ML20210U450
| ML20210U450 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/12/1987 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20210U404 | List: |
| References | |
| NUDOCS 8702180483 | |
| Download: ML20210U450 (14) | |
Text
Unit 3 Table 3.1.1 TTQ Cj REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. Modes in which Number of 3p c3 of Operable Function Must be Instrument ts C) Instrument Trio Level Operable Channels Action C3 Jh Channels Trip Function Setting Provided (1) CIC3 per Trip Refuel Startup Run by Design 3E I*3 Item System (1) (7) o$ khC) 1 1 Mode Switch In X X X 1 Mode Switch A C)PJ Shutdown (4 Sections) '3 O" t* N M 33 '4 2 1 Manual Scram X X X 2 Instrument A 'O Channels 3 3 IRM High Flum $120/125 of Full X X (5) 8 Instrument A Scale Channels 4 3 IRM Inoperative X X (5) 8 Instrument A Channels 5 2 APRM High Flum (.66W+54-0.66aw) X 6 Instrument A or B FRp/MFLPD Channels 'l (12) (13) La Uf 6 2 APRM Inoperative (II) X X X 6 Instrument A or 8 Channels 7 2 APRM Downscale 22.5 Indicated (10) 6 Instrument A or B on Scale Channels 8 2 APRM High Flus 115% Power X X 6 Instrument A in Startup Channels 9 2 High Reactor 11055 psig X(9) X X -4 Instrument A Pressure Channels 10 2 High Drywall 12 psig X(8) X(8) X 4 Instrument A Pressure Channels 11 2 Reactor Low 10 in. Indicated X X X 4 Instrument A Water Level Level Channels /: a m A.
f l l Unit 3 l Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. Modes.in which Number of of operable Function Must be Instrument l Instrument Trip Level Operable Channels Action Channels Trip Function Setting Provided (1) per Trip Refuel Startup Run by Design Item System (.1 ) (7) 1 1 Mode Switch In X X X 1 Mode Switch A Shutdown (4 Sections) 2 1 Manual Scram X X X 2 Instrument A Channels ( 3 3 IRM High Flun $120/125 of Full X X (5) 8 Instrument A Scale Channels 4 3 IRM Inoperative X X (5) 8 Instrument A Channels 5 2 APRM High Flus (.66w+54-0.66 4w) X 6 Instrument A or 8 ii 8 FRP/MFLPD Channels lkj (12) (13) B 6 2 APRM Inoperative (11) X X X 6 Instrument A or 8 Channels 7 2 APRM Downscale 12.5 Indicated (10) 6 Ir.st rument A or 8 on Scale Channels 8 2 APRM High Flui 115% Power X X 6 Instrument A in Startup Channels 9 2 High Reactor 11055 psig X(9) X X a Instrument A Pressure -Channels 10 2 High Drywell 12 psig X(8) X(8) X 4 Instrument A Pressure Channels 11 2 Reactor Low 10 in. Indicated X X X 4 Instrument A Water Level Level Channels l
Unit 2 Tcble 3.1.1 (Cant'd) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. Modes in which Number of cf Operable Function Must be Instrument Instrument Trip Level Operable Channels Action Channels Trip Function Setting Provided (1) per Trip Refuel Startup Run by Design Item System (1) (T) 12 2 High Water Level 150 Gallons x(2) x x 4 Instrument A in Scram Discharge Channels Instrument Volume 13 2 Turbine Condenser ?? en. Hg. x 4 Instrument A or C Low Vacuum v coum Channels 14 2 Main Steam Line 115 x Normal X X X 4 Instrument A High Radiation Full Power Channels
Background
15 4 Main Steam Line $10% Valve x(6) 8 Instrument A Isolation Valve Closure Channels Closure ,wU I 16 2 Turbine Control 500<Pc850 psig x(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid and Disc Dump Valve 17 4 Turbine Stop $10% Valve x(4) 8 Instrument A or D Valve Closure Closure Channels
.n Unit 3 TCblo 3.1.1 (Cant'd) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. Modes in ehtch 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 Design Item System (1) (7) k 12 2 High Mater Level 150 Gallons X(2) X X 4 Instrument A in Scram Discharge Channels Instrument Volume 13 2 Turbtne Condenser 123 in. Hg. X 4 Instrument A or C Lou Vacuum Vacuum Channels l14 2 Main steam Line 515 X Normal X X X 4 Instrument A High Radiation Full Power Channels
Background
