ML20059D494
| ML20059D494 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/30/1993 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059D497 | List: |
| References | |
| NUDOCS 9401070333 | |
| Download: ML20059D494 (25) | |
Text
hd UNITED STATES
[g. DL] j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2056FA001 s.~....f 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 I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commi.;sion) 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 September 15, 1993, as. supplemented by letter dated November 30, 1993, 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 regulat' ions; 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 it 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.
9401070333 9312.?O 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.
57, 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 on January I, 1994.
FOR THE NUCLEAR REGULATORY COMMISSION N
Suzanne. 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:
December 30, 1993
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UNITED STATES 3
,j NUCLEAR REGULATORY COMMISSION 4
't WASHINGTON, D.C. N0001
%,.....,o 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. 46 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 September 15, 1993, as supplemented by letter dated November 30, 1993, 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 Commission's regulations; D.
The issuance 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 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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Accordingly, the license.is amended by changes to the Technical Specificationsias indicated in the attachment to this license amendment
- l and Paragraph 2.C.(2) of Facility Operating License No. NPF,-80 is hereby.
i amended to read as follows:'
2.
Technical' Specifications a
The Technical: Specifications contained in-Appendix A, as; revised through Amendment No.
46, 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.
j 3.
The license amendment is effective as of its' date of issuance to be l
implemented on January 1, 1994.
I FOR THE NUCLEAR REGULATORY COMMISSI'ON QA Suzannb4. Black, Director Project' Directorate IV ;
Division of Reactor Projects.III/IV/V
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Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications j
Date of-Issuance:
December 30, 1993
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ATTACHMENT TO LICENSE AMENDMENT NOS. 57 AND 46 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 vertical lines indicating the areas of change. The corresponding overleaf pages.are also provided to maintain document completeness.
REMOVE INSERT 1-4 1-4 1-6 1-6 B 3/4 11-1 B 3/4 11-1 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4 5-5 5-5 6-27 6-17 6-18 6-18 6-19 6-19 6-23 6-23 6-24 6-24 6-25 6-25 6-26 6-26 a
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DEFINITIONS I - AVERAGE DISINTEGRATION ENERGY 1.12 I shall be the average (weighted in proportion to the concentration of each radionuclide in the sample) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.
ENGINEERED SAFETY FEATURES RESPONSE TI-1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that tim interva'. from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performin safety function (i.e., the valves travel to their required positions,g its pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.
FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS WASTE PROCESSING SYSTEM 1.15 A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
IDENTIFIED LEAKAGE 1.16 JDENTIFIED LEAKAGE shall be:
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump a.
seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or Reactor Coolant System leakage through a steam generator to the-c.
i Secondary Coolant System.
SOUTH TEXAS - UNITS 1 & 2 1-3 4
DEFINITIONS o
MASTER RELAY TEST L
1.17 A MASTER RELAY. TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
MEMBER (S) 0F THE PUBLIC l.18 MEMBER (S) 0F THE PUBLIC means an individual in a controlled area or UNRESTRICTED AREA.
However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
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OFFSITE DOSE CALCULATION MANUAL 1.19 The 0FFSITE DOSE CALCULATION MANUAL (0DCM) s~ all contain the methodology n
and parameters used in the calculation of offsite doses resulting from-radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain.
(1) the Radioactive Effluent Controls and Radiological Environmental l
Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specification 6.9.1.3 and 6.9.1.4.
OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABLITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, 3
cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its i
function (s) are also capable of performing their related support function (s).
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OPERATIONAL MODE - MODE 1
1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor-coolant. temperature specified in Table 1.2.
PHYSICS TESTS i
1 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental j
nuclear characteristics of the reactor core and related instrumentation:
(1) i described in Chapter 14.0 of the FSAR, (2) authorized under the. provisions of -
10 CFR 50.59, or.(3) otherwise approved by the Commission.
1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component-i body, pipe wall, or vessel wall.
SOUTH TEXAS - UNITS 1 & 2 1-4 Unit 1 - Amendment No. 47,M,57 Unit 2 - Amendment No. M,44,46 i
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DEFINITIONS PROCESS CONTROL PROGRAM 1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of. actual or simulated wet solid wastes will-be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
PURGE - PURGING 1.25 PURGE or PURGING shall be any controlled process of discharging air'or gas from a confinement to maintain temperature, pressure,-humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
t 00ADRANT POWER TILT RATIO 1.26 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore-detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector-calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors-shall be used for computing the average.
