View source for BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint

{{Adams
| number = ML20062J335
| issue date = 10/19/1993
| title = Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint
| author name = 
| author affiliation = BOSTON EDISON CO.
| addressee name = 
| addressee affiliation = 
| docket = 05000293
| license number = 
| contact person = 
| document report number = BECO-93-132, NUDOCS 9311040017
| package number = ML20062J334
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS &amp; TEST REPORTS
| page count = 18
}}

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:l Attachment B to BEco Letter 93-132     i Amended Technical Specification Pages t
Paae 2
3 27 29 30 32 35                     ,
38 L
1 931104'A17 931019     E*
* PDR  ADOCK 05000293 P              PDR    k

1.0  DEFINITIONS'(Cont'd)
E. Operable - Operability A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when -it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that-all necessary attendant instrumentation, controls, normal and emergency.
electrical power sources, cooling or seal water lubrication or other :
auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
F. Operatina - Operating means that a system or component is performing its intended functions in its required manner.
G. Immediate - Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit-and the importance of the required action.
H. Reactor Power Operation - Reactor power operation is any operation with-the mode switch in the "Startup" or "Run" position with the reactor critical and above 1% design power.
I. Hot Standby Condition - Hot standby condition means operation with-coolant temperature greater than 212 F,0 system pressure ~1ess than 600' psig, the main steam isolation valves closed;and the mode switch in~
startup.
J. Cold Condition - Reactor coolant temperature equal to or less than 212 F.
K. Mode - The reactor Mode is that which is established by the mode selector-switch. The modes include shutdown, refuel, startup and run which are defined as follows:
: 1.      Startun Mode - In this mode the reactor protectio 7 scram trip, initiated by main steam line isolation Amendment No. -64 ,                                                           2-
_ _ _ _ _ _ ~

1.0 DEFINITIONS (Cont'd) valve closure, is bypassed when reactor pressure is less than          .
.                        600 psig, the low pressure main steam line isolation valve closure trip is. bypassed, the reactor protection system is            '
energized with IRM neutron monitoring system trips and control       '
rod withdrawal interlocks in service.
: 2. Run tioA - In this mode the reactor system pressure-is at or           ,
above 880 psig and the reactor protection.. system is' energized with APRM protection and RBM interlocks in service.                    ;
: 3. Shutdown Mode - The reactor is in the shutdown mode when the-reactor mode switch is in the shutdown mode position and no core alterations are being performed,
: a. Hot Shutdown means conditions as above-with reactor coolant temperature greater than 212 F.                         ;
: b. Cold Shutdown means conditions as above with reactor coolant temperature equal to or less than 212 F.                l
                                                                                                }
: 4. Refuel Mode - The reactor is in the refuel mode when the mode switch is in the refuel mode position. When the mode switch is         j in the refuel position, the refueling interlocks are in service.                                                               ;
L. Resian Power - Design power means a steady-state power level of 1998 thermal megawatts.
1 M. Primary Containment intearity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all         '
of the following conditions are satisfied:
: 1. All manual containment isolation valves on lines connected to the reactor coolant system or containment which. are not required to be'open during accident conditions are closed.
: 2. At least one door in each airlock is closed and sealed.                7
: 3. All blind flanges and manways are closed.
: 4. All automatic primary containment isolation valves are operable        !
or at least one containment isolation valve in'each line having        #
an inoperable valve shall be deactivated in the isolated               i condition.                                                             +
: 5. All containment isolation check valves are operable or at least        i one containment valve in each line having an inoperable valve is secured in the isolated position.
N. Secondary Containment Intearity - Secondary containment integrity means that the reactor building is intact and the following conditions are met:
F Amendment No. 113                                                               3.
                                                                                             .g r

