, fA.~7

1. The battery capacity is adequate to x s:nm lakd ppiy and maintain in OPERABl.E status all of the actual emergency loads for the design a battery duty cycle [#

service test, M =or)lwhen

- the battery is subjected ty ins D tery capacity is equate Lo supply 4 0 l

the 11owing profile w le maintaining the b tery terminalt y loao of ~\

vol age greater than o equal to 105 or 210 its, as ap licable:

) Batteries 2P and 2PB greater than r equal to 710 '

amperes dur' g the initial 6 seco s of the test.

b Batteries A and 2PB greater th ,

~3 182 amperes dur' g i h)) the next 2 seconds of the test '

,c Batteri 2PA and 2PB greater an or equal to j ampere during the next 4 ho s of the test. /

4 d) '

Batte ies 2PA and 2PB great than or equal t 480 '

amne et durine the last 6 e t nnrie nf +ha +ae

- SA N *Tu -- - - - - - s _

e.,< _

, At least once per 60 months (durino snutcown[by verifying that the gg 5. F.84 F > battery capacity is at least 807. of the manufacturer's rating when subjected to a performance discharge test. [A'tthTsonceper60- 4~

. sR 3.7.O g month interva t ,

. in lieu of the battery service test.Inis performance discharge test may be per f.

At least once per 18 months performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has_ reached 857. of the service life ernected for the capac nonlication. /DegracM,1on is inoicatec when/the battery prev y drops more than' 10'4 of rated capacity /from its average /

us performance t/sts. or is below 907. of the manufacturpr/'on 4

s at ' g. j p

i LA.tl FERMI - UNIT 2 ~

3/,4 8 13 Amendment No. 95.121 PAGE A. OF 02 #@'l

$PGC 1 Ftckitord .5 $.lo i

ELECTRICAL PNER SYST*MS % ~ qa;ka n .1.ta)

EVEILLANCERE00 LAM.W5(Continued) i *- 2.

j There.is no visible ca rosion at either terminals or SP8' 7 connectors, or the connection resistance of these items is less than 150 x 10 ' chm, and l 3 gy,6y. _

Theaverageelectrolytetemperatureof{ tin /ofthedonnected')

cells is above 60*F.

j 4g,

c. least once per 18 months by verifying that:

4

1.

The cells, cell plates and battery racks show no visual

2. indication of physical damage or abnormal deterioration, The cell-to-cell and terminal connections are clean, tight,

3. . free of corrosion and coated with anticorrosion material, The is lessresistance of each.

than or equal cell-to-cell

.to 150 x 10 ' ohm, and and terminal connection i 4.

The battery charger will supply at least 100 amperes at a minimum of 129 volts for Division I and at a minimum of '

124.7 volts for Division U for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . l l d. At least once per 18 months by verifying that either:

i 1.

g The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual ' emergency loads for the i

5 PAb design euty cycle (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) when the battery is subjected to a battery service test, or 3,$.L/

2.

The battery capacity is adequate to supply a dumy load of J

the following profile while maintaining the battery terminal l voltage applicable: greater than or equal to 105 or 210 volts, as 4

{ a) Batteries 2PA and 2PB gra ter than or equal to 710

}

b) amperes during the initial 6 seconds of. the test.

Batteries 2PA and 2PB greater than 182 amperes during

.j c) the next 42 seconds of the test.

Batteries 2PA and 2PB greater than or equal to 54 d) amoeres during the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the test.

) Batteries 2PA and 2PB greater than or equal to 480 amperes during the last 6 seconds of the test.

f. e.

At least once per 60 months during shutdown by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. At this once per 60-

] .in lieu of the battery service test. month interval, this performan 4-f.

At least once per 18 months performance discharge tests of battery

^ capacity shall be given to any battery that shows signs of degradation the application.~ or has Dereached 85% of the service life expected for

j. capacity drops more. gradation is indicated when the battery previous rating. performance tests, or is below 90% of the manufa iO 4

j FERMI - UNIT 2

- 3/4 Bell AmendmentNo.9),121 PAGE c1 0F 03 ReVl

. I l- ,

i 0Q3 ELECTRICAt POWER SYSIEMS -

MOTOR OPERATED VAL THERuAt OVE us; n M rT m

/ X/ l

/{ LIMITING CONDITt0N FOR'6PFRATION

\ l 3.8.4.3 Th thermal overload protection of each lve used in safety systems shall be IRA 5LE.

APPLIC LITY: Whenever the motor-operated alve is required.to be OPERABLE.

