ML20086B015
| ML20086B015 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/10/1983 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20086B011 | List: |
| References | |
| NUDOCS 8311160221 | |
| Download: ML20086B015 (13) | |
Text
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PBAPS TABLE OF CONTENTS Page No.
1.0 DEFINITIONS 1
LIMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS 1.1 FUEL CLADDING INTEGRITY 2.1 9
1.2 REACTOR COOLANT SYSTEM INTEGRITY 2.2 29 SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS 3.0 APPLICABILITY 4.1 34 3.1 REACTOR PROTECTION SYSTEM 4.1 35 3.2 PROTECTIVE INSTRUMENTATION 4.2 57 3.3 REACTIVITY CONTROL 4.3 99 A.
Reactivity Limitations A
99 B.
101 C.
Scram Insertion Times C
103 D.
Reactivity Anomalies' D
105 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 115 A.
Normal Operation A
115 B.
Operation with Inoperable Components B
116 C.
Sodium Pentaborate Solution C
117 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 4.5 124 A.
Core Spray and LPCI Subsystems A
124 B.
Containment Cooling Subsystem (HPSW)
B 127 C.
HPCI Subsystem C
128 D.
RCIC Subsystem D
130 E.
Automatic Pressure Relief Subsystem E
131 F.
Minimum Low Pressure Cooling System F
132 Diesel Generator Availability-G.
Maintenance of Filled Discharge Pipe G
133 H.
Engineered Safeguards Compartments H
133 Cooling and Ventilations I.
Average Planar LHGR I
133a J.
Local LHGR J
133a K.
Minimum Critical Power Ration (MCPR)
K 133b 8311160221 831110 PDR ADOCK 05000277 p
-i-
PBAPS TABLE OF CONTENTS (Cont'd)
Page SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENT 3.6 PRIMARY SYSTEM BOUNDARY 4.6 143 A.
Thermal and Pressurization Limitations A
143 l
B.
Coolant Chemistry B
145 C.
Coolant Leakage C
146 D.
Safety and Relief Valves D
147 E.
Jet Pumps E
148 l
F.
Recirculation Pumps F
149 G.
Structural Integrity G
149 3.7 CONTAINMENT SYSTEMS 4.7 165 A.
165 B.
Standby Gas Treatment System 3
175 C.
176 D.
Primary Containment Isolation Valves D
177 3.8 RADIOACTIVE MATERIALS 4.8 203 A.
General A
203 B.
Liquid Effluents B
204 C.
Airborne Effluents C
206 D.
Mechanical Vacuum Pump D
209a 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.
Auxiliary Electrical Equipment A
217 B.
Operation with Inoperable Equipment B
219 C.
Emergency Service Water System C
221 3.10 CORE 4.10 225 A.
Refueling Interlocks A
225 B.
Core Monitoring B
227 C.
Spent Fuel Pool Water Level C
228a D.
Heavy Loads Over Spent Fuel D
228a 3.11 ADDITIONAL SAFETY RELATED PLANT l
CAPABILITIES 4.11 233 A.
Main Control Room Ventilation A
233 B.
Alternate Heat Sink Pacility B
234 C.
Emergency Shutdown Control Panel C
234
{
l D.
Shock Suppressors D
234a 3.12 RIVER LEVEL 4.12 237 A.
High River Water Level A
237 B.
Low River Water Level B
237 C.
Level Instrumentation C
238 11
~.
PBAPS TABLE OF CONTENTS (Cont'd)
Page SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENT 3.13 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCE 4.13 240a 3.14 FIRE PROTECTION 4.14 240c A.
Water Fire Protection System A
240c B.
CO2 Fire Protection System B
240g C.
Fire Detection C
240i D.
240j E.
Water Suppression Systems E
240k F.
