ML20154P083
| ML20154P083 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/14/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20154P088 | List: |
| References | |
| DPR-44-A-117, DPR-56-A-121 NUDOCS 8603200126 | |
| Download: ML20154P083 (28) | |
Text
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~k UNITED STATES s
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NUCLEAR REGULATORY COMMISSION
- j WASHINGTON, D. C. 20555
%...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.ll7 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 17, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
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4 1 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. ll7, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMi1ISSION t,
p Daniel R. Muller, Director BWR Project Directorate //2 Division of BWR Licensing
Attachment:
Changes to the Tcchnical Specifications Date of Issuance: flarch 14, 1986 i
.._,_-,e m
ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 7
7 8
8 38 38 39 39 42 42 45 45 49 49 62 62 63 63 63a 80 80 i
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PBAPS 1.0 DEFINITIONS (Cont'd) outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
Reportable Event - A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
Run Mode - In this mode the reactor system pressure is at or above 850 psig and the reactor protection system is energized with APRM protection (excluding.the 15% high flux trip) and RBM interlocks in service.
Safety Limit - The safety limits are limits below which the reasonable maintenance of the cladding and primary systems are assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit operation.
Operation teyond toch a limit may not in itself result in serious consequences, but it indicates an ope. rational deficiency subject to regulatory review.
Secondary Containment Integrity - Secondary Containment integrity
,'~
means that the reactor building is intact and the following conditions are met:
1.
At least bne door in each access opening is closed.
2.
The standby gas treatment is operable.
3.
All Reactor Building ventilation system automatic isolat' ion valves are operable or deactivated in the' isolation position.
Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed.
After a short time period (about 10 sec), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic system; also, the main steam line isolation scram and main condenser low vacuum scram are bypassed.-
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Amendment No. 102, 110 -
4 PBAPS 1.0 DEFINITIONS (Cont'd)
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
SITE BOUNDARY - That line beyond Which the land is not owned, leased or otherwise controlled by licensee.
Source Check - A source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam line isolation valve closure are bypassed, the reactor protection l
system is energized with IRM neutron monitoring system trip, the APRM 15% high flux trip, and control rod withdrawal interlocks in service.
This is often referred to as just Startup Mode.
This is intended to imply the Startup/ Hot Standby position of the mode switch.
Surveillance Frecuency - Periodic surveillance tests, checks calibrations, and examinations shall be performed within the specified surveillance intervals.
The operating cycle interval as pertaining to instrument and electrical surveillance shall not i
exceed 18 months.
These specified time intervals may be exceeded by 25%.
In cases Where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
Surveillance tests are not required on systems or parts of the systems that are not required to be operable or are tripped.
If tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system to an operable status.
Transition Boiling - Transition boiling means the boiling regime between nucleate and film boiling.
Transition boiling is tts regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.
Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate i
Amendment No. J02 l l
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Unit 2 N
g Table 3.1.1 (Cont'd) 5 n;
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REOUIREMENT g
Minimum No.
Modes in which Number of of Operable Function Must be Instrument O
Instrument Trip Level Operable Channels-Action Channels Trip Function Setting Provided (1) y per Trip Refuel Startup Run by Design System (1)
(7) 27 m
2 High Water Level
<50 Gallons X(2)
X X
4 Instrument A
in Scram Discharge Channels Instrument Volume I
2 Turbine Condenser 123 in. Hg.
X 4 Instrument A or C Low Vacuum Vacuum Channels i
6 2
<3 X Normal Full X X
X 4 Instrument A
High Radiation Power Background Channels 4
<10% Valve X(6) 8 Instrument A
l 1
Isolation Valve Closure Channels Closure i
2 Turbine control 500<P<850 psig X(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels i
sure Between Fast Closure Solenoid and Disc Dump
)
Valve 4
Turbine Stop
<10% Valve X(4) 8 Instrument A or D Valve Closure Closure Channels t
i
Unit 2 PBAPS 1
NOTES FOR TABLE 3.1.1 i
1.
There shall be two operable or tripped trip systems for each function.
If the minimum number of operable sensor channels I
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 cidse 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.
Deleted.
4.
