ML20094B000
| ML20094B000 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/26/1995 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20094A988 | List: |
| References | |
| NUDOCS 9510310252 | |
| Download: ML20094B000 (26) | |
Text
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APRM Gain and Setpoints 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints i
LC0 3.2.4 a.
T shall be a 1.0; or b.
Each required APRM setpoint specified in the COLR shall be made applicable; or i
c.
Each required APRM gain shall be adjusted such that the adjusted APRM readings result in a calculated T a 1.0 whentheAPRMreadingissubstitutedfor[factish[bf Ratid1ThermallPoweg(FRTP)..
APPLICABILITY:
THERMAL POWER 2 25% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1 Satisfy the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> LCO not met, requirements of the LCO.
B.
Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 25% RTP.
Time not met.
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1 RIVER BEND 3.2-4 Amendment No. M LATER 951031o252 951026 PDR ADOCK 05000458 P
PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM REQUIRED REQUIRED FUNCil0N CHANNELS ACTION D.1 1.
Reactor Steam Dome Pressure 2
E 2.
Reactor vessel Water Level-Wide Range 2
E 3.
Reactor Vessel Water Level-Fuel Zone 2
E 4.
Suppression Pool Water Level 2
E 5.
Suppression Pool sector Water Tenperature 2("I E
6.
Drywell Pressure 2
E 7.
Primary Containment Pressure 2
E 8.
Drywell Area Radiation 2
F 9.
Primary Containment Area Radiation 2
F
- 10. Drywell H, Analyzer 2
E
- 11. Containment H, Analyzer 2
E 12.PenetrationFlowPath,Automatj{PCIVPosition 2perpenetgtlonflow E
)
(a) Monitoring each of two sectors.
(b) Not required for isolation valves whose associated penetration flow path is isolated.
(c) Only one position indication channel is required for penetration flow paths with only one control room indication channel.
RIVER BEND 3.3-22 Amendment No. 84 LATER
CRFA System Instrumentation 3.3.7.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
As required by C.1 Declare associated I hour from Required Action A.1 CRFA subsystem discovery of and referenced in inoperable, loss of CRFA Table 3.3.7.1-1.
initiation capability in both trip systems AND C.2 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> trip.
D.
As required by D.1 Declare associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> _from Required Action A.1 CRFA subsystem discovery of and referenced in inoperable.
loss of CRFA Table 3.3.7.1-1.
initiation j
capability in j
both trip systems AND D.2 Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> trip.
E.
Required Action and E.1 Place the associated I hour associated Completion CRFA subsystem in Time of Condition B, Issijgbffee C, or D not met.
fE6L..en mode of cperct i cr..
0E E.2 Declare associated I hour CRFA subsystem inoperable.
RIVER BEND 3.3-69 Amendment No. 81 LATER
CRFA System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)
Control Room Fresh Air System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHAANELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION A.1 REQUIREMENTS VALUE 1.
Reactor vessel Water 1,2,3 2
B SR 3.3.7.1.1 2 -47 inches Level-Low Low, Level 2 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 SR 3.3.7.1.5 2.
Drywell Pressure - High 1,2,3 2
C SR 3.3.7.1.1 s 1.88 psid SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3. 7.1. 4 SR 3.3.7.1.5 3.
Control Room (M el 1,2,3 1
D SR 3.3.7.1.1 s 0.97 x 10
intake Ventilation (a),(b)
SR 3.3.7.1.2 C1/cc Radiation Monitors SR 3.3.7.1.4 SR 3.3.7.1.5 (a) During operations with a potential for draining the reactor vessel.
(b) During CORE ALTERATIONS and during movement of irradiated fuel assenblies in the primary or secondary containment.
l s
1, RIVER BEND 3.3-71 Amendment No. 81 LATER.
LOP Instrumentation 3.3.8.1 Teble 3.3.8.1-1 (page 1 of 1)
Loss of Power Instrumentation REQ'JIRED CHANNELS PER SURVEILLANCE ALLOWABLE FUNCTION DIV!$10N REQUIREMENTS VALUE 1.
