ML20083P498
| ML20083P498 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/19/1995 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20083P489 | List: |
| References | |
| NUDOCS 9505240230 | |
| Download: ML20083P498 (15) | |
Text
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.i 3.5.6 ' During the handling cf irradicted fu 1 in the r:cet:r building, ct 1cect-
)
onedooronthepersonnelandemergencyhatchesshallbecapableofbeingl l
' closed. : The equipment hatch cover shall be.in place with a minimum of four. bolts securing the cover to the sealing surfaces. At least 23 feet of water shall be maintained over the top.of irradiated fuel assemblies seated within the reactor pressure vessel.'
3.8.7.
Isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be closed.
3.8.8
'When two irradiated fuel assemblies are being moved simultaneously by the bridges within the fuel transfer canal, a minimum of.10 feet-separation shall be maintained between the assemblies at all. times.
3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated.to correct the conditions so-thst the specified limits are met, and no operations which may increase the reactivity of the core shall be made.- The provisions of specification 3.0.3 are not applicable.
3.8.10 The reactor building purge isolation system, including the radiation monitors shall be tested and verified to be operable within 7 days prior to refueling operations. The provisions of specification 3.0.3 are not applicable.
4 3.8.11 Irradiated fuel shall not be removed from the reactor until'the unit has been suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
In the event of a l
complete core offload, a full core to be discharged shall be suberitical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge of more than 70 assemblies to the spent fuel pool.- The provisions of j
specification 3.0.3 are not applicable ~
l 3.8.12 All fuel handling in the Auxiliary Building shall cease upon notification of the issuance of a tornado watch for Pope, Yell, Johnson, or Logan counties in Arkansas. Fuel handling operations
'in progress will be completed to the extent necessary to place the fuel handling bridge and crane in their normal parked and locked position. The provisions of specification 3.0.3 are not applicable.
'j 3.8.13 No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmospheric.
j dispersion conditions are equal to or better than those produced by i
Pasquill Type b stability accompanied by a wind velocity of 2 m/sec.
In addition, the railroad spur door of the Turbine Building shall be closed and the fuel handling area ventilation system shall be in operation. The provisions of specif* cation 3.0.3 are not applicable.
3.8.14 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool.. The provisions of specification 3.0.3 are not applicable.
9505240230 950519 PDR ADOCK 05000313 P
PDR Amendment No. M,M,M,H,M, Mt 59
repiccomer.t. The'keff with c11 rods in the c:ro cnd with rsfuS11ng boren
_ concentration is approximately 0.9.-
specification 3.8.5 allows the control room operator to inform the reactor building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.
The specification requiring testing reactor building purge termination is-to verify that these components will function as required should a fuel i
handling accident occur which resulted in the release of significant fission products.
1 1
)
Because of physical dimensions of the fuel bridges, it is physically impossible for fuel assemblies te be within 10 feet of each other while being handled.
Per specification 3.8.6, the reactor building personnel and/or emergency airlock doors may be open during movement of irradiated' fuel in the reactor building provided at least one door is capable of being closed in the event of a fuel, handling accident and the plant is in REFUELING SHUTDOWN with 23 feet of water i
above the fuel' seated within the reactor pressure vessel.
should a fuel handling accident occur inside the reactor building, at least one of the personnel and/or emergency airlock doors will be closed following evacuation of the reactor building.
specification 3.8.11 is required as:
- 1) the safety analysis for the fuel handling accident was based on the assumption that the reactor had been shutdown for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> (8); and, 2) to assure that the maximum design heat l
load of the spent fuel pool cooling system will not be exceeded during a full core offload.
specification 3.8.14 will assure that damage to fuel in the spent fuel pool I
will not be caused by dropping heavy objects onto the fuel. Administrative controls will prohibit the storage of fuel in locations adjoining the walls at the north and south ends of the pool, in the vicinity of cask storage area and fuel tilt pool access gates.
Specifications 3.8.15 and 3.8.16 assure fuel enrichment and fuel burnup limits assumed in the spent fuel safety analyses will not be exceeded.
Specification 3.6.17 assures the boron concentration in the spent fuel pool will remain within'the limits of the spent fuel pool accident and J
criticality analyses.