Bypassed when turbine first stage pressure is less than 220 psig or less than 30% of rated.
5.
IRM's are bypassed when APRM's are onseale 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.
i 9.
Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.
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Amendment No. 23,104 '
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Unit 2 TABLE 4.1.1 (Cont'd)
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2 REACTOR PROTECTION SYSTEM ( SCRA'M) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS
.E t
Group (2)
Functional Test Minimum Frequency (3{
i S
High Water Level in Scram A
Trip Channel and Alarm Every 1 month.
Discharge Instrument Volume Turbine Condenser Low Vacuum (6)
B2 Trip 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).
O Valve Closure 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).
Permissive Turbine Stop Valve Closure A
Trip Channel and Alarm Every 1 month (1).
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Unit 2
>g TABLE 4.1.2 (Cont'd.)
- s REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION b
MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS e
5 l;
E Instrument Channel Group (1)
Calibration (4)
Minimum Frequency (2) 6
<l.l Turbine Control Valve Fast A
Standard Pressure Source Once per operating Closure Oil Pressure Trip cycle.
Turbine Stop Valve Closure A
Note (5)
Note (5)
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PBAPS 3.1 BASES (Cont'd) the amount of water which must be accommodated during a scram.
During normal operation the discharge volume is empty; however, should it fill with water, the water discharged to i
the piping from the reactor could not be accommodated which would result in slow scram times or partial control rod
)
insertion.
To preclude this occurrence, level switches have been provided in the instrument volume which alarm and scram the reactor when the volume of water reaches 50 gallons.
As indicated above, there is sufficient volume in the piping to l
accommodate the scram without impairment of the scram times or amount of insertion of the control rods.
This function shuts the reactor down while sufficient volume remains to accommodate the discharged water and precludes the situation in which a scram would be required but not be able to perform its function adequately.
A source range monitor (SRM) system is also provided to supply additional neutron level information during start-up brut has no scram functions (reference paragraph 7.5.4 FSAR).
Thus, the IRM and APRM are required in the " Refuel" and
" Start / Hot Standby" modes.
In the power range the APRM system provides required protection (reference paragraph 7.5.7 FSAR).
Thus the IRM System is not required in the "Run" mode.
The APRM's cover only the power range.
The IRM's and APRM's provide adequate coverage in the start-up and intermediate range.
The high reactor pressure, high drywell pressure, reactor low water level and scram discharge volume high level scrams are
)
required for Startup and Run modes of plant operation.
They are, therefore, required to be operational for these modes of reactor operation.
The requirement to have the scram functions l'ndicated in
)
Table 3.1.1 operable in the Refuel' mode assures that shifting to the Refuel mode during reactor power operation does not diminish the protection provided by the reactor protection system.
The turbine condenser low vacuum scram is only required during power operation and must be bypassed to start up the unit.
The main condenser low vacuum trip is bypassed except t
in the run position of the mode switch.
Turbine stop valve closure occurs at 10% of valve closure.
Below 220 psig turbine first stage pressure (30% of rated),
j the scram signal due to turbine stop valve closure is j
bypassed because the flux and pressure scrams are adequate to j
protect the reactor.
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1
Unit 2 TABLE 3.2.A Ng INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION g-u a"
g: Minimum No.
of Operable Number of Instrument S Instrument Instrument Trip Level Setting Channels Provided Action Channels per By Design (2) g Trip System (1) 2 Main Steam Line j 200 Deg. F 4 Inst. Channels B
Leak Detection High Temperature 1
Reactor Cleanup
< 300% of Rated 2 Inst. Channels C
System High Flow Flow l
y 1
Reactor Cleanup 3 200 Deg. F.
1 Inst. Channels E
System High Temperature 2
Reactor Pressure f 600 psig 4 Inst. Channels F
(Feedwater Flush System Interlock) b
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PBAPS NOTES FOR IrABLE 3.2.A 1.
Whenevtr 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.
4 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, 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 l
and confirmed to be below 180 degree! F.
F.
Isolate Feedwater Flush System 3.
Instrument seccoint corresponds to 538 inches above vessel i
zero.
4.
Instrument setpoint corresponds to 378 inches above vessel zero.
" ' 5.