.5 4 Main Steam Line $10% Valve X(6) 8 Instrument A Isolation valve Closure Channels Closure 16 2 Turb9ne Control 500<P<050 peig X(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels I sure Between Fast I Closure Solenoid I and Disc Dump Valve 17 4 Turbine Stop 510% Valve X(4) 8 Instrument A or D Valve Closure Closure Channels l l- + Y e m
PBAPS Unit 3 I NOTES FOR TABLE 3.1.1 (Cont'd) 10. The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not high. 11. An APRM will be considered operable if there are at least.2 LPRM inputs per level and at least 14 LPRM inputs of the normal complement. 12. This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), where: i FRP = fraction of rated' thermal power (3293 MWt). MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all 8 x 8 fuel. t The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used. W= Loop Recirculation flow in percent of design. W is 100 for core flow of 102.5 million lb/hr or greater. Delta W = the difference between two loop and single loop effective recirculation drive flow rate at the same core flow. During single loop operation, i the reduction in trip setting (-0.66 delta W) is accomplished by correcting the flow input of the flow biased High Flux trip setting to preserve the original (two loop) relationship between APRM High Flux setpoint and recirculation drive { flow or by adjusting the APRM Flux trip setting. ]t Delta W equals zero for two loop operation. Trip level setting is in percent of rated power (3293 MWt). I j 13. See Section 2.1.A.l. I I 1 l ;
i PBAPS 1 3.0 BASES (Cont'd) the other protection trip system. Each protection trip system-has one more APRM than is necessary to meet.the minimum ~ number 1 required per channel. This allows the bypassing of one APRM per-protection trip system for maintenance,' testing or calibration. Additional IRM channels have.also been provided to allow for bypassing of one such channel. The bases for the scram setting for the IRM, APRM, high reactor pressure, reactor low water level, MSIV closure, generator load rejection, turbine stop valve 3 closure and loss of-condenser vacuum are discussed in . Specification 2.1 and 2.2. i Instrumentation sensing _drywell pressure is provided to detect.a loss of coolant accident and initiate the core standby cooling equipment. A high drywell pressure scram is provided at.the same l setting as the core standby cooling systems-(CSCS) initiation to i minimize the energy which must be accommodated during a loss.of coolant accident and to prevent return to criticality.- This instrumentation is a backup to the reactor vessel water level. instrumentation. High radiation levels in the main steam line tunnel above that 4 j due to the normal nitrogen and oxygen radioactivity is an indication of leaking fuel. A scram is initiated whenever such l radiation level exceeds fif teen times normal background. The purpose of this scram is to limit fission product release so that 10 CFR Part 100 guidelines are_not exceeded. Discharge of excessive amounts of radioactivity to the site environs is i prevented by the off gas treatment system, which provides sufficient delay time to reduce fission product release rates to well below 10 CFR 20 guidelines. A reactor mode switch is provided which actuates or bypasses the various scram functions appropriate to the particular plant operating status. Ref. paragraph 7.2.3.7_FSAR. The manual scram function is active in all modes, thus providing for a manual means of rapidly inserting control rods during all modes of reactor operation. l The APRM (High flux in Start-up or Refuel). system provides protection against excessive power levels and short reactor periods in the start-up and intermediate power. ranges. ) The IRM system provides protection against short reactor periods in these ranges. The control rod drive scram system is designed so that.all of the water which is discharged from_the reactor by a scram can be accommodated in the discharge. piping. The scram discharge volume accommodates in excess of 50 gallons of water and is the low point in the piping. No credit was taken for this volume in the design of the discharge piping as concerns i i. -