Divisions 1 and 2 - 4.16 kV Emergency Bus Urk.lervoltage a.
Loss of Voltage - 4.16 kV 3
SR 3.3.8.1.1 2 2850 V and s 3 'O V basis SR 3.3.8.1.2 SR 3.3.8.1.3 SR 3.3.8.1.4 b.
Loss of Voltage - Time 3
SR 3.3.8.1.2 2 2.67 seconds and Delay SR 3.3.8.1.3 s 3.33 seconds SR 3.3.8.1.4 c.
Degraded Voltage - 4.16 kV 3
SR 3.3.8.1.1 a 3605 V and s 3875 Y basis SR 3.3.8.1.2 SR 3.3.8.1.3 SR 3.3.8.1.4 d.
Degraded Voltage - Time 3
SR 3.3.8.1.2 a 53.4 seconds and Delay, No LOCA SR 3.3.8.1.3 s 66.6 seconds SR 3.3.8.1.4 e.
Degraded Voltage-Time 3
SR 3.3.8.1.2 2 2.67 seconds and Delay, LOCA SR 3.3.8.1.3 s 3.33 seconds SR 3.3.8.1.4 2.
Division 3 -4.16 kV Emergency Bus Undervoltage a.
Loss of Voltage -4.16 kV 2
SR 3.3.8.1.1 a 2831 V and s 3259 Y basis SR 3.3.8.1.3 s
SR 3.3.8.1.4 b.
Loss of Voltage - Time 2
SR 3.3.8.1.3 a 2.67 seconds and Delay SR 3.3.8.1.4 s 3.33 seconds c.
Degraded Voltage -4.16 kV 2
SR 3.3.8.1.1 2 3702 V and s 3852 V basis SR 3.3.8.1.2 SR 3.3.8.1.3 SR 3.3.8.1.4 d.
Degraded Voltage - Time 2
SR 3.3.8.1.2 a 53.4 sh4esseconds ar.d Delay, No LOCA SR 3.3.8.1.3 s 66.6 e4wtesseconds SR 3.3.8.1.4 e.
Degraded Voltage - Time 2
SR 3.3.8.1.2 a 2.67 seconds and Delay, LOCA SR 3.3.8.1.3 s 3.33 seconds SR 3.3.8.1.4 RIVER BEND 3.3-74 Amendment No. 81.LATER 1
RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.11.8
NOTE--------------------
Only required to be met in single loop operation during increases in THERMAL POWER or recirculation loop flow with the recirculation loop' flow in the operating loop s 50% of rated recirculation loop flow or THERMAL POWER sjs 30% of RTP.
Verify the difference between the bottom Once within head coolant temperature and the RPV 15 minutes i
coolant temperature is s 100*F.
prior to an increase in THERMAL POWER or an increase in loop flow SR 3.4.11.9
NOTE--------------------
Only required to be met in single loop 1
operation during increases in THERMAL POWER or recirculation loop flow with the recirculation loop flow in the operating loop s 50% of rated recirculation loop flow, or THERMAL POWER 4iE_30% of RTP, and the idle recirculation loop not isolated from the RPV.
Verify the difference between the reactor Once within coolant temperature in the recirculation 15 minutes loop not in operation and the RPV coolant prior to an temperature is s 50*F.
increase in THERMAL POWER or an increase in loop flow RIVER BEND 3.4-31 AmendmentNo.BlifLATER
Secondary Containment-Operating 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.4.1.2 Verify all secondary containment 31 days j
equipment hatches are closed and sealed indiloopfsea]ssfilled.
