ML20117B464
| ML20117B464 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/19/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117B467 | List: |
| References | |
| NUDOCS 9608270063 | |
| Download: ML20117B464 (11) | |
Text
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l CORRECTED TS PAGES FOR LICENSE AMENDMENT NO. 108 l
FACILITY OPERATING LICENSE N0. NPF-43 DQLKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached corrected TS pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
4 REMOVE INSERT 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*
3/4 6-7 3/4 6-7 3/4 6-8*
3/4 6-8*
3/4 6-9 3/4 6-9***
3/4 6-10*
3/4 6-10*
3/4 6-11 3/4 6-11***
3/4 6-12*
3/4 6-12*
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- 0verleaf page provided to maintain document completeness. No changes contained on these pages.
- TS pages previously issued with Amendment No. 106. Should not have been issued with Amendment No. 108.
- These pages are being re-issued as corrected because their overleaf pages were not issued with Amendment No. 108.
Although marked." Corrected,"
there have been no futher changes to these pages.
9608270063 960819 PDR ADOCK 05000341 P
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APPL _ICABILITY i
i SURVE1LLANCE REQUIREMENTS ftontinued) i ASME Boiler and pressure Vessel Required frequencies Code and applicable Addenda for performing inservice i
terminology for inservice inspection and testing j
inspection.and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days i
Even 9 months At least once per 276 days j
Yearly or annually At least once per 366 days c.
The provisions of Specification 4.0.2 are applicable to the above reoutred frequencies for performing inservice inspection and testing activities.
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d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
j e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical 4
Specification.
4 f.
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 i
in accordance with the staff positions on schedule, methods and personnel, and sample expansion included in this generic letter.
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FERMI - UNIT 2 3/4 0-3 Amendme'nt No. 3t',52 MAR 2 61990 r
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TABLE 4.0.2-1 SURVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 5. 1996 SURVEILLANCE REOUIREMENT DESCRIPTION 4.1.3.1.4.a RPS Rx Steam Dome Press High cal.
Scram discharge vol. vent and drain valve operability 4.3.1.1. Table 4.3.1.1-1, item 3 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 5 RPS MSIV 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 RPS Drywell Pressure High cal g
- 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. Table 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 Wate-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 Fri 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 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 2.e RWCU Isolation 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 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 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 6.b Sec. Cont. Isolation - Drywell Press High channel cal g
4.3.2.3 "
Isoletion Actuation Inst. System Response Time 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 Recire. 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 (ATWS) 4.3.7.4.1. Table 4.3.7.4.-1, Jtem 1 RPV Press Cal - Remote Shutdown 4.3.7.5. Table 4.3.7.5-1, Jtem 1 RPV Press Cal Accident Hon.
