ML20076G367
| ML20076G367 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/31/1983 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20076G365 | List: |
| References | |
| NUDOCS 8306140643 | |
| Download: ML20076G367 (15) | |
Text
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 One charging pump in the boron injection flow path required by Specification (3.1.2.1) or Low Head Safety Injection Pump (with an open reactor coolant system vent of greater than or equal to 3.14 square inches) shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
APPLICABILITY: MODES 5 and 6 ACTION:
With no charging pump or Low Head Safety injection pump OPERABLE, suspend l all operations involving CORE ALTERNATIONS or positive reactivity changes until one charging pump or Low Head Safety Injection pump is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE at least once per 31 days by:
- a. Starting (unless already operating) the pump from the control room,
- b. Verifying, that on recirculation flow, the pump develops a discharge pressure of 2 2402 psig when tested pursuant to Specification 4.0.5, and
- c. Verifying pump operation for at least 15 minutes.
4.1.2.3.2 All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control switches are placed in the PULL-TO-LOCK position and tagged.
4.1.2.3.3 in cases when the Low Head Safety Injection pump is used in lieu of a charging pump, the Low Haad Safety Injection pump shall be deronstrated operable by:
- b. Verification of an operable Low Head Fafety Injection
? ump pursuant to 4.5.2.2
- c. Verification of power available* to MOV-1SI-890C with the plug inserted in its control circuit and an operable low head safety injection flow path from the RWST to the reactor coolant system.
- Emergency backup power need not be available BEAVER VALLEY - UNIT 1 3/4 1-11 PROPOSED WORDING 8306140643 830531 PDR P ADOCK 05000334 PDR
REACTIVITY COMTROL SYSTEMS CHARGING PUMPS - OPERATING LD'ITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE APPLICAIILITY: MODES 1, 2, 3, and 4#
ACTION:
With only one charging pump OPERARLE, restore at least two charging pumps to OPERA 3LE 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 at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1% a k/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERA 3LE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> .
SURVEILLANCE REOUIRDiD IS 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE on a STAGGERED TEST EASIS by verifying, that on recirculation flow, each pu=p develops a discharge pressure of 22402 psig when tested pursuant to _
Specification 4.0.5.
4.1.2.4.2 All charging pumps, except the above required OPERABLE pump, shall be de=onstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is $275'F by verifying that the control switches are placed in the PULL-TO-LOCK position and tagged.
- A caximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the non isolated RCS cold legs is
$275'F.
BEAVER VALLEY - UNIT 1 3/4 1-12 PROPOSED WORDING i
, 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3 /4.1.1. 4 MODERATOR TEMPERATURE COEFFICIENT (MTC) (Continued) fuel cycle. The surveillance requirement for measurement of the MTC at the beginning and near the end of each fuel cycle is adequate to confinn the ?EC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3 /4.1.1. 5 MINIMl'M TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 541*F.
This limitation is required to ensure 1) the moderstor temperature coefficient is within its analyzed temperature range, 2) the pressurizer is capable of being in an OPERABLE status with a steam bubble, 3) the reactor pressure vessel is above its minimum NDTT temperature and 4) the protective instrumentation is within its normal operating range.
3 /4.1. 2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control
, is available during each mode of facility operation. The components required to perform this function include 1) borated water sources,
- 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps,
- 5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200*F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems ' inoperable. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
With the RCS average temperature less than 200*F, a Low Head Safety Injection pump may be used in lieu of the operable charg'ing pump with a -
minimum RCS vent of 3.14 square inches. This will permit charging pump component repair or corrective action and will ensure that negative reactivity control and makeup are available when the charging pumps are out-of-service.
The required volume of water in the refueling water storage tank for reactivity considerations while operating is 424,000 gallons. The associated technical specification limit on the refueling water storage tank has been established at 439,050 gallons to account for reactivity l considerations and the NPSH requirements of, the ECCS system.
The limitations for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 275'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
BEAVER VALLEY - UNIT 1 B 3/4 1-2 PROPOSED WORDING g,y 9 m.w,9.- - - > - ,
.- REACTOR COGLANT SYSTEM SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the coolant loops listed below shall be OPERABLE:
- 1. Reactor Coolant Loop (A) and its associated steam generator and reactor coolant pump, l
- 2. Reactor Coolant Loop (B) and its associated steam generator and reactor coolant pump, l
- 3. Reactor Coolant Loop (C) and its associated steam generator and reactor coolant pump. l
- 4. Residual Heat Removal Pump (A) and a heat exchanger,**
- 5. Residual Heat Removal Pump (B) and a second heat exchanger.**
- b. At least one of the above coolant loops shall be in operation.***
- c. At least one RCP shall be operated throughout a normal cool-down to 160*F to assure that the steam generator follows the RCS temperature.