1

! 'A :

th the thermal overload protect for.one or more of the above required alves inoperable, continuously ass the inoperable thermal overload wit n 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected. alve(s) inoperable and apply the appropr ate

!- ACTION statement (s) for the a eted system (s).

i

j. SURVElllANCE RE0VIREMENT5/

/ / overload protection ford valves

~

l 4.8.4.3 The thermal the above shall recuir j

be demonstrated OPJRABLE by the performance of a CHANNEL CA 'BRATION of a

! representative spple of at least 25% of all thermal over ads for the above required valvessat least once per 18 months, and by perf ance of a CHANNEL '

l CALIBRATION o he affected thermal overload followin ny maintenance {I activity whi could affect the performance of that ermal overload.

~ !

N J NM l

i l

l

! FERMI - UNIT 2 3/4 8 20 Amendment No. 1$/, 127 PAGE SW OF 43

/b /

I.

0 REFUELING OPERATIONS .

5Wn=t em s) 3.9./

(A1w sw SpctRcohw 3.12-)

ef,g g -

. SURVEILLANCE REOUIREMENTS 9.1.1position Refuel 'The reactor as specified: mode switch shall be verified to'be locked in the Shutdown or j

,g a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to: i 1

~q 1. Beginning CORE ALTERATIONS, and

\ 2. Resuming CORE ALTERATI0'NS when the reactor mode switch has been unlocked. ~

t b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' SR 3.4,lo l Q,

i.".l.2 Each of the above require reactor mode switch Refuel @fosition intorlocks*

shallg.be

. . .demonstrated

.4 OPERABLE by performance of a CHANNEL FUNGUONAL TES" et--

7 . m .+=-+a =a9 at least once pe ._

spec. withdr m i or days Lduring control rodf S A*2. '

k9.7.4.J..- , Q. DIE A."ERAnony,' as applicable.

,g <

A 5 b fl UT List

.. suvv s wguls uw s umwww suvus austbn nWTUWI 31L1Un IllLEFlub that 1/affected shal

^

be demonstrate OPERABLE by perfo ance of a CH El O FUNCTiflNAL TEST prior o resuming cont ol rod withdrawal or CORE ALTERATIO , as app 6able, t the Refuelfollowino repair, mainten citinn interi e ce or replacement of ny component tha couldJ i

l.A,l

~'

l b -,

Spaibb%

3. s 0.2.

The reactor mode switch may be placed in the Run or'Startup/ Hot position to test the switch interlock functions provided that all control rods are verified to remain fully inserted in core cells containing one or

more fuel assemblies by a second licensed operator or other technically "qualified member of the unit technical staf.f:

O FERMI - UNIT 2 3/4 9-2 Amendment No.116 PAGE 4 0F 02 04I

f c

6/EL1FICAT)Ord 39,2.

0 (Aho Sec. SfeciNcakm 5.9.I )

REFUELING OPERATIONS- a H "

3 .to,'I.)

SURVEILLANCE RE0VIREMENTS

,4.9.1.1 The reactor mode switch sinall be verified to be locked in the Shutdown or Refuelpositionpsspecifieg WI n 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pri to:

Beginnin' ORE ALTERATIONS, nd 2.

Resum unlo ed..g CORE ALTERATION whenthereactormadeswiMhasb 7 ,

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SR 39 2.g V

,.0...'L Each of the above required eactor mode switch Refuel position interigi sitall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST wunm)

/4{\

Tq)

+

e = r: "--

t- 't- n : n s.~

n withdrawal orf0RE ALTERA70N5) as applicable.

m.: at least once per 7 days during control rod 6%

Mta 6.1.3 Each of the above required reactor mode switch Refuel position interlocks

that is affected shall be demonstrated OPERABLE by performance of a CHANNEL g

,) 3.9.

FUNCTIONAL TEST prior to resuming control rod withdrawal or CORE ALTERATIONS, as D . applicable, following repair, maintenance or replacement of any component that could ffect the Refuel position interlock.

9 Mold: SR 342.2. Alok.h b

M P e reactor mode switch may be placed in the Run or Startup/ Hot Standby Spec I position to test the switch interlock functions provided that all control y,2. { more fuel assemblies by a second licensed operator qualified member of the unit technical staff.

j L

d FERMI - UNIT 2 3/4 9-2 Amendment No.116 f%GE c1 0F 02 &(

~

Tf8CIR CATION 3<l0*2-

} REFUELING OPERATIONS _.