RATED THERMAL POWER 1.27 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3800 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
SHUTDOWN MARGIN 1.30 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be suberitical from its present condition assuming all full-length rod cluster assemblies (shutdown and control)~ are fully inserted except for the single rod cluster assembly of highest' reactivity worth which-is assumed to be fully withdrawn.
SOUTH TEXAS - UNITS 1 & 2 1-5 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36
te DEFINITIONS SITE BOUNDARY 1.31 SITE B0UNDARY means~that line beyond which the land or property is not.
owned, leased or otherwise controlled by the licensee.
SLAVE RELAY TEST
- 1.32 A SLAVE RELAY TEST shall be the energization of each slave' relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST.shall. include a continuity check, as a minimum, of associated testable actuation devices.
SOURCE CHECK 1.34 A. SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS
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1.35 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into.n equal subintervals,- and b.-
The testing of one system, subsystem, train, or.Other designated-component at the beginning of each subinterval.
THERMAL POWER 1.36 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
o TRIP ACTUATING DEVICE OPERATIONAL TEST 1.37 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip-functions. The TRIP ACTUATING DEVICE.0PERATIONAL TEST shall. include-adjustment, as necessary, of the Trip Actuating' Device so that'itiactuates at the required Setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.3B. UNIDENTIFIED LEAKAGE shall be all ' leakage which :is not: IDENTIFIED
- LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED AREA l.39 An UNRESTRICTED. AREA'shall be any area at or beyondlthe SITE B0UNDARY access to which is not controlled by the. licensee for. purposes of protection-
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of individuals from exposure to. radiation and radioactive materials,.. or.any.
area within the SITE BOUNDARY used for residential quarters or for-industrial, J
. commercial, institutional, and/or recreational purposes.
SOUTH TEXAS - UNITS 1 & 2 1-6 Unit 1 - Amendment No. 47, 57
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Unit 2.- Amendment No. 36, 46 T
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3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 DELETED 3/4.11.1.2 DELETED-3/4.11.1.3 DELETED 3/4.11.1.4 LIOUID HOLDUP TANKS The tanks covered by this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of i-holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Waste Processing System.
Restricting the quantity of radioactive material contained in the specified tanks to 10 curies provides assurance that in the event of an l
uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table 2, Column
' l' 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DELETED 3/4.11.2.2 DELETED 3/4.11.2.3 DELETED 3/4.11.2.4 DELETED 3/4.11.2.5 -EXPLOSIVE GAS MIXTURE 1
I-This specification is provided to ensure that the concentration of l
potentially explosive gas mixtures contained in the GASEOUS WASTE PROCESSING 1
SYSTEM is maintained below the flammability limit of oxygen. The-concentration of oxygen in the inlet header.to the GASEOUS WASTE PROCESSING SYSTEM is continuously monitored and a high level alarm isolates the.GASE0US i
WASTE PROCESSING SYSTEM.
Provision is made to manually purge the_ system with nitrogen and/or isolate the source of oxygen. Maintaining the concentration of oxygen below its flammability limit (4%= by volume) provides assurance that the releases of radioactive materials will be controlled in conformance.with the requirements of. General Design. Criterion 60 of Appendix A to 10 CFR Part 50.
Because of analyzer variabilities,. a safety margin of l% by volume is applied. Therefore, the limiting condition for operation is maintaining oxygen concentration below 3% by volume.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 11-1 Unit 1 - Ar.end' ment No. 4,47, 57 Unit 2 - Amendment No. 36,46
RADI0 ACTIVE EFFLUENTS
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BASES 3/4.11.2.6 GAS STORAGE TANKS The tanks included'in this specification are those tanks for which the quantity af radioactivity contained is not limited directly or indirectly by.
another Technical Specification. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the' event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF-THE PUBLIC at the nearest SIYE BOUNDARY will not exceed 0.5 rem. This is consistent w ti h Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981. Since only the gamma body dose factor (DFB,) is used in the analysis, the Xe-133 ' equivalent is determined from the DFB, value for Xe-133 as compared to the composite DFB for the i
actual mixture in the tank.