APPLICABILITY: MODES 4 and 5 ACTION:
- a. With less than the above required loops OPERABLE, i= mediately initiate corrective action to return the required 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 />,
- b. With no coolant loop in operation, suspend all operation involving a reduction in boron concentration of the Reactor Coolant system and immediately Laitiate corrective action to return the required coolant loop to operation.
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- The normal or emergency power source may be inoperable in MODE 5.
- All reactor coolant pumps and Residual Heat Removal pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided: 1) no operations are per=1tted that would cause dilution of the reactor coolant system boron concentration and 2) core outlet temperature is maintained at least 10*F below saturation temperature.
BEAVER VALLEY - UNIT 1 3/4 4-2c PROPOSED WORDING
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i REACTOR COOLANT SYSTEM REACTOR COOLANT PUMP STARTUP LIMITING CONDITION FOR OPERATION F
3.4.1.6 A reactor coolant pump in a non isolated loop shall not be started
! with one or more of the non isolated RCS cold leg temperatures $275'F
- unless
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- 1. The pressurizer water volume is less than 1120 cubic feet, or
- 2. The secondary w.ater temperature
- of each steam generator is less than 50*F .above each of the RCS cold leg temperatures.
APPLICABILITY: MODES 4 and 5 q ACTION: ,
t With the pressurizer water volume greater than 1120 cubic feet or the i temperature of the steam generator in the loop associated with the '
i reactor coolant pump being started greater than 50' above the cold leg temperature of the other non isolated loops, suspend the start-up of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS:
4.4.1.6.1 The pressurizer water volume and the secondary water temperature of the non isolated steam generators shall be determined within ten minutes of starting a reactor coulant pump.
Temperature of the secondary is to be perified by direct measurement, or contact temperature readings'on the,steem ' generator secondary, .or blow-
- down piping af ter purging of stagnant ++,.wkter within the piping.
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- REACTOR COOLANT SYSTEM OVERPRESCURE PROTECTION SYSTEMS i LIMITING CDNDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:
i
- a. Two power operated relief valves (PORVs) with a lif t setting of $350 psig, or
- b. A reactor coolant system vent of 2 3.14 square inches. ,
APPLICABILITY: When the temperature of one or more of the non isolated RCS cold legs is (275'F.
ACTION:
- a. With one PORV inoperable, either restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the ECS through a 3.14 square inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status.
- b. With both PORV's inoperable, depressurize and vent the RCS through a 3.14 square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status.
- c. In the event either the PORVs or the RCS vent (s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient, and any corrective action necessary to prevent recurrence.
- d. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIRLNENT 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE BY:
1 BEAVER VALLEY - UNIT 1 3/4 4-27a PROPOSED WORDING l
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SURVEILIANCE REQUIRDIENTS (Continued)
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- a. Performance of a CHANNEL FUNCTIONAL TEST on the PORV actuatioa j channel, but excluding valve operation, within 31 days prior to t
entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereaf ter when the PORV is required OPERABLE.
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- b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months.
- c. Verifying the FORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.
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! d. Stroking the PORV within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> each time the plant enters Mode 5, unless tested within the preceding three conths.
, 4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once j per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- when the vent (s) is being used for overpressure protection.
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- Except when the vent pathway is provided with a valve which is locked, provided with remote position indication, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.
I BEAVER VALLEY - UNIT 1 3/4 4-27b PROPOSED WORDING l
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. BASES vessel inside radius are essentially identical, the ceasured transition shif t for a sample can be applied with confidence to the adjacent section of the reactor vessel. The heatup and cooldown curves =ust be recalculated when theo RT determined from the surveillance capsule is different fromthecalcu1NkddRT NDT r the equivalent capsule radiation exposure.
The pressure-temperature limit lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrostatic testing have been pro-vided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice leak and hydrostatic testing.
The number of reactor vessel irradiation surveillance speci= ens and the frequencies for re=oving and testing these specimens are provided in Table 4.4-3 to assure compliance with the requirements of Appendix H to 10 CFR Part 50.
