ML20195J009
| ML20195J009 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/18/1998 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195J013 | List: |
| References | |
| NUDOCS 9811240175 | |
| Download: ML20195J009 (9) | |
Text
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION l
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WASHINGTON, D.C. 200e&4001 STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 l
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 July 6,1998, as supplemented on October 28,1998, 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 Commicsion; 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.
9811240175 981118 PDR ADOCK 05000498 P
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1 2.
Accordingly, the license is amended by changes to the Technical Specifications as t
indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility l
Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, 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 30 days of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION Mlk L,)yp Thomas W. Alexion, Project Ma ager Project Directorate IV-1 Division of Reactor Projects ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: November 18, 1998
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UNITED STATES g
j-NUCLEAR REGULATORY COMMISSION o
R WASHINGTON, D.C. 30806 4 001 I
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l STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.86 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 ofitself 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 July 6,1998, as supplemented on October 28,1998, 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 caducted 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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i 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. 86, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l * &.
Nf}fy Thomas W. Alexion. Project M nager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: November 18, 1998
ATTACHMENT TO LICENSE AMENDMENT NOS. 99 AND 86
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FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 4
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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 overleaf pages are also provided to maintain document completeness.
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REMOVE INSERT y
v vi vi 3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-56 i
3/4 3-57 3/4 3-57 B 3/4 34 B 3/4 34 i
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEll_t ANCE REQUIREMFN,TS SECTION PAGE 3/4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...................................3/4 2-1 FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER..................................
Deleted 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fo(Z)....................3/4 2-5 FIGURE 3.2-2 K(Z)- NORMALIZED Fo(Z) AS A FUNCTION OF CORE HEIGHT..Deleted 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR............
3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO...........................
3/4 2-10 3/4.2.5 DN B PARAM ETE RS.......................................
3/4 2-11 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.................
3/43-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION................
'!!43-2 TABLE 3.3-2 (This table number not used)...............................
3/43-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMEN1 ATION SURVEILLANCE I
R EQ U I R E M E NTS..........................................
3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM I N STRU M ENTATION.......................................
3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IN STRU M ENTATION.......................................
3/4 3-18 1
TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM lNSTRUMENTATION TRIP SETPOINTS........................
3/4 3-29 TABLE 3.3-5 (This table number not used)..............................
3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........
3/4342 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations........................
3/4 3-50 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS..................................
3/4 3-51 TABLE 4.3-3 RADIATION MONITO. NG INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS................
3/4 3-53 Movable incore Detectors....................................
3/4 3-54 l
SOUTH TEXAS - UNITS 1 & 2 v
Unit 1 - Amendment No. E-7150, 99 Unit 2 - Amendment No. if;s9,86 l
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.E' 1.
INDEX (ffIO CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
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PAGE SECTION I
3/4 3-58 Meworological Instrumentation.............................
3/4 3-59 TABLE 3.3-8 ME TEOROLOGICAL MONITORING INSTRUMENTATIGN.....
TABLE 4.3-5 ME7EOROLOGICAL MONITORING INSTRUMENTATION 3/4360 SURVEILLANCE REQUIREMENTS.........................
3/4 3-61 Remote Shutdown System................................
3/4 3-62 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM..........................
TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION 3/4 3-66 SURVEILLANCE REQUIREMENTS.........................
3/4 3-67 Accident Monitoring Instrumentation.........................
3/4 3-68 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION............
TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-73 SURVElLLANCE REQUIREMENTS.........................
3/4 3-75 Chemical Detection Systems..............................
3/4 3-77 TABLE 3.3-11 (This table number is not used)...........................~ DELETED Radioactive Liquid Effluent Monitoring Instrumentation TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING DELETED INSTRUMENTATION TABLG 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING DELETED INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-79 Explosive Gas Monitoring Instrumentation....................
3/4 3-80 TABLE 3.3-13 EXPLOSlVE GAS MONITORING INSTRUMENTATION.......
TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-82 SURVEILLANCE REQUIREMENTS.........................
3/4 3-84 3/4.3.4 TURBINE OVEP. SPEED PROTECTION..........................
Unit 1 - Amendment No. 47,99 vi SOUTH TEXAS - UNITS 1 & 2 Unit 2 - Amendment No. S6,86 I
p 3.3.3.3 (Not Used)
I SOUTH TEXAS - UNITS 1 & 2 3/4 3-55 Unit 1 - Amendment No. 4,99 Unit 2 - Amendment No. 86
THIS PAGE INTENTIONALLY BLANK i
SOUTH TEXAS - UNITS 1 & 2 3/4 3-56 Unit 1 - Amendment No. 4,99 i
Unit 2 - Amendment No. 86 l
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l THIS PAGE INTENTIONALLY BLANK 1
1 SOUTH TEXAS - UNITS 1 & 2 3/4 3-57 Unit 1 - Amendment No. 4, 99 Unit 2 - Amendment No. 86
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INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.
APPLICABILITY: At all times.
ACTION:
With one or more required meteorological monitoring channels inoperable a.
for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
This ACTION may be applicable to both units simultaneous y.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3 4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated CPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-5.
4 SOUTH TEXAS - UNITS 1 & 2 3/4 3-58 Unit 1 - Amendment No. 4.
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INSTRUMENTATION BASES REACTORTRIPSYSTEMandENGINEEREDSAFETYFEATURESACTUATIONSYSTh INSTRUMENTATION (Continued)
Radiation Monitoring Bases are discussed in Section 3/4.3.3.1 below.
l The Engineered Safety Features Actuation System interlocks perform the following functions:
P-4 Reactor tripped - Actuates Turbine trip via P-16, closes main feed-water valves on T,yg below setpoint, prevents the opening of the main feedwater valves which were closed by a Safety Injection or High Steam Generator Water i.evel and allows Safety Injection block so that components can be reset or tripped.
Reactor not tripped prevents manual block of Safety Injection.
P-11 On increasing pressurizer pressure, P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure or low compen-sated steamline pressure signals, reinstates steamline isolation on low compensated steamline pressure signals, and opens the accumulator discharge isolation valves. On decreasing pressure, P-11 allows the manual block of Safety Injection actuation on low pressurizer pres-sure or low compensated steamline pressure signals, allows the manual block of steamline isolation on low compensated steamline pressure signals, and enables steam line isolation on high negative steam line pressure rate (when steamline pressure is manually blocked).
l P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the Steam Dump System.
On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the Steam Dump System.
P-14 On increasin0 steam generator water level, P-14 automatically trips the turbine and the main feedwater pumps, and closes all feedwater isolation valves and feedwater control valves.
3/4.3.3 MONITORING INSTRUMENTATION l
3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS, The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:
(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to parait a channel to be out of service for testing or maintenance.
The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions.
Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-3 Unit 1 - Amendment No. J,4
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INSTRUMENTATION BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring Fo(Z) or F% a fullincore flux map is used. Quarter-core flux maps, as defir,ed in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range channelis inoperable.
3/4.3.3.3 (NOT USED) 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorologicalinstrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This espability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN SYSTEM The OPERABILITY of the Remote Shutdown System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.
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SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-4 Unit 1 - Amendment No. 99 Unit 2 - Amendment No. 86 j
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