3/4.11.3 DELETED 3/4.11.4 DELETED s
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l-SOUTH TEXAS - UNITS 1 & 2 8 3/4 11-2 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36
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5.0 DESIGN' FEATURES 5.1 SITE EXCLUSION AREA t
5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.
j LOW POPULATION ZONE 5.1.2 The Low Population Zone shall be as shown in Figure 5.1-2.
MAP DEFINING UNRESTRICTED AREAS AND SITE B0UNDARY FOR RADI0 ACTIVE' GASEOUS AND.
LIOUID EFFLUENTS 3
5.1.3 Information regarding radioactive gaseous.and liquid effluents,'which i
will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figures 5.1-3 and 5.1-4.
The UNRESTRICTED AREA boundary may coincide with the Exclusion (fenced) Area l
boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not
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include areas over. water bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE B0UNDARY, is utilized in the Limiting Conditions for Operation to keep levels of' radioactive materials in liquid and gaseous effluents as low as is reasonably achievable ~, pursuant to 10 CFR 50.36a.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor' containment building is a steel-lined, reinforced' concrete building of cylindrical shape, with a dome roof and having the following~
design features:
a.
Nominal inside diameter - 150 feet.
b.
Nominal inside height = 241.25 feet.
c.
Minimum thickness of concrete walls - 4 feet.
I d.
Minimum thickness of concrete roof - 3 feet.
e.
Minimum thickness of concrete floor mat - 18 feet.
f.
Nominal thickness of steel liner - 3/8 inches.
g.
Net free volume - 3.56 x 10' cubic feet.
DESIGN PRESSURE AND TEMPERATURE-5.2.2 The reactor containment building is designed and shall-be maintained.
for a maximum internal pressure of 56.5 psig and a temperature of 286*F.
SOUTH TEXAS - UNITS 1 & 2 5-1 Unit Amendment No. 57 Unit 2 - Amendment No. 46 i
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1.The core shall contain 193 fuel assemblies with each fuel assembly containing 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 maximum 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 4.5 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length 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.
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 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 1 100 cubic feet at a nominal T,,_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 5.6.1 CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
SOUTH TEXAS - UNITS I & 2 5-6 Unit 1 - Amendment No.. 2,10,15,43-Unit 2 - Amendment No. 2, 5, 32
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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous cffluents in accordance with 10 CFR 20.1302 and with l '.
the methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC-from the radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appro-priate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive-material released in gaseous effluents to areas -beyond the SITE-BOUNDARY conforming to the following:
a.
For' noble gases:
Less than or equal' to a dose rate of 500, mrem /yr to the total body and less than or equal to a. dose' rate of 3000 mrem /yr to the skin, and' b.
For Iodine-131, for Iodine-133, for tritium, and-for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to a dose rate of 1500 mrem /yr to any organ.
8)
Limitations on the annual and ~ quarterly air doses resulting from noble gases released in gaseous ' effluents from each units to areas beyond the SITE B0UNDARY. conforming tol Appendix.I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and'all radio-nuclides in particulate form'with-half-lives greater. than~ 8 days in gaseous effluents released from each unit to areas beyond.the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and SOUTH TEXAS - UNITS 1 & 2.
6-17 Unit 1 - Amendment No. 47,57 Unit 2 - Amendment No. 36,46 a
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) l 10): Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
h)
Radioloaical Environmental Monitorina Procram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program'shall provide (1) representative measurements of radioactivity in the. highest potential exposure pathways, and (2) verificetion of the accuracy of' the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be' contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and 3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.9 REPORTING RE0VIREMEffTS ROUTINE REPORTS t
6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following~ reports shall be submitted to the Regional Administrator of the Regional Office of the-NRC unless otherwise noted.
STARTUP REPORT-6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following:
(1) receipt of an Operating License,'(2) amendment to.
the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different. fuel supplier, and (4) modifications that may have significantly altered the.
nuclear, thermal, or hydraulic performance of the unit.
The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test SOUTH TEXAS - UNITS 1 & 2 6-18 Unit 1 - Amendment No. 47, 57 Unit 2 - Amendment No. %, 46
a ADMINISTRATIVE CONTROLS j
STARTUP REPORT (Continued) program and a comparison of these values with design predictions and specifi-(,di. i on s. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
Startup Reports shall be submitted within:
(1)- 90' days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup_ Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have.been
-completed.
