ML20236F067

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Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904
ML20236F067
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/26/1998
From:
DETROIT EDISON CO.
To:
Shared Package
ML20236F064 List:
References
NUDOCS 9807020010
Download: ML20236F067 (9)
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Text

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l Attachment 3 to ,

, NRC-98-0040

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ATTACHMENT 3 FERMI 2 NRC DOCKET NO. 50-341 f OPERATING LICENSE NPF-43 REQUEST TO REVISE TECHNICAL SPECIFICATIONS "ONE-TIME TECHNICAL SPECIFICATIONS REVISION TO ALLOW EXTENSION OF THE FERMI 2 OPERATING CYCLE"

, Attached is a mark-up of the existing Technical Specifications (TSs), indicating the l

proposed changes (Part 1) and a typed version of the TSs incorporating the proposed changes with a list ofincluded pages (Part 2).

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r 9907020010 990626 ,$

PDR ADOCK 05000341 P PDR<,

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Attachment 3 to

. NRC-98-0040 ATTAClIMENT 3 - PART 1 PROPOSED TECIINICAL SPECIFICATION PAGES MARK-UP l

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LIST OF TABLES i

.IAEL P.ADE  ;

i 1.1 SURVEILLANCE FREQUENCY NOTATION.................. 1-9 l 1.2 OPERATIONAL CONDITIONS........................... 1-10 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

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SETP0lNTS........................................

2-4  ;

'er t in m ,'s.. ar. te m.r.

T INTERVALS EXTENDED TO 8

g g g g .. g g ..... ................................ 374 0-4 O La TEST INT ENDED TO 4< l END OF REFUELING OUTA 7.,..................... 3/4 0-6 l (

3.3.1-1 REACTOR PROTECTION SY RUMENTATION........ 3/4 3-2 3.3.1-2 0ELETED.......................................... 3/4 3-6  !

4. 3.1.1 - 1. REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................ 3/4 3-7 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION.............. 3/4 3-11 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS.... 3/4 3-15 3.3.2-3 0ELETED.......................................... 3/4 3-18 4.3.2.1-1 ISOLAT10H ACTUATION INSTRUMENTATION ,

SURVEILLANCE REQUIREMENTS........................ 3/4 3-20 l 3.3.,3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRLMENTAT ION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-24 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETP0lNTS. . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-27 i

3.3.3-3 DELETB.......................................... 3/4 3-29 4.3.3.1-1 EMERGENCY CORE C00 LING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS........ 3/4 3-30 3.3.4-1 ATVS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.................................. 3/4 3-33 3.3.4-2 ATVS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETP0!NTS........................ 3/4 3-34 FERNI - UNIT 2 xxii AmendmentNo./J,Jpp[

l . APPLICABILITY SURVElltANCE REQUIREMENTS 4.0.1 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. -

4.0.2 Each Surveillance Requirement shall be performed within the speci l

surveillance interval with a maximum allowable extension not to exceed percent of the specified surveillance interval. For the purpose of t *&

i refueling outage, those Surveillance Requirements listed on Table 4.0.

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

I 4.0.3 Failure to perfom a Surveillance Requirement within the allowed surveillance 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the i completion of the surveillance when the allowable outage time limits of the l

ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not l have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable 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 shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class I, 2, 1 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

__ shall be performed in accordance with Section XI. of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by ths. commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

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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: l l

FERMI - UNIT 2 3/4 0-2 AmendmentNo.#,S,p

TABLE 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 5. 1996 i SURVEILLANCE REQUIREMENT DESCRIPTION l 4.1.3.1.4.a Scram discharge vol. vent and drain valve operability 4.3.1.1. Table 4.3.1.1-1. Iten 3 RPS Rx Steam Dame Press High cal.