{ Mso

,[ g, u ste .S$2cScaHe E4'./ ')

il g, y, g SURVElllANCE RE0VIREMENTS 2

4.9.1.1 The Refuel- reactor position mode switch shall be verified to be locked in the Shutdown or as'specified:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to:

1. Beginning CORE ALTERATIONS, and SMcake p' g 2. Resuming CORE ALTERATIONS when the reactor mode switch has been unlocked.

b.( At least once per 12 ho'urs. .

4.9.1.2 Each of the above required reactor mode switch Refuel position interlocks

f[h shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of and at least once per 7 days during control rod M*I withdrawal or CORE ALTERATIONS, as applicable.

4.9.1.3 Each of the above required reactor mode switch Refuel position interlocks

that is affected shall be demonstrated OPERABLE by performance of a CHANNEL fi FUNCTIONAL TEST prior 'co resuming control rod withdrawal or CORE ALTERATIONS, as applicable, following repair, maintenance or replacement of any component that could V . affect the Refuel position interlock.

V

+ t

'L(.03./0,2.o -

\ LR.I

The reactor mode switch may be placed in the Run or'Startup/ Hot Standby T/ position _to test the switch interlock functions provided that all control rods are verified to remain fully inserted in core cells containing one or !

- quaMfie44nember of thy' unit technipil staff:,more fuel mstamhlies 2 iO FERMI UNIT 2- .

3/4 9 2 Amendment No.116 PAGE c2. OF 02 - Rd I ~

PAM Instrumentation 3.3.3.1

- 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LC0 3.3.3.1 ihe PAM instrumentation for each Function in Table 3.3.3.1 1 shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTI0h5

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NOTES - - - - - -

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required . 30 days wiih one required channel to OPERABLE channel . inoperable. status.

B. Required Action and. B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.7.

not met.

C. --- NOTE- -- --

C.1 Restore one reovired 7 days Not cpplicable to channel to OPERABLE j ri;aary containment status.

ydrogen and primary

-l containment oxygen concentration channels.

f l One or more Functions l' with two required channels- inoperable.

(continued) l FERMI UNIT 2 3.3 24 Revision 1. 09/25/98 l

l

(

E PAM Instrumentation' 3.3.3.1^

l

' ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l l

i D. Two required primary D.1 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months l containment hydrogen primary containment concentration channels hydrogen inoperable. concentration channel

-to OPERABLE status.

98

, AND

.Two required primary containment oxygen D.2 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

. concentration channels primary containment inoperable, oxygen concentration channel to OPERABLE status.

E. Required Action and E.1 Enter the Condition- Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1-1 for or D not met. the channel.

I F. As required'by- F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action E.1 and referenced in Table 3.3.3.1 1.

L G. As required by G.1 Initiate action in Immediately H Required Action E.1 accordance with and referenced in Specification 5.6.7.

Table 3.3.3.1-1. l i

l l'

i I

Y i

j

O l: l FERMI - UNIT 2 3.3 25 Revision 1. 09/25/98 l-J 4

v. , , , . . 'n - -

PAM Instrumentation 3.3.3.1 SVRVEILLANCE REQUIREMENTS

.....................................N0TE- - - -- - -- - - -

These SRs appiy to each Function in Table 3.3.3.11.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days

\ SR 3.3.3.1.2 ..... --- - - - NOTES -- - - --

3 1. Only applicable to Functions 7 and 8.

2. Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for one channel, and 7 days for the second channel, after a 15% RTP.

Perform CHANNEL CALIBRATION. 92 days O SR 3.3.3.1.3 -

---NOTES - - - -

l 1. Not applicable to Functions 7 and 8.

2. Radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months g,

O l FEP.MI - UNIT 2 3.3 26 Revision 1. 09/25/98 r

. . _ . . _ . _.... _. _ ._ _..._ _ ._ _ _ _ -.___ _ .m . . . - _ . _ _ _ . - _ _ _ . _ .

r '

m ,

PAM Instrumentation I 3.3.3.1 4

J Table 3.3.3.1-1 (page 1 of 1)

((%

4. '

Post Accident Monitoring Instrumentation ,

i CONDITIONS

' REFERENCED-REQUIRED FROM REQUIRED' FUNCTION CHANNELS ACTION E.1

1. Reactor Vessel Pressure 2 F

2. ' Reactor Vessel Water Level . Fuel Zone 2 F

3. Reactor Vessel Water Level .* Wide Range 2 F l'

, 4. Suppression Pool Water Level 2 F

5. suppression Pool Water Temperature 2 F'