SR 3.6.4.1.3 Verify each secondary containment access 31 days door is closed, except when the access opening is being used for entry and exit.
i SR 3.6.4.1.4 Verify each standby gas treatment (SGT) 18 months on subsystem will draw down the shield a STAGGERED building annulus and auxiliary building TEST BASIS to 2 0.5 and 2 0.25 inch of vacuum water gauge in s 18.5 and s 13.5 seconds, respectively.
j SR 3.6.4.1.5 Verify each fuel building ventilation 18 months on a subsystem will draw down the fuel STAGGERED TEST building to 2 0.25 inch of vacuum water BASIS gauge in s 12.5 seconds, SR 3.6.4.1.6 Verify each SGT subsystem can maintain 18 months on a 2 0.5 and 2 0.25 inch of vacuum water STAGGERED TEST gauge in the shield building annulus and BASIS auxiliary building, respectively, for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SR 3.6.4.1.7 Verify each fuel building ventilation 18 months on a subsystem can maintain 2 0.25 inch of STAGGERED TEST vacuum water gauge in the fuel building BASIS for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
RIVER BEND 3.6-47 Amendment No. M LATER
SCIDs 3.6.4.2 SURVEILLANCE REQUIREMENTS i
l SURVEILLANCE FREQUENCY i
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are open under administrative centrols.
Verify each secondary containment 31 days inclation : nual d:::cr and blind flange that is required to :c closed during 4..am +, -. A 4. +. 4. m.,
.,. m.. m A.
4.
.w
.... i.
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1 SR 3.6.4.2.31 Verify the isolation time of each 92 days PsysirsdipcwerOperatedandc:ah l
iutdMitil SCID is within limits.
4 i
i SR 3.6.4.2.32 Verify each PsydiFsd? automatic SCID 18 months actuates to th~e'isolition position on an actual or simulated automatic isolation j
signal.
4 1
RIVER BEND 3.6-50 Amendment No. 81 LATER I
Fuel Building 3.6.4.5 3.6 CONTAINMENT SYSTEMS 3.6.4.5 Fuel Building LC0 3.6.4.5 The fuel building shall be OPERABLE.
APPLICABILITY:
During movement of irradiated fuel assemblies in the fuel building.
. ACTIONS.
i
NOTE------------------------------------------
LC0 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Fuel building A.1
-Suspend movement of Immediately inoperable.
irradiated fuel assemblies in the fuel building.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.5.1 Verify fuel building vacuum is 2: 0.25 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inch ~of vacuum water gauge.
SR 3.6.4.5.2 Verify all fuel building equipmgnt 31 days hatche: cnd :hield bleck: c.-'. vers are o -
SR 3.6.4.5.3 Verify each fuel building access door is 31 days closed, except when the access opening is being used for entry and exit.
RIVER BEND 3.6-55 AmendmentNo.81LATER
Drywell Air Lock 3.6.5.2 3.6 CONTAINMENT SYSTEMS h
3.6.5.2 Drywell-Air Lock LCO 3.6.5.2-
-The drywell air lock shall be OPERABLE.
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APPLICABILITY:
MODES 1, 2, and 3.
i ACTIONS
.....................................N0TES------------------------------------
1.
Entry and exit is permissible to perf6rm repairs of the_ affected air lock components.
L 2.
Enter applicable Conditions and Required Actions of LCO 3.6.5.1, "Drywell," when air lock leakage results in exceeding overall drywell bypass leakage rate _ acceptance criteria.
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CONDITION REQUIRED ACTION COMPLETION TIME A.
One drywell air lock
NOTES------------
door inoperable.
1.
Required Actions A.1, A.2, and A.3 are not-applicable if both doors in the air lock are inoperable and '
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Condition C is entered.
2.
Entry and exit is permissible for 7 days under administrative controls.
t A.1 Verify the OPERABLE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> door is closed.
AND
{
(continued)
RIVER BEND 3.6-62 AmendmentNo.81LATER
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AC Sources--Operating 3.8.1 1
4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.16
NOTE-------------------
This Surveillance shall not be performed in MODE 1, 2, or 3.
However, credit may be taken for unplanned events that satisfy this SR.
Verify, with a DG operating in test mode 18 months and connected to its bus, an actual or simulated ECCS initiation signal overrides the test mode by:
a.
Returning DG to ready-to-load operation; and b.
Automatically energizing the emergency loads from offsite power.
SR 3.8.1.17
NOTE--------------------
4-This Surveillance shall not be performed in MODE 1, 2, or 3.
