ML20078S882
| ML20078S882 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 02/13/1995 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078S885 | List: |
| References | |
| NUDOCS 9502270367 | |
| Download: ML20078S882 (9) | |
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- UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2006M001 4,.....,d HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 5.0.-3 1 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Company *
(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (C0A) (the licensees), dated November 8, 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 the Commission; C.
There is reasonable assurance:
(1) 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.
Thelissuance of this license amendment will not be inimical to the J
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 Commission's regulations and all applicable requirements have been satisfied.
- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and' has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
t 9502270367 950213 PDR ADOCK 05000498 i
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment l
and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby
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amended to read as follows:
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2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 70, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
1 The licensee shall operate the facility in accordance with the 1
Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION
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Thomas W. Alexion, Proj ct Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation l
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Attachment:
Changes to the Technical Specifications l
Date of Issuance: February 13, 1995 I
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v te p-4 UNITED STATES s
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20056 4001
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HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Company *
(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (C0A) (the licensees), dated November 8, 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 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.
- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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1 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment and Paragraph.2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:
2.
Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 59, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
s 3.
The license amendment is effective as of its date of issuance.
i FOR THE NUCLEAR REGULATORY COP #ilSSION i
(; -
v/ @W Thomas W. Alexion, Projec Nanager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 13, 1995 3
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ATTACHMENT TO LICENSE AMENDMENT NOS. 70 AND 59 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 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 9-2 3/4 9-2 B 3/4 9-1 B 3/4 9-1 i
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i 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to j
ensure that the more restrictive of the following reactivity conditions is met; either:
1 a.
A K, of 0.95 or less, or g
b.
A boron concentration of greater than or equal to 2800 ppa.
l APPLICABILITY: MODE 6.*
ACTION:
With the requirements of the above specification not satisfied, immediately i
suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpa of a solution containing creater than or equal to 7000 ppe boron or its equivalent until K is reduced to less than or equal to 0.95 or the boron concentration is res,tored to greater than or equal to 2800 ppe, whichever is g
the more restrictive.
SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.
4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4.9.1.3 Valves FCV-Il08, FCV-1118, CV0201A, and CV0221 shall be verified closed and secured in position by mechanical stops or by removal of air or electrical power at least once per 31 days.
- The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
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SOUTH TEXAS - UNITS 1 & 2 3/4 9-1 Unit 1 - Amendment No. E,54 Unit 2 - Amendment No. 40,43
REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors
- shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
APPLICABILITY: MODE 6.
ACI1QN:
a.
With one of the above required monitors inoperable or r:t operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
b.
With both of the above required monitors inoperable or ot operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:
a.
A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
A CHANNEL CALIBRATION, excluding the Neutron detectors, every 18 months.
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- An Extended Range Neutron Flux Monitor may be substituted for one of the Source Range Neutron Flux Monitors provided the OPERABLE Source Range Neutron Flux Monitor is capable of providing audible indication in the containment and control room.
SOUTH TEXAS - UNITS 1 & 2 3/4 9-2 Unit 1 - Amendment No. 70 Unit 2 - Amendment No. 59
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 in the safety analyses. The value of 0.95 or less for K includes a 1% ok/k conservative allowance for uncertainties. Similarly, thfboron concentration value of 2800 ppm or greater includes a conservative uncertainty allowance of 50 ppa 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.
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3/4.9.2 INSTRUMENTATION 1
l The OPERABILITY of the Source Range and/or Extended Range Neutron Flux,
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Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME 1
The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time l
has elapsed to allow the radioactive decay of the short-lived fission
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products. This decay time is consistent with the assumptions used in the
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safety analyses for the rapid refueling design.
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 restricted from leakage to the environment. The containment personnel airlock, which is part of the containment pressure boundary, provides a means i
for personnel access during MODES 1, 2, 3, and 4 operation. During periods of shutdown, when containment closure is not required, the door interlock mechanism may be disabled, allowing both doors of the containment personnel airlock to remain open for extended periods when frequent containment entry is necessary.
Both containment personnel airlock doors may be open during CORE ALTERATIONS provided one airlock door is OPERABLE, there is 23 feet of water above the reactor vessel flange, and an individual is available outside the containment personnel airlock to close a door following a fuel handling accident inside containment.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 9-1 Unit 1 - Amendment No. 51,51,59,70 Unit 2 - Amendment No. 40,0,50,59 I
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'n REFUELING OPERATIONS BASES 3/4.9.4 CONTAllMENT BUILDING PENETRATIONS (Continued)
Operability of a containment personnel airlock door requires that the door is capable of being closed, i.e., that the door is unblocked and no cables or hoses run through the personnel airlock. Containment personnel airlock door closure is required to take place within 30 minutes of initiation of a fuel handling accident inside containment if the reactor has been suberitical for less than 165 hours0.00191 days <br />0.0458 hours <br />2.728175e-4 weeks <br />6.27825e-5 months <br />. Fuel movement is not permitted with personnel airlock doors open, if the reactor has not been subcritical for 195 hours0.00226 days <br />0.0542 hours <br />3.224206e-4 weeks <br />7.41975e-5 months <br />.
If the reactor has been subcritical for 165 hours0.00191 days <br />0.0458 hours <br />2.728175e-4 weeks <br />6.27825e-5 months <br /> or more, containment personnel airlock door closure is to occur as soon as practicable, but is assumed to occur within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to be consistent with the accident analysis.
These requirements assure that the associated doses are limited to within acceptable levels. The requirement to have 23 feet of water above the reactor vessel flange is consistent with the fuel handling accident analysis assumptions, Regulatory Guide 1.25, and Toccical Specification 3.9.10 Water level - Refueling Cavity.
3/4.9.5 C0fWUNICATIONS 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) the refueling machine and auxiliary hoist will be used for movement of drive rods and fuel assemblies, (2)~ the refueling machine has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lift <ng force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING 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, unless handled by the single-failure-proof main hoist of the FHB 15-ton crane, 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.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 9-2 Unit 1 - Amendment No. 69 Unit 2 - Amendment No. 58
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