Battery Rm. Vent. Flow Detector F
2401 3.15 SEISMIC MONITORING INSTRUMENTATION 4.15 240t 5.0 MAJOR DESIGN FEATURES 241 6.0 ADMINISTRATIVE CONTROLS 243 6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit violation 253 6.8 Procedures 253 6.9 Reporting Requirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 l
l i
l iii
PBAPS LIST OF TABLES Table Title Page 1
4.2.B Minimum Test and Calibration Frequency 81 for CSCS 1
4.2.C Minimum Test and Calibration Frequency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibration Frequency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibration Frequency 85 for Drywell Leak Detection 4.2.F Minimum Test and Calibration Frequency 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibration Frequency 88 for Recirculation Pump Trip 3.5.K.2 Operating Limit MCPR Values for 133d Various Core Exposures 3.5.K.3 Operating Limit MCPR Values for 133e Various Core Exposures 4.6.1 In-Service Inspection Program for Peach 150 Bottom Units 2 and 3 3.7.1 Primary Containment Isolation Valves 179 3.7.2 Testable Penetrations With Double 184 0-Ring Seals 3.7.3 Testable Penetrations with Testable 184 Bellows 3.7.4 Primary Containment Testable Isolation 185 Valves 4.8.1 Radioactive Liquid Waste Sampling and 210 Analysis 4.8.2 Radioactive Gaseous Waste Sampling and
.211 Analysis 3.ll.D.1 Safety Related Shock Suppressors 234d 1
3.14.C.1 Fire Detectors 240m 3.15 Seismic Monitoring Instrumentation 240u -
4.15 Seismic Monitoring Instrumentation 240v Surveillance Requirements j
-vi-I 1
Table 3.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No.
Modes in which Number of of Operable Function Must be Instrument Instrument Trip Level Operable Channels Action Channels Trip Function Setting Provided (1) per Trip Refuel Startup Run by Desgin System (1)
(7) 2 High Water Level
<50 Gallons X(2)
X X
4 Instrument A
in Scram Discharge Channels Instrument Volume 2
Turbine Condenser
>23 in. Hg.
X(3)
X(3)
X 4 Instrument A or C Low Vacuum Vacuum Channels 2
<3 X Normal Full X X
X 4 Instrument A
High Radiation Power Background Channels w
4 4
<10% Valve X(3)(6) X(3)(6) X(6) 8 Instrument A
Isolation Valve Elosure Channels Closure
?
Turbine Control 500<P<R50 psig X(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid l
and Disc Dump Valve 4
Turbine Stop (10% Valve X(4) 8 Instrument A or D Valve Closure Closure Channels
PBAPS NOTES FOR '1 ABLE 3.1.1 1.
There shall be two operable or tripped trip systems for each function.
If the minimum number of operable sensor channels for a trip system cannot be met, the affected trip system shall be placed in the safe (tripped) condition, or the appropriate actions listed below shall be taken.
A.
Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
B.
Reduce power level to IRM range and place mode switch in the start up position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and c30se main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30% rated.
2.
Permissible to bypass, in refuel and shutdown positions of the reactor mode switch.
3.
Bypassed when reactor pressure is less than 600 psig.
4.
Bypassed when turbine first stage pressure is less than 220 nsig or less than 30% of rated.
5.
IRM's are bypassed When APRM's are onscale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
7 When the reactor is subcritical and the reactor water temperature is less than 212 degrees F, only the following trip functions need to be operable:
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge instrument volume high level 8.
Not required to be operable When primary containment integrity is not required.
9.
Not required to be operable When the reactor pressure vessel head is.not bolted to the vessel. _ _ _ _ _ _ _ _
TABLE 4.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2)
Functional Test Minimum Frequency (3)
High Water Level in Scram A
Trip Channel and Alarm Every 1 month.
l Discharge Instrument Volume
+
Turbine Condenser Low Vacuum (6)
B2 Trin Channel and Alarm (4)
Every 1 month (1).
Main Steam Line High Radiation B1 Trip Channel and Alarm (4)
Once/ week.
Main Steam Line Isolation A
Trip Channel and Alarm Every 1 month (1).
Valve Closure b
i Turbine Control Valve A
Trip Channel and Alarm Every 1 month.