PNPS Table 3.1.1            REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION RE0VIREMEWT                                       -
Operable Inst.                                                                                 Modes in Which Function                 !
Channels per                 Trip Function                    Trip Level Setting                     Must Be Operable                    V. son (I)
Refuel (7) Startup/ Hot
              ' Trio System (1)                                                                                                                Run MinimumlAvail.                                                                                                          Standby 1          1          Mode Switch in Shutdown                                                     X                     X        X            A     ,
1          1          Manual Scram                                                               X                      X        X            A IRM 3          4             High Flux-                        s120/125 of full scale                 X                     X        (5)          A 3          4             Inoperative                                                              X                     X        (5)          A APRM 2          3             High Flux                                      (15)                      (17)                  (17)     X       A or B 2          3             Inoperative                                    (13)                      X                     X(9)     X       A or B
            -2            3             High Flux (15%)                   sl5% of Design Power                   X                     X        (16)    A or B 2          2          High Reactor Pressure                s1085 psig                             X(10)                 X        X            A-2          2          High Drywell Pressure                s2.5 psig                              X(8)                  X(8)     X            A 2          2          Reactor Low Water Level              a9 In. Indicated Level                 X                     X        X            A SDIV High Water Level:               s39 Gallons                            X(2)                  X        X            A         l 2          2          East
             .2           2          West 2          2          Main Steam Line High                 s7X Normal Full Power Radiation                             Background (18)                       X                     X        X(18)   A or C 4          4         ' Main Steam Line
                                    -Isolation Valve Closure s10% Valve Closure                                X(3)(6)                 X(3)(6)  X(6)    A or C 2          2          Turbine Control Valve                a150 psig' Control 0il.
Fast Closure                          Pressure at Acceleration Relay                   X(4)                   X(4)     X(4)    A or D 4          4          Turbine Stop Valve                   s10% Valve Closure                    X(4)                   X(4)     X(4)    A or D '
Closure
              ' Amendment No. 15r-42,-86r-927 -117, 133, 147                                                                                                27
. - _ _ _ _ _       _  _    _ _ - -       _ .    . - . . . - , .   ..- ..             - . - . . - - . - . .-.    . . . . - . ~ . . -

c                                                                                 .q
 +
NOTES FOR-TABLE 3.1.1-(Cont'd)
: 2. Permissible to bypass, with control rod block, for reactor protection             )
.        system reset in refuel and shutdown positions of the reactor mode switch.        ]
: 3. Permissible to bypass when reactor pressure is <600 psig.                .
: 4. Permissible' to bypass when turbine first stage pressure is less than -112. l     :
psig.                                                           .
: 5. IRM's are bypassed when APRM's are onscale and the reactor mode switch is     -l in the run position.
: 6. The design permits closure of any two lines without a scram being initiated.
: 7. When the reactor is subcritical, fuel is in the reactor vessel and the reactor water temperature is less than 212 F, only the following trip            i functions need to be operable:                                                   l A. Mode switch in shutdown                                               1 B. Manual scram                                                            .
C. High flux IRM                                                           {
: 0. Scram discharge volume high level                                       ;
E. APRM (15%) high flux scram                                              i i
: 8. Not required to be operable when primary containment integrity is not-         'l required.                                   .
i
: 9. Not required while performing low power physics tests at atmospheric              ,
pressure during or after refueling at power levels not to exceed 5 MW(t).
: 10. Not required to be operable when the reactor pressure vessel head is not         !
bolted to the vessel.                                                            ,
: 11. Deleted                                                                          j
: 12. Deleted                                                                          t
: 13. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 50% nf the normal complement of LPRM's to       )
an APRM.                                                                         i
: 14. Deleted
: 15. TL APRM high flux trip level setting shall be' as specified in the CORE          :
OPERATING LIMITS REPORT, but shall in no case exceed 120% of rated thermal      !
power.                                        .
: 16. The APRM (15%) high flux scram is bypassed when in the run mode.
: 17. The APRM flow biased high flux scram is' bypassed when in.the refuel or          ;
startup/ hot standby modes.                                                    1
: 18. Within 24 hours prior to the planned start of hydrogen injection with the.       !
reactor power at greater than 20% rated power, the normal full . power         .i radiation background level and associated trip setpoints may be changed          I based on a calculated value of the radiation level expected during the           j injection of hydrogen.      The background radiation level and associated        i trip setpoints may be adjusted based on either calculations or                   i measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip           i setpoints shall be set within 24 hours of re-establishing normal radiation      i levels after completion of hydrogen injection and prior to withdrawing          !
control rods at reactor power levels below 20% rated power.
t Amendment No. 6, 15, 27, 42, 86, 117, 118,.133, 147                            29   l