4.3.1.1. Table 4.3.1.1-1. Iten 4 RPS Rx Low Water Level - Level 3' cal -

4.3.1.1. Table 4.3.1.1-1. Item 5 RPS M51V Closure cal

, 4.3.1.1. Table 4.3.1.1-1. Item 6 RPS Main Steam Line Radiation High cal 4.3.1.1 Table 4.3.1.1-1. Itan 7 RPS 3ryme11 Pressure High cal 4.3.1. 37 RP5 Response fles Test 4.3.2.1. Table 4.3.2.1-1. It a 1.a.1 Pri Cont Isolation actuation As Water Low Level - el 3 cal 4.3.2.1. Table 4.3.2.1-1. Iten 1.a.2 Pri Cent laolation Actuation Rx Water Low Level - evel 2 cal 4.3.2.1. Table 4.3.2.1-1. Iten 1.a.3 Pri Cent Isolation Actuation As Water Low Level Level I cal 4.3.2.1. Table 4.3.2.1-1. Item 1.b Pri Cent Isolation Actuation Drywell Press Hig' al 4.3.2.1. Table 4.3.2.1-1. Iten 1.c.1 Pri Cent Isolation Actuation Main steam Line distion High cal 4.3.2.1. Table 4.3.2.1-1. Iten 1.c.2 Pri Cont Isolation Actuation Main Steam Lt ress Low cal 4.3.2.1. Table 4.3.2.1-1. Iten 1.d Pri Cont Isolation Actuation Main Steam Li tunnel Temp. High cal 4.3.2.1. Table 4.3.2.1-1. Item 1.e Pri Cent Isolation Actuation Condenser P : High cal 4.3.2.1. Table 4.3.2.1-1. Iten 1.f Pri Cont Isolation Actuation Turbine B1 . Area Tele. High cal 4.3.2.1. Table 4.3.2.1-1. Itan 2.e RWCU Isolation Rx Water Low Level - L 1 2 channel ca) l 4.3.2.1. Table 4.3.2.1-1. Itm 2.g RWCU Manual Initiation channel funct al test I 4'.3.2.1. Table 4.3.2.1-1. Item 3.a.1 RC!C Steam Line Flow High DP chan cal 4.3.2.1. Table 4.3.2.1-1. Iten 3.a.2 RCIC Steam Line Flow'High 7 tem Do y cal ,

4.3.2.1. Table 4.3.2.1 1. Iten 4.a.1 HPCI Steam Line Flow High DP cal l 4.3.2.1. Table 4.3.2.1-1. Item 4.a.2 MPCI Steam Line Flow High Ti lay cal '

4.3.2.1. Table 4.3.2.1-1. Iten 4.e NPCI Manual Initiation functi 1 test 4.3.2.1. Table 4.3.2.1-1. Jten 5.a RHR 5/D Cooling Rx Water Le I Low - Level 3 cal 4.3.2.1 f Table 4.3.2.1-1. Item 6.b Sec. Cont. Isolation - Dr 11 Press High channel cal 4.3.2.3 " Isolation Actuation Inst Systen Response Time 4.3.3.1. Table 4.3.3.1-1. Itan 1.b C5 Drywell Press Hign ,

4.3.3.1. Table 4.3.3.1-1. Item 2.b LPCI Drywell Press Hi Cal 4.3.3.1. Table 4.3.3.1-1. Itan 2.f LPCI Riser Different 1 Pressufs High Cal 4.3.3.1. Table 4.3.3.1-1. Item 2.g LPCI Recirc. Pee fferential Pressure High Cal j 4.3.3.1. Table 4.3.3.1-1. Iten 3.b HPC1 Drywell Pres High Cal '

4.3.3.1. Table 4.3.3.1-1. Itas 3.f HPC! Manual Ini ation 4.3.3.1. Table 4.3.3.1-1. Iten 4.f ADS RPV Low L 1 3 Cal 4.3.3.1. Table 4.3.3.1-1. Item 4.1 ADS Manual I ibit Functional Test 4.3.4. Table 4.3.4-1. Item 2 RPV Press h Cal (ATVS) 4.3.7.4.1. Table 4.3.7.4.-1. Iten 1 RPV Press 1 - Remote Shutdoun 4.3.7.5. Table 4.3.7.51. Ites 1 RPV Pre tal Accident Mon.

