ML20033E197
| ML20033E197 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/21/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033E198 | List: |
| References | |
| NUDOCS 9003090336 | |
| Download: ML20033E197 (14) | |
Text
e7
('
?
UNITED STATES j', o, NUCLEAR REGULATORY COMMISSION n
.h ur k WASHINGTON, D C. 20565
\\.....}
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION i
DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) 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 November 30, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; H
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 Comission's regulations; D.
The issuance of this license amendment will net 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 Comission's regulations and all applicable requirements have been satisfied.
9003090336 900221 PDR ADOCK 05000402 P
PNV
I 2
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachnent 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 35, and the Environmental Protection Plan contained in Appendix D, 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.
FOR THE NUCLEAR REGULATORY COHitlSSION Frederick. Hebdon, Director Project Directorate IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 21, 1990
ATTACHMENT TO LICENSE AMENDMENT NO.35
~
FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the pages identified ig below and inserting the enclosed pages. The revised pages are identified by
- ]
amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 4-6 3/4 4-6 3/4 5-9 3/4 5-9 3/4 9-9 3/4 9-9 3/4 9-10 3/4 9-10 B 3/4 5-2 B 3/4 5-2 B 3/4 9-2 B 3/4 9-2 l
E-
e
]
l REACTOR 600LANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one residual heat removal (RHR)~ loop shall be OPERABLE and in operation *, and either:
I One additional RHR loop shall be OPERABLE #, or a.
b.
The secondary side water level of at least two steam generators I
shall be greater than 10% of the wide range.
APPLICABILITY:
MODE 5 with reactor coolant loops filledf#.
ACTION:
With one of the RHR loops inoperable and with less than the required a.
steam generator level, immediately initiate corrective action to i
return the inoperable RHR loop to OPERABLE status or restore the required steam generator level as soon as possible, b.
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation, SURVEILLANCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.4.1.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 0ne RHR loop may be inoperable 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 provided the other RHR loop is OPERABLE and in operation.
- A reactor coolant pump shall not be started unless the secondary water temperature of each steam generator is less than 50*F above each of the Reactor Coolant System cold leg temperatures.
- The RHR pump may be deenergized for up to I hour provided:
(1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.
e WOLF CREEK - UNIT 1 3/4 4-5
~
REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE # and at least one RHR loop shall be in operation.*
APPLICABILITY:
MODE 5 with Reactor Coolant loops not filled.
ACTION:
With less than the above required RHR loops OPERABLE, immediately a.
initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
b.
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
SURVEILLANCE REQUIREMENTS 4.4.1.4.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 0ne RHR loop may be inoperable 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 provided the other RHR loop is OPERABLE and in operation.
- The RHR pump may be deenergized for up to I hour provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, (2) core outlet temperature is maintained at least 10 F below saturation temperature, and (3) the reactor vessel water level is above the vessel, flange.
WOLF CREEK - UNIT 1 3/4 4-6 Amendment No. 35
EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 ECCS SUBSYSTEMS - T,yg < 200'F LIMITING CONDITION FOR OPERATION 3.5.4 All Safety Injection pumps shall be inoperable.
APPLICABILITY:
MODE 5 with the water level above the top of the Reactor Vessel flange, and MODE 6 with the Reactor Vessel head on and with the water level above the top of the Reactor Vessel flange.
ACTION:
l With a Safety Injection pump OPERABLE, restore all Safety Injection pumps to an inoperable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.4 All Safety Injection pumps shall be demonstrated inoperable
- by verifying that the motor circuit breakers are secured in the open position at least once per 31 days.
l l
- An inoperable cump may be energized for testing or for filling accumulators provided the oischarge at 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.
l WOLF CREEK - UNIT 1 3/4 5-9 Amendment No. 35
)
-EMERGENCY COR'E COOLING SYSTEMS-3/4.5.5 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with:
A minimum contained borated water vol me of 394.000 gallons, a.
b.
'A boron concentration of between 2400 and 2500 ppe of boron, A minimum solution temperature of 37'F and c.
d.
A maximum solution temperature of 100'F.
APPLICABILITY:
MODES 1, 2, 3, and 4.
i.
ACTION:
With the RWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least H0T 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 />.
SURVEILLANCE REQUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:
At least once per 7 days by:
a.
1)
Verifying the contained borated water volume in the tank, and 2)
Verifying the boron concentration of the water, b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is either less than 37'F or greater than 100'F.
WOLF CREEK - UNIT 1 3/4 5-10 Amendment No. 23
l 9
REFUELING OPERATIONS
- 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL I
LIMITING CONDITION FOR OPERATION i
3.9.8.1 At least one residual heat removal (RHR) loop shall be OPERABLE and in operation.*
APPLICABILITY: MODE 6 when the water level above the top of the reactor vessel flange is greater than or equal to 23 feet.
ACTION:
With no RHR loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentra-tion of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to OPERABLE and operating status as soon as possible.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.9.8.1 At least once per twelve hours, one RHR loop shall be verified.in operation and circulating coolant at a flow rate of:
a.
greater than or equal to 1000 gpm, and b.
sufficient to maintain the RCS temperature at less than or equal to 140*F.
