ML20099C850
| ML20099C850 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/30/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099C853 | List: |
| References | |
| NUDOCS 9208040334 | |
| Download: ML20099C850 (13) | |
Text
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0 PASES_(continued) restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits.
If these Actions are not completed within the allowable ot'tage time limits, a shutdown is required to place the facility in a mode or condition in which the Specification no longer applies.
It is not intended that the shutdown Action requiremen'.s be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from service in lieu of cther alternatives that would not result fn redundant systems or components being inoperable.
The specified time limits of the Action requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.
The time limits of the Action requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems.
Individual Specifications may incia.le a specified time limit for the complction of a Surveillance Requirement when equipment is removed from service.
In this case, the allowable outage tiene limits of the Action requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with Action requirements, the plant may have entered a modo in which a new specification becomes applicable.
In this case, the timo limits of the Action requirements would apply from the point in time that the new specification becomes applicable if the iequirements of the Limitirg Condition for Operation are not met.
3.0.2 Establishes that noncompliance with a Specification exists when the requirements of the Limit ing Condition for Operation are not met and the associated Action requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implernentation of the Action requirements within the specified time interval constitutes compliance with a Specification and (2) completion of the remedial measures of the Action requirements is not required when compliance with a Limiting Condition for Operation is restored within the time int erva l specified in the associated Action requirements.
3.0.3 Establishes the shutdown Action requirements that must be implamented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated Action requuements. The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown mode when plant operation cannot be maintained within the lirits l
for sofe operation defined by the Limiting Conditions for Operation and its Act ion requirements.
It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems c,r components from service in lieu of other alternatives that would not resul: in redundant systems or componnnts being inoperable.
One hour in allowed te prepare for an orderly shutdown before initiating a change in plant operation.
This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.
The time limits specified to reach lower modes of operation permit the shutdown to proceed in a controlled and orderly Amendment No.161 15b-1 9208040334 920730 PDR ADOCK 05000313-p PDR
BASES Rott t d) manner th *t is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE.
This reduces thermal stresses on components of the primary coolant systems and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.
If remedial measures permitting limited continued operation of the facility under the provisions of the Action requirements are completed, the shutdown may be terminated.
The time limits of the Action requirements are applicabic from the point in time there was a f ailure to meet a 1.f miting Condition for Operation.
Therefore, the shutdown may be terminated if the Action requirements have been met or the time limits of the Action requirements have not expired, thus providing an allowance for the completion of the required Actions.
The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in
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the C0hD SIIUTDOWN condition when a shutdown is required during the POWER mode of operation.
If the plant is in a lower mode of operation when a shutdown is required, the time liailt for reaching the next lower mode of operat.on j
applies.
Ilowever, if a lower mode cf operatfore is reach 6A in less time than allowed, the total allovable time to reach CO
SIIUTDOWN, or other applicable mode, is not reduced. For example, if Il0T S'1 ANDDY is t eached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SlIUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time 3
I to reach Il0T SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
I Therefore, if rernedial measures are completed that would permit a return to p0WER operation, a penalty is not incurred by having to reach a lower mode of l
operation in sess than the total t ime allowed.
l The same principle applies with negard to toe allowable outage tirne limits of th; Action requirements, if cornpliance with t he Action r equirements for one i
specification results in entry into a mode or condf Lion of operation for l
another specification in which the requir emen ts of t he himit ing Condit f or, for Operation are not met.
If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage tima l
limits of the second specification.
However, the a llowabic outage time limits j
of Action requirements for a higher inode of operation mny not he used to extend tbo allowable outage time that is applicable when a Limiting Condition l
for Operation is not met in a lower mode of operation.
I The shutdown requirements of Specification 3.0.3 do not apply in COLD SHUTDOWN and KEFULLING SilUTDOWN, because the Action requirements of individual specifications define the remedial measures to be taken.
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3.0.4 Establishes limitations on modo changes when a Limit ing Condit ion for operation is not met.
it precludes placing the facility in a higher mode of operation when the requirements for a Limiting Condition for Operation are not j
met and continued noncompliance to these conditions would result in a shutoown to coinply with t he Action requirements if a change in modes were permitted.