4.3.7.5. Table 4.3.7.5-1. Iten 11 SRV Po tion Indic Cal Accident Mon.

4.3.7.5. Table 4.3.7.5-1. Itan 12 MT gh Range Red Monttoring C41 Accident Mon.

4.3.7.5. Table 4.3.7.5-1. Iten 2.s RPV u 1 Zone Level C41 Accident Mon 4.3.7.10.c L ef Detection System Cal 4.3.9.1. Table 4.3.9.1-1. Item HifnWa r Level 8 Cat FV/ Main Turbine Trip

_4. 3. 9. 2 - / Main Turb ne Trip L5FT i 4.3.11.1. Table 4.3.11.1 . Item 7 Alt $/D syst Rs Vater Level instroent operability l 4.3.11.J. Table 4.3.!! -1 item 8 Alt $/D syst Rs Press instrument operability l

4.4.2.1.1 $RV Tail Pi Pressure $ witch Cal 4.4.2.1.2 , SRV lift set point test 4.4.2.2.b SRV Low Low t Prassure setpoint Ca1 and L5FT 4.4.3.1.6 Drywell 5 Flow /Lvl Monitoring Cal 4.4.3.2.2.s RC5 Press e Isol Valve Leak Test 4.5.1.d.2.a ADS Sys Functional Test

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FERMI - UNIT 2 3/4 0-4 Amendment N 06, 108 Correcte Augus . . 1996 1

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w l TABLE 4.0.2-1 8 l

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$ SURVEILLANCE TEST INTERVALS HTENDED TO OCTOBER 5.1996 Cont' SURVEILLANCE REQUIREMENT DESCRIPTION l

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4. .t.1.e suppressl e Chad er operability (visual ine
4. . 1.h ton) suppressimi thener eserability SW to torus sa leek test 4.8. Instr. Dummes Flow Check operability 4.6.3. TIP Emplesive squib operability test -

4.6.4.1. 2.s Terus/Oryme11 vacum breaker setpoint -abillty 4.8.4.1.b. b Terus/Drytell vacum benaker posttten nd";;atten eel g 4.5.4.1.b.t. Torus /Drytell vacum breaker switch Ing esp

  • 4.4.4.2.b.t.a RS/ Torus Waou m Breaker operabiltt (setpoint) 4.5.4.2.b.t.b M/ Torus faces treaker operabil 4.5.4.2.b.t.c (visual)

RS/ Torus fasenas Breaker positt indicatteT operability 4.7.11.4 4.8.4.2.a.1.a alternative Shutdeun Centeel revit Functlanal Test Primary Centatruent 4160 Vol Penetratten Protective Relay Cal 4.8.4.2.a.1.b Primary Canta Nuent 4160 V t Penetration Protective Device Integrated Functlanal 7 g

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TABLE NOTATIONS

( The surveillance interval of channels within the same trip sys required to be tested at least once every N times 18 months, wh a N is the total number of channels in the trip system, may be based upo the performance of the surveillance during the fifth refueling outage.

FERMI - UNIT 2 3/40-5 Amendment No.1 1

TABLE 4.0.2-2 SURVEILLANCE TEST INTERVALS EXTENDED TO END OF REFUELING OUTA

$ SURVEILLANCE RE0VIREMENT DESCRIPTION 1 4.1.3.5.b.I CR Accoulater Integrity Test (Check Valve L 4.1.5.d.1 SLC% operabtitty Manual Initiation 4.1.5.d.1 4.1.5.d.3 SLCS pop Relief Valve operability SLCS flow path deanstratten 4.3.1.1. Table 4.3.1.1-1. Item 11 RP5 Rs flade Switch shutsson positten funct 4.3.1.2 RPS Logic Syst m 'unctlen Test 1