- The RHR loop may be removed from operation for up to I hour per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.
WOLF CREEK - UNIT 1 3/4 9-9 Amendment No. 35
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be in operation."
j APPLICABILITY:
MODE 6 when the water level above the top of the reactor vessel flange is less than 23 feet.
7
,J ACTION:
With less than the required RHR loops OPERABLE, immediately initiate a.
corrective action to return the required RHR loops to OPERABLE a
status, or to establish greater than or equal to 23 feet of water above the reactor vessel flange, as soon as possible.
b.
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
i 4
SURVEILLANCE REQUIREMENTS i
4.9.8.2 At least once per twelve hours, one RHR loop shall be verified in operation and circulating coolant at a flow rate of:
a.
greater than or equal to 1000 gpm, and F
b.
sufficient to maintain the RCS temperature at less than or equal to 140'F.
i l
- Prior to initial criticality, the RHR loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 2-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.
-WOLF CREEK - UNIT 1 3/4 9-10 Amendment No.35 M
I 4
3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES
~
3/4.5.1 ACCUMULATORS The OPERABILITY of each Reactor Coolant System (RCS) accumulator ensures i
that a sufficient volume of borated water will be immediately forced into the core through each of the cold legs in the event the RCS pressure falls below
]
the 9tessure of the accumulators.
This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are j
met.
J The accumulator power operated isolation valves are considered to be
" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.
In addition, as these accumulator ir.olation valves fail to meet single failure criteria, removal of power to the valves is required.
The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.
If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.
3/4.5.2, 3/4.5.3, and 3/4.5.4 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.
In addition, each ECCS subsystem provides long-term core cooling capability in the recirculation mode during the accident recovery period.
With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
WOLF CREEK - UNIT 1 B 3/4 5-1
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirements to verify all charging pumps except the required OPERABLE charging pump to be inoperable in MODES 4 and 5 and in MODE 6 with the reactor vessel head on, provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV or RHR suction relief valve.
In addition, the requirement to verify all Safety Injection pumps to be inoperable in MODE 4, in MODE 5 with the water level above the top of the reactor vessel flange, and in MODE 6 with the reactor vessel head on and with water level above the top of the reactor vessel flange, provides assurance that the mass addition can be relieved by a single PORV or RHR suction reifef valve.
With the water level not above the top of the reactor vessel flange and with the vessel head on, Safety Injection pumps may be available to mitigate the affects of a loss of decay heat removal during a reduced RCS inventory condition.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA.
Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to; (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration.
(2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
The Surveillance Requirements for leakage testing of ECCS check valves ensures that a failure of one valve will not cause an intersystem LOCA.
The Surveillance Requirements to vent the ECCS pump casings and accessible, i.e., can be reached without personnel hazard or high radiation dose, discharge piping ensures against inoperable pumps caused by gas binding or water hammer in ECCS piping.
3/4.5.5 REFUELING WATER STORAGE TANK The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
The limits on RWST minimum volume and boron concentration ensure that: (1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes assuming all the control rods are out of the core.
These assumptions are consistent with the LOCA analyses.
WOLF CREEK - UNIT 1 B 3/4 5-2 Amendment No< 23, 35
.' EMERGENCY CORE COOLING SYSTEMS BASES l
REFUELING WATER STORAGE TANK (Continued)
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
i I
4 l
l WOLF CREEK - UNIT 1 B 3/4 5-3 Amendment No. 35
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION
)
The limitations on reactivity conditions during REFUELING ensure that:
i (1) the reactor will remain suberitical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
The limitation on Keff of no greater than 0.95 is sufficient to prevent reactor criticality during refueling operations.
The locking closed of the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portions of the Reactor Coolant System.
This action prevents flow to the RCS of unborated water by closing flow paths from sources of unborated water.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.
l 3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity j
condition of the core.
6 3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.
This decay time is consistent with the assumptions used in the safety analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be l
restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
The OPERABILITY of this system ensures the containment purge penetrations will be automatically isolated upon detection of high radiation levels within containment.
The OPERABILITY of this system is required to restrict the release of radioactive materials from the containment atmosphere to the environment.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling l
station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
WOLF CREEK - UNIT 1 B 3/4 9-1 l
BASES 3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine and auxiliary hoist ensure that: (1) manipulator cranes will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lif t a drive rod or fuel assembly, and (3) the core internals and reactor vessel 4
are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
{
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY 1
The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool areas ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.
This assumption is consistent with the activity release assumed in the safety analyses.
1 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.
The minimum of 1000 gpm allows flow rates which provide additional margin against vortexing at the RHR pump suction while in a reduced RCS inventory condition.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of RHR capability.
With the reactor vessel head removed and at least 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling.
- Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
3/4.9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment purge penetrations will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
WOLF CREEK - UNIT 1 B 3/4 9-2 Amendment No.35
.