ML20236U806
| ML20236U806 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/21/1998 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236U807 | List: |
| References | |
| NUDOCS 9807310088 | |
| Download: ML20236U806 (8) | |
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UNITED STATES I
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NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D.C. enmaam
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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 1
DOCKET NO. 50-482 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 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 March 24,1995, as supplemented by letters l
dated July 26,1995, and September 5,1996, complies with the standards and l
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 i
regulations; l
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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the l
Commission's regulations and all applicable requirements have been satisfied.
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9807310088 980721 PDR ADOCK 05000482 P
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2 Accordingly, the license is amended by changes to the Technical Specifications as J
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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
- 119, 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.
Also, Paragraph 2.C.(15) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
(15) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment
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No.119, are hereby incorporated into this license. Wolf Creek Nuclear Operating f
Corporation shall operate the facility in accordance with the Additional Conditions.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date ofissuance. Implementation of the license amendment shall include the relocation of certain technical specifications requirements to the appropriate licensee-controlled document as described in the licensee's application dated March 24 1995, as supplemented by letters dated July 26,1995, and September 5,1996, and evaluated in the staff's safety evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION l
1 W
Kristine M. Thomas, Project Manager i
Project Directorate IV-2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Attachments: 1. Changes to the Technical Specifications
- 2. Appendix D - Additional Conditions Date of issuance:
July 21,1998
Q ATTACHMENT TO LICENSE AMENDMENT NO.119
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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 3/4 5-1 3/4 5-1 3/4 5-2 3/4 5-2 B 3/4 5-1 B 3/4 5-1 i
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3/4,5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System accumulator shall be OPERABLE with:
a.
The isolation valve open and power removed, b.
A contained borated water volume of between 6122 and 6594 gallons, A boron concentration of between 2300 and 2500 ppm, and c.
d.
A nitrogen cover-pressure of between 585 and 665 psig.
APPLICABILITY: MODES 1. 2. and 3*.
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ACTION:
a.
With one accumulator inoperable due to boron concentration not within limits, either restore the boron concentration to within the above limits 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 reduce RCS' pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With one accumulator inoperable for reasons other than ACTION a..
l restore the' inoperable accumulator 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 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 reduce RCS pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1)
Verifying that the contained borated water volume and ' nitrogen cover-pressure in the tanks are within their limits, and i
l 2)
Verifying that each accumulator isolation valve is open.
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- Pressurizer pressure above 1000 psig, j
t WOLF CREEK - UNIT 1 3/4 5-1 Amendment No. -11.23.103.119 l
e EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 70 gallons by verifying the boron concentration of the accumulator solution. This surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that its boron concentration is within limits of Specification 3.5.5.
At least once 3er 31 days when the RCS pressure is above 1000 psig c.
by verifying tlat the circuit breaker supplying power to the isolation valve operator is open.
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WOLF CREEK - UNIT 1 3/4 5-2 Amendment No. W.119
3/4 5 EMERGENCY CORE COOLING SYSTEMS i
BASES 5
3/4.5.1 ACCUMULATORS The OPERABILITY of each Reactor Coolant System (RCS) accumulator ensures 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 pressure 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 met.
The accumulator
" operating bypasses" power operated isolation valves are considered to be in the context of IEEE Std. 279-1971, which requires that I
bypasses of a protective function be removed automatically whenever permissive conditions are not met.
In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.
l The allowed outage time limit for operation with one accumulator inoperable due to boron concentration not within limits reflects the fact that no credit is taken in the accident analysis for boron concentration in the accumulators during the LOCA blowdown phase.
Injection of borated water I
provides the fluid medium for heat transfer from the core and prevents excessive clad temperatures, contributing to the filling of the reactor vessel downcomer. The downcomer water elevation head provides the driving force required for the reflooding of the reactor core. Negative reactivity is initially a function of the void formation in the core. One accumulator below the minimum boron concentration limit will have no effect on available ECCS water and an insignificant effect on core subcriticality during reflood.
Boiling of ECCS water in the core during reflood concentrates boron in the saturated liquid that remains in the core.
Boron concentration during the sump recirculation phase is dominated by the RWST boron concentration.
Technical Specification 4.5.1.2. which required the performance of a channel calibration of each accumulator water level and pressure channel once per 18 months, was relocated to the Updated Safety Analysis Report. This was accomplished in accordance with the recommendations of Generic Letter 93-05 and NUREG-1366. These recommendations were based on the recognition that accumulator instrumentation operability is not directly related to the capability of the accumulators to perform their safety function.
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 Amendment No.119
2 EMERGENCY CORE COOLING SYSTEMS 1
BfSES 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 relief 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 8 3/4 5-2 Amendment No. 23, 35
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APPENDIX D ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-42 Wolf Creek Nuclear Operating Corporation shall comply with the following conditions on the schedules noted below:
4 Amendment implementation Number Additional Condition Date 108 The licensee is authorized to relocate certain The amendment shall technical specification requirements to be implemented 30 licensee-contro ed documents. Implementation days from the date of u
of this amendment shallinclude the relocation issuance.
I of these technical specification requirements to the appropriate documents, as described in the licensee's application dated February 17,1997, and evaluated in the staffs safety evaluation dated July 23,1997.
(
.119 The licensee is authorized to relocate certain The amendment shall i
technical specification requirements to be implemented 30 I
licensee-controlled documents. Implementation days from the date of i
of this amendment shallinclude the relocation
- issuance, of these technical specification requirements to the appropriate documents, as described in the i
licensee's application dated March 24,1995, as supplemented by letters dated July 26,1995, and September 5,1996, and evaluated in the staffs safety evaluation dated July 21,1998.
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1 Amendment No. 408,119 4
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