4.3.t.1. Table 4.3.2.1-1. Item 1.h Pri Cent feeletten Actuation llanuel Ini atten factlanal 4.3.2.1. Table 4.3.t.1 1. It m t.d blCU - SLCS intttstion channel funett I test .

l 4.3.t.1. Table 4.3.2.1*1. Itse 5.c bet S/0 Cooling Rn manual Initiation unctional test

' 4.3.t.1. Table 4.3.t.1-1. Stee 6.a Sec. Cent. Testatten - Rs Water Law I - tmel I sal 4.3.2.2 feetatten Actuotten inst. L5FT 4.3.3.1. Table 4.3.3.1-1. Its 1.s Cs RPV Law Level 1 Cal 4.3.3.1. Table 4.3.3.1-1. Itas 1.c CS Rs Steam Osu Press Law Cal l

4.3.3.1. Table 4.3.3.1-1. Ito 1.d C5 Ilanual Initiation 4.3.3.1. Table 4.3.3.1-1. It s 2.s LPCI RPV Les Level 1 Cal 4.3.3.1. Table 4.3.3.1-1. Its 2.c LPCI Rs Steam Oame Press L Cal 4.3.3.1. Table 4.3.3.1-1. It s 2.d LPCI Rs Law Level 2 Cal

! 4.3.3.1. Table 4.3.3.1-1. Its f.e LPCI Rs Steam Does Press Cal 4.3.3.1. Table 4.3.3.1-1. Item t.h LPCI Manual Initiation 4.3.3.1. Table 4.3.3.1-1. It s 3.s MPCI RPV Low Level !

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4.3.3.1. Table 4.3.3.1-1. Itse 3.e NPCI RPV Migh Level 8 1 4.3.3.1. Table 4.3.3.1-1. Item 4.s A05 RPV Law Level 1 1 i

4.3.3.1. Table 4.3.3.1-1. It s 4.h A05 Drywell Pressu High Sypass Timor g

! 4.3.3.2 (CCS Logic Syst e unctional Tests l 4.3.3.3"' ECCS Response 71 Tests I 4.3.4. Table 4.3.4 1, Item 1 RPV Law Water

! 4.3.4.2 1 2 Cal (ATW5)

L ATW5 Logic 5 en Functional Test 4.3.5.1. Table 4.3.5.1-1. its a RPV Low Love I Cal (RCIC) 4.3.5.1. Table 4.3.5.1-1. Its b RPV Migh L 18Ca1(RCIC) 4.3.5.2 RCIC Lost ysten Functional Test 4.3.6. Table 4.3.5-1. It s 5.b Scram Of . Vol. Trip Bypass Funct. Test 4.3.6. Table 4.3.6-1. Itas 7 Rs witch Shutdown Pos. Red Black Funct. Test

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4.3.7.4.1. Table 4.3.7.4.-1. Itas t RPV L el Cal - Remote Shutdown 4.3.7.5. Table 4.3.7.5-1. It s il CTNT salation Valve Positten Cal Accident tien 4.3.7.5. Table 4.3.7.5-1. It s 2.b de Range Level Cal Accident Non 4.5.1.c.1 $ System Functional Test t

4.8.3.2 rimary Contalment Isol Valve operability 4.6.5.t.6 secordery Contalment isoletten Danger Actuettas 4.7.1.2.b ftCW Autenstic Actuotten 4.7.1.3.b EE$W Automatic Actuction 4.7.1.4.b EDS Cooling Water Pao Automatic Actuetten 4.7.2.1.t.1 ER Venttistian Filter Penetratten 4.7.2.1.t.t CR Venttistian Filter Cherceal Laboratory Ane13 ste 4.7.2.1.s.3 CR Centgency 711tratten syste Flowrote 4.7.2.1.e.1 Vent 11stian Filter Pressum Drop