REFERENCES (1)
FSAR, Section 9.5 (2)
FSAR, Section 14.2.2.3 (3)
FSAR, section 14.2.2.3.3
)
Amendment No. H,W,M,4W 59b
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REFUELING OPERATIONS DECAY TIME AND SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.3.a The reactor shall be suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
l 3.9.3.b In the' event of a complete core offload, a full core to be discharged shall be suberitical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge of more than 70 assemblies to the spent fuel pool.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor suberitical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all operations
'l involving movement of irradiated fuel in the reactor pressure vessel. With the reactor suberitical for less than 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br />, suspend all operations involving movement of more than 70 fuel assemblies from the reactor pressure vessel to the spent fuel pool. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.3.a The reactor shall be determined to have been suberitical for at' least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of suberiticality prior l
to movement of irradiated fuel in the reactor pressure vessel.
4.9.3.b The reactor shall be determined to have been suberitical for at J
1 east 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> by verification of the date and time of suberiticality prior to movement of the 71st irradiated fuel assembly from the reactor pressure vessel to the spent fuel pool, ARKANSAS - UNIT 2 3/4 9-3 Amendment No. 44
-3
. REFUELING OPERATIONS CONTAIMMENT BUILDING PEMETRATIONS LIMITING CONDITION POR OPERATION I
3.9.4 The containment building penetrations shall be in the following status:-
a.
The equipment door closed and held in place by a minimum of four
- bolts,
-l b.-
A minimum of one door in each airlock is capable of being closed, and l
c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
closed by an isolation valve, blind flange, or manual valve, or 2.
-Exhausting through OPERABLE containment purge and exhaust system HEPA filters and charcoal adsorbers.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, inunediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are'not applicable.
SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be detet. ned_to be in its above required conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment.
4.9.4.2 The containment purge and exhaust system shall be demonstrated OPERABLE at the following frequencies:
a.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation sone comeunicating with the system by:
1 1
1 l
i ARKANSAS - UNIT 2 3/4 9-4 Amendment No.
u
3/4.9 EEFUELING OPERATIONS BASES 3/4.9.1 EORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: 1) the reactor.will remain suberitical during C07.5 ALTERATIONS, and
- 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures.
that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor cuberiticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the accident analyses.
The minimum requirement for reactor suberiticality prior to movement of more than.70 irradiated fuel assemblies to the spent fuel pool ensures that sufficient time has elapsed to allow radioactive decay of the short-lived fission products such that the heat generated will not exceed the cooling capacity of the spent fuel pool cooling system. This decay time and total assembly limitation is conservatively within the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY of the containment purge and exhaust system HEPA filters and charcoal adsorbers ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurisation potential while in the REFUELING MODE.
Operation of the containment purge and exhaust system HEPA filters and charcoal adsorbers and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
The containment personnel airlock doors may be open during movement of irradiated fuel in the containment and during CORE ALTERATIONS provided a minimum of one door is capable of being closed in the event of a fuel handling accident and the plant is in NODE 6 with 23 feet of water above the fuel seated within the reactor pressure vessel, should a fuel handling accident occur inside containment, a minimum of one personnel airlock door will be closed following an evacuation of containment.
ARKANSAS - UNIT 2 5 3/4 9-1 Amendment No. 44
1, REFUELING OPERATIONS BASES 3/4.9.9 and 3/4.9.10 MATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL MATER LEVEL The restrictions on minLaum water level ensure that sufficient water depth is available to remove 99% of the assumed 124 iodine gap activity l
released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM The limitations on the fuel handling area ventilation system ensure that all radioactive materials released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere. The operation of this system and the resulting lodine removal capacity are consistent with the assumptions of the accident analyses.
3/4.9.12 FUEL STORAfaK Region 1 of the spent fuel storage racks is designed to assure fuel assemblies of less than or equal to 4.1 w/o U-235 enrichment will be maintained in a suberitical array with K,gg 50.95 in unborated water.
These conditions have been verified by criticality analyses.
Region 2 of the spent fuel storage racks is designed to assure fuel assemblies within the burnup and initial enrichment limits of Figure 3.9.2 will be maintained in a subcritical array with K,gg 50.95 in unborated water. These conditions have been verified by criticality analyses.
The requirement for 1600 ppm boron concentration is to assure the fuel assemblies will be maintained in a suberitical array with K,gg 50.95 in the event of a postulated accident.