TABLE 4.1.1                                                     -
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION FUNCT20NAL' TESTS MINIMUM FUNCTIONAL TEST FRE0VENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCUITS Functional Test Minimum Freauency (31 Mode Switch in Shutdown                                             Place Mode Switch in Shutdown             Each Refueling Outage Manual Scram                                                        Trip Channel and Alarm                    Every 3 Months RPS Channel Test Switch (5)                                        Trip Channel and Alarm                     Once per week IRM High Flux                                                      Trip Channel and Alarm (4)                 Once Per Week During Refueling and Before Each Startup Inoperative                                                   Trip Channel and Alarm                     Once Per Week During Refueling and Before Each Startup APRM High Flux                                                      Trip Output Relays (4)                     Every 3 Months (7)
Inoperative                                                    Trip Output Relays (4)                     Every 3 Months Flow Bias                                                      Trip Output Relays (4)                     Every 3 Months High Flux (15%)                                                 Trip Output Relays (4)                     Once Per Week During Refueling and Before Each Startup High Reactor Pressure                                              Trip Channel and Alarm (4)                 Every 3 Months High Drywell-Pressure                                             . Trip Channel and Alarm (4)                Every 3 Months Reactor low Water Level                                            Trip Channel and Alarm (4)                 Every 3 Months High Water Level in Scram Discharge Tanks                          Trip Channel and Alarm (4)                 Every 3 Months i
Main Steam Line High Radiation                                     Trip Channel and Alarm (4)                 Every 3 Months Main Steam Line Isolation Valve Closure                            Trip Channel.and Alarm                     Every 3 Months Turbine Control Valve Fast Closure.                                Trip Channel and Alarm                     Every 3 Months
   . Turbine First Stage Pressure Permissive                          . Trip Channel and Alarm (4)                Every 3 Months Turbine Stop Valve Closure                                         Trip Channel and Alarm                     Every 3 Months Reactor Pressure Permissive                                        Trip' Channel and Alarm (4)                Every 3 Months Amendment No. 79;-99; 117, 147                                                                                                        30
       -_. _ ~ . _   ..    . - . . _ . . . . . _     _    . . _      . _ . _ . . _ _       . _ . _ . . _ _    . _ . _   _. __    - _ . . _     _ . ~ . . . .

TABLE 4.1.2 REACTOR PR01ECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FRE0VENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel                                          Calibration Test (5)                  Minimum Freauency (2)          ,
    .IRM High Flux                                                                  Comparison to APRM on Controlled      Note (4)
Shutdowns Full Calibration                     Once/ Operating Cycle APRM High Flux                                                                                                                                       ,
Once'every 3 Days-Output Signal                                                            Heat Balance Flow Bias Signal                                                         Calibrate Flow Comparator and         Each Refueling Outage Flow Bias Network Calibrate Flow Bias Signal (1)        Every 3 Months LPRM Signal                                                                    TIP System Traverse                   Every 1000 Effective Full Power Hours High Reactor Pressure                                                          Note (7)                              Note (7)
High Drywell _ Pressure                                                        Note (7)                              Note (7)                        t Reactor Low Water Level                                                        Note.(7)                              Note (7)
High Water level in Scram Discharge Tanks                                      Note (7)                              Note (7)
Main Steam Line Isolation Valve Closure                                        Note (6)                              Note (6)
Main Steam Line'High Radiation                                                 Standard Current Source (3)           Every 3 Months
    , Turbine-First Stage Pressure Permissive                                       Note (7)                              Note (7)
Turbine' Control Valve Fast Closure                                            Standard Pressure Source              Every 3 Honths Turbine Stop Valve' Closure                                                 -Note (6)                                Note (6)
Reactor Pressure Permissive-                                                   Note (7)'                             Note (7) 32 Amendment No. 79, 147,