I 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 2.a RPV Fuel Zone Level Cal Accident Mon 4.3.7.10.c Loose Part Detection System Cal 4.3.9.1. Table 4.3.9.1-1, item a RPV High Water Level 8 Cal FV/ Main Turbine Trip 4.3.9.2 FV/ Main Turbine Trip LSFT 4.3.11.1. Table 4.3.11.1-1, Item 7 Alt S/D system Rx Water Level instrument operability 4.3.11.1. Table 4.3.11.1-1, Jtem 8 Alt $/D system Rx Press instrisnent operability 4.4.2.1.1 SRV Tail Pipe Pressure Switch Cal
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4.4.2.1.2 SRV lift set point test
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4.4.2.2.b SRV Low Low Set Pressure setpoint Cal and LSFT 4.4.3.1.b Drywell Stanp Flow /Lvl Monitoring Cal 4.4.3.2.2.s RCS Pressure Isol Valve Leak Test 4.5.1.d.2.a ADS System Functional Test 4.6.1.4.d.3 MSIV LCS Press Inst. Cal and DP Calibration l
FERMI - UNIT 2 3/4 0-4 Amendment No.106,108 Corrected
- August 19, 1996
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1 TABLE 4.0.2-1 EftVEILLANCE TEST INTERVALS EXTENDED TO OCTOBER 5.1996 Cont'd SURVEILLANCE REQUIREMENT DESCRIPTION 4.8.I.1.e suppression Chader operability (visual inspection) 4.6.2.1.h suppressten Chader operability OW to torus bypass leek test 4.6.3.4 Instr. Escess Flow Check operabt11ty 4.6.3.5.b TIP Explosive Squib operabillty test
- 4. 6. 4.1. b.t.a Torus /Drywell vacum breaker setpoint operability 4.6.4.1.b.t.b Torus /Drywell vacum breaker position indication cal 4.8.4.1.b.t.c forus/Drywell vacum bensker switch opening gap 4.5.4.2.b.t.a RS/ Torus Vacuun Breaker operability (setpolst) l 4.5.4.2.b.t.b RS/ Torus Vacum Breaker operability (visual) g 4.6.4.2.b.t.c RS/ Torus Vacum Breaker position indicattom operability g
4.7.11.4 alternative shutdown Control Circuit Functlanal-lost l
4.8.4.2.a.1.a Primary Contairement 4150 Volt Penetration Protective Relay Cal g
4.8.4.2.a.1.b Prianry Contalment 4160 Volt Penetration Pestective Device g
i Integrated Functional Test l
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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 mDnths, where N is i
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.106 LD 1 17:
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i TABLE 4.0.2-2 8
SURVEILLANCE TEST INTERVALS EXTENDED TO END OF REFUELING OUTAGE 5 l
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SURVEILLANCE REQUIREMENT DESCRIPTION i
4.1.3.5.b.2 CR Accumulator Integrity Test (Check Valve Leakage) 4.1.5.d.1 SLCS operability Manuel Initiation i
4.1.5.d.t SLCS pop Relief Valve operablitty 4.1.5.d.3 SLCS flow path demonstration 4.3.1.1. Table 4.3.1.1-1 Jtem 11 RPS Rx Mode Switch shutdown position functional i
4.3.1.2 RPS Logic System Function Test j
4.3.2.1, Table 4.3.2.1-1. Item 1.h Prt Cent Isolation Actuation Manual Initiation Functional 4.3.2.1. Table 4.3.2.1-1. Item t.d RWCU - SLCS initiation channel functional test I
4.3.2.1. Table 4.3.2.1-1. Item 5.c RIE S/D Cooling Rx manual initiation functional test i
1 4.3.2.1. Table 4J.t.1-1. Jtem 8.a Sec. Cont. Isoletten - Rx Water Lnw Level - Level I cal i
4.3.2.2 Isolation Actuation Inst. LSFT I
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4.3.3.1. Table 4.3.3.1-1,1 ten 1.a CS RPV Low Level 1 Cal I
i 4.3.3.1. Table 4.3.3.1-1. Item 1.c CS Rx Steam Dome Press Low Cal l
4.3.3.1. Table 4.3.3.1-1. Item 1.d CS Ranual Initiation l
4.3.3.1. Table 4.3.3.1-1. Itse 2.a LPCI RPV Low Level 1 Cal I
i 4.3.3.1. Table 4.3.3.1-1. Jtem t.c LPCI Rx Steam Dame Press Low Cal i
4.3.3.1. Table 4.3.3.1-1,1 tan 2.d LPCI Rx Low Level 2 Cal 4.3.3.1. Table 4.3.3.1-1. Item t.e LPCI Rx Steam Dome Press Low Cal i
4.3.3.1. Table 4.3.3.1-1. Item 2.h LPCI Manual Initiation
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4.3.3.1. Table 4.3.3.1-1. Item 3.a MPCI RPV Low Level I Cal l
4.3.3.1. Table 4.3.3.1-1. Item 3.e HPCI RPV Migh Level 8 Cal I
i 4.3.3.1. Table 4.3.3.1-1. Item 4.s ADS RPV Law Level 1 Cal l
