ML20207A100
| ML20207A100 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/17/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207A105 | List: |
| References | |
| NUDOCS 9905260144 | |
| Download: ML20207A100 (19) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
2 WASHINGTON, D.C. 20e60001
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STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 q
SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.109 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by STP Nuclear Operating Company
- acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (COA) (the licensees), dated October 29,1998, as supplemented by letter dated March 15,1999, 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 tne common defense and security or to the health and safety of the public; and E.
Trio issuance of this amendment is in accordance with 10 CFR Part 51 of the Con. mission's regulations and all applicable requirements have been satisfied.
- STP Nuclear Operatang Company is authorized to act for Houston Lighting & Power Company (HL&P), 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.
9905260144 990517
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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 Soecifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 109, 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 and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
e Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: May 17, 1999
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t UNITED STATES l
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001
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STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. %
License No. NPF-80 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by STP Nuclear Operating Company
- acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City j
Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (COA) (the licensees), dated October 29,1998, as supplemented by letter dated March 15,1999, 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.
- STP Nuclear Operating Company is authorized to act for Houston Lighting & Power Company (HL&P), 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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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 amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, 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 and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: May 17, 1999 h
l ATTACHMENT TO LICENSE AMENDMENT NOS.109 AND %
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 revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert ix ix x
x*
xiii xiii*
xiv xiv 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 3/4 7-22a 3/4 7-22a 3/4 7-22b 3/4 7-22b 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 B 3/4 7-4 B 3/4 7-4 B 3/4 7-5 B 3/4 7-5 i
B 3/4 7-6 B 3/4 7-6 6-23 6-23*
6-24 6-24
- Overleaf pages provided to maintain document completeness. No changes on these pages.
l
I INDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE T4.6.3 CONTAINMENT ISOLATION VALVES 3/4 6-18 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers.....................................
3/4 6-19 3
Electric Hydrogen Recombiners............................
3/4 6-20 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Saf ety Valves..........................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING 4 LOOP OPERATION....................................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP 3/4 7-3 Auxiliary Feedwater System...............................
3/4 7-4 Auxiliary Feedwater Storage Tank..........................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE I
AND ANALYSIS PROGRAM..............................
3/4 7-8 Main Steam Line Isolation Valves 3/4 7-9 Atmospheric Steam Relief Valves...........................
3/4 7-10 Main Feedwater System..................................
3/4 7-10a 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...
3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM..................
3/4 7-12 3/4.7.4 ESSENTIAL COOLING WATER SYSTEM....................
3/4 7-13 3/4.7.5 U LTI MATE H EAT S I N K..................................
3/4 7-14 3/4.7.6 (This specification number is not used.)
3/4.7.7 CONTROL ROOM MAKEUP AND CLEANUP FILTRATION i
SYST E M..............................................
3/4 7-16 1
3/4.7.8 FUEL HANDLING BUILDING (FHB) EXHAUST AIR SYSTEM.....
3/4 7-19 3/4.7.9 (This specification number is not used.)
l 3/4.7.10 SEALED SOURCE CONTAMINATION.......................
3/4 7-27 3/4.7.11 (This specification number is not used.)
3/4.7.12 (This specification number is not used.)
3/4.7.13 (This specification number is not used.)
l 3/4.7.14 ESSENTIAL CHILLED WATER SYSTEM.....................
3/4 7-33 SOUTH TEXAS - UNITS I & 2 ix Unit 1 - Amendment No. 67;460,109 Unit 2 - Amendment No. 56;ey, %
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IEfrl LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS
,PA J, g
SECTION 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0p e ra ti ng................................................
3/4 8-1 TAB LE 4. 8-1 DIESEL GENERATOR TEST SCHEDULE........................
3/4 8-8 5hutdown.................................................
3/4 8-9 3/4.8.2 D.C. SOURCES 0perating................................................
3/4 8-10 i
l TABLE 4.8-2 8ATTERY SURVEILLANCE REQUIREMENTS.....................
3/4 8-12 Shutdown.................................................
3/4 8-13 3/4.8.3 ONSITE POWER DISTRIBUTION 0perating................................................
3/4 8-14 5hutdown.................................................
3/4 8-16 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices......................................
3/4 8-17 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................
3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................
3/4 9-2 3/4.9.3 DECAY TIME...............................................