3.1 BASES (Cont'd) i i
     .        The requirement that the IRM's be inserted in the' core when the APRM's read 2.5 indicated on the scale assures there is proper overlap in the neutron monitoring systems and thus, sufficient coverage is provided for all ranges of reactor operation.                                                              !
The provision of an APRM scram at 115% design power in the Refuel and Startup/ Hot Standby modes and the backup IRM scram at 1120/125 of full scale assures there is proper overlap in the Neutron Monitoring Systems and thus, sufficient coverage is provided for all ranges of reactor operation.                                                                                    j The APRM's cover the Refuel and Startup/ Hot Standby modes with the APRM                      l 15% scram, and the power range with the flow-biased rod block and scram.                      :
The IRM's provide additional protection in the Refuel and Startup/ Hot Standby modes. Thus, the IRM and APRM 15% scram are required in the Refuel and Startup/ Hot Standby modes. In the power range, the APRM system provides the required protection (Reference FSAR Section 7.5.7).                       !
Thus, the IRM system is not required in the Run mode.
The high reactor pressure, high drywell pressure, reactor low water level, and scram discharge volume high level scrams are required for                          i Startup/ Hot Standby and Run modes of plant operation. They are, therefore, required to be operational for these modes of reactor operation.                                                                                    i The requirement to have the scram functions, as indicated in Table 3.1.1,                     !
operable in the Refuel mode is to assure shifting to the Refuel mode during reactor power operation does not diminish the capability of the                        .
reactor protection system.
i Below 176 psig (analytical limit) turbine first-stage pressure (45% of rated core thermal power for the most limiting balance-of-plant configuration), the scram signals due to turbine stop valve closure or                        ;
fast closure of turbine control valves are bypassed because flux and                          i pressure scram are adequate to protect the reactor. If the scram                             i signal due to turbine stop valve closure or fast closure of turbine                           !
control valves is bypassed at lower powers, less conservative MCPR and MAPLHGR operating limits may be applied as specified in the CORE                              i OPERATING LIMITS REPORT.                                                                    'l Average Power Range Monitor (APRM)
APRM's #1 and #3 operate contacts in one subchannel and APRM's #2 and #3                      ,
operate contacts in the other subchannel. APRM's #4, #5, and #6 are arranged similarly in the other protection trip system. -Each protection trip system has one more APRM than is necessary to meet the minimum number 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.
Amendment No. 79, 147                                                       35 I
                                                                                                          .1

3.1 BASES (Cont'd) remains well above the safety limit MCPR in all cases,.and system          _
l
  -      pressure does not reach the safety valve settings.. The scram setting is approximately 15 inches below the normal operating range and is thus                        i sufficient to avoid spurious scrams.
Iurbine Stop_yalve Closure The turbine stop valve closure scram anticipates the pressure, neutron                     _
flux, and heat flux increase that could result from rapid closure ~ of the                  i turbine stop valves. With a scram trip setting'of < 10 percent of valve closure from full open, the resultant increase in surface heat flux is                      -
limited such that MCPR remains above the safety limit MCPR even.during the worst case transient that assumes the turbine bypass is closed.                         ,
Turbine Control Valve Fast Closure                                                          l The turbine control valve fast closure scram anticipates the pressure,                      '
neutron flux, and heat flux increase that could result from fast closure -
of the turbine control valves due to load rejection exceeding the capability of the bypass valves. The reactor protection system initiates                    :
a scram when fast closure of the control valves is initiated by the                         .
acceleration relay. This setting and the fact that control valve closure                    ;
time is approximately twice as long as that for the stop valves means that resulting transients, while similar, are less severe than for stop valve closure. MCPR remains above the safety limit MCPR.
I Main Steam Line Isolation Valve Closure The low pressure isolation of the main steam lines at 880 psig (as-specified in Table 3.2.A) was provided to protect against rapid reactor depressurization and the resulting rapid cooldown of the vessel.
Advantage is taken of the scram feature that occurs when the main steam line isolation valves are closed, to provide for reactor shutdown so that -
high power operation'at low reactor' pressure does not occur, thus providing protection for'the fuel cladding integrity. safety limit.
Operation of the reactor at pressures lower than 785 psig requires the reactor mode switch be in the startup position where protection of the fuel cladding integrity safety limit is provided by the IRM high neutron'                   ,
flux scram and APRM 15% scram. Thus, the combination of main steam line                  .
low pressure isolation and isolation valve closure scram assures the availability of neutron flux scram protection over the entire i
0 e
u Amendment No. 6, 79, 99, 133, 147                                          38 E                                                                                       . _ . _ _ _

