ML20077K350
| ML20077K350 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/29/1994 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077K352 | List: |
| References | |
| NUDOCS 9501100296 | |
| Download: ML20077K350 (13) | |
Text
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- 4atro UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066-0001 49.....,o WOLF CRFEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated February 23, 1994, 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, as amended, 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 license 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.
9501100296 941229 PDR ADOCK 05000482 P
sw
,. 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. NPF-42 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 82, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
l/
CA MAX)
James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 29, 1994 l
7 ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT XV XV 3/4 1-10 3/4 1-10 3/4 3-6 3/4 3-6 3/4 8-1 3/4 8-1 3/5 8-8 3/4 8-8 8 3/4 1-1 8 3/4 1-1
l-BASES SECTION PEE 3/4.0 APPLICABILITY...............................................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTR0L..........................................
B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS..........................................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................
B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS...................................
B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE.....................................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R.........................
B 3/4 2-1 3/4.2.4 QUADRANT POWER TILT RATI0.................................
B 3/4 2-2 3/4.2.5 DNB PARAMETERS............................................
B 3/4 2-3 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...............
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................
B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................
B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............
B 3/4 4-1 3/4.4.2 SAFETY VALVES.............................................
B 3/4 4-1 3/4.4.3 PRESSURIZER...............................................
B 3/4 4-2 3/4.4.4 RELIEF VALVES.............................................
B 3/4 4-2 WOLF CREEK - UNIT 1 XV Amendment No. 82
e.
BASES I
i i
SECTION PAGE I
i REACTOR COOLANT SYSTEM (Continued) t 3/4.4.5 STEAM GENERATORS..........................................
B 3/4 4-2 I
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE............................
B 3/4 4-4 j
3/4.4.7 CHEMISTRY.................................................
B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY.........................................
B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS...............................
B 3/4 4-6 TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS..........................
B 3/4 4-10
' FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF SERVICE LIFE (EFFECTIVE FULL POWER YEARS)......
B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY.....................................
B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS............................
B 3/4 4-16 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS..............................................
B 3/4 5-1 3/4.5.2, 3/4.5.3, and 3/4.5.4 ECCS SUBSYSTEMS.....................
B 3/4 5-1 3/4.5.5 REFUELING WATER STORAGE TANK..............................
B 3/4 5-2 l
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.......................................
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................
B 3/4 6-3 3/4.6.3, CONTAINMENT ISOLATION VALVES..............................
B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...................................
B 3/4 6-4 i
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I 1
WOLF CREEK - UNIT 1 XVI Amendment No. 40
REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 One centrifugal charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.
APPLICABILITY:
MODES 4, 5, and 6.
ACTION:
With no centrifugal charging pump OPERABLE or capable of being powered from an OPERABLE emergency pnwer source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.3.1 The above required centr'l;?al chargin0 pump shall be demonstrated OPERABLE by verifying, on recirculat.
flow, that the pump develops a dif-ferential pressure of greater than or <<aal to 2400 psid when tested pursuant to Specification 4.3.5.
4.1.2.3.2 All centrifugal charging pumps, excluding the above required OPERABLE pump, shall be demonstrated inoperable
- at least once per 31 days, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position.
- An inoperable pump may be energized for testing or for fijling accumulators provided the discharge of the pump has been isolated from the RCS by a closed isolation valve with power removed from the valve operator, or by a manual isolation valve secured in the closed position.
WOLF CREEK - UNIT 1 3/4 1-9
+
REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION i
3.1.2.4 At least two centrifugal charging pumps shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.*
ACTION:
With only one centrifugal charging pump OPERABLE, restore at least two centri-fugal charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1.3% ok/k at l
200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two centrifugal charging pumps shall be demonstrated OPERABLE by verifying, on recirculation flow, that the pump develops a differential pressure of greater than or equal to 2400 psid when tested pursuant to Specification 4.0.5.
l l
- The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 3 for the centrifugal charging pump declared inoperable pursuant to Specification 4.1.2.3.2 provided that the centrifugal charging pump is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs exceeding 375'F, whichever comes first.
WOLF CREEK - UNIT 1 3/4 1-10 Amendment No. 82
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TABLE 3.3-1 (Continued)
TABLE NOTATIONS
- 0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
- The boron dilution flux doubling signal any be blocked during reactor startup in accordance with normal operating procedures.
- The provisions of Specification 3.0.4 are not applicable.
MBelow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
N#Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1)The applicable MODES for these channels noted in Table 3.3-3 are more restrictive and therefore applicable.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel
~
to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1; and c.
Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
a.
Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or b.
Above the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.
ACTION 4 - With the number of OPERABLE channels one less than the Minimum Chanr.els OPERABLE requirement suspend all operations involving positive reactivity changes.
WOLF CREEK - UNIT 1 3/4 3-5 Amendment No. 12, 43 n
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TABLE 3.3-1 (Continued)
I ACTION STATEMENTS (Continued)
ACTION 5 - a.
With the number of OPERABLE channels one less than the Minimum l
Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes and verify valves BG-V178 and BG-V601 are closed and secured in position within the next hour.
b.
