ML20083E442
| ML20083E442 | |
| Person / Time | |
|---|---|
| Site: | South Texas  (NPF-80-A-018, NPF-80-A-18) |
| Issue date: | 09/18/1991 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083E444 | List: |
| References | |
| NUDOCS 9110020367 | |
| Download: ML20083E442 (5) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION 5-
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WASHINGTON, D.C. 205s5 gu.....f HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND L?GHT COMPANY CITY OF AUSTIN, TEXAS _ _ _
DOCKET NO. 50-499 SOUTH TEXAS PROJECT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 18 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 rower and Light Company (CPL),
and City of Austin, Texas (C0A) (the licensees) dated June 12, 1930, as supplemented by letter dated July 17, 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 f acility.
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9110020367 91091u PDR ADOCK 05000499 PDR p
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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.
18,. and the Environmental Protection Plan contained in Appendix B, are hereby incorpcrated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
j 3.-
The license amendment is effective as of its date of issuance and is to be implemented prior to restart from the second refueling outage, 1
which is presently scheduled to begin in September 1991.
i FOR THE NUCLEAR REGULATORY COMMISSION
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Suzanne C. Black, Director Project Directorate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1991 4
1
W ATTACHMENT TO LICENSE AMENDMENT NO. 18 FACILITY OPERATING LICENSE NO. NPF-80 DOCKET NO. 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 vertical lines indicating the areas of change, REMOVE INSERT 1/4 5-11 3/4 5-11 B 3/4 5-3 B 3/4 5-3 l
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ENERGENCY CORE COOLING SYSTEMS 3/4.!.6 RE51 DUAL _ HEAT RD ^ ML (RHR) SriTEM LIMITWG CONDITION FOR OPERATION T$[ee independent ReIidual Heat Removal (RHQ) locps shall be OPERABLE 3.5.6 with each loop compoised of:
a.
One OPERABLE RHR heat exchanger, and c.
One OPlRABLE flowpath capable of taking suction from its associated RCS hot leg and discharging to its associated RC$ cold leg.*
APPLICA'lLITY:
MODES 1, 2 and 3.
ACTION:
a.
Witn one RHR loop inoperable, restore the required loop to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDEsY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With two isHR loops inoperal'le, restore at least two RHR loopc 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 be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
I c.
With t.hree RHR loops inoperable, immediately initiate corrective action to restore at east one RHR loop to OPERABLE status as soon as pnsbible.
$URVEILLA7 E REQUIREMENTS 4.5.6.1 Each RHR loop shall t,a demonstrated OPERABLE pursuant to the require-ments of Specification 4.0.5.
4.5.6.2 At least once per 18 months by verifying automatic isolation ** and
,I interlock action of the RHR system from the Reactor Coolant System to ensure tna,:
a.
With a simulated or actual Reactor Coolant System pressure signal greater than or equal to 350 psig, the interlocks prevent the valves from being opened, and
- b.
With a siinulated or actual Reactor Coolant System pressure si nal less than or equal to 700 psig, the interlocks will 0
cause the valves to automatically close.
- Valves HOV-0060 A, B, and C and MOV-0061 A, B, and C may have power removed to su.7 port the EHAR (Fire Hazard Analysis Report) assumptions, e
- This surveillance is applicable to Unit 1 only.
t SOUTH TEXAS - UNITS 1 & 2 3/4 5-11 Unit 1 - Amendment No. 4 Unit 2 - Amendment No. 18
T' LMERGENCY CORE COOLING SYSTEMS
_fl A_S E S 3/4.5.6 RESIDUAL HE AT REMOVAL. (RHR) $YSipt The OPEPsABillTY of the RHR syt, tem ensures adequate heat removal capabili-tier, for Long-lerm Core Cooling in the event of a small-breal loss-of-coolant accident '.LOCA), an isolatable LOCA, or a secondary break in H0Dl51, 2, and 3.
The limits on the OPERABIL11Y of the RHR system ensure that at least one RHR loop is available for cooling including single active f ailure criteria.
The surveillances ensure that RHR s; stem isolation valves clese upon an overpressure protection syst(m signal.*
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- This surveillance is applicable to Unit 1 only.
SOUTH TEXAS - UNils 1 & 2 8 3/4 5-3 Unit 2 - Amendment No. 18