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Attachment C to BEco Letter 93-132 i-i                 Marked-up Technical Specification Pages i
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                       ~
1.0 DETINITIONS (Cont'd)                                                           >
-s E. Operable - Operability                                                        ,
        /
e       A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functi,o n(s).
          '          Implicit in this definition shell be the assu=ption that all necessary
             /       attendant instrumentation, controls, normal and . emergency electrical t
4       power sources, cooling or seal water, lubrication or other auxiliary
        '    g       equipment that are required for the system, subsystem, train, component         :
        /    )       or device to perfons its function (s) are also capable of performing their
             /       related support function (s).
F. Operatint - Operating means that s' system er component is perforn-    ,     ,
ing its intended functions in its required manner.
G,    Immediate - Immediate means that the required action will be ini-tiated as soon as practicable considering the safe operation cf the unit and the importance of the required action.
B. Reactor power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 12 design power.                   -
: 1. Hot Standby Condition - Hot standby condition means operation with 0
                     - coolant temperature greater than 212 F, system pressure less than 600 psis, the main steam isolation valves closed and the mode svitch in startup.
J. Cold condition - Reictor coolant temperature equal to or less than 212 T.
* K. Mode - The reactor mode is that which is established by the mode-selector-svitch. The modes include shutdown, refuel, startup and; run which are defined as follows:
: 1. Startup Mode - In this mode the reactor protection scram trip.
initiated by % e:: ]                   main steam line isolation a
   ~
AmendmentNo.//
2

I!
l'. 0 REFINITIONS (Cont'd)             4 i
_.                  valve closure, m bypassed when reactor pressure is less than                    i 600 psig, the ow pressure main steam line isolation valve closure trip is bypassed, the eactor protection system is energized with IRM neutron monitoring system trips and control rod withdrawai interlocks in service.                                       fi i,
: 2. Run Motfg - In this mode the reactor system pressure is at or               j above 880 psig and the reactor protection system is energized               i.
with APRM protection and RBH interlocks in service.
: 3. Shut @wn Mode - The reactor is in the shutdown mode when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
: a. Hot Shutdown means conditions as above with reactor                  '
coolant temperature greater than 212*F.
: b. Cold Shutdown means conditions as above with reactor coolant temperature equal to or less than 212*F.
: 4. Refuel Mode - The reactor is in the refuel mode when the mode switch is in the refuel mode pmition. When the mode switch is in the refuel position, the refueling interlocks are in service.
L. Resion Power - Design power means a steady-state power level of 1998 thermal megawatts.
M. Etimary Containment Intrarity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all         '
of the following conditions are satisfied:                                       7
: 1. All manual containment isolation valves on lines connected to the reactor coolant system or containment which are not required to be open during accident conditions are closed.
: 2. At least one door in each airlock is closed and sealed.
: 3. All blind flanges and manways are closed.                            -
                                                                                       /
: 4. All automatic primary containment isolation valves are operable d
or at least one containment i mlation valve in each line having an inoperable valve shall be deactivated in the isolated condition.
: 5. All containment isolation check valves are operable or at least  /'
one containment valve in each line having an inoperable valve    '
is secured in the isolated position.
N. SemnAry_fontainment Intearity - Secondary containment integrity                       '
means that the reactor building is intact and the following conditions are met:
bi sicriM-                                                                                 t Amen men    o. T/                                                          3                   ,
j l'    '
i

n PNPS Table 3.1.1     REACTOR PROTECTION     ~
FEM (SCRAM) INSTRUMENTATION REQUIREMENT.               '
Operable Inst.                                                          Modes in Ubich Function Channels per            Trip Function           Trip Level Setting             Must Be Operable           Action (I)
Trio System (1)                                                          Refuel (7) Startup/ Hot Run                         .
MinimumlAvail.                                                                          Standby                                   ,
1             1    Mode Switch in Shutdown                                   X          X          X            A 1             1    Manual Scram                                              X          X          X            A               //
IRM                                                                                                  /
3             4      High Flux              s120/125 of full scale           X          X          (5)          A               fy 3             4      Inoperative                                             X          X          (5)          A               ',,
APRM                                                                                                     /
                                                                                                                                 ' <j h
2             3      High Flux                          (15)                 (17)       (17)       X       A or B           #
2            '3      Inoperative                        (13)                 X          X(9)       X       A or B                   /
2             3      High Flux (15%)         sl5% of Design Power            X          X          (16)    A or B            /       .
                                                                                                                                /V
: 2.            2    High Reactor Pressure    s1085 psig                       X(10)      X          X            A
                                                                                                                                /       !
2             2-   High Drywell Pressure     s2.5 psig                       X(8)       X(8)       X            A           ,  /1 s
29 In, Indicated Level
                                                                                                                                'j 2             2    Reactor Low Water Level                                   X          X          X            A
                                                                                                                                /
<                      SDIV High Water Level:    s39 Gallons                     X(2)       X          X            A 2             2    East                                                                                                     ('
   .2             2    West
[/   ,
  'h             h    T4ah-4;endenser-Low 4
                      #acwa_.                  @n.HgVacup
                                                               =-
Q# h@                                 /g 2'            2    Main Steam Line High      s7X Normal Full Power                                                              f Radiation                  Background (18)                X          X          X(18)   A or C        -
                                                                                                                               '/ ,
                                                                                                                               /
4             4    Main Steam Line                                                                                         ,e';
Isolation Valve Closure s10% Valve Closure              X(3)(6)      X(3)(6)    X(6)    A or C                 '
2'            2    Turbine Control Valve    al50 psig Control Oil                                                          /)-
Fast Closure               Pressure at                                                                  /
y,'
Acceleration Relay             X(4)       X(4)       X(4). A or D
                 .4   -Turbine Stop Valve       s10% Valve Closure               X(4)                          A or D          !-
4                                                                                       X(4)       X(4)
Closure
       ,endmentI 15 85 -921-117, 133, 7    1    1                                                                                   27