! 4.7.1.1.e.t Emergency Ft1tratten System Operettenal Mode Actuetten i

4.7.2.1.e.4 CR reency Nakeup Inlet Mester Olssipetten 4.7.5.e r Functiens1 Test 4.8.1.1. Inspectten 4.8.1 .t.o. LeadRejection(1888bW) 4.8 .1.2.e.3 lead Rejection (2850 kW)

4. 1.1.t.. 4.. Lor tw sheddtag

.1.1.2.e.4.6 Lor Auto start and Lo.4 sequencias 4 i o

W V"r 4 F I - WIT 2 3/4 0 6 Amendment No.106 i

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l TABLE 4.0.2-2 '

SURVEILLANCE TEST INTERVALS EXTENDED TO) END OF SURVEILLANCE REQUIREMENT DESCRIPTION '

g 4.8.1.1.2.e.5 4.8.1.1.2.e.6 a EDG ECCs Auto Start

4. 8.1.1. 2.e. 8. b EDG LDP / ECCS Lead Shedding l

4.8.1.1.2.e.7 EDG LDP / ECC5 Auto Start and Load Sequencin 4 . 8.1.1. 2.e.8 EDG Non-essential Trip Bypass l

4.8.1.1.2.e.8 EDG 24 Hour Run and Hot Fast 5 tart. l i

4.8.1.1.2.e.10 EDG Auto Connect Load Verification l

4.8.1.1.2.e.!! EDG Restoration of Offstte Power *

! EDG Auto Load secuencer Tlear 4.8.1.J .2.e.12.s g ,

4.8.1.1.2.e.12.b EDG 4150-volt E5F Bus Lockout g I i

' 4. 8.1.1.2.e.12.c EDG Otfferential Trip Lockout  !

I 4.8.2.1.c.3 EDG Shutdown Relay Trie Lock I 4.8.2.1.c.4 130 VDC Battery Connections A tetance l j 4.8.2.1.d 130 VDC Batteey Charger Fu tonal Test i l 130 VDC Battery Capacity g

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TABLE NOTATIONS (a) e surveillance interval of channels within the same trip system equired to be tested at least once every N times 18 months, where N is the total number of' channels in the trip system, may be based upon the performance of the surveillance during the fifth. refueling outage.

! FERMI - UNIT 2 3/4 0-7 Amendment No.las

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a Attachment 3 to

.- NRC-98-0040 l

i ATTACHMENT 3 - PART 2 PROPOSED TECHNICAL SPECIFICATION REVISED PAGES INCLUDED PAGES: l 1

j Xxii )

3/40-2  ;

3/40-4 l 3/40-5 3/40-6 3/40-7 I

L_ _ .__. __ -. _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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.lB9.f1 L LIST OF TABLES i

>M ILAGE 1.1 SURVEILLANCE FREQUENCY. NOTATION.................. 1-9 1.2 OPERATIONAL CONDITIONS........................... 1-10 4

2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETP0lNTS........................................ 2-4  ;

1 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO SEPTEMBER 14, 1998............................... 3/4 0-4 j 4.0.2-2 SURVEILLANCE TEST INTERVALS EXTENDED TO END OF REFUELING OUTAGE 6....................... 3/4 0-6 l

, ' 3'. 3.1 - 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION........ 3/4 3-2 l'

l 3.3.1-2 DELETED.......................................... 3/4 3-6 3

4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION J SURVEILLANCE REQUIREMENTS........................ 3/4 3-7 q l

3.3.2-1. ISOLATION ACTUATION INSTRUMENTATION.............. 3/4 3 } 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS.... 3/4 3-15 l-3.3.2-3 DELETED.......................................... 3/4 3-18 i 4.3.2.1-1 ISOLATION ACTUATION INSTRUMENTATION l SURVEILLANCE REQUIREMENTS........................ 3/4 3-20 3.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.................................. 3/4 3-24 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION ,

