ML20092L176

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Proposed Tech Specs,Allowing one-time Extension of Surveillance Intervals
ML20092L176
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 09/20/1995
From:
DETROIT EDISON CO.
To:
Shared Package
ML20092L174 List:
References
NUDOCS 9509260322
Download: ML20092L176 (8)
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Text

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' NRC-95-0096 -

Page1 PROPOSED TECHNICAL SPECIFICATION CIIANGES l

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i 9509260322 950920 PDR AD(L ' V5000341

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..PDR

APPLICABILITY SURVEILLANCE REQUIREMENTS Surveillance Requirements shall be met during the OPERATIONkL 4.0.1 CONDITIONS or other conditions specified for individual Limiting Coaditions 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 percent of the specified surveillance interval.

For the purpose of the fifth 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 i

noncompliance with the OPERABILITY requiremen'ts 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 prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservi,pe inspection and testing of ASME Code Class 1, 2, & 3 components shall be ap31icable 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 Specifjcations:

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FERMI - UNIT 2 3/4 0-2 Amendment No. Al, A5,

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-l CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)-

g.-

ECCS and RCIC containment ' isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak -

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' tested at least once per 18 months.

h.

Purge supply and exhaust isolation valves with resilient material seals _ shall be tested and demonstrated OPERABLE per Specification 4.6.1.8.2.

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The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2a., 4.6.1.2b.* and 4.6.1.2c.

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  • Extension of Specification 4.6.1.2b per Table 4.0.2-1 for the fifth refueling outage is: allowed.

F FERMI - UNIT 2 3/4 6-7 Amendment No.

1 PLANT SYSTEMS

~ SURVEILLANCE RE0'UIREMENTS fContinued) i h.

At'least once per)36 months ## by verifying that the sections of j

Control Room Emergency Filtration System duct listed in Table 8

4.7.2.1-1, when leak tested in accordance with ASME N510-1989

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exhibit 1nleakage less.than the acceptance criteria listed in Table 4.7.2.1-1 for the associated pressures.

4.7.2.2 The portions.of the Control' Room Emergency Filtration System duct listed below, which are accessible during normal operation, shall be visually inspected at least once per 366 days for cracking, debonding, or other~

abnormal degradation of the applied silicone sealant. Any such cracking,-

I debonding, or other abnormal. degradation shall be reported in accordance with

- Specification-6.9.2 within 14 days in a Special Report describing the findings

.i and giving the intended course of action, including evaluation of and justification for continued plant operation.

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a.

Normal intake between damper T4100F042 and the Control Room wall

_(Penetration V-430) b.

Nor. mal exhaust between damper T4100F044 and the Control Room wall l

.(Penetration V-429) c.

Discharge of recirculation fans T4100C047, 48 between the discharge flanges on filter train T41000016 and the 5th Floor CCHVAC Equipment Room wall (Penetration V-5048) j d.

Division II supply plenum between the Control Room wall (Penetration V-431) and the 4th Floor Aux. Building ceiling (PenetrationV-9014) 4 e.

Emergency intake between the discharge flange on filter train T4100D0ll and the inlet flange on filter train T4100D016 f.

. Recirculation duct between the 5th Floor CCHVAC Equipment Room wall (Penetration V-504A) and the inlet flange on filter train l

T4100D016 4 -

  1. Tests performed in accordance with ANSI N510-1980 prior to the implementation

.of,this requirement satisfy.this requirement until the next required

.per_formance of the test.

    1. This surveillance' requirement may be extended on a one-time basis to June 1, L

1998.

FERMI - UNIT 2 3/4 7-10a Amendment No. SS,

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TABLE 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 5. 1995 SURVEILLANCE REOUIREMENT 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. Item 3 RPS Rx Stesm Dome Press High cal.