     ._     -NOTES FOR' TABLE 3.1.1 (Cont'd)
: 2. Permissible to bypass, with control rod block, for reactor protection system             i reset in refuel and shutdown positions of the reactor mode switch.                //g,
                                                                                                           ~
: 3. Permissible to bypass when reactor pressure is <600 psig.
: 4. Permissible to bypass when turbine first stage pressure is less than          psig.      ;
: 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, fuel is in the reactor vessel and the reactor water temperature is less than 212 F, only the following trip functions need to be operable:
f A. Mode switch in shutdown B. Manual scram C. High flux IRM D. Scram discharge volume high level E. APRM (15%) high flux scram
: 8. Not required to be operable when primary containment integrity is not required.          !
: 9. Not required while performing low power physics tests at atmospheric pressure            '
during or after refueling at power levels not to exceed 5 MW(t).                         ,
: 10. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.
: 11. Deleted
: 12. Deleted
: 13. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 50% of the normal complement of LPRM's to an APRM.
: 14. Deleted
: 15. The APRM high flux trip level setting shall be as specified in the CORE '
OPERATING LIMITS REPORT, but shall in no case exceed 120% of rated thermal power.
: 16. The APRM (15%) high flux scram is bypassed when in the run mode.
: 17. The APRM flow biased high flux scram is bypassed when in the refuel or startup/ hot standby modes.
: 18. Within 24 hours prior to the planned start of hydrogen injection with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a                 ;
calculated value of the radiation level expected during the injection of hydrogen.      The background radiation level and associated trip setpoints may be adjusted based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be              ,
determined and associated trip setpoir,ts shall be set within 24 hours of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to withdrawing control rods at reactor power levels below 20% rated power.
L
    , ,     em               wV Q*stDft-ND     . __w
~
Amendment No. 6, 15, 27, 42, 86, 117, 118, 133,                                 29 l