However, credit may be taken for unplanned events that satisfy this SR.
Verify sequence time is within i 10% of 18 months design for each load sequencer timer.
i (continued) l RIVER BEND 3.8-13 Amendment No. 84 LATER j
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e AC Sources--Shutdown 3.8.2 l
3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources--Shutdown LC0 3.8.2 The following AC electrical power sources shall be OPERABLE:
a.
One qualified circuit between the offsite transmission l
network and the onsite Class IE AC electrical power distribution subsystem (s) required by LC0 3.8.10,
" Distribution Systems--Shutdown"; and b.
One diesel generator (DG) capable of supplying one division of the Division I or II onsite Class 1E AC electrical power distribution subsystem (s) required by LC0 3.8.10; and l
c.
One qualified circuit, other than the circuit in LC0 3.8.2.a, between the offsite transmission and the Division III onsite Class 1E electrical power distribution subsystem, or the Division III DG. capable of supplying the Division III onsite Class 1E AC electrical power distribution subsystem, when the i
Division III onsite Class 1E electrical power i
distribution subsystem is required by LC0 3.8.10.
APPLICABILITY:
MODES 4 and 5, l
During movement of irradiated fuel assemblies in the primary containment or fuel building, j
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RIVER BEND 3.8-17 Amendment No. 81 LATER i
i
.____.___m._
Distribution Systems--Operating 3.8.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
One or more Division I C.1 Restore Division I 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or 11 DC electrical and II DC electrical power distribution power distribution AND subsystems inoperable.
subsystems to OPERABLE status.
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO D.
Required Action and D.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, AND B, or C not met.
D.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E.
One or more E.1 Declare High Pressure Immediately 1
DC,crACvital{pi Division III ACr Core Spray System and i
us Standby Service Water electrical power System pump 2C distribution inoperable.
subsystems inoperable.
F.
Two or more divisions F.1 Enter LC0 3.0.3.
Immediately with inoperable i
distribution subsystems that result in a loss of function.
f RIVER BEND 3.8-39 Amendment No. 81 LATER
Programs and M nuals 5.5 l
l 1
5.5 Programs and Manuals 5.5.11 Technical Specifications (TS) Bases Control Proaram (continued) c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.
d.
Proposed changes that do not meet the criteria of either Specification 5.5.11.b.1 or Specification 5.5.11.b.2 above shall be reviewed and approved by the NRC prior to implementation.
Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.12 Bicfculine Preventien :nd Octection A pr gram, which will include the procedures te prevent bicfculing of :sfety related equipment, to :: ure detection of Cerbicula in the intake embayment and the clarifier influent, and t: =cnitor and curvey : tety related equipment te detect bicfculing.
Changes to this program will bc submitted tc and approved by the NRC (both the Regien and NRR) prior to implementation.
t RIVER BEND 5.0-16 Amendment No. 81 LATER
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued) the immediate work areas and the maximum allowable stay times for individuals in those areas.
In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over'the activities being performed within the area.
5.7.3 In addition to the requirements of Specification 5.7.1, for individual high radiation areas with radiation levels of a 1000 mrem /hr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists guarded,andwherenoenclosurecanbereas}o{na[66}{ continuously for purposes of locking, or that cannct bc bly constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.
)
i RIVER BEND 5.0-21 Amendment No. 81 LATER
License Amendment Request 95-10 October 26,1995 TECHNICAL SPECIFICATIONS BASES MARK-UPS
CRFA System Instrumentation B 3.3.7.1 l
B 3.3 INSTRUMENTATION B 3.3.7.1 Control Room Fresh Air (CRFA) System Instrumentation BASES BACKGROUND The CRFA System is designed to provide a radiologically controlled environment to ensure the habitability of the control room for the safety of control room operators under all plant conditions.
Two independent CRFA subsystems are each capable of fulfilling the stated safety function. The instrumentation and controls for the CRFA System automatically initiate action to isolate or pressurize the main control room (MCR) to minimize the consequences of radioactive material in the control room environment.