Two recuired for each steam line.
6.
These signals also start SEG S and initiate secondary containment isolation.
"l.
Only required in Run Mode (interlocked with
.tode 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.
Amendment No. 82, 104, 111. - - -..., - -. -.
PBAPS NOTES FOR TABLE 3.2.A (Continued) 9.
In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 250 degrees F for a period not to l
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 temperature so in the event of rapid increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.
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j TABLE 4.2.A ft J
j MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS g
Instrument Channel (5)
Instrument Fbnctlonal Test Calibration _Freguency Instrument Check
?
m S 1)
Reactor High Pressure (1)
Once/3 months None (Shutdown Cooling Permissive)
=.
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. 2)
Reactor Low-Low-Low (1) (3)
Once/ operating cycle once/ day Water Level (7) w i
P3)
Main Steam High Temp.
(1)(3)
Once/ operating cycle Once/ day m4)
Main Steam High Flow (7)
(1)(3)
Once/ operating cycle Once/ day
%5)
Main Steam Low Pressure (1)
Once/3 months None 6)
Once/3 months once/ day High Flow
)
7)
Once/3 months None High Temp.
B)
Reactor Pressure (Feedwater (1)(3)
Once/ operating cycle Once/ day i Flush Permissive)
I I
E Logic System Functional Test (4) (6)
Frequency l
1)
Main Steam Line Isolation Vvs.
Once/6 months Main Steam Line Drain Vvs.
Reactor Water Sample Vvs.
2)
RHR - Isolation Vv. Control-Once/6 months Shutdown Cooling Vvs.
Head Spray i
3)
Reactor Water Cleanup Isolation -
Once/6 months
~
4)
Drywell Isolation Vvs.
Once/6 months TIP Withdrawal Atmospheric Control Vvs.
Sump Dral'n Valves 5)
Standby Gas Treatment System Once/6 months Reactor Dullding Isolation
==
p KEC g UNITED STATES 8
fJUCLEAR REGULATORY COMMISSION o
- E WASHINGTON, D. C. 20555
\\...+/
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. DPR-56 1.
The Nuclear Regulatory Commission.(the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 17, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
--v-e
. Technical Specifications The Technical Specifications cuntained in Appendices A and B, as revised through Amendment No.121, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY L FilSSION fh))
-w Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14,1986 W.
O ATTACHMENT TO LICENSE AMENDMENT NO. 1 21 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 7
7 8
8 38 38 39 39 42 42 45 45 49 49 62 62 63 63 63a j
80 80 w,
t o.
PBAPS M.
1.0 DEFINITIONS (Cont'd) outage, the required surveillance testing need not be perscrmed
'until the next regularly scheduled outage.
Reportable Event - A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
Run Mode - In this mode the reactor system pressure is at or above 850 psig and the reactor protection system is energized with APRM protection (excluding.the 15% high flux trip) and RBM interlocks in service.
l Safety Limit - The safety limits are limits below which the reasonable maintenance of the cladding and primary systems are I
assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit operation.
Operation beyond such a limit may not in itself result in serious consequences, but it indicates an ope. rational deficiency subject to regulatory review.
i Secondary Containment Integrity - Secondary Containment integrity means that the reactor building is intact and the following conditions are met:
1.
At least one door in each access opening is closed.
2.
The standby gas treatment is operable.
3.
All Reactor Building ventilation system automatic isolat' ion valves are operable or deactivated in the' isolation position.
Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
}
l I
Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed.
Af ter a short time period (about 10 sec), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic system; also, the main steam line isolation scram and main condenser low vacuum scram are bypassed.
l
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Amendment No. 104, 113 *
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PBAPS 1.0 DEFINITIONS (Cont'd)
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the i
circuit in question.
I SITE BOUNDARY - That line beyond Which the land is not owned, leased or otherwise controlled by licensee.
4 Source Check - A source check shall be the qualitative assessment of channel response When the channel sensor is exposed to a radioactive source.
4I Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam line isolation valve closure are bypassed, the reactor protection l
system is energized with IRM neutron monitoring system trip, the APRM 15% high flux trip, and control rod withdrawal interlocks in service.
This is often referred to as just Startup Mode.
