ML19339B891

Proposed Tech Spec 3.1 Re Reactor Coolant Sys

ML19339B891
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/31/1980
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19339B887	List: ML19339B886 ML19339B891
References
NUDOCS 8011100382
Download: ML19339B891 (13)

Text

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3. LIMITING CONDITIONS FOR OPERATION l .

3.1 REACTOR COOLANT. SYSTEM j-Applicability f Applies to the operating status of the reactor coolant system.

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Objective

. To specify those ' limiting conditions for operation of the reactor coolant system which must be met to ensure safe reactor operations, lt

} '3.1.1 Operational Components i

Specification 3.1.1.1 Reactor Coolant Pumps A. Pump combinations permissible for given power levels

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shall be as shown in Table 2.3-1.

f B. The boron concentration in the reactor coolant system i

shall not be reduced unless at least one reactor coolant pump or one decay heat removal pump is circulating reactor i coolant.

1 3.1.1.2 Steam Generator i

, A. Two steam generators shall be operable whenever the

, reactor -coolant average temperature is above 280 F.

, 3.1.1.3 Pressurizer Safety Valves

A. The reactor shall not remain critical unless both pres-j surizer code safety valves are operable.

i i B. When the reactor is suberitical, at least one pres-surizer code safety valve shall be operable if all.re-actor coolant system openings are closed, except for

hydrostatic tests in accordance with ASME Boiler and j Fressure Vessel Code,Section III.

3.1.1.4 Reactor Internals Vent Valves i

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The structural integrity and operability of the reactor in-ternals vent valves shall be maintained at a level consistent with the acceptance criteria in Specification 4.1.  ;

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3.1.1.5 Reactor Coolant Loops

A. Wi*h the reactor coolant average temperature above 280*F, she reactor coolant loops listed below shall be operable:

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1. Reactor Coolant Loop (A) and at least one associated

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reactor coolant pump.

. 2. Reactor Coolant Loop (B) and at least one associated reactor coolant pump.

Othe rwise , restore the required loops to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or reduced the reactor coolant average

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temperature to less than or equal to 280 F within the next

, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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B. With the reactor coolant average temperature above 280 F, at least one of the reactor coolant loops listed above

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shall be in operation.

3.1.1.6 Decay Heat Removal With the reactor coolant average temperature at or below 280 F, but the reactor above the refueling shutdown condition, at least two of the coolant loops listed below shall be oper-able, and at least one loop shall be in operation:*

1. Reactor Coolant Loop'(A) and its associated steam gen-

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erator and at least one associated reactor coolant pump.

2. Reactor Coolant Loop (B) and its 3ssociated steam gen--

erator and at least one associated reactor coolant pump.

3. . Decay Heat Removal Loop (A)**

4. Decay Heat Removal Loop (B)**

A. With less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant-loops to OPERABLE status.as soon as possible; be in COLD SHUTr3WN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

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B. With no coolant loop in operation, suspend all operations

involving a reduction in boron concentration of the Reactor i Coolant System and immediately initiate corrective action to return the required coolant loop to operation. ,

3 *All reactor coolant pumps and- decay heat removal pumps may be de-ener-

gized for up to I hour provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration,

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and (2) core outlet temperature is maintained at least 10 F below sat-uration temperature.

• • The normal or emergency power source may be inoperable when the re-actor is in a cold shutdown condition.

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BASES:

The plant-is designed to operate with both reactor coolant loops and at least one reactor coolant pump per loop in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.

Whenever the reactor coolant average temperature is above 280*F, single

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failure considerations require that two loops be operable.

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The decay heat removal system suction' piping is designed for 300*F,

. thus, the system can remove decay heat when the reactor coolant system is below this temperature. (2,3)

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.One pressurizer code safety valve is capable of preventing overpres-

surization i en the reactor is not critical since its relieving capacity is greater than that required by the sum of the available heat sour

which are pump energy, pressurizer heaters, and reactor decay heat.{gg Both pressurizer code safety valves are required to be in service

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prior to criticality to. conform.to the system design relief capabili-d ties. The {gge safety valves prevent overpressure for a . rod withdrawal

accident. The pressurizer code safety. valve lift set point.shall be set at 2,500 psig 1 1 percent allowance for error and each valve shall j be capable of relieving 300,000 lb/h of saturated steam at a pressure j not greater than 3 percent above the se,t pressure.

