ML20199H772
| ML20199H772 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 01/21/1999 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199H778 | List: |
| References | |
| NUDOCS 9901250315 | |
| Download: ML20199H772 (11) | |
Text
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION wAsMNGTON, D.C. 306e6 0001 STP NUCLEAR OPERATING COf0PANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment Nc.101 i
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 2g,1998, 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 Chapt 6r 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 c efense 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.
i 9901250315 990121 PDR ADOCK 05000499 P.
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as l
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 1
The Technical Specifications contained in Appendix A, as revised through Amendment No.101, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the iicense. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
The license amendment is effective as of its date of issuance, to be implemented within I
30 days ofissuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
t
>,;w anau Thomas W. Alexion, Project Manager Project Directorate IV-1 l
Division of Reactor Projects Ill/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 21, 1999 l
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- 4 UNITED STATES l*
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NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D.C. 20066 0001 g{* (
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l STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 l
SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 l
License No. NPF-80 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, 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 l'
' indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility l
Operating License No. NPF-80 is hereby amended to read as follows:
i i
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 88, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate l
the facility in accordance with the Technical Specifications and the l
Environmental Protection Plan.
3.
The license ainendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas W. Alexion, Project anager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: January 21, 1999 L
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ATTACHMENT TO LICENSE AMENDMENT NOS.101 AND 88 I
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FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 i
DOCKET NOS. 50-498 AND 50-499 j
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Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginallines indicating the areas of change. The corresponding overbaf pages are also provided to maintain document completeness.
j REMOVE INSERT vi vi xiii xiii 3/4 3-84 3/4 3-84 B 3!4 3-6 B 3/4 3-6 i
)
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1 lblDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILt ANCE REOUIREMFNTS EECTION PAGE 3/41 POWFR DISTRIBUTION LIMITR 4
1
]
3/4.2.1 AXIAL FLUX DIFFERENCE................................... 3/42-1 FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF 1
RATED THERMAL POWER..................................
Deleted i
3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fe(Z)....................- 3/42-5 l
FIGURE 3.2-2 K(Z)- NORMAllZED F (Z) AS A FUNCTION OF CORE HEIGHT..
Deleted 4
3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR
........... 3/42-9 3/4.2.4 QUADRANT POWER TILT RATIO.....,.......................
3/4 2-10 s
l 3/4.2.5 DNB PARAMETERS........................................
3/4 2-11 i
3/4.3 INSTRUMENTATION i
i 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..................
3/4 3 1 I
TABLE 3.31 REACTOR TRIP SYSTEM INSTRUMENTATION................
3/4 3-2
)
TABLE 3.3-2 (This table number not used)..............................
3/4 3-9
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TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE Q U I R EM ENTS..........................................
3/4 3-11
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3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM j
IN STRU M ENTATION.......................................
3/4 3-16 i
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM l
IN STRU M ENTATION.......................................
3/4 3-18 i
TABLE 3.3 4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM i
INSTRUMENTATION TRIP SETPOINTS........................
3/4329 TABLE 3.3-5 (TNs table number not used)...............................
3/4 3-37 i
TABLE 4.3 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM l
INSTRUMENTATION SURVElLt.ANCE REQUIREMENTS........... 3/4342 f
3/4.3.3 MON!TORING INSTRUMENTATION Radiation Monitoring for Plant Operations........................
3/4 3-50
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TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS..................................
3/4 3 51 1
TABLE 4.3 3 RADIATION MONITORING INST'.UMENTATION FOR PLANT i-OPERATIONS SURVEILLANCE REQUIREMENTS................
3/4 3-53 Movable incore Detectors 3/4 3-54 m.,...............................
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i SOUTH TEXAS - UNITS 1 & 2 y
Un't 1 - Amendment No. EF;60, 99 Uralt 2. Amendment No. 47;99f 86 NOV 181m L
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Metecrological Instrumentation.............................
3/4 3-58 TABLE 3M METEOROLOGICAL MONITORING INSTRUMENTATIGN......
3/4 3-59 TABLi: 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS........................
3/4 3-60 Remote Shutdown System................................
3/4 3-61 TABLE 3.3 9 REMOTE SHUTDOWN SYSTEM..........................
3/4 3-62 I,
3 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION
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SURVEILLANCE REQUIREMENTS.........................
3/4 3-66 Accident Monitoring Instrumentation.........................
3/4 3-67 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION............
3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING JNSTRUMENTATION SURVEILt.ANCE REQUIREMENTS.........................
3/4 3-73 Chemical Detection Systems..............................
3/4 3-75 j
TABLE 3.3-11 (This table number is not used)..........................
3/4 3-77 J-Radioactive Uquid Effluent Monitor Instumentation DELETED TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING l
lNSTRUMENTATION DELETED TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED
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Explosive Gas MonitorRn9 Instrumentation...................
3/4 3-79 TABLE 3.3-13 EXPLCSIVE GAS MONITORING INSTRUMENTATION.......
3/4 3-80
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i TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................
3/4 3-82 3/4.3.4 (This specification number is not used) l l
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1 SOUTH TEXAS - UNITS 1 & 2 vi Unit 1 - Amendment No. 47;99.10'1 Unit 2 - Amendment No. 06;96,88 1-
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ElDEX 1
BASES I
l SECTION fMGE 3/4.0 AP PLIC ABILITY.............................................