I i l i TABLE 3.2.A Unit 2 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) Trip System Item (1) 1 2 (6) Reactor Low Water 1 0" Indicated 4 Inst. Chwnne l s A Level Level (3) 2 1 Reactor High Pressure 1 75 psig 2 Inst. Channels D (Shutdown Cooling Isolation) 3 2 Reactor Low-Low-Low at or above -160" 4 Inst. Channels A Water Level indicated level (4) I h! 4 2 (6) High Drywell Pressure 1 2 psig 4 Inst. Channels A i l5 2 High Radiation Main 115 X Normal Rated Full (8) 4 Inst. Channels 8 Steam Line Tunnel Power Background 6 2 Low Pressure Main 1 850 psig (7) 4 Inst. Channels 8 Steam Line 7 2 (5) High Flow Main i 140% of Rated 4 Inst. Channels 8 Steam Line Steam Flow 8 2 Main Steam Line i 200 deg. F (9) 4 Inst. Channels 8 Tunnel Enhaust Duct High Temperature
TABLE 3.2.A Unit 3 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) Trip System Item (1) 1 2 (6) Reactor Low water 1 0" Indicated 4 Inst. Channels A Level Level (3) 2 1 Reactor High Pressure 1 75 psig 2 Inst. Channels D (Shutdown Cooling Isolation) g 3 2 Reactor Low-Low-Low at or above -160" 4 Inst. Channels A EA Water Level indicated level (4) w I 4 2 (6) High Drywell Pressure 1 2 psig 4 Inst. Channels. A l5 2 High Radiation Main $15 X Normal Rated Full (8) 4 Inst. Channels B Steam Line Tunnel Power Background i-6 2 Low Pressure Main 1 850 psig (T) 4 Inst. Channels B Steam Line 7 2 (S) High Flow Main 5 140% of Rated 4 Inst. Channels 5 Steam Line steam Flow 8 2 Main Steam Line 1 200 deg. F (9) 4 Inst. Channels" 8 Tunnel Exhaust Duct High Temperature
Unit 2 TABLE 3.2.0 INSTRUMENTATION THAT INITIATES PRIMARY CSNTAINMENT ISOLATION 5 Mlntmum No, of Operable Number of Instrument Instrument Instrument Trip Level Setting Channels Provided Action Channels per By Design (2) Trip System item (' t ) 9 2 Main Steam Line 1 200 Dec. F 4 Inst. Channels B Leak Detection High Temperature 10 1 Reactor Cleanup 1 300% of Rated 2 Inst. Channels C System High Flow Flow 11 1 Reactcr Cleanup i 200 Dog. F. 1 Inst. Channels E System High Temperature 12 2 Reactor Pressure 3 600 psis 4 Inst. Channels F (Feedwater Flush System Interlock) l Os N 1 t I
~ _.. ~. Unit 3 TABLE 3.3.5 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) Trip System Item (1) 9 2 Main Steam Line 1 200 Deg. F 4 Inst. Channels B 1 Leak Detection High Temperature 10-1 Reactor Cleanup i 300% of Rated 2-Inst. Channels C System Migh Flow Flow 11 1 Reactor Cleanup 5 200 Dog. F. 1 Inst. Channels E System High Temperature 12 2 Reactor Pressure 1 600 psig 4 Inst. Channels F (Feedwater Flush System Interlock) m N 1
PBAPS Unit 2 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 hours. 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 t'ater Cleanup Filter Demineralizers unless the following provision is sa21sifed. 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 hours, provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F. F. Isolate Feedwater Flush System 3. Instrument setpoint corresponds to 538 inches above vessel zero. 4. Instrument setpoint corresponds to 378 inches above vessel zero. 5. Two required for cach steam line. 6. These signals also start SBGTS and initiate secondary containment isolation. 7. Only required in Run Mode (interlocked with Mode Switch). 8. 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. i l l l l