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

4.3.1.1. Table 4.3.1.1-1, Item 5 RPS MS!V 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, item 7 kPS Drywell Pressure High cal 7

4.3.1. 3

RPS Response Time Test 4.3.2.1. Table 4.3.2.1-1, item 1.a.1 Pri Cont Isolation Actuation Rx Water Low Level - Level 3 cal 4.3.2.1 Tablw 4.3.2.1-1, item 1.a.2 Pri Cont Isolation Actuation Rx Water Low Level - 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 - 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.d Pri Cont Isolation Actuation Main Steam Line Tunnel Temp. High cal

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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, Jtem 2.e RWCU ! solation Rx Water Low Level - Level 2 channel cal 4.3.2.1, Table 4.3.2.1-1, Item 2.g RWCU Manual Initiation channel functional test 4.3.2.1. Table 4.3.2.1-1, Item 3.a.1 RCIC Steam Line Flow High DP channel cal 4.3.2.1. Table 4.3.2.1-1, item 3.a.2 RCIC Steam Line Flow High Time Delay cal 4.3.2.1, Table 4.3.2.1-1, Item 4.a.1 HPCI Steam Line Flow High DP cal t

4.3.2.1, Table 4.3.2.1-1, Item 4.a.2 HPCI Steam Line Flow High Time Delay cal 4.3.2.1, Table 4.3.2.1-1, Jtem 4.e HPCI Manual Initiation functional test i

4.3.2.1, Table 4.3.2.1-1, Item 5.a RHR S/D Cooling Rx Water Level Low - Level 3 cal 4.3.2.1 Table 4.3.2.1-1, Item 6.b Sec. Cont. Isolation - Drywell Press High channel cal 7

4.3.C.3

Isolation Actuation Inst. System Response !ime 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 2.f LPCI Riser Differential Pressure High Cal 4.3.3.1, Table 4.3.3.1-1, Item 2.g LPCI Recirc. Pump Differential Pressure High 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 3.f HPCI Manual Initiation 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 4.1 ADS Manual inhibit Functional Test 4.3.4, Table 4.3.4-1, item 2 RPV Press High Cal (ATVS) 4.3.7.4.1, Table 4.3.7.4.-1, Item 1 RPV Press Cal - Remote Shutdown 4.3.7.5, Table 4.3.7.5-1, Item 1 RPV Press Cal Accident Hon.

4.3.7.5, Table 4.3.7.5-1, item 11 SRV Position Indic Cal Accident Mon.

4.3.7.5, Table 4.3.7.5-1, Item 12 CTMT High Range Rad Monitoring Cal Accident Mon.

4.3.7.5, Table 4.3.7.5-1, item..A RPV Fuel Zone Level Cal Accident Mon 4.3.7.1D.c Loc.,e Part Detection System Cal 4.3.9.1. Table 4.3.9.1-1, Item M High Water level 8 Cal FW/ Main Turbine Trip 4.3.9.2 R :tsin Turbine Trip LSFT 4.3.11.1. iable 4.3.11.1-1,11 u

  • l'.t S/D system Rx Water Level instrument operability 4.3.11.1 Table 4.3.11.1-1, Itte e Alt S/D system Rx Press instrument operability 4.4.2.1.1 SRV Tail Pipe Pressure Switch Cal 4.4.2.1.2 SRV lif t set point test 4.4.2.2.b SRV Low Low Set Pressu v setpoint Cal and LSFT 4.4.3.1.b Drywell Sump Flow /Lvl hu..itoring Cal 4.4.3.2.2.a RCS Pressure Isol Valve Leak Test 4.5.1.d.2.a ADS System functional Test 4.6.1.2.b Type B and C LLRT's 4.6.1.2.d MSIV Leak Test 4.6.1.2.g Hydrostatic Leak Test ECCS/RCIC Cont Isol Valves 4.6.1.4.d.3 MSIV LCS Press Inst. Cal and DP Calibration FERMI - UNIT 2 3/4 0-4 Amendment No.

l TABLE 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 5. 1995 Cont'd g

EURVEILLANCE REQUIREMENT DESCRIPTION 4.6.2.1.e Suppression Caamber operability (visual inspection) 4.6.2.1.h Suppression Chamber operability DW to torus bypass leak test 4.6.3.4 Instr. Excess Flow Check operability 4.6.3.5.b TIP Explosive Squib ope.

lity test 4.6.4.1.b.2.a Torus /Drywell vacuum breaker setpoint operability 4.6.4.1.b.2.b Torus /Drywell vacuum L eaker position indication cal 4.6.4.1.b.2.c Torus /Drywell vacuum breeker switch opening gap 4.6.4.2.b.2.a RB/TorusVacuumBreakeroperability(setpoint) 4.6.4.2.b.2.b RB/ Torus Vacuum Breaker operability (visual) 4.6.4.2.b.2.c RB/ Torus Vacuum Breaker position indication operability 4.7.11.4 Alternative Shutdown Control Circuit Functional Test 4.8.4.2.a.1.a Primary Containment'4160 Volt Penetration Protective Relay Cal 4.8.4.2.a.1.b Primary Containment 4160 Volt Penetration Protective Device Integrated Functional Test i

l 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 fifth refueling outage.

