ML20237D146

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Amend 124 to License NPF-43,providing one-time Extension of Interval for Number of TS Surveillance Requirements That Will Be Performed During 6th Refueling Outage
ML20237D146
Person / Time
Site: Fermi 
Issue date: 08/04/1998
From: Kugler A
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20237D147 List:
References
NUDOCS 9808250097
Download: ML20237D146 (11)
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Text

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t UNITED STATES

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NUCLEAR REGULATORY COMMISSION e

WASHINGTON, D.C. 3068H001

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DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 124 License No. NPF-43 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Detroit Edison Company (the licensee) dated June 26,1998, as supplemented July 16 and July 23,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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9808250097 900804 ADOCK 050003 1 DR o-__-----___

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2} of Facility Operating License No. NPF-43 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 124, and the Environmental Protection Plan contained in Appandix B, are hereby incorporated in the license. DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance with full implementation within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Andrew J, Kugler, Project Manager j

Project Directorate 111.-1 1

Division of Reactor Projects -Ill/lV

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Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 4, 1998 i

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l ATTACHMENT TO LICENSE AMENDMENT NO.124 j

E6CILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 i

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain verticallines j

indicating the area of change.

REMOVE INSERT l

l xxii xxii 3/4 0-1 3/4 0-1*

3/4 0-2 3/4 0-2 3/4 0-3 3/4 0-3*

3/4 0-4 3/4 0-4 3/4 0-5 3/4 0-5 3/4 0-6 3/4 0-6 l

3/4 0-7 3/4 0-7 l

  • Overleaf pages provided to maintain document completeness. No changes contained on these pages.

INDEX LIST OF TABLES

.TR.LE

_P.bAGE l

1.1 SURVEILLANCE FREQUENCY NOTATION..................

1-9 1.2 OPERATIONAL CONDITIONS...........................

1-10 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETP0INTS.................

2-4 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO SEPTEMBER 14.

1998...............................

3/4 0-4 l

4.0.2-2 SURVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 18. 1998................................

3/4 0-6 l

3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION........

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

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 DELETED......................

3/4 3-18 4.3.2.1-1 ISOLATI0" ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................

3/4 3-20 3.3.3-1 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 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 ATWS RECIRCULATION PUMP TRIP SYSTEM l

I NSTRUMENTATI ON..................................

3/4 3-33 3.3.4-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETP0lNTS........................

3/4 3-34 l

FERMI

. UNIT 2 xxii Amendment No.42. 100. 106.124 1

3/4,0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained' in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTIDW requirements shall be met.

3.0.2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirement.s are not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

I.

At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

At least HDT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION

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requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

This Specification is not applicable in OPERATIONAL CONDITION 4 or 5.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall I

8 not be made when the conditions for the Limiting Conditions for Operation are I

not met and the associated ACTIDH requires a shutdown if they are not met I

within a specified time interval. Entry into an OPERATIONAL CONDITION or I

l ether specified condition may be made in accordance with the ACTION I

l requirements when conformance to them permits continued operation of the I

j facility for an unlimited period of time. This provision shall not prevent I

l passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION l

J requirements.

Exceptions to these requirements are stated in the individual Specifications.

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FERMI - UNIT 2 3/4 0-1 Amendment No.83 JUN 2 51992 L

APPLICABILITY SURVEILLANCE RE0VIREMENTS 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 specified surveillance' interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

For the purpose of the sixth l

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.

i 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 prevent passage through or to OPERATIONAL CONDITIONS ks required to comply with 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, Section50.55a(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 Csde and applicable Addenda shall be applicable as follows in these Technical Specifications:

l FERMI - UNIT 2 3/4 0-2 Amendment No. JJ, #, #5,124

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APPLICABILITY SURVEILLANCE REQUIREMEtiTS.(Continued)

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ASME Sailer and Pressure Versal Required frequencies Code and applicable Addenda for performing inservJce terminology for inservice inspection and testing inspectionandtestingactivities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 monus At least once per 92 days semiannually or every 6 months At least once per 184 days Every 9 mor.ths At least once per 276 days Yearly or annually At least once per 366 days c.

The provisions of Specification 4.0.2 are applicable to the above recuired frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities st.all be in addition to other specified Surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

1.

The Inservice Inspection (NDE) Program for piping identified in NRC Generic Letter 88-01, dated January 25, 1988, 'NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping", shall be performed in accordance with the staff positions on schedule, methods and

vrsonnel, and sample expansion included in this generic letter.

l FEr.! - UNIT 2 3/4 0-3 Amendment No. 2T,52 l

NAR261990

1 TABLE 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO SEPTEMBER 14. 1998 l

SURVEILLANCE REQUIREMENT DESCRIPTION 4.3.1.1, Table 4.3.1.1 1, Item 3 RPS Rx Steam Dome Press High cat.