ANNUAL REPORTS
- 6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior.to March 1 of. the year-following initial criticality.
Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, and other individuals, for whom monitoring was required, (including contractors) receiving exposures greater than 100 mrem in one calendar year and their associated man-rem exposure according to work and, job functions ** (e.g., reactor operations and surveillance, inservice inspection, routine maintenance,.
special. maintenance [ describe maintenance], waste processing, and refueling). The dose assignments to various. duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totailing less than 20% of the individual total dose need not be accounted for.
4 In the aggregate, at least 80% of the total whole-body dose received from external. sources should be assigned to specific major work functions; and b.
The results of specific activity analyses in which the. primary -
coolant exceeded the limits of. Specification 3.4.8.
The.following information shall be included:
(1) Reactor power history starting:
- A single ~ submittal may.be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
- This tabulation supplements the requirements of G20.2206 of 10 CFR Part 20.
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SOUTH TEXAS - UNITS I & 2 6-19 Unit 1 - Amendment No. 47,57 Unit 2 - Amendment No. 36,46-
ADMINISTRATIVE CONTROLS-ANNUAt~ REPORTS (Continued) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />' prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiod!ne performed prior.to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and-the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration (pCi/gm) and one other radiofodine isotope concentration (gC1/gm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.3 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May I of each year. The report shall include.sumaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT **
6.9.1.4 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the station; however, for units with separate radwaste systems, the submittal'shall specify the releases of radioactive material from each unit.
SOUTH TEXAS - UNITS 1 & 2 6-20 Unit 1 - Amendment No. 47, 52 Unit 2 - Amendment No. B6, 41
l.
ADMINISTRATIVE CONTROLS-SPECIAL REPORTS 6.9.2 Special reports shall be submitted to.the Regional Administrator of the.
Regional Office of the NRC within~ the time period specified for each report.
6.10 RECORD-RETENTION t
6.10.1 In addition to the applicable record' retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for i
at least the minimum period indicated.
6.10.2 The following records shall be retained for at least 5 years:
a.
Records. and logs of unit operation covering time interval at each power level; b.
Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety;.
c.
All REPORTABLE EVENTS; i
d.
Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e.
Records of changes made to the procedures required by Specifica-tion 6.8.1; f.
Records of sealed source and fission detector leak tests and results; and g.
Records of annual physical inventory of all sealed source material
'l of record.
6.10.3 The following records shall be retained for the duration of the unit Operating License:
a.
Records and crawing changes reflecting unit design modifications l
made to systems and equipment described in the Final Safety Analysis Report-b.
Records of_ new and irradiated fuel inventory, fuel transfers, and' assembly burnup histories, c.
Records of doses received by all individuals.for whom monitoring-was required; j
d.
Records of gaseous and liquid radioactive material released to the environs; 1
SOUTH TEXAS - UNITS 1 & 2 6-23 Unit 1 - Amendment No. 47,57.
Unit 2 - Amendment No. 36,46-
^
ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION (Continued) e.
Records of transient or operational cycles for those unit components identified in the UFSAR; f.
Records of reactor tests and experiments; g.
Records of training and qualification for current members of 'the unit staff; h.
Records of inservice inspections performed pursuant to these Technical Specifications;
- i. Records of quality assurance activities required by the Opera-tional Quality Assurance Plan;
- j. Records of. reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; k.
Records of meetings of the PORC and.the NSRB; 1.
Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.9 including the date at-which the service life commences and associated installation and-maintenance records; m.
Records of secondary water sampling ~ and water quality; and n.
Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation-of the accuracy of the analysis at a later date. This should include Orocedures effective at specified times and QA records showing that these procedures were followed.
O.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL AND THE PROCESS CONTROL PROGRAM.
p.
Records of radioactive shipments.
