ML20078L958
| ML20078L958 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/22/1994 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078L965 | List: |
| References | |
| NUDOCS 9412010270 | |
| Download: ML20078L958 (9) | |
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UNITED STATES k
NUCLEAR REGULATORY COMMISSION
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S WASHINGTON, D.C. 20555-4001 g.
t!0USTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO 1
CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-498 i
SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 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 licenseas), dated April 29, 1994, as supplemented by letter dated September 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.
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 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.
9412010270,941122 PDR ADOCK 05000498, p
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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 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. 66, 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.
3.
The license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0
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k4BN IC Thomas W. Alexion, 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: November 22, 1994 i
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- E UNITED STATES i%
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WASHINGTON D.C, 20555-0001
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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 N0. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 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 April 29, l
1994, as supplemented by letter dated September 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, t
2.
Accordingly, the license is amended by' changes to the Technical l
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 The Technical Specifications contained in Appendix A, as revised
[
through Amendment No. 55, and the Environmental Protection Plan i
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..
3.
The license amendment is effective as of its date of issuanct, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r7 LO7)Dj / -
' bN Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
November 22, 1994
ATTACHMENT TO LICENSE AMENDMENT N05. 66 AND 55 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 7-2 3/4 7-2 8 3/4 7-1 B 3/4 7-1 i
s e
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With four reactor coolant loops and associated steam generators in a.
operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, either the inoperable valve is restored to OPERABLE l
status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, 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 /> ard in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
The provisions of Spec)fication 3.0.4 are not applicable.
SURVEILLANCE REOUTREMENTS 4.7.1.1 There are no additional requirements other than those required by Specification 4.0.5 i
1 Unit 1 - Amendment No. 4 59 SOUTH TEXAS - UNITS 1 & 2 3/4 7-1 Unit 2 - Amendment No. 4I
t TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING 4 LOOP OPERATION MAX 1 MUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER)
I 63 2
45 3
27 l
l i
l SOUTH TEXAS - UNITS 1 & 2 3/4 7-2 Unit I - Amendment No. 66 Unit 2 - Amendment No. 55-
3/4.7 PLANT SYSTEMS 1
BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures that the Secondary System pressure will be limited to within 110% (1413.5 psig) of its design pressure of 1285 psig during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a Turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition.
The to all of the steam lines is 20.65 x j0}al relieving capacity for all valves on lbs/h which is 122% of the total secondary steam flow of 16.94 x 10 lbs/h at 100% RATED THERMAL POWER. A ninimum of two OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THERMAL POWER required by the reduced Reactor trip settings of the Power Range Neutron Flux channels.
The Reactor Trip Setpoint reductions are derived on the following bases:
Hit - (100) (w,h,,N)
Q K
Where:
Hi & - Safety analysis power range high neutron flux setpoint, percent Q
- Nominal NSSS power rating of the plant (including reactor coolant pump heat), MWt K
= Conversion Factor, 947.82 (BTU /sec)/MWt w,
- Minimum total steam flow rate capability of the operable MSSVs on any one steam generator at the highest MSSV opening pressure, including tolerance and accumulation, as appropriate, in Ibm /sec.
For example, if the maximum number of inoperable MSSVs on any one steam generator is one, then w, should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV.
If the maximum number of inoperable MSSVs per steam generator is three, then w should be a summation of the capacity of the operable MSSVs al the highest operable MSSV operating pressure, excluding the three highest capacity MSSVs.
h,,
- Heat of vaporization for steam at the highest MSSV operating pressure including allowances for tolerance, drift, and accumulation, as appropriate, Btu /lbm N
= Number of loops in the plant.
The calculated values are lowered an additional 9% full power to account for instrument and channel uncertainties.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-1 Unit 1 - Amendment No. 66 Unit 2 - Amendment No. 55 j
PLANT SYSTEMS BASES 3 /4.7.1. 2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a total loss-of-offsite power.
Each auxiliary feedwater pump is capable of delivering a total feedwater flow of 500 gpm at a pressure of 1363 psig to the entrance of the steam l
^
generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System i
temperature to less than 350*F when the Residual Heat Removal System may be placed into operation. The AFW pumps are tested using the test line back to the AFST and the AFW isolation valves closed to prevent injection of cold water into the steam generators. The STPEGS isolation valves are active valves required to open on an AFW actuation signal. Specification 4.7.1.2.1 requires these valves to be verified in the correct position.
3/4.7.1.3 AUXILIARY FEEDWATER STORAGE TANK (AFST)
The OPERABILITY of the auxiliary feedwater storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offsite power, main feedwater line break and failure of the AFW flow control valve followed by a cooldown to 350*F at 25'F t
per hour. The contained water volume limit includes an allowance for water l
not usable because of tank discharge line location or other physical characteristics.
3 /4. 7.1. 4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture.
This dose also includes the effects of a coincident I gpm primary-to-secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.
3 /4.7.1. 5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no vnore than one steam generator will blow down in the event of a steam line rupture. This restriction is required to:
(1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analyses.
9 SOLITH TEXAS - UNITS 1 & 2 B 3/4 7-2 Unit 1 - Amendment No. M, 61 Unit 2 - Amendment No. 44, 50 t
.