ARKANSAS - UNIT 2 B 3/4 9-3 Amendment No. 44
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e MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (FORINFO ONLY) j
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3.8.6 DurAng the hindling cf irrcdicted fu 1 in the r cct:r building, ct 10cct onedooronthepersonnelandemergencyhatchesshallbecapableofbeinal
}
l closed. The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces.
At least 23 feet l
of water shall be maintained over the too of irradiated fuel assemblies seated within the reactor crossure vessel.
3.8.7 Isolation valves in lines containing automatic containment j
isolation valves shall.be operable, or at least one shall be l
closed.
l l
3.8.8 When two irradiated fuel assemblies are being moved simultaneously by the bridges within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemblies at all times.
3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made. The provisions of specification 3.0.3 are not applicable.
3.8.10 The reactor building purge isolation system, including the radiation monitors shall be tested and verified to be operable within 7 days prior to refueling operations. The provisions of specification 3.0.3 are not applicable.
3.8.11 Irradiated fuel shall not be removed from the reactor until the unit has been suberitical for at least 49122 hours.
In the event of a l
complete core offload, a full core to be discharged shall be suberitical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge of more than 70 assemblies to the spent fuel pool. The provisions of specification 3.0.3 are not applicable.
3.8.12 All fuel handling in the Auxiliary Building shall cease upon notification of the issuance of a tornado watch for Pope, Yell, Johnson, or Logan counties in Arkansas. Fuel handling operations in progress will be completed to the extent necessary to place the fuel handling bridge and crane in their normal parked and locked position. The provisions of Specification 3.0.3 are not applicable.
1 3.8.13 No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmospheric dispersion conditions are equal to or better than those produced by Pasquill Type D stability accompanied by a wind velocity of 2 m/sec.
In addition, the railroad spur door of the Turbine Building shall be closed and the fuel handling area ventilation system shall be in operation. The provisions of Specification 3.0.3 are not i
applicable.
3.8.14 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool. The provisions of j
specification 3.0.3 are not applicable.
I Amendment No. M,H,M,H,M, Mk 59 l
1
repiccoment. Ths koff with all roda in ths coro and with refusling boron l
concentration is approximately O.9.
Specification 3.8.5 allows the control room operator to inform the reactor building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.
The specification requiring testing reactor building purge termination is to verify that these components will function as required should a fuel hanJ11ng accident occur which resulted in the release of significant fission products.
Because of physical dimensions of the fuel bridges, it is physically Lopossible for fuel assemblies to be within 10 feet of each other while being handled.
Per specification 3.8.6, the reactor buildina personnel and/or emercenev airlock doors may be ooen durino movement of irradiated fuel in the reactor buildino provided at least one door is capable of beino closed in the event of a fuel handlina accident and the olant is in REFUELING SHUTDOWN with 23 f eet of water above the fuel seated within the reactor pressure vessel.
Should a fuel handlina accident occur inside the reactor buildino, at least one of the oersonnel and/or emeroency airlock doors will be closed followina evacuation of the reactor buildina.
Specification 3.8.11 is required as:
- 1) the safety analysis for the fuel handling accident was based on the assumption that the reactor had been shutdown for 49122 hours (8); and, 2) to assure that the maximum design heat l
load of the spent fuel pool cooling system will not be exceeded during a full core offload.
Specification 3.8.14 will assure that damage to fuel in the spent fuel pool will not be caused by dropping heavy objects onto the fuel. Administrative controls will prohibit the storage of fuel in locations adjoining the walls at the north and south ends of the pool, in the vicinity of cask storage area and fuel tilt pool access gates.
Specifications 3.8.15 and 3.8.16 assure fuel enrichment and fuel burnup limits assumed in the spent fuel safety analyses will not be exceeded.
Specification 3.8.17 assures the boron concentration in the spent fuel pool will remain within the limits of the spent fuel pool accident and criticality analyses.