REFERENCES 1

l (1) FSAR, Tables 9-10 and 4-3 through 4-7 (2) FSAR, Section 4.2.5.1 and 9.5.2.3

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(3) FSAR, Section 4.2.5.4 4

(4) FSAR, Section 4.3.10.4 and 4.2.4 (5) FSAR, Section 4.3.7 i

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i 3.8.3.4. At least one decay heat removal loop shall be in operation.*

Otherwise, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration

of the reactor coolant system, and close all containment

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penetrations providing access from the containment atmosphere

to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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b. When the water level above the top of the irradiated fuel 1 assemblies seated within the reactor pressure vessel is less than 23 feet, two decay heat removal loops shall be oper-

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• The decay heat removal loop may be removed from operation for up to 1 bour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of core alterations.

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• • The normal or emergency power source may be inoperable for each shut-down cooling loop.

BASES:

1 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 9.7 of the rSAR incorporating built-in interlocks and safety features, provide assurance ,

that no incident could occur.during the refueling operations that would

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. result in a hazard to public health and safety. If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition.

The requirement that at least one decay heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor prescure vessel at the refueling temperature (normally 140 F), and (2) suffisient coolant

circulation is maintained through the reactor core to minimize the

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effec tron.{g)ofaborondilutionincidentandpreventboronstratifica-

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The requirement to have two decay heat removal loops operable 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 heat removal capability. With

the reactor vessel head removed and 23 feet of water above the core,-

, a large heat sink is available for core cooling, thus in the event of

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a failure of the operating decay heat removal loop, adequate time is l provided to initiate emergency procedures to cool the core.

l TheshutdownmarginindicatedinSpecification3.8.4willkeeptgg) core subcritical, even with all control rods withdrawn from the core. The

boron concentration will be maintained above 1,800 ppm. Although this l concentration is sufficient to maintain the core k eff

$10.99 if all the i_ control rods were removed from the core, only a few control rods will-be

, removed at any one time during fuel shuffling and replacement. The k eff

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with all rods in the core and with refueling boron concentration is approximately 0.9. Specification 3.8.5 allows the control room operator to inform the reactor building personnel of any impending unsafe condi-tion detected from the main control board indicators during fuel move-ment.

On a one time basis during Cycle 3 operation a 25 ton NAC-1 cask shall be allowed to be carried by the auxiliary building crane for the purpose of removing the fuel storage pool irradiated B C test rods.

4 The cask handling shall be in accordance with restriction set forth in AP&L

. letter dated September 25, 1978.

The specification requiring testing reactor building purge termination is to verify that these components will function as required should a fuel handling accident occur which resulted in the release of signifi-cant fission products.

Because of physical dimensions of the fuel bridges, it is physically impossible for fuel assemblies to be within 10 feet of each other while being handled.

Specification 3.8.11 is required as the safety analysis for the fuel handlingaccidentwasg3sedontheassumptionthatthereactorhadbeen shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Specification 3.8.14, which requires cooling of the full core for 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge to the spent fuel pool when seven relcad batches are already stored in the pool, is necessary to assure that the maximum design heat load of the spent fuel pool cooling system will not be exceeded.

Specification 3.8.15 will assure that damage to fuel in the spent fuel pool will not be caused by dropping heavy objects onto the fuel. Ad-ministrative 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, until the review specified in 3.8.16 is completed.

Specification 3.8.16 assures that the spent fuel cask drop accident cannot occur prior to completion of the NRC staff's review of this potential accident and the completion of any modifications that may be necessary to preclude the accident or mitigate the consequences. Upon satisfactory completion of the NRC's review, Specification 3.8.16 shall be deleted.

REFERENCES (1) FSAR, Section 9.5 (2) FSAR, Section 14.2.2.3 (3) FSAR, Section 14.2.2.3.3 i

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SURVEILLANCE:

4.26 Decay Heat Removal APPLICABILITY:

Applies to surveillance of the decay heat removal system and to the reactor coolant loops and associated reactor coolant pumps as needed for decay heat removal.