The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurir.er is operated within the design criteria assumed for the fatigue analysis perfor=ed in accordance with the ASME Code requirements.
The OPERABILITY of two PORVs or an RCS vent opening of greater than 3.14 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are $275'F. Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the sec-ondary water temperature of the steam generator $50*F above the RCS cold leg temperature or (2) the start of a charging pump and its injection into a water solid RCS.
3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a
! (g) (6) (1) .
1 3/4.4.11 RELIEF VALVES The relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency power source to ensure the ability to seal this possible RCS leakage path.
BEAVER VALLEY - UNIT 1 B 3/4 4-10 PROPOSED WORDING l
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EERJESCY CORE COOLING SYSTEMS SI'RVEILLANCE REQUIREMENTS (Continued)
- b. At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> af ter each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution.
- c. At least once per 31 days when the RCS pressure is above 2000 psig be verifying that power to the isolation valve oparator control circuit is disconnected by removal of the plug in the lock out jack from the circuit.
- d. Verifying at least once per 18 months that each accumulator isolation valve opens automatically under each of the following conditions:
- 1. When the RCS pressure exceeds 2000 psig.
- 2. Upon receipt of a Safety Injection test signal 4.5.1.2 Each accumulator water level and pressure alarm channel shall be demonstrated OPERAELE:
- a. At least once per 31 days by the performance of a CHANNEL FUNCTIONAL TEST.
- b. At least once per 18 months by the performance of a CHANNEL CALIBRATION.
4.5.1.3 During normal plant cooldown and depressurization, each accu-mulator discharge isolation valve [MOV-lSI-865A, B and C] shall be verified to be closed with control power removed within one hour following RCS pressure decrease to less than 1000 psig.
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l l BEAVER VALLEY - UNIT 1 3/4 5-2 PROPOSED WORDING
.. EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T ;
<350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a mini =um, one ECCS subsystem comprised of the following shall be OPERABLE:
- a. One OPERABLE centrifugal charging pump,# <
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- b. One OPERABLE Low Head Safety Injection Pump, and
- c. An OPERABLE flow path capable of taking suction from the refueling water storage tank upcn being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY: .TDE 4 ACTION:
- a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />,
- b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
SURVEILLANCE REOUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the appli-cable Surveillance Requirements of 4.5.2.
4.5.3.2 All charging pumps and Low Head Safety Injection Pumps, except the above required OPERABLE pumps, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the non isolated RCS cold legs is $275'F by verifying that the control switches are placed in the PULL-TO-LOCK position and tagged.
- A caximum of one centrifugal charging pump and one Low Head Safety Injection pump shall be OPERABLE whenever the temperature of one or more of the non isolated RCS cold legs is $275'F.
BEAVER VALLEY - UNIT 1 3/4 5-6 PROPOSED WORDING i 9 m --+ -, .- -mm - e-- - - .4---4
EMERGENCY CORE COOLING SYSTEMS 3 /4. 5. 4 EORON INJECTION SYSTEM BORON INJECTION TANK h 350*F l LIMITING CONDITION FOR OPERATION 3.5.4.1.1 The boron injection tank shall be OPERABLE with: l
- a. .. minimum contained volume of 900 gallons of borated water,
- b. Between 20,000 and 22,500 ppm of boron, and
- c. A minimum solution temperature of 145*F.
APPLICABILITY: MODES 1, 2, 3 ACTION:
With the boron injection tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to 1: Ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to OPERAELE status within the next 7 days or be in 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 />.
SURVEILLANCE REOUIREMENTS 4.5.4.1.1 The boron injection tank shall be demonstrated OPERABLE by: l
- a. Verifying the water level in the surge tank at least once per 7 days,
- b. Verifying the boron concentration of the water in the surge tank at least once per 7 days, and
- c. Verifying the water temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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BEAVER VALLEY - UNIT 1 3/4 5-7 Page A PROPOSED WORDING e - - - - -
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. DIERGENCY CORE COOLING SYSTEMS 3 /4.5.4 BORON INJECTION SYSTEM BORON INJECTION TANK 2 350*F l LIMITING CONDITION FOR OPERATION 3.5.4.1.1 The boron injection tank shall be OPERABLE with:
- a. A mini =um contained volume of 900 gallons of borated water,
+* b. Between 2,000 and 7,700 ppm of boron, and
- c. A minimum solution temperature of 65'F.
- 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> deviation is permitted to correct the out of specifica-tion condition.
