ML20248C521
| ML20248C521 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/31/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248C525 | List: |
| References | |
| NUDOCS 8908100065 | |
| Download: ML20248C521 (9) | |
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,8 NUCLEAR REGUL.ATORY COMMISSION n
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HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY
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DOCKET NO. 50-498 d
SOUTH TEXAS PROJECT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 10 License No. NPF-76 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Houston Lighting & Power Company * (HL&P) acting on behalf of itself and for the City PublicServiceCoardofSanAntonio(CPS),CentralPowerand Light Company (CPL), and City of Austin, Texas (C0A) (the licensees) dated June 1, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission; 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 Comission'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 thir amendment is in accordance with 10 CFE Part 51 of the Comission'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, operatica 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-76 is hereby amended to read as follows:
2..
Technical Specifications The Technical Specifications contained in Appendix'A,..as revised through Amendment No. 10, 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.
FOR THE NUCLEAR REGULATORY C0hMISSION
, n l h ).. C l A {
Frederick J. Hhbdon, Director -
Project Directorate - IV 4
Division of Reactor Projects - III, IV, Y and Soecial Projects-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 31, 1989 1
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UNITED 3TATEs
('t NUCLEAR REGULATORY. COMMISSION En fj WASHINGTON, D. C. 20555
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HOUSiON LIGHTING & POWER COMPANY CITY PURIC 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 OPEPATING LICENSE Amendment No. 2 License No. NPF-30 1.
The Nuclear Regulatory Comission -(the Comission) has found that:
A.
The application for amendment by Houston Lighting-& Power Company * (HL&P) acting on behalf af itself and for the City Public Service Board of San Antonio (CPS), Central Power and
-Light Com any (CPL), and City of Austin, Texas (C0A) (the licensees dated June 1, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission; C.
There is reasonable assurance:
(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations; D.
The issucnce of this license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have
-been satisfied.
- Houston Lightiiig & 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.
1
.. 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. 2, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
,% N w b YL Frederick J. Hebdon, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclecr Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 31, 1989 i
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i ATTACHMENT TO LICENSE AMENDMENT NOS.10 AND 2 4-9..
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FACILITY OPERATING LICENSE NOS. NPF-78 "ND NPF-80
-t DOCKET NOS. 50-498 AND 50-4E.
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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.' The corresponding overleaf pages are also provided to maintain document. completeness.
l Remove Insert B 3/4 1-1 B 3/4 1 5-6 5-6 k
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3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3
3/4.1.1.1 and 3/4.1.1.2 -SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that:
(1) the reactor can be made suberitical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg.
In MODES 1 and 2, the most restrictive condition occurs at EOL, with T,yg,at no' load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.75% ok/k is required to control the reactivity transient.
The 1.75% Ak/k M UTDOWN MARGIN is the design basis minimum for the 14-foot fuel using silver-indium-cadmium and/or Hafnium control rods (Ref. FSAR l
Table 4.3-3).
Accordingly, the SHUTDOWN MARGIN requirement for MODES 1 and 2 is based upon this limiting condition and is consistent with FSAR safety anal-ysis assumptions.
In MODES 3, 4, and 5, the most restrictive condition occurs at BOL, when the boron concentration is the greatest.
In these modes, the required SHUTDOWN MARGIN is composed of a constant requirement and a variable requirement, which is a function of the RCS boron concentration.
The constant SHUTDOWN MARGIN requirement of 1.75% Ak/k is based on an uncontrolled RCS cool-down from a steamline break accident.
The variable SHUTDOWN MARGIN requirement is based on the results of a boron dilution accident analysis, where the SHUT-DOWN MARGIN is varied as a function of RCS' boron concentration, to guarantee a minimum of 15 minutes for operator action after a boron dilution alarm, prior to a loss of all SHUTDOWN MARGIN.
The boron dilution analysis assumed a common RCS volume, and maximum dilution flow rate for MODES 3 and 4, and a different volume and flow rate for MODE 5. The MODE 5 conditions assumed limited mixing in the RCS and cooling with the RHR system only.
In MODES 3 and 4 it was assumed that at least one reactor coolant pump was operating.