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 4.3.3.3*
ECCS Response Time Tests 4.3.4. Table 4.3.4-1. Itan 1 RPV Low Water Level I Cal (ATWS) 4.3.4.2 ATWS Logic System Functional Test i
4.3.5.1. Table 4.3.5.1-1. Item a RPV Low Level 2 Cal (RCIC) l 4.3.5.1. Table 4.3.5.1-1. Item b RPVHighLevel8 Cal (RCIC) g 4.3.5.2 ACIC Logic System Functional Test l
4.3.6. Table 4.3.5-1. Item 5.b Scram Disc. Vol. Trip Sypass Funct. Test 4.3.6. Table 4.3.5-1. Item 7 Rx Node Switch Shutdown Pos. Rod Block Funct. Test 4.3.7.4.1. Table 4.3.7.4.-l. Item I RPV Level Cal - Remote Shutdown l
4.3.7.5. Table 4.3.7.5-1. Item Il CTNT Isolation Valve Position Cal Accident Mon i
4.3.7.5. Table 4.3.7.5-1. Item 2.b RPV Vide Range Level Cal Accident Mon I
4.5.1.c.1 ECCS Systen Functional Test i
4.6.3.2 Primary Containment Isol Valve operability
- 4. 8. 5.2.b Secondary Containment Isolation Damper Actuation 4.7.1.2.b ECCW Automatic Actuation l
4.7.1.3.b EESW Autonette Actuation l
i 4.7.1.4.b EDE teoling Water Pop Automatic Actuation 4.7.2.1.c.1 CR Ventilation Filter Penetration l
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l 4.7.2.1.c.2 CR Venttistion Filter Charcoal Laboratory Analysts 4.7.2.1.c.3 CR Emergency Filtration System Flowrote 1
4.7.2.1.e.1 CR Venttistion 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 Dissipetion 4.7.5.e snubber Functional Test l
4.8.1.1.E.e.1 EDE Inspection 4.8.1.1.2.e.2 E06LoadRejection(1666kW) i 4.8.1.1.t.e.3 EDG Load Rejection (2850 kW) 4.8.1.1.2.e.4.s EDS LOP Load Shedding i
4.8.1.1.2.e.4.6 EDE LOP Auto Start and Load sequencing ir i
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FERMI - UNIT 2 3/4 0-6 Amendment No.106 g
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l CONTAINMENT SYSTEMS
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THIS PAGE HAS BEEN INTENTIONALLY DELETED l
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d FERMI - UNIT 2 3/4 6-7 Amendment No. 106, 108 Corrected August 19, 1996
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT' AIR L0 cts LIMITING CONDITION FOR OPERATIM 3.6.1.3 Each primary containneet air lock shall be OPERABLE with:
8 Both doors closed estopt when the air lock is being used for normal a.
transit entry and exit through the containment, then at least one air lock door shall he closed, and b.
An overall air lock leakage rate of less than or equal to 0.05 La P, 56.5 psig.
at a
APPL 1tABILITY: OPERATIONAL CORITIONS 1, 2*, and 3.
ACTION:
With one primary containment air lock door inoperable:
a.
1.
Maintain at least the OPERABLE air lock door closed and either restore the inomrable air lock door to OPERABLE status within i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or loc t the OPERABLE air lock door closed.
i 2.
Operation may then continue until performance of the next required overall air lock leakage test provided that the CPERABLE air lock, door is verified to be locked closed at least i
ence per 31 days.
3.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHU15DWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I b.
With the primary containment air lock inoperable, except as a result of an inoperable air lack door, maintain at least one air lock door closed; restore the inuyerable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least ET SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within tRe following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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- See Special Test Exception 3.10.1.
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- WIT 2 3/46-8 Amendment No. 83, WM 2 61992
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each primary containment air lock shall be demonstrated OPERABLE:
l a.