+ To per=it adequate recirculation and sampling following actions taken to correct the baron concentration, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed for verification of the sanple results providing corrective action was taken within the first hour.
APPLICABILITY: MODES 1, 2, 3 ACTION:
With the boron injection tank inoperable, he in HOT STANDBY and borated to l a SHUTDOWN MARGIN equivalent to 1% Ak/k at 200*F within the next'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to OPERABLE status within the next 7 days or be in 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 />.
SURVEILLANCE REOUIREMENTS 4.5.4.1.1 The boron injection tank shall be demonstrated OPERABLE by: l
- a. Verifying the water level in the surge tank at least once per 7 days.
- b. Verifying the boron concentration of the water in the surge tank at least once per 7 days.
- c. Verifying the water temperature and recirculation flow at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- d. Verifying that the temperature of the heat traced portions of the BIT injection flow path is 265*F when the ambient air temperature of the Auxiliary Building is 665'F once per 7 days.
NOTE: This specification applicable for N & N-1 loop operation with all Loop stop valves open.
BEAVER VALLEY - UNIT 1 3/4 5-7 Page B PROPOSED WORDING
l 3 /4. 5 EKERGENCY CORE COOLING SYSTEMS (ECCS)
. BASES ,
3/4.5.1 ACCUMULATORS The OPERABILITY of each of the RCS accumulators ensures that a suffi-cient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
i The limits on accumulator volume, boron concentration and pressure l ensure that the assumptions used for accumulator injection in the accident l analysis are met.
The limit of one hour for operation with an inoperable accumulator j minimizes the time exposure of the plant to a LOCA event occurring con-current with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration. Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
, The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained.
The limitation for a maximum of one charging pump to be OPERABLE and the Surveillance Requirement to verify all charging puups except that required OPERABLE pump to be inoperable below 275'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single FORV.
3 /4.5.4 BORON INJECTION SYSTEM i
The OPERABILITY of the boron injection systen as part of the ECCS j
ensures that sufficient negative reactivity is injected into the core to ;
counteract any positive increase in reactivity caused by RCS system cool- 1 down. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.
The boron injection tank is required to be isolated when RCS temperature is less than 350*F to prevent an overpressurization due to an inadvertant safety injection signal. I BEAVER VALLEY - UNIT 1 B3/4 5-1 Page A PROPOSED WORDING
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,, 3/4.5 DIERGENCY CORE COOLING SYSTEMS (ECCS)
- ~ .SES i
l 3 /4.5.1 ACCUMULATORS 1
l The OPERABILITY of each of the RCS accumulators ensures that a suf fi-cient volume of borated water will be i= mediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanisa during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the accident analysis are met.
The limit of one hour for operation with an inoperable accumulator minimizes the time exposure of the plant to a LOCA event occurring con-current with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.
l 3 /4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS f
., The OPERABILITY of two separate and independent ECCS subsystems
- ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration. Either subsystem operating in conjunction
.with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest
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long term core cooling capability in the recirculation mode during the accident recovery period.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assemptions used in the accident i analyses are met and that subsystem OPERABILITY is maintained.
The limitation for a maximum of one charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except that required OPERABLE pump to be inoperable below 275'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
i 3/4.5.4 BORON INJECTION SYSTEM The OPERABILITY of the boron injection system as part of the ECCS
, ensures that sufficient negative reactivity is injected into the core to limit the positive increase in reactivity caused by RCS system cool- [
down. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.
The boron injection tank is required to be isolated when RCS temperature is less than 350*F to prevent an overpressurization due to an inadvertant safety injection signal.
BEAVER VALLEY - UNIT 1 B3/4 5-1 Page B PROPOSED WORDING
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l EMERGENCY CORE COOLING SYSTDiS 3/4.5.4 BORON INJECTION SYSTDi BORON INJECTION TANY < 350*F LIMITING CONDITION FOR OPERATION 3.5.4.1.2 The boron injection tank shall be INOPERABLE:
APPLICABILITY: MODES 4, 5, and 6 ,
i ACTION:
With the boron injection tank operable, restore the tank to INOPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.4.1.2 The boron injection tank shall be verified INOPERABLE by:
4 a. Verifying at least once per 7 days that each flowpath into
! the RCS through the boron injection tank is isolated and de-energized except for purposes of flow testing or stroking the BIT inlet and outlet valves.
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BEAVER VALLEY - UNIT 1 3/4 5-7a PROPOSED WORDING
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