.6. orywell Pressure + Wide Range -2 F l 7. Primary Containment 02 concentration 2 .F l

l 8.' Primary Containment Hg Concentration 2 F l

9. Primary containment High Range Radiation Monitor 2- G j

10. PCIV Position . 2 per penetration F I flow path (a)(b) j l

4 O (s).Notrecp.tiredfor(selaitonvalves'whoseassociatedpenetrationflowpathisisolatedby'atleastone

" closed and deactivated automatic valve, closed manuel valve, blind flange, or check velve with flow

)

through the valve secured. '

(b) Only one position indication channel is required for penetration flow paths with only one instetted control room indication channel.

l l

4 l

+

'1' l

i F

' 4

[ FERMI UNIT'2 3.3 27 Revision 1, 09/25/98

, , e . -e , - , - .- ,, - , , - -

- _~ -. -. . .- . . - . . . - -. . . . - . - . . . . . . . - . . - . . - . . -

SRVs 3.4.3 r

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

, SR 3.4.3.1 Verify the safety function lift setpoints In accordance of the required ~SRVs are as follows: with the Inservice Number of .Setpoint Testing Program SRVs (osia) 5 1135

34.05 5 1145 34.35 5 1155

34.65 Following testing, lift settings shall be I within i 1%.

SR 3.4.3.2 -- - -

NOTE- - -

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

' _ _ 1 d ^

Verify each required SRV opens when manually actuated.

18 months I

l i

l l

i i

t% l l- FERMI - UNIT 2 3.4 7 Revision 1, 09/25/98 i

DC Sources-Operating 3.8.4 l

[ ;o X). SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY L

i- SR 3'.8.4.1 Verify battery terminal voltage is = 130 V 7 days for Division I and = 125.7 V for l Division II on float charge.

r l

SR .3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.

Verify each bantery cell to cell and terminal connection resistance is s 1.5E 4 ohm.

SR 3.8.4.3 Insmet battery tells, cell plates, and 18 months i racts.for visual indication of physical l- damage or abnormal deterioration.

,m l? % ),

SR 3.8.4.4 Remove visible corrosion and verify battery 18 months

. cell to cell and terminal connections are i

coated with anti corrosion material.

l SR 3.8.4.5 Verify each battery cell to cell and 18 months

' terminal connection resistance s 1.5E 4 ohm.

L SR 3.8.4.6 Verify each required battery charger 18 months l supplies for Division I: = 100 amps at i- = 129 V for = 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and Division II- .

m.100 amps at = 124.7 V for = 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l (continued)

. g% ' .

3.8 17 Revision 1,

[ FERMI . UNIT 2 09/25/98 4

4

l PAM Instrumentation

, B 3.3.3.1

. (A) BASES l LC0 (continued) l Only two Category I thermocouple channels are needed for post accident monitoring of suparession pool water temperature (Refs. 3 and 4). T1e outputs for the PAM sensors T50N404A and T50N405B are recorded on two independent recorders in the control room (channel A is redundant to channel B). Both of these recorders must be

OPERABLE to furnish two channels of PAM indication. These recorders are the primary indication used by the operator l during an accident. Therefore, the PAM Specification deals specifically with this portion of the instrument channels.

l

6. Drywell Pressure Drywell pressure is a Type A. Category I variable provided to detect a breach of the RCPB and to verify ECCS functions that operate to maintain RCS integrity. Two wide range drywell pressure signals are transmitted from separate pressure transmitters and are continuously recorded and displayed on two control room recorders. These recorders l are the primary indication used by the operator during an accident. Therefore, the PAM Specification deals specifically with this portion of the instrument channel.

C l 7. 8. Primary Containment Hydrocen and 0xvoen j Concentration r

Primary continament hydrogen and oxygen analyzers are Type l

C, Category I instruments provided to detect high hydrogen or oxygen concentration conditions that represent a l- potential for containment breach. This variable is also important in verifying the adequacy of mitigating actions.

9. Primary Containment Hiah Ranae Radiation Monitor l

l Primary containment area radiation (high range) is a Type E.

l Category I variable, and is provided to monitor the l potential of significant radiation releases and to provide l release assessment for use by operators in determining the

! need to invoke site emergency plans. The instrumentation l

provided for this function consists of redundant sensors, microprocessors and indicators. A common 2 pen recorder in the control room continuously records signals from both channels. The redundant indicators in the relay room and the common recorder in the control room are the primary indication used by the operator during an accident.

i O

. v l FERMI UNIT 2 B 3.3.3.1 - 5 Revision 1, 09/25/98

- PAM Instrumentation B~3.3.3.1 BASES LC0 (continued) -

~ Therefore, the PAM Specification deals specifically with this portion'of the instrument channel.

