ML20045F714
| ML20045F714 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 06/29/1993 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045F715 | List: |
| References | |
| NUDOCS 9307080294 | |
| Download: ML20045F714 (17) | |
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UNITED STATES l"
^,t NUCLE AR REGULATORY COMMISSION i
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HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO
-1 CENTRAL POWER AND LIGHT COMPANY I
-DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. NPF l 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 Public Service Board of San Antonio (CPS), Central Power and Light Company-(CPL), and City of Austin, Texas (C0A) (the licensees) dated April 29, 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;.
1 B.
The facility will operate in conformity with the application, as i
amended, the provisions of the Act, and the rules and regulations of 1
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 j
in compliance with the Commission's regulations; i
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-l the Commission's regulations and all applicable requirements have been 1
satisfied.
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- 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.
93070B0294 930629 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. 52, 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 15 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l.ty m C & v(
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: June 29,1993 6
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NUCLEAR REGULATORY COMMISSION n
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....s 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. 41 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, 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:
(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.
s
_2 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-80 is hereby i
amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, 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 15 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 5 5 u C 226cL Suzanne C!) Black, Director I
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: June 29. 1993
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ATTACHMENT TO LICENSE AMENDMENT NOS. 52 AND 41 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 xix xix l-4 1-4 3/4 11-1 3/4 11-1 3/4 11-3 3/4 11-3 6-20 6-20 6-26 6-26 i
INDEX l
ADMINISTRATIVE CONTROLS k
SECTION P_A_G E A
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB).............
6-9 L
Function..........................
6-10 Composition.........................
6-10 Alternates......................... 6-10 Consultants 6-10 Meeting Frequency 6-10 Quorum...........................
6-10 Review...
6-10 Audits...........................
6-11 Records 6-12 1
6.5.3 TECHNICAL REVIEW AND CONTROL Activities.........................
6-12 6.6 REPORTABLE EVENT ACTION 6-13 r
6.7 SAFETY LIMIT VIOLATION.................... 6-13
[
t 6.8 PROCEDURES AND PROGRAMS 6-14 6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS 6-18 Startup Report.............
6-18 Ann u al Report s.......................
6-19 Annual Radiological Environmental Operating Report.....
6-20 Annual Radioactive Effluent Release Report.........
6-20 Monthly Operating Reports 6-21 Core Operating Limits Report................ 6-21 6.9.2 SPECIAL REPORTS 6-23 6.10 RECORD RETENTION 6-23 SOUTH TEXAS - UNITS 1 & 2 xix Unit 1 - Amendment No. 9,37,47, 52 Unit 2 - Amendment No. +,47,36, 41
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INDEX ADMINISTRATIVE CONTROLS SECTION PJ.GE f
6.11 RADIATION PROTECTION PROGRAM 6-24 5
6.12 HIGH RADIATION AREA..................... 6-24 f
6.13 PROCESS CONTROL PROGRAM (PCP) 6-26 t
t 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6-23 l
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SOUTH TEXAS - UNITS 1 & 2 xx Unit 1 - Amendment No. 47 Unit 2 - Amendment ~No.
36 e
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DEFINITIONS E - AVERAGE DISINTEGRATION ENERGY 1.12 E 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 TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, 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 IDENTIFIED 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.
Secondary Coolant System.
SOUTH TEXAS - UNITS 1 & 2 1-3
4 DEFINITIONS MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The KASTER RELAY TEST shall include a continuity check of each associated slave relay.
MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licens.ee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION HANUAL (0DCM) shall contain the methodology 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 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 OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE 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 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:
(1) 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.
a PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.
SOUTH TEXAS - UNITS 1 & 2 1-4 Unit 1 - Amendment No. 47, 52 Unit 2 - Amendment No. 36, 41
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS LIOUID HOLDUP TANKS
- LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any unprotected outdoor a.
tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.4.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each unprotected outdoor tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
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- Tanks included in this specification are those outdoor tanks that are either not surrounded by liners, dikes, or walls capable of holding the tank contents or that do not have tank overflows and surrounding area drains connected to the Liquid Waste Processing System.
SOUTH TEXAS - UNITS 1 & 2 3/4 11-1 Unit 1 - Amendment No. 4,47, 52 Unit 2 - Amendment No. -36, 41
l RADIOACTIVE EFFLUENTS 7
3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE
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LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM inlet shall be limited to less than or equal to 3% by volume.
APPLICABILITY: At all times.
ACTION:
i a.
With the concentration of oxygen in the GASEOUS WASTE PROCESSING
~
SYSTEM inlet exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.11.2.5 The concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM i
shall be determined to be within the above limits by continuously monitoring i
the waste gases entering the GASE0US WASTE PROCESSING SYSTEM with the oxygen monitor required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.
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SOUTH TEXAS - UNITS 1 & 2 3/4 11-2 Unit 1 - Amendment No. 47.
Unit 2 - Amendment No. 36 1
r RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 Thequantityofradioactivitycontainedjneachgasstoragetank shall be limited to less than or equal to 1.0 x 10 Curies of noble gases (considered as Xe-133 equivalent).
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.4.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
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SOUTH TEXAS - UNITS 1 & 2 3/4 11-3 Unit 1 - Amendment No. 47,52 Unit 2 - Amendment No. 36,41
ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) program and a comparison of these values with design predictions and specifi-cations. 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 comitments 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 comercial 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 comercial operation), supplementary rcports 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 I of the year following initial criticality.
Reports required on an annual basis shall include:
A tabulation on an annual basis of the number of station, utility, a.
and other personnel (including contractors) receiving exposures greater than 100 mrem /yr 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 totalling less than 20% of the individual total dose need not be accounted for.
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 i
information shall be included:
(1) Reactor power history starting l
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- 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.
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- This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
SOUTH TEXAS - UNITS 1 & 2 6-19 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36
ADMINISTRATIVE CONTROLS t
ANNUAL REPORTS (Continued) t 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 radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one I
analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine 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 (yCi/gm) and one other radioiodine isotope concentration (yCi/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 1 of each year. The report shall include summaries, 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 1 to 10 CFR Part 50.
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- 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 common to all units at the station; however, for units with separate radwaste systems, the submittal shall l
specify the releases of radioactive material from each unit.
l SOUTH TEXAS - UNITS 1 & 2 6-20 Unit 1 - Amendment No. 47, 52 Unit 2 - Amendment No. M, 41
ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the perfonnance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/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:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowled-geable of them; or c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health and Safety Services Manager in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) 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 except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the imediate work areas and the maximum allowable stay 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 surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
SOUTH TEXA5 - UNITS 1 & 2 6-25 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36
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.o.
This documentation shall contain:
- 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 s
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 (CDCM)
Changes to the ODCH:
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
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 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 effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the PORC and 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 l~
L the report in which any change to the ODCM was made.
Each change i
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.
SOUTH TEXAS - UNITS 1 & 2 6-26 Unit 1 - Amendment No. 47,52 Unit 2 - Amendment No. 36,41 3
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