ML20070E533
| ML20070E533 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/07/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070E535 | List: |
| References | |
| NUDOCS 9407150181 | |
| Download: ML20070E533 (7) | |
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1 UNITED STATES.
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NUCLEAR REGULATORY COMMISSION t
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WASHINGTON. D.C. 20555-0001 j
i WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 1
AMEN 0 MENT TO FACILITY OPERATING LICENSE
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Amendment No. 74 License No. NPF-42 l
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!O._; ear Regulatory Commission (the Commission) has found that:
i The application for amendment to the Wolf Creek Generating Station (the facility)' facility Operating License No. NPF-42 filed by the vloi t Creek Nuclear Operating Corporation (the Corporation), dated February 24, 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 ti,e Loc.m: ssion; r
1 C.
There.is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health j
and safety of the noblic, 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 l
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 h
of the Commission's regulations and all applicable requirements have '
been satisfied.
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9407150181 940707 DR p
ADOCM 05000482 PENT
2.
Accordingly, the licence is amended by changes to the Technical Specifications as indiccted 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. 74, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 03-Qfk h~
Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 7, 1994 J
ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE 40. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with thn attached pages.
The revised pages are identified by Amendment number and contain T.arginal lines indicating the areas of change.
The corresponding everlaaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 9-4 3/4 9-4 B 3/4 9-1 B 3/4 9-1
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REFUELING OPERATIONS 3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subtritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
APPLICABILITY:
During movement of irradiated fuel in the reactor vessel.
3 ACTION:
I With the reactor subcritical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all operations involving movement of irradiated fuel in the reactor vessel.
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SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor vessel.
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WOLF CREEK - UNIT I-3/4 9-3
BE[ULLJN3 OPEP.ATIONS 4.14 ':0NTAINMENT BUILDING PENETRATIONS m
ljM,LTjjjG CONDITION FOR OPERATION 3.s.4 The containment building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four
- bolts, b.
A minimum of one door in each airlock is closed *, and l
c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1)
Closed by an isolation valve, blind flange, manual valve, or approved functional equivalent, or 2)
Be capable of being closed by an OPERABLE automatic containment purge isolation valve.
++b.J.ABitilY:
During CORE ALTERATIONS or movement of irradiated fuel within c.
.u-ent.
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With the equirements of the above specification not satisfied, immediately
.u3penc a.i cperations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
SURV[!LLANCE REOUIREMENTS 4.9.4 Each of the above required containment 'auilding penetrations shall be cetermined to be either in its closed / isolated condition or capable of being
.lmoed by an OPERABLE automatic containment purge isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:
a.
Verifying the penetrations are in their closed / isolated condition, or b.
Testing the containment purge isolation valves per the applicable portions of Specification 4.6.3.2.
'An emergency escape hatch temporary closure device is an acceptable replacement for that airlock door.
i WOLF CREEK - UNIT 1 3/4 9-4 Amendment No. 74
l 3/4.9 REFUELING OPERATIONS BASES 3/4.9.] BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
(1) the reactor will remain subtritical 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 l
no greater than 0.95 is sufficient to prevent reactor criticality during refueling operations.
The locking clcsed 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 baron dilution incident in the safety analyses.
3/4.9.2 INSTRUMENTATION j
The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the roactivity condition of the core.
I When determining compliance with action statement requirements, addition to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to be a positive reactivity change.
3j4.9.3 DECAY TIME The minimum requirement for reactor subtriticality prior to movement of irradiatea fuel assemblies in the reactor vessel ensures that sufficient time has olapsed to allow the radioactive decay of the short-lived fission prouucts.
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 i
will be restricted from leakage to the environment.
The OPERABILITY and clcsure 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.
Equivalent isolation methods for the emergency personnel escape lock and containment wall penetrations ensure releases from containment are prevented for credible accident scenarios.
The isolation techniques must be approved by an engineering evaluation and may include use of a material that can provide a
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temporary, pressure tight seal capable of maintaining the integrity of the j
penetrations and airlock to restrict the release of radioactive material from a fuel element rupture.
WOLF CREEK - UNIT 1 B 3/4 9-1 Amendment No. 74
REFUELING OPERATIONS j
BASES 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
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 lift
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a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently.
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engaged during lifting operations.
3 /4. 9,7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY The restriction on movement of loads in excess of the nominal weight of a f # M codrcl rod assembly and associated handling tool over other fuel astcmblies 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 s i ng'. : futi assembly, and (2) any possible distortion of fuel in the storage racks m il not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
3 d i.! NQL HEAT REMOVAL AND COOLANT CIRCULATION 1he 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.
Addition of borated water with a concentration greater than or equal to the minimum required RWST concentration but less than the actual RCS boron concentration shall not be considered a reduction in boron concentration.
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.
WOLF CREEK - UNIT 1 B 3/4 9-2 Amendment No. 35 fevertier 22,1993 r