4 The purpose of this specification is to ensure that facility operation is not j
l Amendment No. 161 15b-2
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j initiated or that higher modes of operation are not cetered when corrutive action is being taken to obtain compliance with a Specification by restoring equipment to OPERABbt status or parameters to specified limits. Compliance with Action requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a mode change. Therefore, in this case, if the requirements for continued i
operation have been met in accordance with the requiremont of the specification, then entry into that mode of operation is permissible. The provisions of this specification should not, however, be interpreted as endorsing the failure to exerciso good practice in restoring systems or a
components to OPERABLE status before plant startup.
When a shutdown is required to comply with Action requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower mode of operation.
For the purpose of compliance with this specification the term ' shutdown' is defined as a required reduction in the REACTOR OPERATING CONDITION.
3.0.5 Delineates what additional conditions must be satisfied to permit operation to continue when a normal or emergency power source is not OPERABLE.
It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.
The provisions of t his speci ficat ion permit the Limiting Condition for Operation staternen's essociated with individual systems, subsystems, trains, component s or devices to be consistent with the Limiting Condition for Oper at ion statemerit s of the associated electrical power soulce.
It allows operation to be governed by the time limits of the Limiting Condition for Operation for the normal or emergency power source, not the individual Limiting Condition for Operati, statements for each system, r,u bsy s t e m, train, component or device that is detarmined to bn inoperable solely because of the inoperability of its normal or einergency power source.
For example, Specification 3.7.2.C provides for 6 2 day out-of-service time when one emergency diesel generator is not OPERABLE.
If the definition of OPERABLE were applied without consideration of 3pecification 3.0.5, all systems, subsystems, trafos, components cnd devices supplied by the inoperable emergency power source would alt-be inoperable.
This would dictate invoking the applicable Act ion statements for each of the applicable 1.imit ing Condit ions for Operation.
However, the provisions of Speci ficat ion 3.0. 5 permit the time limits for continued operation to Ameadment No.161
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be con.istent with the ' Limiting Condition for Operation statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.
In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components and devices must be OPERABLE, or otherwise satisfy Specificatien 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE).
If they are not satisfied, shutdown is required.in 7
accordance with this specification.
As a further er. ample, Specification 3.7.1.A requires in part that two physically independent circuits between the offsitt transmission network and the onsite Class AE distribution system be OPERABLE.
Specification 3.7.2.8 provides a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> out-of-service time when both required offsite circuits are not OPERABLE.
If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits would also be inoperable.
This would dictate invoking the applicable Limiting Condition for Operation statements for each of the applicable LCOs.
However, the provisions of-Specification 3.0.5 permit the time limits-for continued operation to be consisteht with the Limiting condition for Operation statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied.
In this case, this would mean that for one division the emergency power source must be OPERABLE (vi must be the components supplied by ths emergency power source).and all redundant systems, subsystems, trains, components and devices in the other divi-sion must be OPERABLE, or likewise: satisfy Specification 3.0.5 (i.e.,
be capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, compo-nents and devices in both divisions must also be OPERABLE.
If these conditions are not satisfied, shutdown is required in accordance with this specification.
During Cold Shutdown and Refuelin Shutdown, Specification 3.0.5 is not applicable and thus the individua Action statements for each applicable Limiting Condition for-Operation in these MODES must--be adhered to.
Amendment No. 57 15c
4 3.1.2 hfgAnt,iullpn. licA(upand Cooldoutlinitat long SpecificallDD 3.1.2.1 Ilydro Tests i.
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For thermal steady state system hydro tests, the system may be j
pressurized to the limits act forth in Specification 2.2 when there 1
are fuel assemblics in the core, under the provisions of 3.1.2.3, and to ASME Code limits when no fuel essemblies are present provided the reactoc coolant system limits are to the right of and below the limit line in Figure 3.1.2-1.
The provisions of Specifications 3.0.3 l
are not applicable.
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3.1.2.2 Leak Tests
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Leak tests required by Specification 4.' shall be conducted under i
the provision of 3.1.2.3.