EHC Oil Pressure Turbine First Stage Pressure A
Trip Channel and Alarm Every 3 months (1).
Parmissive Turbine Stoo Valve Closure A
Trip Channel and Alarm Every 1 month (1).
R; actor Pressure Permissive (6)
B2 Trip Channel and Alarm (4)
Every 3 months.
TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel Group (1)
Calibration (4)
Minimum Frequency (2)
IRM High Flux-C Comparison to APRM on Maximum frequency once Controlled Shutdown per week.
APRM High Flux Output Signal B1 Heat Balance Twice per week.
Flow Bias Signal B1 With Standard Pressure Every refueling outage.
Source LPRM Signal B1 TIP System Traverse Every 6 weeks.
i-High Reactor Pressure B7 Standard Pressure Source Once per operating cycle.
High Drywell Pressure B2 Standard Pressure Source Once per operatoing cycle.
Reactor Low Water Level B2 Pressure Standard Once per operating cycle.
High Water Level in Scram A
Water Column Every refueling outage.
Discharge Instrument Volume Turbine Condenser Low Vacuum B2 Standard Vacuum Source Once per operating cycle.
Main Steam Line Isolation A
Note (5)
Note (5)
Valve' Closure Main Steam Line High Radiation B1 Standard Current Source (3)
Every 3 months.
-Turbine First State Pressure A
Standard Pressure Source Every 6 months.
Parmissive
TABLE 3.2.A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No.
- Of Operable Number of Instrument Instrument Instrument Trip Level Setting Channels Provided Action Channels per By Design (2)
Trio System (1) 2 Main Steam Line
< 200 deg. F.
4 Inst. Channels B
~
Leak Detection High Temperature Reactor Cleanup
< 300% of Rated 2 Inst.. Channels C
- 1 ~ '
System High Flow Flow b
1 Rw_ctor Cleanup
< 200 deg. F 1 Inst. Channel E
l System High I
s 1
Temperature Y
~
f 4
v
PBAPS NOTES FOR TABLE 3.2. A 1.
Whenever Primary Containment integrity is required by Section 3.7, there 'shall be two operable or tripped trip systems for each function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken:
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shutdown Cooling.
E.
Isolate Reactor Water Cleanup Filter Demineralizers unless the following provision is satisfied.
The RWCU Filter Demineralizer may be used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank, with the high' temperature trip inoperable for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F.
3.
Instrument setpoint corresponds to 117.7" above top of active fuel.
4.
Instrument setpoint corresponds to 129.7" above top of active fuel.
5.
Two required for each steam line.
6.
These signals also start SBGTS and initiate secondary containment isolation.
e 7.
Only required in Run Mode (interlocked with Mod Switch).
8.
At a radiation level of 1.5 times the normal' rated. power background, an alarm will be tripped in the control room to alert the control room operators to an increase in the main steam line tunnel-radiation level.
- 9. - In the event of a loss of ventilation in the main steam line tunnel area, the main stmam line tunnel e'xhaust duct high temperature setpoint n.ay be raised up to 250 degrees F for a period not to exceed 30 minutes to permit' restoration of the ventilation flow.
During the 30 minute period, an' operator shall observe control room indications of the~ duct-y temperature su) in the event of rapid increases-(indicative of a steam line break) the operator shall promptly close'the main steam line isolation valves..
TABLE 3.2.C INSTRUMENTATION THAT INITIATES CONTROL ROD BLOCKS Minimum No.
Instrument Trip Level Setting Number of Instrument Action of Operable Channels Provided Instrument by Design Channels Per Trip System 2
APRM Upscale (Flow
-<(0.66w+47-0.66Aw) x 6 Inst. Channels (1)
Biased)
FRP MFLPD (2) 2 APRM Upscale (Startun
<12%
6 Inst. Channels (1)
Mode)
?