PBAPS Unit 3 NOTES FOR TABLE 3.2.A 1. Wnenever 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 hours. 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 satisifed. The RWCU Filter Demineralizer may be used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank,. i with the high temperature trip inoperable for up to 48 hours, 4 provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F. j F. Isolate Feedwater Flush System 3. Instrument setpoint corresponds to 538 inches'above vessel zero. 4. Instrument setpoint corresponds to 378 inches.above vessel zero. Two required for each steam line. 5. l 6. These signals also atart SBGTS and initiate-secondary containment isolation. 7. Only required in Run Mode (interlocked with Mode Switch). 8. 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. i ! l
PBAPS 3.2 BASES (Cont'd) the emergency diesel. generators. These trip level settings were chosen to be high enough to prevent spurious actuation but low enough to initiate CSCS operation and primary system isolation so that post-accident cooling can be accomplished and the guidelines of 10 CFR 100 will not be exceeded. For large breaks up to the complete circumferential break of a 28-inch recirculation line and with the trip setting given above, CSCS initiation and primary system isolation are initiated in time to meet the above criteria. Reference paragraph 6.5.3.1 FSAR. The.high drywell pressure instrumentation is a diverse signal for malfunctions to the water level instrumentation and in addition to initiating CSCS, it causes isolation of Group 2 and 3 isolation valves. For the breaks discussed above, this instrumentation will generally initiate CSCS operation before the low-low-low water level 4 instrumentation; thus the results given above are applicable here also. See Spec. 3.7 for Isolation Valve Closure Group..The water level instrumentation initiates protection for the full spectrum of loss-of-coolant accidents and causes isolation of all isolation valves except Groups 4 and 5. j Venturis are provided in the main steam lines as a means of measuring steam flow and also limiting the loss of mass inventory from the vessel during a steam line break accident. The primary function of the instrumentation is to detect a break in the main steam line. For the worst case accident, main steam line break outside the drywell, a i trip setting of 140% of rated steam flow in conjunction with the flow limiters and main steam line valve closure, limits the mass inventory loss such that fuel is not uncovered, fuel temperatures peak at approximately 1000 degrees F and release of radioactivity to the environs is below CFR 100 guidelines. Reference Section 14.6.5 FSAR. Temperature monitoring instrumentation is provided in the main steam line tunnel exhaust duct and along the steam line in the turbine building to detect leaks in these areas. Trips are provided on this instrumentation and when exceeded, cause closure of-isolation valves. ] See Spec. 3.7 for valve Group. The setting is 200 degrees F for the main steam line tunnel detector. For large breaks, the high steam flow instrumentation is a backup to the temperature instrumentation.. j High radiation monitors in the main steam line tunnel have been l provided to detect gross fuel failure as in the control rod drop accident. With the established setting of 15 times normal background, j and main steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this l accident. Reference Section 14.6.2 FSAR. I i , l [ \\
n en b E !I CERTIFICATE OF SERVICE t F ..U M [; I hereby certify that copies of the foregoing Application were served on-the following by deposit in the United States mail, first-class postage prepaid, on this 12th day of February,1987. f t Regional Administrator U.S. Nuclear Regulatory Commission, Region I 631 Park Avenue s King of Prussia, PA 19406 [ T. P. Johnson, Resident Inspector l U. S. Nuclear Regulatory Commission } Peach Bottom Atomic Power Station j P. O. Box 399 t Delta, PA 17314 ,i Mr. Thomas Gerusky, Director ,f Bureau of Radiation Protection Department of Environmental Resources Fulton Bank Building, 5th Floor Third 6 Locusts Streets Harrisburg, PA 17120 4 ( i: f I, i: 1-l / Eugg J. #Bradley Attorney for i Philadelphia Electric Company ? b i ......}}