In the event of a Reactor Vessel. Water Level-Low Low, Level 2, Drywell Pressure-High, or Control Room [6bil Iithijventilation Radiation Monitor signal, the CRFA" System TT~i6thmatically started in the ischtien ienisijyhby mode.
The MCR air is then recirculated through ths'Eharcoal filter, and sufficient outside air is drawn in through the normal intake to keep the MCR slightly pressurized with respect to adjacent areas.
The CRFA System instrumentation has two trip systems: one trip system initiates one CRFA subsystem, while the second trip system initiates the other CRFA subsystem (Ref. 1).
Each trip system receives input from the Functions listed above. The Functions are arranged as follows for each trip system. The Reactor Vessel Water Level-Low Low, Level 2 and Drywell Pressure-High are arranged together in a one-out-of-two taken twice logic. The Control Room L6ssi 15thsVentilationRadiationMonitorsarearrangedis's" two ppg-out-of-onej,twe logic. The channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints.
When the setpoint is exceeded, the channel output relay actuates, which then outputs a CRFA System initiation signal to the initiation logic.
APPLICABLE The ability of the CRFA System to maintain the habitability SAFETY ANALYSES, of'the MCR is explicitly assumed for certain accidents as LCO, and discussed in the USAR safety analyses (Refs. 2 and 3).
APPLICABILITY CRFA System operation ensures that the radiation exposure of control room personnel, through the duration of any one of (continued)
RIVER BEND B 3.3-198 Revision No. O LATEPi
CRFA System Instrumentation B 3.3.7.1 BASES APPLICABLE 2.
Drywell Pressure-Hiah (continued)
SAFETY ANALYSES, LCO, and Drywell Pressure-High signals are initiated from four APPLICABILITY pressure transmitters that sense drywell pressure.
Four channels of Drywell Pressure-High Function are available (two channels per trip system) and are required to be OPERABLE to ensure that no single instrument failure can preclude CRFA System initiation.
The Drywell Pressure-High Allowable Value was chosen to be the same as the Secondary Containment Isolation Drywell Pressure-High Allowable Value (LC0 3.3.6.2).
The Drywell Pressure-High Function is required to be OPERABLE in MODES 1, 2, and 3 to ensure that control room personnel are protected during a LOCA.
In MODES 4 and 5, the Drywell Pressure-High Function is not required since there is insufficient energy in the reactor to pressurize the drywell to the Drywell Pressure-High setpoint.
3.
Control Room Essal%IntaksiVentilation Radiation Monitors measure radiation [ lev]e$1Miks3 Ventilation Radiation Monitor The Control Room 6Es ls exte?ior to the inlet ducting of the MCR. A high radiation level may pose a threat to MCR personnel; thus, a detector indicating this condition automatically signals initiation of the CRFA System.
The Control Room [66iljInfiksjVentilation Radiation Monitors Function consists of'two 16 dependent monitors. Two channels of Control Room L3EAMIsfikslVentilation Radiation Monitors are available and~iFi"iFliUiffd to be OPERABLE M ensure that i
no single instrument failure can preclude CRFA System initiation. The Allowable Value was selected to ensure protection of the control room personnel.
The Control Room EssilDistikslVentilation Radiation Monitors Function is requiFed ~fB" tie"0PERABLE in MODES 1, 2, and 3, and during CORE ALTERATIONS, operations with a potential for i
draining the reactor vessel (f@f]se)condary containment to OPDRVs, and movement of irradiated fuel in the pdmir ensure that control room personnel are protected during a LOCA, fuel handling event, or a vessel draindown event.
During MODES 4 and 5, when these specified conditions are l
not in progress (e.g., CORE ALTERATIONS), the probability of l
a LOCA or fuel damage is low; thus, the Function is not l
required.
l (continued)
RIVER BEND B 3.3-201 Revision No. O LATER
1 CRFA System Instrumentation B 3.3.7.1 BASES ACTIONS D.1 and D.2 (continued)
Because of the diversity of sensors available to provide initiation signals and the redundancy of the CRFA System design, an allowable out of service time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is provided to permit restoration of any inoperable channel to OPERABLE status. However, this out of service time is only acceptable provided the associated Function is still maintaining CRFA System initiation capability. A Function is considered to be maintaining CRFA System initiation capability when sufficient channels are OPERABLE or in trip, such that one trip system will generate an initiation signal from the given Function on a valid signal.