. OBJECTIVE To assure the operability of the decay heat removal system and the reactor coolant loops as needed for decay heat removal.

SPECIFICATION 4.26.1 The required reactor coolant pumps shall be determined oper-able once per seven (7) days by verifying correct breaker alignments and indicated power availability.

4.26.2 The required decay heat removal loop (s) shall be determined operable per Specification 4.2.2.

4.26.3 The required steam generator (s) shall be determined operable by verifying the secondary side water level to be ]t 20 inches on the startup range at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.26.4 The required reactor coolant loop (s) shall be determined operable by verifying the required loop (s) to be in operation and circulating reactor coolant at least once per 12 hous .

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3/4.4 REACTOR COOLANT SYSTEM

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3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.

APPLICABILITY: I and 2.*

ACTION:

With less than the above required reactor coolant pumps in operation, be in at least HOT STANDBY within I hour.

SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• See Special Test Exception 3.10.3.

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REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a. The reactor coolant loops iisted below shall be operable:

1. Reactor Coolant Loop (A) and at least one associated reactor coolant pump.

2. Reactor Coolant Loop (B) and at least one associated reactor coolant pump.

b. At least one of the above Reactor Coolant Loops shall be in operation.*

APPLICABILITY: MODE 3 ACTION:

a. With less than the above required reactor coolant loops operable, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SKUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. With no r_ actor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required loop to opera-tion.

SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• All reactor-coolant pumps may be de-energized for up to I hour provided (1) no operations are permitted that would cause dilution of the reactor

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coolant system boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.

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REACTOR' COOLANT SYSTEM SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two f the coolant loops listed below shall be OPERABLE:

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1. Reactor Coolant Loop (A) and its associated steam generator and at least one associated reactor _ coolant pump.

2. Reactor Coo? ant Loop (B) and its associated steam t

generator and at least one associated reactor coolant pump.

3. Shutdown Cooling Loop (A)#

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4. Shutdown Cooling Loop (B)#

b. At least one of the above coolant loops shall be in

operation.*

APPLICABILITY

Modes 4 and 5 ACTION:

a. With less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant loops to OPERABLE status as soon as possible; be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

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b. With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

I SURVEILLANCE REQUIREMENTS ~

4.4.1.3.1 The required shutdown cooling loop (s) shall be determined

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OPERABLE per Specification 4.0.5.

4.4.1.3.2 The required reactor coolant pump (s), if not_in operation,

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I shall be determined to be-OPERABLE once per 7 days by verifying

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correct breaker alignments and indicated power availability.

^All reactor coolant pumps and decay heat removal pumps may be de-energized

for up to I hour provided (1) no ~ operations are permitted that would

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cause dilution of-the reactor coolant system boron concentration, and (2).

core outlet temperature is maintained at least 10 F below saturation temperature.

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1. The normal or emergency power source may be inoperable in Mode 5.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by

-verifying the secondary side water level to be 1 23% indicated level at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.4 At least one coolant loop shall be verified to be in operation and circulating reactor coolant 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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REFUELING OPERATIONS

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3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE.*

APPLICABILITY: MODE 6 when the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet.

ACTION:

a. With less than the required shutdown cooling loops OPERABLE, immediately initiate corrective action to return the loops to OPERABLE status as soon as possible.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 The required shutdown cooling loops shall be determined OPERABLE per Specification 4.0.5.

• The normal or emergency power source may be inoperable for each shutdown cooling loop.

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4 3/4.4 REACTOR COOLANT SYSTEM

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BASES 3/4.4.1 REACTOR C00LAYT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

In MODES 4 and 5, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires two shutdown cooling loops to be OPERABLE.

The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reducti Ts will, thereJ,re, be within the capability of operator recognition and control.

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REFUELING OPERATIONS

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BASES 3/4.9.8 COOLANT CIRCULA^ ION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below

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140*F as required during the REFUELING MobE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown ecoling loops OPERABLE when there is less than 23 feet of water above the core, ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss 4

of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.

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