10. Primary Containment Isolation Valve (PCIV) Position l-L PCIV. position is a Type B, Category I variable, and is provided for verification of containment integrity. In the case of PCIV position, the important information is the isolation status-of the containment penetration. The LC0 requires one channel of valve position indication in the-control room to be OPERABLE for each active PCIV in a containment-penetration flow path, i.e., two total channels of PCIV position indication for a penetration flow path with - 1 l

two active valves. For containment penetrations with only one active PCIV having control room indication Note (b) reouires a single channel of valve position indication to be

OPERABLE. This is sufficient to redundantly verify the isolation status of each isolable pnetration via indicated L

status of the active' valve, as applicable, and prior knowledge of passive valve or system boundary status. If r penetration flow path is isolated, position indication for

- the PCIV(s) in the associated penetration flow path.is not

!'O l

needed to determine status. Therefore the position indication for valves in an isolated )enetration flow path is not required to be OPERABLE. The )CIV aosition PAM L instrumentation consists of position switcles, dring, cabling, and control room indicating lamps for active PCIVs. ;

Therefore, the PAM specification deals specif f eally with these instrument channels.

l L APPLICABILITY The PAM instrumentation LC0 is a)plicable in MODES 1 and 2.

! These variables are related to tie diagnosis and preplanned actions required to mitigate DBAs. The applicable DBAs are assumed to occur in MODES 1 and 2. In MODES 3, 4, and 5.

plant conditions are such that the likelihood of an event j that would recuire PAM instrumentation is extremely low:

l therefore, PAP instrumentation is not required to be t

OPERABLE in these MODES.

t h -ACTIONS . Note 1 has been added to the ACTIONS to exclude the MODE t

i change restriction C !C0 3.0.4. - This exception allows entry into the appl ._ ole MODE while relying on the ACTIONS i '

i:

l FERMI UNIT 2 B 3.3.3.1 - 6 Revision 1, 09/25/98

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PAM Instrumentation B 3.3.3.1 f

( )) . BASES l

ACTIONS (continued) l i

even though the ACTIONS may eventually require plant I shutdown. This exception is acceptable due to the passive !

function of the instruments, the operator's ability to l diagnose an accident using alternative instruments and I methods, and the low probability of an event requiring these I instruments.

Note 2 has been provided to modify the ACTIONS related to PAM instrumentation channels. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables l expressed in the Condition discovered to be inoperable or i not within limits, will not result in separate entry into I the Condition. Section 1.3 also specifies that Required I Actions of the Condition continue to apply for each I additional failure, with Completion Times based on initial !

entry into the Condition. However, the Required Actions for I inoperable PAM instrumentation channels provide appro)riate l compensatory measures for separate Functions. As suc1, a !

Note has been provided that allows separate Condition entry l for each inoperable PAM Function.

( M When one or more Functions have one required channel that is inoperable, the required inoperable channel must be restored i to OPERABLE status within 30 days. The 30 day Completion l Time is based on operating experience and takes into account '

the remaining OPERABLE channels (or, in the case of a Function that has only one required channel, other non Regulatory Guide 1.97 instrument channels to monitor the Function), the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation during this interval.

U If a channel has not been restored to OPERABLE status in 30 days, this Required Action specifies initiation of action in accordance with Specification 5.6.7, which requires a written report to be submitted to the NRC. This report ,

discusses the results of the root rause evaluation of the inoperability and identifies proposed restorative actions.

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l FERMI UNIT 2 B 3.3.3.1 - 7 Revision 1, 09/25/98

. . . - .- - - - ._. . ~ ,

1 PAM Instrumentation '

B 3.3.3.1

( BASES SURVEILLANCE REQUIREMENTS (continued)

The 18 month Frequency for all channels except the primary containment hydrogen analyzers (per Note 1 to SR 3.3.3.1.3) is based on operating experience and consistency with the <

typical industry refueling cycles. The 92 day Frequency for i the primary containment hydrogen analyzers (per Note 1 to i SR 3.3.3.1.2) it based upon vendor recommendations and instrument accurccy requirements.

SR 3.3.3.1.2 is modified by Note 2 stating that performance

- of the calibration of the oxygen and hydrogen monitors may be delayed until after exceeding 15% RTP (i.e., the power at which LC0 3.6.3.2 requires the primary containment to be !

inerted). This. delay is allowed for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for one oxygen and one hydrogen monitor, and for 7 days for the second oxygen and hydrogen monitor. These delays facilitate more accurate calibration methods, which can be employed with the primary containment inerted.