With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes and verify compliance with the $HUTDOWN MARGIN requirements of I
Specification 3.1.1.1 within I hour and every 12-hours l
thereafter, and verify valves BG-V178 and BG-V601 are closed and secured in position within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and verified to be closed and secured in position every 14 days.
ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.
ACTION 7 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is operable.
ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 9 - With the number of OPERABLE Reactor Trip Breakers one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one breaker may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provitied the other breaker is OPERABLE.
ACTION 10- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
ACTION 11-With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
WOLF CREEK - UNIT 1 3/4 3-6 Amendment No. 12,25,42,82 l
m 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES t
OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
Two physically independent circuits between the offsite transmission network and the Onsite Class IE Distribution System, and b.
Two separate and independent diesel generators, each with:
1)
A separate day tank containing a minimum volume of 510 gallons l
of fuel, 2)
A separate Fuel Oil Storage System containing a minimum volume of 85,300 gallons of fuel, and 3)
A separate fuel transfer pump.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With an offsite circuit of the above required A.C. electrical power a.
sources inoperable, demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Specification 4.8.1.1.1 within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
If either diesel generator of the above required A.C. electrical power sources has not been successfully tested within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, demonstrate OPERABILITY by performing Specification 4.8.1.1.2a.4* separately for that diesel generator within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the offsite A.C.
sources by performing Specification 4.8.1.1.1 within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Specification 4.8.1.1.2a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> **; restore the inoperable diesel generator to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- The automatic start and sequence loading of a diesel generator satisfies the testing requirements of Specification 4.8.1.1.2a.4 for this Action Statement.
- This test is required to be completed regardless of when the inoperable diesel generator is restored to OPERABLE status unless the diesel was declared inoperable to do preplanned preventative maintenance, testing, or maintenance to correct a condition which, if left uncorrected, would not affect the operability of the diesel generator.
WOLF CREEK - UNIT 1 3/4 8-1 Amendment No. 8, 82
.s.
ELECTRICAL POWER SYSTEMS-l A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and the Onsite Class IE Distribution System, and b.
One diesel generator with:
1)
A day tank containing a minimum volume of 510 gallons of fuel, l
2)
A fuel storage system containing a minimum volume of 85,300 gallons of fuel, and 3)
A fuel transfer pump.
i APPLICABILITY: MODES 5 and 6.
ACTION:
I I
With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel, or crane operation with loads over the spent fuel pool.
In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.
SURVEILLANCE RE0VIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1, 4.8.1.1.2 (except for Specification 4.8.1.1.2a.5)), and 4.8.1.1.3.
WOLF CREEK - UNIT 1 3/4 8-8 Amendment No. 8,82
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 SHUTDOWN MARGIN l
A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of The most restrictive fuel depletion, RCS baron concentration, and RCS Tat no load operaYIn.g temperature condition occurs at E0L, with T,y, associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.3% Ak/k is required to control the reactivity transient. Accord-ingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition With T,y less than and is consistent with FSAR safety analysis assumptions.
200*F, the reactivity transients resulting from a postulated steam, line break cooldown are minimal and a 1.3% Ak/k SHUTDOWN MARGIN provides adequate protection.
3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of HTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.
l WOLF CREEK - UNIT I B 3/4 1-1 Amendment No. R,82
t REACTIVITY CONTROL SYSTDIS BASES MODERATOR TEMPERATURE COEFFICIENT (Continued)
The most negative MTC value equivalent to the most positive moderator density coefficient (MC), was obtained by incrementally correcting the MC used in the FSAR analyses to nominal operating conditions. These corrections involved subtracting the incremental change in the MC associated with a core condition of all rods inserted (most positive MC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL p0WER conditions. This value of the MC was then transformed into the limiting MTC End of Life (E0L) value specified in the CORE OPERATING LIMITS REPORT (COLR). The 300 ppa surveillance limit NTC value specified in the COLR represents a conservative value (with corrections for 1
burnup and soluble boron) at a core condition of 300 ppe equilibrium boron concentration and is obtained by making these corrections to the limiting E0L i
MTC value specified in the COLR.
The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY
[
This specification ensures that the reactor will not be
.A critical I
with the Reactor Coolant System average temperature less than 551*F. This limitation is required to ensure: (1) the moderator temperature coefficient is within it analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its l
minimum RT, temperature.
3 /4.1. 2 BORATION SYSTEMS The Boration Systems ensures that negative reactivity control is
{
available during each mode of facility operation. The components required to perform this function include: (1 borated water sources (2) centrifugal charging pumps, (3) separate flow) paths, (4) boric acid transfer pumps, and (5) an emergency power supply from OPERA 8LE diesel generators.
l With the RCS average temperature equal to or greater than 350*F a minimum t
of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoper-able. The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1.3% Ak/k after xenon decay and cooldown to 200*F. The maximum expected boration capability require-ment occurs at E0L from full power equilibrium xenon conditions and requires 17,658 gallons of 7000 ppm borated water from the boric acid storage tanks or 83,754 gallons of 2400 ppm borated water from the RWST. With the RCS average temperature less than 350*, only one boron injection flow path is required.
i WOLF CREEK - UNIT 1 B 3/4 1-2 Amendment No. 27. 61 I
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