The provisions of Specification 3.0.3 are j
not applicable.
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3.1.2.3 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Tigure 3.1.2-2 and Figure 3.1.2-3, and are as follows:
i llea t up:
Allowable combinations of pressure and temperature shall be to the right of and below the limit line in Figure 3.1.2-2.
The heatup j
rate 5 shall not exceed those shown in Fi;;ur e 3.1.2-2.
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Cooldown:
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Allowable combinations of pressure and temperature for a specific cooldown shall be to the right of and below the limit line in Figure 3.1.2-3.
Cooldown rates shall not exceed those shown in Figure
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3.1.2-3.
3.1.2.4 The secondary side of the steam genrrator shall not bc
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pressurized above 200 psig if the temperature of the steam generator shell is below 100F.
3.1.2.5 The pressurizer heatup and cooldown rates shall net l
exceed 100F/hr.
The spray shall not be used if the temperature dif ference bet ween the pressurizer and the spray fluid is greater j
than 430F.
3.1.2.6 With the limits of Specifications. 3.1.2.3 or 3.1.2.4 or 3.1.2.5 exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the ef fects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least 110T STANDBY within the next.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS Tavg to less than l
200F, while maintaining PCS temperature and pressure below the curve, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Amendment No. //, 16. E/, JE A,161 18 l
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1 3.1.2.7 prior to reaching fifteen effective full power years of operation, Figures 3.1.2-1, 3.1.2-2 and 3.1.2-3 shall be updated for the next service period in accordance with 10CFR50, Appendix G.Section V.B.
The service perkd chall be of sufficient duration to permit the scheduled evaluation of a portion of the surveillance data scheduled in accordance with the latest revision of Topical Report BAW-1543(5). The highest predicted adjusted reference temperature of all the beltline l
region materials shall be used to determine the adjusted reference temperature at the end of the service period.
The basis for this prediction shall be submitted for NRC staff review in accordance with Specification 3.1.2.8.
The provisions of Specificat f or; 3.0.3 are not applicable.
3.1.2.8 The updated proposed technical specifications referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to the end of the service period.
Appropriate additional NRC review time shall be allowed for proposed technical specifications submitted in accordance with 10 CFR part 50, Appendix G.Section V.C.
3.1.2.9 With the exception of ASME Section XI testing and when the core flood tank is depressurized, during a plant cooldown the core flood tank discharge valves shall be closed and the circuit breakers for the motor operators opened before depressurizing the reactor coolant system below 600 psig.
3.1.2.10 With the exception of ASME Section XI testing, fill and vent on' the reactor coolant eyrtam. emergency RCS makeup and to allow maintenance of the valves, when the reactor coolant temperature is less than 300 F, the High Pressure lujection motor operated valves shall be closed with their opening control circuits for the motor operators diaablad.
3.1.2.11 The plant shall not be operated in a water solid condition when the RCS pressure boundary is intact except as allowed by Emergency Operating procedures and during System Hydrotest.
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i Amendment No. 57, fA, 97, J/f., J40, 16a ARKANSAS - UNIT 1 JEA, 161
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I 3.5.5 fire Detection Instrustniat.ing DELETED
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1 Amendmeist No. /R, pf, 57, JJE,158 53d
3.8.15* The spent fuel shipping cask shall not be carried by the Auxiliary t
Building crano pending the evaluation of the spent fuel cask drop accident and the crane design by Ap&b and NRC review and approval.
The provisions of Specification 3.0.3 are not applicable.
l 3.8.16 Storage in the spent fuel pool shall be restricted to fuel assemblies
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i having initial enrichment less than or equal to 4.1 w/o U-235.
The provisions of Specification 3.0.3 are not applicable.
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3.6.17 Storage in Region 2 (as shown on Figure 3.8.1) of the spent fuel pool
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shall be further rest ricted by burnup and enrichment limits spec.fied in-Figure 3.8.2.
In the event a checkerboard storage configuration is l
deemed necessary for a portion of ReE on 2, vacant spaces adjacent to 1
the faces of any fuel assembly which does not meet the Region 2 burnup J
criteria (non-restricted) shall be physically blocked before any such j
fuel assembly may be placed in Region 2.