SR 3.3.3.1.3 is also modified by Note 2 stating that radiation detectors are excluded from calibration requirements. I REFERENCES 1. Regulatory Guide 1.97. " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident,"

Rev. 2 December 1980.

2. Detroit Edison Letter NRC 89 0148, " Additional l

l Clarification to Fermi 2 Compliance to Regulatory Guide I 1.97, Revision 2 " dated June 19, 1989. !

l

3. Detroit Edisen Letter NRC 89 201, " Regulatory Guide i 1.97 Revision 2 Design Review " dated September 12, l 1989.

4. NRC Letter, " Emergency Response Capability Conformance l to Regulatory Guide 1,97, Revision 2 (TAC No. 59620)."

dated May 2, 1990. l

5. Detroit Edison Letter NRC 93 0105. " Fermi 2 Review of Neutron Monitoring System Against Criteria of ,

NED0 31558A," dated September 28, 1993.

i

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l FERMI UNIT 2 B 3.3.3.1 - 11 Revision 1 09/25/98 4

PAM Instrumentation B 3.3.3.1

)' BASES REFERENCES (continued)

6. NRC Letter, " Regulatory Guide 1.97 Boiling Water Reactor Neutron Flux Monitoring Fermi 2 (TAC No. M59620)," dated February 17, 1994. j

7. NRC Letter, " Regulatory Guide 1.97 Boiling Water ,

Reactor Neutron Flux Monitoring Fermi 2 (MPA-17 !

TAC No. M59620)," dated May 10, 1993. .

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l FERMI UNIT 2 B 3.3.3.1- 12 Revision 1, 09/25/98

.'l t

j

E SRVs 1

.B 3.4.3 :

' BASES APPLICABILITY In MODES 1, 2,'and 3.-11 SRVs must be OPEN BLE. since i considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in

-these MODES. The SRVs may be required to provide 3ressure relief to discharge energy from the core until sucr time that the Residual Heat Removal (RHR) System is capable of dissipating the core heat. 1 In MODE 4,. decay heat is low enough for the RHR System to provide adequate cooling, and reactor pressure is low enough that the overpressure limit is unlikely to be approached by assumed operational transients or sccidents. In MODE 5, the l reactor vessel head is unbolted or removed and the reactor 1 is at. atmospheric pressure. . The SRV function is not needed

, during these conditions. l

)

t i i ACTIONS A.1 and A.2

. With less than the minimum number of required SRVs OPERABLE. J t a transient may result'in the violation of the ASME Code i--

limit on reactor pressure. If the safety function of any l- . required SRVs cannot be maintained, the plant must be j

! brought to a MODE in which the LC0 does not apply. To- -

achieve this status, the slant must be brought to MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MO)E 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed >

Completion Times are reasonable, based on operating experience, to reach required plant conditions from full power conditions in an orderly manner and without

= challenging plant systems.

1 SURVEILLANCE SR 3.4.3.1 '

REQUIREMENTS This Surveillance requires that the required SRVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the SRV safe lift i settings must be performed during shutdown, since this is a bench test, to be done in accordan:e with the Inservice Testing Program. The lift setting pressure shall ccrrespond L to ambient conditions of the valves at nominal operating tem)eratures and pressures. The SRV setpoint is i 3t for

OPERABILITY. however, the valves are reset to i 1t during F the Surveillance to allow for drift.

4 i !

j,.O l. FERMI UNIT 2 B 3.4.3-3 Revision 1, 09/25/98 r

I i

DC Sources-Operating B 3.8.4 (3

(v) BASES BACKGROUND (continued) -

Each DC battery subsystem is separately housed in a ventilated room a) art from its charger and distribution centers. Each su) system is located in an area separated ;

physically and electrically from the other subsystems to 4 ensure that a single failure in one subsystem does not cause ,

a failure in a redundant subsystem. There is no sharing l between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels.

The batteries for DC electrical power subsystems are sized l such that under the worst case condition, with no battery ;

charger available and the battery cell electrolyte j temperature at 60 F, the batteries are able to carry all i required loads for four hours without the minimum cell I voltage dropping below 1.75 VDC for Division I and below 1.81 VDC for Division II.

Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation, while at the same time maintaining its battery bank fully charged.

/3, Each battery charger has sufficient capacity to restore the l battery from the design minimum charge to its fully charged V state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying normal steady state i

loads (Ref. 11).

