ML20106H740
| ML20106H740 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/18/1996 |
| From: | Polich T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20106H742 | List: |
| References | |
| NUDOCS 9603220010 | |
| Download: ML20106H740 (10) | |
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t UNITED STATES 7
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E NUCLEAR REGULATORY COMMISSION
'f WASHINGTON, D.C. 2055fWKC1
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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated November 21, 1995 (TXX-95289), as supplemented by letters dated February 22 (TXX-96061 and TXX-96062) and 28, (TXX-96068), and March 13, 1996 (TXX-96090),
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 smended, 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; i
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.
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. i 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-87 is hereby amended to read as follows:
2.
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee 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.
i FOR THE NUCLEAR REGULATORY COMMISSION M
Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 18, 1996 i
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t UNITED STATES j,
j NUCLEAR REGULATORY COMMISSION
't WASHINGTON. D.C. 20555 4001
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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. NPF-89
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1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated November 21, 1995 (TXX-95289), as supplemented by letters dated February 22 (TXX-96061 and TXX-96062) and 28, (TXX-96068), and March 13, 1996 (TXX-96090),
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and 1
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.
. 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-89 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 34, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
TU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Timothy J. Polich, Project Manager Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation f
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 18,1996 l
1 ATTACHMENT TO LICENSE AMENDMENT NOS. 48 AND 34 i
FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 1
DOCKET N05. 50-445 AND 50-446 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 9-4 3/4 9-4 3/4 9-4a 3/4 9-4a B 3/4 9-1 B 3/4 9-1 i
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i REFUELING OPERATIONS 3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be suberitical 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.
ACTION:
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 RE0VIREMENTS 4.9.3 The reactor shall be determined to have been suberitical for at least i
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 l
movement of irradiated fuel in the reactor vessel.
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t COMANCHE PEAK - UNITS 1 AND 2 3/4 9-3 l
REFUELING OPERATIONS SURVEILLANCE 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 l an OPERABLE automatic containment ventilation 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 that, 1.
Containment ventilation isolation occurs on a high radiation test signal from a containment atmosphere gaseous monitoring instrumentation channel and the containment ventilation isolation valve (s) can be closed remotely from the control room, or 2.
the containment ventilation isolation valve (s) are closed /
isolated.
b.
Verifying the remaining penetrations of 3.9.4, not covered by a.
above, are in their required condition.
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COMANCHE PEAK - UNITS 1 AND 2 3/4 9-4a Unit 1 - Amendment No. 48 Unit 2 - Amendment No. 34
REFUELING OPERATIONS BASES 3 /4. 9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine main hoist and auxiliary monorail hoist ensure that:
(1) the main hoist will be used for movement of fuel assemblies, (2) the auxiliary monorail hoist will be used for latching, unlatching and movement of control rod drive shafts, (3) the main hoist has sufficient load capacity to lift a fuel assembly (with control rods), (4) the auxiliary monorail hoist has sufficient load capacity to latch, unlatch and move the control rod drive shafts, and (5) the core internals and reactor vessel 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 AREAS 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 a storage pool 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 possibla 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.
3 /4. 9,8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) 14 'p 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 i
incident and prevent boron stratification.
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 residual heat removal capability.
With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is avail-able 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.
COMANCHE PEAK - UNITS 1 AND 2 B 3/4 g-2
3/4.9 REFUELING OPERATIONS BASES 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 uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident includes a 1% Ak/k The value of 0.95 or less for K, boron concentration in the safety analyses.
Similarly, thy conservative allowance for uncertainties.
value of 2400 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron. The locking closed of the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portion of the RCS._ This action prevents flow to the RCS of unborated water by closing flow paths from sources of unborated water.
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.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality 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 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.
Both containment personnel airlock doors may be open during movement of irradiated fuel or during core alterations provided one airlock door is capable of being closed and water level in the refueling cavity is maintained as required.
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.
COMANCHE PEAK - UNITS 1 AND 2 B 3/4 9-1 Unit 1 - Amendment No. +9724,48 Unit 2 - Amendment No. Erle, 34 l