Within 7 days following each closing, except when the air lock is 8
being used for multiple entries, then at least once per 30 days, by verifying seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to Pa*
56.5 psig, b.
Prior to establishing PRIMARY CONTAINMENT INTEGRITY when the air i
lock has been opened during periods when containment integrity was not required. The demonstration shall verify a seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to P 56.5 psig, unless the air lock is testedpursuanttoSpecif$c,ation4.6.1.3.c.2.
By conducting an overall air lock leakage test at P, 56.5 psig, c.
a and by verifying that the overall air lock leakage rate is within its limit:
1.
Prior to initial fuel loading and at 30 months
- intervals l
thereafter, 2.
Prior to establishing PRIMARY CONTAINMENT INTEGRITY when the air lock has been opened during periods when containment integrity was not required, if maintenance which could affect the leak tight integrity of the doors has been performed since the last successful test pursuant to Specification 4.6.1.3.c.1.
d.
At least once per 6 months by verifying that only one door in each air lock can be opened at a time.**
- The provisions of Specification 4.0.2 are not applicable.
- Except that the inner door need not be opened to verify interlock OPERABILITY when the primary containment is inerted, provided that the inner door interlock is tested within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the primary containment has been deinerted.
FERMI - UNIT 2 3/4 6-9 Amendment No.108 Corrected August 19, 1996
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.I CONTAINMENT SYSTEMS J
MSIV LEAKAGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION i
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3.6.1.4 Two independent MSIV leakage control system (LCS) subsystems shall be OPERABLE with each subsystem comprised of a flow path from the associated j
control air division to the main steam lines.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
I ACTION:
With one MSIV leakage control system subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS Each MSIV leakage control system subsystem shall be demonstrated 4.6.1.4 OPERABLE:
1 At least once per 31 days by cycling each testable valve except the a.
motor-operated MSIVs through at least one complete cycle of full
- travel, b.
During each COLD SHUTDOWN, if not performed within the previous 31 days, by cycling each valve including the motor-operated MSIVs not testable during operation through at least one complete cycle of full travel.
At least once per 18 months by performance of_a functional test of c.
the subsystem throughout its operating sequence, and verifying that each interlock operates as designed and each automatic valve actuates to its correct position.
d.
By verifying the pressure control (pressure and Ap) instrumentation to be OPERABLE by performance of a:
1.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.
CHANNEL FUNCTIONAL TEST at least once per 92 days, and 3.
CHANNEL CALIBRATION at least once per 18 months.
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FERMI - UNIT 2 3/4 6-10
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[0NTAINMENT SYSTEMS PRIMARY CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION l
3.6.1.5 The structural integrity of the primary containment shall be i
maintained at a level consistent with the acceptance criteria in Specification l
4.6.1.5.1.
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APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
i ACTION:
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With the structural integrity of the primary containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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SURVEILLANCE RE0VIREMENTS 1
i 4.6.1.5.1 The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment shall be determined during the I
shutdown for each Type A containment leakage rate test by a visual inspection of those surfaces. This inspection shall be performed prior to the Type A containment leakage rate test and during two other refueling outages before the next Type A test if the interval for the Type A test has been extended to 10 years to verify no apparent changes in appearance or other abnormal degradation.
4.6.1.5.2 Reoorts Any abnormal degradation of the primary containment structure detected during the above required inspections shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days. This report shall include a description'of the condition of the j
structure, the inspection procedure, the inspection criteria, and the j
corrective actions taken.
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l FERMI - UNIT 2 3/4 6-11 Amendment No.108 Corrected August 19, 1996
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CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.6 Drywell and suppression chamber internal pressure shall be maintained between -0.10 and +2.00 psig.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
1 ACTION:
With the drywell and/or. suppression chamber internal pressure outside of the specified limits, restore the internal pressure to within the limit within 1
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i SURVEILLANCE REQUIREMENTS 4.6.1.6 The drywell and suppression chamber internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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%m FERMI - UNIT 2 3/4 6-12
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