APPLICABLE The initial conditions of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses in the UFSAR, Chapter 6 (Ref. 4) and Cha)ter 15 (Ref. 5), assume that Engineered Safety Feature (ES ) systems are OPERABLE. The DC electrical power system 3rovides normal and emergency DC electrical power for the IDGs, emergency auxiliaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis of the unit. This includes maintaining sufficient DC sources OPERABLE during accident conditions in the event of:

a. An assumed loss of all offsite AC power or all onsite AC power; and

,ry

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l FERMI - UNIT 2 B 3.8.4 -2 Revision 1, 09/25/98

9 l

DC- Sources -Operating B 3.8.4 BASES I~ APPLICABLE SAFETY ANALYSES-(continued)

b. A worst case single failure.

The DC sources satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). I 1

1 I

LC0 The DC electrical power subsystems-with each DC subsystem !

consisting of two 130 VDC batteries in series, two battery chargers, and the corresponding control equiment and ].

interconnecting cabling supplying power.to tle associated bus, are required to be OPERABLE to ensure the availability of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational ;

occurrence (A00) or a postulated DBA. Loss of any DC i electrical power subsystem does not prevent the minimum i safety function from being performed (Ref. 3).

J APPLICABILITY The'DC electrical power sources are required to be OPERABLE in MODES 1, 2, and 3 to ensure safe unit operation and to I- ensure that:

a. Acceptable fuel design limits and reactor coolant [

pressure boundary limits are not exceeded as a result :

of A00s or abnormal transients; and ;

I

b. Adequate core cooling is provided, and containment integrity and other vital functions are maintained in the event of a postulated DBA. l The DC electrical power requirements for MODES 4 and 5 are addressed in the Bases for LC0 3.8.5. "DC Sources-Shutdown." ,

ACTIONS A.1 and B.1 Conditions A and B represent one division with a loss of ability to completely respond to an event, and a potential loss of ability to remain energized during normal operation.

If one of the re inoperable (e.g. ,quired DC electrical inoperable power subsystems battery, inoperable battery is charger (s), or inoperable battery charger and associated l FERMI UNIT 2 B 3.8.4-3 Revision 1, 09/25/98 m

. ~ - . ._ __ . _ . .. . .~ - - - - .- . .

DC Sources-Operating B 3.8.4 r%

'd BASES ACTIONS (continued) inoperable battery), the remaining DC electrical power subsystems have the capacity to support a safe shutdown and to mitigate an accident condition. A subsequent worst case single failure could, however, result in the loss of minimun necessary DC electrical subsystems to mitigate a worst case accident. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the potential for complete loss of DC power to the affected

. division. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time (Required Action A.1) for restoration of an inoperable battery charger allows time to replace the ir. operable charger with an OPERABLE spare battery charger, if available. The four hour limit is reasonable based on the remaining capability of the battery to carry the loads for this period. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limit for Required Action B.1 is consistent with the allowed time for an inoperable DC Distribution System division. The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time is based on Regulatory Guide 1.93 (Ref. 6) and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe

,e unit shutdown.

M N'

l C.1 and C.2 If the station service DC electrical power subsystem cannot be restored to OPERABLE status within the required Completion Time, the unit must be brought to a MODE in which the LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the recuired plant conditions from full power conditions in an orcerly manner and without challenging plant systems. The Com)letion Time to bring the unit to MODE 4 is consistent wit 1 the time required in Regulatory Guide 1.93 (Ref. 6).

SURVEILLANCE SR 3.8.4.1 REQUIREMENTS Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge D

U l FERMI UNIT 2 B 3.8.4-4 Revision 1. 09/25/98

DC Sources-Operating B 3.8.4 R

. BASES SURVEILLANCE REQUIREMENTS-(contirued) required to' overcome the internal losses of a battery (or battery cell)-and maintain the battery (or a battery cell) in a fully charged state. - The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with manufacturer recommendations and IEEE 450 (Ref. 7).

SR 3.8.4.2 Visual. inspection to' detect corrosion of the battery cells and connections,'or measurement of the resistance of each inter cell and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The connection resistance limits procedurally established for this SR are no more than 20% obove the resistance as measured during installation and not above the ceiling value established by the manufacturer. This provides conservative j measures to assure the' Technical Specification limit is not i

q. exceeded.

The frequency for these inspe..'tions, which can detect conditions that can cause power losses due to resistance heating, is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends.

SR 3.8.4.3 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. Indications of damage or abnormal deterioration are evaluated to assess impact on the OPERABILITY of the battery.

The 18 month Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable from a ::tandpoint of maintaining reliability.

i O l FERMI UNIT 2 B 3.8.4-5 Revision 1, 09/25/98

-- . - - = - - . - .