INSTRUMENTATION SETP0lNTS........................ 3/4 3-27 1 3.3.3-3 DELETED.......................................... 3/4 3-29 4.3.3.1-1 EMERGENCY CORE COOLING. SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS........ 3/4 3-30 3.3.4-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.................................. 3/4 3-33

'3.3.4-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETP0lNTS......................... 3/4 3-34 FERMI - UNIT 2 xxii Amendment No. M , Jpp, JS$,

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APPLICABILITY SURVEILLANCE REQUIREMENTS )

4.0.1 Surveillance Requirements shall be met during the OPERATIONAL 3

l 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 performed within the specified

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

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

. 4.0.3 . Failure 'to perform a Surveillance Requirement within the allowed surveillance 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.-

4.0.4 ' Entry into an OPERATIONAL CONDITION or other specified applicable 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 shall not:arevent' passage through or to OPERATIONAL CONDITIONS as required to comply witi ACTION requirements.

'4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code 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 shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(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:

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FERMI - UNIT 2 3/4 0-2 Amendment No. JJ, S , JSJ,

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l TABLE 4.0.2-1 l SURVEILLANCE TEST INTERVALS EXTENDED TO SEPTEMBER 14. 1998 l SURVEILLANCE REQUIREMENT DESCRIPTION 4.3.1.1, Table 4.3.1.1 1, Jtem 3 RPS Rx Steam Dome Press High cal.

4.3.1.1, Table 4.3.1.1 1, item 4 RPS Rx Low Water Level - Level 3 cal

, 4.3.1.1, Table 4.3.1.1 1, Item 6 RPS Main Steam Line Radiation High cal l 4.3.1.1, Table 4.3.1.1 1, item 7 RPS Drywell Pressure High cal 4.3.2.1, Table 4.3.2.1 1, item 1.a.1 Pri Cont Isolation Actuation Rx Water Low - Level 3 cal 4.3.2.1, Table 4.3.2.1 1, Item 1.a.2 Pri Cont Isolation Actuation Rx Water Low - Level 2 cal 4.3.2.1, Table 4.3.2.1 1, item 1.a.3 Pri Cont Isolation Actuation Rx Water Low - Level 1 cal 4.3.2.1, Table 4.3.2.1 1, Item 1.b Pri cont Isolation Actuation Drywell Press High cal 4.3.2.1, Table 4.3.2.1 1, Item 1.c.1 Pri Cont Isolation Actuation Main Steam Line Radiation High cal 4.3.2.1, Table 4.3.2.1-1, Item 1.c.2 Pri Cont Isolation Actuation Main Steam Line Press Low cal 4.3.2.1, Table 4.3.2.1 1, Item 1.c.3 Pri Cont Isolation Actuation Main Steam Line Flow High cal 4.3.2.1, Table 4.3.2.1 1, Itam 1.d Pri Cont isolation Actuation Main Steam Line Tunnel Tenp. High cal 4.3.2.1, Table 4.3.2.1 1, item 1.e Pri Cont isolation Actuation Condenser Press High cal 4.3.2.1, Table 4.3.2.1-1, Item 1.f Pri Cont Isolation Actuation Turbine Bldg. Area Temp. High cal 4.3.2.1, Table 4.3.2.1 1, item 1.h Pri cont isolation Actuation Manual Initiation Functional 4.3.2.1, Table 4.3.2.1 1, item 2.d RWCU - SLCS initiation channel functional test 4.3.2.1, Table 4.3.2.1 1, Item 2.e RWCU lsolation Rx Water Low Level - Level 2 channel cal 4.3.2.1, Table 4.3.2.1 1, Item 5.s RHR S/D Cooling Rx Water Level Low - Level 3 cal 4.3.2.1, Table 4.3.2.1 1, Item 5.c RHR S/D Cooling Rx manual initiation functional test 4.3.2.1, Table 4.3.2.1 1, item 6.b Sec. Cont. Isolation Drywell Press High channel cal 4.3.3.1, Table 4.3.3.1-1, Item 1.b CS Drywell Press High Cal 4.3.3.1, Table 4.3.3.1 1, Item 2.b LPCI Drywell Press High Cal 4.3.3.1, Table 4.3.3.1 1, Item 3.s HPCI RPV Low Level 2 Cal 4.3.3.1, Table 4.3.3.1-1, Item 3.b HPCI Drywell Press High Cal 4.3.3.1, Table 4.3.3.1 1, Item 4.s ADS RPV Low Level 1 Cat 4.3.3.1, Table 4.3.3.1-1, Item 4.f ADS RPV Low Level 3 Cal 4.3.3.1, Table 4.3.3.1-1, Item 4.h ADS Drywell Pressure High Bypass Timer 4.3.4, Table 4.3.4 1, Item 1 RPV Low Water Level 2 Cat (ATWS) 4.3.4, Table 4.3.4-1, Item 2 RPV Press High Cat (ATWS) 4.3.4.2 ATWS Logic System Functionat Test 4.3.5.1, Table 4.3.5.1 1, item a RPV Low Level 2 Cat (RCIC) 4.3.5.1, Table 4.3.5.1 1, Item b RPV High Level B Cal (RCIC) 4.3.5.2 RCIC Logic System Functional Test 4.3.7.5, Table 4.3.7.5-1, Item 1 RPV Press Cal Accident Mon.