B 3/4 0-1 4
4 i
3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL.....................................
B 3/41-1 3/4.1.2 BORATION SYSTEMS......................................
B 3/41-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...........................
B 3/41-3 j
3/4.2 POWER DISTRIBUTION LIMITS................................
B 3/4 2-1.
3/4.2.1 AXlAL FLUX DIFFERENCE..................................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR r.nd l
NUCLEAR ENTHALPY RISE HOT CHANNEL FAC7 OR............
B 3/4 2-2 FIGURE B 3/4.2-1 TYPICAL INDICATED AXIAL FLUX DE FERENCE VERSUS TH ERMAL POW ER........................................
B 3/4 2-3 i
3/4.2.4 OUADRANT POWER TILT RATIO.............................
B 3/4 2-5 i
3/4.2.5 DNB PARAMETERS......................................
B 3/4 2-5 1
3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY i
FEATURES ACTUATION SYSTEM INSTRUMENTATION..........
B 3/4 3-1 j
3/4.3.3 MONITORING INS 7RUMENTATION...........................
B 3/4 3-3 3/4.3.4 (This specification number is not used) l l
1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR CiN LOOPS AND COOLANT CIRCULATION......
B 3/4 4-1 3/4.4.2 SAFETY VALVES............................. e............
B 3/4 4-1 1
3/4.4.3 PR ESS U RIZEF................. -...........................
B 3/4 4-2 3/4.4.4 R ELI EF VALVES..........................................
B 3/4 4-2 3/4.4.5 STEAM GENERATORS....................................
B 3/4 4 2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE......................
B 3/4 4-3 3/4.4.7 C H EMI STRY............................................
B 3/4 4 4 i
' 3/4.4.8 SPECIFIC ACTIVITY.......................................
B 3/4 4-5 e
SOUTH TEXAS - UNITS 1 & 2 nii Unit 1 - Amendment No.101 Unit 2 - Amendment No. 88
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A INDEX BASES SECTION PAGE 3/4.4.9' PRESSURE / TEMPERATURE LIMITS...............................
B 3/4 4-6 TABLE 8 3/4.4-la REACTOR VESSEL TOUGHNESS (UNIT 1)................
8 3/4 4-9 TABLE B 3/4.4-1b REACTOR VESSEL TOUCSNESS (UNIT 2)................
8 3/4 4-10 FIGURE 8 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE..................................
8 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY.....................................
B 3/4 4-15 1
3/4.4.11 REACTOR VESSEL HEAD VENTS.......................
B 3/4 4-1Ts 16 5 EMERGENCY CORE COOLING SYSTEMS
.3/4.5.1 ACCUMULATORS..............................................
B 3/4 5-1
'f/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 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.......................................
8 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 COM8USTIBLE GAS CONTR0L...................................
8 3/4 6-4 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.............................................
8 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........
8 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................
8 3/4 7-3 3/4.7.4' ESSENTIAL COOLING WATER SYSTEM............................
B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK........................................
8 3/4 7-3 3/4.7.6 (Notused) 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 SNUBBERS..................................................
8 3/4 7-4 SOUTH TEXAS - UNITS 1 & 2 xiv Unit.)-AmendmentNo.J
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TABLE 4.3-9 (Continued, TABLE NOTATIONS (Notused) l During SASE0US WASTE PROCES$1NG SYSTEM operation.
(1) (NotUsed)
(2)
(NotUsed)
.l (3)
(NotUsed)-
g (4) (NotUsed)
(5) The CHANNEL CALIBRATION shall include the use of a standard gas samp*4e containing a nominal two volume percent oxygen, balance nitrogen.
SOUTH TEXAS - UNITS 1 1 2 3/43-83 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36
=:.
INSTRUMENTATION 3/4.3.4 Not Used 2,
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SOUTH TEXAS - UNITS 1 & 2 3/4 3-84 Unit 1 - Amendment No. 49;e;67,101 Unit 2 - Amendment No. 06;56,88 i
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INSTRUMENTATION BASES 3&L3.3.6 ACCIDENT MONITORING INSTRUMENTATION (Continued) i quadrant. The unit specific response to item II.F.2 of NUREG-0737 further discusses the core
^
exit thermocouples. Two sets of two thermocouples ensure a single failure will not disable the ability to determine the radial temperature gradient. The subcooling margin monitor requirements are not affected by allowing 2 thermocouples/ channel / quadrant as long as each channel has at least fcur operable thermocouples in any quadrant (e.g., A Train has four operable thermocouples in one of the quadrants, and C Train hat, four operable thermocouples in the same quadrant or any other quadrant.). This gesserves the ability to withstand a single failure.
3/4.3.3.7 (Not Used) 3/4.3.3.8 (Not Used) j l
3/4.3.3.9 (Not Used) l 3/4.3.3.10 DELETED I
l 3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASEOUS WASTE PROCESSING j
l SYSTEM.
l 3/4.3.4 (Not Used) l l
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l SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amendment No. 4h76;W,101 Unit 2 - Amendment No. 96;65;66,88
.