ML20149E863
| ML20149E863 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/11/1997 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20149E866 | List: |
| References | |
| NUDOCS 9707210105 | |
| Download: ML20149E863 (6) | |
Text
,P' "%,,k UNITED STATES
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- g NUCLEAR REGULATORY COMMISSION it WASHINGTON, D.C. 20066 4001
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,o WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. NPF-42 1
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 April 23, 1997, 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 i
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 coicaon defense and security or to the health and safety of the public: and E.
The issuance of this amendment is in accordance with 10 rrR Part 51 of the Commission's regulations and all applicable regi.1rements have been satisfied.
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9707210105 970711 PDR ADOCK 05000482 P
2-2.
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.107 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 3
b.
James C. Stone, Senior Project Manager
-Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation j
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Attachment:
Changes to the Technical 1
Specifications
]
Date of Issuance:
July 11, 1997 4
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ATTACHMENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following aages of the Appendix A Technical Specifications with the attached pages. T1e revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
The corresponding n
overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 9-4 3/4 9-4 B 3/4 9-2 B 3/4 9-2 l
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4 REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 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, by A minimum of-one door in the emergency airlock is closed
- and one door in the personnel airlock is capable of being closed, and 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.
]
d.
Penetration P-63 (Service Air valves KA V-039 and KA V-118) and Penetration P-98 (Breathing Air valves KB V-001 and KB V-002) may be opened under administrative controls.
APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within the containment.
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With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
i SVRVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its required condition or capable of being closed 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 required condition, or b.
Testing the contain'nent purge isolation valves per the applicable portions of Specificatio: 4.6.3.2.
- An emergency escape hatch temporary closure device is an acceptable replacement for that airlock door.
WOLF CREEK - UNIT 1 3/4 9-4 Amendment No. 74,S0,05,107 (Next page is 3/4 9-9) e f
1 3/4.9 REFUELING OPERATIONS BASES i
3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a unifona boron cencentration is maintained for reactivity centrol 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 RLS 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.
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 condition of the core.
When determining compliance with action statement requirements, addition 4
to the RCS of borated water with a concentration greater than or equal to the 4
minimum required RWST concentration shall not be considerod to be a positive reactivity change.
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3/4.9.3 DEC.AY T[ME E
The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in'the reactor vessel ensures that sufficient time has eltpsed to allow the radioactive decay uf 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 l
The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material from containment will be minimized.
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 OPERABII.ITY 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, h
idOLF CREEK - UNIT 1 2 3/4 9-1 Amendment No. 74,95
EffffiULG OPERATIONS I
BASES 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS (Continued)
Both containment personnel airlock doors may be open during movement of irradiated fuel or CORE ALTERATIONS, provided one airlock door is capable of being closed and the water level in the refueling pool is maintained as required.
Service Air valves KA V-039 and KA V-Il8 (Containment penetration P-63) and Breathing Air valves KB V-001 and KB V-002 (Cont:inment penetration P-98) may be opened under administrative controls during movement of irradiated fuel or CORE ALTERATIONS to provide air services to the reactor building to support outage activities.
Administrative controls ensure that 1) appropriate personnel are aware of the open status of the containment during movement of irradiated fuel or CORE ALTERATIONS, 2) specified individuals are designated and readily available to close the airlock or the service air and breathing air valves following an evacuation that would occur in the event of a fuel handling accident, and 3) any obstructions (e.g., cables and hoses) that could prevent rapid closure of an open airlock can be quickly removed.
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 % approved by an engineering evaluation and may include use of a material that can provide a temporary, pressure tight seal capable of maintaining the integrity of the penetrations and airlock to restrict the release of radioactive material from a fuel element rupture.
3/4.15 DELETED 3/4.9.6 DELETED 3/4.9.7 DELETED 3/4.9.8 RESIDUAL e AT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that: (1) sufficient ccoling capacity is available to remove decay heat end 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 concentratior, 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 ev3nt of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
WOLF CREEX - UNIT 1 8 3/4 9-2 Amendment No. M,80,05,107
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