This would require one trip system to have two channels, each OPERABLE or in trip.
In this situation (loss of CRFA System initiation capability), the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance of Required Action D.2 is not appropriate.
If the Function is not maintaining CRFA System initiation capability, both CRFA subsystems must be declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of discovery of loss of CRFA System initiation capability in both trip systems.
If the inoperable channel cannot be restored to OPERABLE status within the allowable out of service time, the channel must be placed in the tripped condition, per Required Action D.2.
Placing the inoperable channel in trip performs the intended function of the channel (starts the associated CRFA subsystem in the isolation mode). Alternately, if it is not desired to place the channel in trip (e.g., as in the case where it is not desired to start the subsystem), Condition E must be entered and its Required Actions taken.
The 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Completion Time is based on the consideration that this Function provides the primary signal to start the CRFA System, thus ensuring that the design basis of the CRFA System is met.
E.1 and E.2 With any Required Action and associated Completion Time not met, the associated CRFA subsystem must be placed in the hchticr smEEgsncy mode of operation (Required Action D.1) to ensure thiit c6ntrol room personnel will be protected in
~
the event of a Design Basis Accident. The method used to place the i
(continued)
RIVER BEND B 3.3-204 Revision No. O LATER 1
.. _. ~._
RCS P/T Limits B 3.4.11 l
i BASES j
i SURVEILLANCE SR 3.4.11.8 and SR 3.4.11.9 (continued)
REQUIREMENTS Plant specific test data has determined that the bottom head is not subject.to temperature stratification with natural circulation at power levels as low as M430% of RTP wand j
with,any single loop flow rate great 4tha;nj50%iofjated loopfflowphen the recirculetion. pump is on hibh : peed Operction.
Therefore, SR 3.4.11.8 and SR 3.4.11.9 have been i
modified by a Note that requires the Surveillance to be met only when THERMAL POWER or loop flow is being increased when l
the above conditions are not met.
The Note for SR 3.4.11.9 l
further limits the requirement for this Surveillance to exclude comparison of the idle loop temperature if the idle loop is isolated from the RPV since the water in the loop can not be introduced into the remainder of the reactor coolant system.
l REFERENCES 1.
2.
ASME, Boiler and Pressure Vessel Code,Section III, Appendix G.
3.
ASTM E 185-82, " Standard Practice for Conducting Surveillance Tests For Light-Water Cooled Nuclear Power Reactor Vessels," July 1982.
4.
5.
Regulatory Guide 1.99, Revision 2, May 1988.
6.
ASME, Boiler and Pressure Vessel Code,Section XI, Appendix E.
7.'
NED0-21778-A, " Transient Pressure Rises Affecting Fracture Toughness Requirements For BWRs,"
December 1978.
8.
USAR, Section 15.4.4.
l l
RIVER BEND B 3.4-61 Revision No. O LATER
i Secondary Containment-Operating j
B 3.6.4.1 BASES ACTIONS B.1 and B.2 (continued) experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
i SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS j
This SR ensures that the shield building annulus, auxiliary i
building, and fuel building boundary is sufficiently leak i
d tight to preclude exfiltration under expected wind conditions.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed j
based on operating experience related to secondary containment vacuum variations during the applicable MODES and the low probability of a DBA occurring between surveillances.
Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the operator to an abnormal secondary containment vacuum condition.
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SR 3.6.4.1.2 and SR 3.6.4.1.3 i
Verifying that secondary containment equipment hatches and access doors are closed ensures that the infiltration of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur.
Veri fying that all such openings are closed provides adequate assurance that exfiltration from the secondary containment will not occur.