4.3.7.5, Table 4.3.7.5-1, Item 2.a RPV Fuel Zone Level Cal Accident Mon 4.3.7.5, Table 4.3.7.5 1, Item 2.b RPV Wide Range Level Cat Accident Mon 4.3.7.5, Table 4.3.7.5-1, Item 12 CTMT High Range Red Monitoring Cal Accident Mon.

4.3.7.5, Table 4.3.7.5 1, item 16 CTNT isolation Valve Position Cal Accident Mon 4.3.9.1, Table 4.3.9.1 1, Item a RPV High Water Level 8 Cat FW/ Main Turbine Trip 4.3.9.2 FW/ Main Turbine Trip LSFT j 4.3.11.1, Table 4.3.11.1 1, Item 7 Alt S/D system Rx Water Level instrument operablAity i 4.3.11.1, Table 4.3.11.1 1, Item 8 Alt S/D system Rx Press instre ent operability 4.4.2.2.b SRV Low Low Set Pressure setpoint Cat and LSFT 4.5.1.d.2.a ADS System Functiorial Test 4,6.3.2 Primary Containment Isol Valve operability 4.7.4.c.1 RCic Functional Test 4.8.4.2.a.1.a Prl. Cont. Pen. Conductor Overcurrent Devices Functional Test 4.8.4.2.a.1.b Prl. Cont. Pen. Conductor Overcurrent Devices Functional Test FERMI - UNIT 2 3/4 0-4 Amendment No. JpE, JSE,