This is intended to imply the Startup/ Hot Standby position of the mode j
switch.
I Surveillance Frequency - Periodic surveillance tests, checks calibrations, and examinations shall be performed within the specified surveillance intervals.
The operating cycle interval as pertaining to instrument and electrical surveillance shall not j
exceed 18 months.
These specified time intervals may be exceeded by 25%.
In cases Where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall i
commence at the end of the original specified interval.
l Surveillance tests are not required on systems or parts of the i
systems that are not required to be operable or are tripped.
If l
tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system to an operable status.
Transition Boiling - Transition boiling means the boiling regime between nucleate and film boiling.
Transition boiling is the regime in Which both nucleate and film boiling occur intermittently with neither type being completely stable.
I Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate I
Amendment No.104 i
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?I Unit 3
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Table 3.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT 5
Minimum No.
Modes in which Number of of Operable Function Must be Instrument E$
Instrument Trip Level Operable Channels Action Channels Trip Function Setting Provided (1) per Trip )
Refuel Startup Run by Design System (1 (7) 0 co 2
High Water Level 150 Gallons X(2)
X X
4 Instrument A
in Scram Discharge Channels Instrument Volume 2
Turbine Condenser
>23 in. Hg.
X 4 Instrument A or C
,w Low Vacuum Vacuum Channels 2
Main Steam Line 13 X Normal Full X X
X(14) 4 Instrument A
High Radiation Power Background Channels 4
Main Steam Line 310% Valve X(6) 8 Instrument A
Isolation Valve Closure Channels Closure 2
Turbine Control 500<P<850 psig X(4) 4 Instrument A or D l
Valve Fast Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid i
and Disc Dump Valve 1
4 Turbine Stop 310% Valve X(4) 8 Instrument A or D Valve Closure Closure Channels
Unit 3 PBAPS NOTES FOR TABLE 3.1.1 l
1.
'ihere 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.
c 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 mede 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 close 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.
Deleted.
4.
Bypassed when turbine first stage pressure is less than 220 psig 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.
Amendment No. 33,108 ~r
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9 Unit 3 N
{
TABLE 4.1.1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS
.o E0 Group (2)
Fur.ctional Test Minimum Frequency (3)
High Water Level in Scram A
Trip Channel and Alarm Every 1 month.
Discharge Instrument Volume Turbine Condenser Low Vacuum (6)
B2 Trip Channel and Alarm (4)
Every 1 month (1).
Main Steam Line High Radiation 31 Trip Channel and Alarm (4)
Once/ week.
Main Steam Line Isolation A
Trip Channel and Alarm Every 1 month (1).
,g Valve Closure I
Turbine Control Valve A
Trip Channel and Alarm Every 1 month.
EHC OiJ Pressure Tnrhin s First. Stage Pressure A
Trip Channel and Alarm Every 3 months (1).
Permiesive Turbite Stop Valve Closure A
Trip Channel and Alarm Every 1 month (1).
D Unit 3 5
S TABLE 4.1.2 (Cun t ' d. )
5 T.EACTOR FROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION gy MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS El Instrument Channel Group (1)
Calibration (4)
Minimum Prequency (2)
Turbine Control Valve Fast A
Stanoard Pressure Source Once per optrating Closure Oil Pressure Trip cycle.
l Turbine Stop Valve Closure A
Note (5)
Note (5) 1 T
t f-
i.
PBAPS 1
3.1 BASES (Cont'd)
I the amount of water which must be accommodated during a 4
During normal operation the discharge volume is emptyr however, should it fill with water, the water discharged to the piping from the reactor could not be accommodated which would result in slow scram times or partial control rod insertion.
To preclude this occurrence, level switches have l
been provided in the instrument volume which alarm and scram I
l the reactor when the volume of water reaches 50 gallons.
As i
indicated above, there is sufficient volume in the piping to accommodate the scram without impairment of the scram times or amount of insertion of the control rods.
This function shuts the reactor down While sufficient volume remains to 1
accommodate the discharged water and precludes the situation j
in Which a scram would be required but not be able to perform its function adequately.
s A source range monitor (SRM) system is also provided to supply additional neutron level information during start-up but has no scram functions (reference paragraph 7.5.4 FSAR).