APRM Downscale
>2.5 indicated on 6 Inst. Channels (1) scale 1 (7)
Rod Block Monitor
~<(0.66w+41-0.66Aw)x 2 Inst. Channels (1)
(Flow Biased)
FRP j
MFLPD (2) 1 (7)
Rod Block Monitor 12.5 indicated on 2 Inst. Channels (1)
Downscale scale 3
IRM Downscale (3)
>2.9 indicated on R Inst. Channels (1) scale 3
IRM Detector not in (R)
R Inst. Channels (1)
Startup Position 3
IRM Upscale
<108 indicated on R Inst. Channels (1) scale 2 (5)
SRM Detector not in (4) 4 Inst. Channels (1)
Startuo Position 2 (5)(6)
SRM Upscale
<10 counts /sec.
4 Inst. Channels (1) 1
' Scram Discharge
<29 gallons 1 Inst. Channel (4) l Instrument Volume High Level
/
TABLE _4.2.C MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL FOD BLOCKS ACTUATION Instrument Functional Instrument
. Instrument Channel Test Calibration Check
'L )
APRM - Downscale (1) (3)
Once/3 months Once/ day 2).
APRM - Unscale (1) (3)
Once/3 months once/ day 3)
RIM - Upscale (2) (3)
Startup or Control Shutdown (2) 4)
IRM - Downscale (2) (3)
Startup or Control Shutdown (2) 5)
RBM - Upscale (1) (3)
Once/6 months Once/ day 6)
RBM - Downscale (1) (3)
Once/6 months Once/ day 7)
SRM - Upscale (2) (3)
Startuo or Control Shutdown (2) 8)
SRM - Detector Not in Startup (2) (3)
Startup or Control Shutdown (2)
Position 9)
IRM - Detector Not in Startuo (2) (3)
Startuo or Control Shutdown (2)
Position
,gl 10)
Scram Discharge Instrument Volume Quarter 1v Once/ Operating Cycle NA
- High Level Logic System Functional Test (4) (6)
Freauency (1)
System Logic Check once/6 months -
l
F'...
PBAPS j
3.2 BASES (Cont'd).
Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 850 psig.
The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode is less severe than the loss of feedwater analyzed in section 14.5 of the FSAR; therefore, closure of the Main Steam isolation valves for thermal transient protection when not in RUN Mode is not required.
The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping.
Tripping of this instrumentation results in actuation of HPCI isolation valves.
Tripoing logic for the high flow is 1 out of 2 logic.
Temperature is monitored at four (4) locations with four (4) temperature sensors at each location.
Two (2) sensors at each location are powered by "A" DC control bus and two (2) by "B" DC control bus.
Each pair of sensors, e.g.,
"A" or "B" at each location are physically separated and the tripping of either "A" or "B" bus sensor will actuate HPCI isolation valves.
The trip settings of < 100% of design flow for high flow and 200 degrees F for high temperature are such that core uncovery is prevented and fission product release is within limits.
The RCIC high flow and temperature instrumentation are arranged the l
same as that for the HPCI.
The trip setting of < 300% for high flow and 200 degrees F for temperature are based on the same' criteria as the HPCI.
The Reactor Water Cleanup System high flow instrumentation is arranged similar to that for the HPCI System.
The trip settings are such that core uncovery is prevented and fission product release is maintained within limits.
The high temperature instrumentation downstream of the non-regenerative heat exchanger is provided to protect the' ion exchange resin in the deuineralizer from damage due to hiqh temperature.
Such damage could impair the resins' ability to remove impurities from the primary coolant and possibly result in the release of previously captured impurities back into the coolant in large concentrations.
The instrumentation which initiates CSCS action is arranged in a dual bus system.
As for other vital instrumentaiton arranged in this fashion, the Specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed.
An exception to this is when logic. functional testing is boing 6
performed.
The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the fuel cladding integriAy safety limit.
The trip logic for this function of 1 out of na e.g., any trip on one of 6 APRM's, 8 IRM's, or 4 SRM's will result in a rod block.
The minimun instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.
The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing or calibration.
.ThisLtime period is only 3% of the operating time in a month and does,not significantly increase the risk of preventing an inadvertent control 1 rod withdrawal.. i...
.. a