m
[O Ar                              REACTOR PROTECTION TF SYSTEMFUNCTIONAL' J INSTRUMENTATION (SCL[14.1.1 TESTS -
s.
                                                                                                                                                                              /
MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCUITS Functional Test                                      Minimum Frequency (3)-
Mode Switch in Shutdown                                            Place Mode Switch in Shutdown                         Each Refueling Outage Manual Scram                                                       Trip Channel and Alarm                                Every 3 Months RPS Channel Test Switch (5)                                       Trip Channel and Alarm                                 Once per week IRM High Flux                                                      Trip Channel and Alarm (4)                             Once Per Week During Refueling and Before Each Startup Inoperative                                                    Trip Channel and Alarm                                 Once Per Week.During Refueling-and Before Each Startup APRM High Flux                                                      Trip Output Relays (4)                                 Every 3 Months (7)
Inoperative                                                    Trip Output Relays (4)                                 Every 3 Months Flow Bias                                                      Trip Output Relays (4)                                 Every 3-Months.                         ..
High Flux (15%)                                                Trip Output Relays (4)                                 Once Per Week During Refueling and Before Each Startup High Reactor Pressure                                             Trip Channel and Alarm (4)                             Every 3 Months High Drywell Pressure                                             Trip Channel and Alarm (4)                             Every 3 Months Reactor Low Water Level                                           Trip Channel and Alarm (4)                             Every 3 Months High Water Level in Scram Discharge Tanks                         Trip Channel and Alarm (4) -                           Every 3 Months
(.htrbine-Condenser                       Lew W                  d rip Channel and D                                    CEverdMonth?)$
Main Steam Lint Hign~Ka01ation                                    Trip Channel and Alarm-(4)                             Every 3 Montlis Main Steam Line Isolation Valve Closure                          Trip Channel and Alarm                                  Every 3 Months Turbine Control Valve Fast Closure                               Trip Channel and Alarm                                  Every 3 Months Turbine First Stage' Pressure Permissive                         Trip Channel and Alarm (4)                              Every 3 Months-Turbine-Stop Valve Closure                                       Trip Channel and Alarm                                  Every 3 Months?
Reactor'. Pressure Permissive                                   . Trip Channel and Alarm (4)                             Every 3 Months hAmendment i den %               {.
No. 79    -99, 117, 5                                                                                                                                 30 l
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TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel                                   Calibration Test (5)                      Minimum Frequenc_y (2) ' s IRM High Flux                                               Comparison to APRM on Controlled          Note (4)                       Y Shutdowns                                                             ,
Full Calibration                          Once/ Operating Cycle Output Signal Flow Bias Signal Heat Balance Calibrate Flow Comparator and Flow Bias Network Once every 3 Days Each Refueling Outage j
[!
Calibrate Flow Bias Signal (1)            Every 3 Months              /(
c   e LPRM Signal                                                 TIP System Traverse                       Every 1000 Effective Full Power Hours         / )
[
                                                                                                                                 / .
High Reactor Pressure                                       Note (7)                                  Note (7)                   j High Drywell Pressure                                       Note (7)                                  Note (7)                    q Reactor low Water Level                                     Note (7)                                  Note (7)
High Water Level in Scram Discharge Tanks                   Note (7)            -
Note (7)                        -
hr4>4nc Condenscr-4ew--Vacam-                              ht                                                                         .
Main Steam Line Isolation Valve Closure                     Note (6)                                  Note (6)                 f-i     '
Main Steam Line High Radiation                              Standard Current Source (3)               Every 3 Months           )        .
Turbine First Stage Pressure Permissive                    ' Note (7)                                 Note (7)                          :
Turbine Control Valve Fast Closure                          Standard Pressure Source                  Every 3 Months
                                                                                                                                 /
Turbine Stop Valve Closure                                  Note (6)                                  Note (6)               [
V Reactor Pressure Permissive                                 Note (7)                                  Note (7)               X hAmendment Isich Ko. M                                                                                                  32
              %R
* i I
a 3.1    BASES (Cont'd)
The requirement that the IRM's be inserted in the core when the APRM's                      el read 2.5 indicated on the scale assures there is proper overlap in the neutron monitoring systems and thus, sufficient coverage is provided for 4,
all ranges of reactor operation.                                                           '
rl The provision of an APRM scram at $15% design power in the Refuel and                            1 Startup/ Hot Standby modes and the backup IRM scram at $120/125 of full scale assures there is proper overlap in the Neutron Monitoring Systems                    ]     ,
and thus, sufficient coverage is provided for all ranps of reactor                           '
operation.                                                                                   7      -
The APRM's cove. Or Refuel and Startup/ Hot Standby modes with the APRM                         ,
15% scram, and the so wer range with the flow-biased rod block and scram.                    '
The IRM's provide additional protection in the Refuel and Startup/ Hot Standby modes. Thus, the IRM and APRM 15% scram are required in the
                                                                                                                 )   ;
(,
Refuel and Startup/ Hot Standby modes. In the power range, the APRM system ,                 '
provides the required protection (Reference FSAR Section 7.5.7).                  Thus,      -
the IRM system is not required in the Run mode.                                                 ,
The high reactor pressure, high drywell pressure, reactor low water level, ? '
and scram discharge volume high level scrams are required for Startup/ Hot Standby and Run modes of plant operation. They are, therefore, required-to be operational for these modes of reactor operation.
A v              The requirement to have the scram functions, as indicated in Table 3.1.1, operable in the Refuel mode is to assure shifting to the Refuel mode                       /
during reactor power operation does not diminish the capability of the                     /
reactor protection system.
                                                                                  ~                       f      ,
                -T he-tdrbine-conde n se r-l ow-va cuum-scw-am--is--only-req u i red-d u ri ng-power.      /
                -operat4an and must bs4ypassed te star 4up the unit.             Below-305- ps i g --      ,<
              . 4urbine4irst-stage-pressure 445Lo0-r-atedfThe scramTig'naEbue          n              to %           :
A turbine stop Tralve closure or fast closure of turbine control valvesh f.f                           l bypassed because flux and pressure scram are adequate to protect the                      /         ,
reactor. If the scram signal due to turbine stop valve closure or fast                     /'
closure of turbine control valves is bypassed at lower powers, less conservative MCPR and MAPLHGR operating limits may be applied as specified                 ,
in the CORE OPERATING LIMITS REPORT.                                                                '
Average Power Range Monitor (APRM)                                                         '
p APRM's #1 and #3 operate contacts in one subchannel and APRM's #2 and #3                   /
operate contacts in the other subchannel. APRM's #4, #5, and #6 are                        A arranged similarly in the other protection trip system. Each protection trip system has one more APRM than is necessary to meet the minimum number                           i 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.                                                                           r        ,
Y                                     - k /96 psi 7[M YN)&
Yb.      h       f&g'P""^'-[Mo f^*M                                             35 cmdwa.1my w)wn9 AA-~a-fp&d                                                                     'j