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TABLE 4.0.2-2 SURVEILLANCE TEST INTERVALS EXTENDED TO END OF REFUELING OUTAGE 6 l SURVEILLANCE RE0VIREMENT DESCRIPTION 4.0.5 IST - Non Interruptible Air Supply (NIAS) Isolation Valves 4.1.3.5.b.2 CR Accumulator Integrity Test (Check Valve Leakage) 4.1.5.d.1 SLCS operability Manual Initiation 4.1.5.d.2 SLCS pump Relief Valve operability 4.1.5.d.3 SLCS flow path demonstration 4.3.1.1, Table 4.3.1.1-1, Item 11 RPS Rx Mode Switch shutdown position functional 4.3.1.2 RPS Logic System Function Test 4.3.2.1, Table 4.3.2.1-1, Item 6.a Sec. Cont. Isolation - Rx Water Low Level - Level 2 cal 4.3.2.2 Isolation Actuation Inst. LSFT 4.3.3.1, Table 4.3.3.1-1, Item 1.a CS RPV Low Level 1 Cal 4.3.3.1, Table 4.3.3.1 1, item 1.c CS Rx Steam Dome Press Low Cal 4.3.3.1, Table 4.3.3.1 1, item 1.d CS Manual Initiation 4.3.3.1, Table 4.3.3.1 1, Item 2.a LPCI RPV Low Level 1 Cat 4.3.3.1, Table 4.3.3.1-1, Item 2.c LPCI Rx Steam Dome Press Low Cal 4.3.3.1, Table 4.3.3.1-1, item 2.d LPCI Rx Low Level 2 Cal 4.3.3.1, Table 4.3.3.1-1, item 2.e LPCI Rx Steam Dome Press Low Cat 4.3.3.1, Table 4.3.3.1 1, Item 2.h LPCI Manual Initiation 4.3.3.2 ECCS Logic System Functional Tests 4.3.3.3(a) ECCS Response Time Tests 4.3.6, Table 4.3.6 1, item 5.b Scram Disc. Vol. Trip Bypass Funct. Test 4.3.6, Table 4.3.6-1, Item 7 Rx Mode Switch Shutdown Pos. Rod Block Funct. Test 4.5.1.c.1 ECCS System Functional Test 4.6.5.1.d.1 Secorufary containment SGTS Test 4.6.5.1.d.2 Secondary containment SGTS Test 4.6.5.2.b secondary containment Isolation Damper Actuation 4.7.1.2.b ECCW Automatic Actuation 4.7.1.3.b EESW Automatic Actuation 4.7.1.4.b EDG Cooling Water Punp Automatic Actuation 4.7.2.1.c.1 CR Ventilation Filter Penetration 4.7.2.1.c.2 CR Ventilation Filter Charcoal Laboratory Analysis 4.7.2.1.c.3 CR Emergency Filtration System Flowrate 4.7.2.1.e.1 CR Ventilation Filter Pressure Drop 4.7.2.1.e.2 CR Emergency Filtration System Operational Mode Actuation 4.7.2.1.e 4 CR Emergency Makeup Inlet Heater Dissipation 4.7.5.e Snubber Functional Test 4.8.1.1.2.e.1 EDG Inspection 4.8.1.1.2.e.2 EDG Load Rejection (1666 kW) 4.8.1.1.2.e.3 EDG Load Rejection (2850 kW) 4.8.1.1.2.e.4.a EDG LOP Load shedding 4.8.1.1.2. e. 4. b EDG LOP Auto Start and Load Sequencing 4.8.1.1.2.e.5 EDG ECCS Auto Start 4.8.1.1.2.c.6 a EDG LOP / ECCS Load Shedding 4.8.1.1.2.e.6.b EDG LOP / ECCS Auto Start and Load Sequencing 4.8.1.1.2.e.7 EDG Non-essential Trip Bypass 4.8.1.1.2.e.8 EDG 24 Hour Run ard Hot f ast Start.

4.8.1.1.2.e.9 EDG Auto connect Load Verification 4.8.1.1.2.e.10 EDG Restoration of Offsite Power 4.8.1.1.2.e.11 EDG Auto Load Sequencer Timer 4.8.1.1.2.e.12.s EDG 4160-volt ESF Bus Lockout 4.8.1.1.2.e.12.b [DG Differentiet Trip Lockout 4.8.1.1.2.e.12.c EDG Shutdown Relay Trip Lockout 4.8.2.1.c.3 130 VDC Battery Connections Resistance 4.8.2.1.d 130 VDC Battery capacity 4.8.4.5.a SLCS Circuit Breakers Functional Test TABLE NOTATIONS (a) The surveillance interval of channels within the same trip system required to be tested at least once every N times 18 months, where N is the total number of channels in the trip system, may be based upon the performance of the surveillance during the sixth refueling outage. l FERMI - UNIT 2 3/4 0-6 Amendment No. R6,

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