3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................
3/4 9-4 3/4.9.5 COMMUNICAT10NS...........................................
3/4 9-5 l
3/4.9.6 REFUELING MACHINE.......................................
3/4 9-6 l
3/4.9.7 CRANE TRAVE L - FUE L HANDLING BUILDING....................
3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1.........................................
3/4 9-8 l
Low Water Leve1..........................................
3/4 9-9 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM.................
3/4 9-10 e
3/4. 9.10 WATER, LEVEL - REFUELING CAVITY..........................
3/4 9-11 1
SOUTH TEXAS - UNITS 1 & 2 x'
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BASES
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SECTION Eagg 3/4.0 AP PLIC ABILITY.............................................
B3/401 S/4.1 REACTMTY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL.....................................
B 3/411 3/4.1.2 BORATION SYSTEMS......................................
B 3/412 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...........................
B 3/4 1 4 3/4.2 POWER DISTRIBUTION LIMITS................................
8 3/4 2 1 3/4.2.1 AXIAL FLUX DIFFERENCE..................................
B 3/4 2-1 Sf4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR............
B 3/4 2-2 FIGURE B 3/4.2-1 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL POWER........................................
B 3/4 24 3/4.2.4 OUADRANT POWER TILT RATIO.............................
B 3/4 2 4 3/4.2.5 DNB PARAMETERS.......................................
B 3/424 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION..........
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...........................
B 3/4 3-3 3/4.3.4 (This specification number is not used) l 3/4.4 REACTOR COOLANT SYSTEM S/4.4.1 REACTOR COOLANT LOOPS AND COO!. ANT CIRCULATION......
B 3/4 +1 3/4.4.2 SAFETY VALVES..........................................
B 3/4 4-1 3/4.4.3 PRE S S U RIZER...........................................
B 3/4 4 2 3/4.4.4 RELIEF VALVES..........................................
B 3/4 4 2 3/4.4.5 STEAM G EN ERATORS.......... ~...........................
B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE......................
B 3/444 3/4.4.7 C HEMI STRY.............................................
B 3/44 4 3/4.4.8 SPECIFIC ACTMTY.......................................
B 3/4 4 4 SOUTH TEXAS. UNITS 1 & 2 mill Unit 1. Amendment No.101 Unit 2. Amendment No. 88 JAN 211999
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INDEX BASES SECTION PAGE 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..........................
B 3/4 4-6 TABLE B 3/4.4-1a REACTOR VESSEL TOUGHNESS (UNIT 1).............
B 3/4 4-9 i
TABLE B 3/4.4-1b REACTOR VESSEL TOUGHNESS (UNIT 2).............
B 3/4 4-10 l
FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>lMeV) AS A FUNCTION OF FULL POWER SERVICE LIFE................................
B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY..................................
B 3/4 4-15 l
3/4.4.11 REACTOR VESSEL HEAD VENTS...........................
B 3/4 4-15 1
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 AC C U M U LATO R S.........................................
B 3/4 5-1 l
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS.............................
B 3/4 5-1 3/4.5.4 (This specification number is not used).........................
B 3/4 5-2 j
3/4.5.5 REFUELING WATER STORAGE TANK........................
B 3/4 5-2 3/4.5.6 RESIDUAL HEAT REMOVAL (RHR) SYSTEM...................
B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...................................
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................
B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES...........................
B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTROL...............................
B 3/4 6-4 1
3/4.7 PLANT SYSTEM 5 3/4.7.1 TU R BI N E CY C LE..........................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION....
B 3/4 7-3 3/4.7.3 COMPONINT COOLING WATER SYSTEM.....................
B 3/4 7-3 3/4.7.4 ESSENTIAL COOLING WATER SYSTEM.......................
B 3/4 7-3 3/4.7.5 U LTIMATE H EAT SINK.....................................
B 3/4 7-3 3/4.7.6 (Not used) 3/4.7.7 CONTROL ROOM MAKEUP AND CLEANUP FILTRATION SYSTEM...
B 3/4 7-4 3/4.7.8 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM..............