I Thus, the IRM and APRM are required in the " Refuel" and i
" Start / Hot Standby" modes.
In the power range the APRM system provides required protection (reference paragraph 7.5.7 FSAR).
Thus the IRM System is not required in the j
"Run" mode.
The APRM's cover only the power range.
The IRM's and APRM's provide adequate coverage in the start-up I
and intermediate range.
The high reactor pressure, high drywell pressure, reactor low water level and scram discharge volume high level scrams are required for Startup and Run modes of plant operation.
They are, therefore, required to be operational for these modes of reactor operation.
The requirement to have the scram functions indicated in Table 3.1.1 operable in the Refuel mode assures that shifting to the Refuel mode during reactor power operation does not diminish the protection provided by the reactor protection system.
The turbine condenser low vacuum scram is only required during power operation and must be bypassed to start up the unit.
The main condenser low vacuum trip is bypassed except in the run position of the mode switch.
Turbine stop valve closura occurs at 10% of valve closure.
I Below 220 psig turbine first stage pressure (30% of rated),
the scram signal due to turbine stop valve closure is 4
bypassed because the flux and pressure scrams are adequate to protect the reactor.
-49
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Unit 3 TABLE 3.2.A k
INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION n
W Minimum No.
u, P
of Operable Number of Instrument Instrument Instrument Trip Level Setting Channels Provided Action S
Channels per Trip System By Design (2)
(1) 2 Main Steam Line f 200 Deg. F Channels B
4 Inst.
Leak Detection High Temperature 1
Reactor Cleanup
< 300% of Rated 2 Inst. Channels C
,g System High Flow FTow i
1 Reactor Cleanup j 200 Deg. F.
1 Inst. Channels E
System High Temperature 2
Reactor Pressure
< 600 psig 4 Inst. Channels F
(Feedwater Flush System Interlock)
~. "
........ L'..
~
NOTES FOR 7ABLE 3.2.A 1
1.
Whenevtr 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.
Isolete 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, 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 degreef F.
F.
Isolate Feedwater Flush System
\\
3.
Instrument seteeint corresoonds to 538 inches above vessel zero.
4.
Instrument setpoint corresponds to 378 inches above vessel zero.
5.
Two recuired for each steam line.
6.
These signals also start SEG S and initiate secondary containment isolation.
7.
Only required in Run Mode (interlocked with
.tode Seitch).
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.
l Amendment No. 81, 108, 115 --
PBAPS NOTES FOR TABLE 3.2. A (Continued) 9.
In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may 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 temperature so in the event of rapid increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.
=
0 W
e e WE
-63a-l
^
~
TABLE 4.2.A h
r;-
MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS k
Instrument channel (5)
Instrument rbnet4onal Test Calibration Freguency Instrument Check k1)
Reactor Righ Pressure (1)
Once/3 months None g)
(Shutdown Cooling Permissive)
" * ~
2 Reactor Low-Low-Low (1) (3)
Once/ operating cycle Once/ day 2
,o Water Level D)
J)
Main Steam High Temp.
(1)(3?
Once/ operating cycle Once/ day
,m4)
Main Steam High Flow (7)
(1)(3J Once/ operating cycle Once/ day
_.5 )
Main Steam Low Pressure (1)
Once/3 months None p)
Once/3 months Once/ day High Flow 7)
Once/3 months None High Temp.
8)
Reactor Pressure (1)(3)
Once/ operating cycle Once/ day l Flush Permissive)(Feedwater t
E
_ Logic System Functional Test (4) (6)
Frequency i
1)
Main Steam Line Isolation Vvs.
Once/6 months Main Steam Line Drain Vvs.
Reactor Water Sample Yvs.
f 2)
RRR - Isolation Vv. Control-Once/6 months i
Shutdown Cooling Vvs.
Head Spray
?
3)
Reactor Water Cleanup Isolation -
Once/6 months 4)
Drywell Isolation Vvs.
Once/6 months TIP Withdrawal Atmospheric Control Vvs.
Sump Dral'n Valves 5)
Standby Gas Treatment System Once/6 months Reactor Building Isolation 9
- - - - - -