This will prevent inadvertent 1
fuel assembly insertion into two adjacent storage locations.
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provis ons of Specification 3.0.3 are not applicable.
f 3.8.18 The boron concentration in the spent fuel pool shall be maintained (at L
all times) at greater than 1600 parts per million.
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j Detailed written procedures will be available for use by refueling personnel.
These procedures, the above specifications, and the design of the fuel handling equipment as described in Section 9.6 of the FSAR incorporating built-in interlocks and safety features, provide assurance that no incident could occur i
during the refueling operations that would result in a hazard to public health I
and safety.
If no change is being made in core geomet ry, one flux monitor is i
sufficient. This perrnits maintenance on the ins t rument at.f on.
Continuous monitoring of radiation levels and neutron flux providos immediato indict Jon of g
an unsa fe condition.
I The requirement that at least one decay heat removal loop he in operation l
ensures that (1) sufficient cooling capacity is available to remwe decay hen and maintain the water in the reactor pressure vessel at the refueling temperature (normally 140*F). and (2) sufficient coolant = circulation is maintained through t he reac+ or core to minimize t he effects of a bar on d ilut ion l
incident and prevent boron st rati fication.(')
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The requirement to have two decay heat removal loops operoole when there is less than 23 feet of water above the core, ensures that a single failure of the operating decay heat removal loop will not result in a complete loss of decay i
heat remova l capabilit y.
With the reactor vessel head removed and 23 feet of l
water above the core,-a large heat sink is available for core cooling. thus in l
the event of a failure of t he operating decay heat removal loop,- adequat e t ime is provided to initiate emergency procedures to cool the core.
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The shutdown margin indicated in Specification 3.8.4 will keep the core subcritical, even with all control rods withdrawn from the core.( 8 ) Although the refueling boron concentration is sufficient to maintain the core k 5 0.99 if all the control rods were removed from the core, only a few control N s will be removed at any one time curing fuel shuffling and Note:
- An exception to 3.8.15 is granted for the period of October-15, 1991, through January 31, 1992, for the movement of two spent fuel rods utilizing a 17 ton shipping cask.
Amendment No. J/, EE, J/, 16,./p/,
59a 113, 161
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3.18 FIRE SUPPRESSION SPRINKLER SYSTEM DELETED i
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l Amendment No.19, f), y, JJr., 158 66n i
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i 3.19 CONTROL ROOM AND AUXJL~ARY CONTROL E00H llALON SYSTEMS 1
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4 Amendment'No. pp, 57, JJE, 158 66o
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3,20 FIRE HOSE STATIONS t
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3.21-FIRE BARRIERS f
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Amendment-No. Ef, 57, 127, 158 66q
Tablo 4.1-1 (Cont.)
Channni Des c r int _ i on Check Tpst Calibrate Remarks
- 30. Decay heat removal S(1)(2)
M(1)(3) R (1)
Includes RCS Pressure Analog Channel system isolation valve (2)
Includes CFT Isolation Val'.e Position automatic closure and (3) At least once every refueling shutdown, interlock system with Reactor Coolant System Pressure greater than or equal to 200 psig, but less than 300 psig, verify automatic isolation of the decay heat removal system from the Reactor Coulant System on high Reactor Coolant System pressure.
- 31. Turbine overspeedtrip NA k
NA (1) The provisions of Specification 4.C.4 mechanism are not appli able.
- 32. Diesel generator M
Q NA protective relaying starting interlocks and circuitry
- 33. Off-site power undervoltage K
R(1, R(1)
(1) Shall be tested during refveling and protective relaying shutdown to demonstrate selective interlocks and circuitry load shedding interlocks function during manual or automatic trans-fer of Unit 1 auxiliary load to Startup Transformer No. 2.
34 Borated Water sto-age W
NA R
tank level indicator
- 35. Reactor trip upon loss M
PC R
of main feedwater circuitry Amendment No.
4, 19. 30. (f. 67, 92, 132, 161 72
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