In this application the term " sealed" has no connotation of leak tightness. Maintaining secondary containment OPERABILITY requires verifying each door in the access opening is closed, except when the access opening is exhaust!d_d. t?dfa.iMry, and. exit.,dsthetturbineVeFifyingithe%AinJp being used for ent c
loopcsealian bu i l d i ng/ aux il i ary i bu ll d i rig Texh auit / duc tTd rsi n?l o6p&e al s ares full fofj wa ter n al so ? preventsii n fil. t rat i on;oftouts i de tai r andiexfiltrationtfromitheisecondary! containment M The"31" day FFeduintf foTthise'SRs^ has"been^shownFto be' adshdate based
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on operating experience, and is considered adequate in view of the other controls on secondary containment access openings.
(continued)
RIVER BEND B 3.6-86
. Revision No. 0.ATER L
Secondary Containment-0perating B 3.6.4.1 BASES SURVE1LLANCE SR 3.6.4.1.4 and SR 3.6.4.1.6 REQUIREMENTS The SGT System exhausts the shield building annulus and auxiliary building atmosphere to the environment through appropriate treatment equipment.
To ensure that all fission products are treated, SR 3.6.4.1.4 verifies that the SGT System will rapidly establish and maintain a pressure in the shield building annulus and auxiliary building that is less than the lowest postulated pressure external to the secondary containment boundary. This is confirmed by demonstrating that one SGT subsystem will draw down the shield building annulus and auxiliary building to a 0.5 and 2 0.25 inches of vacuum water gauge in s 18.5 and s 13.5 seconds, respectively. This cannot be accomplished if the secondary containment boundary is not intact.
SR 3.6.4.1.6 demonstrates that each SGT subsystem can maintain 2 0.5 and a 0.25 inches of vacuum water gauge for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows shield building annulus and auxiliary building to be in thermal equilibrium at steady state conditions. Therefore, these two tests are used to ensure the integrity of this portion of the secondary containment boundary.
Since these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LC0 3.6.4.3, either SGT subsystem will perform this test.
Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency. Therefore, the. Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.6.4.1.5 and SR 3.6.4.1.7 The Fuel Building Ventilation System exhausts the fuel building atmosphere to the environment through appropriate treatment equipment. To ensure that all fission products are treated, SR 3.6.4.1.5 verifies that the Fuel Building Ventilation System will rapidly establish and maintain a pressure in the fuel building that is less than the lowest postulated pressure external to the secondary containment boundary.
This is confirmed by demonstrating that one fuel building ventilation subsystem will draw down the fuel building to a 0.25 inches of vacuum water gauge in s 12.5 seconds. This cannot be accomplished if the (continued)
RIVER BEND B 3.6-87 Revision No. O LATER J
Secondary Containment-0perating B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.5 and SR 3.6.4.1.7 (continued) l REQUIREMENTS l
secondary containment boundary is not intact.
demonstrates that each SGT subsystem can maintain l
2: 0.25 inches of vacuum water gauge for I hour.
The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows the fuel building to be in thermal t
l equilibrium at steady state conditions. Therefore, these j
two tests are used to ensure the integrity of this portion j
of the secondary containment boundary.
Since these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LC0 3.6.4.3, either SGT subsystem will perform this test. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with j
the reactor at power. Operating experience has shown these components usually pass the Surveillance then performed at the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
REFERENCES 1.
USAR, Section 15.6.5.
2.
USAR, Section 15.7.4.
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l RIVER BEND B 3.6-88 Revision No. O LATER
SCIDs B 3.6.4.2 BASES ACTIONS C.1 and C.2 (continued) reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
D.1, 0.2, and D.3 If any Required Action and associated Completion Time cannot be met, the plant must be placed in a condition in which the LC0 does not apply. When applicable, movement of irradiated fuel assemblies in the fuel building must be immediately suspended.
Suspension of this activity shall not preclude completion of movement of a component to a safe position.
Required Action D.1 has been modified by a Note stating that LC0 3.0.3 is not applicable.
If rnoving irradiated fuel assemblies while in MODE 4 or 5, LC0 3.0.3 would not specify any action.