l l
1 3.1     PASES (Cor,t'd) 3 y
remains well above the safety limit MCPR in all cases, and system pressure does not reach the safety valve settings. The scram setting is                                     /
1 approximately 15 inches below the normal operating range and is thus sufficient to avoid spurious scrams.                                                                   '
Turbine Ston valve Closure The turbine stop valve closure scram anticipates the pressure, neutron                                N-flux, and turbine       heat stop     flux increase that could result from rapid closure of the valves.                                                                j                                :
With a scram trip setting of < 10 percent of valve           I                             ;
closure from full open, the resultant increase in surface heat flux is                        /
limited such that MCPR remains above the safety limit MCPR even during the worst case transient that assumes the turbine bypass is closed.                              /
Turbine Control Valve Fast Closure                                                             <
I              !
The turbine control valve fast closure scram anticipates the pressure,
                                                                   ~                                            V neutron flux, and heat flux increase that could result from fast closure of the turbine control valves due to load rejection exceeding the capability of the bypass valves. The reactor protection system initiates ' ,,                                  .
t a scram when acceleration          fast closure of the control valves is initiated by the relay.
I This setting and the fact that control valve closure - ''                                  -;
time is approximately twice as long as that for the stop valves means that'                                             j resulting transients, while similar, are less severe than for stop valve y closure.                                                                                                                   '
                             -MCPR remains above the safety limit MCPR.
                   ,                 ~               -
j Main Condenser t.ow Vacuum                        _
j y                        .
              -To-pr.otec t._the-mai n condenser againtt nvernentmro;        a inte nf enndontor vacuum initiates bg us-veh e'..        automatic    closure   of the turMne4 top - valves and- turbine' Tc -anH+4pate the trans4ent.-and-2utnmatir fm the thwee-ef-the-turbhe-stg valvcs, low-sondenser vacuumccram resulting-                       '
                                                                                                                                   - i1
              -iniMete'. a scram The kw-vacuum-ssram jetpo4ntas4 elected to init44te.                     '
i                         i w a-scram-batore the- closure of           the turbine 4 top-valves- is initiated,            r                         j '.
f C
N 14ain Stean Line Isolation Valve closure                                                     /
The low pressure isolation of the main steam lines at 880 psig (.as.                       /
specified in Table 3.2.A) was provided to protect against rapid reactor                                              '
depressurization and the resulting rapid cooldown of the vessel.                                                           !
Advantage is taken of the scram feature that occurs when the main steam                   7                                 ,
high power operation at low reactor pressure does no providing protection for the fuel cladding integrity safety' limit.
Operation of the reactor at pressures lower than 785 psig requires the                    f reactor mode switch be in the startup position where protection of the fuel cladding integrity safety limit is provided by the IRM high neutron flux scram and APRM 15% scram. Thus, the combination of main steam line               r low pressure isolation and isolation valve closure scram assures the                     r                                  :
availability of neutron flux scram protection over the entire r                                   i p"%~ --            -m        .
                                                                                                      /
M*J*4etEIiu.. _i@  .                                                                                                                  l Amendment No. 6,79,99,133.g47                                                          38     '                '
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