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 cet 4.3.1.1, Table 4.3.1.1 1, Item 7 RPS Drywell Pressure High cal 4.3.1.3, Table 4.3.1.1 1, Item 2.b APRM Flow Blased Thermal Power - High 4.3.1.3, Table 4.3.1.1 1, Item 2.c APRM Fixed Heutron Flux - High 4.3.2.1, Table 4.3.2.1 1, Item 1.a.1 Pri Cent Isolation Actuation Ax Water Low Levet 3 cat 4.3.2.1, Table 4.3.2.1 1, Item 1.s.2 Pri Cent 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 cent Isolation Actuation Drywall Press High cal 4.3.2.1, Table 4.3.2.1 1, Item 1.c.1 Pri cent 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 cat 4.3.2.1, Table 4.3.2.1 1, item 1.d Pri Cont Isolation Actuation Main Steam Line Tunnet Temp. 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 cm Isolation Actuation Turbine Bldg. Area Temp. High cal 4.3.2.1, Table 4.3.2.1 1, item 1.h Pri Cent Isolation Actuation Manual Initiation Functional 4.3.2.1, Table 4.3.2.1 1, item 2.d RWCU SLCS initiation channet functional test 4.3.2.1, Table 4.3.2.1 1, item 2.e RWCU Isolation Rx Water Low Level - Level 2 channel cal 4.3.2.1, Table 4.3.2.1 1, item 5.s RHR $/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 menual initiation functional test 4.3.2.1, Table 4.3.2.1 1, Item 6.b Sec. Cont. Isolation - Drywell Press High channet 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 Cat 4.3.3.1, Table 4.3.3.1 1, item 3.b HPCI Drywell Press High Cat 4.3.3.1, Table 4.3.3.1 1, I tem 4.s ADS RPV Low Level 1 Cal 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 gypass 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 Functional 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 8 Cat (RCIC) 4.3.5.2 RCIC Logic System Functional Test 4.3.7.5, Table 4.3.7.5 1, item i RPV Press Cat Accident Mon.

4.3.7.5, Table 4.3.7.5 1, item 2.s RPV Fuel Zone Level Cat Accident Mon 4.'l.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 Cat Accident Mon.

4.3.7.5, Table 4.3.7.5 1, Item 16 CTMT Isolation Valve Position Cal Accident Mon 4.3.9.1, Table 4.3.9.1 1, Item a RPV High Water Level 8 Cal FW/ Main Turbine Trip 4.3.9.2 FW/ Main Turbine Trip LSFT 4.3.11.1, Table 4.3.11.1 1, Item 7 Alt S/D system Rx Water Levet instrunent operability 4.3.11.1, Table 4.3.11.1 1, item 8 Alt S/D system Rx Press instrument operability 4.4.2.2.b SRV Low Low Set Pressure setpoint Cat and LSFT 4.5.1.d.2.s ADS System Functional Test 4.6.3.2 Primary Containment Isol valve operability 4.7.4.c.1 RCIC Functional Test 4.8.4.2.a.1.s Prl. Cont. Pen. Conductor overcurrent Devices Functional Test l

I 4.8.4.2.a.1.b Prl. Cont. Pen. Conductor Overcurrent Devices Functional Test

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FERMI - UNIT 2 3/4 0-4 Amendment No. 106. 108. 124 l

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FERMI - UNIT 2 3/4 0-5 Amendment No. Jp),124 J

TABLE 4.0.2-2 SURVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 18. 1998 l

SURVEILLANCE REQUIREMENT DESCRIPTION l

4.1.3.5.b.2 CR Accunutator Integrity Test (Check valve Leekage) 4.1.5.d.1 SLCS operability Manual Initiation 4.1.5.d.2 sLCs purp Relief Velve 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 functionet 4.3.1.2 RPS Logic system Function Test 4.3.2.1, Table 4.3.2.1 1, Item 6.e 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.s CS RPV.ow Level 1 Cet 4.3.3.1, Tebte 4.3.3.1 1, Item 1.c Cs Rx steam Dome Press Low Cet 4.3.3.1, Table 4.3.3.1 1, item 1.d Cs Manual Initletion 4.3.3.1, Table 4.3.3.1 1, Item 2.s LPCI RPV Low Levet 1 Cet 4.3.3.1, Table 4.3.3.1 1, Item 2.c LPCI Rx steem Dome Press Low Cat 4.3.3.1, Table 4.3.3.1 1, Item 2.d LPCI Rx Low Levet 2 Cat 4.3.3.1, Table 4.3.3.1 1, item 2.e LPCI Rx steem 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 serem 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 secondary Containment SGTS Test 4.6.5.1.d.2 secondary Containment $GTs Test 4.6.5.2.b secondary Containment Isolation Denper 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 Putip Automatic Actuation 4.7.2.1.c.1 CR Ventilation Filter Penetration 4.7.2.1.c.2 CR Ventitetton Filter Charcoat Laboratory Analysis 4.7.2.1.c.3 CR Emergency Filtration system Flowrote 4.7.2.1.e.1 CR Ventilation Filter Pressure Drop 4.7.2.1.e.2 CR Emergency Fittration system Operational Mode Actuation 4.7.2.1.e.4 CR Emergency Makeup Intet Hester Dissipation 4.7.5.e snubber Functionet 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.s EDG LDP Loed shedding 4.8.1.1.2.e.4.b EDG LDP Auto start and Loed sequencing 4.8.1.1.2.e.5 EDG ECCS Auto start 4.8.1.1.2.e.6.e EDG LDP / ECCS Load shedding 4.8.1.1.2.e.6.b EDG LDP / ECCS Auto start and Load sequencing 4.8.1.1.2.e.7 EDG Non essentist Trip Bypass 4.8.1.1.2.e.8 EDG 24 Hour Run and Hot fast start.

4.8.1.1.2.e.9 EDG Auto connect Load verification 4.8.1.1.2.e.1D EDG Restoration of Dffsite Power 4.8.1.1.2.e.11 EDG Auto Load sequencer Timer 4.8.1.1.2.e.12.s EDG 416D volt EsF Bus Lockout 4.8.1.1.2.e.12.b EDG Dif forentist Trip Lockout 4.8.1.1.2.e.12.c EDG shutdown Retsy Trip Lockout 4.8.2.1.c.3 13D VDC Battery Connections Resistance 4.8.2.1.d 13D VDC Battery Capacity 4.8.4.5.a SLCS Circuit Breakers Ftmettonal 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. 206.124

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l FERMI - UNIT 2 3/4 0-7 Amendment No. JSE 124 u__.-_-----

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