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6.11 RADIATION PROTECTION PROGRAM 3
6.11.1 - Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.12 hlGH RADIATION AREA 1
t 6.12.1 Pursuant to paragraph 20.1601(c) of 10 CFR Part 20, in lieu of the j
" control device" or " alarm signal" required by paragraph 20.1601(a), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of SOUTH-TEXAS - UNITS 1 & 2 6-24 Unit 1 - Amendment No. 46,47,57 Unit 2 - Amendment No. E,%,46
s
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j ADMINISTRATIVE' CONTROLS u
.i 6'.12 -HIGH RADIATION AREA (Continued) l 1
radiation is equal to or'less than 1000 mrem /h'at 30 cm (12 in.) from the -.
. b-i radiation source lor from any surface _which the radiation penetrates shall be 1
barricaded and conspicuously posted as a high. radiation area ~and entrance j
thereto shall be controlled by requiring issuance of a-Radiation Work Nrmit (RWP).
Individuals qualified.in radiation protection procedures '(e.gL Health-
~
Physics Technician) or personnel continuously escorted by such-individuals may i
be exempt from the RWP issuance-requirement during the performance of their assigned duties in high radiation areas with dose rates equal ~ to or.less than 1000 mrem /h, provided they are otherwise following plant' radiation protection procedures for entry into such high radiation areas. :Any-individual or group of individuals permitted to enter such areas shall' be provided with.or_ accompanied by one or more of the following:
1 a.
A radiation monitoring device which continuously in~dicates the radiation dose rate in the area; or
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~
b.
A radiation monitoring device which continuously integrates the; radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry.into such areas with this.
i monitoring device may be made after the dose' rate levels in.the:
area have been established and individuals have been made
.l.
1 knowledgeable of them; or y
i c.
An individ2al qualified in radiation protection pr6cedures with a
]
radiation dose rate monitoring device, who is responsible for:
3 providing positive control over the activities within the area'and.-
shall perform periodic radiation surveillance at the frequency specified by health physics supervision'in the RWP.
[.-
j j
6.12.2 In addition to the requirements of Specification 6.12.1,' areas; accessible to -individuals with radiation levels greater than 1000 mrem /h 'at 30.
l_
cm (12-in.) but less than 500 Rads in one hour at one meter. from.the radiation -
source or from any surface.which the' radiation penetrates.shall be provided -
with locked doors to prevent. unauthorized entry,. and the-keys shall be maintained under the administrative' control of the Shift Supervisor'on duty-and/or health physics supervision. Doors shall remain' locked except1during 1
periods ~ of access by -individuals under an approved RWP which shall specify the~
[
dose rate levels in the'immediate work areas.and the maximum allowable stay 1
time for: individuals'.in that area. -In lieu of the stay time specification of the RWP, direct or; remote (such as closed circuit TV cameras) continuous j
surveillance may be made by individuals qualified'in: radiation protection
- [
l procedures to provide positive exposure control over,the activities being performed within the area.-
j For' isolated high radiation areas accessible to personnel with. _
radiation levels: of greater than 1000 mrem /h at 30 cm (12. in.) but 1.ess' than 500 Rads in~ one hour at one' meter that are located within~large areas, such as-4 PWR containment, where no enclosure exists, for purposes ~ of.. locking,; and where no enclosure can be reasonably constructed around the isolated area, that 1
isolated area shall-be barricaded, conspicuously posted, and a-flashing. light i
shall be activated as a warning device.
l SOUTH TEXAS - UNITS 1 & 2
.6-25 Unit 1 < Amendment No. G, 57 i
Unit 2 - Amendment No. M, 46 i
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ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.0.
This.
documentation shall contain:
i
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification'6.10.3.o. This documentation shall contain:
1)
Sufficient information to support the change together.with the appropriate analyses or evaluations justifying the change (s) and 1
- 2) A determination that the change will maintain the level of 9
radioactive effluent control required by 10 CFR 20.1302,
.[
40 CFR Part 190, 10 CFR 50.36a, and Appendix I to'10 CFR Part 50 and not adversely impact the accuracy or reliability of l
effluent, dose, or setpoint calculations.
]
b.
Shall become effective after review and acceptance by the PORC and l
the approval of the Plant Manager.
c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent'with the Annual Radioactive Effluent Release Report for-the period of the report in which any. change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the' date (e.g., month / year) the change was.
implemented.
1' SOUTH TEXAS - UNITS 1 & 2 6-26 Unit 1 - Amendment No. U,52, 57 y
Unit 2 - Amendment No. %,44,46 a