ML20086D940
| ML20086D940 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/08/1991 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086D944 | List: |
| References | |
| NUDOCS 9111260333 | |
| Download: ML20086D940 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION fp t WAsHINoToN, D. C. 205s5 c,
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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. 50-498 SOUTH TEXAS PROJECT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Housten 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 December 21, 1990, as supplemented by letter dated October 15, 1991, 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.
9111260333 911108 PDR ADOCK 05000498 F
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2.
Accordingly, the license is amended by changes to the Tech,ical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 31, and the Environmental Protection Plan contained in Appendix 0, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Yechni:a1 Specifications and the Environmental Protection Plan.
3.
The license amendment is effective at of its date of issuance.
FOR THE HUCLEAR REGULATORY COMMISSION
%sm_ C. /ght Suzanne'0IBlack, Director Project directorste IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issusnce: November 8, 1991 l
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9 NUCLE AR REGULATORY COMMISSION 3m a
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HOUSTON LIGHilNG & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN, TEXAS DOCKET NO. 50-499 SOUTH TEXAS PROJLCT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPf-80 1.
The Nuclear Regulatory Commission (th-Commission) has f ound 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 (C' L),
and City of Austin, Texas (C0A) (the licensees) dated December 21, 1990, and supplemented by letter dated October 15, 1991, 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 fcrth 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 au..iorized 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 icimical to the common defense and security or to the health and safety of the public; and
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The issuance of this amendment is in accordance with 10 CFR Part 51 0
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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2.
Accordingly, the license is amended by changes to the Technical Specifi-cations 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 The Technical Specifications contained in Appendix A, as revised through Amendment No. 22, and the Environmental Protection Plan coi. Tined in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Proter +. ion Plan.
3.
The license amendment is effective as of its date of issuance.
FOR lHE NUCLEAR REGULATORY COMMI5510N CY
>vvA Suzanne black, Director Project Directorate IV-2 Division of Reactor Projects - !!!/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Sptcifications Date of Issuance: November 8, 1991 O
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ATTACHMENT TO LICENSE AMENDMENT N05. 31 AND 22 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET N05. 50-498 AND 50-499 i
i Replace the following page of the Appendix A Technical Specifications with the 4",tached page.
The revised page is identified by Amendment number and ematains vertical lines indicating the area of change.
The corresponding a er. af page is also provided to maintain document completeness.
i REMOVE INSERT 3/4 4-36 3/4 4-36 i
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REAC70R COOLANT SYSTEM PRESSURIZER LIMITING _CQRITIONFOROpERATION 3.4.9.2 1he pressurizer temperature shall be limited to:
A maximum heatup of 100*F in any 1-hour period, a.
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A maximum cooldown of 20J"F in any 1-hour period, and A maximum spray watet temperature differential of 621*f.
c.
APPLICABILITY: At all times.
ACTION:
With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the ef fects of the out of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation 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 the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4 g & QN,JE RE0VIREMENTS 9
4.4.9.2 The pressurizer temperatures shall be determined to be within the c
limits at least once per 30 minutes during system heatup or cooldown.
The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during auxiliary spray operation.
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4 SOUTH TEXA5 - UNITS 1 & 2 3/4 4-35 4
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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS p
l LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE:
Two power-operated relief valves (PORVS) with lift settings which a.
do not exceed the limit established in Figure 3.4-4, or b.
The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2.0 square inches.
APPLICABILITY:
MODES 4 and 5, and MODE 6 when the head is on the reactor vessel.
ACTION:
a.
With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERADLE status within 7 days or depressurize and vent the RCS through at least a 2.0 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With one PORV inoperable in MODES 5 or 6 with the head on the reactor vessel, restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or complete depressurization and venting of the RCS through at least a 2 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.*
With both PORVs inoperable, depressurize and vent the RCS throug5
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at least a 2.0 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.*
d.
In tht event either the PORVs or the RCS vent (s) are used to mitigate l
an RCS pressure transient, a Special Report shall be prepared and submitted to tne Commission pursuant to Specification 6.9.2 within 30 days.
The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.
The provisions of Specification 3.0.4 are not applicable.
c.
- This ACTION may be suspended for up to 7 days to allow functional testing to verify PORV operability.
During this test period, operation of systems or components which could result in an RCS mass or temperature increase will be administratively controlled.
During the ASME stroke testing of two inoperable PORYs, cold overpressurization mitigation will be provided by two RHR discharge relief valves associated with two OPERABLE and operating RHR loops which have the auto closure interlock bypassed [or deleted).
If one PORV is inoperable, cold overpressure mitigation will be provided by the OPERABLE PORV and one RHR discharge relief valve associated with an OPERABLE and operating RHR loop which has the auto closure interlock bypassed [or deleted).
SOUTH TEXAS - UNITS 1 & 2 3/4 4-36 Unit 1 - Amendment No. 31 Unit 2 - Amendment No. 22
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