FERMI - UNIT 2 3/4 0-5 Amendment No.

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TABLE 4.0.2-2 SURVEILLANCE TEST INTERVALS EXTENDED TO END OF REFUELING OUTAGE 5 SURVEILLANCE REQUIREMENT DESCRIPTION i

4.1.3.5.b.2 CR Accumulator Integrity Test (Check Valve Leakage) f 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 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 5.c RHR S/D Cooling Rx manual initiation functional 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 i

4.3.3.1. Table 4.3.3.1-1, Item 2.a LPCI RPV Low Level 1 Cal 4.3.3.1. Table 4.3.3.1-1. Item 2.c LPCI Rx Stea.n Dome Press Low Cal t'

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 Cal 4.3.3.1. Table 4.3.3.1-1, Item 2.h LPCI Manual Initiation 4.3.3.1. Table 4.3.3.1-1, Item 3.a HPCI RPV Low Level 2 Cal 4.3.3.1. Table 4.3.3.1-1, Item 3.e HPCI RPV High Level 8 Cal 4.3.3.1 Table 4.3.3.1-1. Item 4.a ADS RPV Low Level 1 Cal 4.3.3.1 Table 4.3.3.1-1, item 4.h ADS Drywell Pressure High Bypass Timer 4.3.3.2 ECCS Logic System functional Tests i

4.3.3.3

  • ECCS Response Time Tests 4.3.4, Table 4.3.4-1, Item 1 RPV Low Water Level 2 Cal (ATVS) 4.3.4.2 ATWS Logic System Functional Test 4.3.5.1, Table 4.3.5.1-1, Item a RPV Low Level 2 Cal (RCIC) 4.3.5.1 Table 4.3.5.1-1, Item b RPV High Level 8 Cal (RCIC) 4.3.5.2 RCIC Logic System Functional Test 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 4.3.7.4.1. Table 4.3.7.4.-l, Item 2 RPV Level Cal - Remote Shutdown 4.3.7.3 Table 4.3.7.5-1, item 16 CTMT ! solation Valve Position Cal Accident Mon 4.3.7.5, Table 4.3.7.5-1, Item 2.b RPV Vide Range Level Cal Accident Mon 4.5.1.c.1 ECCS System Functional Test 4.6.3.2 Primary Containment Isol Valve operability 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 Pump 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 EDGLoadRejection(1666kW) 4.8.1.1.2.e.3 EDG Load Rejection (2850 kW) 4.8.1.1.2.e.4.a EDS LDP Load Shedding 4.8.1.1.2.e.4.b EDG LDP Auto Start and Load Sequencing i

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FERMI - UNIT 2 3/4 0-6 Amendment No.

TABLE 4.0.2-2 i

SURVEILLANCE TEST INTERVALS EXTENDED TO END OF REFUELING OUTAGE 5'(Cont'd)

{

SURVEILLANCE REQUIREMENT DESCRIPTION I

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4.8.1.1.2.e.5 EDG ECCS Auto Start 4,8.1.1.2.e.6.a EDG LOP / ECCS Load Shedding i

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 and Hot fast Start.

4 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.a EDG 4160-volt ESF Bus Lockout 4.8.1.1.2.e.12.b EDG Differential Trip Lockout i

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4.8.1.1.2.e.12.c EDG Shutdown Relay Trip Lockout j

2 4.8.2.1.c.3 13D VDC Battery Connections Resistance 1

4.8.2.1.c.4

-13D VDC Battery Charger Functional Test 4.8.2.1.d 13D VDC Battery Capacity 1

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i 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 fifth refueling outage.

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

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