B 3/4 7-4 3/4.7.9 (This specification number is not used.)
l SOUTH TEXAS - UNITS 1 & 2 xiv Unit 1 - Amendment No. 4,109 Unit 2 - Amendment No. %
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PLANT SYSTEMS 3/4.7.9 (Not Used) l l
SOUTH TEXAS - UNIT 1 & 2 3/4 7-21 Unit 1 - Amendment No. 44,109 Unit 2 - Amendment No. OS, 96
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SOUTH TEXAS - UNITS 1& 2 3/4 7-22 Unit 1 - Amendment No. 44, 109 Unit 2 - Amendment No. OS, %
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SOUTH TEXAS-UNITS 1 & 2 3/4 7-22a Unit 1 - Amendment No. 44,109 Unit 2 - Amendment No. SS, %
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1 SOUTH TEXAS - UNITS 1 & 2 3/4 7-22b Unit 1 - Amendment No. 44,109 Unit 2 - Amendment No.63, %
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SOUTH TEXAS - UNITS 1 & 2 3/4 7-24 Unit 1 - Amendment No.109 Unit 2 - Amendment No. %
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SOUTH TEXAS - UNITS 1 & 2 3/4 7-25 Unit 1 - Amendment No.109 Unit 2 - Amendment No.%
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SOUTH TEXAS - UNITS 1 & 2 3/4 7-26 Unit 1 - Amendment No.109 I
Unit 2 - Amendment No.96 4
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PLANT SYSTEMS BASES The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," March 1974.
3/4.7.6 (Not used) 3/4.7.7 CONTROL ROOM MAKEUP AND CLEANUP FILTRATION: SYSTEM The OPERABILITY of the Control Room Makeup and Cleanup Filtration System ensures that: (1) the ambient air temperature does not exceed the allowable temperature for continuous-duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions. Operation of the system with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this system in conjunction with control room i
design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A,10 CFR Part 50. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.8 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM i
The OPERABILITY of the Fuel Handling Building Exhaust Air System ensures that radioactive materials leaking from the ECCS equipment within the FHB following a LOCA are filtered prior to reaching the environment. Operation of the system with the heaters operating for the least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.9 (Not Used) l SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-4 Unit 1 - Amendment No. 49,109 Unit 2 - Amendment No. 9, 96
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l SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-5 Unit 1 - Amendment No. 49r44,109 Unit 2 - Amendment No. 9res, 96
PLANT SYSTEMS BASES 3/4.7.10 SEALED SOURCE CONTAMINATION' The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a) (3) limits for plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are r.emoved from the shielded mechanism.
3/4.7.11 (Not used) 3/4.7.12 (Not used)
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SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-6 Unit 1 - Amendment No.M.109 -
I Unit 2 - Amendment No.9res, 96 I
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M)MINISTRATIVE CONTROLS I
CORE OPERATING LIMITS REPORT (Continued) 6.9.I.6.d The CORE' OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle,' to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector.
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 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
~ 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; d.
Records of surve'.llance activities, inspections, and calibrations required by these Technical Specifications; e.
Records of changes made.to'th; procedures required by Specification 6.8.1; f.
Records of sealed source and fission detector leak tests and results; and g.
Records of annual physical inventory of 611 sealed source material of record.
6.10.3 The following records shall be retained for the duration of the unit Operating License:
a.
Records and drawing changes reflecting unit design modifications 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; d.
Records of gaseous and liquid radioactive material released to the environs; SOUTH TEXAS - UNITS 1 & 2 6-23 Unit 1 - Amendment No. 4h67,89 Unit 2 - Amendment No. 4b46,76 AUG 191997
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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; I
h.
Records of inservico inspections performed pursuant to these Technical Specifications; i.
Records of quality assurance activities required by the Operational Quality Assurance Plan; i
J.
Records of reviews performed for changet m9de to procedures or equipment or l
reviews of tests and experiments pursuant to 10 CFR 50.59; k.
Records of meetings of the PORC and the NSRB; 1.
NOT USED I
m.
Records of secondary water sampling and water quality; I
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 procedures effective at specified times and QA records showing that these procedures were followed.
j o.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL AND THE PROCESS CONTROL PROGRAM; and I
p.
Records of radioactive shipments.
6.11 RADIATION PROTECTION PROGRAM 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 invoMng personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.1601(c) of 10 CFR Part 20, in lieu of the " 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 I
SOUTH TEXAS - UNITS 1 & 2 6-24 Unit 1 - Amendment No. 40,47,07,109 Unit 2 - Amendment No. 95;96:46, 96