REFERENCES (1)
FSAR, Section 9.5 (2)
FSAR, Section 14.2.2.3 (3)
FSAR, Section 14.2.2.3.3 Amendment No. %,54,%,4%
59b 5
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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FORINFO ONLY)
y REFUELING OPERATIONS 3
DECAY TIME AND SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.3.a The reactor shall be subcritical for at least MM hours.
l
)
3.9.3.b In the event of a complete core offload, a full core to be discharged shall be subcritical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge 1
of more than 70 assemblies to the spent fuel pool.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor suberitical for less than M g hours, suspend all operations l
involving movement of irradiated fuel in the reactor pressure vessel. With the reactor suberitical for less than 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br />, suspend all operations involving movement of more than 70 fuel assemblies from the reactor pressure vessel to the spent fuel pool. The provisions of Specification 3.0.3 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.9.3.a The reactor shall be determined to have been suberitical for at least M g hours by verification of the date and time of subcriticality prior l
to movement of irradiated fuel in the reactor pressure vessel.
4.9.3.b The reactor shall be determined to have been suberitical for at least 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> by verification of the date and time of suberiticality prior to movement of the 71st irradiated fuel assembly from the reactor pressure vessel to the spent fuel pool.
ARKANSAS - UNIT 2 3/4 9-3 Amendment No. M
1 REFUELING OPERATIONS
. c.,
CONTAIMMENT BUILDING PENETRATIONS LIMITING CONDITION POR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four boltog l-b.
A minimum of one door in each airlock is canable of beina closed, and l
c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve,-
or 2.
Exhausting through OPERABLE containment purge and exhaust system HEPA filters and charcoal adsorbers.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
Mith the requirements of the above specification not satisfied, immediately suspend all operations involving OORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.
l l
SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be I
determined to be in its above required conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or' movement of irradiated fuel in the containment.
4.9.4.2 The containment purge and exhaust system shall be demonstrated l
OPERABLE at the following frequencies:
1 a.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
1 l
1 ARKANSAS - UNIT 2 3/4 9-4 Amendment No.
I
3/4.9 REFUELING OPERATIONS RASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity. conditions during REFUELING ensure that: 1) the reactor will remain suberitical during OORE ALTERATIONG, and
- 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
3/4.9.2 IMsTRUMENTATION The OPERA 5'!LITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME 4
The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the 4
assumptions used in the accident analyses.
The minimum requirement for reactor suberiticality prior to movement of more than 70 irradiated fuel assemblies to the spent fuel pool ensures that sufficient time has elapsed to allow radioactive decay of the short-lived fission products such that the heat generated will not exceed the cooling capacity of the j
spent fuel pool cooling system. This decay tLee and total j
assembly limitation is conservatively within the assumptions used in the accident analyses.
l 3/4.9.4 CONTAINMENT PENETRATIONS I
The requirements on containment penetration closure and OPERABILITY of the containment purge and exhaust system REPA filters and charcoal adsorbers ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere.
The OPERABILITY and closure restrictions are sufficient to restrict
-radioactive material release from a fuel element rupture based upon the lack of containment pressurisation potential while in the REFUELING MODE.
Operation of the containment purge and exhaust system HEPA filters and charcoal adsorbers and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
The containment personnel airlock doors may be open durina movement of irradiated fuel in the containment and durina CORE ALTERATIONS nrovided a minimum of one door is canable of beino closed in the event of a fuel handlina accident and the clant is in MODE 6 with 23 feet of water above the fuel seated within the reactor Dressure vessel.
Should a fuel handlina accident occur inside containment. a minimum of one oorsonnel airlock door will be closed followina an evacuation of containment.
l s
j ARKANSAS - UNIT 2 B 3/4 9-1 Amendment No. 44
1 REFUELING OPERATIONS BASES 3/4.9.9 und 3/4.9.10 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 1924 iodine gap activity l
released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM The limitations on the fuel handling area ventilation system ensure that all radioactive materials released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere. The operation of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
3/4.9.12 FUEL STORAGE Region 1 of the spent fuel storage racks is designed to assure fuel assemblies of less than or equal to 4.1 w/o U-235 enrichment will be maintained in a subcritical array with K,gg 50.95 in unborated water.
These conditions have been verified by criticality analyses.
Region 2 of the spent fuel storage racks is designed to assure fuel assemblies within the burnup and initial enrichment limits of Figure 3.9.2 will be maintained in a suberitical array with K,gg 50.95 in unborated water. These conditions have been verified by criticality analyses.
The requirement for 1600 ppm boron concentration is to assure the fuel assemblies will be maintained in a suberitical array with K,gg 50.95 in the event of a postulated accident.
ARKANSAS - UNIT 2 B 3/4 9-3 Amendment No. +&
5
_. _ _ _ _ _ _ _ _ - _