DC Sources-Operating B 3.8.4 BASES SURVEILLANCE REQUIREMENTS-(continued)

SR 3.8.4.4 and SR 3.8.4.5 ;

1 Visual inspection and resistance measurements of inter cell l and terminal connections provides an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti corrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and i inspection under each terminal connection.

The removal of visible corrosion is a preventive maintenance I SR. The presence of visible corrosion does not nece I represent a failure of this SR, provided visible cor.ssarily rosion is removed during performance of this Surveillance.

The connection resistance limits procedurally established i for this SR are no more than 20% above the resistance as I measured during installation, and not above'the ceiling l value established by the manufacturer. This provides ;

conservative measures to assure the Technical Specification j limit is not exceeded.

V The 18 month Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. '0.nerating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable from a standpoint of maintaining I reliability. i SR 3.8.4.6 Battery charger capability requirements are based on the design capacity of the chargers (Ref. 3). According to l Regulatory Guide 1.32 (Ref. 8), the battery charger supply is required to be based on the largest combined demands of the various steady state loads and the charging capacity to l restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the unit during these demand occurrences. The minimum required amperes and duration ensures that these requirements can be satisfied.

The Frecuency is acce) table, given the unit conditions requirec to perform t1e test and the other administrative

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l FERMI - UNIT 2 B 3.8.4 - 6 Revision 1, 09/25/98

DC Sources-Operating B 3.8.4 O 8^SES SURVEILLANCE REQUIREMENTS-(continued) controls existing to ensure adequate charger performance I during these 18 month intervals. In addition, this '

Frequency is intended to be consistent with expected fuel cycle lengths.

SR 3.8.4.7 A battery service test is a special test of the battery's capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length corresponds to the design duty cycle requirements as specified in Reference 4.

The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.32 (Ref. 8) and Regulatory Guide 1.129 (Ref, 9), which state that the battery service test should be performed during refueling operations or at some other outage, with intervals between tests not to exceed 18 months.

This SR is modified by a Note that allows the performance of

,f a performance discharge test in lieu of a service test once per 60 months.

SR 3.8.4.8 A battery performance discharge test is a test of constant current capacity of a battery, normally done in the as found i condition, after having been in service, to detect any '

change in tne capacity determined by the acceptance test. l The test is intended to determine overall battery I degradation due to age and usage. l The battery performance discharge test is acceptable for satisfying SR 3.8.4.7 as noted in SR .4.7.

The acceptance criteria for this Surveillance is consistent I with IEEE 450 (Ref. 7) and IEEE 485 (Ref. 10). These references recommend that the battery be replaced if its !

capacity is below 80% of the manufacturer's rating. A capacity of 80% shows that the battery rate of deterioration is increasing, even if there is ample capacity to meet the load requirements.

The Frequency for this test is normally 60 months. If the battery shows degradation, or if the battery has reached 85%

j FERMI - UNIT 2 B 3.8.4 - 7 Revision 1, 09/25/98 ,

DC Sources-Operating i B 3.8.4 O

g BASES l

l SURVEILI ANCE REQUIREMENTS -(continued) of its expected life, the Surveillance Frequency is reduced to 18 months. Degradation is indicated, according to IEEE 450 (Ref. 7), when the battery ca)acity drops by more 1 than 10% relative to its capacity on t1e previous performance test or when it is 10% below the manufacturer's rating. The 60 month Frequency is consistent with the l

recommendations in IEEE 450. (Ref. 7); however, the 18 month )

Frequency is based on previously accepted industry practice. 1 and the need to perform this test during an outage.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would remove a required DC electrical power subsystem from service, perturb the electrical distribution system, and challenge safety systems. Credit may be taken for unplanned events that j satisfy the Surveillance.

REFERENCES 1. 10 CFR 50, Appendix A. GDC 17.

l g- 2. Regulatory Guide 1.6.

U 3. IEEE Standard 308, 1978.

4. UFSAR. Chapter 6. j

5. UFSAR, Chapter 15.

6. Regulatory Guide 1.93. !

7. IEEE Standard 450. l 3

8. Regulatory Guide 1.32, February 1977. ;

9. Regulatory Guide 1.129, December 1974.

10. IEEE Standard 485, 1983. j

11. UFSAR, Section 8.3.2. j A

Q' l FERMI UNIT 2 B 3.8.4 -8 Revision 1, 09/25/98

v t e Letter Sequence Request
TAC:MA2455, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other:
MONTHYEAR1998-09-28 [Table View]

ML20154E562

Text

SUMMARY

SUMMARY

3.2.9 OPERABLE

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