If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.
SURVEILLANCE SR 3.5.'.2.1 REQUIREMENTS Thi: SR verific c:ch ccendary containment inclation : nual d::per and blind flange that is required te be cle ed during accident ccndition: is cle:cd.
The SR help: te ensure that pcst ccident leak:ge cf radic ctive fluid cr g sc: cutside of the :ccendary centainment beundary is within design limits.
Thi; SR d :: net require any tc: ting er d: per manipul: tion.
R;ther, it invcivc verification th;t these SCID: in ccend:ry centainment that are capabic cf being mispcsitiened arc in the correct pccition.
Since the c SCID: Orc readily accessible to per:cnnel during normal unit Operation and verificatien of their position is relatively 0;;y, the 31 day Frequency w:: che cn to provide added ::urance that the SCID: arc in the ccrrect pccitions.
(continued)
RIVER BEND B 3.6-93
. Revision No. O l..ATER
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SClDs B 3.6.4.2 k
I BASES SURVEILLANCE SR 3.5.4.2.1 (continued)
REQUIREMENTS Twc Note: have been added tc thic SR.
The first Note applic; te d: per and blind flanges located in high radiation arca: and allcw: them te be verified by use Of administrative = cans.
Allowing verificatien by administrative mean: is cencidered acceptable, since access to the:c arc : is typically restricted during MODES 1, 2, 1
and 3 for ALARA rc; ens.
Thereferc, the probability of mic lign=cnt of these SCID, ence they have been verified te be in the prcper pc;ition, is lcw.
A ccend Mct h:: been included to clarify that SCID: that arc open under adminirtrative contrel: cre not required to
=cet the SR during the time the SCID: cre Open.
SR 3.6.4.2.31 Verifying the isolation time of each FEijdifsdl power cperated
- nd cach automatic SCID is within limits'^is~nquired to j
demonstrate OPERABILITY.
The isolation time test ensures i
that the SCIDs will isolate in a time period less than or equal to that assumed in the safety analyses.
The Frequency of this SR is 92 days.
SR 3.6.4.2.32 Verifying that each requiibeC automatic SCID closes on a secondary containment issistion signal is required to prevent leakage of radioactive material from secondary containment following a DBA or other accidents.
This SR ensures that each automatic SCID will actuate to the isolation position on a secondary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.
Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
(continued)
RIVER BEND B 3.6-94 Revision No. O LATER
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Fuel Building B 3.6.4.5 BASES (continued)
. APPLICABILITY In plant operating MODES 1,2, and 3, OPERABILITY of the fuel building is addressed in LC0 3.6.4.1, " Secondary Containment
- Operating." Regardless of the plant operating MODE, anytime irradiated fuel is being handled there is the potential for a FHA and the fuel building OPERABILITY is required to mitigate the consequences.
ACTIONS A.1 With the fuel building inoperable the plant must be brought to a condition in which the LCO does not apply since it is incapable of performing its required accident mitigation function. To achieve this, irradiated fuel handling must be suspended immediately.
Suspension shall not preclude completion of fuel movement to a safe position.
SURVEILLANCE SR 3.6.4.5.1 REQUIREMENTS This SR ensures that the fuel building boundary is sufficiently leak tight to preclude exfiltration under expected wind conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed based on operating experience related to fuel building vacuum variations during the applicable MODES and the low probability of a FHA occurring between surveillances.
Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in view of other indications available in the control room,
)
including alarms, to alert the operator to an abnormal fuel building vacuum condition.
SR 3.6.4.5.2 and SR 3.6.4.5.3 Verifying that fuel building equipment hatches EoViERars
!16 stilled and access doors are closed ensures that~thE" ~
ThfilfFation of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur.
Verifying that all such openings are closed provides adequate assurance that exfiltration from the fuel building will not occur.
Maintaining fuel building OPERABILITY requires verifying each door in the access opening is closed, except when the access opening is being used for entry and exit.
(continued)
RIVER BEND B 3.6-105 Revision No. O LA.TER
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