If at least one reactor coolant pump is not operating in MODE 3 or 4, then the SHUTDOWN MARGIN requirements for MOLE 5 shall apply.
3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 1-1 Unit 1 - Amendment No.10 Unit 2 - Amendment No. 2
, REACTIVITY CONTROL SYSTEMS ASES B
MODERATOR TEMPERATURE COEFFICIENT (Continued)
The most negative MTC, value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.
These corrections involved subtracting the incremental change in the MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL POWER conditions.
This value of the MDC was then transformed into the limiting MTC value -4.0 x 10 4 Ak/k/ F.
The MTC value of -3.1 x 10 4 ok/k/*F represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained by making these corrections to the limiting MTC value of -4.0 x 10 4 ok/k/ F.
The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 561'F.
This limitation is required to ensure:
(1) the moderator temperature coefficient is within its analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) tne pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reacter vessel is above its m'= 5um RT temperature.
NDT 3/4.1.2 BORATION SYSTEMS The Boren Injection System ensures that negative reactivity control is available during each mode of facility operation.
The components required to perform this function include:
(1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an em6rgency power supply from OPERABLE diesel generators.
With the RCS average temperature above 350*F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable.
The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1.75% ak/k after xenon decay and cooldown to 200*F.
The maximum expected boration cepability requirement occurs at EOL from full power equilibrium xenon conditions and requires 27,000 gallons of 7000 ppm borated water from the boric acid storage system or 458,000 gallons of 2500 ppm borated water from the refueling water storage tank (RWST).
The RWST volume is an ECCS requirement and is more than adequate for the required boration capability.
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i DESIGN FEATURES
,5.3' REACTOR CORE l
FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly con-taining 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of.168 inches.
The initial core loading shall have a maxi-y mum enrichment of 3.5 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.5 weight percent U-235.
CONTROL R0D ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies.
The full-1 angth control rod assemblies shall contain a nominal 158.9 inches of absorber material. The absorber material within each ' assembly shall be. silver-indium-cadmium or hafnium.
Mixtures of hafnium and silver-indium-cadmium are not permitted within a bank.
All control rods shall be clad with stainless steel tubing.
1 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the l
applicable Surveillance Requirements, b.
For a pressure.of 2485 psig, and c.
For a temperature of 650 F, except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,814
+ 100 cubic feet at a nominal T,yg of 561*F.
5.5 METEOROLOGICAL TOWER LOCATION
. 5. 5.1 The meteorological towers shall be ' located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance of SOUTH TEXAS - UNITS 1 & 2 5-6 Unit 1 - Amendment No. 2,10 Unit 2 - Amendment No. 2
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1 DESIGN FEATURES f alIEilllEl:m:
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly con-taining 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 168 inches.
The initial core loading shall have a maxi-mum enrichment of 3.5 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum errichment of 3.5 weight percent U-235.
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1 CONTROL ROD ASSEMBLIES i
5.3.2 The core shall contain 57 iall-length control rod assemblies.
The full-i length control rod assmblies shall contain a nominal 158.9 inches of absorber material.
The absorber material within each' assembly shall be silver-indium-cadmium or hafnium.
Mixtures of hafnium and silver-indium-cadmium are not j
permitted within a bank. All control rods shall be clad with stainless steel tubing.
- 5. 4 REACTOR COOLANT SYSTEM I
I DESIGN PRESSURE AND TEMPERATURE J
5.4.1 The Reactor Coolant System is designed and shall be maintained:
In accordance with the Code t$nuirements specified in Section 5.2 f
a.
of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, I
b.
For a pressure of 2485 psig, and
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c.
For a temperature of 650 F, except for the pressurizer which is 680'F.
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VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,814
+ 100 cubic feet at a nominal T f 561 F.
avg
- 5. 5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological towers shall be located as shown on Figure 5.1-1.
l 5.6 FUEL bTORAGE CRIT!CALITY 5.6.1. The spent fuel storage racks are designed and shall be maintained with:
i A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance of I
i SOUTH TEXAS - UNITS 1 & 2 5-6 Unit 1 - Amendment No. 2,10 Unit 2 - Amendment flo. 2 1
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